Forwards 'Niagara Mohawk Power Corp,Nine Mile Point ...NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 November 8, 1993 NMP2L 1453

ACCEI ERAT DOCVMENT DIST VTION SYSTEMREGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9311150064 DOC.DATE: 93/11/08 NOTARIZED: NO DOCKET gFACIL:.50;-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410

AUTH.NAME AUTHOR AFFILIATIONTERRY,C.D. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATIONDocument Control Branch (Document Control Desk)

D

NOTES:

SUBJECT: Forwards "Niagara Mohawk Power Corp, Nine Mile Point INuclear Station Unit 2 — Pump 6 Valve First Ten YrIn-Service Testing Program Plan," NMP2-IST-001.Planincorporates changes per GL-89-04.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR f ENCL Q SIZE:TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code

RECIPIENTID CODE/NAME

PD1-1 LAMENNINGPJ

COPIESLTTR ENCL

1 02 2

RECIPIENTID CODE/NAME

PD1-1 PD

COPIESLTTR ENCL

1 1 D

INTERNAL: ACRSNRR/DE/EMEBNUDOCS-ABSTRACTOGC/HDS1RES/DSIR/EIB

6 6 AEOD/DSP/ROAB1 1 NRR/EMCB1 1 OC Q)CB1 0 ~~E~ Ol1 1

1 11 11 01 1

D

EXTERNAL: EG&G BROWNpBNRC PDR

1 11 1

EGGG RANSOMEPCNSIC

1 11 1

D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK,

ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISIS FOR DOCUMENTS YOU DON'T NEED!

D

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19

NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511

November 8, 1993NMP2L 1453

U. S. Nuclear Regulatory CommissionA'ttn:- .Document.'Control Desk-IWashington, D. C. 20555

Re: Nine Mile Point Unit 2Docket No. 50-410

F-

Gentlemen:

Enclosed is the "Niagara Mohawk Power Corporation, Nine MilePoint Nuclear Station Unit 2-Pump and Valve First Ten-Year In-Service Testing Program Plan", NMP2-IST-001, Revision4. This revision supersedes the previous revision and incorporates changes made in accordancewith Generic Letter 89-04, 10CFR50.59 and various Commission Safety Evaluation Reports.

There are no Code relief requests or deviations in this revision which require Commissionevaluation or approval. This Revision is being submitted in compliance with Generic Letter89-04.

Very truly yours,

C. D. TerryVice President

Nuclear Engineering

MGM/mlsAttachment

p: W~AhRegional Administrator, Region IMr. R. A. Capra, Director, Project Directorate I-l, NRRMr. J. E. Menning, Project Manager, NRRMr. B. S. Norris, Senior Resident Inspector

A chm n

Records Management93ii i'50064 93i:i08 ';PDR,'. '"ADOCKI 05000410='

,,

'

PDR

tg) ~

~,

h ~

NIAGARAMOHAWKPOWER CORPORATION

NMP2 IST PROGRAM PLANNMP2-IST-001, REV 4

REVISION 4 SUMMARYSHEET

;,:Description of Change Reason for Change~IHINMItHIMNINNNNNNNHHNIMIHNMMNHHtMtHMtNHHMIMHHIMtH~ ItotHHHtMMtMIMltNMMHHMINtHIIMHotHtNtHIMMIMMMHotoolHIHOIHotHIIMI~ ItotoOHIHMNINNlttHotNlttHHIHHotHIIIOHHHMIOIMOIHHltotlMH

The Following Changes Are Incorporated Into This Revision

2.

3.

4,

6.

7.

8.

9.

Revise Technical Specification Leakage testreferences in the IST Program Plan, as well aseditorial changes

Change Request 2-91-IST401: Add cold shutdownjustification ISCNS-I for testing the containment

, vacuum breakers, 2ISC*RV33A and B throughRV36A and B

Change Request 2-91-IST-002: Correct testfrequency for valves 2SWP~V1002A and B, to beconsistent with Relief Request No. SWP-VRR2

Change Request 2-91-IST403: Delete'Section III,Pump and Valve IST Program Plan from the general10-year ISI Program Plan since the Pump and Valve

'" IST Program Plan exists under a separate document,NMP2-IST401

Change Request 2-91-IST404: Revise SWPZS-2 todelete valves SWP~V1024 and V1025 and add themto quarterly test due to additional system lineupevaluation and change

;'Change Request 2-91-IST405: Delete the closesafety function and the associated test requirementsfor valves 2CMS~SOV23A through E and2CMS~SOV25A through D per design basisAppendix "B" determination No. 91409 and SafetyEvaluation No. 91405, Rev. 2; the valves'afety

" function is to open only.

Change Request 2-91-IST407: Editorial, to correct-, change request numbers incorporated into Revisions

1,2, and 3

Change Request 2-91-IST408: To correct pagenumber in SWP system

Change Request 2-91-IST409: Change 10CFR50,Appendix J, LJ type C test with air to Appendix J,LK type C test with water for systems that arenormally filled with water and operating under post-accident condition

To reflect Tech Spec Amendment 37, dated 3/24/92, TACNo. M82635

To comply with NRC SER dated May 28, 1991, TAC No.79781

Editorial change

Administrative change

To comply with the Code quarterly test requirements

To test the valves to their safety function

To comply with QA audit recommendation

Editorial, to correct a typo

To reflect NMP2 Tech Spec amendment No. 22, datedOctober 11, 1990 (TAC No. 7719)

NMP2-IST-001, Rev. 4

p$ t(/5 09 Qg

October 1993I

Page i of v

rr'5..

a t>

-:P;IO»„07 qrauq'ratio>1»qJisq,88Q i -P 'IIO ';,)2»VP»5i

"nr>).)~5!tiish. f)t;~,

"snUqfn(h3l . >

'

>ah

n.',h

;.<,) ) y,!0) ii>H

a',»v'S'> 9)»hQ,, a.l>aa, a>n gn')2'I, r .~.f>h)i nof)~.r,.

P.-(Q nni)su .v.'

".r >frff»tt "'sq SP>ufr„".

l V>!>ari>'I 0

if ''«((!Tq >I>",L a '>US Of C .9kai ~f)~2» fd >» 'h'.

~C. P.a>!J O'Aol)2 su(

I rt>jjk I >I a>> a I Ir

hq a'.> .'I'»>i''a> hh„>

I> 'sq>)iq ioq>

>l gafu"'>i J»tasg I I A'.f, .;, < ~SSC'. at4> ~

>:0 r, 0 ~ '-'I'l >>V(hf S

(>>i("a>:, '>)!Pl'r>5iq aO

d ('Ci!:20%,~-Q:. I

'aj j>j> a< t>.I

I a r! >fi) 12»> GT, ~ >~» ':,i 'P)Gled >(xs ) -. 'v>Jar dsitiv l>rs v«a»thpsil 'ni.

V':I a»>.'f>S»+UO '>!I .

r,ili)'~thoi!>1'6bns AK-" ~

bns it('.B.W)>noh)'»2> 'hgr> )(fbi!1qqA'>It.'(> 'arh'oifs»R AAi'."-

8 hasAKVH'nuuosr

1nsrn:.>JU.IU1> i " I > ' r a/" >

noifs»2>i)JB, LSL" ~

f>,(fi'i I. '!Iv

hnos OT,zsgnsfts if i)of.fw

~,'.Q": J?OCfJ» ):;I'

r' 4! i aihjf,t)»'f

Ur>tl(>S nl»>R(t.:.r>, it,> V a~A ASSI!>S,

>. '! I) ft'i)-f>v h. s,'Ifhncitisq »fit iu'vf

>a~(iT 'life Jo:,v)aI'',llt»>." vfli7

r. (IO!)isa)q PC-i.'.Ub!Vi

fdft.'f)

a 'u» I Sh>q~~h

) f)OOQ'6:)ZBGa ~ «

;i-M-S casu))sent sganr!:3p>::o»s ai gnt'2. 1 aoifsidiv.:-MN i~f sboD d

, »)jbs Li>>) >tisnoitibbAradii i lllal. 01~I Stif 0)

)2»UJs: zi >JgasrD, htx

If:,'rZ""OR~2h':.'l5'U".tsui

"AH sii) uff(fsrl'm>a

a)Q I:«a>l ASqÃSI!i(> r ~

' "r">ff »«a Ck~-h. )2»UP>J 1 Pg'Inft r

'In",'2 fvi-> S!II) n':" II ll'h>flr1»

) '~>'- "x-2 )2J!fns)i ssoyri'3'hslvj»il ( 8 FI)iYO

.'VV)."'~OIPk~il a

h';i sq,g!!Ibt, 'lf',0'1 nrtirtt> ht~

"': nh)if>;»I")i)2»t. nwn~un: -sq»sno')1'~"fi's'ssIqsi., >OS.)tm'lO a',>auu»f"z qd JJI(r)

'. ass. Isq,>,g(, bfe«A()"" ngis»b,a>.'1)cut >!.03)

-',A-QFII! (.usnifaysfst)~ Jsrlt sairuis;;-b. S;L) 1,;S.o

.. »is 8 bns nM rlguoi>J>SIO~Stu! ) 'r&S~ a"i»~»IUn 2i y»n»>u ph>i»"&a) oh%'8 1

iJJih,a!I > j>>1

.;-5l too,i'Zl;„(Q-„",;SiPQ.;'Q '. HJ ..>oivsiq 2»"nf'his

~ '( .w ir;~<'-u.>!)»1k~i

:(bh'f 'I I>';,Ct)-('. APf. 'I'> aifahagolq„ld p'i)> 0) ..

''+"rf>f i>a>lj'II()f'[I'k(rt»2ib 'fo'>ii.V l~l) ';., i»lq)(SV.'$0 .'

Iq ll»>oiqqrf I'1 J2>a>JPSR

0> sh>>)if >ft«> it:noJ!bb>2.r..>C

.'Ilf 'Loi 2)>r.tnh&BI Uif»asg.n fs 'hff;0)tb»fili)a)

'Q-T. '.-('.-~.qx.'tr>

J'> I>SV ')JO)Sli nro > V>J>)

.'. *! ':I:.' J r '»UIJI') "-9>'Sft»ii)."V

...)-I> 'i:3R<i q gniha«.'.>

>''I ' «gqA

a>'«jjr!S'r a

12.

13.

14.

15.

16.

17.

Description of Change

Change Request 2-92-IST-002: To perform pumpvibration testing in accordance with OMA-1988, Part6 'ode per NRC-approved Relief 'equest.Additionally, add editorial changes and clarific'ationto the Program Plan I

N

Change, Request 2-92-IST403: Delete valves2CMS~SOV25A through D from testing and addthem to the Exclusion/Justification section, retired inplace per PM 89-94 and Safety Evaluation 91-84

\4

Change Request 2-92-IST-004: Change page numberin the CMS system

'hangeRequest 2-92-IST-005: Add Relief RequestGVRR-5 to deviate from ASME Section XISubsection IWV-3417(a) to allow the use ofestablished reference value instead ofprevious stroketime for trending, per NRC GL8944, Position 6

Change Request 2-92-IST406: Delete coldshutdown justification and testing frequency andreplace it with once per refueling outage frequencyfor the vacuum breakers 21SC*RV33A and B through36A and B, per Tech Spec Section 4.6.2.1 and4.6.4. Further design basis analysis Appendix Bdetermination f8947, Rev. 2 and USAR Section6.2.1.1.2 determine that valves 2ISC~RV33A and Bthrough 36A and B are not containment vacuumbreakers and, therefore, OM-1-1981, Subsection1.3.4.2 test frequency is not applicable.

LDCR 2-92-IST-001, Rev. 1: Editorial changes,changes previous CR 2-92-IST406 to LDCR 2-92-IST401

LDCR 2-92-1ST@02: Add Relief Request ICS-VRR-2 to the IST Program Plan to allow the performanceof disassembly and inspection in lieu of full forwardflow exercise for valve 2ICS~V29. This ReliefRequest is approved per NRC GL 8944, Position 2.Additional changes to specify individual testrequirements for the pressure relief valve devices andother editorial changes

LDCR 2-92-IST403: Revise GVRR-5 to cover allpowerwperated valves to allow the use ofestablishedreference value instead of previous stroke time fortrending per NRC GL 8944, Position 6

Reason for Change

To comply with NRC SER, dated 10/29/90 g AC No. 63429)

Component retired in place with no safety function

Editorial change, typo

For proper trending per NRC GL 8944, Position 6

To test the valves in accordance with Tech Spec frequencywhich meets and exceeds the OM-1 Code frequency

To comply with Nuclear Interface Procedure NIP-LPPAI

System configuration does not allow full forward flow exceptpartial flow at quarterly

For proper trending per NRC GL 89~, Position 6

NMP2-IST-001, Rev. 4 October 1993 Page ii of v

OI

IIn)0 OTI ')IIillWt

,Ii 'JiV~r,

oJN>jlnqfno»"Ir')Iihom

~ 'gfqn oo oT('GV""3.'.

(!If.lll)oOT..fo~'I'nr.fq

-9W8 fzwpeSN1ot1Af'Ol 8 bP I ~

dna yMmlo'::;, '".

JC7 .")A'H 1so

I!Oi>os2 ot tnsr! e

'.tnolnotiui»

101 )0)1Uq III.l~

f)re I)sba1qqv I.',Oi»'.

';

mrnqgllilaH y,'I'' iZNAI:"M.(t'iri'.

.53 IC if osq2 I': a

b.-a .K, " .

'4 )IA P9 12I t8na,,'

,:ZOO- .I:M ROGJ"'IPZ r,. >:. '~ol S;fiRV

„)<0 Ia)2bio4 nollosqanI

ii)i~aII,,N-N~ iree IL'3f)lolcyfqlnl

) 'il 85QOI10$ ;POD

9/1>.cd 8~1lllP&

I 4

C

b

F

Description of Change

LDCR 2-93-IST405: Revise Relief Request SWP-VRR-2 for valves 2SWP~V1002A and B to performpartial exercise quarterly and disassembly andinspection once per refueling outage per NRC GL8944, Position 2; also adding a statement to SectionI.2, "Basis", to ensure Code requirements areimplemented within six months time period forcomponents whose design function is upgraded andrequires testing per ASME/ANSI Code

Reason for Change

To comply with NRC regulations and guidelines and todocument deviation from the Code; also, to state NMPCposition for time required to implement the Code forcomponents whose design function is upgraded (notmodification)

19. LDCR 2-92-IST406: Revise pump testing program To comply with NRC SER dated April 19, 1993 (TAC No.plan.to be in compliance with ASME/ANSI OM4, M85500)1988 Code pursuant to 10CFR50.55a(0

20. LDCR 2-93-IST407: Revise Tech Spec leakagereferences, TS amendment nos. 22, 37, and 49;incorporate all issued changes against IST ProgramPlan, Rev. 3, into Rev. 4

To comply with NRC GL 89M requirements and to reflectplant Tech Spec changes

NMP2-'IST-001, Rev. 4 October 1993 Page iiiof v

"Q 80 8JGATi ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

...la~'~'3 >al".I n:.-

~ ~ 0 ~

p~) fp 1

ZQVi 'l,

V)V~.'gy[«\ «

~ ~ ~ ~ ~ ~

'..:l!')Zliah,.'.

3:,VB 'Z"."-.'DLVO";.."

F MVr3 „'zol!- -~SVD >~:.

~ . P5IVD Jn)"I'M8

ovL:.'..,

.. noijoubovfnIaqooz gnilzoT .

ow/ahnsmoN - ale;. BlsT maigoH (TZI) .,...... a~>oH2 mt':;l.....,.... JaOUP."8'

iIIU~I'if

MA;I<VASOOM 'Tc'..

fl.. '~t„bo lfnr )'nl' '.)

'~nJz8T ~"'lv"< „,

oEU) "i ';.'/I -bldg".'ioaT

~f)e ~-.'! (7PI) ..v!zambo.'.

:zslnf

P'0 C.~ ~ 'illL) L

'IJ~RMD

.. PA&HP.3

t\)''

i' ).):tl») ii,<)t&l

TABLEOF CORI'ENTS

SECTION I PAGE

I-1.0I-2.0I-3.0IC.OI-5.0I-6.0I-6.1I-6.2I-6.3I-6.4I-6.5I-7.0I-8.0

Introduction t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Basls ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

General Program Plan Concept .

OrganizationDefinitionsRelief Requests Discussion....Relief Request GVRR-1 - ValvesRelief Request GVRR-2 - ValvesRelief Request GVRR-3 - ValvesRelief Request GVRR-4 - ValvesRelief Request GVRR-5 - ValvesPump and Valve P&ID's.....References

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

..I- 1

..I- 3..I-5..I-7..I- 8

I-10I-12I-14I-16I-17I-18I-19

. I-21

SECTION II—PUMP IST PROGRAM PLAN

II-1.0II-2.0II-3.0II-3.1II-3.3II-4.0

II

Pump Program Introduction"..........Pump Inservice Testing ScopePump Test Table - Nomenclafure.......Sample Pump /ST) Program TablePump Test Tables & NotesPump Relief Requests..............

. . II- 1

. . II- 2

. . II- 4

. . II- 6

. . II- 7

.. II-10

SECTION III—VALVEIST PROGRAM PLAN

m-1.0III-2.0III-3.0III-3.1III-3.2III-4.0

Valve Program Introduction..........Valve Inservice Testing ScopeValve Test Table - Nomenclature.... ~ ..Sample Valve /ST) Program TableValve Table CodesValve Test Tables:

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

. . III- 1

. . III-2

. . III-7III-10III-11

Attachment 1

Attachment 2Attachment 3Attachment 4Attachment 5

AASCCPCMSCPS...CSH

III- 1-1III-2-1III-3-1III-4-1III-5-1

NMP2-IST-001, Rev. 4 October 1993 Page iv of v

."$ )

V58c=.!'~i, V

'4( (

(L

lr

xk

t')

d

'\ L

Jl,

««d

(

L

XL

."NGR '"BAA

218'EG'

KHZKDZ)iCci

~ ! x'V4P.

PP.P,

J)d L ~

(4( )

Kav

V

".K'L f«LPg

.!Plkb.hfi8'bNHQbECV

Qh5'EE

."~ car "

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~ 1

~ ~

'- ~CI fill&?",lfiPJ.le...C.d

Table of Contents (Cont'd.)

Attachment 6Attachment 7Attachment 8

Attachment 9Attachment 10Attachment 11

Attachment 12

Attachment 13

Attachment 14Attachment 15Attachment 16Attachment 17Attachment 18Attachment 19Attachment 20Attachment 21Attachment 22Attachment 23Attachment 24Attachment 25Attachment 26Attachment 27Attachment 28Attachment 29Attachment 30

CSLDERDFREGAEGFFPWFWSGSNHCSHVKIAS .

ICS .

ISC .

LMSMSSNMSRCSRDSRHS,.SAS .

SFC .

SLS .

SVVSWPWCS

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

III-6-1III-7-1III-8-1

III-9-1..... III-10-1..... III-11-1

III-12-1..... III-13-1..... III-14-1..... III-15-1..... III-16-1..... III-17-1..... III-18-1..... III-19-1..... III-20-1..... III-21-1..... III-22-1..... III-23-1..... III-24-1..... III-25-1..... III-26-1..... III-27-1..... III-28-1..... III-29-1..... III-30-1

APPENDIX A EXCLUSION/JUSTIFICATIONTABLE

NMP2-IST-001, Rev. 4 October 1993 Page v of v

,\ NH'QOQRtilT

(Q%~+

GiIgffl03H T BffiT! Ioz>~"'>",0 f't~s

.'.3tvl.'~

'IPif~.»

tt

C

~l)iEiV

'r

I / ** I 4(

p'p

-'gyes

.p>". fir',8 aoni"

.~. 3zb

)z8850'>.'a

3ff3 A."

'A >RfA'IG~

oaN

t

r-rs'~l.

1.0 INTRODUCTION

This document presents Revision 4 to the First Ten Year Program Plan for Inservice Testing(IST) of Pumps and Valves at the Nine Mile Point Nuclear Station Unit 2 (NMP-2) incompliance with the requirements of 10CFR50.55a(g) and Station Technical Specification 4.0.5.This Program Plan was prepared in accordance with the rules of the ASME Boiler and PressureVessel Code, Section XI, 1983 Edition through Summer 1983 Addenda, and ASME/ANSIOM-1and OM-6, 1988 for relief valves and pump testing respectively.

Unit 2 IST Program Plan, Revision 1, was issued on 4/6/88 and incorporated the followingChange Requests:

PSI/ISI CR¹ 305, 306, 307, ISI/IST¹ 309, 310, 311, 312, 313,314, 315, 316, 317, 318, 319, 320, 321, 322, 323, 324, 325, 326,327, 328, 329, 330, 331, 332, 333, 334, 335, 336, 377, 338, 343,344, 345, 346, 347, 350, 351, 352, 353, 354 and 355.

Revision 2 was issued on 9/11/90 and incorporated the following Change Requests:

ISI/IST CR¹ 356, 362, 363, 364, 365, 366, 367, 369, 371, 372,373, 374, 375, 376, 377, 2-88-034-001 (Rev. 2), 2-89-034-024, 2-89-034-025, 2-89-034-028, 2-89-034-030 (Rev. 1), 2-89-034-31,2-89-034-32,2-89-034-42,2-89-034-60,2-89-034-61,2-89-034-62,2-89-2-89-034-63, 2-89-034-64, 2-89-034-65, 2-89-034-66, 2-89-034-67, 2-89-034-68, 2-89-034-69, 2-89-IST-70, 2-89-034-71, 2-90-IST-81, 2-90-IST-92, 2-90-IST-93, 2-90-IST-107, 2-90-IST-112, 2-90-IST-113, a!id 2-90-IST-114.

Revision 3 incorporates the following Change Requests:

2-90-IST-001, 002, 003, 004, 005, 006, 010, 011, 012, 013, 015,016, 018, 019, 020, 021, 022, 023, 024, 025, 028, 029, 030, 031,032, 033, a!ld 2-91-IST-034.

All requests for relief from the requirements of 10CFR50.55a(g) and ASME Code Section XIsince Revisions 1 and 2 have been submitted to the NRC and interim relief has been granted perNRC SER dated October 29, 1990 (Ref. TAC No. 63429).

These Relief Requests are included in this document and are being implemented. Additionally,in the effort to standardize the format of the Unit 1 and 2 ISI/IST Program Plans, this documentformat was changed to more closely follow the format established for the Unit 1 IST ProgramPlan, NMP1-IST-001. Additional changes incorporated into this document are as follows:

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 1 of 22

4'-'A02 da9.'.

)znibba z9vlsv ~

9l0$ ')I lit1 "lS,'!')R'9rfl 3C

(":)-

gf

liph 1'i

'L L

l .'bIn5i

,.)qc

apl.,iAt gJly",9~ j4)ok'.Oc. H~DOI

.(CO~ 814 .oi

lBhajlb9 919W ~

1.0 Introduction (Cont'd.)

Relief Requests EGA-VRR-1 and EGA-VRR-2 weredeleted. The valves addressed in these Relief Requests arenon-ASME; therefore, a Relief Request is not required.The contents of the Relief Requests were incorporated intoNotes (1) and (2).

~ All notes pertaining to valve set points were removed.These notes were found in the ISC, RHS, and SVV ValveTables. These setpoints are included in the plantsurveillance procedures.

~ Various changes were made to "Relief Request" and "ColdShutdown Identification Nomenclature" as listed in theRecord of Revisions.

~ Added the specific required test parameter for Relief andVacuum Breakers per OM-1.

~ Perform inservice testing for all pumps in accordance with OM-6,pursuant to 10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993(Ref. TAC No. M85500).

Allother changes to this document were editorial changes only.


319W Zgf>IW81b C

RAPU AwsrfoM'f mrrgoH

TR'>1iN9ffTaf. Qi19n90nf q91q oJ

.; -""I,~'~f1% Jn,

~n„f

'x"I "'n I

">l'f 7i? <,

."8 (f 5if i

«'1-'j.

!xQ. "", Jon vb ".<

,vlfn9op"znoa~oiJizoq gnf rf

IlffJ nl R9f1Jfl9

.3.„'i("i:,:-3

fi'f.'-.IiJII9)

i-(J9JI'c.

),'.9J 9d oJ

19noqmo."fa b9Jail 9d

;,Jn9rnoooh aiz'f IofIGqnfOO '(gf

"if).s, t '«)1 Ipl

g$

".~IP

.~+ a

"IBq zJ"

I9 fq I ~C'

z3ffJ o.

'f81301 ).Iaol ~~fe

'I l9J9'au..(.:i il

pl

i.P..)8

'~ .'IOI

,,=:--A.',.-',DJ,~.".nf qmo

...t>bG ff

Ifvnlo:9fJ 1

ifJ8'~).30

..)~'J'~iHDi

ooQf .l')ivo1<

2.0 BASIS

The Nine Mile Point Unit 2 P&ID drawings were used in conjunction with the ASME XI Code,Generic Letter 89-04, the Niagara Mohawk USAR, ANSI/ASMEOM-1, and ANSI/ASME OM-6to prepare the NMP2 1st Interval IST Program Plan and the Exclusion/Justification document.

The Exclusion/Justification document contains components which would otherwise be found in theIST Program, but for special cases have been exempted from the Plan.

The bases for excluding these components may be summarized as:

The component is exempt from testing per ASME XI IWV-1200. This includesvalves used for operating convenience, valves used for system control, and valvesused only for maintenance or test.

The component is safety-related, but considered passive with respect to its functionduring an accident. The component function has been evaluated by Niagara MohawkDesign Engineering and/or Licensing.

Components required to operate post-accident have DIV I or DIV III Class 1E power available.The Class 1E power designation, called "overcoding", is represented by yellow or green, and isidentified on the P&ID at each safety-related component mark number. Components which are notsafety-related (pipe class 4 or N), or do not receive Class 1E power post-accident, are ~n requiredto be tested per ASME XI and, consequently, are ~no contained in this document. Passivecomponents which do not have to change position to perform their intended safety function(s) willbe listed and comprise many of the entries in this document.

As part of the development of this document, a problem report (PR9301) and 33 associatedsupplements were prepared to identify components subject to testing. The Engineering dispositionsto these PR Supplements and the Program Change Requests were generated to define the ISTProgram at Unit 2. All safety-related components considered passive during an accident wereevaluated by Engineering via a PR Supplement or by Licensing via a 10CFR50 Appendix B QualityDetermination and inserted into the Exclusion/Justification Document. The attached Table containsa listing of the justification material used to substantiate this document.

In addition to the reference Code Edition and Addenda, the Program Plan has been prepared incompliance with the NRC guidance (except where exception/relief has been requested) containedin the NRC letter dated January 1978, "Guidance for Preparing Pump and Valve Testing ProgramDescriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)", and10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993 (Ref. TAC No. M85500); the NRCletter dated November 1976, "NRC Staff Guidance for Complying with Certain Provisions of10CFR50.55a(g) Inservice Inspection Requirements"; and NRC Generic Letter 89-04, dated April3, 1989, "Guidance on Developing Acceptable Inservice Testing Programs". These four documentsprovide the basis for selection of components, test requirements, and relief requests.


I R/qoD6 lOGIgC»

u arlJ a/imzoq~inism bns ".'.

'I~'I faBIJUMV","

ti'lift)OP.3.2 nq.Mlllp9'I,'tHpiir 'a

j fi~ e

>1/i+ ~~

>ll"f~V>

,f'iap, =~ I

t'ai=~

.*'tQ~

)")

'O'Il ~i

. 3fF.LXj

iA('C'

I

< ~".zt ll

i-~~i

2.0 BASIS (Cont'd.)

Additionally, the Valve Testing Program adopts Code Case N-415 (approved for use by the NRCper R.G.1.147, Rev. 5), which permits the use of ANSI/ASME OM-1, 1981 as alternativerequirements for replacement, repair and maintenance, inservice testing, and testing frequency forsafety valves, primary containment vacuum relief valves, relief valves (including all other vacuumrelief valves which are tested as relief valves) and rupture disks.

Regarding the inclusion of certain valves based on their Containment/Reactor Coolant Isolationfunctions, this Program is inclusive of valves which are categorized as Containment IsolationValves, as specified in the latest NMPC NMP2 Appendix J Program.

Current NMP2 practice is to perform Leakage Testing in accordance with the NMP2 Appendix JProgram. Any changes to the Appendix J Program shall be incorporated into the IST Program Planas applicable.

NMPC's position regarding time required to implement Code (ASME/O&M) requirements forupdated/upgraded design basis or design requirements is six (6) months from the update of theapplicable design basis documents (i.e., Tech Spec, USAR, Appendix "B" determination).

Pump inservice testing at NMP2 shall be performed in accordance with ASME/ANSI OM-6,pursuant to 10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993 (Ref. TAC No. M85500).


lZ QlHfz03 IX r

'!on@ bo)j f:

E

UW~ tk4l

o-xAO 'iP.NZ

zoic ioeqz mr";

v goi3zs3 rloo

:iQQ P.

:qmi zi.. zaotn!>

mRzyz ',

F89

'lC 2l QmJcOt

.Aq flSQd Mlti 3orr ~ot rroi3r.".;

. Azoic alamo)ls:

3.0 GENERAL PROGRAM PLAN CONCEPT

The Program Plan specifies Section XI testing requirements for the valves and ASME/ANSI OM-6~ ~

~

~

~

for the pumps providing a safety-related function. By definition, a safety-related function is onethat is required to assure:

A.B.C.

integrity of the reactor coolant pressure boundary;capability to achieve and maintain safe shutdown;capability to prevent or mitigate the consequences of postulated accidents whichcould result in off-site exposures comparable to the guidances of 10CFR50.55a(g),Part 100.

The selection criteria used for components included in this Program Plan are safety-related activecomponents. Safety-related passive components have no operability test requirements, and are notincluded in the Program Plan. Only those safety-related passive components which have leakageand position indication requirements have been included in the Program Plan.

Station Technical Specifications, manufacturers recommendations, system operating conditions,etc. may suggest additional components which should be included in the overall station testingprogram, but whose functions fall outside the criteria above and are not addressed by this ProgramPlan.

In general, Section XI and ASME/ANSI OM-6 require Quarterly testing of components unless itis impractical to do so. This Program specifies quarterly functional testing of pumps and valvesunless it has been determined that such testing would:

A.B.C.D.E.

render a safety-related system inoperable;cause a reactor scram or turbine trip;require significant deviations from the normal operations;require entry into inaccessible station areas;increase the possibility of an inner system LOCA.

Each component excluded from quarterly testing has been analyzed to determine when appropriatetesting may be performed. Ifoperation of a valve is not practical during station operation, theASME Section XI Code allows part-stroke exercising during normal station operation, and full-stroke exercising at cold shutdown.

Since the ASME Section XI Code allows testing at cold shutdown, this Program does not requestrelief for those valves for which testing is delayed until cold shutdown. The Valve IST ProgramPlan provides a justification for the delay of testing until cold shutdown. These justifications areprepared in a format similar to relief requests, and are included following the Valve Test Tablesfor each system.

Where it has been determined that testing is not practical during station operation, or at coldshutdowns, a specific relief request has been prepared unless the valves are non-ASME. Thespecific relief requests provide justification for not performing the ASME Section XICode requiredtesting, and also provide appropriate alternate testing.


~z lawns',at~soi$ orrqm*'l o3 EX

ar nall Ji

i;;<a

3.0 General Program Plan Concept (Cont'd.)

In addition to specific relief requests, general relief requests which address specific ASME SectionXI Code requirements found to be impractical for this station have been prepared. Because of thegeneral nature of these relief requests, and the number of components involved, they are presentedin Section I and are not in the individual system sections.


37QO'l%

QlII2'<3i

9'l)FN

') b'ooi/ibb.

4.0 ORGANIZATION

The Pump and Valve Inservice Testing Program Plan is organized into three sections:

Section I represents the general program commitment basis, theconceptual framework used in developing the Program Plan, andgeneral relief requests for Code requirements found to be impracticalfor this Station.

Section II deals specifically with the Pump Test Program.

Section IIIdeals specifically with the Valve Test Program.

Sections II and III are formatted in a manner to aid review. EachSection summarizes the basis and concepts used to formulate thePump and Valve Test Tables. Pump testing requirements aresummarized in a single Pump Test Table attached to Section II.Valve test requirements are summarized in Valve Test Tables attachedto Section III. The Valve Test Tables are arranged into separateattachments for each system.

Where quarterly testing has been found to be impractical, either a justification fordelay of test to cold shutdown or a relief request is provided following theappropriate Pump or Valve Test Table.

In those cases where additional discussion of the test requirements for a componentis needed, the remarks column of the Test Table contains a note number. Thesenotes may be found following the Valve Test Tables for each system.


~ lf

5.0 DEFINITIONS

The terms below, when used in the Inservice Testing Program Plan, are defined as follows:

Quarterly An interval of 92 days for testing components whichcan be tested during normal plant operation.

Cold Shutdown Testing deferred until cold shutdown where testingshall commence within 48 hours of achieving coldshutdown, and shall continue until testing is completeor until the plant is ready to return to power.Completion of cold shutdown testing is not aprerequisite to return to power. Any testing notcompleted at one cold shutdown shall be preferentiallyscheduled for testing at subsequent cold shutdowns.Cold shutdown testing of a component is not requiredif less than 92 days have passed since the last coldshutdown test of that component.

NOTE: Cold Shutdown test results in the "Alert Range" shallhave the test frequency of the applicable component(s)increased such that testing is performed duringsubsequent cold shutdown ifnot performed during thelast 45 days,

Refueling Testing deferred to refueling willbe performed duringthe normally scheduled refueling shutdown beforereturning to power operation.

PressureIsolation Any valve which acts as an isolation boundary between

the high pressure Reactor Coolant System and a systemhaving a lower operating or design pressure.

ContainmentIsolation Unless exempted per Technical Specification, any

valve which performs a containment isolation functionand is included in the Appendix J Leakage Rate TestProgram.

Active Any valve which is required to change position toaccomplish its safety-related function.


4

5.0 Definitions (Cont'd.)

Passive Any valve which is not required to change position toaccomplish a specific function. Additionally, passivevalves are those valves where the normal and safetyposition are the same, and the valve is not required tochange position during any normal plant operatingcondition, except for convenience use, and providedthe valve does not receive an automatic actuationsignal.


6.0 RELIEF REQUESTS DISCUSSION

6.1 General

Written relief requests, as allowed by 10CFR50.55a(g)(5)(iii), are discussed in Section I forgeneral relief requests; Section II for specific pumps; and Section IIIfor specific valves, toprovide justification for:

performance of testing requirements on pumps and valves that are impracticalduring both operation and cold shutdown;

~ the use of alternate testing methods when Code requirements are eitherimpractical, or where the alternate methods provide equal to, or greater,assurance of pump and valve operational readiness.

Each relief request is formatted to include the following information:

relief request number;system (specific relief requests only);pump or valve identification number;category (valves only);class;function (specific relief requests only);testing requirement;basis for relief;alternate testing.

6.2 Generic Pump and Valve Relief Requests

Generic relief requests are used when a relief request applies to pumps or valves in general,e.g., all containment isolation valves that are Type C tested, or all centrifugal pumps.

These relief requests are formatted for numerical filing as follows:

GVRR-Y or GPRR-Y where:

GVRR = Generic Valve Relief Request;GPRR = Generic Pump Relief Request;Y = Sequential Number


6.0 RELIEF REQUFDTS DISCUSSION (Cont'd.)

6.3 Specific Relief Requests~

~ ~

These reliefs are used to provide relief to specific pumps or valves and are formatted fornumerical filing as follows:

XXX-PRR-Y or XXX-VRR-Y where:

XXX = System Designation;PRR = Pump Relief Request;VRR = Valve Relief Request;Y = Sequential Relief Request number in any system.


6.3 RELIEF REQUEST NO. GVRR-I

Valves Containment Isolation Valves

Category A

Class 1,2

TestingRequirements Leak rate test in accordance with Subsection IWV-3420.

Basis forRelief IWV-2200(a) defines "Category A" valves as "valves for which seat

leakage is limited to a specified maximum amount in the closedposition for fulfillment of their function". Containment isolationvalves, as defined in technical specifications, have been identified as"Category A" valves for ASME XI testing purposes since they arerequired to be leak rate tested. Leak rate requirements for thesevalves are based on a total allowable leakage rate for all valves. Onlythose containment isolation valves with potential for bypass leakagepaths outside containment have individual maximum allowable leakrates (as defined in technical specifications). For example, excessflow check valves listed in technical specifications as containmentisolation valves will receive an operability test and will not receiveleak rate testing as allowed by technical specifications and IWV-3421.

Since containment isolation valves are "Category A", leakage ratetesting requirements of IWV-3420 must be satisfied. The leakage ratetesting performed, per Appendix J, satisfies the requirements ofIWV-3421 through 3425. However, it does not satisfy the individual valveleakage rate analysis and corrective actions required by IWV-3426and 3427. Therefore, the requirements of IWV-3426 and 3427(a)will be applied to individual leakage rate testing results obtainedduring (Appendix J) technical specification required surveillancetesting. The requirements of IWV-3427(b) will not be applied asoutlined in NRC generic letter No. 89-04.

AlternateTesting Those valves listed as containment isolation valves in the Technical

Specifications and categorized as "Category A or AC" valves (withthe exception ofcertain valves in Table 3.6.3-1, Item D) shall be leakrate tested in accordance with 10CFR50, Appendix J. In addition,individual valve leakage rates willbe obtained by test or analysis andthe requirements of IWV-3426 and 3427(a) will be applied via aseparate procedure.


6.3 Relief Request No. GVRR-1 (Cont'd.)

Containment isolation valves that are exempted from 10CFR50,Appendix J, shall meet the test requirements of the TechnicalSpecification Table 3.6.3-1 notes, the USAR Table 6.2-56, 10CFR50,Appendix J requirements, or of the Inservice Testing Program. Forexample, excess flow check valves shall meet the requirements ofTechnical Specifications Table 3.6,3-1, Note "E", and IST ProgramPlan Relief Request GVRR-2.


Valves

6.4 RELIEF REQUEST NO. GVRR-2

Excess Flow Check Valves

Category

Class

TestingRequirements Quarterly Operability Testing

Basis forRelief Excess flowcheck valves are installed on instrument lines penetrating

containment to minimize leakage in the event of an instrument linefailure outside the containment in accordance with Regulatory Guide1.11. The excess flow check valve is basically a spring loaded ballcheck valve. Since the system is normally in a static condition, thevalve ball is held open by the spring. Any sudden increase in flowthrough the valve (i.e., line break) will result in a differentialpressure across the valve which will overcome the spring and closethe valve. The valve is designed to allow some leakage past the seatin the closed position. This leakage will act to equalize pressureacross the valve in the event the excess flow condition is corrected,thus allowing the spring to reopen the valve. At NMP2, there areexcess flow check valves with and without installed positionindication. Functional testing of valve closure is accomplished byventing the instrument side of the valve while the process side isunder pressure and observing the position indicator (for those withinstalled position indicators) and by verifying that only a smallamount of leakage exists through the vent.

The testing described above requires the removal of the associatedinstrument or instruments from service. Since these instruments arein use during plant operation and cold shutdown, removal of any ofthese instruments from service could cause a spurious signal whichcould result in a plant trip, an inadvertent initiation of a safetysystem, loss of decay heat removal and/or the defeating of safetyinterlocks.

In addition to the plant safety concerns, personnel safety concernsmust be considered since the process side of many of these valves isnormally high pressure (>500 psig) and/or high temperature(>200'F) and highly contaminated reactor coolant. The remainderof the valves process side is the containment atmosphere which isinerted, contaminated, and at atmospheric pressure during operationand cold shutdown; therefore, the test described above cannot beaccomplished.


6.4 Relief Request No. GVRR-2 (Cont'd.)

I

In summary, due to the plant and personnel safety concerns and plantoperating conditions that prohibit the testing of these valves quarterlyor at cold shutdown, testing will be performed at refueling whendecay heat loads are at a minimum, the containment is de-inerted andventilated, and safety systems can be removed from service to preventinadvertent initiation.

AlternateTesting Functional testing willbe performed at refueling.


6.5 REUEF REQUEST NO. GVRR-3

Valves Rapid actuating power-operated valves with stroke times of 2 sec orless

Category A,B

TestingRequirements IWV-3417 requires corrective action ifthe measured stroke time for

a valve that normally strokes in 10 sec or less varies by 50% fromthe last measured stroke time. IWV-3413 allows measurement to thenearest sec for stroke times of 10 sec or less.

Basis forRelief For rapid actuating power-operated valves, the application of the

above criteria could result in requiring corrective action when thevalves are functioning normally. These valves generally are small airand solenoid operated valves which, because of their size and actuatortypes, stroke very quickly. Operating history on this type of valveindicates that they generally either operate immediately or fail tooperate in a reasonable length of time. The intent of the referencedCode sections is to track valve stroke time as a means of detectingvalve degradation. This type of valve does not lend itself to thistracking technique.

AlternateTesting A maximum stroke time of 2 sec will be specified for each rapid

actuating valve. If the valve strokes in 2 sec or less, it will beconsidered acceptable and no corrective action will be required. Ifthe valve exceeds 2 sec, it will be considered inoperable and theappropriate corrective action willbe taken.


6.6 RELIEF REQUEST GVRR-4

Valve(s) System Pressure Pump Discharge Check Valves

2CSH*P2 to CSH Header 2CSH*V17, V552CSL*P2 to CSL Header 2CSL*V14, V21,and 2RHS*V47, V48

2RHS*P2 to valves 2RHS*V60, V61, V17, and V18

Category

Class 2

TestingRequirements Quarterly reverse flow operability testing

Basis forRelief These check valves close on the initiation of the associated ECCS

system to prevent the diversion ofECCS pump discharge flow via thepressure pump piping. In each case above, these check valves are inseries without any means provided for individual reverse flowverification. NMPC contacted General Electric who designed thesystem to determine the need for both check valves. GE said thatonly one was needed and that the second was placed there for addedreliability. NMPC considered removing the internals from one valve;however, NMPC determined a more conservative approach would beto test the valves as a unit. The test results of each set will beapplied to each valve of the set individually.

AlternateTesting Test each set of series check valves as a unit quarterly for reverse

flow closure.


Relief Request GVRR-5

IvesCategory

Code Requirements

Code Acceptance Criteria

Allpower-operated valves other than rapid acting valves.

A,B

Corrective Action, IWV-3417(a)

The acceptance criteria provided by IWV-3417(a) allows anunchecked gradual degradation (stair steps) of valve stroke timerather than fixing an allowable deviation limit from whichcorrective action is started.

Basis for Relief Basing the trending of stroke times for power-operated valves onthe stroke time measured for a valve during its previous test canpermit the gradual degradation of valve over an extended periodof time without taking any action until the limiting values of fullstroke time is exceeded.

To base acceptance criteria on reference values would giveadequate assurance to operational readiness and provide areasonable alternative to the Code requirements. In addition, thisis a more conservative than the Code requirements and provides anacceptable level of quality and safety because it willnot permit thegradual increase in valve stroke time without requiring correctiveaction.

Alternate AcceptanceCriteria Reference values shall be determined from the results ofpreservice

testing or from the results of inservice testing. These tests shallbe performed under conditions as near as practicable to thoseexpected during subsequent inservice testing.

Reference values shall only be established when the valve is knownto be operating acceptably. If the particular parameter beingmeasured can be significantly influenced by other relatedconditions, then these conditions shall be analyzed.

Per GL 89-04, position 6, reference values willbe used instead ofthe previous stroke time to determine acceptability in accordancewith IWV-3417(a).


7.0 PUMP AND VALVEP&ID's

A listing of all the P&ID's identifying ASME Class 1, 2, and 3 safety-related pumps and valves~ ~

~

~

~ ~

~ ~ ~

is included in Table 2.3-1.

ID BER

TABLE2.3-1PUMP AND VALVE(IST) PROGRAM P&ID'S

2-A,B,C,D,E1-A,B,C,D,E,F,J

6-B11-A,B,C,D,E„G,H,J,L,P,Q13-A,B,C,D,E

19-D,E,F,G,J,L,M

20-E28-A,B,C29-A,B,C30-B,C31-A,B,C,D,E,F,G32-A33-A,B35-A,B,C,D36-A37-A,BEM-38A38-A,B,C43-G

SymbolsMain SteamMainsteam Safety Valves,Vents, and DrainsFeed waterService WaterReac. Bldg. Closed LoopCooling WaterInstrument AirService AirBreathing AirReactor Vessel InstrumentReactor Recirc. SystemCRD Hydraulic SystemResidual Heat Removal SystemLow-Pressure Core SprayHigh-Pressure Core SprayReactor Core Isolation CoolingStandby Liquid ControlReactor Water Cleanup SystemNeutron Monitoring SystemFuel Pool Cooling and CleanupFire Protection Water

(MSS)(SVV)

(FWS)(SWP)(CCP)

(IAS)(SAS)(AAS)(ISC)(RCS)(RDS)(RHS)(CSL)(CSH)(ICS)(SLS)(WCS)(NMS)(SFC)(FPW)


P&ID MBER Y TEM

53-A,B61-A,B62-A,B63-E67-A81-A82-A,B104-AB,C

105-B

Control Bldg. Chilled WaterPrimary Containment PurgeDBA Hydrogen RecombinerReactor Bldg. Floor DrainsDrywell Equipment DrainsCont. Leakage MonitoringCont. Atmosphere MonitoringDiesel Gen. Air StartupStandby Diesel Gen. FuelNitrogen System

(HVK)(CPS)(HCS)(DFR)(DER)(LMS)(CMS)(EGA)(EGF)(GSN)


8.0 REFERENCES

8.1

8. 2

8. 3

8. 4

8. 5

ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection ofNuclearPower Plant Components; 1983 Edition through Summer 1983 Addenda.

10CFR50.55a(g), Inservice Inspection Requirements, Guidance for Preparing Pump andValve Testing Program Descriptions and Associated Relief Requests.

Updated Safety Analysis Report (USAR), Nine Mile Point Nuclear Station Unit 2.

Updated Safety Analysis Report (USAR), Sections 1.12-32a, NMP2 for LimihxlVibrationon ECCS Systems.

USNRC Letter, Capra to Mangan, "Use of ASME Code Case N-415 for the Inservice Testing(IST) Program at Nine Mile Point Unit 2 (TAC 67172), dated April 14, 1988. Access¹09416 1615. NMPC Letter NMP2L 1104, Mangan to USNRC, Untitled, subject regardinguse of ASME Code Case N-415, dated January 18, 1988. Access ¹09104 3800.

8. 6 ANSI/ASME OM-1 1981, "Requirements for Inservice Performance Testing of NuclearPower Plant Pressure Relief Devices".

8. 7

8.8

8. 9

ANSI/ASME OM-6 1987, "Inservice Testing of Pumps in Light-Water Reactor PowerPlants". Used for guidance only.

ANSI/ASME OM-10 1987, "Inservice Testing of Valves in Light-Water Reactor PowerPlants". Used for guidance only.

Nine Mile Point Unit 2 Technical Specifications.

8.10

8.11

8.12

8.13

8.14

NRC letter dated January 1978, "NRC Staff Guideline for Preparing Pump and Valve TestingProgram Descriptions and Associated Relief Requests, pursuant to 10CFR50.55a(g)".

NRC letter dated November 1976, "NRC Staff Guidance for Complying with CertainProvisions of 10CFR50.55a(g) Inservice Inspection Requirements".

NRC Generic Letter 89-04, dated April 3, 1989, "Guidance on Developing AcceptableInservice Testing Programs" and "Minutes to Public Meeting on Generic Letter 89-04".

Division I Draft Regulatory Guide and Valve Impact Statement (Draft 2), "Identification ofValves for Inclusion in Inservice Testing Programs".

NRC Regulatory Guide 1.26, "Quality Group Classification and Standards for Water-, Steam,and Radioactive-Waste-Containing Components of Nuclear Power Plants".

8.15 NRC Regulatory Guide 1.137, "Fuel Oil Systems for Standby Diesel Generators".


8.0 References (Cont'd.)

8.16 NRC IE Information Notice 84-74, "Isolation of Reactor Coolant System from Low-PressureSystems Outside Containment".

8. 17 NMPC Correspondence - Prior to Code Case N-415 approved

A. P.E. Francisco to it 2 Licensing File, Notes of Telecon with NRC regarding IST ReliefRequest and Commercial operation of Unit 2, dated March 9, 1988. Access ¹ 094003404.

B. K.B. Thomas to R. Abbott, Nine Mile Point Unit 2 IST, dated March 10, 1988. Access¹09400 3408.

C. K.B. Thomas to Unit 2 Licensing File, Notes ofTelecon with NRC IST Relief Requests,Dated March 14, 1988. Access ¹09401 2677.

8.18 NMPC Correspondence - SRV Testing

A. Egap to Korcz, Pump and Valve Program Revision and SRV Testing, File Code SM-CS90-0293, dated August 15, 1990.

B. Egap to Distribution, SRV Testing (Korcz response to above memo), File CodeNMP73769, dated November 28, 1990.

C. Egap to Distribution, IST Meeting Minutes, File Code NMP 71597, dated September 26,1990.

8.19 NMPC Correspondence - Vacuum Breakers

A. Hammelmann/Egap, ANSI/ASMEOM-1 Code Interpretation, File Code SM-ISI90-0053,dated November 27, 1990.

8.20 USNRC Safety Evaluation of the Inservice Testing (IST) Program for Pumps and Valves,Nine Mile Point Unit 2 LTAC No. 63429, dated October 29, 1990.

8.21 USNRC SER for ISC-VRR-1, TAC No. 79781, dated May 28, 1991.

8.22 USNRC SER for EGF-PRR-1, SLS-prr-2, and GPRR-3, TAC No. M85500, dated April 19,1993 (allows the use of ASME/ANSI OM-6 for pump testing).


1.0 PUMP PROGRAM INTRODUCTION

Class 1, 2, and 3 pumps which are within the scope of the Inservice Testing Program, as definedin Section II Paragraph 2.1, and which are not exempt per Section IIParagraph 2.1.1, shall betested in accordance with the ASME/ANSI OM-6 Code Editions stated in Section I Paragraph1.0. Tables listing the pumps, including all applicable testing requirements and frequencies, arecontained in this Section. Pump table descriptions are found in this Section. When the pumptesting requirements of the applicable Code cannot be met for any reason, Relief Requests areprovided at the end of this Section.

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 1 of 10

2.0 PUMP INSERVICE TESTING SCOPE

2.1 INTRODUCTION

The scope of the Pump IST Program includes certain Class 1, 2, and 3 safety-related centrifugal and positive displacement type pumps that are provided withan emergency power source and that are not exempt by Paragraph 2.1.1, andwhich function to:

shut down the reactor; and/or

mitigate the consequences of an accident.

These safety-related pumps are found within the ASME Class 1, 2, and 3boundaries. The pumps within this scope are listed in Section II.

2.1.1 PUMP EXCLUSIONS IDENTIFIED IN OM-6, 1.2

NOTE: The term "Exclusions" is used in OM-6, 1.2 and, for the purposeof this Program Plan, is synonymous with "Exemptions".

A. drivers of pumps, with the exception that the driver and pump form an. integral unit and the pump bearings are in the driver;

B. pumps supplied with emergency power solely for operating convenience.


3.0 PUMP TEST TABLE - NOMENCLATURE

PUMP PROGRAM TABLEDESCRIPTION

o Pump Table Summary

The ASME Class 1, 2, and 3 Pump IST Program Table (Section Il)contains an alpha-numeric listing of all the safety-related pumps includedin the NMP2 Pump ASME/ANSE OM-6 IST Program. The data

. contained in these Tables identifies the inservice test parameters to bemeasured, the applicable Relief Requests, and any applicable remarks. Acolumn for testing frequency was not included since all the required pumptesting willbe performed QUARTERLY.

o Pump Program Table Format

The Pump IST Program Tables have been organized to provide thefollowing information:

Note; The numbers in parentheses correspond to those found onthe following sample pump (IST) Program Table.

(1) PUMP ID NUMBER: The pump identification number;

(2) SYS ID: 3-digit abbreviation for the pump's specific system;

(3) CODE CLASS: ASME Code Class;

(4) P&ID and COORD.: Piping and Instrumentation Drawing wherepump is located and location coordinates of the pump on theP&ID;

(5) NOTE: Applicable notes (eg., Technical Specification references,etc.) in numerical format and explained in detail on the last pageof the Pump Table;

(6) PARAMETERS: This column lists the applicable testingparameters that willbe measured. The parameters listed are thoserequired by the Code unless alternate testing is provided by ReliefRequest. The following is a description of applicable parameters:

(6.1) SPEED - pump speed (only required for variable speedpumps);


3.0 Pump Test Table - Nomenclature (Cont'd.)

(6.2) Discharge Pressure for positive displacement pumps;

(6.3) DIFF. PRESS - pump differential or discharge pressure;

(6.4) FLOW - pump flowrate;

(6.5) VIB. - pump vibration velocity;

(7) REMARKS: Any additional pertinent information


3.1 SAMPLE PUMP /ST) PROGRAM TABLE

NMP2-IST-001DATE 'X/XX/XX

PUMP SYSTEM ASMB P&ID AND NOTE SPEED DISCHAROB DIFF FLOW VIBRATION REMARKSNO. CLASS COO RD. PRESSURE PRESSURE

(3) (4) (6.1) (6 '2) (6.3) (6.4) (6.S)


NMP2-IST-001, R. 4FIRST TEN-YEAR INTERVAL

NINE MILE POINT NUCLEAR POWER STATION — UNIT 2DATE: 10/25/93PAGE: 6 of 10

PUMP IDSYS ASME P&ID/ID CLAS COORD NOTE SPEED

DISCH. DELTAPRESS. PRESS. FLOW VIBRATION REMARKS "

2CSH*P1 CSH 2 33BH-7

'NOTE 1 N/R Y

2CSL*P1

2EGF*P1A

CSL 2

EGF 3

32AB-8

104CE-6

NOTE 1 N/R Y

NOTE 1 N/R Y

2EGF*P1B EGF 3 104BE-8

NOTE 1 N/R Y

2EGF*PlC

2EGF*P1D

2EGF*P2A

EGF 3

EGF 3

EGF 3

104CC-6

104BC-8

104BE-4

NOTE 1 N/R Y

NOTE 1 N/R Y

NOTE 1 N/R Y

2EGF*P2B EGF 3 104BC-4

NOTE 1 N/R Y

2HVK*P1A

2HVK*P1B

53AC-6

53AC-10

NOTE 1 N/R Y

NOTE 1 N/R Y

2ICS*P1 ICS 2 35DG-9

N/R Y

2RHS*P1A RHS 2 31FD-7

NOTE 1 N/R Y


NINE MILE POINT NUCLEAR POWER STATION — UNIT 2DATE: 10/25/93PAGE: 7 of 10

PUMP ID

2RHS*P1B

SYSID

ASME P&ID/CLAS COORD NOTE

31EE-2

SPEED

NOTE 1

DISCH. DELTAPRESS. PRESS.

N/R Y

FLOW VIBRATION REMARKS

2RHS*P1C 31GD-6

NOTE 1 N/R Y

2SFC*P1A

2SFC*P1B

2SLS*P1A

SFC

SFC

SLS

38BE-3

38AE-10

36AH-5

NOTE 1

NOTE 1

NOTE 1

N/R Y

N/R Y

SLS-PRR-1

2SLS*P1B SLS 36AH-9

NOTE 1 SLS-PRR-1

2SWP*P1A SWP 11BC-9

NOTE 1 N/R Y

2SWP*P1B SWP 11AH-5

NOTE 1 N/R Y

2SWP*pjc SWP 11AH-10

NOTE 1 N/R Y

2SWP*P1D SWP 11AD-5

NOTE 1 N/R Y

2SWP*P1E

2SWP*P1F

SWP

SWP

11BH-9

11AD-10

NOTE 1

NOTE 1

N/R Y

N/R Y


NINE MILE POINT NUCLEAR POWER STATION — UNIT 2DATE 10/25/93PAGE: 8 of 10

PUMP IDSYSID

ASMECLAS

P&ID/COORD NOTE SPEED

DISCH. DELTAPRESS. PRESS. FLOW VIBRATION REMt&KS

2SWP*P2A SWP 11JJ-6

NOTE 1 N/R Y

2SWP*P2B SWP 11JJ-6

NOTE 1 N/R Y

PUMP TEST TABLENOYES

In the Pump Test Table, the parameters to be measured or observed and the test frequency areidentified. Footnote 1 refers to amplifications, deviations, and exceptions to the Code requirementsand is further discussed below:

(1) For pumps with constant speed drive, the speed is not measured sincethe test will be performed at nominal motor nameplate speed, as

required by OM-6.


System

Pump(s)

4.0 RELIEF REQUEST NO. SLS-PRR-1

Standby Liquid Control

2SLS*P1A, P1B

Class

Function Inject borated solution into the reactor for emergency shutdown.

TestingRequirements In accordance with IWP-4600, flow rate shall be measured using

a rate or quantity gravity meter installed in the pump test circuit.The meter may be in any class that provides an overall readoutrepeatability of J 2% of full scale.

Basis forRelief These pumps'est circuits are not provided with in-place flow

meters. Flow measurement for these pumps willbe accomplishedby use of a clamp on ultrasonic flow meter with a full-scalerepeatable accuracy of J 3%. The J 3% accuracy exceeds theallowable instrument accuracy contained in Table IWP-4110-1;however, this small reduction in accuracy will not provide asignificant reduction in the ability to determine pump operability.NMPC will continue to evaluate industry development of moreaccurate instrumentation.

AlternateTesting Flow rate willbe measured using a clamp on ultrasonic flow meter

with a repeatable full-scall accuracy of J 3%.


0

1.0 VALVEPROGRAM INTRODUCHON

Class 1, 2, and 3 valves which are within the scope of the Inservice Testing Program, as definedin Section III, Paragraph 2.1, and which are not exempt per Section III, Paragraph 2.1.3, shallbe tested in accordance with the Section XI Code Editions stated in Section I, Paragraph 1.0.Valve Table descriptions and the Tables listing the valves, including all applicable testingrequirements and frequencies, are contained in this Section. When valve testing must bedeferred to cold shutdown, cold shutdown test justifications are provided at the end of eachrespective systems Table in this Section. When the valve testing requirements of the applicableCode cannot be met for any reason, Relief Requests are provided at the end of each respectivesystems Table in this Section.

NMP2-IST-001, Rev. 4 Section III- October 1993 PAGE 1 of 10

„2.0 VALVEINSERVICE TESTING SCOPE

INTRODUCTION

The scope of the valve IST program includes certain ASME Class 1, 2, and 3safety-related valves that are not exempt by Paragraph 2.1.3 and which functionis to:

shut down the reactor to a cold shutdown condition; and/or

mitigate the consequences of an accident.

These safety-related valves are found within the ASME Class 1, 2, and 3boundaries. The valves within this scope are listed in Section III.

2.1.1 CODE REQUIRED POSITIONS

This Section indicates the positions used to clarify Code requirements as theyapply for the formulation and the implementation of this program:

o Check Valve Full/Partial Stroke

In most cases, full design flow through a check valve requires less thanfull mechanical valve movement. As used in this program, with theexception of testable check valves, the term "full stroke" refers to theability of the valve to pass design flow and not the full mechanicalstroking. Forward flow stroke operability testing willbe by any methodthat verifies the valve is capable of passing design flow. Any test thatverifies less than full design flow capability is considered as a partialstroke test.

o Valve Position Indicator Verification

Verification of proper indication of remote position indication willnormally be accomplished by locally observing the position of the valveand comparing it with the remote indication. However, certain valves,such as solenoid-operated and excess flow check valves, are not equippedwith a local means to verify position; therefore, position willbe verifiedby the observation of system parameters, such as flow or pressure,

NMP2-IST-001, Rev. 4 Section III - October 1993 PAGE 2 of 10

2.0 Valve Inservice Testing Scope (Cont'd.)

during valve cycling, in conjunction with valve light indicators (unless thevalve is of a design that requires a positive change in disk position toeffect a change in the indicator lights).

2.1.3 VALVEEXEMPTIONS IDENTIFIEDIN IWV-1200

A. Maintenance Valves - Valves which are used only to isolatecomponents to perform maintenance, including relief valves whichprovide overpressure protection for a component that is isolatedonly for maintenance;

B. Operating Convenience Valves - Valves used only for operatingconvenience, such as manual vent, drain, instrument, and testvalves;

C. System Control Valves - Valves such as pressure-regulating, flowcontrol, and manual throttle valves, that do not have an analyzedfail safe function;

D. Valves in External Control Protection Systems - systemsresponsible for sensing plant conditions and providing signals forvalve operation.

2.1.4 ALTERATIONS TO CODE REQUIREMENTS

o Increased Testing Frequencies

The testing frequencies for certain Category C and D valves havebeen increased in compliance with Technical Specification orUSAR commitments. The specific frequency designations and theassociated references are contained in the test frequency section ofValve Table.

o Cold Shutdown Test Justification Discussion

The Code permits the delay of valve testing that is impracticalduring operation to be performed during cold shutdown.Justification for this delay of testing is provided by the ColdShutdown Test Justifications located following each systems valveTable. Each cold shutdown test justification is formatted tocontain the following information:



cold shutdown test justification number;system;valve identification number;category;function;quarterly test requirements;cold shutdown test justification;quarterly partial stroke testing(as applicable);

cold shutdown testing.

The cold shutdown test justifications are formatted for numerical filingasfollows:

XXX-CS-Y where:

XXXCSY

system designation;valve cold shutdown test justification;sequential number within any system'sRelief Request number, USAR or Tech.Spec. reference, is provided in this space.

OM-1-1981 APPLICABILITYSTATEMENTS

NMP2 IST Program Plan adopts ASME XICode Case N415 which statesthat the requirements for acceptance testing, replacement, repair andmaintenance, periodic testing, and test frequency contained inANSI/ASME OM-1-1981 may be used as alternate requirements forpreservice tests, replacement, repair and maintenance, inservice tests, andtest frequency for safety valves, relief valves (including vacuum reliefvalves), and rupture disks (non-reclosing pressure relief devices) ofSubsection IWV of Section XI, Division 1.

o Use of ASME Code Case N-415 was approved for use at NMP2by the NRC in their letter dated April 14, 1988, R. Capra to C.V.Mangan, entitled "Use of ASME Code Case N-415 for theInservice Testing Program at Nine Mile Point Unit 2 (TAC67172)". See Reference 8.16.



Before the NRC approval of Code Case N-415, each componentreceived a base line test in accordance with the IST Program Planprior to commercial operation, as required by ASME Section XI,IWV-3100. Implementation of OM-1 commenced at commercialoperation April 1988. See References listed in 8.17.

Note: This is consistent with ASME Section XI, IWA-2420;inspection intervals begin at "initialstart ofpower unit commercialoperation".

'n

October 1990, a review of the Safety Relief Valve testingindicated that Relief Request MSS-VRR-1 was no longer required.Other changes to the IST Program Plan are discussed inReferences 8.10.

In November 1990, discussions with an OM-1-1981 representativeindicated that only vacuum breakers whose function is to protectthe containment are to be tested in accordance with OM-1-1981,Section 1.3.4.3 (3.3.2.3 and 3.4.2.3). Allother vacuum breakersare to be tested as pressure relief devices and tested in accordancewith OM-1-1981, Section 1.3.4.1 (3.3.2.1 and 3.4.2.1). Thisnecessitated the addition of ISC-VRR-1. See Reference 8.19,Section I.

o Relief and Vacuum Breakers not meeting acceptance criteria

ASME Class 1, 2 and 3 pressure relief devices tested inaccordance with ANSI/ASMIOM-1, 1981 code which exceed theset pressure acceptance criteria by J 3% or greater, the followingrequirements shall be met:

ao Additional valves shall be set pressure tested on the basisof two additional valves to be tested for each valve failureup to the total number of valves of the same type andmanufacturer. If any of the additional valves testedexceeds the stamped set pressure criteria by + 3% orgreater, then all valves of the same type and manufacturershall be tested.



b. The cause of failure shall be determined and evaluated.

c. Valve shall be repaired or replaced and retested before thevalve returned to service.

o When installing a partial complement of pretestedASME Class 1, 2 and 3 valves to replace thosevalves that had been in service in accordance withthe applicable test schedule, shall be pressure testthe valves which were removed within three (3)months of removal from the system or beforeresumption of electric power generation, whicheveris longer.


3.0 VALVETEST TABLE- NOMENCLATURE

VALVEPROGRAM TABLEDESCRIPTION

The Valve Program Tables (Section III)provide a tabulation of ASME Class 1, 2, and 3 safety-related valves included in the NMP2 Valve IST Program. The Tables are arranged by systemand the valves in each system are listed in alpha-numeric sequence.

VALVEPROGRAM TABLEFORMAT

NOTE: The numbers in parentheses correspond to those found on the samplevalve IST Program Table, found on the next page.

(1) SYSTEM: the system that the particular Table applies to;

(2) VALVENUMBER: the valve identification mark number;

(3) CLASS: ASME Code Class;

(4) P&ID: piping and instrumentation drawing where the valve is located;

(5) COORD: location coordinates of the valve on the P&ID;

(6) VCAT: valve category, as identified by IWV-2200

(7) SIZE: valve size in inches;

(8) VALVETYPE: valve design type;

(9) ACTUATTYPE: type of actuator used to change position of valve;

(10) VALVEPOSITIONS:

(A) NRM - position during normal plant operation;(B) SAF - position to fulfillsafety function;(C) FAL - position valve fails to on loss of actuator power;


3.0 Valve Test Table - Nomenclature (Cont'd.)

(11) ASME Section XITEST/FREQ/DIR: The testing requirement, frequency the testshould be performed and, in parentheses, either the direction(s) stroke timeshould be measured for power-operated valves, or the direction(s) the valveshould be exercised for check valves. This column identified ASME Section XICode requirements. The IST Program Plan commitment column will reflect thesame test requirements unless alternate testing is provided by relief request orcold shutdown test justification.

Format for the field is as follows:

Test Code - Frequency Code (stroke time or exercise direction)

eg.,: FE-Q(F&R) = Full stroke exercise quarterly in the forwardand reverse flow direction;

ST-CS(O) = Measure valve stroke time in the opendirection during cold shutdowns;

FE-R(R) = Full stroke exercise during a refuelingoutage in the reverse direction;

(12) RELIEF REQ./C.S. JUST.: Indicates whether or not there is a Relief Request,or Cold Shutdown Test Justification applicable. This column identifies thespecific Relief Request or Cold Shutdown Test Justification.

(13) IST PROGRAM PLAN COMMITMENT - TEST/FREQ/DIR: This columnreflects the actual testing to be performed as required by ASME Section XI or aswritten relief was requested. This column also reflects testing as required byCold Shutdown Justifications. This column reflects the total programcommitment for the valve.

(14) REMARKS: Any additional pertinent information, such as TechnicalSpecification note references are provided in this space.

VALVEPROGRAM TABLE CODES

A quick reference table providing definitions for the codes (abbreviations) used on the ValveProgram Tables is provided following the Valve Table sample.


SAMPLE VALVE/ST) PROGRAM TABLE

FIRST TEN-YEAR INTERVALNINE MILEPOINT NUCLEAR POWER STATION - UNIT 2

NMP2-IST-001DATE: XX/XX/XX

SYSTEM: (I)

IST POM. PLANVALVE ASME P&ID VALVE SIZE ACTU POSITIONS ASMBSBCIION XI REL REQ. COMMITMENT

NO. CLASS COORD. (CAT.) &TYPE TYPE NRM SAF FAL TEST/FREQ/DIR C.S. JUST. TEST/FREQ/DIR REMARKS

NMP2-IST-001, Rev. 4 Section III- October 1993 Page 9 of 10

VALVETABLE CODES

CODE DEFINITION

VALVETYPE

CODB DEFINITION CODE

ACI1JATOR TYPE

DEFINITION

AOV Angle Valve Needle EHA EcctrntHydraulic Actuator

BFV

BLV

DIV Diaphragm

POV

PRV

Plug

Regulating

Rupture Disc

Relief

AOA

HOA

AirOperator

Explosive Operator

Hydraulic Operator

Manual Operator

FCV Plow Control

OTV 0ate

OLV Olobe

SKV

TCV

MOA Motor Operator

NOA Nitrogen Operator

SEA Self-Actuated

CODE

VALVEPOSITIONS

DESCRIFIION CODB

0 Open

C Closed

TEST DIREC11ON

DEFINITION

AI

hhotticd - Dctcnnincd by System Parameters, i.c.,Check ValveAs is

DI

PE

U

PI

RT

BD

AO

DEFINITION

Disassembly and Inspection

Bxphwive Valve pcr IWV-3610

Full Stroke Exercise pcr IWV-3412 or 3522

Partial Stroke Exercise

Fail Safe pcr IWV-341$

Leak Test pcr IOCFR50 App ILeak Test pcr Section XI (Prcssure isoLtioa Only)

Remote Position Indication Test pcr IWV-3300

Valve Sct Pressure Test pcr OM-I

Rupture Disc Replacement pcr OM-I

Stroke Time per IWV-3413

Visual Exanunation pcr OM-I

As Found Tightness Leakage Test pcr OM.I

VcnTication of Bahnce Dcviccs pcr OM-I

AuxiliaryActuating Dcviccs pcr OM-I

Pl

p4

DEFINITION

Rcfwhng

Evcty Rcfwiing and When Conditions Spccificd in Relief Request E

Every Other Rcfwling Outage

50% Each Rcfuchng Outage pcr FSAR 5.2.2.10 and MSS Note 3b

Every 10 Years pcr OM-I

Every 5 Years Replacement pcr OM-I

25% Evcty 2 Years, But No Valve WillExceed Onco Every 5 Yca pcrOM-I50% Bach Rcfwling Outage pcr T.S. 4.13.d. I

I Squib Each Rcfwling Outage pcr T.S. 4.633.b

Every 2 Years

NMP2-IST-001, Rev. 4 Section III- October 1993 Page 10 of 10

REPORT . 10/22/93

SYSTEM: BREATHING AIR

FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2 NMP2-IST-001

Rev. 4

VALVE NO.

AS P&IDME &CL COOR

VALVECAT.

SIZE(IN) & ACTUTYPE TYPE

POSITION

NRM SAF FAL

IST PROG.PLNASME XI RELIEF REQ COMMITMENT

TEST/FREQ/DIR C.S.JUST. TEST/FREQ/DIRREMARKS

2AAS*HCV134 2 20ED-3

2.00GLV

LC LCLJ-RPI-T GVRR-1

LJ-RPI-T

2AAS*HCV135 2 20EC-7

F 00GLV


LJ-RPI-T

2AAS*HCV136 2 20ED-3

2.00GLV


LJ-RPI-T

2AAS*HCV137 2 20EE-7

2.00GLV


LJ-RPI-T

III — AAS — 1

REPORT .,10/22/93 FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2

SYSTEM: REACTOR BLDG. CLOSED LOOP COOLING WATERNMP2-IST-001Rev. 4

VALVE NO.

ASMECL

P&ID SIZE& VALVE (IN) &

COOR CAT. TYPE

POSITIONACTUTYPE NRM SAF FAL


TEST/FREQ/DIR C.S.JUST. TEST/FREQ/DIRREMARKS

2CCP*AOV37A 13EJ-2

1.50GTV

AOA 0 C CFE-QST-Q(C)FS-QPI-T

FE-QST-Q(C)FS-QPI-T

2CCP*AOV37B 13ED-8

2.00GTV

AOA 0 C CFE-QST-Q (C)FS-QPI-T

FE-QST-Q(C)FS-QPI-T

2CCP*AOV38A 13EJ-4

l. 50GTV

AOA 0 C CFE-QST-Q(C)FS-QPI-T

FE-QST-Q(C)FS-QPI-T

2CCP*AOV38B 13ED-10

2.00GTV

AOA 0 C CFE-QST-Q (C)FS-QPI-T

FE-QST-Q(C)FS-QPI-T

2CCP*MOV122 13CJ-6

8.00GTV

MOA 0 C AIFE-QST-Q(C)PI-TLJ-R

GVRR-1CCP-CS-2

FE-CSST-CS(C)PI-TLJ-R

III — CCP — 1

REPORT D . 10/22/93 FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2


VALVE NO.

ASMECL

P&ID SIZE& VALVE (IN) &

COOR CAT. TYPE


ASME XI RELIEF REQTEST/FREQ/DIR C.S.JUST.

IST PROG.PLNCOMMITMENT

TEST/FREQ/DIRREMAINS

2CCP*MOV124 13CI-6

8.00GTV


GVRR-1CCP-CS-2


2CCP*MOV14A 13EG-7

12.00GTV

MOA OC C AIFE-QST-Q(C)PI-T

FE-QST-Q(C)PI-T

2CCP*MOV14B 13EH-10

12.00GTV

MOA OC C AIFE-QST-Q (C)PI-T

FE-QST-Q(C)PI-T

2CCP*MOV15A 13DK-6

4.00GTV


GVRR-1CCP-CS-1


2CCP*MOV15B 13AI-7

F 00GTV


GVRR-1CCP-CS-1


III — CCP — 2

REPORT : 10/22/93 FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2


VALVE NO.

AS P&IDME & VALVECL COOR CAT.

SIZE(IN) &TYPE


ASME XI RELIEF REQTEST/FREQ/DIR C.S.JUST.


TEST/FREQ/DIRREMARKS

2CCP*MOV16A 13DK-7

F 00GTV


GVRR-1CCP-CS-1


2CCP*MOV16B 13AG-7

F 00GTV


GVRR-1CCP-CS-1


2CCP*MOV17A 13DC-7

4. 00GTV


GVRR-1CCP-CS-1


2CCP*MOV17B 13BE-7

F 00GTV


GVRR-1CCP-CS-1


2CCP*MOV18A 13EG-5

12 ~ 00GTV


FE-QST-Q(C)PI-T

III — CCP — 3

REPORT 10/22/93 FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2


VALVE NO.

AS P&IDME & VALVECL COOR CAT.


POSITION

NRM SAF FALASME XI RELIEF REQ

TEST/FREQ/DIR C.S.JUST.


TEST/FREQ/DIRREMARKS

2CCP*MOV18B 13EI-8

12.00GTV


FE-QST-Q(C)PI-T

2CCP*MOV265 13CB-6

8.00GTV

MOA 0 C AIFE-QST-Q(C)PI-TLZ-R

GVRR-1CCP-CS-2

FE-CSST-CS(C)PI-TLZ-R

2CCP*MOV273 13CC-6

8.00GTV


GVRR-1CCP-CS-2


2CCP*MOV94A 13DC-7

4.00GTV


GVRR-1CCP-CS-1


2CCP*MOV94B 13BE-8

4.00GTV


GVRR-1CCP-CS-1


III — CCP — 4

REPORT . 10/22/93 FIRST TEN Y TERVAL — VALVESNINE MILE POINT NUCLEAR POWER STATION — UNIT 2


VALVE NO.

AS P&IDME &CL COOR

VALVECAT.


POSITION

NRM SAF FAL


TEST/FREQ/DIR C.S.JUST. TEST/FREQ/DIRRE2GQKS

2CCP*RV170 2 13BF~7

AC 0.75REV

C 0 AIRT-P2VT-P2LA-P2LJ-R

GVRR-1RT-P2VT-P2LA-P2LJ-R

2CCP*RV171 2 13AH-6

AC 0.75REV

C 0 AIRT-P2VT-P2LA-P2LJ-RBD-P2

GVRR-1RT-P2VT-P2LA-P2LJ-RBD-P2

2CCP*RV64A 3 13EH-5

2.00REV

C 0 AIRT-P2VT-P2LA-P2

RT-P2VT-P2LA-P2

2CCP*RV64B 3 13EI-9

2.00REV

C 0 AIRT-P2VT-P2LA-P2

RT-P2VT-P2LA-P2

III — CCP — 5

COLD SHVIDOWNTEST JUSTIFICATION CCP-CS-1

System

Valve(s)

Reactor Building Closed Loop Cooling Water

2CCP*MOV15A,B2CCP*MOV16A,B2CCP*MOV17A,B2CCP~MOV94A,B

Category A (2CCP*MOV15A, 15B, 16A, 16B, 17A, 17B, 94A,94B)

Class 2 (2CCP~MOV15A, 15B, 16A, 16B, 17A, 17B, 94A,94B)

Function Inlet and outlet primary containment isolation valves torecirculation pump coolers and CCP return line blockvalves,

Quarterly TestRequirements

~

~

Cold Shutdown TestJustification

Exercise and stroke time.

Testing during operation would cause a loss of CCP flowto the recirculation pump seal coolers, motor bearingcoolers, and motor winding coolers. The failure of anyone of these valves to reopen after stroking would result ina complete loss of cooling to the associated recirculationpump, which could cause extensive damage to the pump.Furthermore, loss of cooling requires a plant shutdown.

Quarterly PartialStroke Testing The operating circuitry of these valves only permits full

stroke operation.

Cold ShutdownTesting Exercise and stroke time.

NMP2-IST-001, Rev. 4 III-CCP-6 of 7

COLD SHVI'DOWNTEST JUSTIFICATION CCP-CS-2"<ff

System

Valve(s)

Reactor Building Closed Loop Cooling Water

2CCP~MOV1222CCP*MOV1242CCP*MOV2652CCP*MOV273

Category

Class

Function CCP supply and return line primary containment isolationvalves to drywell unit coolers

Quarterly TestRequirements Exercise and stroke time

Cold Shutdown Test~ ~

Justification The drywell coolers are required, during normal plantoperation, to maintain the average drywell temperaturebelow 150'F. Cycling of these valves will interruptcooling water flow to the drywell coolers. The failure ofany one of these valves to reopen after testing would resultin a complete loss of cooling water to the drywell coolers.This loss would lead to a high drywell temperaturecondition and required plant shutdown. Furthermore, theloss of drywell cooling could result in equipment damageand/or a high drywell pressure and subsequent reactor trip.

Quarterly PartialStroke Testing The operating circuitry of these valves only permits full

stroke operation.

Cold ShutdownTesting Exercise and stroke time

NMP2-IST-001, Rev. 4 III-CCP-7 of 7

Documents

Forwards 'Niagara Mohawk Power Corp,Nine Mile Point ...NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 November 8, 1993 NMP2L 1453