, . , - 4_. ,/ -'7'

L Jt!N 8 1987

~ MEMORANDUM FOR: . Charles E. Rossi, DirectorDivision' of Operational Events Assessment

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FROM: Wayne Lanning, Acting ChiefEvents Assessment Branch-Division of Operational Events Assessment ,{

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SUBJECT: - THE OPERATING REACTORS EVENTS MEETING -)APRIL'6, 1987 - MEETING 87-10g -i

~ lOn| April 6,1987, an Operating Reactors Events meeting (87-10) was ' held to

]brief senior managers. from NRR, RES, AE00 and Regional Offices.on ev0ntswhich occurred since our last meeting on March 30,: 1987. - The list of. attendees .is included as Enclosure 1.

-The events 'iscussed-and the significant elements of these" events are presented )din Enclosure 2. Enclosure 3 provides a summary of reactor scrams and j

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t-. "significant events" that will be input to NRC's performance indicator program.

Original Signed by+ . Wayne D, Lanning

Wayne Lanning, Acting Chief'

.eEvents Ass'essment Branch.

'

Division of Operational Events Assessment *

. Enclosures:'

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As stated50 2G3- 50 ~20 l ,

cc w/ Encl :See Next Page 5@~26 N , ~} -

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50-26DISTRIBUTION ~

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Charles E. Rossi -2-

cc: T. Murley- H. Pastis '

J. Sniezek .B. YoungbloodR. Starostecki S. McNeil-J. Taylor R. CapraE. Jordan G. KalmanE.'Beckjord' G. KnightonW. Russell, Reg..I-

.

-J. Nelson Grace. Reg. II i

B. Davis, Reg. IIIR. D. Martin, Reg. IVJ. B. Martin, Reg. VW. Kane, Reg. I-L. Reyes, Reg. II 1

C. Norelius, Reg. IIIE. Johnson, Reg. IV-D. Kirsch, Reg. V-S; Varga-

' D. Crutchfield -B. BogerG. LainasG. HolahanF.:Schroeder-L. ShaoJ. Partlow -

B. Grimes.F. CongelH. MillerE. WeissS. BlackT. Martin,-EDOF. MiragliaE. MerschoffR. Hernan

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?. ENCLOSilRE 1

-LIST OF ATTENDEES'

OPERATING REACTORS EVENTS BRIEFING (87-10)

APRIL 6, 1987

o

NAME . DIVISION NAME DIVISION

J. Sniezek NRR G.'Holahan' .NRR

R. Smith- DEPER H. Pastis NRR

M. Chiramal. AE00- W. Lanning AEOD

K.-Eccleston TOSB J. Clifford 'NRR

|- S. Black- NRR V. Benaroya NRR

G. Murphy ORNL 5. McNeil' NRR

G. Klingler IE- W. Haass- ~IE

' G. Kalman NRR M. Virgilio NRR

- J. Rosenthal' IE. A. Thadani NRR

T..Novak NRR F. Miraglia NRR |T. Gwynn OCM. F. Schroeder NRR

R. Bernero- 'NRR W.'Swenson NRR

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ENCLOSURE 2.

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0PERATIflG PEACTOR EVENTS BRIEFIMG 87-10

APRIL 6,1987

OCONEE:1, 2,.3 FOULING.0F LOW. PRESSURE SERVICE WATER,

LOW PRESSURE INJECTION, AND.,

REACTOR BUILDING COOLING UNITS

CALVERT CLIFFS 1 UNIT SHUTDOWN DUE T0 ENVIRONMENTAL

QUALIFICATION PROBLEMS

OTHER FVENT'0F INTEREST

RANCHO SEC0' POWER CHANNEL DESIGN DOES NOT MEET

SEPARATION CRITERIA

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APPIL 6, 1987-

OCOMEE 1, 2 AND 3 - FOULING OF LOW PRESSURE,SEPVICE WATER, LOW PPFSSllPF INJECTION AND

REACTOR BUILDING COOLING UNITSMAPCP 3), 1987 - (H, PASTIS, NRR)

PROBLEM: FOULING OF THE LOW PRESSURE INJECTION (LPI) AND REACTOR ,

BillLDING COOLING UNIT (RPCU) HEAT EXCHANGER LIMITSOPERATING POWEP

CAUSE: LAKE SEDIMENT :

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SIGNIFICANCE:

EQUIPMENT INCAPABLE OF PERFORMING DESIGNED SAFETY FUNCT10tl*

DISCUSSION:

UNIT 3 WAS STARTING UP FROM ITS REFUELING OUTAGE AND TESTING*

THE REACTOR BUILDING COOLING UNITS AT NORMAL OPERATING CONDITIONS

THE LOW PRESSURE SERVICE WATER TAKES PAW LAKE WATER TO COOL THE*

LPI AND RBCU

LICENSEE ANALY7ED THE TEST DATA AFD CORRELATED IT TO*

EMERGENCY CONDITIONS j

THE ANALYSIS SHOWED THAT UNDEP LOCA CONDITIONS, THE COOLERS WOULD*

NOT PERFORM AT DESIGil RATINGUNIT 3 WAS BROUGHT TO COLD SHUTDOWN; Ut!1T 2 TO 60% POWER: ,

*

AND UNIT 1 TO 89% POWER

FOLLOW-UP:LICENSEE WILL CHEMICALLY CLEAN THE COOLERS FOR llNIT 3,*

HAS NOT YET DEVELOPED PLANS FOR OCONEE UNIT 2 AND 1 C00LEPS i

NRR ISSUED TEMPORARY WAIVER OF COMPLIANCE WHILE PROCESSING AN*

EMERGENCY AMENPMENT TO THE TECHNICAL SPECIFICATIONS

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APRIL 6, 1987-

CALVERT CLIFFS 3 - IINIT SHUTDOWN

DUE TO FNV!PONMENTAL OttALIFICATION PROBLEMSAPRIL 1, 1987 - (S. A MCNEIL, NRR)

PROBLEM: LICENSEE SHUTDOWN UNIT 1 TO INVESTIGATE ADEQUACY OF

ENVIRONMENTAL CUAllFICATION OF MOTOP OPERATED VALVES ANDS0LENDID OPERATED VALVES,

CAUSE: INCOMPLETE LICENSEE VEPIFICATION OF ENVIRONMENTAL QUAllFICATION

OF SAFETY-RELATED ELECTRICAL EQUIPMENT

SIGNIFICANCE: POTENTIAL FOR FAULTY ENVIRONMENTAL QUAllFTCAT10N'0F OTHER

SAFETY-RELATED ELECTRICAL COMPONENTS WHICH C0llLD Fall

WilEN REQUIRED FOR SPECIFIC DESIGN BASIS EVENTS

DISCUSSION:.MARCH 14, 1987 - UNIT 2 SHUTDOWN FOR REFUELING*

REGION I ENVIRONMENTAL QUALIFICATION INSPECTION TEAM IDENTIFIED THE*

USE OF TAPE IN ELECTRICAL SPLICES ON UNIT 2 THAT WAS NOTENVIRONMENTALLY QUALIFIEDTO BE ENVIRONMENTALLY QUALIFIED, THE METHOD OF TAPING, THE TYPE OF*

TAPE AND THE LOCATION MUST BE CONSIDEREDAPRIL 1, 1987 - LICENSEE SHUTDOWN UNIT 1 TO INVESTIGATE POTENTIAL*

ENVIRONMENTAL QUALIFICATION PROBLEMS !

APRIL 3,_1987 STATUS OF INSPECTION*

44 0F 83 SOLEN 0ID OPERATED VALVES INSPECTED, 12 VALVES HAVE-

TAPED SPLICES, UNQUAllFIED WIPING IN 5 VALVES13 0F 40 MOTOR OPERATED VALVES INSPECTED, Al.L SPLICES WERE-

ACCEPTABLE. ENVIRONMENTAL QUALIFICATION OF SillCON INSULATEDINSTPllMENTATION WIPING ON 5 MOTOR OPERATED VALVES WAF !DUESTIONABLE,

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CALVFRT-CLIFFS 1 (CON'T).

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FOLLOWilP ;

LICENSEE:

CONTINUE UNIT 1 ENVIPONMENTAL QUALIFICATION INSPECTION OF POTOP*

OPEPATED VALVES AND SOLENnID OPERATED VALVES

REPLACE TAPED SPLICES WITH RAYCHEM HEAT SHRINK TUBING*

INSPECT'480 VAC MOTOPS FOR' ENVIRONMENTAL QUALIFICATION*

DEVISE NEW CHECK LISTS AND INSPECT ALL PENETRATIONS AND*

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INSTRUMENTATION AND CONTROLS FOR ENVIRONMENTAL QUALIFICATION

CONTRACT AN INDEPENDENT ENVIRONMENTAL QUALIFICATION AUDIT j*

BRIEF REGION 1 AND NRR WHEN LICENSEE IS SATISFIED THAT UNIT 1 IS*

FULLY QUALIFIEDADDPESS STATUS 0F ENVIRONMENTAL QUALIFICATION FROM NOVEMBER 30, 1985*

4

TO PRESENT AND HOW THESE PROBLEMS AROSE

REGION 1:* DETERMINE IF LICENSEE HAS SATISFACTORILY OUALIFIED. UNIT 1 PRIOP

T0 PERMITTING RESTART*

CONDUCT FOLLOWUP INSPECTION LATER THIS YEAR

NRR: ASSIST REGION I WHERE NECESSARY

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APRll 6, 1987,.-

OTHER EVENT OF INTEREST

RANCHO SECO - POWER CHANNEL DESIGN

DOES NOT MEET SEPARATION CRITERIA'

april 6, 1987 - (GEORGE KALMAN, FPR)

.

PROBLEM: EACH SET OF TWO POWFP CHANNELS SUSCEPTIBLE TO-COMMON MODE FAllllRE

CAUSE: B8W DESIGN ERROR

SIGNIFICANCE:

SAFETY SYSTEM SEPARATT.0N COMPROMISED. POTENTIAL FOP SINGLE FAILURE*

TO DISABLE REACTOR TRTP

DISCUSSION:* FEBRUARY 214, 1987, B&W NOTIFIED LICENSEE OF POTENTIAL PROBLEM WITH

SEPARATION OF POWER CHANNELS'

*

RPS CHANNELS A&D FEED COMMON ICS POWER AVERAGER''

PPS CHANNELS C8D FEED COMMON ICS POWER AVERAGER*

FIX lNVOLVES USE OF ISOLATION AMPLIFIERS* B&W BELIEVES, BASED ON INHOUSE DESIGN DRAWINGS, PROBLEM IS UNIQUF-

TO RANCHO SECO*

10 CFR 21 REPORT NOT ISSUED BY B8W

EOLLOW-UP:*

daw LETTER TO OWNERS RECOMPENDING SITE SPECIFIC CHFCK*

LICENSEE INITIATED INP0 NOTIFICATION NETWORK"

LICENSEE TO ISSUE 10 CFR 21 NOTIFICATION!

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[- RfACTORSCRAWSUMMARY.'

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~ WEEK ENDING 04/05/B7, ,

!. PLANT SPECIFIC LATA

DATE' SITE' UN!i F0WER RFS CAUSE COMPLI- YTD YTD ' YTD,

' CAT 10NS- AB0VE BELOW TOTAL

'151 151

03/30/87 FRA!RIE ISLAND' 1 71 A P SONNEL: NO 1 0 1

03/31/57 BYRON- ' 2 17 A UNr'0dN ND 1 3 4

. 03/31/27 HARRIS:' ! 56 A EQUIP . N0 5 2 7E

-04/02/87 SUSQUEHANNA 1 -100 A EQUIP / ELECT NO. 1 0 1

04/02/87 CALLAWAY: 1 1A EQUIP / ELECT NO 0 1 1-

04/03/87 HARRIS 1 75 M FERSONNEL' NDL 6 -2 B

04/03/07 MONTICELLO 1 100 a EQUIP NO~ 3 0- 3,

' 04/04/87 INDIAN POINT 3 -!! A EQUIP NO '2 1 '3-.04/04/87 SURRY- 2 !! A UNKNOWN' NO 0 2 2,

E04/04/07.DIABLOCANYON. 2- 12 A . UNYN7aN ND 1 2 3

.04/04/07 POINT BEACH 1| ~.0 M PERSONNEL ND 0 1- 1

04/05/87 V0GTLE -1- 25 A ' - EQUIP /TURB!hE ND 1 ~6 7

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.I I . COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES+

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SCRAMS FOR WEEK ENDING-.

04/05/87

SCRAM CAUSE POWER NUMBER 1987 19G6 1985OF WEEKLY WEEKLY WEEKLY j

SCRAMS (5) AVERAGE AVERAGE AVERAGEYTD (3)(4) (8) (9)

** POWER >15%EDUIP. RELATED >15% 4 3.6 4.3 5.4PERS. RELATED(6) >15% 2 1.6' 1.8 2.0OTHER(7)' >15% 1 1.0 0.4 0.6** Subtotal **

7 6.2 6.5 8.0 ||

** POWER <15%EOUIP. RELATED <15% 2 1.1 1.4 1.3PERS. RELATED <15% 1 1.0 0.8 0.9

4OTHER <15% 2 0.4 0.2 0.2 1** Subtotal 4* {

5 2.5 2.4 2.4 !-4** Total ***

|12 8.7 8.9 10.4 i

MANUAL VS AUTO SCRAMSl

TYPE NUMBER 1987 1986 1985OF WEEKLY WEEKL.Y WEEKLY

SCRAMS AVERAGE AVERAGE AVERAGEYTD

MANUAL SCRAMS 2 1.3 1.0 1.0AUTOMATIC SCRAMS 10 7.4 7.9 9.4

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