7
ATTAGED IS A PART 21 EPORT FROM IE t%IL UNIT - ROOM 359 E/W , , n.;4; n~ , PART 21 IDENTIFICATION NO.- Fo - Mr-oco C0FPAW IMFE.4 Ch o c DATE OF ETTER. %/Fo DOCKET t0. 9o - Y/ 6 J'o - F 7 DATE DISTRIBUTED 7/ ro/ r d ORIGIIRL REPORT [ SUPPlDENTARY DISTRIBUTION: REACTOR (R){ FUEL CYCE & SAFEGlMRDS (S) IEN U IEFILES IE FILES AD/ROI(2) IEFILES AD/SG AD/RCI(2) AD/FFFEI AD/ROI EGIONSI,II,III,IV,V EGIONS I,II,Ill,IV,V EGIONS 1,II,Ill,lV,V VENDOR BR. R-IV VENDOR BR R-IV VENDOR BR. R-IV . L0EB / IPA FTB 5715 tE S / FCFS SS-396 NRR/ DOL AEOD FIG 7602 LDEB/MPA FTB 5715 ItES / SG SS-881 NRR/ DOE AEOD FIG 7602 L0EB/FFA F16 5715 NRR/DSI CENTPALFILES 016 AEOD FIG 7602 NRR/ DST CENTPAL FILES ( GRON) CENTPAL FIES 016 NRR/ DOL PDR CBITPAL FIES (GRW) CENTRALFILES 016 LPDR CENTPAL FILES SS-396 CENTRAL FIES (GR0fD TERA PDR PDR - LPDR . LPDR TEPA - miliefh. ACTION: PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOWJP AS SFOWN BELOW: IE 1 NRR itBS OTliER @ ROI SG FFMSI TlHS DOCUMENT CONTAINS POUR QUAUTY PAGES 8007150o33 EV: 7/9/80

ATTAGED IS A PART 21 EPORT FROM IE t%IL UNIT ...ATTAGED IS A PART 21 EPORT FROM IE t%IL UNIT - ROOM 359 E/W, n.;4; n~,, PART 21 IDENTIFICATION NO.-Fo - Mr-oco C0FPAW IMFE.4 Ch o c

  • Upload
    others

  • View
    0

  • Download
    0

Embed Size (px)

Citation preview

  • ATTAGED IS A PART 21 EPORT FROM IE t%IL UNIT - ROOM 359 E/W,

    ,

    n.;4; n~,PART 21 IDENTIFICATION NO.- Fo - Mr-oco C0FPAW IMFE.4 Ch o cDATE OF ETTER. %/Fo DOCKET t0. 9o - Y/ 6 J'o - F 7DATE DISTRIBUTED 7/ ro/ r d ORIGIIRL REPORT[ SUPPlDENTARYDISTRIBUTION:

    REACTOR (R){ FUEL CYCE & SAFEGlMRDS (S)IEN UIEFILES IE FILES

    AD/ROI(2) IEFILES AD/SG

    AD/RCI(2) AD/FFFEI AD/ROI

    EGIONSI,II,III,IV,V EGIONS I,II,Ill,IV,V EGIONS 1,II,Ill,lV,V

    VENDOR BR. R-IV VENDOR BR R-IV VENDOR BR. R-IV.

    L0EB / IPA FTB 5715 tE S / FCFS SS-396 NRR/ DOL

    AEOD FIG 7602 LDEB/MPA FTB 5715 ItES / SG SS-881

    NRR/ DOE AEOD FIG 7602 L0EB/FFA F16 5715

    NRR/DSI CENTPALFILES 016 AEOD FIG 7602

    NRR/ DST CENTPAL FILES ( GRON) CENTPAL FIES 016

    NRR/ DOL PDR CBITPAL FIES (GRW)

    CENTRALFILES 016 LPDR CENTPAL FILES SS-396

    CENTRAL FIES (GR0fD TERA PDR

    PDR - LPDR.

    LPDR TEPA-

    miliefh.

    ACTION:

    PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR

    FOLLOWJP AS SFOWN BELOW:

    IE 1 NRR itBS OTliER .@

    ROISGFFMSI

    TlHS DOCUMENT CONTAINS

    POUR QUAUTY PAGES

    8007150o33 EV: 7/9/80

  • * ' ,, .,_ , . . _ ,--m,

    .: DATA SHEET '. .. . . . . . . ~ . . . . .. :. .: ~~ ^ * . - . . . -... . .. -.;"r :- 10 CFR -PART 21 REPORT ' J DENTIFICATION AND,. - .

    ..,- '

    RECORDING OF IE , ACTIONS -.. .. .

    ,

    FA27 21 IDENTIncAT70N NO. ,. g p * AIT8 *, *NAxr45) Or uCuas) vnDos(n ,-+hA~P- 4 m c. .

    -

    ,= go ^ or=2 o^c^*22=x(5)o g . P x c. ,p- ;.< . l.

    .

    y-

    OFEEPORT W-N Wh ** *cnT2AI.kUs.rE/ct@w l.O_ ti- M %d cb O-:, Od U.M $.M4 tf, DNTE OF ENITIA2. NOTIncAT20N DAYE(5) Or PART 21 REFORT(5). (5 DAY & SUPPLEMEN(, !us nova zzrorr) 7/A/Fc1 '%t/cdir !|i i ir

    t . ,

    TACI277(IES) DWOLVED: 80 " ' Y/(p YO - Y/ 7 - !j(

    -i,

    \*

    t

    !RESPONSI2LE IE 01GANIEAT10N(5)

    { ;LEAD = 1 SUPPORTTVE = 2 - FF& MSI SI RCI ROI_

    _

    .

    I |IE ACTIONS - CHECK OR PROVIDE DAhA AS APPROPRIATE ~ i '!*

    !15T OTHEF. NRC OTMCIS !.NTOP m- !

    ,

    .~~' vec I we IenDISCI *SSED 1;"TH Ds':TIATOR1 s:n iREFORT 15 REQUIRED

    DATE: ;, UNDER FART 217 * j '.

    EIQL*IST MADE TOR ADDITIONAL DsTO7 IN QUIRY7DA""I ,E EGTD:

    .

    FRE55 RELIASE(5).

    , INSPECTION 7 |

    F.E% as W TOR POTENT 1AI. Af O' (MC 2120) f INVESTIGATION 7DATE: ,

    TF.ANSTEFED TO O.au NRC OFTICE7 | | | ENTORCEMENT7 | |.*

    BUI.LETLV155UED7 NO. CORRECTIVE ACTION TAKE30 f fDATE OF C145EOUT: - CRCULAR ISSUID7

    NO.

    CLOSCOUT METHOD:~

    .

    ..

    II AI?OET NUMEEP.5:.

    DATE Or TDiAL REVIE1|r & D157%I3UTION:"

    (XOOS) - . *..

    ' * **GADDITIONAL CONO'.INTS:,,

    _.

    .

    f

    . e

    4 .

    b.. . . wegeg

    ,. # . O U - .

    - 7/1/78. .

    *.

    . ._.

    4 * ,. g

    . *g

    * e-

    '~

    ,. .-. . _t .

  • ,. ..

    . p* - MISSISSIPPI POWER & LIGHT COMPANYHelping Build Mississippi

    P. O. B O X 16 4 0, J A C K S O N. MISSISSIPPI 39205" " " " " " "

    NUCLEAR PRODUCTION DEPARTMENT July 2, 1980

    Office of Inspection & Enforc(mentU. S. Nuclear Regulatory Commission ,yy{,OOORegion II101 Marietta Street, NWSuite 3100Atlanta, Georgia 30303

    Attention: h'r. J. P. O'Reilly, Director

    Dear Mr. O'Reilly:SUBJECT: Grand Gulf Nucicar Station

    File 0260/15525/15526Supplemental Reports under10CFR21 for Previously FiledItems under 10CFR50.55(e)PRD-79/08, PRD-79/18 & PRD-79/19/GCM-80/147

    As requested, Mississippi Power & Light Company has reviewed pastreports filed under 10CFR50.55(e) since August 1977 to determine if in-formation required under 10CFR21 should also have been included. We havedetermined that three reports filed under our Architect / Engineer's (Bechtel,Power Corporation) scope of work fall in this category. These items involveparts supplied by Rosemount, Inc. , Could-Brown Boveri, and Westinghouse ElectricCompany. Supplemental reports to the ones previously filed under 30CFR50.55(e)for these are attached.

    .

    Sincerely,

    .

    g; # J. P. McGaughy, Jr.Assistant Vice President, iNuclear Production

    WDH:lbAttachment

    cc: Mr. N. L. Stampley )Mr. R. B. McGehee |Mr. T. B. Conner

    Mr. Victor Stello, Director, w/3Division of Inspection & EnforcementU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

    1

    Member Middle South Utilities System-

    _

  • 39 63 LUE w LLwuf f.

    * 1. Identifir tion af individual (s) infermi;g th3 NRC:.

    "Name(c): T. E. Reavu , Jr.

    Telephone call to F. Cantrell, NRC, Region II 7/2/80.

    Address: Mississippi Power & Light Company P. o. Box 1640, Jackson, MS 39205

    2. Identification of entity f ailing to comply or containing a defect (check appropriate blocks):

    CRAND CULT NUCLEAR STATION

    Unit 1311ait 2

    Other C(Specify)

    3. Supplier: Gould-Brown BoveriSwitchgear DivisionFt. Washington, Pa.

    4 Nature of the defect or failure to comply and the safety hazard wi.ich is created or could be created bysuch defect or failure to comply:

    Saa pn en yn ntw T nnd TT n e t-n rh,on t- em sm e.T in n- " tgr E C! 79/121,dated 11/2/79

    .

    .- .- ~ ..

    5. Date information obtained for this report: 7/2/80.

    6. Additional information-for defective components incorporated in other facilities, as applicable:

    Number in use, supplied for.

    Facilitv/Loestion or being supplied.

    San Onofre Nuclear Station See NoteSusquehanna Nuclear Station See Note

    ,

    Note: MP&L has been unable to determine how many of these solid-state tripdevices are incorporated in the above listed Nuclear Power Stations.

    7. Corrective Action:See Paragraph II, attachment to AECM-79/121, dated 11/2/79

    Responsibility: Mississipoi Power 5,1.it5t Quality Assurance Section.

    (Name of individual or organization) -

    Time Required To Complete Acticn: 3/22/79 to 3/14/80

    8. Advice related to the defect or f ailure to coe.oly about the facility, activity, or basic compocent: that has been, is being, or will be given to purchasers or licensees:

    N/A

    --- ._ s__

  • f~% .,,,? ' . ? < # ,* i '

    ..

    _ '

    sT7,-

    gh, .< r '

    L MISSISSIPPI POWER & ' LIGHT COMPANY(! |h '_

    h . Helping Guild Mis sis sippi'. dM M P. O. B O X 16 4 0. J A C K S O N. MIS SIS SIP PI ' 9205J

    P AODUCT EON O E f A R T he C si T November 2, 1979

    Office of. Inspection and EnforcementU. S. . Nuclear. Regulatory CommissionRegion 11101 Marietta.Stre - Suite 3100Atlanta,. Georgia 20303

    4

    -Attention: Mr. J. P. O'Reilly, Director

    '

    Gentlemen:

    SUBJECT: Grand Gulf Nuclear StationFile 0260/0498/15525dnits 1 and 2Docket Nor.. 50-416/417Final Report for Potential

    Reportable Deficiency 79/0S asDefined in 10 GFR 50.55(c)

    AECM-79/121

    On March 23, 1979, Mississippi Power & Light Company notifiedMr. J. K. Rausch of your offfice of a potential reportable deficiency at'the Grand Gulf Nuc1 car Station construction site concerning the failure*of several " solid-state trip devices". which are part of the " low voltagepower circuit breaker". The deficiency was determincd to be the result-of an operator error during the assembly or printed circuit boards by oursupplier, Gould-Brown'Boveri Switchgcar Division. ,

    TJe have determined that this matter is a reportable deficiencywhich satisfics the criteria of 10 CFR 50.55(c). Details of our findings.are described in the attached final report.

    .

    Yours truly,

    "n.L.' F. Dale ,Nuclear Project Manager

    JRF/JDR:pa~ At tactuaent

    cci Mr. N. L. Stampley bec: Dr. D. C. GibbsMr. R. B. McGehee Mr. A. Zaccaria

    'Mr. T. B. Conner Mr. J. N. WardMr. D. M. Lake

    ' Mr. Vit:: tor Ste'llo, Jr. , Director Mr. R. L. Scott,

    ' Division'ofLinspection & Enforcement Mr. W. L. Nail'

    U.__S. Nuclear' Regulatory Commission Mr. J. P. McGaughyWashington, D. C. 2 55 Mr. T. E. Rea9ddilS COPY f t:R. . . .

    } ,@ 7hM 3 59 6. ""j.'c."|fL"

    .

    : - Member Middle South.Utilitics Sh[Sm -...-......._..:.... .... . . . . m-

    a

  • e F .- --.. ,w

    .* . , ( s. . .* -. '

    FlHAl REPORT FOR5 REl'ORTAlu.E DEF1CIENCYNO." 79/08 AS DEFINEI) 1N 10 CFR' 50.55(e)

    *

    1. Description of Deficiency:

    . Solid-state. trip devices on the 480 Volt Load Centers failed to

    .' operate properly during a system' functional test. The 480 Volt

    Load Centers were manufactured and supplied by Gould-Bro.m Boveri,.

    Switchgear Division for Units 1 6 2. Investigation revealed that

    .' the problem in the solid-state trip devices was due to inadequate

    or incomplete soldering on printed circuit board leads.

    .Il. Safety Implications:

    The 480 Volt Load Centers control the electrical functions of various.

    systems determined to be safety related. llence , failure of an intri-

    cate component in a safety related system to function properly during

    .

    an unplanned event or p'rior -to a planned event could adversely affect..-

    the safety of operations of the nuclear power plant.

    111.-. Corrective Action Taken.

    .

    The supplier investigation has deterrined that the cause of the

    problem was due to an operator error during the asseir.bly of printed*

    *'

    circuit boards.

    The extent of the problem was further determined, fron manufacturing

    -records, to be limited to a three-day period during t:hich a soldering

    operation was inadvertently omitted. Thc operator was replaced for

    other reasons. 'All 460-Volt load Centers received at the Grand Gulf

    Nucicar Station for Units 1 and 2 have been examined for the problem.

    .

    W7(41~b-'\'3 01-

    *

    |m.sa.n ;.y psm-c.u.m.m ~:.w-~~..emn w w w 2.w.es:- 3

  • --

    _,,

    o. 3-2-* ,,

    t

    A total of 12 trip units were found with poor so]dering joints on

    the circuit boards. These trip units except for one that was re-

    turned to the supplier in the "as-found" condition, were reworked

    to correct the soldering on the printed circuit board joints and

    the retests of the units were satisf actory.

    The supplier has initiated corrective action to establish an auto-

    matic soldering operation to replace the manual soldering operation.

    This has been accomplished to the extent possible. Ilowever, not

    all models can be processed in this manner. llence , the supplier has

    committed to inspect all soldering leads. This inspection will also

    be required on those items processed by the automatic soldering pro-

    cess. The supplicr's investigation also included an examination of

    un-delivered units for this soldering problem in which none were

    found. The source of the problem was found to exist only on'those.

    units assembled during a three day period. Details of this corrective

    action are summarized in Bechtel llanagement Corrective Action 1cport,.

    ,GCNS-48 and will be available for your review at the CGSS construction

    site..

    u

    N

    if .;.,2 - .m - 7 . .mm-- p :.. ~ 2.m ' 2.i. m a ?.nt. : c --*' .2------- r...= =:- .. .- .