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ATTAGED IS A PART 21 EPORT FROM IE t%IL UNIT - ROOM 359 E/W,
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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
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.: DATA SHEET '. .. . . . . . . ~ . . . . .. :. .: ~~ ^ * . - . . . -... . .. -.;"r :- 10 CFR -PART 21 REPORT ' J DENTIFICATION AND,. - .
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RECORDING OF IE , ACTIONS -.. .. .
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I |IE ACTIONS - CHECK OR PROVIDE DAhA AS APPROPRIATE ~ i '!*
!15T OTHEF. NRC OTMCIS !.NTOP m- !
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.~~' 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
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DATE Or TDiAL REVIE1|r & D157%I3UTION:"
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' * **GADDITIONAL CONO'.INTS:,,
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. 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
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f~% .,,,? ' . ? < # ,* i '
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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-
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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-
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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
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