ML19320B835

Part 21 Rept,Supplementing Info Previously Filed Under 10CFR50.55(e),re Gould-Brown Boveri solid-state Trip Devices.Rept Should Have Been Included in Review of Deficiencies Filed Since 1977

ML19320B835
Person / Time
Site:	Grand Gulf
Issue date:	07/02/1980
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:
References
REF-PT21-80-245-000 AECM-80-147, NUDOCS 8007150099
Download: ML19320B835 (4)

Text

,

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:

FUEL CYCE & SAFEGlMRDS (S)

REACTOR (R){

IEFILES IEN U 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

,--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,p-m c. .

= o ,

go ^ or=2 o^c^*22=x(5) .

g . P x c.

.< . l y-ct@w cnT2AI.kUs.rE/l.O_ OFEEPORTcb W-N O-

, Wh **

• U.M $.M ti- M %d Od 4 tf

, DNTE OF ENITIA2. NOTIncAT20N DAYE(5) Or PART 21 REFORT(5). (5 DAY & SUPPLEMEN(,  !

us nova zzrorr) 7/A/Fc1 r

'%t/cdir i i i !l t . ,

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

(

, i

• \

t RESPONSI2LE IE 01GANIEAT10N(5)

{  ;

LEAD = 1 SUPPORTTVE = 2 - FF& MSI _

SI RCI ROI _

I l IE ACTIONS - CHECK OR PROVIDE DAhA AS APPROPRIATE

~

i '

!15T OTHEF. NRC OTMCIS !.NTOP m

.~~

DISCI *SSED 1;"TH Ds':TIATOR1 ' vec I en we I i s:n REFORT 15 REQUIRED DATE:  ;

, UNDER FART 217 * '

j EIQL*IST MADE TOR ADDITIONAL DsTO7 IN QUIRY7 DA""I ,E EGTD:

FRE55 RELIASE(5) INSPECTION 7 l

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

TF.ANSTEFED TO O.au NRC OFTICE7 l l l ENTORCEMENT7 l l BUI.LETLV155UED7 NO. CORRECTIVE ACTION TAKE30 f f DATE OF C145EOUT: -

CRCULAR ISSUID7 NO.

~

CLOSCOUT METHOD: .

II AI?OET NUMEEP.5:

DATE Or TDiAL REVIE1lr & D157%I3UTION:

(XOOS) -

ADDITIONAL CONO'.INTS: ' * **G f

e 4 .

b.. . .

w egeg ,

. # . O U - .

- 7/1/78 4 * ,

. g g

'~

• e t . . _

p MISSISSIPPI POWER & LIGHT COMPANY Helping 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(ment U. S. Nuclear Regulatory Commission Region II ,yy{,OOO 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 Attention: h'r. J. P. O'Reilly, Director

SUBJECT:

Grand Gulf Nucicar Station File 0260/15525/15526 Supplemental Reports under 10CFR21 for Previously Filed Items under 10CFR50.55(e)

PRD-79/08, PRD-79/18 & PRD-79/19

/GCM-80/147 As requested, Mississippi Power & Light Company has reviewed past reports filed under 10CFR50.55(e) since August 1977 to determine if in-formation required under 10CFR21 should also have been included. We have

, determined that three reports filed under our Architect / Engineer's (Bechtel Power Corporation) scope of work fall in this category. These items involve parts supplied by Rosemount, Inc. , Could-Brown Boveri, and Westinghouse Electric Company. Supplemental reports to the ones previously filed under 30CFR50.55(e) for these are attached.

Sincerely, g; # J. P. McGaughy, Jr.

Assistant Vice President, i Nuclear Production WDH:lb Attachment cc: Mr. N. L. Stampley )

Mr. R. B. McGehee l Mr. T. B. Conner Mr. Victor Stello, Director, w/3 Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1

Member Middle South Utilities System

f 39 63 LUE w LLwuf

• 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 13 11ait 2 Other C (Specify)

3. Supplier: Gould-Brown Boveri Switchgear Division Ft. Washington, Pa.

4 Nature of the defect or failure to comply and the safety hazard wi.ich is created or could be created by such 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 Note Susquehanna Nuclear Station ,

See Note Note: MP&L has been unable to determine how many of these solid-state trip devices 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 '

, .< r 7,- sT '

(! gh _

L MISSISSIPPI POWER & ' LIGHT COMPANY dM lh ' h . Helping Guild Mis sis sippi M P. O. B O X 16 4 0. J A C K S O N. MIS SIS SIP PIJ ' 9205 P AODUCT EON O E f A R T he C si T November 2, 1979 Office of. Inspection and Enforcement U. S. . Nuclear. Regulatory Commission Region 11 101 Marietta.Stre - Suite 3100 Atlanta,. Georgia 20303 4

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

SUBJECT:

Grand Gulf Nuclear Station File 0260/0498/15525 dnits 1 and 2 Docket Nor.. 50-416/417 Final Report for Potential Reportable Deficiency 79/0S as Defined in 10 GFR 50.55(c)

AECM-79/121 On March 23, 1979, Mississippi Power & Light Company notified Mr. 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 voltage power circuit breaker". The deficiency was determincd to be the result of an operator error during the assembly or printed circuit boards by our supplier, Gould-Brown'Boveri Switchgcar Division. ,

TJe have determined that this matter is a reportable deficiency which 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. Gibbs Mr. R. B. McGehee Mr. A. Zaccaria

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

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

' Division'ofLinspection & Enforcement Mr. W. L. Nail Mr. J. P. McGaughy U.__S. Nuclear' Regulatory Commission Washington, D. C. 2 55 Mr. T. E. Rea9ddilS COPY f t:R

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

- Member Middle South.Utilitics Sh[Sm -

...-......._..:.... .... . . . . m-a

e F .

. ,w - --.

.* . , ( s. .

FlHAl REPORT FOR5 REl'ORTAlu.E DEF1CIENCY NO." 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.

W 1-7(41~b-'\'3 0

.y psm-c.u.m.m ~

.w-~~..emn w w w 2.w.e lm.sa.ns

- 3

. o 3

, , 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------- r...= =: .;.,2 - .m - 7 . .

.mm-- p :.. ~ 2.m ' 2.i. m a ?.nt. : c --