ML20215A319

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Forwards 10CFR50.55(e) & Part 21 Rept Re Tdi Diesel Generator Jackwater Thermostatic Control Valve Fracture. Followup on Generic Aspects of Problem Requested
ML20215A319
Person / Time
Site: Grand Gulf, 05000000
Issue date: 06/27/1980
From: Murphy C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20215A161 List:
References
FOIA-86-656, REF-PT21-80 NUDOCS 8612110246
Download: ML20215A319 (3)
v • d • e


Text

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.p s UNITED STATES '

If . 3 , fr NUCLEAR REGULATORY COMMISSION

  • REGION 11 8

101 MARIETTA 37 N.W.,$UlfF 3100 -

ATLANTA, GEORCIA 30303 /

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4 MDIORANDUM FOR: Chief, Vendor Inspection Branch, Region IV /

! FROM:

Charles E. Murphy, Chief, Reactor Construction and.

Engineering Support Branch, Region II

SUBJECT:

CONSTRUCTION DEFICIENCY REPORT - CONFIRMATION OF TELECON (AITS NO. F02500158 ) .

Attached is a 10 CFR 50.55(e)/10 CFR 21 report received from Mississippi Power & Light .

' This . appears to be a generic problem. Would you please followup on the generic ar.pects of the problem with the AE/ Vendor, Should you have additional questions, we will be glad to discuss them with you.

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Charles E. Mthdy, f Reactor Construction and Engineering Support Branch cc: Princirtil Staff, RII RC&ES Branch Chiefs, RI III, IV, V G., Wayne Reinmuth, IE CONTACT: M. Hunt (242- 4184)

Is 209 PDR_

.s'I* i: .: - 1%.iu i! ,,Anle_2J,u1.9A0,__,,..... ,

ITEM FACILITY 1;OTI r iCATION ITFE OR EVDff' ' KEuiJNA1' ACTION'

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Crand Gulf 1 Telecon Chit - Diesel Generator Jacketwater 'Ihermostatic Followup per' e -

I'N: 50-416 6/26/80 Control Valve-I.evel I. l4P6L reported that MC 2512. RIV

^

during purge testing a f racture ww friund irt notified.

the beketwater therinostatic control valve m body. The valve was furnished as part of the standby diesel generator by identified by DeLavn1 as Valve No. F501-3:

fart No. F-157202. The licensee has listed four possible causes for this deficiency:

1. Casting flaw; 2. Valve was shipped and installed with pipe spools attached; 3.

Forces due to pressure test (pressure did not '

exceed 40 psi); 4. Flange jacks used at the connections to the jacketwater cooler during

, , c o,. a v >.n test could have h uac]' u. Low-u forces. Report due 7/,28/80,lgiy be r,cnerie.

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.TEU.Non P! l'OR1 F.k'I1.1TY Grand Gulf _

D0u;ET NO. 50-416- ,,

D.U E 6/26/80 TIME 10:15 a.m. t,ic, occ, go, SCLJECT: CDR Diesel Generator,Jacketwater Thermostatic Control Valve Level _I.,

D:.5C llP!iOY Or um UlGENCE: MP&L reported that during purge testing a fracture

- was fo.u.nd. i. n...the. j a.ck.etwater th.e. rmo. ..s t. a.t_i_c._co. _nt_ro. l .v..a.l_v_e .b.o.d..y.. . .. The va.lv,e..w.a_s furnished as part of the standby __ diesel _ generator by_DeLavel and identified by DcLavel as Valve No. F501-B; Part No. F-157202. The Licensee has listed four

.possible causes.for this defic.iency:

~1. Casting Flaw

2. Valve was shipped and installed with pope spools attached ,_
3. Forces due to pressure test (pressure did not exceed 40 PSI) 4.. F1,an6e_ jacks used at_the connections to the_,lacketwater cooler dur_i_ng, test could have caused unknown forces -__

Report due 7/28/80 may be generic.

SIGNATURI: M. Hunt

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AITS'FOA5COISE j

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MISSISSIPPI POWER St LIGHT uWl,P' Helping Build Mississippi ~ ~ *. '

P. D. BOX 1840. J ACKSON. MISSISSIPPI 7g .

39205

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mensgga September 16, 1980

  • 23 att *. ; y Office of Inspection & Enforcasant U. 8. Nuclear Regulatory Commission .

Region II - - -

101 Marietta Street, N.W.

Suite 3100 Atlanta, Geor81a 30303 Attention: Mr. J. P. O'Railly, Director

Dear Mr. O'Reilly:

SUBJECT:

Grand Gulf Nuclear Station .

Units 1 sad 2 Docket Nos. 50-416/417 File 0260/15525/15526 FRD-80/34, Final Report. Information incorrectly Transferred From Design Drawing to Field skatch AEO!-80/223 Rafarance: AECN-80/164,7/23/80 --

On June 26, 1980 Mississippi Power & Light notified Mr. N.

Hunt of your office of a Potentially Reportable Deficiancy (FRD) at the Grand Gulf Nuclear station (CCNS) construction site._~ 'the deficiency concerns the incorrect translation of weld requirements i

from design drawings to field sketches.

l

  • l We have since determined that this deficiency is reportable l under 10CFR50.55(e). Our final report on this matter is attached.

l Tours truly r *W .

p r J. F. McCaugby, Jr.

Assistant Vice President,

, , , Nuclear Production WDErst Attachment ee: Mr. N. L. Stampley Mr. Victor Stello, Director Mr. R. 3. McCahoe Divisica of Inspection & Enforcement Mr. T. 3. Conner U. 5. Nuclear Regulatory Commission Washington, D.C. 20555

  • Y/:$Wfff/l df f OFFICTALCOQ Io Member Middle South Utilities System V ,

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,,775,.F@5m. .s.. ./g

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MISSISSIPPI POWER & LIGHT COMPANYJ'~ '. -

Helping Build Mississippi .'] ,

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tlWdhWidd5 P. O. B O X 18 4 0. J A C K S O N. Ml S SIS Si kt '{p 2 0 5 9

"E.UN'

  • y November 10, 1980 8&CE

' Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Kegion II 101 Marietta Street, N.W.

Suite 3100 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Director

Dear Mr. O'Reilly:

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/417 File 0260/15525/15526 PRD-80/35, Interim Report #2, Standby Diesel Generator Jacket Water Cooler Thermostatic Valve Fracture AECM-80/281

Reference:

AECM-80/166, 7/23/80 On June 26, 1980, Mississippi Power & Light notified Mr. M.

Hunt of your office of a Potentially Reportable Deficiency (PRD) concerning the Standby Diesel Generator. The deficiency was a j fractured valve body on the Jacket Water Thermostatic Valve.

l We have determined this deficiency to be reportable within

the meaning of 10CFR50.55(e). The condition is not reportable r

under 10CFR21 because the components have not been offered to MP&L for acceptance. Attached is our interim report.

We expect to submit a final report by January 29, 1981.

Yours truly.

-g J. P. McCaughy, Jr.

ATR:mt Attachment l

l cc Mr. N. L. Stampley Mr. Victor Stello, Director  ;

Mr. R. B. McGehee Division of Inspectiou & Enforcement l Mr. T. B. Conner U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4 111"eW M @ 1mCTALCOPY l Member Middle South Utllitle_s_ System

(* , 4 Atts:hmes.)to AEOf-80/281-

' ' ' = * * - ~*

  • l

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Pag 3.1 cf 1

.I INTERIM REPORT FOR PRD-80/35 l

1

1.- Descriptica of~ Deficiency During pneumatic pressure testing of the Unit-1 "B" Standby Diesel Generator, the jacket water thermostatic control valve

-cracked at-.the flange connection with adjacent piping. The~

. pressure at the moment of failure was less than the valve ,

design pressure.

It has been determined that failure of the valve could have led to a loss of coolant water which could have resulted in the failure of the Standby Diesel Generator. The failure of the Diesel Generator could have adversely affected the safety of plant operations, since its failure could degrade the safety related -functions of the ESF 4.16 kv busses when off-site power i is not available.

.II. Corrective Action Taken and Results Achieved The remaining Unit i valve, on the "A" Standby Diesel Genera-tor, was subjected to magnetic particle examination. The valve was found to have a hairline linear indication. It was deter-mined that the valve had been subjected to similar conditions as the Unit 1 "B" valve.

Both the vendor and the constructor are identifying causes and corrective actions to preclude recurrence, as applicable, to their organizations.

III. Reason for Delaying Final Report Corrective actions to preclude recurrence have not been completed.

IV. Projected Final Report Date l

A final report is expected to be Jubmitted by February 5,1981.

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