ML18219C353

From kanterella
Revision as of 14:03, 16 August 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
LER-1976-023-00 and LER-1976-024-00 for Donald C. Cook, Unit 1 - Failure of Various Containment Isolation Valves to Meet Acceptable Type B Lake Rate Specifications, and Excessive Opening Torque Found in Ice Condenser Lower Inlet Door
ML18219C353
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/02/1976
From: Jurgensen R
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-023-00, LER-1976-024-00
Download: ML18219C353 (8)


Text

INDIANA&NICHIGAN PDNEB CONPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 2, 1976 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No.50-315

Dear Mr.Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 4, Section 2.b, the following reports are submitted:

RO-50-315/76-23 RO-50-315/76-24 Sincerely, t R.W.J ge en Plant an er/bab cc: R.S.Hunter J.E.Dolan ,G.E.Lien R.Kilburn R.J.Vollen BPI R.C.Callen MPSC K.R.Baker RO:III P.W.Steketee., Esq.R.'Walsh, Esq.G.Charnoff,,Esq.

G.Olson J.M.Hennigan PNSRC RES.Keith Dir., IE (30 copies)Dir., MIPC (3 copies) 7r CONTROL BLOCK: 1 I ICENBEE EVENT RE9ORT t'PLEASE PRINT ALI.REQUIRED INFORMATION)

M I 7 89 LICENSEE NAME LICENSE NUMBEA C C 1'0-0 0 0 0 0 14 15 LICENSE TYPE EVENT TYPE 0 0 4 1 1 1 1 L0GG3~I 25 26 30 31 32 REPORT.CATEGORY TYPE.~o~coNv~L 7 8 57'8 59 EVENT DESCRIPTION

@~2 WHILE.IN NODE 5 7 8 9 AEPOAT SOURCE DOCKET NUMBEA~L 0 5 0-0 3 60'1 EVENT DATE REPORT DATE 1 5 0 5 0 2 7 6 0 68 69 74 75 DURING SURVEILLANCE TESTING OF CONTAINMENT ISOLATION VALVES VARIOUS ILED TO EET P B E TYPE B LEAK'ATE SPE I 80 80 7 89 I t004j RE I E EC L SPECIFICATIONS PARAGRAPH 3.6.1.2.b.

7 8 9 Jog 7 8 9 Jog (RO-50-31 5/76-23)80 80 80 7 8 9 SYSTEM CAUSE COOE, CODE PAM E COMPONENT COMPONENT COMPONENT CODE SUPPUEA MANUFACTUREA VOLATION~S.D E V" A L V E X 0 7 8 9 10 11 12 17 43-44 47 48 CAUSE DESCRIPTION Q~B EXCESSIVE LEAKAGE DUE TO DEPOSIT BUILDUP ON VALVE SEATS AND WEAR BY VALVE OPERA I N 80 7 8 9 80 Qo9 ALL VALVES WITH EXCESSIVE LEAK RATES WERE REPAIRED AND RETESTED', TOTAL LEAKAGE WAS 80 7 8 9 Qg WITHIN SPECI FI CATION.7 89 FACIUTY STATUS POWER OTHER STATUS~G~00 0 NA 7 8 910 12 13 FORM OF ACTIVITY COATENT RELEASEO Of RELEASE~,, AMOUNT OF ACTIVITY Q1g-,~Z" Z NA~7 8 9" 10 11 PERSONNEL EXPOSURES EH3 Lab~LZJ 7 89 11 12 13 PERSONNEL IN JURIES NUMBER DESCRIPTION

~~~~oo o 7 89 11 12 PROBABEE CONSEQUENCES-Qg NA 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION t116t~Z NZ 7 89 10 PUBLICITY NA 7 89 ADDITIONAL FACTORS Jig.NA 7 89 METHOD OF OSCOVEAY 44 45.46 NA 44 45 DISCOVERY DESCRIPTION SURVEILLANCE TESTING LOCATION OF RELEASE 80 80 80 80 80 80 80 80'80 7 89 JACK RISCHLING , 80 PHPNEI 616 465-'5901 368)GFO 88I 667 SUPPLEMENT TO REPORTABLE OCCURRENCE RO-50-315 76-23 SUPPLEMENT TO EVENT DESCRIPTION THE FOLLOWING VALVES WERE FOUND TO HAVE EXCESSIVE LEAKAGE: DCR-621 ECR-15 GCR-314 NCR-105 NCR-106 NSW-244-2 NSW-244-3 NSW-244-4 WCR-958 NSW-417-4 NSW-415-1 NSW-415-2 WCR-905 NSW-415-3 NSW-415-4 WCR-922 WCR-921 NSW-417-3 VCR-106 VCR-206 SI-189 N-102 SM-1

y LICENSEE EVENT REPORTS joO~I N I 7 89 CONTRDL BLOCK: 1 LICENSEE NAME D C C 1 14 15 LIC EN S E NUM BE R 0 0-0 0 0 0 0-LICENSE TYPE 4 1 1 1 1 25 26 30 EVENT TYPE 31 32 (PLEASE PRINT ALL REOUIRED INFORIVIATIONg REPORT.REPORT CATEGORY TYPE'OURCE

~os coN'T~I.~L 7 8 57 58 59 60 DOCKET NUMBER EVENT DATE REPORT DATE 0 5 0 0 3,1 5 0 5 0 6 7 6 0 60 1 7 6 61 68 69 74 75 80 EVENT DESCRIPTION Qom WHILE IN MODE 5, DURING ICE CONDENSER INLET DOOR OPENING TORQUE SURVEILLANCE TESTING, 7 8 9 80 I LOWER INLET DOOR 1-R OPENING TORQUE WAS FOUND IN EXCESS OF TECHNICAL SPECIFICATION 7 89 Qp43 PARAGRAPH 4.6.5.3.1 b3 LIMIT OF 195 INCH POUNDS.LOWER INLET DOOR 3-L INITIAL 80 7 8 9 80 toOI 0PENING TOR UE wAs F0UND TO BE IN ExcEss 0F TEGHNIGAL sPEGIFIGATI0N PARAGRAPH 4.6.5.3.1 7 8 9'ol b1 LIMIT OF 675 INCH POUNDS.DOOR 1-R SPRING TENSION (SEE SUPPLEMENT)(RO-50-315/7644 7 89 SYSTEM CODE PRME COMPONENT'UPPUER CAUSE CODE COMPONENT CODE Ion~]~SB F X X X X X X N 7 8 9 10'l1 12 17~43 CAUSE DESCRIPTION

[Gag DOOR 1-R LIMIT WAS EXCEEDED DUE TO SPRING COMPONENT MANUFACTURER W 1 2" 0 44 47 48 TENSION DRIFT.DOOR 3-L INITIAL OPENING 80 7 8 9 Qol 7 8 9~o 7 89 FACIUTY STATUS POWER EH 0~00 0 NA 7 8 9 , 1012 13 FORM OF ACTMTY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Q~g~Z Z NA 7'9'0 11 PERSONNEI EXPOSURES 7 89 11 12 13 PERSONNEL IN JURIES NUMBER DESCRIPTION

~i~~00 0 NA 7 89,'1 12 PROBABLE CONSEQUENCES

'~g NA 7 89 LOSS OR DAMAGE TD FACILITY TYPE DESCRIPTION Q~g Z NA 7 89 10 PUBLICITY~17 NA 7 89 80 E EEDED LIMITS BECAUSE OF AN ICE BUILDUP FROM CONDENSATION ON THE LOWER SILL.ADDITIONAL FACTORS Q~g NA 7 89 Qqg NA 7 89 NAME J.RISCHLING OTHER STATUS METHOD OF DISCOVERY DISCOVERY DESCRIPTION

{616)465-5901(368)

B SURVEILLANCE TESTING 44 45 46 LOCATION OF RELEASE NA 44 45 80 80 80 80 80 80 80 80 80 80 GPG SS'I~667 SUPPLEMENT TO REPORTABLE OCCURRENCE'RO"50"315/76" 24 SUPPLEMENT TO EVENT DESCRIPTION WAS ADJUSTED TO PROVIDE A 189 INCH POUND OPENING TORQUE.DOOR 3-L BOTTOM SILL WAS CLEANED AND INITIAL OPENING TORQUE WAS REMEASURED AT 287 INCH POUNDS.

~~~I'L