ML18219C361

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LER-1976-014-00 for Donald C. Cook, Unit 1 - Violation of Technical Specifications Paragraph 4.6.5.3.1b3
ML18219C361
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/07/1976
From: Jurgensen R, Shaller D
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-014-00
Download: ML18219C361 (8)


Text

NRC FOAM 195 U.S. NUCLEAR AEGULATORY COMMISSION DOCKET NUMBER 12 7B) 50-315 FILE NUMBER NRC DISTRIBUTION FDA PART 50 DOCKET MATERIAL INCIDENT REPORT J.G. Keppler FRQM: Indiana 8I Michigan Power Co: DATE OF DOCUMENT Bridgman, Michigan 4-7-76 R.W. Jurgensen DATE RECEIVED 4-9 76 OLETTEA, ONOTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL ~ ~~~'i

,l3COPY g UN C LASS IF IE D 30 DESCRIPTION ENCLOSURE Ltr. trans the followngg....... RO P'6-14, on 3-25-76, Concerning Inadequate Data Review.......

(30 Cys. Received)

~ - - p gt.+',4...1 DO NOT H,a~MOVE ACKNOWLEDGED PLANT NANE: COOk 8 1 NOTE! IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION 'ENVIRO BRANCH CHIEF:

W 3 CYS FOR ACTION LIC ~ ASST: .

9/ CYS ACRS 16 CYS KNQXNQ/ ENT TO LA ~

INTERNAL D IST RI BUTION NRC PDR I &E 2 SCHROEDER/IPPOLITO NOVAK CHECK S HWEN E TEDES 0 HACCA F

BAER SHAO VOLLMER BUN H KRE E OL S EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: . eP TIC NSIC 3602 NRC FORM 155 (2-76)

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ri INDIANA 8 lÃICHIGAN 'D VER CD DONALD C. COOK NUCLEAR P lSggg'ON P.O. Box 4SB, Bridgman, Michigan geyy~

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April 7, b I 1976 cF '

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 Comiission Regulatory Guide 1.16, Revision 4, Section 2.a the following report is submitted:

RO 50-315/76-14.

This event had been reported to NRC RO: III by telephone and letter on March 25, 1976.

Sincerely, R.W. Jurgensen Plant Manager

/bab cc: R.S. Hunter J.E. Dolan G.E. Lien R. Kilburn R.J. Yollen BPI 3602

~ 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 R.S. Keith Dir., IE (40 copies)

Dir., MIPC (4 copies)

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LICENSEE EVENT REPORT CDNTROL 8LOCK: (PL ASS PRINT ALL REOUIREO INFORMATION) 1 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

.[oaj I 0 C C I 0 0 0 0 0 0 0 4 I 1 I 1 ~01 7 89 14 15 25 26 30. 31 32 REPORT. AEPOAT

~o~ cow'r~ CATEGORY 57 58 TYPE P

59 SOURCE

~L 60 0 5 OOCKET NUMBER 0 0 3 1 5 60 69 0 3 EVENT OATE 2 5 7 6 74 0

75 4

REPORT OATE 0 I' 6 80 7 0 61 EVENT DESCRIPTION I

toOg WHILE IN MODE 1 AT 81 PERCENT POWER, A REVIEW OF SURVEILLANCE TEST DATA TAKEN AS 7 89 7

conj 7 0 9 09

. REQUIRED BY TECHNICAL SPECIFICATIONS PARAGRAPH 4. 6. 5. 3. 1b3 DURING JULY AND OCTOBER, 1975, INDICATED THAT FIVE ICE CONDENSER INLET DOORS EXCEEDED THE MAXIMUM OF 195 INCH-80 00 0O Qo5 POUNDS OPENING TORQUE WHEN 40 DEGREES OPEN. ADDITIONALLY, ONE DOOR INDICATED A HINGE top~) FRICTION FORCE IN EXCESS OF 40 INCH-POUNDS AS REQUIRED (SEE SUPPLEMENT)(RO-50-315-76 ]4 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT CODE SUPPUER MANUFACTURER IoO~] ~EH ~D x x x x x X ~N

'W 1 2 0 Y 7 0 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Qo0 THE CAUSE OF THE VIOLATION WAS A DEFECTIVE SURVEILLANCE TEST PROCEDURE AND INADEQUATE 7 09 80 Qo9 DATA REVIEW.

7 09 80

'10 7 89 'ETHOO 80 7 0 FACIUTY STATUS 9

E FORM OF

'08 10 55 POWER I

12 13

~

NA,.OTHER STATUS 44 OSCOVEAY

~8 45 OF

.46 OISCOVEAY OESCILPTION ROUTINE DATA REVI EN 80 ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE ca Z Z NA 7 o o 10 11 44 45 80

. PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION t

[<is] ~00 0 ~2 NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

~14 7 89

~OJQJ11 12 NA 00 PROBABLE CONSEQUENCES Q~

7 I09 ANALYSIS 'WAS DONE WITH THE ACTUAL MEASURED VALUES AND THERE WERE NO SAFETY RELATFD CONSEQUENCES. 0o LOSS OR DAMAGE TO FACILITY TYPE OESCFUPTION 0~~3 Z NA 7 89 10 80 PUBLICITY Qc7] NA 7 89 80 ADDITIONAL FACTORS gg00 PREVENTATIVE ACTION TAKEN TO AVOID RECURRENCE OF THIS TYPE OF PROBLEM INCLUDES ~THE 7 00 ISEE SUPPL~EMENTI Pg LFOLLOl'IING'II ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES 7 89 NAME. T.F. PLUNKETT PHDNE 616 465 5901(331 CPO 88I 887

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SUPPLEMENT TO RO-050-315/76-14 SUPPLEMENT TO DESCRIPTION OF CONDITION BY TECHNICAL SPECIFICATIONS PARAGRAPH 4.6.5.3.lb5. THE ACTUAL MEASURED VALUES WERE AS FOLLOWS:

DOOR NUMBER OPENING TOR UE (inch-pounds) 15L 223 15R 213 19R 245 22R 207 ~

23L 236 DOOR NUMBER HINGE FRICTION FORCE (inch-pounds) 23L 45 THE FAILURE TO RECOGNIZE THE DOORS DEFICIENT CONDITION AT THE TIME OF THE TEST 'WAS DUE IN PART TO THE SURVEILLANCE TEST PROCEDURE NOT DIRECTLY SPECIFYING THE OPENING TORQUE AS A TECHNICAL SPECIFICATION ITEM AND IN

'I PART TO INADEQUATE'DATA REVIEW AT THE TIK': OF THE TESTS. ON MARCH 25, 1976, THE PLANT WAS BROUGHT TO MODE 2 AND ALL INLET DOORS WERE TESTED WITH SATISFACTORY RESULTS. A TEMPORARY CHANGE SHEET WAS WRITTEN TO CORRECT SURVEILLANCE TEST PROCEDURE TKP 4030 STP.207 AND A PROCEDURE REVISION WAS INITIATED TO PROPERLY SPECIFY THE REQUIRED TORQUE VALUES ON THE DATA SHEET.

SUPPLEMENT TO ADDITIONAL FACTORS ARE BEING REVISED TO ENSURE THAT THEY ACCURATELY REFLECT THE REQUIREMENTS

. OF THE TECHNICAL SPECIFICATIONS.

(2) ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES WILL BE REVISED TO CLARIFY THE ACCEPTABLE CRITERIA PORTION OF THE PROCEDURE AND INCLUDE DATA SPECIFICATIONS ON THE DATA SHEETS TO AFFORD BETTER REVIEW OF DATA TAKEN.

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