ML18142B873

LER 1975-010-00 for R. E. Ginna, Personnel Error Which Could Prevent Fulfillment of Functional Requirements of Systems Required to Cope with Accidents Analyzed in the SAR

ML18142B873
Person / Time
Site:	Ginna
Issue date:	06/25/1975
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1975-010-00
Download: ML18142B873 (8)

Text

< RH ~ OCCURIU NCE AND/OR INCIDENT NRC L RIBUTION FOR PART 50 DOCKE ATERIAL e

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(TEMPORARY FORM)

CONTROL NO: 7416 FILE INCIDEWC REPORT FILE, FROM: Rochester Gas & Elec. Co p DATE OF DOC DATE REC'D LTR TWX RPT OTHER Rochester, N.Y ~ " 14649.

6-25-75 7-11-75 TO: ORIG CC OTHER SENT AEC PDR Mr. J. P. O'Reilly 1 signed SENT LOCAL PDR

CLASS UNC LASS PROPINFO INPUT NO CYS REC'D DOCKET NO

1 50-244 DESCRIPTION: Ltr trans the following: Licensee Event Report AO-50-244/

75-10 on 6>>11-75 re failure of the "C" SI pump discharge MOV's 871A tN 871B'were found closed...

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PLANT NAME: R,E. Ginna t i<(IE()

FOR ACTION/INFORMATION DHL 7-12-75 BUTLER (L) SCIEWENCER (L) ZIEMANN (L) REGAN (E)

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'Regula tory Docket File

,"I1AM Ill/// . ///////////// J ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON O. WHITE, JR. TEEEPHONE VICE PRESIDENT AREA CODE TIS 546-2700 June 25, 1975 3

q Mr. James P. O'Reilly, Director /~l 4g~

U. S. Nuclear Regulatory Commission ~>> 0gp4g~

Office of Inspection and Enforcement p~

Region I Egg .

8 8 631 Park Avenue King of Prussia, Pennsylvania 19406 ~ < P Abnormal Occurrence 75-10, Pers which could prevent J'ubject:

the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications, Article 6.6.2a, the attached report of Abnormal Occurrence 75-10 is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

Very truly yours, L. D. White, Jr.

Attachment cc: Mr. Donald F. Knuth (40)

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CONTROL BLOCK:

~ LICENSEE EVENT REPOR nl.-": $

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fPLE 8E PAINT ALL REQUIRED INFOAMATIOIII) 1 UCENSEE EVENT NAME LICENSE NUMBER TYPE TYPE Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~0011 7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

[oa~j corn ~BI58 T L 0 5 0 0 2 4 4 0 6 1 1 7 5 0 6 2 5 7 5 7 8 57 59 60 61 68 69 74 75 80 EVENT DESCRIPTION Jog Durin safe uard valve surveillance testin the "C" SI um dischar e MOV's 871A and 7 8 9 80

[os] 871B were found closed. The two other SI um s on se arate buses were ca able of 89 80 100j4 performing their intended function. Valves were placed to correct open position. Sub-7 8 9 "80 Qpg sequently a check was made to verify that all SIS valves were in the proper position.

7 8 9 80

[pP~J (Abnormal Occurrence 50-244/75-10) 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTUREA

[on>I~SF A 6 8 8 8 6 8 ~B H 9 9 9 Y 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

[oas] Incorrect position of the valves was due to operator error during safety injection pump 7 8'9 80

~09 monthly surveillance testing. Measures to prevent recurrence are on attached page.

7 8 9 80

~10 7 89 80 FACIUTY METHOD OF STATUS 96 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Pg8 6 ~os o NA NA 7 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION

~4 ~00 0 NA 7 89 11 12 80 OFFSITE CONSEQUENCES Q~g NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY=

TYPE OESCAIPTION

~16 P NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Q~g In the event of safeguards actuation, all 3 50% capacity SI pumps are automatically 7 89 80

~19 started in a timed sequence, and, in case one of the other (cont'd. on attached page) 7 89 80 Bruce A. Snow PHDNEI 716-546-2700, ext. 291-214 GPO 88 I 667

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e Ltceneee Event Repk I 50-244/75-10 Measures to Prevent Recurrence:

The operator involved was reprimanded for his error. The procedure used during error committal was reviewed and no inadequacies were noted in the procedure. However, a procedure change was reviewed by the Plant Operations Review Committee and was recommended for approval on June 23, 1975 to eliminate procedural options relative to the operation of MOV-871A and MOV-871B.

In addition, the Operations Engineer has issued a memorandum to all operators to once again impress upon them the importance of adhering to procedures, and stressed the importance of verification of status lights on safeguards equipment when assuming control board duties.

Additional Factors cont'd. )

2 SI pumps fails to start, one of the "C" SI pump discharge MOV's will automatically close to direct flow to the affected loop. Emergency Procedure E-1.1, Safety Injection Actuation, directs operators to observe measured variables and status indicators to verify proper automatic actions, and to perform any necessary actions manually. In doing so, if either "A" or "B" SI pump were to fail to start, the required manual action would be performed to provide flow to the affected loop from the "C" pump, namely to open the appropriate MOV.

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