ML18142B875

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

ML18142B875
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: ML18142B875 (6)

Text

X' Ri AI. OGGUitPv.IMAGE AND OR XNGXDENX'R~STRIBUTION FOR PART 50 DOCk,, MATERIAL-(TEMPORARY FOBivl)

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FROM. Rochester Gas 8o Electric DATE OF DOC DATE R EC'D LTR TWX RPT OTI-IE R Rochester N. Y-L D White Jr 6-25-75 7-2-75 ORIG CC OTHER SFNT AEC PDR Mr. O'Reilly none, signed. SENT LOCAL PDR CLASS UNC LASS PROP INFO tNPUT NO CYS REC'D DOCKET NO:

XXXX 40 50-2tttt DESCR IPTION ENCLOSURES:

Ltr trans the following: Abnormal. Occurrence Report No.

75-.10 on 6-11-75, during safeguard. valve survei-

'ACKNOvVLHDGED nce testing the "C" SX pump discharge MOV's 873A and"871j3 were found closed.;.

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.,~/ r I IAIC III'(/'/'lA'i~i~!3Il~i/ur'I!lg ROCHESTER GAS AND ELECTRIC CORPORATION , 89 EAST AVENUE, ROCHES ER, N.Y. 14649 LEON D. WHITE, JB. TEEEI'HONE '"

VICE PRESIDENT *REA cooE Tue 546.2700 June 25, 1975

$(.V @qQ s, 'IO I

Mr. James P. O'Reilly, Director ~

<<EIIt U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement legion I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Abnormal Occurrence 75-10, Personnel error which could prevent 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 l 8

/,y cc: Mr. Donald F. Knuth (40) ><It+

45 iCP~~ EE~

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a 1 4

LICENSEE EVENT REPCPy

'ON~lOL BLOCK: (PLEASE PRII'4T ALL REQUIRED IMFORPJIATION3 LICENSEE UCENSE EVENT NAME LICENSE NUMSER TYPE TYPE N Y R R G 1 0 0 0'0 0 0 0 0 0 4 1 1 1 1 ~01 7 89 14 15 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMOER EVENT DATE REPORT DATE

~01 cON> ~DI58 ~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 tOD3] 871B were found closed. The two other SI um s on se arate buses were ca able of 7 89 80 toOj4 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

[oO~J (Abnormal Occurrence 50-244/75-10) 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VIOIATION

[oarI ~sF ~A H 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION l00m Incorrect position of the valves was due to operator error during safety injection pump 7 8 9 I 80

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

7 8 9 80

~10 7 89 FACIUTY METHOD OF 80 STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Qg8 '

~z ~os o NA b NA 7 10 12 13 44, 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE gg 7 8 9 H ~p 10 11 44 45 NA 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~00 0 NA 7 89 11 12 80 OFFSITE CONSEQUENCES 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

~16 P, NA 7 89 10 80 PUBLICITY NA 7 8 9 80 ADDITIONAL FACTORS Q~g In the event of safeguards actuation, all 3 50% capacity SI pumps are automatically 7 89 80

~qg started in a timed sequence, and', in case one of the other (cont'd. on attached page) 7 89 80 NAME. Bruce A. Snow PHDNEI 716-546-2700, ext. 291-214 GFO 881 ~ 667

Licgnsee Event Rep.

50-244/'05-10 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.