05000244/LER-1989-016-02, Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21

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Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21
ML17261B085
Person / Time
Site: Ginna 
Issue date: 06/28/1990
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17261B086 List:
References
REF-PT21-90 NUDOCS 9007090051
Download: ML17261B085 (2)
v • d • e


LER-1989-016, Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21
Event date:
Report date:
2441989016R02 - NRC Website
v • d • e

text

ACCELERATED DISTRIBUTION DEMONSTPJ!!.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9007090051 DOC.DATE: 90/06/28 NOTARIZED: NO DOCKET g

FACIL:50-244 Robert Emmet Ginna Nuclear Plant," Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION, Document Control Branch (Document Control Desk)

R D,

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S 05000244

/

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

SUBJECT:

Forwards LER 89-016-02 re 891117 design deficiency failure of SI block/unblock switch could render some AAF inoperable.

DISTRIBUTION CODE:

IE28T COPIES RECEIVED:LTR J ENCL $

SIZE: I+

TITLE: Licensee Event Report (LER) 6 Part 21 Rept Combination (50 Dkt RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB DEDRO NRR/ADP/DRP14 E4 NRR/DET/ECMB 9H NRR/DET/ESGB SD NRR/DLPQ/LPEB10 NRR/DOEA/OGCB11 NRR/DREP/PRPB11 NRR/DRIS/RVIB9D NRR/DST/SELB SD NRR/DST/SPLBSD1 NSIC SILVER,E REGION 1

REGION 3

REGION 5 RES/DSR/HFB/HFS RGN1 FILE 01 EXTERNAL:

EGGG STUART,V.A L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1

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RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP IRM TECH ADV NRR/ADSP DIR NRR/DET/EMEB9H3 NRR/DLPQ/LHFB11 NRR/DOEA/OEABll NRR/DREP/PRAB10 NRR/DRIS/RSIB9A NRR/DST 8E2 NRR/DST/SICB 7E

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REGION 4

RES/DSIR/EIB RES/DSR/PRAB INPO RECORD CTR LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

D D

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:

LTTR 52 ENCL 51

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ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 tfg g 0 ee C ~f A~ci cooc r>o 546 2700 June 28, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 89-016 (Revision 02),

Due To a Design Deficiency The Failure of the SI Block/Unblock Switch Could Render Some Automatic Actuation Features of Both Trains of SI Inoperable R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report

System, item (a)

(2)

(v)

(D) and (a)

(2) (vi), which requires a

report of, "any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident",

and in accordance with 10 CFR '-1, "Reporting of Defects and Noncom-pliances", the attached Licensee Event Report LER 89-016 (Revision 02) is hereby submitted.

This revision is necessary to add additional information obtained as a result of a review of the application of similar switches.

Due to the date of the original installation (1969),

the condition is technically not 10 CFR 21 reportable.

However, due to the potential significance of the failure scenario, Rochester Gas

& Electric is submitting voluntary notification.

Specific information regarding failure identification and corrective actions can be obtained from Mr. Richard A.

Baker, Electrical Engineering, on (716) 546-2700.

This event has in no way affected the public's health and safety.

Very truly yours, Robert C.

Mec dy Division Manager Nuclear Production XC ~

U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 90070'r0051 900628 PDR ADOCK 05000244 8

FDC

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