ML18142A953
| ML18142A953 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/18/1976 |
| From: | White L Rochester Gas & Electric Corp |
| To: | O'Reilly J NRC/IE, NRC Region 1 |
| References | |
| IEC-76-002 | |
| Download: ML18142A953 (3) | |
Text
ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, eoex l
Reit N.Y. I4649 LEON D. WHITE. JR.
VICC PRCSIDCNT TCCCPHDHC ARCA CDDC 7IG 546-2700 October 18, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
IE Circular 76-02:
Relay Failures-Westinghouse BF (ac) and BFD (dc) Relays R. E. Qinna Nuclear Power Plant, Unit 41 Docket No. 50-244
Dear Mr. O'Reilly:
This letter is in response to Inspection and Enforcement Circular 76-02,, dated August 18, 1976 and received at Ginna Station on August 20, 1976 concerning a number of Westinghouse type BFD relays'hich mal-
'unctioned at the Point Beach station and the Westinghouse Beaver facility.
Our investigation was divided into two areas,
- 1) connected with the Reactor Protection System and the Safeguards Systems; and 2) connected with auxiliary power circuit breakers and emergency generators.
In the first area each associated relay was verified as being checked in the performance of periodic surveillance testing procedures.
The following is a list of these procedures, their frequency of use, and the latest date of performance.
Procedure No..
Title Performance Date
~Pre uenc PT-5 '.
Process Instrumentation Reactor 10/15/76 Protection Channel Trip Test Monthly PT-5.50 Auto Stop Oil Pressure Switch and Relay Test
'9/17/76 Monthly e
PT-6.1 Source Range Nuclear Instrumen-10/11/76 tation System Weekly PT-6.2 NIS Intermediate Range Channels 9/ 2/76 Prior to Reactor Startup
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ROCMESTER GAS AND ELECTRI P.
DATE October 18, 1976 Mr. James P. O'Reilly, Director SMEET !40.
2 Procedure No.
Title Performance Date Pre uen'c PT-6.3 Power Range Nuclear Instrumen-tation System 10/12/76 Biweekly PT-9 Undervoltage
& Underfrequency, 9/2 1/76 Protection llA & llB 4160 volt Buses Monthly PT-14 Circulating Water Pumps
. High Water Trip Logic 2/2S/76 Refueling PT-17. 2 Process Radiation Monitors R11-R-20, Iodine Monitors RlOA &
R10B 9/22/76 Monthly
'PT-20 Main Steam Isolation Valve Solenoids Trip Test 9/13/76 Bimonthly PT-21 Cleaning Boric Acid Tank Level 10/13/76 Sensing Lines Weekly PT-32 Reactor Trip Logic Test A or B Trains 3/19/76 Refueling PT-32.1 Plant Safeguard Logic Test A or B Train 3/11&12/76 Refueling In the second area, the associated circuit breakers receive annual maintenance in accordance with procedure M-32.1, DB-25, DB-SO, and DB-75 Circuit Breaker Maintenance and Overcurrent Trip Device Test and/or Replacement Procedure.
A proposed change to this procedure has been sub-mitted which willrequire specifically documenting verification of operability of the relays in this area.
Complete verification of operability of these relays willbe carried out by the end of the 1977 refueling shutdown.
'In the two areas investigated, no malfunctions of the type described in the subject Circular were found.
Very truly yours,
~'~r ~Pi.
L. D. White, Jr.
cc:
NRC Office of Inspection and Enforcement Division of Reactor Inspection Programs Washington, D. C.
20555