ML20069A333
| ML20069A333 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/07/1983 |
| From: | Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-SSINS-6820 IEB-83-01, IEB-83-1, NUDOCS 8303150602 | |
| Download: ML20069A333 (5) | |
Text
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John D. O'Teois Vice Presroent a
Consohdated Edison Company of New Yoik, Inc 4 frying r Ace. New York NY 10003 Telephone '212) 460-2533 March 7, 1983 Re:
Indian Point Unit No. 2 Docket No. 50-247 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Document Conrol Desk Washington, D. C.
20555
Dear Mr. Haynes:
Attachment A to this letter contains our response to IE Bulletin No. 83-01 " Failure of Reactor Trip Breakers (Westinghouse DB-50) To Open On Automatic Trip Signal".
This response is being provided pursuant to Section 182 of the Atomic Energy Act as amended.
Should you or your staff have any additional questions, please contact us.
Ver truly yours,
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T b Y LOVE Notary PutAi: Stab of New York 1
No. 3121.09533 1
QuoBfled in New Ycr.< C n nty Commission Expires March J0.1983 attach.
cc Mr. Ronald C.
Haynes, Regional Administrator j
office of Inspection and Enforcement j
Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 l
Mr. Thomas Foley, Senior Resident Inspector
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U.
S. Nuclear Regulatory Commission gp j
P. O. Box 38
[f 8i Buchanan, New York 10511 9303150602 830307 PDR ADOCK 05000247 0
t ATTACHMENT A Response to IE Dulletin No. 83-01
" Failure of Reactor Trip Dreakers (Westinghouse DB-50) To Open On Automatic Trip Signal" Consolidated Edison Company of New York, Inc.
Indian Point Unit No. 2 Docket No. 50-247 March, 1983
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b Response to IE Dulletin No. 83-01 4.-
Provide written reply within 7 days of receipt of this bulletin, a.
identifying results of testing performed in response to i
item 1, 1.
Perform surveillance test of undervoltage trip function independent of the shunt trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of receipt of this Bulletin unless equivalent testing has been performed within 5 days.
Those plants for which on-line testability is not provided may complete this item before resuming operation or if currently operating, at the next plant shutdown.
Response to 4a.
Periodic test " Reactor Protection Logic Channel Functional Test",
(PTM-14A) was successfully performed on February 25, 1983 prior to receipt of IE Bulletin No. 83-01.
The test demonstrated the
. operability of the reactor trip and bypass breaker undervoltage trip function independent of the shunt trip.
b.
identifying conformance of maintenance program to W
3 recommendation and describing results of maintenance performed directly as a result of this Bulletin in response to item 2, 2.
Review the maintenance program for conformance to recommended W program (attachment) including frequency and lubricant applied to trip mechanism.
Verify actual implementation of the W program.
If maintenance including lubrication does not conform, initiate such maintenance within 5 days of receipt of this bulletin or provide an alternate maintenance program.
Repeat the testing required in item 1 prior to declaring the breaker OPERABLE.
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s Response t'o 4b.
The existing maintenance program was reviewed with respect to the Westinghouse program in the areas ' of maintenance frequency and type of lubrication applied to - the trip mechanism.
This review was begun on ' February '25, 1983.
Revision to the program to meet i
the Westinghouse recommendations was commenced on February 26, 1983.
Initiation of maintenance program changes (i.e. procedure review, approval and acquisition of specified lubricant) began on February 28, 1983.
A new - procedure " Reactor - Trip and Bypass Breakers Air Circuit Breaker DB-50 P/M Semi Annual Inspection" (MP-16.33) was developed and approved on March 2, 1983.
The preventive maintenance program, including a surveillance test of the undervoltage trip function was performed on all four-reactor trip and bypass breakers on March 2 and -March 3,
1983.
The breakers were found in satisfactory condition after the application of minute amounts of lubrication in appropriate locations, with no additional remedial action required.
c.
provide statement that provisions are in place to notify licensed operators of the Salem event and bring to their attention appropriate failure-to-trip emergency procedures upon their arrival on-shift.
3.
Notify all licensed operators of the failure-to-trip event which occurred at Salem.
Review the appropriate emergency operating procedures for the event of failure-to-trip with each operator upon his arrival on-shift.
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Response to 4c.
Upon their first arrival on chift, each SWS, SRO and RO was directed by instruction in the night order book to review a memorandum which describes the failure to trip event at Salem.
By the same memorandum, all such personnel were directed to review the appropriate emergency operating procedures for the event of failure to trip.
Completion of the required review is documented by written acknowledgement by each SUS, SRO and RO.
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