ML20154Q219
| ML20154Q219 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/18/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, SBN-967, NUDOCS 8603210068 | |
| Download: ML20154Q219 (3) | |
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March 18, 1986 Pubuc Service of New Hampshire SBN-967 T.F. B4.2.99 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5
References:
(a) Construction Permit CPPR-135 and CPPR-136, Docket Nos.
50-443 and 50-444 (b) USNRC Letter, dated August 10, 1983, " Safety Evaluation Report un the Generic Westinghouse Design for Automatic Shunt Trip Actuation," D. G. Eisenhut to J. J. Sheppard (WoG)
(c) PSNH Letter (SBN-868), dated September 9, 1985, " Additional Response to Generic Letter 83-28 (Positions 4.1 and 4.3),"
J. DeVincentis to G. W. Knighton
Subject:
Additional Information Regarding Generic Letter 83-28, Position 4.3
Dear Sir:
In Reference (c) Public Service of New Hampshire stated that an addi-tional response would be developed for response numbers 4, 9, 10, 11, and 12, when plant-specific test procedures were completed. The referenced olant-specific test procedures have been completed and the following information is being presented to close out Position 4.3.
4.
Reauest
" State whether the test procedure / sequence used to independently verifv' operability of the undervoltage and shunt trip devices in response to an automatic reactor trip signal is identical to the test procedure proposed by the Westinghouse Owners Group (WOG). Identify any differences between the WOG test procedure and the test procedure to be used and provide the rationale / justification for these differences."
Response
Seabrook Station has developed four test procedures that require independent verification of the operability of the undervoltage and shunt trip devices. These procedures are identient to the proposed WOG Test I['/
Procedures.
9 8603210068 860318 PDR ADOCK 05000443
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P.O. Box 300. Seabrook, NH O3874. Telephone (603)474 %21
a United States Nuclear Regulatory Commission March 18, 1986 Attention:
Mr. Vincent S. Noonan Page 2 9.
Request
" Verify that the operability of the Control Room manual reactor trip switch contacts and wiring will be adequately tested prior to startup af ter each refueling outage. Verify that the test procedure used will not involve installing jumpers, lifting leads, or pulling fuses and identify any deviations from the WOG procedure. Permanently installed test connections (i.e., to allow connection of a voltmeter) are acceptable."
Resnonse The operability of the Control Room manual reactor trip switch contacts and wiring will be tested prior to startup after each refueling outage.
The procedure, " Post Refueling Pre-Startup RX Trip Breaker Surveillance,"
tests the Control Room manual reactor trip switch contacts and wiring, and does not involve installing jumpers, lif ting leads or removing fuses.
- 10. Request
" Verify that each bypass breaker will be tested to demonstrate its operability prior to placing it into service for reactc* trip breaker testing."
Response
Plant-specific procedures have been developed that use the local close and trip pushbutton switches when testing each bypass breaker prior to placing them into service for reactor trip breaker testing.
- 11. Request
" Verify that the test procedure used to determine reactor trip breaker operability will also demonstrate proper operation of the associated Control Room indication / annunciation."
Response
Plant procedures that were developed to determine reactor trip breaker operability also demonstrate proper operation of the associated Control Room indication / annunciation.
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,I United States Nuclear Regulatory Commission March 18, 1986 Attention:
Mr. Vincent S. Noonan Page 3 a
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- 12. Request j
" Verify that the response time of the automatic shunt trip feature will be i
tested periodically and shown to be less than or equal to that assumed in the FSAR analyses or that specified in the Technical Specifications."
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Response
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l The automatic shunt trip feature for each trip and bypass breaker will be
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tested during each refueling. The response time will be verified equal to j
or less than 0.167 seconds, as referenced in the Generic Westinghouse Design for Automatic Shunt Trip Actuation, WOG 1etter Number OG-101 from l
J. J. Sheppard to D. G. Eisenhut, dated June 14, 1983.
Should you have any additional questions, please do not hesitate to contact us.
j Very truly y urs, f
John DeVincentis, Director
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