ML20002D177

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Forwards Request for Addl Info Re SEP Topic VII-1.A, Isolation of Reactor Protection Sys from Nonsafety Sys
ML20002D177
Person / Time
Site: Oyster Creek
Issue date: 12/26/1980
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
References
TASK-07-01.A, TASK-7-1.A, TASK-RR LSO5-80-12-048, LSO5-80-12-48, NUDOCS 8101190704
Download: ML20002D177 (3)


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L POR JWetmore Docket No. 50-219 CRBd5 reading RDiggs LS05-80-12-048 NRR reading JRoe.'

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Mr. I. R. Finfrock, Jr.

WPaulson TNovak Vice President - Generation TJCarter RTedesco Jersey Central Power & Light Comany 0Crutchfield Glainas OELD GCwalina Madison Avenue at Punch Bowl Road' 01&E(3)

SEP file (4)

Morristown, New Jersey 07960 NSIC, JBuchanan

Dear Mr. Finfrock:

TERA RE: SEP TOPIC VII-1.A. ISOLATION OF REACTOR PROTECTION SYSTEM FROM NON-SAFETY SYSTEMS, INCLUDING QUALIFICATION OF ISOLATION DEVICES The staff has prepared the enclosed request for additional infomation on the subject topic. These questions only address the instrumentation aspects of our review. Because cyster Creek uses protective relaying as isolation devices, additional questions may be forwarded as a part of our audit of the adequacy of protective relay coordination.

We request your response within 30 days of your receipt of this letter.

Sincerely.

Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Enclosure:

Request for Additional Infomation on SEP Topic VII-1.A cc w/ enclosure:

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DEC 2 61980 Docket No. 50-219 LS05-80-12-048 Mr. I. R. Finfrock, Jr.

Vice President - Generation Jersey Central Power & Light Concany Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960

Dear Mr. Finfrock:

RE: SEP TOPIC VII-1.A, ISOLATION OF REACTOR PROTECTION SYSTEM FROM NON-SAFETY SYSTEMS, INCLUDING QUALIFICATION OF ISCLATION DEVICES The staff has prepared the enclosed request for additional information on the subiect topic. These questions only address the instrumentation aspects of our review. Because Oyster Creek uses protective relaying as isolation devices, additional cuestions may be forwarded as a part of our audit of the adequacy of protective relay coordination.

We request your response within 30 days of your receillt of this letter.

Sincerely, N.

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Dennis M. Crutchfield, Chief Operating Reactors Branch 15 Division of Licensing

Enclosure:

Request for Additional Information on SEP Topic VII-1.A cc w/ enclosure:

See next page l

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s Mr. I. R. Fi nf rock, J r.

cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.

Bureau of Radiation Protection Washington, D. C.

20036 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Cocinissioner Licensing Manager New Jersey Department of Energy 260 Cherry Hill Road 101 Coninerce Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 91715th Street, N. W.

Oyster Creek Nuclear Generating Washington, D. C.

20006 Station P. O. Box 388 Forted River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident Inspector P. O. Box 1060 c/o U. S. NRC Toms River, New Jersey 03753 P. O. Box 445 Forted River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General Director, Criteria and Standards State of New Jersey Division -

Office of Radiation Programs Department of Law and Public Safety 1100 Raymond Boulevard (ANR-460)

Newart, New Jersey 07012 U. S. Environmental Protection Agency Ocean County Library Washington, D. C.

20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR Lacey Township 25 Fe.ieral Plaza l

P. O. Box 475 New York, New Yort 10007 I

Forked River, New Jersey 08731 Comissioner Department of Public Utilities I

State of New Jersey 101 Comerce Street Newart, New Jersey 07102

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON OYSTER CREEK 1 FOR SEP TOPIC VII-1.A The FSAR and available drawings do not contain sufficient information for us to review the degree of isolation between the Reactor trip system and non-safety control systems. Therefore, please provide the following additional information:

1.

Describe the isolation buffer circuits used for isolation of high level and low level signals to the plant on line computer from safety related circuits.

Provide-9 ectrical schematics, equipment specifications and a description of how the eouipment satisfies the requirements of IEEE Std. 279-1968 (Ref. License application FSAR Supplement #6, 1 November 1973).

2.

Describe the types of isolation devices that define the Class IE boundary for each Reactor Trip System (RTS) interface.

3.

Describe the method of isolation between channels of the RTS and between the RTS and the following functions: Mode switch, RTS by-pass switches, manual switches for control of RTS functions, and the event recorder. Define how these inter-faces satisfy the requirements of IEEE Std. 279-1968.

4.

Provide current electrical schematic-drawings of the follty,;ing systems:

(a) core spray system (b) containment spray system (c) pois6n system (d) primary containment system l

(e) stand by gas treatment system 5.

Identify the type of relay (s) used in the RTS for signal isolation by model number.

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