BSEP-96-0136, Submits Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits

Submits Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits

ML20107H771
Person / Time
Site:	Brunswick
Issue date:	04/18/1996
From:	Campbell W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-96-0136, BSEP-96-136, GL-96-01, GL-96-1, NUDOCS 9604240216
Download: ML20107H771 (5)

Text

e a a---as o CP&L Carolina Power & Light Company William R. Campbell PO Box 10429 Vice President '

Southport NC 28461 0429 Brunswick Nuclear Plant )

, SERIAL: BSEP 96-0136

! April 18,1996 I

United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 i l

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 l DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 l RESPONSE TO THE NRC GENERIC LETTER 96-01, " TESTING OF SAFETY-RELATED LOGIC 1 CIRCUlTS" l Gentlemen:

On January 10,1996, the NRC issued Generic Letter (GL) 96-01, " Testing of Safety-Related Logic Circuits." The generic letter notified addressees regarding problems with testing of safety-related logic circuits, requests that addressees implement the actions described therein, and requires addressees to submit within 60 days of the date of the i generic letter a written response regarding the implementation actions. The NRC's i February 14,1996 letter extended the GL 96-01 response submittat date to no later than April 18,1996, based on the March 19,1996 Nuclear Energy Institute (NEI) workshop.

CP&L agrees to perform the requested actions as restated in the Enclosure 1.

Please refer any questions regarding this letter to Mr. George Honma at (910) 457-2741.

Sincerely, e

William R. Campbell GMT/gmt l

Enclosure:

1. Response 24 0 053ist of Reguiatory Commitments 0 6[

% P Tel 910 457 2496 Fax 910 457 2803

Document Control Desk BSEP 96-0136 / Pags 2 William R. Campbell, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, and agents of Carolina Power & Light Company.

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My commission exp!res: b ;j$g s

cc: Mr. S. D. Ebr eter, NRC Regional Administrator, Region il Mr. C. A. Patterson, NRC Senior Resident inspector - Brunswick Plant Mr. D. C. Trimble, Jr., NRR Project Manager - Brunswick Plant The Honorable H. Wells, Chairman - North Carolina Utilities Commission l

ENCLOSURE 1

. BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR 62 RESPONSE TO THE NRC GENERIC LETTER 96-C 1,

" TESTING OF SAFETY-RELATED LOGIC CIRCUITS' Reauested Actions CP&L's Brunswick Steam Electric Plant, Unit Nos.1 and 2 plan to implement the requested actions of Generic Letter (GL) 96-01 as described in the following:

A. NRC Reauested Actions

1. Compare electricalschematic drawings and logic diagrams for the reactor protection system, EDG load shedding and sequencing, and actuation logic for the engineered safety features systems against plant surveiHance test procedures to ensure that auportions of the logic circuitry, including the paraHetlogic, interlocks, bypasses and inhibit circuits, are adequately coveredin the surveiHance procedures to fulfiH the TS requirements. This review should also include relay contacts, control switches, and other relevant electricalcomponents within these systems, utilized in the logic circuits performing a safety function.

2. Modify the surveiHance procedures as necessary for complete testing to comply with the technicalspecifications. AdditionaHy, the licensee may request an amendment to the technical specifications if relief from certain testing requirements can be justified.

It is requested the completion of these actions be accomplished prior to startup from the first refueling outage commencing one year after the issuance of this generic letter.

Remainina NRC Reovired ResDonse.

Within 30 days of completion of the requested actions, a response confirming completion.

_Q.P&L Response CP&L will undertake a program to implement the above stated NRC Requested Actions. Surveillance procedures identified as needing revision will be modified as necessary to comply with technical specifications or if appropriate, an amendment to technical specifications will be submitted. These actions will be completed prior to startup from the first refueling outage commencing one year after the issuence of GL 96-01. These outages are, the Unit 2 outage (B213R1) scheduled for the 3rd Quarter of 1997, and the Unit 1 outage (B112R1) scheduled for the 2nd Quarter of 1998.

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l Within 30 days of completion of the NRC Requested Actions on both Units, a response will confirm the completion of the above actions.

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• ENCLOSURE 2

, . . BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & CPR 62 RESPONSE TO THE NRC GENERIC LETTER 96-01,

" TESTING OF SAFETY-RELATED LOGIC CIRCUITS" LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light Company in this document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this  !

document or any associated regulatory commitments. ,

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l Committed '

Commitment date or outage

1. CP&L will undertake a program to implement the above stated U-1 B112R1 NRC Requested Actions. Surveillance procedures identified as needing revision will be modified as necessary to comply with U-2 B213R1 technical specifications. These actions will be completed prior to startup from the first refueling outage commencing one year after the issuance of GL 96-01.

2. Within 30 days of completion of the NRC Requested Actions on N/A both Units, a response will confirm the completion. j l

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