ML20107G218
| ML20107G218 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/17/1996 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9604230148 | |
| Download: ML20107G218 (6) | |
Text
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch. Minnesota 55089 April 17,1906 Generic Letter 96-01 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to Generic Letter 96-01, Testing of Safetv-Related Logic Circuits This letter is in response to Generic Letter 96-01: Testing of Safety-Related Logic Circuits. The Generic Letter requests a written response within 60 days indicating our intentions with respect to the actions requested in the letter. Our intentions are discussed in an attachment to this letter, in this letter we have made the following new Nuclear Regulatory Commission 1
commitment:
We will complete the requested actions of the Bulletin to the schedule outlined in Section D of the attached response.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
/}b lOe0 Ate Michael D Wadley Plant Manager Prairie island Nuclear Generating Plant c: (see next page) 23000G 9604230148 960417 I
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- USNRC NORTHERN STATES POWER COMPANY April 17,1996 Page 2 c:
Regional Administrator - Region lil, NRC Senior Resident inspector, NRC NRR Project Manager, NRC J E Silberg Attachments:
- 1. Affidavit
- 2. Response to Generic Letter 96-01 4
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GL9601,0. DOC 4
i UNITED STATES NUCLEAR REGULATORY COMMISSION l
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 1
50-306 GENERIC LETTER 96-01, TESTING OF SAFETY-RELATED LOGIC CIRCUlTS Northern States Power Company, a Minnesota corporation, with this letter is submitting information requested by NRC Generic Letter 96-01.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY (b( 04 BY i AL Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant k
On this N day of M @/
I before me a notary public in and for said County, petsonally appeire( Michael D Wadley', Plant Manager, Prairie Island Nuclear Generating Plant; and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge,information, and belief the sta ents made in it are true and that it is not interposed for delay.
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RESPONSE TO GENERIC LETTER 96-01 From Generic Letter 96-01:
Requested Actions The NRC staff requests that all addressees take the following
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actions:
(1)
Compare electrical schematic 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 surveillance test procedures to ensure that all portions of the logic circuitry, including the parallel logic, interlocks, bypasses and inhibit circuits, are adequately covered in the surveillance procedures to fulfill the TS requirements. This review should also include relay i
contacts, control switches, and other relevant electrical i
components within these systems, utilized in the logic circuits performing a safety function.
(2)
Modify the surveillance procedures as necessary for complete j
testing to comply with the technical specifications.
Additionally, the licensee may request an amendment to the te-hnical specifications if relief from certain testing i
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.
i Responses to the Reauested Actions:
I A.
Coordinated review for GL 96-01 and improved Technical Specifications The Prairie Island Nuclear Generating Plant has begun a project to upgrade the current Custom Technical Specifications to Improved Technical Specifications (ITS).
l This conversion is based on the Standard Technical Specifications for Westinghouse Plants, NUREG-1431. Our present schedule is to submit the Technical Specification conversion package to the NRC in June of 1997, with implementation planned for April of 1998.
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Per a discussion held with the NRC staff on April 2,1996, the response to GL 96-01 will be coordinated with the development of the Prairie Island ITS. As such, the
April 17,1996 Page 2 j
reviews performed in response to GL 96-01 will be based on the ITS rather than the current Technical Specifications.
B.
Review of drawings and surveillance procedures Per GL 96-01, " Requested Actionf ::ection, paragraph (1), Prairie Island staff will compare the plant's electrical schematic drawings and logic diagrams for the reactor protection system, Emergency Diesel Generator load shedding and sequencing, and 3
actuation logic for the engineered safety features systems against plant surveillance test procedures.
This comparison will ensure that the safety function portions of these systems' logic circuitry, including the parallel logic, interlocks, bypasses and inhibit circuits, are adequately covered in surveillance procedures to fulfill the ITS surveillance testing requirements applicable to Prairie Island.
This review will include relay contacts, control switches, and other relevant electrical components within these systems, utilized in the logic circuits performing a safety function.
C.
Actions to be taken if inadequate testing is found If, during the course of this review, a component is found be inadequately tested under an applicable ITS requirement, Prairie Island will review existing technical specifications for testing adequacy.
Operability determinations and required actions will be based upon existing Prairie Island technical specifications.
D.
Schedule Per GL 96-01, " Requested Actions" section, paragraph (2), Prairie Island staff will complete the Unit 2 systems reviews and revise surveillance procedures as necessary to comply with existing Prairie Island technical specifications prior to start-up from the next Unit 2 refueling outage. The next Unit 2 refueling start-up is presently scheduled for 2/24/97.
Per GL 96-01, " Requested Actions" section, paragraph (2), Prairie Island staff will complete the Unit 1 and shared unit systems reviews and revise surveillance procedures as necessary to comply with existing Prairie Island technical GL9601_0. DOC
April 17,1996 Page 3 Island technical specifications prior to start-up from the next Unit 1 refueling outage.
- The next Unit 1 refueling start-up is presently scheduled for 10/18/97.
Surveillance procedure revisions for ITS will be completed per the ITS Implementation schedule.
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GL9401.0. DOC