ML20107G605
| ML20107G605 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/17/1996 |
| From: | Hill W NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9604230288 | |
| Download: ML20107G605 (5) | |
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Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362 9637 April 17,1996 Generic Letter 98-01 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR 22 initial Response to NRC Generic Letter 96-01:
"Testino of Safetv-Related Loalc Circuits" NRC Generic Letter 96-01," Testing of Safety Related Logic Circuits," issued January 10, 1996, provided licensees notification of problems with testing of safety-related logic circuits.
The generic letter requests licensees to perform a review of logic circuit testing for the reactor protection system, emergency diesel generator load shedding and sequencing, and engineered safety features actuation logic to ensure such testing fulfills plant technical specification requirements.
Required response item (1) of the generic letter requested an initial response within 60 days of the date of the genericletter. By letter dated February 14,1996 the NRC staff extended the submittal date for the initial generic letter response to 30 days from the date of the industry workshop held on March 19,1996, conceming this issue. Attachment A of this submittal provides Monticello's response to Required Response item (1) of the generic letter. This letter contains the following new NRC commitment:
1.
Monticello willimplement the requested actions of NRC Generic Letter 96-01.
The review of logic circuit testing, as well as any required procedure modifications resulting from the review, will be completed prior to startup from the 1998 Monticello refueling outage.
Please contact Mary Engen, Sr Licensing Engineer, at (612) 295-1291 if you require further information.
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William J Hill P8' Manager Mu ticello Nuclear Generating Plant 9604230280 960417 PDR ADOCK 05000263 P
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USNRC-NORTHERN STATES POWER COMPANY
' A'pril 17,' 1996 Page 2 1
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Regional Administrator - 111, NRC i
NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota, Attn: Kris Sanda Attachments: Affidavit to the US Nuclear Regulatory Commission (A)
Monticello initial Response to NRC Generic Letter 96-01 4
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i UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 INITIAL RESPONSE DATED April 17,1996 TO NRC GENERIC LETTER 96-01:
" TESTING OF SAFETY-RELATED LOGIC CIRCUlTS" Northern States Power Company, a Minnesota corporation, hereby provides the required initial response to NRC Generic Letter 96-01," Testing of Safety Related Logic Circuits." This letter contains no restricted or other defen::e information.
NORTHERN STATES POWER COMPANY
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By William JHill' Plant Manager Monticello Nuclear Generating Plant On this INday of A e 4 i99 0 before me a notary public in and for said County, personally appedred William J Hill, Plant Manager, Monticello 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 statements made in it are true and that it is not interposed for delay.
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IWMNNCHMDM Marvin R Engen/
sormwpuma.m Notary Public - Minnesota comae m.m Sherbume County My Commission Expires January 31,2000 1
o Attachment A Monticello initial Resoonse to NRC Generic Letter 96-01 Reauested Actions The NRC staff requests that all addressees take the following actions:
(1)
Compare electncal schematic drawings and logic diagrams for the reactor protection system, EDG Ioad 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 circuitty, including the parallel logic, interlocks, bypasses and inhibit circuits, are adequately covemd in the surveillance procedures to fulfill the TS requirements. This review should also include relay contacts, control switches, and other televant electncal components within these systems, utilizedin the logic circuits performing a safety function.
(2)
Modify the surveillance procedures as necessary forcomplete testing to comply with the technical specifications. Additionally, the licensee may request an amendment to the technical specifications if relief from certain testing taquirements can bejustified.
It is requested the completion of these actions be accomplished pdor to startup from the first refueling outage commencing one year after the issuance of this genedc letter.
Reauired Response AII addressees, including those who have already completed the requested actions, are required to submit a wntten response to this genedc letter as follows:
(1)
Within 60 days of the date of this genedc letter, a written response indicating whetherornot the addressee willimplement the actions requested above. If the addressee intends to implement the requested actions, submit a schedule for completing implementation. If an addmssee chooses not to take the requested actions, submit a descnption of any proposed attemative course of action, the schedule for completing the attemative course of action (if applicable), and the safety basis for determining the acceptabi!!ry of the planned attemative course of action.
Monticello Response Monticello willimplement the requested actions of NRC Generic Letter 96-01. The review of logic circuit testing, as well as any required procedure modifications resulting from the review, will be completed prior to startup from the 1998 Monticello refueling outage. The Monticello 1998 refueling outage is scheduled to commence in January of 1998 and is the first refueling outage to commence one year after the date of issuance of the generic letter.
Attachm:nt A
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April 17,1996 Page 2 The requested review will be performed for the actuation logic for the reactor protection system, emergency diesel generator load shedding and sequencing, and for the engineered safety features systems (ESFs). The ESFs to be included in this review are based on those specified in the Monticello USAR, Section 6.1. The review will ensure that all portions of the actuation logic circuit required for performance of required safety functions are adequately addressed in the plant surveillance procedures to meet Monticello Technical Specification requirements.
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