ML19340D333

Application for Amend of Licenses DPR-42 & DPR-60,changing Tech Specs Re TMI Lessons Learned Category a Procedural & Equipment Requirements

ML19340D333
Person / Time
Site:	Prairie Island
Issue date:	12/19/1980
From:	Mayer L NORTHERN STATES POWER CO.
To:
Shared Package
ML19340D332	List: ML19340D331 ML19340D333 ML19340D334
References
RTR-NUREG-0578, RTR-NUREG-578 TAC-12428, TAC-12429, NUDOCS 8012300305
Download: ML19340D333 (3)

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSE NO. DPR-42 & DPR-60 (License Amendment Rec,uest Dated December 19, 1980)

Northern States Power Company, a Minnesota corporstion, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B.

Exh ibit A descri'aes the proposed changes along with reasons for the change.

Exhibit B is a set of Technical Specification pages incorporating the proposed changes.

This request contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By h.

V L 0 Mpfer Manager of Nuclear Support Services On this ((

day of

, /ffd before me a notary public in and for 'said County, phrsonally appeared L 0 Mayer, Manager of Nuclear Support Services, 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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EXHIBIT A Prairie Island Nuclear Generating Plant License Amendment Request dated December 19, 1980 Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 and DPR-60 Pursuant to 10 CFR 50.59 and 50.90, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, Technical Specifications :

TMI Lessons Learned C. tegory A Technical Specification Changes 3

PROPOSED CHANGE Revise the Technical Specifications to include the following TMI Lessons Learned Category A requirements:

a.

Functional requirements for pressurizer water level instruments, power operated relief valves (PORV's),

PORV block valves, and heaters b.

Pressurizer ?ORV, PORV block valve, and safety valve position indication c.

Inadequate Core Cooling instrumentation d.

Containment isolation diversity Auxiliary Feedwater. System initiation instrumentation and' e.

flow indicators f.

Shif t Technical Advisior g.

System Integrity Measurements Program h.

Improved Iodine Measurements Program Refer to Exhibit B for the proposed wording of these changes.

REASON FOR CHANGE These changes are being submitted at the request of the NRC Staff. They provide the Staff with assurance that the Prairie Island plant will be maintained within the limits deterrined acceptable following the imple-mentation of the TMI Lessons Learned Category "A" requirements.

The proposed changes follow the recommendations contained in a letter dated July 2, 1980 from D G Eisenhut, Director, Division of Licensing, USNRC, with the following exceptions:

t EXHIBIT A

, a.

All currently installed methods of monitoring valve position have been given equal credit in the proposed Technical Speci-fication changes for providing assurance of pressurizer PORV, PORV block valve, and safety valve position.

The model Technical Specifications provided with Mr Eisenhut's letter would require the plant to initiate a shutdown witnin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the primary indication (limit switches for the PORV's and block valves and RTD's for safety valves) are inoperable.

We believe that the Laportance of the primary position indication instrumentation has been overemphasized in the model Technical Specif ica tions.

Such severe restrictions are not warranted if secondary position indicators are operable.

b.

Proposed Technical Specification changes relating to Auxiliary Feedwater System initation and flow indication were submitted l

on December 31, 1979. This submittal satisfies the requirements j

outlined in Mr Eisenhut's letter of July 2, 1980 for the Auxiliary Feedwater System. For convenience, Exhibit B of our December 31, 1979 License Amendment Request is incorporated in this request.

c.

Proposed Technical Specification changes relating to Safety Injection initiation signals were included with our License Amendment Request dated May 6, 1980. Since these changes are also associated with the TMI Lessons Learned requirements, for convenience they are being resubmitted with this request.

d.

We believe the requirements for system integrity and improved iodine measurement programs should-be included in the Technical Specifications and not in the License. We have included them in Section 6, "Adminis trative Controls," in this change reques t.

In recent years, a number of Commission requirements have been implemented as License paragraphs.

This is not an appropriate location for detailed administrative or operating requirements.

Indeed, the original purpose of Appendix A to the License was to contain requirements of this nature.

SAFETY EVALUATION These changes add requirements to the Technical Specifications related to the TMI Lessons Learned Category A Requirements. The proposed changes are l

based on guidance provided by the NRC Staff.

Existing requirements of the Technical Specifications are not affected by these proposed changes.

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