ML20065S757

Application for Amend to Licenses DPR-42 & DPR-60 Consisting of Changes to Tech Specs Re Containment Sys,Refueling & Fuel Handling,Snubbers,Event Monitoring Instrumentation & ESF

ML20065S757
Person / Time
Site:	Prairie Island
Issue date:	10/29/1982
From:	Musolf D NORTHERN STATES POWER CO.
To:
Shared Package
ML20065S748	List: ML20065S746 ML20065S757 ML20065S759
References
REF-GTECI-B-24, REF-GTECI-EL, REF-GTECI-ES, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-B-24, TASK-B-24-.2, TASK-OR, TASK-TM NUDOCS 8211020005
Download: ML20065S757 (4)

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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 NOS. DPR-42 & DPR-60 (License Amendment Request Dated October 29, 1982)

Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B. Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is a set of Technical Specification pages incorporating the proposed changes.

This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By Dd A, David Musolf h Manager - Nuclear Support ServiYes On this ,N day of n , / N M before me a notary public in and for said County, personally appeared David Musolf, Manager - 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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, BETTY J. DEAN -

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9 EXHIBIT A Prairie Island Nuclear Generating Plant License Amendment Request Dated October 29, 1982 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-6Q hereby propose ,the following changes to Appendix A, Technical Specifications:

1. Specification: Containment System TS 3.6 & Table TS.4.4-1 PROPOSED CHANGE

, The Technical Speifications on page TS 3.6-2 and Table TS.4.4-1 are to be revised as noted 'in Exhibit B.

REASON FOR CHANGE These changes revise the Technical Specifications as required by the NRC Staff Safety Evaluation Report dated Spetember 9, 1982,

" Completion of Containment Purge Generic Issue B-24 NUREG-0737 I

Item II.E.4.2 - Prairie Island Unit Nos. 1 and'2."

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Double gasketed blind flanges will be installed on both the normal '

and the inservice purge systems to eliminate the potential for valve leakage during normal operation.' Debris screens are being installed on the inservice purge system penetrations. This system may be used during plant operation following verification of valve leak tightness. The system will be used only when required for safe plant operation.

! SAFETY EVALUATION Refer to the NRC Staff Safety Evaluation Report dated September 9, 1982.

i 2. Specification: Refueling and Fuel Handling TS

3.8 PROPOSED CHANGE

An explanation is' added to the basis to clarify the intent of Specification 3.8. A.7. The words "when the cavity is being i drained for head replacement" were deleted from the specification.

See Exhibit B.

{ The typographical error in the word " head" was corrected.

i The basis used the words "adsorber" and " absorber" interchangeably

!. in discussing charcoal efficiency testing. All were changed to i adsorber-for accuracy.

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REASON FOR CHANGE A clarification was needed to remove confusion in interpreting TS.3.8.A.(7).

Typographical errors cre corrected.

SAFETY EVALUATION ,

1 None required.

3. Specification: TS 3.12 Snubbers PROPOSED CHANGE Additions, deletions, and corrections to table TS.3.12-1 Safety Related Snubbers.

REASON FOR CHANGE To maintain the table current as modifications are completed and to correct errors.

SAFETY EVALUATION

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Any snubber addition or removal is evaluated in accordance with the design change and Work Request Authorization processes.

4. Specification: TS 3.15 Event Monitoring Instrumentation PROPOSED CHANGE Changes to TS.3.15, Table TS.4.1-1 and the addition of a new table TS.3.15-2 for radiation event monitoring instrumentation.

See Exhibit B.

REASON FOR CHANGE This change provides limiting conditions for operation and surveillance requirements for plant modifications implementing NUREG-0737 Items II.F.1.1 and II.F.1.2.

SAFETY EVALUATION These radiation monitors assist the operator to assess the extent of an accident.

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5. Specification: TS 4.5 Engineer'ed Safety Feature PROPOSEDiCHANGE I Revise TS 4.5.A.5(b) to read.."At least once every 18 months, subject each diesell angine.to a thorough inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service".

REASON FOR CHANGE 4

To clarify the inspection interval. Prairie Island plant has two refuelings each year and.the existing wording does not identify which refueling outage requires the engine inspection.

l' SAFETY EVALUATION The philosophy which applies to diesel generator inspection.also applies to the inspections of the diesel cooling water engine.

The 18-month inspection interval is adequate to insure these engines are well maintained without 'oeing out of service unnecessarily. The surveillances .being performed to satisfy TS i requirements 4.5.A.5(a) and 4.5.B.I (b) give early indication of problems with the diesel engines.

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