ML20236L519

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing High Flux,Power Range Monitor,Low Setpoint.Fee paid.NSPNAD-8725, Analysis of Revised Low Setpoint for High Flux,Power Range, Also Encl

ML20236L519
Person / Time
Site:	Prairie Island
Issue date:	11/03/1987
From:	Musolf D NORTHERN STATES POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20236L521	List: ML20236L519 ML20236L528 ML20236L544 ML20236L589
References
NUDOCS 8711100389
Download: ML20236L519 (3)

Text

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• ' 1 ' Northern States Power Company l i

414 Nicollet Mall ~ ]

Minneapohs, M nnesota 55401

'l Telephone (612) 330 5500 j November 3, 19.87 ~!

10 CFR Part 50  !

,Section 50.90 1 Director Office 'of Nuclear Reactor Regulation Attn: Document Control Desk U S Nuclear Regulatory Commission Washington, D C. 20555, FRAlRIE' ISLAND NUCLEAR GENERATING PLANT, Docket Nos, 50-282 License Nos. DPR-42 50-306 DPR-60 i License Amendment Request- Dated November .3, 1987 .j High Flux, Power Range Monitor, Low Set Point :q Attached is a request for a change of Technical Specifications, Appendix q A, of the Operating ~ Licenses, for the Prairie Island Nuclear Generating j Plant. This request is submitted in accordance with the, provisions of 10 j CFR Part 50, Section 50.90.

A check is attached in the amount of $150.00 j' in accordance with 10 CFR Part 170 for the amendment application fee.'

Exhibit'A describes the proposed changes, provides the reasons for the i changes, and provides the supporting safety evaluation /significant hazards evaluation. Exhibit B describes the proposed wording changes to the Technical Specifications. Exhibit C contains the revised Technical ' #

i Specification page.

This amendment request is based on an evaluation performed by the Northern States Power Nuclear Analysis Department (NSPNAD).. The results  ;

of this evaluation are contained in NSPNAD Report No. 8725 " Analysis of the Revised Low Setpoint for High Flux, Power Range", October, 1987. A copy of NSPNAD-8725 is attached as Exhibit D.

It is requested that these changes be reviewed and approved by the NRC Staff prior to the next startup following refueling, currently scheduled for Unit 2 Cycle 12, in February,1988.

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, EXHIBIT A i

By changing the Technical Specification limit to lui actual power of 40% <

the trip set point can remain at a nominal setting' of 25C of indicated power and future Technical Specification violations will not' occur. H Eafetv Evaluation and Determination of Significant '

Hazard Considerations ,

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The proposed change to the Operating Licenso has been evaluated to' ,

determine whether it constitutes a significant hazards consideration as i

required by 10 CFR Part 50, Section 50.91 using standards provided in J Section 50.92. This analysis is provided below:  ;

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1. The proposed amendment will not involve a significant increase in R the probability or consequences of an accident previously evaluated.

The high flux, power range low set point is used in both the Uncontrolled RCC Assembly Withdrawal from a Subcritical Position analysis and a Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection) analysis. Both analyses have been reanalyzed to verify the  !

acceptability of the proposed high flux, power range low set point.  ;

The analyses are summarized in Exhibit D (NSPNAD-8725, " Analysis of the Revised Low Setpoint for High Flux, Power Range", October 1987).

The report contained in Exhibit D was prepared by Northern States Power Company personnel using methods approved by the NRC Staff in a l

Safety Evaluation Report dated July 14, 1986. The changes requested by the Staff in the Safety Evaluation Report have been incorporated and are being implemented in NSPNAD-8102, Revision 5. The analyses performed cover both the Westinghouse OFA fuel assemblies and ENC TOPROD assemblies which are the fuel types used at Prairie Island.

Since the proposed high flux, power range low set point has been analyzed utilizing approved and previously applied methods and has been found to be acceptable, this change will not involve a l

' significant increase in the probability or consequences of an accident previously evaluated.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed.

This is only a change in the limiting high flux., power range low set point. The trip set point will remain at nominally 25% of rated power. This change provides a margin between the trip set point and L the limiting set point used in transient' analyses. Applicable safety analyses have been reanalyzed, meeting all acceptance criteria. All instrumentation which monitors the high flux, power range low set point will remain the same. No physical changes are being made to the plant, fuel types being utilized or procedures used for startup.

For these reasons, the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed.

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1 D'irector of NRR Nodhem States Power Company November,3, 1987 Page 2 Please contact us if you have any questions related to this request.

D O.,k-David Musolf  ;

Manager - Nuclear Suppor Services l

DMM/ TAP / tap c: Regional Administrator - Ill,.NEC NRR Project Manager, NRC <

Resident Inspector, NRC -

MPCA (State Contact)

Attn: Dr J W Ferman G Charnoff-

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Attachments:

Affidavit and Check for $150,00 to the U S Nuclear Regulatory Commission j Exhibit A - Evaluation of Proposed Changes to the Technical Specifications j Exhibit 3 - Proposed Changes Marked-Up on Existing Technical Specification l Pages

! Exhibit C - Revised Technical Specification Pages Exhibit D - NSPNAD-8725, " Analysis of the Revised Low Setpoint for High i

) Flux, Power Range", October, 1987, I

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