ML20211E820

Notice of Partial Denial of Amends to Licenses DPR-42 & DPR-60 & Opportunity for Hearing.Nrc Concluded That Portion of Licensee Request Cannot Be Granted

ML20211E820
Person / Time
Site:	Prairie Island
Issue date:	09/15/1997
From:	Wetzel B NRC (Affiliation Not Assigned)
To:
Shared Package
ML20211E780	List: ML20211E776 ML20211E790 ML20211E820
References
NUDOCS 9709300280
Download: ML20211E820 (4)

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7690-01-P i

i UNITED STATES NUCLEAR REGULATORY COMMISSION l

PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NOS.1 AND 2 DOCKET NOS. 50 282 and 50 306 NOTICE OF PARTIAL DENIAL OF AMENDMENTS TO FACILITY OPERATING LICENSES AND OPPORTUNITY FOR HEARING i

The U.S. Nuclear Regulatory Commission (the Commission) has denied a portion of a

. request by Northem States Power Company (the licensee) for amendments to Facility f

Operating Lloonses Nos. DPR 42 and DPR 60 issued to the licensee for operation of the Prairie island Nuclear Generating Plant, Unit Nos.1 and 2, located in Goodhue County, M6nnesota. Notice of Consideration of lasuance of these amendments was published in the FEDERAL REGISTER on July 2,1997 (62 FR 35850).

The purpose of the licensee's amendment request was to revise the Technical Specifications to delete limitations on crane operations in the spent fuel pool enclosure relating to spent fuel pool special ventiation system operability and conform the Technical i

i Specifications to the gu; dance of NUREG 1431, " Standard Technical Specifications, Westinghouse Plants."

l The NRC staff has concluded that a portion of the licensee's toquest cannot be granted.

The licensee was notified of the Commission's denial of the proposed change by a letter dated September 15. 1997.

- By October 20,1997, the licensee may demand a hearing with respect to the denial i

described above. Any person wtiose interest may be affected by this proceeding may file a wrMten petition for leave to intervene.

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9709300290 970915 PDR ADOCK 05000292 P

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. A request for hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention:

Rulemakings and Adjudications Staff, or may be delivoied to tt.e Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC, by the above date.

A copy of any petitions should also be sent to the Office of the General Counsel, U.S.

Nuclear Regulatory Commission, Washington, DC 20555, and to Jay Silberg, Esq., Shaw, Pittman, Potts, and Trowbridge, 2300 N Street, NW, Washington, DC 20037, attomey for the licensee.

For further details with respect to this action, see (1) the application for amendments dated May 7,1997, as supplemented May 30, July 29, and September 12,1997, and (2) the Commission's letter to the licensee dated September 15, 1997.

These documents are available for public inspection at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Was'ilngton, DC, and at the local public document room located at the Minneapolis Public Library, Technology and Science Department,300 Nicollet Mall, Minneapolis, Minnesota 55401.

Dated et Rockville, Maryland, this 15th day of September 1997.

For the Nuclear Regulatory Commission das Q Beth A. Wetzel, Senior Project Manager Project Directorate ill 1 Division of Reactor Projcets til/lV Office of Nuclear Reactor Regulation 7

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l 3.3.8 5 3.8 trn.T13ND AND FUII. MAND 11NC

&g3AA sentinued When the concentratten of beren in the spent fuel pool is less than

• required by specification 3.8.R.2.a. immediate action must be taken to preclude the occurrence of an accident or to mitigate the consequences of an accident in progress. 2his is most efficiently achieved by immediaraly suspending the movement of fuel assemblies. The concentr'ation of boren is restored simultaneously with suspending movement of fuel assemblies. The suspension of fuel movement is not intended to preclude movement of a fuel assembly to a safe posf tien.

Rafarancas

1. USAR, Section 10.2.1.2 2.

USAR, Section 14.5.1 3.

USAR, Section 10.3.7 4

' Criticality Analysis of the Prairie Isla.d Units 1 & 2 Fresh and Spent Fuel Racks' Westinghouse Commercial Nuclear Fuel Division, February 1993.

3. WCAF 14416 NF.A, ' Westinghouse Spent Fuel Esek Criticality Analysis Methodology *, Revision 1. Novenbar 1996.

6.

American Nuclear Society, 'American National standard Design Requirements for 1.ight Water Reactor Fuel Storage Facilities at 1

Nuclear Fower Plants", AN$1/ANS.57.21983, October 7, 1983.

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Nuclear Regulatory Commission, latter to All Power Reactor 1.icensees from 3. R. Crimes '07 Position for Review and Acceptance of Spent Fuel Storage and Mandling Applications", April 14, 1978.

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' Northern States Power Frairie Island Units 1 and 2 Spent Fuel Rack Criticality nalysis Using Soluble Soron Credit', Westin& ouse h

Commercial Nuclear Fuel Division, February 1997.

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Safety Rvaluation 50 475,

• spent Fuel Peel Personnel Acoass Doors.'

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1Yairie Island Unit 1 Amendment M M 129 Prairie Island Unit 2 Amendment.lef, M 121 4

Revised by NRC letter, dated Septembe'r 15,1997 "4'

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o 3.0 trWIUNC AMD FETL MAND 11Mc laana sentinued when the une.ntration of boren in the pent ful voel is less than

• required by Speciftsation 3.8.3.2.a. Lamediate action put be taken te preclude the occurrence of an accident er to sitigate the sensequensas of an accident in progress. This is most efficiently achieved by immediately suspending the mevosent of fuel asseabites. The sencontratten of beren is restored simultaneously with suspending movement of fuel assemblies. N suspensten of fuel nevement is not intended to Preclude movement of a fuel assembly to a safe positten.

Rafaranens

1. WSAR, Sostion 10.2.1.2

2. W8AR, Section 14.5.1

3. t$AR Section 10.3.7 A.

' Criticality Analysis of the Prairie Island Unita 1 & 2 Fresh and Spent Fuel Racks', Westinghouse Commercial Nuclear Fuel Division.

February 1993.

5. WCAP.16416.NF.A Westinghouse Spent Fuel Rack Criticality Analysis Methodelegy*, Revision 1. Novoaher 1996.

6.

American Nuclear Society, *American National Standard Design kequirements for Light Water Rasetor yuel storaSe Facilities at Walear Power Plants', AN81/ANs.57.21983, October 7, 1983.

7.

Nuclear Regulatory Commission, Lstter to All Power Reactor Licensees from 3. R. Crimes, 'OT Position for Review and Acceptance of Spent Fuel Storage and Mandling Applications' April 14, 1978.

8.

Verthern States Power Prairie Island Units 1 and 2 Spent Fuel Rack Criticality Analysis Using Soluble Seren Cred!t*, Westinghouse Cosmarcial Nuclear Fuel Divisien, February 1997.

9.

Safety Evaluatten 50 475,

• Spent Fuel Post Personnel Aspas Seers.'

l Finirie Island Unit 1

/Frairie Island Unit 2 Amendment JO5", g, 129 Amendoent.30f,Jt7,121 Revised by NRC letter dated Septembe'r 15,' 1997

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