ML20236D261

Requests Fr Publication of Notice of Consideration of Issuance of Amend to License DPR-45 & Proposed NSHC Determination & Opportunity for Hearing on 870617 Request Re Tech Spec Rev Concerning Reactor Shutdown & Defueling

ML20236D261
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/23/1987
From:	Berkow H Office of Nuclear Reactor Regulation
To:	NRC
References
NUDOCS 8707300382
Download: ML20236D261 (4)

Text

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[9 'o UNITED STATES

.! ' 3, ( Igo NUCLEAR REGULATORY COMMISSION o a $ WASHINGTON, D. C. 20555

%,..u.../ July 23, 1987 MEMORANDUM FOR: Sholly Coordinator FROM: Herbert N. Berkow, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects

SUBJECT:

REQUEST FOR PUBLICATION IN BI-WEEKLY FR NOTICE - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR A HEARING Dairyland Power Cooperative, Docket No. 50-409, Lacrosse Boilina Water Reactor, Lacrosse, Wisconsin Date of amendment request: June 17, 1987 Description of amendment request: The licensee proposes that License No.

DPR-45 for the permanently shutdown and defueled Lacrosse Boiling Water Reactor (LACBWR) be amended to: (1) revise the Technical Specifications (TS) to state that' the reactor will not be operated; (2) delete TS requirements for reactor nuclear instrumentation channels to be in operation; and (3) delete TS requirements to perform inservice inspection of high pressure primary systems and the TS requirement to use NUREG-0313, Revision 1, to govern repair and -

replacement of piping.

Basis for proposed no significant hazards consideration d. termination: The C%nission has provided standards for detennining whether a s:,#ficant hazards consideration exists (10 CFR 50.92(c)). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation and/or maintenance of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; cc(3)involveasignificantreductioninamarginofsafety.

S707300382 870723 PDR ADOCK 05000409 P PDR

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The licensee has evaluated the proposed changes with respect to 10 CFR 50.92(c) and has determined that the proposed amendment would not:

1) involve a significant increase in the probability or consequences of an accident previously evaluated. Removing the TS reference to reactor operation is strictly an administrative change to support the previously proposed license amendment for possess-but-not-operate status. Eliminating the requirement to keep a nuclear instrumentation channel in operation will have no effect on accident probability or consequences, since the reactor has been permanently shut down and defuelea. Terminating inspection of piping that will no longer be used as a pressure boundary and inspection of components which will no l longer be utilized cannot increase the probability or consequences of an accident, since there will be no significant adverse consequences if these components fail. Additionally, removing requirements dealing with NUREG-0313, which applies to BWR Coolant Pressure Boundary piping above 200 F, will have no effect on the probability or consequences of an accident, since the plant will not be in the condition for which the NUREG was written;

2) create the possibility of a new or different kind of accident from any accident previously evaluated. Non-operation of the reactor will not create the possibility of a new type of accident. Eliminating the need to monitor a defueled reactor with nuclear instrumentation cannot cause a new type of accident because there is nothing for the instrumentation to monitor.

Terminating inspection of piping and components not required to be operable cannot cause a new type of accident, since unneeded piping and components pose no new accident threat; or

3) involve a significant reduction in a margin of safety. Cessation of plant operation will not cause a reduction in the margin of safety since the

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margin of safety relates to plant operation. Eliminating neutron monitoring of a reactor with no fuel assemblies in it cannot reduce the margin of safety.

Termination of inservice inspection of unused primary system piping and components and of related systems will have no effect on the margin of safety. 1 Deletion of requirements pertaining to NUREG-0313 will have no effect on the I margin of safety, since the primary system is in a cold shutdown status and the NUREG applies to a reactor coolant pressure boundary above 200 F.

Based on the above, the licensee has determined that the proposed amendment does not involve a significant hazards consideration. The NRC staff has l

reviewed the licensee's no significant hazards consideration determination and )

agrees with the licensee's analysis. Accordingly, the Commission proposes to determine that the requested amendment does not involve a significant hazards considera t' ion.

Local Public Document Room location: Lacrosse Public Library, 800 Main Street, Lacrosse, Wisconsin 54601.

Attorney for licensee: Kevin Gallen Esquire, Newman and Holtzinger,1615 L -

l Street, N.W., Washington, D.C. 20036 NRC Project Director: Herbert N. berkow

.f JW erbert N. Berkow, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, i V and Special Projects 1

i

'~~', July 23, 1987 margin of safety relates to plant operation. Eliminating neutron monitoring of a reactor with no fuel assemblies in it cannot reduce the margin of safety.

' Termination of inservice inspection of unused primary system piping and components and of related systems will have no effect on the margin of safety.

Deletion of requiNments pertaining to NUREG-0313 will have no effect on the margin of safety, since the primary system is in a cold shutdown status and the NUREG applies to a reactor coolant pressure boundary above 200'F.

Based on the above, the licensee has determined that the proposed amendment does not involve a significant hazards consideration. The NRC staff has reviewed the licensee's no significant hazards consideration determination and agrees with the licensee's analysis. Accordingly, the Commission proposes to determine that the requested amendment does not involve a significant hazards consideration.

Local Public Document Room location: Lacrosse Public Library, 800 Main Street, Lacrosse, Wisconsin 54601.

Attorney for licensee: Kevin Gallen, Esquire, Newman and Holtzinger, 1615 L Street, N.W., Washington, D.C. 20036 NRC Project Director: Herbert N. Berkow he#ga}!,s U

r gg,y Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects DISTRIBUTION:

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