ML20063C956

Forwards Application for Amend to License DPR-22,requesting Changes to TS to Require Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA

ML20063C956
Person / Time
Site:	Monticello
Issue date:	01/26/1994
From:	Richard Anderson NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20063C961	List: ML20063C956 ML20063C982 ML20063C994
References
NUDOCS 9402070264
Download: ML20063C956 (2)

Text

d' Nc +5em States Power Company ,

414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 s

January 26, 1994' ,

~i U S Nuclear Regulatory Commissior 10 CFR Part 50 Attn: Document Control Desk Section 50.90 Washington, DC 20555  :

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 License Amendment Request Dated January 26, 1994 Main Steam Isolation Valve Leak N@l Requirements Attached is a request for an amendment to the Technical Specifications, Appendix A of the Operating License for the Monticello Nuclear Generating  ;

Plant. This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.

Technical Specificati<a 3.7.A.2.b.3 currently requires that the main steam .

isolation valve leakage cate shall be limited to 11.5 SCFH (standard cubic feet per hour) when tested at 25 psi. Technical Specification Surveillance Requirement 4.7.A.2.b.5 currently specifies that main steam isolation valve leakage tests shall be conducted with gas at a test pressure greater than or ,

equal to 25 psig every 18 months. Both of these specifications represent an l exemption from the requirements of 10 CFR Part 50, Appendix J. The proposed l amendment involves changing these specifications to require the valves to be tested at a pressure greater than or equal to the calculated peak containment internal pressure related to the design basis loss-of-coolant accident, P, ( 42 psig). This change would comply with the Type C leak rate test requirements of 10 CFR Part 50, Appendix J and would therefore be consistent with the testing performed on other primary containment isolation valves. The leakage i acceptance criteria would be increased to 25.3 SCFH at 42 psig (a leak rate }

equivalent to 11.5 SCFH at 25 psig) to reflect the higher P, test pressure, ,

Exhibit A contains a description of the proposed change, the reasons for requesting the change, a Safety Evaluation, a Determination of Significant-Hazards Consideration, and'an Environmental Assessment. Exhibit B contains the current Technical Specification pages marked up with the proposed change.

Exhibit C contains revised Monticello Technical Specification pages.

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USNRC NORTHERN STATES POWER COMPANY January 26, 1994 Page 2 This submittal contains no new NRC commitments, nor does it modify any p(4.o,

' commitments. Please contact Terry Coss, Sr Licensing Engineer, at (612) s95-1449 if you require additional information related to this request. I Roger O Anderson ,

Director Licensing & Management Issues i I

c Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC State of Minnesota Attna Kris Sanda J Silberg  !

i Attachments: Affidavit to the US Nuclear Regulatory Commission Exhibit A - Evaluation of Proposed Change Exhibit B - Technical Spesification pages marked up with t proposed crenge [

Exhibit C - Revised Monticello Technical Specification Pages [

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