ML20197H832

Forwards Application for Amend to Licenses DPR-42 & DPR-60, Revising Tech Spec 3.10.G.1 to Allow Continued Operation for 72 H for Diagnosis & Repair

ML20197H832
Person / Time
Site:	Prairie Island
Issue date:	11/14/1990
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20197H838	List: ML20197H832 ML20197H840 ML20197H850
References
NUDOCS 9011200202
Download: ML20197H832 (2)

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414 Nicollet Mall Minneapolis, Minnesota 554011927 Telephone (612) 330 5500 l November 14, 1990 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PIANT L Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated November 14, 1990 Control Rod Operability Limitations Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant.

-This request is submitted in accordance with the provisions c.f 10 CFR Part 50, Section 50.90.

Prairie Island Technical Specification 3.10.G.1 currently specifies that a control rod which~cannot be moved by its drive mechanism and cannot be

. corrected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> be declared inoperable. SpecJfication L '.J.G.2 specifies that the reactor shall be brought to the_ hot shutdown condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> should more than one inoperable rod be discovered during pover operations. These current specifications do not provide adequate time for the diagnosis and repair of problems in the rod control system which render control rods electrically immovable.

+ Prairie Island Technical Specification Section 3.10.G and its associated Bases are being revised to allow continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for diagnosis and repair, with one or more control rods immovable due to an electrical problem in the rod control systera, provided all affected control rods remain trippable.

Exhibit A contains.a description of the proposed changes, the reasons for requesting the changes and the supporting safety evaluation /st.gnificant hazards determination. Exhibit B contains current Prairie Island Technical l Specification pages marked up to show the proposed changes. Exhibit C contains the revised Technical Specification pages.

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. USNRC November 14, 1990 Northem States Power Company Page 2 l

l Please contact us if you have any questions related to this License Amendment I Request, I

/' l f/ $7/W69 l Thomas M Parker  ;

Manager Nuclear Support Services j

c: Regional Administrator III, NRC  ;

NRR Project Manager, NRC i Senior Resident Inspector, NRC i MPCA ,

Attn: J W Ferman l

C Charnoff  ;

Attachments: j Affidavit Exhibit A'- Evaluation of Proposed Changes to the Technical Specifications j i

Exhibit B Proposed Changes Marked Up on Existing Technical Specification Pages  ;

Exhibit C Revised Technical Specification Pages  ;

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