ML20064J919

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Forwards Application for Amend to Licenses DPR-42 & DPR-60, Consisting of Changes to Tech Specs Re Overtime Allowed for Individuals Working at Plant.Submittal Addresses All Items in Generic Ltr 82-16
ML20064J919
Person / Time
Site: Prairie Island  
Issue date: 01/14/1983
From: Musolf D
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20064J924 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.2.08, TASK-2.K.2.13, TASK-2.K.3.03, TASK-2.K.3.12, TASK-TM GL-82-16, NUDOCS 8301180246
Download: ML20064J919 (2)


Text

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Northem States Power Company 414 Ncollet Matt Minneapohs. Minnesota 55401 Telephone (612) 330 5500 January 14, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated January 14, 1983 Response to NRC Generic Letter 82-16 dated September 20, 1982 Attached are three originals and 37 conformed copies of a request for a change of Technical Specifications, Appendix A, of Operating Licenses DPR-42 and 60.

Also attached is one copy of the License Amendment class determination and a check in the amount of $1,600 for the amendment fee.

This request contains an addition to Section 6.1 of the Technical Specifications regarding the overtime allowed for individuals working at the plant. With this submittal, all items in NRC Generic Letter 82-16 have been addressed:

1. STA Training (I.A.l.l.3)

Your Septraber 20, 1982 letter still identifies this as an open item pending a decision by the Commission.

2. Limit Overtime (I.A.l.3)

A license amendment request reflecting NSP position is included with this letter.

3. Short Term Auxiliary Feedwater System (II.E.1.1)

The letter f rom NRC to NSP dated March 27, 1982, "NRC Letter and Safety Evaluation Report NUREG-0737, Items II.E.1.1 and II.E.1.2, Evaluation of Prairie Island Auxiliary Feedwater Systems", contained the resolution of this item.

No additicaal Technical Specificaiton changes are required in eddition to those requested in our September 14, 1982 submittal.

4. Safety Grade AFW System Initiation and Flow Indication (II.E.1.2)

Same as item 3

5. Dedicated Hydrogen Penetrations (II.E.4.1)

Prairie Island is installing an internal recombiner system in each unit.

Each unit is also provided with a purge and vent combustible gas control system with dedicated penetrations. Testing of these renetrations is required by the Technical Specifications. Your letter dated June 1, 1982 confirmed your acceptance of the Prairie Island Nuclear Generating Plant design with respect to the dedicated hydrogen control penetrations.

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NORTHERN OTATE.C3 POWER COMPANY Director of NRR Ja'nuary 14, 1983 Page 2

6. Containment Pressure Setpoint (II.E.4.2.5)

The letter from NRC to NSP dated December 2,1981, "TMI Task Action Plan, Item II.E.4.2(5) Containment Pressure Setpoint Prairie Island Units 1 & 2" resolved the issue. No Techncial Specification changes are required.

7. Containment Purge Valve (II.E.4.2.6)

A license amendment request was submitted on October 29, 1982 which addressed this issue.

8. Radiation Signal on Purge Valves (II.E.4.2.7)

Prairie Island already has this requirement in their Technical Specifications in Table TS 3.5-4.

9. Upgrade B&W AFW System (II.K.2.8)

This item is not applicable to Prairie Island.

11. B&W Thermal-Mechanical Report (II.K.2.13)

This item is not applicable to Prairie Island.

12. Reporting SV and RV Failures and Challenges (II.K.3.3)

A license amendment request was submitted on September 14, 1982.

13. Anticipatory Trip on Turbine Trip (II.K.3.12)

Prairie Island already has this requirement in their Techncial Specifications in TS 3.5-2 and Table TS 4.1-1.

Exhibit A describes the proposed change, reason for change, and the safety evaluation. Exhibit B contains the revised Appendix A pages. Please contact us if you have any questions concerning this License Amendment Request.

D gMusolf%

Divi Manager - Nuclear Sup o t Services DMM/SAF/bd cc: Regional Administrator, NRC NRR Project Manager, NRC NRC Resident Inspector G Charnoff