ML20066B241
| ML20066B241 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/26/1990 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20066B244 | List: |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, NUDOCS 9101070015 | |
| Download: ML20066B241 (2) | |
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Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330 5500 December 26, 1990 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Reques, Dated December 26, 1990 Feedwater Isolation Limitations Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Ni e Generating Plant.
This request is submitted in accordance with the provtsions of 10 CFR Part 50, Section 50.90.
Generic Le tte r 89-19, " Request for Action Related to Resolution of Unresolved Safety Issue A-47", recommended that Technical Specifications for all Westinghouse plants include provisions to periodically verify the operability l
of the main feedwater overfill protection and ensure that the automatic overfill protection-is operable during reactor power operation.
Our response l
to Generic Letter 89 19, dated March 15, 1990, committed to submit a License i
Amendment Request to revise Technical Specification Table TS.3.5-4 to include limiting conditions for operations for feedwater isolation.
The NRC closeout of our response to Generic Letter 89-19, transmitted by letter dated July 17, 1990, requested that Technical Specification Surveillance Section 4.0 also be changed to require surveillance of both low l
and high steam generator water level instrumentation.
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Prairic Island Technical Specification Tables TS.3.5-4 and TS.4.1-1 are being
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revised to incorporate the feedwater isolation specifications requested by
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l Generic Letter 89 19 and the subsequent NRC closcout.
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91010700J5 901226 A 0 ()/
PDR ADOCK 05000282 P
e Northern States Power Company USNRC December 26, 1990 Page 2 l
l Prairie Island Technical Specification Table TS.4.1-1 is also being corrected to remove surveillances related to the low steam generator water level coincident with steam /feedwater mismatch reactor trip which was removed from the Technical Specifications by License Amendments Nos. 87 and 80.
Exhibit A contains a description of the proposed change, the reasons for requesting the changes and the supporti..g safety evaluation /significant hazards determination.
Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changes.
Exhibit C contains the revised Technical Specification pages.
if you have any questions related to this License Amendment Please contact us Request.
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v Thomas M Parker Manager Nuclear Support Services c:
Regional Administrator-III, NRC NRR Proj ect Manager, NRC Senior Resident Inspector, NRC MPCr\\
Attn: J W Ferman J E Silberg Attachments:
Affidavit Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages
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