ML20217P128
| ML20217P128 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/02/1998 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217P134 | List: |
| References | |
| NUDOCS 9803100053 | |
| Download: ML20217P128 (3) | |
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Northern states Power Company 1717 Wakonade Dr. E.
Welch, MN 55089 Telephone 612-388-1121 March 2,1998 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-80 Supplement 6 to License Amendment Request Dated December 14,1995 Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Specifications Pursuant to discussions with the NRC Staff, current Technical Specification requirements for reporting challenges to pressurizer power operated relief valves and safety valves have been incorporated into the reporting requirements for the proposed amendments to Technical Specifications Chapter 6. In accordance with the bracketed guidance shown in NUREG-1431, these challenges will be reported with the monthly operating reports. Attachment 1 shows these proposed changes marked up on page TS.6.0-13 (some material is moved to page TS.6.0-14). contains these Technical Specification pages revised to their final
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l form to reflect the changes proposed by this supplement.
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Also, nttachment 3 is included for your convenience. It lists all of the pages which h,j/
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are affected by this proposed License Amendment and identifies the source document associated with this proposed License Amendment.
This License Amendment Request proposes to relocate some current Technical Specification requirements to other documents. Attachment 4 lists requirements which have been or will be relocated to other documents. Those specifications which contain action statements are proposed to be relocated to a new document, i
the Technical Requirements Manual (TRM), which is a subset of the USAR. NSP proposes the relocation schedule in accordance with the following License Conditions:
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L USNRC 3/2/98 Pago 2 of 2 6.
Relocate current Technical Specification 3.1.E, Maximum Reactor Oxygen, Chloride and Fluoride Concentration, and Technical Specification 5.1 flood shutdown requirements to the USAR (TRM).
Implementation Date: Jan 1,2001.
7.
Relocate current Technical Specification 4.4.D, Diesei Fuel Oil L
Testing, requirements to the Diesel Fuel Oil Testing Program.
Implementation Date: 90 days after issuance of Chapter 6 LAR.
As a matter of clarification, it is NSP's intent to relocate the requirements of the entire section TS.3.1.E. The original submittal incorrectly referred to "TS.3.1.E.3",
although the supporting discussion and page markup cor ectly addressed relocation of the entire section.
A revised Safety Evaluation, Significant Hazards Determination and Environmental Assessment have not been submitted with the changes proposed by this letter since l
these evaluations, as originally presented in the December 14,1995 submittal, continue to bound the proposed license amendment as modified by this supplement.
If you have any questions related to this information in support of the subject license amendment request, please contact myself or Dale Vincent at 612-388-1121.
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oel P. Sorensen Plant Manager, Prairie Island Nuclear Generating Plant Attachments:
Marked Up Technical Specification Pages for Supplement 6 2
Revised Technical Specification Pages for Supplement 6 3
List of pages affected by License Amendment dated December 14,1995 4.
Status of Relocated Requirements c:
Regional Administrator-lil, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg