ML20149M717
| ML20149M717 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/23/1997 |
| From: | Hill W NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20149M719 | List: |
| References | |
| NUDOCS 9701270108 | |
| Download: ML20149M717 (2) | |
Text
Northern States Power Company l
Montmello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362 9637 January 23,1997 US Nuclear Regulatory Commission 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 23,1997 Update of Desian Basis Accident Containment Temperature and Pressure Response 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.
The purpose of this License Amendment Request is to:
1)
Clarify Section 3.5/4.5.C of the Technical Specification Bases to describe the l
minimum Residual Heat Removal (RHR) and Residual Heat Removal Service Water (RHRSW) pump requirements for post accident containment heat removal.
2)
Submit, for NRC Staff review and approval, an update to the design basis accident containment temperature and pressure response for the limiting single failure (loss of diesel generator) which results in minimum RHR and RHRSW pump availability.
i k
These issues were identified recently by an NRC Safety System Operational Performance
/
Inspection (SSOPl) team.
Exhibit A contains a description of the proposed changes, the reasons for requesting the
()6 Y changes, 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 changes. Exhibit C contains revised Monticello Technical l
Specification pages. Exhibit D centains General Electric report NEDO-32418, "Monticello l
Nuclear Generating Plant Design Basis Accident Containment Pressure and Temperature Response for USAR Update," December,1994.
9701270108 970123 PDR ADOCK 05000263-
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USNRC Northern States Power Company January 23,1997
- Page 2 This submittal contains no new NRC commitments, nor does it modify any prior commitments.
1 Please contact Mr Samuel Shirey, Sr Licensing Engineer, at (612) 295-1449 if you require additional information related to this request.
hlN hhu William J Hill j
Plant Manager Monticello Nuclear Generating Plant c:
Regional Administrator-lli, NRC NRR Project Manager, NRC Resident inspector, NRC State of Minnesota Attn: Kris Sanda J Silberg, Esq Attachments:
Affidavit to the US Nuclear Regulatory Commission Exhibit A -
Evaluation of Proposed Change t
Exhibit B -
Technical Specification pages marked up with proposed changes Exhibit C -
Revised Monticello Technical Specification pager Exhibit D -
General Electric report NEDO-32418, December.1994 I
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