ML20141B902
| ML20141B902 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/19/1997 |
| From: | Hill W NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20141B908 | List: |
| References | |
| TAC-M97781, NUDOCS 9706240200 | |
| Download: ML20141B902 (3) | |
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Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 June 19,1997 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 Licanse No. DPR-22 Revision No. 2 to License Amendment Request Dated January 23,1997 Uodate of Desian Basis Accident Containment Temos.sture and Pressure Response TAC No. M97781 Attached is a complete revision and replacement for our January 23,1997, License Amendment Request as revised and supplemented by our submittals dated January 28,1997, and March 4,1997. The scope of the License Amendment Request has been expanded to address the use of containment pressure for assuring adequate net positive suction head (NPSH) for emergency core cooling system (ECCS) pumps under worst-case conditions. This submittal also provides our response to NRC Staff requests for additional information dated March 12,1997, and May 13,1997.
The following Technical Specification changes are proposed:
1)
Clarify Section 3.5/4.5.C of the Technical Specification Bases on pages 112 and 113 to describe the minimum Residual Heat Removal (RHR) and Residual Heat Removal Service Water (RHRSW) pump requirements for post accident containment heat removal. This will clearly identify the limiting combination of RHR and RHRSW pumps for suppression pool cooling with the limiting single failure (loss of diesel generater).
2)
Clarify Section 3.7.A of the Technical Specification Bases on page 176 to state that credit is taken for containment pressure to meet the NPSH requirements for core spray and RHR pumps following a loss of coolant accident. The use of containment pressure to satisfy the NPSH requirements of core spray and RHR pumps was not adequately documented when the plant was originally licensed.
NRC Staff review and approval of the proposed changes is requested to provide resolution of one unreviewed safety question and one unresolved item which were identified during an NRC System Operational Performance Inspection (SOPI) completed on January 8,1997.
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4 USNRC Northern States Power Company June 19,1997 Page 2 The following Exhibits are included with this License Amendment Request:
Exhibit A Description of the proposed changes, the reasons for requesting the changes, a Safety Evaluation, a Determination of Significant Hazards Consideration, and an Environmental Assessment.
Exhibit B Current Technical Specification pages marked up with the proposed changes.
Exhibit C Revised Monticello Technical Specification pages.
Exhibit D General Electric Report GE-NE-T2300731-2, "Monticello Nuclear Generating Plant LOCA Containment Analysis For Use in Evaluation of NPSH for the RHR and Core Sprav Pumps," June, 1997 Exhibit E Duke Engineering & Services Calculation Package V75100.NSP97.00501," Determination of Containment i
Overpressure Required for Adequate NPSH of the Low Pressure ECCS Pumps," June 18,1997 Exhibit F
" Torus Attached Piping Evaluation," Monticello Nuclear Generating Plant, Revised June,1997 Exhibit G
" Evaluation of RHR Room Temperature During DBA LOCA,"
Monticello Nuclear Generating Plant, Revised June,1997
&hibit H
" Evaluation of Environmental Qualification Bounding Conditions,"
Monticello Nuclear Generating Plant, June,1997 Exhibit I Response to NRC Request for AdditionalInformation dated March 12,1997 Exhibit J Response to NRC Request for Additional information dated May 13,1997
USNRC Northern States Power Company June 19,1997 Page 3 This submittal contains no new NRC commitments, nor does it modify any prior commitments.
Please contact Mr Joel Beres, Licensing Engineer, at (612) 295-1436 if you require additional information related to this request.
Wgths fk William J Hill Plant Manager Monticello Nuclear Generating Plant c:
Pegional Administrator-Ill, NRC NRR Project Manager, NRC Resident Inspector, NRC State of Minnesota Attn: Kris Sanda J Silberg, Esq Attachments:
Affidavit to the US Nucloar Regulatory Commission Exhibits A - J
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