ML20197H325
| ML20197H325 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/15/1997 |
| From: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19317C821 | List: |
| References | |
| NMP2L-1740, NUDOCS 9712310248 | |
| Download: ML20197H325 (3) | |
Text
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1 NIAGARA MOHAWK
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GENERATION BUSINESS GROUP B IVthiSYLVIA uoca m n n e g g g, December 15,1997 NMP2L 1740 U. S. Nuclear Regulatory Commission Attn: Documeni Comrol Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-41 NPF-69 Gentlemen:
k Niagara Mohawk Power Corporation (NMPC) hereby transmits an Application for J
Amendment to Nine Mile Point Unit 2 (NMP2) Opera'ing License NPF-69. Enclosed is a proposed change to the Technical Specifications (TS) set forth in Appendix A of the above mentioned License. Supporting information and analyses which demonstrate that the proposed change involves no significant hazards consideration pursuant to 10CFR50.92 are included as Attachment B. A marked-up copy of the affected current TS pages is providc<1 as Attachment C to assist your review.
The proposed TS change contained herein represents a revision to the Index, Sectiou ? !
Safety Limits, Bases Section 2.1 and Section 3/4.4.1.
On May 24,1996, General Electric (GE) notified the NRC of a reportable condition involving the generic safety limit calculational methodology. NMPC submitted NMP2 Licensec Event Report (LER) 96-06 on June 3,1996, and provided additional information regarding the impact of the nonconservative values. NMPC concluded that neither the Safety Limit nor the Operating Limit would have been exceeded for any analyzed plant transient, based on the increased Safety Limit value and the core performance up to that point in the operating cycle. The Supplemental Reload Licensing Report, Updated Safety Analysis Report (USAR), and Core Operating Limits Report (COLR) have been revised to include the correct Safety Limit Minimum Critical Power Ratio (MCPR) for the current operating cycle.
This change to the TS completes the corrective actions described in LER 96-06. NMPC and GE have completed an analysis to determine the necessary Safety Umit MCPR for the upcoming operating cycle (Cycle 7). This analysis shows that the required Safety Limit MCPR will decrease from the current cycle's value based on the cycle specific Safety Limit MCPR calculation. As a result, thh TS change revises the Safety Limit MCPR from 1.07 to i
1.09 for two recirculation loop operation and from 1.08 to 1.10 for single loop operation to account for these changes.
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9712310248 971215 DR ADOCK 050004 0
s Page 2 In addition, Bases Section 2.1 is revised for consistency on page B2-1 and to delete some of the detailed informatio3 and refer instead to General Electric Standard Application for Reactor Fuel ((iESTAP 11), NEDE-240ll-P-A and to the cycle :pecinc analysis (Supplemental 191oad Licensing Report). This level of detail is consistent with that in the Improved Standarc Technical Specifications (NUREG-1434). Some of the wording has been revised to more ac urately reficct current pactices.
A footnote on ptge 3/4 41 is also deleted. This footnote only applied to the first operating cycle and is therefore no longer applicable or necessary.
The GE methodoiogy used to determine the cyde specific Safety Limit MCPR for NMP2 is the same methodology used for other BWRs. Information regarding this methodology is provided as Attachment D.
Attachment D is considered by its preparer, GE, to contain proprietary information exempt from disclosure pursuant to 10CFR2.790. Therefore, on behalf of GE, NMPC hereby makes application to withhold this document from public disclosure in accordance with 10CFR2.790 (b)(1). An affidavit executed by GE detailing the reasons for the request to withhold the proprietary information has been included as Attachment E. A non-proprietary version of this document has been included with this letter as Attachment F.
Smce the proposed change includes a revision to the Safety Limit MCPR to reflect the cycle spe(.ific limit for the upcoming operating cycle (Cycle 7), NMPC requests that the proposed change be approved by May 15, 1998. NMPC also requests the flexibility to implement this TS Amendment prior to startup in Cycle 7 (currently scheduled for early June 1998) versus the normal 30 day implementation requirement. Adequate administrative controls are currently in place to control the Operating Limit and Safety LinCt MCPR for the remainder of the current operating cycle.
Pursuant to 10CFR50.91(b)(1), Niagara Mohawk has provided a copy of this license amendment and the associated analyses regarding no significant hazards consideration to the appropriate state representative.
Very truly yours, h/ 0 K
B. Ralph Sylvia Chief Nuclear Officer BRS/TWP/cmk Attachments
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-;Page 3 xc:-. Mr. H.~ J. Miller, NRC Regional Administrator
- Mr. A. W. Dromerick, Acting Director, Project Directorate I-1,- NRR Mr. L'_ S. Nonis, Senior Resident Inspector Mr. D. S. Hood, Senior Project Manager, NRR --
Mr. J. P. Spath NYSERDA 2 Empire Plaza, Suite 1901 Albany, NY 12223-1253
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