ML20205L050
| ML20205L050 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/01/1999 |
| From: | Abbott R NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20205L053 | List: |
| References | |
| NMP1L-1419, TAC-MA1945, NUDOCS 9904140111 | |
| Download: ML20205L050 (2) | |
Text
mz NiagarahMohawk' Richard B. Abbott Phone: 315.349.1812 Vce Presiderg Fax: 315.349.4417 NuclearEngineering April 1, 1999 NMPIL 1419 U. S. Nuclec.r Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Subject:
Additional Infonnation Regarrling Increased Spent Fuel Pool Stomge Capacity at Nine Mile Point Nuclear Station Unit 1 (TAC No. MAIMS)
Gentlemen:
By letter dated May 15,1998, Niagara Mohawk Power Corporation (NMPC) submitted an application to amend Nine Mile Point Unit 1 (NMP1) Technical Specification (TS) 5.5, Storage of Unirradiated and Spent Fuel. The changes reflect proposed modifications to increase the storage capacity of the NMP1 spent fuel pool (SFP) from 2776 to 4086 fuel assemblies. The NRC's letters dated August i1,1998, August 24,1998, October 27,1998, and December 9,1998 requested additional information regarding our application. Our submittals of September 25,1998, October 13, 1998, December 9,1998, and Janu.iry 11, 1999 provided our responses.
Attachment C, Section 5.0 (proprietary) and Attachment F, Section 5.0 (non-9roprietary) of our amendment application provided the thermal-hydraulic analysis to support the proposed TS changes. As part of an internal Safety System Functional Irupection, NMPC has determined that the SFP heat exchanger heat removal rate assumed in this analysis was incorrect (i.e., the
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heat exchanger tube material assumed was incorrect). Accordingly, NMPC has re-performed the thermal-hydraulic analysis with the correct heat rernoval rates and has included the revised version elSection 5.0 as Attachment A. As iniicated in Section 5.8, this assumption has had minimal affect on t5 results of the thermal-hyoraulic analysis including SFP tempera:ures, time-to-boil and boil-off rates, and the ability to meet required acceptance criteria. Because.
revised Section 5.0 does not contain proprietary information, it replaces both Attachment C, Section 5.0 (proprietary) and Attachment F, Section 5.0 (non-proprietary) of our original Jubmittal,. Also included in Attachment A is tSe resulting change to the Table of Contents.
NMPr' was asked to supplement its response to Questions No. 8 and No.10 of our October 13, 1998 letter. Concerning Question No. 8, the NRC asked that we provide specific results if we assume 200 spent fuel assemblies (SFAs) as the previously discharged SFAs. The revised version of Section 5.0 provides this supplemental information.
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Page 2 Concerning Question No.10, NMPC's response indicated a SFP high temperature alarm provides temperature indication to assure that SFP temperature limits are maintained. The NRC requested we provide the associated alarm setpoint, the action time provided and the specific actions. This information is provided as Attachment B.
Sincerely,
,4f b b Bd6&f Richard B. Abbott Vice President Nuclear Engineering RBA/JMT/sc Attachments xc:
Mr. H. J. Miller, NRC Regional Administrator Region I Mr. S. S. Bajwa, Director, Project Directorate I-1, NRR Mr. G. K. Hunegs, Senior Resident Inspector Mr. D. S. Hood, Senior Project Manager, NRR Mr. John P. Spath NYSERDA
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