ML18038A734
| ML18038A734 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/18/1993 |
| From: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17056C275 | List: |
| References | |
| NMP1L-0736, NMP1L-736, TAC-M79135, NUDOCS 9303020490 | |
| Download: ML18038A734 (4) | |
Text
NIAGARAMOHAWKPOWER CORPORATION/NINE MILEPOINT, PO. BOX63, LYGOMING,NY 13093/TELEPHONE (315) 349-2882 B. Ralph Sylvia Executive Vice President Nuclear February 18, 1993 NMP1L 0736 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re:
Nine MilePoint Unit 1 Docket No. 50-220 DPR-63 AC No. M7 1
Gentlemen:
SUBJECT:
PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO REACTOR COOLANT SYSTEM ANDPRIMARY CONTAINMENT ISOLATION VALVETABLES AND CONTAINMENTLEAKAGERATE TESTS By letter dated February 7, 1992, Niagara Mohawk submitted an Application for License Amendment to Nine Mile Point Unit 1 Operating License DPR-63.
The proposed amendment would update the Reactor Coolant and Primary Containment Isolation Valve Tables, and includes changes to conform to the requirements of 10CFR50 Appendix J, consistent with NRC SER dated May 6, 1988 and NRC correspondence dated November 9, 1988.
Letters dated June 22, 1992 (NMP1L 0674) and January 29, 1993 (NMP1L 0729) provided additional information regarding the License Application.
This letter provides changes to Reactor Coolant and Primary Containment Isolation Valve Tables 3.2.7 and 3.3.4 resulting from Niagara Mohawk and Staff review during the week of February 1, 1993.
These changes are: 1) addition and deletion of valves which define the Reactor Coolant and Primary Containment Isolation boundary to be consistent with NRC SER; 2) removal of footnote (1) from H,O, ¹11 sampling system and Containment Atmosphere supply line to be consistent with NRC SER; 3) addition of notation to reflect issuance of Amendment 134; 4) deletion of footnotes and addition of check valve normal positions to be consistent with industry practice; 5) addition of manual valves which are included under Type C testing; and 6) editorial changes.
Attachment 1 contains a revised Technical Specification page listing similar to Attachment A of the above mentioned License Application and revised Technical Specification pages.
In addition, all other previously submitted Technical Specification pages have been retyped with no change in content and have been included for completeness.
The proposed change in Attachment 1 has been reviewed in accordance with Section 6.5 of the Technical Specifications.
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Page 2 U.S. Nuclear Regulatory Commission February 18, 1993 contains revised supporting information similar to that contained in Attachment B of the February 7, 1992 License Application. The No Significant Hazards Analysis of Attachment B of the February 7, 1992 License Application remains unchanged.
Assuming approval, please issue a License Amendment which willbe effective upon issuance and shall be implemented within 90 days of issuance.
As stated in our January 29, 1993 letter, approval is required by May 1, 1993 in order to incorporate the changes in the June 30, 1993 FSAR update.
Very truly yours, B. Ralph Sylvia Exec. Vice President - Nuclear MGM/1mc Attachments XC:
Regional Administrator, Region I Mr. W. L. Schmidt, Senior Resident Inspector Mr. R. A. Capra, Director, Project Directorate I-1, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR Ms. Donna Ross Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 Records Management
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