ML20078E015
| ML20078E015 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/28/1994 |
| From: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20078E017 | List: |
| References | |
| NMP2L-1505, NUDOCS 9411090311 | |
| Download: ML20078E015 (2) | |
Text
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N U MOHAWK Y NIAGARA
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NIAGARA MOHAWK POWER CORPORATION /NiNE MILE PolNT, P.O. box 63, LYcOMING, NY 13093/ TELEPHONE (315) 349-2882
- 8. Ratph Sylvia '
Ex:cutwe Vice President Nuchar OClober 28,1994 NMP2L 1505 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-410 NPF-69 Gentlemen:
Niagara Mohawk Power Corporation hereby transmits an Application for Amendment to Nine Mile Point Unit 2 Operating License NPF-69. Also enclosed are the proposed changes to the Technical Specifications set forth in Appendix A of the above mentioned license.
Supporting information and analysis demonstrating that the proposed changes involve no significant hazards consideration pursuant to 10CFR50.92 are included as Attachment B.
The proposed Technical Specification changes contained herein represent revisions to Specification 1.0, " Definitions," Specification 3/4.3.2, " Isolation Actuation Instrumentation,"
and Specification 3/4.9.3, " Control Rod Position." Specifically, Definition 1.7, " Core Alteration," is proposed for revision to clarify that movement or replacement of SRMs, IRMs, LPRMs, TIPS or special moveable detectors are not considered to be core alterations.
The definition is also expanded to state that " control rod movement is not considered to be a CORE ALTERATION provided that there are no fuel assemblies in the associated core cell."
In addition, Specification 3/4.9.3, " Control Rod Position," and the associated Bases are proposed for revision to be consistent with the definition of CORE ALTERATION by changing the requirement to verify that all rods be inserted only during loading of fuel assemblies into the core. These changes are consistent with the " Improved Standard Technical Specifications," NUREG-1434 and those to be incorporated in Revision 1. Similar changes have been approved as Amendments 168 and 199 for Brunswick Steam Electric Plants, Units 1 and 2, respectively.
On April 7,1993, Niagara Mohawk submitted an Application for Amendment to remove the requirement for the Standby Liquid Control System (SLCS) to be operable in Operational Condition 5. This was issued as Amendment 48 on September 30,1993. Currently, Tables 3.3.2-1 and 4.3.2.1-1 show that SLCS initiates Reactor Water Cleanup System (RWCS) isolation in OPERATIONAL CONDITION 5. This requirement should have been deleted at the time of the previous amendment. The proposed revision deletes this requirement along with the associated notes.
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The revised definition of CORE ALTERATION provides flexibility in that replacement of control blades and LPRMs will no longer renuire secondary containment OPERABLE, thereby potentially reducing the duration of tne outage. Anproval of this amendment is requested by April 1,1995, to support Refueling Outagt; 6, currently scheduled for April 1995.
Pursuant to 10CFR50.91 (b)(1), Niagara Mohawk has provided a copy of this license amendment request and the associated analysis regarding no significant hazards consideration to the appropriate state representative.
Very truly yours,
[yf?cdphhl0 B. Ralph Sylvia Executive Vice President - Nuclear MGM/Imc Attachments xc:
Regional Administr.9 tor, Region I Mr. L. B. Marsh, Director, Project Directorate I-1, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR Mr. B. S. Norris, Senior Resident Inspector
-i Ms. Donna Ross Division of Policy and Analysis New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 Records Management 5
y e.