B16530, Application for Amend to License NPF-49,modifying Wording in TS Surveillance 4.4.1.3.3
| ML20141B973 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/13/1997 |
| From: | Brothers M NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20141B977 | List: |
| References | |
| B16530, NUDOCS 9706240245 | |
| Download: ML20141B973 (7) | |
Text
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Northeast Nuclear Energy Company.
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P.O. Ikis 128 Waterford, CF 06385-0128 i
j (860) 447 1791 Fax (860) 444-4277 4
The Northeast Utilities System JUN 131997 i
Docket No. 50-423 i
B16530 f
Re: 10CFR50.90 i
4 U.S. Nuclear Regulatory Commission Attention: Document Control Desk j
Washington, DC 20555 Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System - Hot Shutdown (PTSCR 3-28-97)
Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License NPF-49 by incorporating the attached proposed i
revision into the Millstone Unit No. 3 Technical Specification 4.4.1.3.3.
Descriotion of Prooosed Revision Technical Specification Surveillance 4.4.1.3.3 currently requires "At least one reactor coolant or RHR loop shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
This proposed revision to Technical Specification modifies the surveillance statement to read; "The required loops shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
1 Markuo of Proposed Revision A copy of the marked up Technical Specification page is contained in Attachment 2.
The markup reflects the currently issued version of the Technical Specifications.
Pending Technical Specification revisions or Technical Specification revisions issued subsequent to this submittal are not reflected in the enclosed markup.
A DM' i Retvos of Proposed Revision A copy of the retyped Technical Specification page is contained in Attachment 3. The retyped page reflects the currently issued version of the Technical Specifications.
Pending Technical Specification revisions or Technical Specification revisions issued ago g g j,3
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c U.S. Nucinar Regulatory Commission B16530\\Page 2 subsequent to this submittal are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.
Backaround. Safety Assessment. Sianificant Hazards Consideration and Environmental Considerations The Background, Safety Assessment, Significant Hazards Consideration and Environmental Considerations that support this proposed revision are contained in Attachments 4 and 5.
Plant Operations Review Committee and Nuclear Safety Assessment Board Review The Plant Operations Review Committee and the Nuclear Safety Assessment Board 4
have reviewed this proposed amendment request and concur with the contained determinations.
State Notification in accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment to ensure their awareness of this request.
i Schedule Reauest for NRC Acoroval NNECO requests NRC review and approval of this proposed revision by October 24, 1997, and that the license amendment be effective upon issuance with implementation within sixty (60) days.
4 If the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. D. Smith at (860) 437-5840.
i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY U /k l A
M. H. Brothers I'
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Vice President - Millstone Unit No. 3 i
Subscribed and sworn to before me this
)3 day of LC 1997 k_m. w>.Yw llbhYmA Date Commission Expires:
Alov 30 c9CD/
cc: See Page 3 hWm DONNA LYNNE WILLIAN$
munnypens NOTARY PHUC conmesma e,neems,.sa see, STATE OF COMECRCUT
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U.S. Nuclecr Regulttory Commission j
B16530)Page 3 cc:
H. J. Miller, Region l Administrator W. D. Travers, PhD., Director, Special Projects Office J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Corne, Senior Resident inspector, Millstone Unit No. 3 i
Mr. Kevin T. A. McCarthy, Director
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Bureau of Air Management l
Monitoring and Radiation Division l
Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 4
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Docket No. 50-423 B16530 l
l Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System -Hot Shutdown (PTSCR 3-28-97)
NNECO's Commitments i
1 June 1997
l U.S. Nuclerr Regulatory C:mmission 1
B16530\\ Attachment 1\\Page 1 Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document.
Please notify the Manager - Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.
l Commitment Committed Date or Outage NONE N/A l
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Docket No. 50-423 B16530 j
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Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System - Hot Shutdown (PTSCR 3-28-97)
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Marked Uo Paae d
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i June 1997 1
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U.S. Nucirr R:gulatory Commission B16530\\ Attachment 2\\Page 1 MARKUP OF PROPOSED REVISION Refer to the attached markup of the propcsed revision to the Technical Specifications.
The attached markup reflects the currently issued version of the Technical Specifications listed below. Pending Technical Specification revisions or Technical Specification revisions issued subsequent to this submittal are not reflacted in the enclosed markup.
The following Technical Specification change is included in the attached markup:
The existing text "At least one reactor coolant or RHR loop..." is replaced with "The required loops". The balance of the surveillance statement remains unchanged:...shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
l 4.4.1.3.3
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