B17799, Application for Amend to License NPF-49,incorporating Editorial Revs to TS Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Sections B 3/4.3.2,B 3/4.4.11, B 3/4.6.1.2 & B 3/4.8.4

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Application for Amend to License NPF-49,incorporating Editorial Revs to TS Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Sections B 3/4.3.2,B 3/4.4.11, B 3/4.6.1.2 & B 3/4.8.4
ML20210Q511
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/05/1999
From: Necci R
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20210Q516 List:
References
B17799, NUDOCS 9908160051
Download: ML20210Q511 (5)


Text

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3' Northeast R pe Fe@ @oute %, horW N Nuclear Energy wiiistooe sociear Power station Northeast Nuclear Eoergy Company P.o. Box 128 i

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'g ' Taterford, CT 06385-0128 (860) 447-1791 Faz (860) 444 4277 he Northeast Utilities System AUG - 5 1999

_ Docket No. 50-423 l

B17799 Re:10CFR50.90

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U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 j Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification Correction of Tvocarachical Errors (TSCR 3-06-99)

Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License NPF-49 by incorporating the attached proposed revisions into the Millstone Nuclear Power Station, Unit No. 3 (MP-3) Technical Specifications (TS) sections 3.8.3.2, 4.6.2.1, - 4.6.2.2, 4.8.1.1, 4.9.12, and Bases sections B 3/4.3.2, B 3/4.4.11, B 3/4.6.1.2 and B 3/4.8.4.

Descriptiori of Proposed Revision I

l . The proposed TS changes are editorial and do not alter or effect the design, operation,  ;

maintenance or surveillance requirements associated with MP-3 Structures, Systems,

, and Components (SSC) during normal or accident operations.

l Markuo of Proposed Revision A copy of the marked up Technical Specification pages are contained in Attachment 1.

The markup reflects the currently issued version of the Technical Specifications. ,

l Pending Technical Specification Amendments are not reflected in the enclosed markup.

i 9908160051 990005 PDR ADOCK 05000423 bh j p PDR Os3422 5 RF11245

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U.S. Nuclear Regulatory Commission B17799/Page 2

. Retvoe of Proposed Revision A copy of the retyped Technical Specification pages are presented in Attachment 2.

The retyped pages reflect the incorporation of the proposed changes to the Technical Specification. The retyped pages reflect the currently issued version of the Technical Specification. Pending Technical Specification Amendments are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with recently issued Technical Specifications amendments prior to issuance.

Backaround. Safety Summarv. Sianificant Hazards Consideration and Environmental Considerations The Background and Safety Summary, related to this TSCR is presented in Attachment 3. The Significant Hazards Consideration (SHC) and Environmental Considerations are presented in Attachment 4.

Plant Operations Review Committee and Nuclear Safety Assessment Board Review I

Plant Operations Review Committee and Nuclear Safety Assessment Board have reviewed this proposed License Amendment change and concur with the conclusions presented in the rationale for the proposed change relative to safety.

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.

Schedule Reauest for NRC Anoroval NNECO requests NRC review and approval of this proposed revision, and that the license amendment be effective upon issuance. Furthermore NNECO requests that this proposed revision to the TS be implemented within 60 days of issuance.

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U.S. Nuclear Regulatory Commission B17799/Page 3 1,f the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. D. W. Dodson at (860) 447-1791 extension 2346.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY t

vers R. P. Necci Vice President-Nuclear Oversight and Regulatory Affairs !

Subscribed and sworn to before me

- this 6 day of d# 1999 mfd _

My Domesson t.xp.. Jan. 54, twa Date Commission Expires:

l cc: H. J. Miller, Region I Administrator J. A. Nakoski, NRC Project Manager, Millstone Unit No. 3 l A.C. Cerne, Senior Resident inspector, Millstone Unit No. 3 Director l Bureau of Air Management Monitoring and Radiation Division Department of environmental Protection 79 Elm Street Hartford, CT 06106-5127 '

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't;. 6 Docknt No. 50-423 B17799 Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification Correction of Tvooarachical Errors (TSCR 3-06-99)

Marked Up Pages August 1999

i. 4 U.S. Nucl::ar Regulatory Commission B17799/ Attachment 1/Page 1 MARKUP OF PROPOSED REVISION Refer to the attached markup of the proposed revision to the Technical Specifications.

The - attached markup reflects the currently issued version of the Technical Specifications listed below. Pending Technical Specification revisions are not reflected in the enclosed markup.

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The following Technical Specification changes are included in the attached markup. )

1)- TS 3.8.3.2-Change 3.8.3.2.b.4.1 to 3.8.3.2.b.4.a in order to correct sequential numbering.

2) TS 4.6.2.1.a.1 and TS 4.6.2.2.a-Adds the word "that" after the words " flow path."

This change addresses a TS modification that was pre /iously approved by the NRC in Amendment 50. This change was inadvertently omitted from the TS when '

Amendments 100 and 122 were approved. This TS change is editorial in nature and is provided to correct grammar and provide ease of reading. TS Amendments issued subsequent to Amendment 50 were reviewed and none were found which requested deletion of the words "that. "

3) TS 4.8.1.1.2.i.-Change TS 4.8.1.1.2.i.1 to TS 4.8.1.1.2.i in order to reflect that there is only one surveillance requirement in this paragraph. I

- 4) TS 4.9.12-Change TS 4.9.12 to TS 4.9.12.1 in order to correct sequential l numbering.

5) Bases section 3/4.3.1 and 3/4.3.2-Delete reference to Operating Procedure 3273. ,
6) Bases section 3/4.4.11-Change valve number 3RCS*SV80965B to the correct valve number designation 3RCS*SV8096B.
7) Bases section 3/4.6.1.2-Delete reference to Operating Procedure 3273.
8) Bases section 3/4.8.4-Delete reference to Operating Procedure 3273.