View source for B16844, Application for Amend to License NPF-49,revising TS Surveillance Requirement 4.5.2.d.1 by Changing Pressure from 390 Psia to 412.5 Psia to Take Bistable Reset Into Account & Deleting Words or Actual RCS Pressure

{{Adams
| number = ML20199G927
| issue date = 11/14/1997
| title = Application for Amend to License NPF-49,revising TS Surveillance Requirement 4.5.2.d.1 by Changing Pressure from 390 Psia to 412.5 Psia to Take Bistable Reset Into Account & Deleting Words or Actual RCS Pressure
| author name = Brothers M
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000423
| license number = 
| contact person = 
| document report number = B16844, NUDOCS 9711250337
| package number = ML20199G934
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 5
| project = 
| stage = Request
}}

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nterford, CT 0(2385 0128 (860)447 1791 Fax (8t4) 444 4277 The Nottimt Utihts ,'ystern NOV I 41997 Docket No. 50-423 B16844 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attention:     Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification Residual Heat Removal System Open Pressure Interlock (DTSCR 3-36-97)
Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License NPFw9 by incorporating the attached proposed revision to Technical Specification Surveillance Requirement 4.5.2.d.1 into the Millstone Unit No. 3 Technical Specifications.
Description of Procosed Revistor)
Technical Specification Surveillance Requirement 4.5.2.d.1 currently requires
           " Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 390 psia the interlocks prevent the valves from being opened." The proposed change will change the pressure from 390 psia to 412.5 psia to take the bistable reset into account a.ed delete the words "or actual Reactor Coolant System pressure".
{
Markup of Proposed Revision A copy of the marked up Technical Specification page is contained in Attachment 2. gol The markup rt? acts the currently issued version of the Technical Specifications.
Pending Technical Specification revisions or Technicsl Specification revisions issued subsequent to this submittal are not reflected in the enclosed markup.
Retvoe of Proposed Revision A copy of the retyped Technical Specification page is contained in Attachment 3. The tetyped pages reflect the currently issued version of the Technical Specifications.
Pending Technical Specification revisions or Technical Specification revisions issued
                             ,-,n 9711250337 971114
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t i U.S. Nuclear Reguictory Commission B16844\Page 2
        , subsequent to this submittel are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.
Backaround. Safstv Assessment. Sionificant Hazards Consideration and Environmental Considerations The Background, Safety Assessment, Significant Hazards Consideration and Environmental Considerations that scpport 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 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.
Schedule Reauest for NRC Acoroval NNECO requests NRC review and approval of this proposed revision by December 19, 1997 and that the license amendment be effective upon issuance with implementation within sixty (60) days.
If the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. D. Smith at (860) 437-5840.
Very truly yours, NORTHEAST UCLEAR ENERGY COMPANY
                                                                                    /dNl                             '
M. H. Brotherd Vice President - Millstone Unit No. 3 Subscribed and sworn to before me this                       N   day of L% gar.1997
            %m [                          sc_ W t 0ltdown U
,           Date Commission Expires: no30 acol I
cc: See Page 3

                                   . _.                       .   .-     -  .  . . . . . = _ - - .
U.S. Nucirer Regulctory Commission 3         B16844\Page 3 cc-     H. J. Miller, Region I Administrator W. D. Travers, PhD, Director, Special Projects Offee J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Corne, Senior Resident inspector, Millstone Unit No. 3 Director
                 - Bureau of Air Man 6.gement Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 4
1

             . - .. -                                               Docket No. 50- 423 B16844 Attachment 1 Millstone Nuclear Power Station, Unit No. 3                       .
Proposed Revision to Technical Specification Residual Heat Removal System Open Pressure Interlock (PTSCR 3-36-97)
NNECO's Commitments I
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November 1997

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  . 4 U.S. Nuclear Regulatory Commission B16844%ttachment 1\Pagei Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document.
Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.
Commitment                            Committed Date or Outage NONE                                    N/A}}