View source for A02456, Application to Amend License DPR-65,revising Tech Specs to Allow Startup & Power Operation W/One Inoperable Reed Switch Position Indicator Per Control Element Assembly Group

{{Adams
| number = ML20071P449
| issue date = 10/22/1982
| title = Application to Amend License DPR-65,revising Tech Specs to Allow Startup & Power Operation W/One Inoperable Reed Switch Position Indicator Per Control Element Assembly Group
| author name = Counsil W
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Clark R
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000336
| license number = 
| contact person = 
| document report number = A02456, A02617, A2456, A2617, TAC-49061, NUDOCS 8211020513
| package number = ML20071P451
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 4
| project = TAC:49061
| stage = Request
}}

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(203) 666-6911 seOnte(ast se,Qian End AGvCOasrasst October 22, 1982 Docket No. 50-336 A02617 A02456 Director of Nuclear Reactor Regulation Attn:     Mr. Robert A. Clark, Chief Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission Washington, D.C. 20555

==References:==
(1)      R. A. Clark letter to W. G. Counsil, dated April 23,1982.
(2)      D. C. Switzer letter to G. Lear dated, January 23,1978.
(3)      W. G. Counsil letter to R. A. Clark dated, February 19, 1982.
(4)      E. L. Conner letter to W. G. Counsil dated, July 2,1982.
(5)      W. G. Counsil letter to R. Reid, dated March 22,1979.
(6)      W. G. Counsil letter to R. A. Clark dated, September 2,1982.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications                                               l Large and Small Break Loss-of-Coolant Accident Evaluations                                                 jly oOI Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby                                                  > uO proposes to amend its operating license, DRP-65, for Millstone Unit No. 2 by                                            I  '
incorporating the changes identified in Attachment 1 into the Technical Specifications. The proposed changes are summarized briefly as follows:
: 1.         Revise Technical Specification 3.1.3.3, Action b to allow startup and power operation, including mode changes, with an inoperable reed switch position indicator channel per CEA group. This change is proposed in response to Reference (1) and amends our application of Reference (3).
8211020513 821022 PDR ADOCK 05000336 P                            PDR

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: 2. Revise - Technical Specification 3.5.1, Limiting Condition -for Operation b to expand the allowable volume band _ for the safety injection tanks (SIT).' This will provide for greater operational flexibility through reasonable measurement tolerances without impacting the safety analyses.
: 3. Revise Technical Specifications- 3.6.1.1 and 3.6.'. 3 to clarify the applicability of the containment integrity requirements when the containment air lock seal is inoperable. This change incorporates several provisions of the current Standard Technical Specifications into the Millstone Unit No. 2 license.
Concerning the second proposed change described above, the revised SIT level was utilized as input to the Cycle 5 large break LOCA analysis docketed in Reference (3). No other safety analyses are affected by this proposed change.
* The proposed . changes have been reviewed pursuant to the requirements of 10CFR50.59 and have not been found to constitute an unreviewed safety question.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the above proposed changes and has concurred in the above determinations.
NNECO is also taking this opportunity to provide the NRC Staff revised large break LOCA analysis results in response to the commitment ' documented in Reference (4) as well as a small break LOCA evaluation. In anticipation of the potential for additional steam generator tube plugging, both efforts have been completed to demonstrate acceptable plant operation with additional plugged steam generator tubes resulting in a reduced primary coolant system flow rate and steam generator heat transfer area.
The large break LOCA analysis assumptions included the following:
Steam Generator tube plugs:            15.3% (1300 tubes in one generator)
Primary Coolant Flow:                 350,000 gpm in addition, the SlT levels proposed herein have been utilized in the analysis.
The results of the large break LOCA analysis, presented in Attachment 2, demonstrated continued compliance with the criteria delineated in 10CFR50.46.~
Specifically, the peak clad temperature calculated following g double-ended-cold-leg guillotine at the reactor coolant pump discharge is 2055 F and the local and core-wide metal-water reactions were calculated to be 4.5 and O.3 percent, respectively.
A reevaluation of the docketed small break LOCA analysis and results was performed to determine their applicability to Cycle 6 operation. This evaluation is provided as Attachment 3. NNECO concludes that continued Plant operation is acceptable with an additional 9.2 percent reduction in the steam generator heat transfer area as compared to that assumed in the Reference (5) small break LOCA analysis and a reduced reactor coolant flow rate of 350,000 gpm.
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As discussed in Reference (6), a revised small break LOCA model for Millstone Unit No. 2 is scheduled to be submitted to the NRC Staff in March,1983 by our fuel vendor in fulfillment of item II.K.3.30 of NUREG-0737. Upon approval of the model, a small break LOCA analysis will be performed and docketed for Staf f review. NNECO does not expect the conclusions presented in Attachment 3 to be impacted by the results of the small break reanalysis.
NNECO has reviewed the proposed license amendment pursuant to the requirements of 10CFR170 and has determined that the change constitutes a Class ill license amendment.
The basis for this determination is that the proposed changes involve a clearly identified NRC position, a single safety issue and do not involve a significant hazards consideration. As such, enclosed is the appropriate Class III license amendment fee of $4,000 dollars.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY l          RT      .
                                                                      ~
W. G. Counsir ~
Senior Vice President

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   <r STATE OF CONNECTICUT )
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COU:rIY OF HARTFORD Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
Notary Pu m e h.b My Commission Expires March 31,1986 b
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