View source for B14315, Forwards Addl Info Needed to Complete Review of 921028 Application for Amend to License

{{Adams
| number = ML20057A018
| issue date = 12/04/1992
| title = Forwards Addl Info Needed to Complete Review of 921028 Application for Amend to License
| author name = Opeka J
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = B14315, IEB-80-04, IEB-80-4, NUDOCS 9309100294
| package number = ML20057A019
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
| project = 
| stage = Request
}}

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December 4, 1992                                                    :
Docket No. 50-336 B14315 U.S. Nuclear Regulatory Commission Attention:          Document Centrol Desk                                                                                                 i Washington, DC 20555                                                                                                                      i Gentlemen:
6 Millstone Nuclear Power Station, Unit No. 2                                                                    l Proposed Revision to Technical Specifications                                                                   !
Main Steam Line Break Design Limits                                                                     *
                                        &Joense to Reog}t for Additional Information                                                                    i in a {{letter dated|date=October 28, 1992|text=letter dated October 28, 1992}},"' Northeast Nuclear Energy Company (NNECO)                                                           !
l             proposed to amend Operating License DPR 65 for Mill tone Unit No.                                          2.         In                  :
response to NRC Staf f review questions, telephone conferences were held on                                                               !
November         6,     November 9           and Nove ber 30, 1992, during whi.h additianal                                               !
information was requested,                       in a {{letter dated|date=November 20, 1992|text=letter dated November 20, 1992}},d' NNECO                                            l
,             provided the infornation that had been initially transmitted via facsimile as                                                             !
l             requested in the November 6 and 9 telephone conferences. Attachment I to this                                                             i letter provides information which was transmitted to the Staff via facsimile                                                             j shortly following the November 30, 1992, telephone conference, in response to two main areas of Staff interest. The first of which was the core response to train steam line break (MSLB) and loss-of-coolant accident (LOCA). Attach-                                                                !
ment I discusses core response to MSLB and large and small break LOCA. The                                                                l l              second Staff interest was associated with equipment qualification (EQ)                                                                   i associated with the peak containment temperature and pressure.                                        The peak                           i parameters are approximately 425.4*F and 53.7 pounds per square inch gauge.                                                               1 The EQ review for the design change is also included in Attachment 1. Addi-                                                               ;
tional analytical information will be provided in NNECO's revised response to                                                             l NRC 1&E Bulletin 80-04 as previously committed by the end of 1992.
(1)        J. F. Opeka letter to U.S. Nuclear Regulatory Conrnission, " Millstone                                                   !
Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications Main Steam Line Break Design i.imits,' d:ted October 28, 1992.
(2)        J. F. Opeka letter to U.S. Nuclear Regulatory Commission, ' Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Main Steam Line Break Design Limits Response to Request,                                              f/f u
for Additional Information,' dated November 20, 1997.                                              P                     l 5
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E14315/Page 2                                                                                                                                                   ;
Deceece 4, 1002 As part of their technical review, the Staff also requested that NNECO perform an emergency diesel - generator start on safety injection actuation signal                                                                                       ,
surveillance beyond that to which the unit was originally licensed. After l
discussion and evaluation, NNECO hereby commits to submit a license amendment, i                   worded similarly to that requested by the Staff, within approximately 90 days l                   from unit startur, with the following considerations: This additional commit-
;                    ted surveillnt                          will first be performed at an appropriate time associated                                                                ,
]  '
with the next routinely scheduled Millstone Unit No. 2 refuel and maintenance-outage (expected mid-1994).                                  Independent from this commitment,                               NNECO intends                       ;
to perform a similar functional demonstration, as part of the test plan asso-ciated with the design change modi fication package cl;;ure, during this                                                                                         ,
i                    outage.                                                                                                                                                          '
I d
We appreciate the opportunity to respond to the Staff's technical review                                                                                         ;
questions in an efficient manner.                                   We hope the Staff finds this additional
                                                                                                                                                                                      ~
information appropriate toward completing their technical review to allow                                                                                        1 issuance of the license amendment on or before December 21, 1992, as requested                                                                                   I i                    subsequent to the {{letter dated|date=October 28, 1992|text=October 28, 1992, letter}}.                                                     If you have further questions, ,
please contact my Staff.                                                                                                                                         ,
i j                                                                                                      Very truly yours,                                                              '
;                                                                                                      NORTHEAST NUCLEAR ENERGY COMPANY                                               ,
h , F. CSA                                                   !
J. F. fpe3h                     O
;                                                                                                      Executive Vice President                                                       .
cc:   T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2                                                                                                   !
P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2,                                                                                       i and 3                                                                                                                                                    ,
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