View source for 05000423/LER-1996-044, Forwards LER 96-044-00,documenting Condition That Was Determined at Millstone Unit 3,on 961108.Commitments,encl

{{Adams
| number = ML20135D662
| issue date = 12/04/1996
| title = Forwards LER 96-044-00,documenting Condition That Was Determined at Millstone Unit 3,on 961108.Commitments,encl
| author name = Brothers M
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000423
| license number = 
| contact person = 
| document report number = B16025, NUDOCS 9612100081
| package number = ML20135D666
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 4
}}
{{LER
| Title = Forwards LER 96-044-00,documenting Condition That Was Determined at Millstone Unit 3,on 961108.Commitments,encl
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000423
| LER year = 2096
| LER number = 44
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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                              ' Utilities System                                                      e.o. au 128 Waterford, CT 06385-0128 (203) 447-1791 1
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:                                                                                                          December 4,1996 -
;                                                                                                          Docket No. 50-423 B16025 i
Re:10CFR 50.73(a)(2)(ii)(B)                                ,
10CFR 50.73(a)(2)(v)(C) t 10CFR 50.73(a)(2)(v)(D)
:                    U. S. Nuclear Regulatory Commission Document Control Desk i                    Washington, DC 20555 -
Millstone Nuclear Power Station Unit 3
'                                                         Licensee Event Report 96-044-00 Submitted Pursuant to 10CFR 50.73(a)(2)(ii)(B)
]                    This letter forwards Licensee Event Report 96-044-00, documenting a condition j                    that was determined at Millstone Unit No. 3 on November 8,1996. This LER is j                    submitted pursuant to 10CFR 50.73(a)(2)(ii)(B), 10CFR 50.73(a)(2)(v)(C),
:                    10CFR 50.73(a)(2)(v)(D). NNECO's commitments in response to this event are j                   . contained within Attachment 1 to this letter.
;                    Should you have any questions regarding this submittal, please contact Mr.
James M. Peschel at (860) 437-5840.
h i
l Very truly yours, i                                                                                                                                                     \
NORTHEAST NUCLEAR ENERGY COMPANY                                               d i- \
090112 i                                                                       M M. H. Brothers xW          '
IO
                                                                                                                                                   /
Unit Director, Millstone Unit No. 3
<               9612100001          961204-ADOCK 05000423,
;              .PDR j               0                         PM

U.S. Nucinar Regulatory Commission
 ;             B16025\Page 2 j              

==Attachment:==
: 1)            NNECO's commitments in response to LER 96-044-00
;                            2)'         LER 96-044-00 cc:   H. J. Miller, Region l Administrator A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3
:                    W. D. Travers, Dr., Director, Special Projects I
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Docket No. 50-423 B16025 4
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Attachment 1 a
4 Millstone Nuclear Power Station, Unit No. 3 NNECO's Commitments
{'                                                                           In Response To (LER 96-044-00)
December 4,1996

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U.S. Nuclear Rsgulatory Commission i    .              B16025\ Attachment 1\Page 2-i I
l l                                                                                                   Enclosure                            l t-List of Regulatory Commitments                               !
l i                                                                                                                                         1
;                   The following table identifies those actions committed- to by NNECO in this                                           l l                 - document. Any other actions discussed in the submittal represent intended or                                          l j                   planned actions by' NNECO. They are described to the NRC for the NRC's                                                l l                   information and are not regulatory commitments. Please notify the Manager                                         -
l l                   Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions                                  l
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regarding this document or any associated regulatory commitments.                                                     !
;                        Number                                                         Commitment                        Due             l B16025-01                        A design review of the FWA system and                         Prior to enry into
!                                                    associated components will be performed.                           mode 4            l
!                   B16025-02                        Design modifications required to restore                      Prior to enry into     !
i                                                    the FWA system to its design basis will be                         mode 4 identified.
;                   816025-03                        The FWA system will be restored to its design                 Prior to declaring i                                                    basis requirements.                                             FWA system l                                                                                                                   operable for all l-                                                                                                                  modes of plant i                                                                                                                      operation
;                   B16025-04                        The RCS will be maintained at less than                               N/A l                                                    200 F until the design basis requirements i                                                    have been restored for the FWA system.
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