View source for 05000423/LER-1997-034, Forwards LER 97-034-01,documenting Condition That Was Determined at Millstone,Unit 3 on 970918.Attachment 1 to Ltr Contains Commitments in Response to Event

{{Adams
| number = ML20217F220
| issue date = 09/29/1997
| title = Forwards LER 97-034-01,documenting Condition That Was Determined at Millstone,Unit 3 on 970918.Attachment 1 to Ltr Contains Commitments in Response to Event
| author name = Hicks G
| 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 = B16777, NUDOCS 9710080020
| package number = ML20217F224
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 5
}}
{{LER
| Title = Forwards LER 97-034-01,documenting Condition That Was Determined at Millstone,Unit 3 on 970918.Attachment 1 to Ltr Contains Commitments in Response to Event
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000423
| LER year = 2097
| LER number = 34
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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September 29,1997 l                                                                                    Docket No. 50-423 l                                                                                                     S16777 Re: 10CFR 50.73(a)(2)(1)(B)
U. S. Nuclear Regulatoly Commission Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station Unit 3 Licensee Event Report 96-034-Q1 Submitted Pursuant to 10CFR 50.73(a)(2)(i)(B)
This letter forwards Supplement 1 to Licensee Event Report 96-034-00, documenting a condition that was determined at Millstone Unit No. 3 on                                          -
September 18, 1996.           This LER is submitted pursuant to 10CFR 50.73(a)(2)(i)(B). NNECO's     commitments in response to this event are contained within Attachment i to this letter.
Should you have any questions regarding this submittal, please contact Mr.
David A. Smith at (860) 437-5840.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
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==Attachment:==
: 1)         NNECO's commitments in response to LER 96-034-01
: 2)      LER 96 034-01 cc:     H. J. Miller, Region I Administrator A. C. Corne, Senior Resident Inspector, Millstone Unit No. 3 J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 W. D. Travers, Dr., Director, Special Projects Corrective Action Group Files (CR M3 97 2864) j

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Docket'No. 50-423                ;
B18777 l
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Attachment 1 4
MPhtone Nuclear Power Station, Unit No. 3 NNECO's Commitments Iri Response To (LER 9643441)                                                  ;
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                                                                                                                               .1 September 29,1997

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Enclosure
.                                             List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document. Any other actions discussed in the submittal represent intended or planned actions by NNECO. They are described to the NRC for the NRC's-information and are not regulatory commitments. Please notify the Manager -
Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.
Number                             Commitment                                          Due B15939-01     As a result of the September 18,1996 ovent, a                             Complete Technical Specifications Change was implemented on July 10,1997 that revised the setpoint value identified in Technical Specifications 3.4.9.3.a.2 and 3.4.9.3.a.3 from the current value of 450 psig to 2 426.8 psig and5: 453.2 psig.
B16777-01     Investigation into the cause of this event is                         Prior to entry into ongoing. A supplement to this report will be                               Mode 4 submitted based on the results of this investigation.
B167 77-02    The setpoint calculation will be revised to                           Prior to entry into incorporate the RHR pump suction relief valve                              Mode 4 temperature correction for the full temperature range.
_B16777-03     An evaluation of the RHR relief valve setpoint                       Prior to entry into effect on the RHR piping stress analyses will                              Mode 4 be performed.
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Millstone Nuclear Power Station, Unit No. 3                                                                                          -
NNECO's Submittal of                                                                                                   i (LER 94-03441)                                                                                                       T i
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