View source for BECO-87-153, Supplemental Application for Amend to License DPR-35, Revising Tech Spec Section 3.12.B.b to Requirement Orderly Shutdown Reactor If Backup Fire Water Supply Sys Not Established within 24 H of Suppression Sys Inoperability

{{Adams
| number = ML20235E416
| issue date = 09/21/1987
| title = Supplemental Application for Amend to License DPR-35, Revising Tech Spec Section 3.12.B.b to Requirement Orderly Shutdown Reactor If Backup Fire Water Supply Sys Not Established within 24 H of Suppression Sys Inoperability
| author name = Bird R
| author affiliation = BOSTON EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000293
| license number = 
| contact person = 
| document report number = BECO-87-153, NUDOCS 8709280109
| package number = ML20235E418
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 2
| project = 
| stage = Supplement
}}

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* j Ralph G. Bird senior Vice President - Nuclear h           4 September 21, 1987 BECo 87-153                     ,
                    ,0. S. Nuclear Regulatory Commission a                   ' Document Control Desk hlashington' DC 20555 1
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,                                                                                            License DPR-35 Docket 50-293 Sucolement to Technical Specification f   3.12.B.b Fire Hater Sucoly System

==Dear Sir:==

The enclosed supplemental change to Technical Specification (TS) 3.12.B.b is being submitted at the request of the NRC staff (R. Nessman on 8/11/87) and                            i revises the proposed changes Boston Edison (BECo) previously submitted on May 22, 1987. The changes are indicated by revision bars in the margins of the affected pages.
1 The requested change revises the proposed action statement in Section 3.12.B.b. by reinserting a requirement to orderly shutdown the reactor if the backup Fire Hater Supply System is not established within 24 hours of the Fire Suppression Water System becoming inoperable. The requirement exists in the current TS Section 3.12.B.b but was not included in the proposed changes submitted on May 22, 1987. The requirement was not part of the May submittal l
because BECo's position was that 10CFR50.36 automatically mandated an orderly                           ;
reactor shutdown if a Limiting Condition for Operation (LCO) was not met. The NRC staff, however, requested that specific language mandating the shutdown be retained in the Technical Specification.
The supplemental wording shown on the attached proposed Technical Specification page 206a is an identical restatement of the wording contained in the currently approved Technical Specification. The proposed change neither relaxes any existing requirement nor increases requirements above those currently contained in the Technical Specification. The proposed change maintains the same degree of conservatism as in the current TS and is encompassed by the "no significant hazards evaluation" already provided in our May 22 submittal.
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t This. supplemental' change also includes a revised ' Bases' section for Technical Specification: Section 3/4.12B shown on the attached.page 2061. The revision?
provides additional ~ information to clarify .the source of. the backup Fire Water              i Supply System which is identified in Section 3.12.B.b.
An application fee was previously provided with our May 1987 submittal. No additional fee is deemed necessary for this supplemental information since it is being provided at the request'of the NRC staff.
                                                                $4-R. G. Bird
' Attachments: Technical- Specification Pages 206a, 2061 and 2061-1 cc: Mr. R. H. Hessman, Project Manger Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 U. S. Nuclear Regulatory Commission Region I                                                                                     l 631 Park Avenue                                                                              I King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station TAV/amm/985 i
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