View source for BECO-87-141, Application for Amend to License DPR-35 Revising 870601 Application to Change Tech Specs 3.5.C.1 & 3.5.D.1 to Specify,Quantitatively,Reactor Operating Conditions for Which HPCI & RCIC Required to Be Operable

{{Adams
| number = ML20237L695
| issue date = 09/01/1987
| title = Application for Amend to License DPR-35 Revising 870601 Application to Change Tech Specs 3.5.C.1 & 3.5.D.1 to Specify,Quantitatively,Reactor Operating Conditions for Which HPCI & RCIC Required to Be Operable
| 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-87-141, NUDOCS 8709090041
| package number = ML20237L699
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 1
| project = 
| stage = Request
}}

=Text=
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10CFR50.90
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Executive Ofhces 800 Boylston Street                           -
E Boston, Massachusetts 02199 Ralph G. Bird Senior Vice President - Nuclear                                             BECo 87-141 U. S. Nuclear Regulatory Commission                                                                         7 Document Control Desk Washington, DC 20555                                                                    License DPR-35        i Docket 50-293 Revision to Clarify Proposed Technical Specification Changes Concernina HPCI and RCIC Operability

==Dear Sir:==
c By letter to the NRC dated June 1,1987, an amendment to the Pilgrim Nuclear                                   !
Power Station Technical Specifications was proposed to revise the pressure range over which the high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) systems are required to be operable. As discussed with Mr. R. H. Hessman on July 13, 1987, proposed changes to Technical Specifications 3.5.C.1 and 3.5.D.1 are hereby revised as shown on the attached pages to specify, quantitatively, the reactor operating conditions for which the hPCI and RCIC systems are required to be operable. Associated changes to Technical Specification Bases are included on attached Technical Specification Pages 116 and 117.
This revision to clarify the proposed changes to Technical ? specifications 3.5.C.1 and 3.5.D.1 does not impact the safety evaluation performed on the original proposed change and does not alter any other part of the remaining proposed change. This revision has been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.
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==Attachment:==
Revised Technical Specification Pages 107,108,116, and 117 for Proposed Change Concerning HPCI and RCIC Operability.
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      -nj o                        631 Park Avenue King of Prussia, PA 19406
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o                         Mr. R. H. Hessman, Project Manager
        ,g                         Division of Reactor Projects I/II w                            Office of Nuclear Reactor Regulation 80                           U. S. Nuclear Regulatory Commission
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