ML20079C713

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Forwards Revised Pages to 910410 Proposed Change to Facility Reactor Coolant Leakage Detection Systems Tech Spec
ML20079C713
Person / Time
Site: Pilgrim
Issue date: 06/13/1991
From: Gina Davis
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20079C714 List:
References
BECO-91-77, NUDOCS 9106250191
Download: ML20079C713 (2)


Text

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BOSTON EDISON rmgom Nuc a.m rene, stimon Hot ky Hal Hcmd rn mouth, Massachusetts 02300 George W. Davis June 13, 1991 sem vu mm'ent No"er BECo 91- 77 U.S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555 License DPR-35 Docket 50-293 l

Addenda to Proposed Change to the Reactor Coolant Leakage Detection Systems Technical Specifications for the Pilgrim Nuclear Power Station In response to a request from your staff, Boston Edison Company is providing revised pages to our April 10, 1991 proposed change to the Pilgrim reactor coolant leakage detection systems tehnical specification.

Specifically, in section 3.6.C.1.a.4, on page 125a, "within" is substituted for the words " averaged over" in reference to the 2gpm increase in unidentified leakage in a 24-hour period. The associated bases paragraph on page 144 is also changed accordingly.

These revised words should clarify our intent to keep within the guidelines of published NRC documents regarding reactor coolant leakage detection systems limiting conditions of operation. This change does not affect the determination of no significant hazards consideration provided in our April 10, 1991 proposal.

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cc: Mr. R. Eaton, Project Manager Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Mail Stop: 1401 U. S. Nuclear Regulatory Connission 1 White flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident inspector Pilgrim Nuclear Power Station l