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NUCLEAR REGULATORY COl.*MisslON 5 *?;%ny usuunnon. v. c. m 4 n+~.(##
%,,, g December 8, 1977 MEMORANDUM FOR:
$c-. Sniezek, Assistant Director for Field Coordination, DROI, IE i
'FROM:
K. R. Goller, Assistant Director for Operating Reactors DDR, NRR
SUBJECT:
TECHNICAL SPECIFICATIONS FOR lilNIMUM CRITICAL POWER RATIO (MCPR) b In response to your memorandum dated October 7,1977 on the above subject, we have reviewed the requirement that a licensee restore MCPR to within the required limits in two hocrs or be in cold shutdown within the succeeding 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
We find that the above requirement resulted from our February 1976 letter to BWR licensees which requested them to propose uniform remedial action statements for their Technical Specifications in the event that limits for MCPR, Minimum Average Planar Linear Heat Generation Rate (MAPLHR), or LHGR were violated.
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The Stancard Technical Specifications (STS) currently require only a reduction in power until MCPR. is restored. Existing " custom" MCPR Technical Specifications, which were the result of our February 1976 letter, are more severe.
However, this severity is more hypothetical than real since no ' reactor facility, to our knowledge, has had to shutdown-as a. result of a MCPR violation.
If you are aware of any facilities that have had to shutdown as a result of a MCPR violation, pidase provide us the appropriate information.
With regard to implen,entation of the STS position, we are continuing our program of converting existing " custom" Technical Specifications to STS (at the initiative of the licensees); Nine Mile Point is currently undergoing this~ process. Upon adoption of the STS by Nine Mile Point and other operating BWR facilities, the modified M:PR requirement (rssulting in a power reduction rather than a shutdown requirement) together with a number of other improvements, will be implemented.
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k:A Karl R. Golle, Assistant Director for Operati g Reactors Division of 0;erating Reactors e707090085 070701 PDR FDIA WILLIAM 87-121 PDR
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