ML20127E702
| ML20127E702 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/06/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| References | |
| TAC-56816, NUDOCS 8506240625 | |
| Download: ML20127E702 (2) | |
Text
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June 6, 1985 Docket No. 50-344 DISTRIBUTION:
DOC RI; FILE-JPartlow Mr. Bart D. Withers NRC PDR LMLazo Vice President Nuclear Local PDR PMKreutzer Portland General Electric Company ORB #3 Rdg ACRS +10 121 S. W. Salmon Street HThompson Gray File Portland, Oregon 97204 OELD EJordan
Dear Mr. Withers:
BGrimes
SUBJECT:
TECHNICAL SPECIFICATIONS FOR REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIME SURVEILLANCE REQUIREMENTS It has come to our attention that the specified response time requirement for the overtemperature a T trip function was incorrectly specified in Tech-nical Specifications for some Westinghouse plants. We believe this is the case for Trojan.
In some instances, this response time has been specified as less than or equal to 6 seconds on the bases that the safety analysis as documented in Chapter 15 of the FSAR notes that assumed time delay for this trip function is 6 seconds. The safety analysis assumption for the response time of this trip function includes a 2 second delay which is attributable to primary coolant sample transport and thermal lag response delays associated with the RTD bypass manifold measurement of reactor coolant temperature. Since the Reactor Trip System Response Time is defined in the technical specifications as the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor (emphasis added) until the loss of stationary gripper coil voltage, the transport and thermal lag delays associated with this trip function are excluded from the response time surveillance require-ments. Therefore, the Westinghouse Standard Technical Specifications, NUREG-0542, presents 4 seconds as the appropriate response time surveillance requirement for this trip function.
You are requested to review the technical specification requirements for your plant and confirm that the response time surveillance requirement is appropriate and consistent with the definition of the reactor trin system response time and is conservative by at least 2 seconds less than the safcty analysis assumptions applicable for this trip function. Should you find that an appropriate response time has not been specified in the technical specification, a license change request should be submitted on a schedule as negotiated with the Project Manager assigned to your facility.
Sincerely, Orfhfneisf ned by:
2 Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
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cc: See next page 0
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Mr. Bart D. Withers Trojan Nuclear Plant Portland General Eletric Company Senior Resident Inspector
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U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chainnan Board of County Commissioners Columbia County St. Helens, Oregon 97501 William T. Dixon Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 Regional Administrator USNRC, Region V Office of Executive Director for Operations 1450 Maria Lane, Suite 210 Walnut Creek, California 94596