ML20234E591
| ML20234E591 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/30/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-83-37, NUDOCS 8707070619 | |
| Download: ML20234E591 (4) | |
Text
{{#Wiki_filter:e ..o-Dunn POWER COMPANY ; P.O.'DOX 33189 - CHARLOTTE, N.O. 28242 HALH. TUCKER, numm-nos permaneirr (7o4) 373-4531 WUE3 LEAR PRODEM7FICW ' June 30, 1987-U.S. Nuclear Regulatory Commission MDoctde & ConholiDesk M Washington, D.C. 20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Technical Specification Bases l for-RVLIS l Gentlemen: I ~!
- )
By letter dated July 31,'1984, Duke Power submitted proposed changes to the McGuire Nuclear Station Technical Specifications to incorporate operability and. -{ surveillance requirements for an additional subcooling Margin Monitor channel"and' j the Reactor Vessel Level Instrumentation System (RVLIS).. These proposed changes 1 were incorporated into the Technical Specifications by License Amendment numbers. i] 40 (Unit 1) and'21 (Unit 2) dated February 28, 1985. The' changes were consistent with the guidance contained in Generic Letter 83-37, however did not include the Bases for the Specifications. j Duke has developed Bases for the RVLIS and has incorporated them into the existing-Bases. 'As the Bases are not a part of the Technical, Specifications (in accordance with 10CFR 50.36(a)) and are therefore not incorporated-into the facility'oper- ) ating licenses, no license amendment is necessary prior to updating the Bases.. As / such, no ' analysis of significant hazards considerations pursuant to10CFR 50.91 is required. I 1 J Accordingly, the additional Bases to be incorporated into the existing Bases are .j attached. Please incorporate the new information into the Bases section of 1 McGuire's Technical Specification. f I -Very truly yours, i / ]6 Hal B. Tucker-JBD/199/j ge' W Attachment \\ 1 ,hl 8707070619 870630 ( PDR ADOCK 05000369 j p-PDR-t
Document Control Desk June 30,1987 Page 2 I xc: Dr. J. Nelson Grace Regional Administrator, Region II ) U.S. Nuclear Regulatory Commission 1 101 Marietta St. NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood 0.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. W.T. Orders NRC Resident Inspector McGui:e Nuclear Station J
(. l INSTRUMENTATION BASES MOVABLE INCORE DETECTORS (Continued) The OPERABILITY of this system is demonstrated by irradiating of the core. each detector used and determining the acceptability of its voltage curve. ForthepurposeofmeasuringF(Z)orFhafullincorefluxmapisused. 9 Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range channel is inoperable. 3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capa-bility is requirad to permit comparison of the measured response to that used in the design basis for the f acility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974. 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that suf ficient meteorological data are available for estimating potential radia-f tion doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972. 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50. 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTS 1(ON The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on select (d plant parameters to monitor and assess these variables following an accident. This capability is consis-tent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." McGUIRE - UNITS 1 and 2 B 3/4 3-3
INSTRUMENTATION BASES l The Reactor Vessel Level Instrumentation System (RVLIS) is designed to monitor the water level in the reactor vessel, or the void content under forced circulation conditions, during postulated accident conditions. The RVLIS was installed as a part of the Inadequate Core Cooling Instrumentation (ICCI) as required by NUREG-0737. The system consists of three level channels which indicate on the Inadequate Core Cooling Monitor. These channels are the upper range (64 - 120%), the lower range (0 - 70%), and the dynamic head (D/P) range (0 - 120%). The upper range and lower range channels are actually level measurements over a specific height of the reactor vessel with no reactor coolant pumps running. These channels indicate " invalid" with one or more reactor coolant pumps operating. The dynamic head channel indicates a differential pressure across the reactor core when the reactor ceolant pumps are operating and indicates " invalid" with no pumps running. The two channels that are required to be operable by Technical Specifications are the lower range and the dynamic head range. The upper range is not required because it does not serve to monitor or mitigate an Inadequate Core Cooling Incident. The upper range channel would be used to assist operators in venting noncondensible gases from the upper head of the reactor vessel; a level indication on the upper range channel would indicate thatothe core is covered, thus any ) inadequate core cooling event has been terminated. l 1 4 MCGUIRE - UNITS 1 AND 2-B 3/4 - 3a
INSTRUMENTATION BASES 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the detection instrumentation ensures that both adequate warning capability is available for prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge j extinguishing agent in a timely manner. Prompt detection and suppression of i fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. Fire detectors that are used to actuate Fire Suppression Systems represent a more critically important component of a plant's fire protection program than datectors thet are installed solely for early fire warning and notification. Consequently, the minimum number of OPERABLE fire detectors must be greater. The loss of detection capability for Fire Suppression Systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. 3/4.3.3.8 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid ef flue"ts during actual or potential releases of liquid effluents. The Alarm / Trip Se ?oints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS. 3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or pot'ential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive' gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 4 McGUIPE - UNITS 1 and 2 B 3/4 3-4 .}}