ML17278B175
| ML17278B175 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/21/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278B176 | List: |
| References | |
| TAC-61222, NUDOCS 8702030469 | |
| Download: ML17278B175 (21) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PPOlECT I'IO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
36 License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Puhlic Power Sup-ply System (the Supply System, also the licensee),
dated April 8, 1986, as clarified by letter dated November 20,
- 1986, complies with the standards and requirements of the Atomic Energy Act of ]954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of the Facility Operating License No. NPF-21 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
36, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
870P030469 870121 PDR
- DOCK 05000397 P
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Elinor G. Adensam, Director BWR Project Directorate No.
3 Division of BWR Licensing Date of Issuance:
January 2l, lg87
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ENCLOSURE TO LICENSE AMENDMENT NO.
FACILITY OPERATIN('ICENSE NO.
NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE vi X111 3/4 3-78 3/4 7-6 3/4 7-7 B 3/4 3-5 B 3/4 3-6 B 3/4 3-7 INSERT V1 X111 3/4 3-78 3/4 7-6 3/4 7-7 B 3/4 3-5 B 3/4 3-6 B 3/4 3-7
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............
3/4 3"1 3/4.3. 2 ISOLATION ACTUATION INSTRUMENTATION......; 3/4 3"10 3/4.3. 3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..
3/4 3-25 3/4. 3. 5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION......,......:.
3/4.3.6 CONTROL, ROD BLOCK INSTRUMENTATION.
3/4. 3. 4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation..
End-of-Cycle Recirculation Pump Trip System Instrumentation.
3/4 3"37 3/4 3-41 3/4 3-47 3/4 3-52 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....
Seismic Monitoring Instrumentation.
Meteorological Monitoring Instrumentation..
Remote Shutdown Monitoring Instrumentation.
Accident Monitoring Instrumentation..
Source Range Monitors.......
Traversing In-Core Probe System.
Fire Detection Instrumentation.
Loose-Part Detection System..
Radioactive Liquid Effluent Monitoring Instrumentation..
Radi oacti ve Gaseous Effluent Honitoring Instrumentation..
3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.
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3/4 3-58 3/4 3-61 3/4 3"64 3/4 3"67 3/4 3-70 3/4 3"76 3/4 3-77 3/4 3-79 3/4 3-83 3/4 3-84 3/4 3"89 3/4 3-96 3/4.3.9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...................
3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION.....
3/4 3-98 3/4 3-102 WASHINGTON NUCLEAR - UNIT 2 vl Amendment No.
36
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INO EX BASES SECTION INSTRUMENTATION (Continued)
PAGE 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......
Seismic Monitoring Instrumentation.........
Meteorological Monitoring Instrumentation..
Remote Shutdown Monitoring Instrumentation.
Accident Monitoring Instrumentation........
Source Range Monitors.........,........
Traversing In-Core Probe System.................
Fire Detection Instrumentation..................
Loose-Part Detection System.
Radioactive Liquid Effluent Moni'toring Instrumentation.......
Radioactive Gaseous Effluent Monitoring Instrumentation...
B 3/4 3"4 B 3/4 3"4 B 3/4 3"5 B 3/4 3-5 B 3/4 3"5 B 3/4 3"5 B 3/4 3"5 B 3/4 3"6 B 3/4.3-6 B 3/4 3-6 B 3/4 3-7 TURBINE OVERSPEED PROTECTION SYSTEM.............
B 3/4 3-7 3/4. 3. 8 3/4. 3. 9 FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.......................
B 3/4 3"7 B 3/4 3-7 3/4;3.10 NEUTRON FLUX MONITORING INSTRUMENTATION....-....
3/4. 4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.;......................
B 3/4 4" 1 3/4.4.2 SAFETY/RELIEF VALVES..................
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4"1 3/4.4. 4 Leakage Detection Systems.......................
Operational Leakage.....'........................
CHEMISTRY..................................
8 3/4 4-2 B 3/4 4-2 B 3/4 4"2 3/4.4. 5 SPECIFIC ACTIVITY.
3/4.4. 6 3/4.4. 7 PRESSURE/TEMPERATURE LIMITS..........
MAIN STEAM LINE ISOLATION VALVES.
B 3/4 4"3 B 3/4 4"4 B 3/4 4"5 WASHINGTON NUCLEAR " UNIT 2 X111 Amendment No.
36
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This page intentionally blank WASHINGTON NUCLEAR " UNIT 2 3/4 3"78 Amendment No.
36
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (2} following painting, fire, or chemical release in any ventilation zone communicating with the train by:
1.
Verifying that the train satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05K and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978 when operating at a flow rate of 1000 cfm + 10K.
d.
e.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C. 6. a of Regulatory Guide 1. 52, Revision 2, March 1978, for a methyl iodide penetration of less than 1.0X; and 3.
Verifying a tr ain flow rate of 1000 cfm + lOX during train operation when tested in accordance with ANSI N510-1980.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Positon C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position. C.6 '
of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1.0X.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches water gauge while operating the train at a flow rate of 1000 cfm + 10K.
WASHINGTON NUCLEAR - UNIT 2 3/4 7-6 Amendment No. 36
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 2.
Verifying that on each of -the below pressurization mode actuation test signals, the train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch water gauge relative to the outside atmosphere during train operation at a flow rate less than or equal to 1000 cfm:
a)
Drywell pressure-high, b)
Reactor vessel water level-low, and c)
Reactor Building exhaust plenum-high radiation.
3.
Verifying that the heaters dissipate 5.0 + 0.5 kW when tested in accordance with ANSI N510-1980.
f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05%
in accordance with ANSI N510-1980 while operating the train at a flow rate of 1000 cfm + lOX.
g.
After each complete.or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the train at a flow rate of 1000 cfm + 10K.
WASHINGTON NUCLEAR " UNIT 2 3/4 7-7 Amendment No.
36
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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4. 3.7. 3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radiation 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.
This instrumentation is consistent with the recommendations of Regulatory Guide l.23, "Onsite Meteorological Programs,"
- February, 1972.
3/4. 3. 7. 4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit 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 Appendix A to 10 CFR Part 50.
.3/4. 3. 7. 5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the acci'dent monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.
This capability is consistent 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-0737, "Clarification of TMI Action Plan Requirements,"
November 1980.
3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.
At these power levels, reactivity additions shall not be made without this flux level information available to the operator.
Mhen the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN"CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distz'ibution of the reactor core.
WASHINGTON NUCLEAR - UNIT 2 B 3/4 3-5 Amendment No. 36
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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4. 3.7. 8 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 f'ire detectors, will discharge extinguishing agent in a timely manner.
Prompt detection and suppression of 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 detectors that are installed solely for early fire warning and noti.fication.
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 war rented 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 unt'il the inoperable instrumentation is restored to OPERABILITY.
3/4.3.7.9 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1. 133, "Loose-Part Detection Program for the Primary System of Light-Mater-Cooled Reactors,"
May 1981.
3/4.3.7.10 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of 'radioactive materials in liquid effluents during actual or potential releases of liquid 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.
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.
WASHINGTON NUCLEAR - UNIT 2 B 3/4 3-6 Amendment No. 36
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INSTRUMENTATION
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BASES MONITORING INSTRUMENTATION (Continued) 3/4. 3.7. 11 RADIOACTIVE 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 potential releases of gaseous effluents.
The alarm/
trip setpoints for these instruments shall be calculated and adjusted in ac-cordance 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.
3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are.
. OPERABLE and will protect the turbine from excessive overspeed..
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.
3/4.3.9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater system/main turbine trip system actuation instrumentation is provided to initiate the feedwater system/main turbine trip system in the event of'eactor vessel water level equal to or greater than the level 8
setpoint associated with a feedwater controller failure.
3/4. 3. 10 NEUTRON FLUX MONITORING INSTRUMENTATION At the high power/low flow corner of the operating
- domain, a small prob-ability of limit cycle neutron flux oscillations exists depending on combina-tions of operating conditions (e.g.,
rod patterns, power shape).
To provide assurance that neutron flux limit cycle oscillations are detected and sup-
- pressed, APRM and LPRM neutron flux noise levels should be monitored while operating in this region.
Stability tests at operating BWRs were reviewed to determine a generic region of the power/flow map in which surveillance of neutron flux noise levels should be performed.
A conservative decay ratio of 0.6 was chosen as the bases for determining the generic region for surveillance to account for the plant to plant variability of decay ratio with core and fuel designs.
This generic region has been-determined to correspond to a core flow of less than or equal to 45K of rated core flow and a thermal power greater than that specified in Figure 3.4. 1. 1-'1 (Reference).
WASHINGTON NUCLEAR " UNIT 2 B 3/4 3-7 Amendment No.
36
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