ML20084R969
| ML20084R969 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/30/1995 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084R972 | List: |
| References | |
| NUDOCS 9506090478 | |
| Download: ML20084R969 (9) | |
Text
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UNITED STATES g
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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; 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.
950609047a 950530 PDR ADOCK 05000382 p
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.107, 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.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION cks R(&
Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 30, 1995
9 ATTACHMENT TO LICENSE AMENDMENT NO.107 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
REMOVE PAGES INSERT PAGES V
V 3/4 3-34 3/4 3-34 8 3/4 3-2 8 3/4 3-2
. ~.
JNDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE RE0VIREMENTS i
SECTION EA_Q1 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................
3/4 2-1 3/4.2.2 PLANAR RADIAL PEAXING FACT 0RS...........................
3/4 2-3 3/4.2.3 AZIMUTHAL POWER TILT....................................
3/4 2-4 3/4.2.4 DNBR MARGIN.............................................
3/4 2-6 3/4.2.5 RCS FLOW RATE...........................................
3/4 2-10 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................3/4 2-11 3/4.2.7 AXIAL SHAPE INDEX.......................................
3/4 2-12 3/4.2.8 PRESSURIZER PRESSURE....................................
3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................
3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION................. 3/4 3-28 SEISMIC INSTRUMENTATION..............................
3/4 3-35 METEOROLOGICAL INSTRUMENTATION.......................
3/4 3-38 REMOTE SHUTDOWN INSTRUMENTATION...................... 3/4 3-41 ACCIDENT MONITORING INSTRUMENTATION..................
3/4 3-44 CHEMICAL DETECTION SYSTEMS...........................
3/4 3-47 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............
3/4 3-60 3/4.3.4 DELETED.................................................
3/4 3-68 WATERFORD - UNIT 3 V
Amendment No. 50,68,103,104,107
=
INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE DEQUIREMENTS SECTION PAGE 3/4. 4 REACTOR COOLANT SYSTEM 3/4. 4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.............................
3/4 4-1 HOT STANDBY.............................................
3/4 4-2 HOT SHUTD0WN............................................
3/4 4-3 COLD SHUTDOWN - LOOPS FI LLED............................ 3/4 4-5
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COLD SHUTDOWN - LOOPS NOT FILLED........................
3/4 4-6 3/4.4. 2 SAFETY VALVES SHUTD0WN.............................................
3/4 4-7 0,PERATING............................................
3/4 4-8 3/4.4.3 PRESSURIZER PRESSURIZER..........................................
3/4 4-9 AUXILIARY............................................
3/4 4-9a 3 /4. 4. 4 STEAM GENERATORS........................................
3/4 4-10 3,/4. 4. 5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAG E DETECTION SYSTEMS............................
3/4 4-17 OPE RATI ONAL LE A KAG E.................................. 3/4 4-18 3/4.4.6 CHEMISTRY...............................................
3/4 4-21 3/4. 4. 7 SPECIFIC ACTIVITY.......................................
3/4 4-24 3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM...............................
3/4 4-28 PRESSURIZER HEATUP/C00LDOWN..........................
3/4 4 33 OVERPRESSURE PROTECTION SYSTEKS......................
3/4 4-34 3/4.4.9 ST R U CTU RAL I NT E G RI TY....................................
3/4 4-36 3/4.4.10 REACTOR COOLANT SYSTEM VENTS............................
3/4 4-37 3 /4. 5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS..................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Modes 1. 2. and 3....................
3/45-3 I
3/4.5.3 ECCS SUBSYSTEMS - Modes 3 and 4........................
3/4 5-8 3/4.5.4 REFUELING WATER STORAGE P00L............................
3/4 5-9 WATERFDRD - UNIT 3 VI Amendment No. 22.34
l All!I 4.3 3 (tunt inucil)
RAD.IAl_ ION MONilHRINf; INNIRUMINIAllDN SURV1lilANCI RLQUIRLMENTS tilANNil MODES FOR WHICil
( llANNI I I IIANNI I IUNLI10NAL SURVEIILANCE INSTRUMENT f lilI K LAIIHRAI10N 11 Si 15 REQUIRED __
3.
EFFLUENT ACCIDENT MONITORS Containment High Range H
Q 1, 2, 3, & 4 l
a.
b.
Plant Stack High Range 5
R Q
1, 2, 3, & 4 l
c.
Condenser Vacuum Pump High Range S
R Q
1, 2, 3, & 4 l
d.
Fuel Handling Building Exhaust High Range S
R Q
1*,
2*, 3*, & 4*
l Main Steam Line High Range S
R Q
1, 2, 3, & 4 l
e.
- With irradiated fuel in the storage pool.
WATERFORD - UNIT 3 3/4 3'-33 Amendment No. 96
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This paae has been deleted.
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i WATERFORD - L5flT 3 3/4 3-34 AMENDMENT NO. 7b90,107 s
a 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION The OPERABILITY of the Reactor Protective and Engineered Safety Features Actuation Systems instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter tonitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.
The redundancy design of the Control Element Assembly Calculators (CEAC) provides reactor protection in the event one or both CEACs become inoperable.
If one CEAC is in test or inoperable, verification of CEA position is performed at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If the second CEAC fails, the CPCs will use DNBR and LPD penalty factors to restrict reactor operation to some maximum fraction of RATED THERMAL POWER.
If this maximum fraction is exceeded, a reactor trip will occur.
The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standarcs.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
The quarterly fre-quency for the channel functional tests for these systems comes from the analy-ses presented in topical report CEN-327: RPS/ESFAS Extended Test Interval Evaluation, as supplemented.
The treasurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is Completed within the time limit assumed in the safety analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping, or total channel test treasurements provided that such tests demonstrate the total channel response time as defined.
Sensor response tin,e verification say be demonstrated by either (1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.
3/4.3.3 MDNITORING INSTRUMENTATION 3/4.3.3.1 RADIATION M3NITORING INSTRUMENTATION ine OPERASILITY of the radiation monitoring channels ensures that:
(2) the raciation levels are continually measured in the areas served by the WATERFOC - UN:T 3 E 3/4 3-2 MENOMENT ND.69
INSTRUMENTATION BASES individual channels; (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these 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 and Environs Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.
3/4.3.3.2 INCORE DETECTORS This section has been deleted.
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 capability is required to permit ccmparison of the measured response to that used in the design basis for the facility 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 Earthquakes," April 1974.
3/4.3.3.4.
METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological 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 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 Part 50.
I WATERFORD UNIT 3 B 3/4 3-2 AMENDMENT NO.107
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