Text

Amend 143 to License NPF-21,modifying Index of WNP-2 TS by Deleting Ref to Bases Pp
	ML17291B133
Person / Time
Site:	Columbia
Issue date:	11/24/1995
From:	Clifford J; NRC (Affiliation Not Assigned)
To:	;
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ML17291B134	List: ML17291B133; ML17291B135;
References
	NUDOCS 9512040095
	Download: ML17291B133 (18)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 ASHINGTON PUBLIC POWER SUPP Y SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT 0.

MENDMENT TO FACILIT OPERATING LICENS Amendment No. 143 License No.

NPF-21 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Washington Public Power Supply System (licensee) dated June 6,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, 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 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; 0.

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 Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.

NPF-21 is hereby amended to read as follows:

95i2040095 95ii24 PDR ADQCK 05000397 P

PDR

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(2) echnical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

143 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 amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ja es M. Cliff d, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 24, 1995

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T ACHMENT TO ICENSE AMENDMENT MENDMENT NO.

143 TO FACILITY OPERATING LICENSE 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 areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

EMOV NSERT iV X11 Xii 1 XiV XV XV1 XV11 XV111

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Xix XX xx(a)

XX1 XX11 XX111 XX1 V 1V X11 X111 X1V XV XV1 XV11 XV111 X1X XX

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INDE SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTIO 1

SAFE Y

I I S

AGE THERMAL POWER, Low Pressure or Low Flow...................

2-1 THERMAL POWER, High Pressure and High Flow................

2-1 Reactor Coolant System Pressure...........................

2-1 Reactor Vessel Water Level................................

2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints.......

2-3 WASHINGTON NUCLEAR UNIT 2 iv Amendment No.

143

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTIDN 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 PRIMARY CONTAINMENT INTEGRITY................

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM..................

3/4. 10. 3 SHUTDOW MARGIN DEMONSTRATIONS...............

3/4. 10. 4 RECIRCULATION LOOPS.....

3/4. 10. 5 OXYGEN CONCENTRATION.........................

3/4.10.6 TRAINING STARTUPS.....-...>>....... -.---.-..-.

3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUENTS Liquid Ho1dup Tanks..............'.....................

3/4 11.2 GASEOUS EFFLUENTS Exp1osl ve Gas Mixture.................................

Mann Condenser........................................

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING Entire section re1ocated to ODCM.

PAGE 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 3/4 10-5 3/4 10-6 3/4 11-1 3/4 11-2 3/4 11-3 WASHINGTON NUCLEAR - UNIT 2 Amendment No. 98

INDE DESIGN FEATURES

~SECTIO 5.

SITE

~AG xclusion Area...............................................

E 5-1 Low Population Zone..........................................

5-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents...............................

5-1 5.

CONTAINMENT C f C'

onfsguratson................................................

5-1 Design Temperature and Pressure..............................

5-1 Secondary Containment........................................

5-1 5.3 REACTOR CORE Fuel Assembl)es..............................................

5-5 Control Rod Assemblies..........

5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature..............................

5-5 olume.......................................................

V

5. 5 METEOROLOG ICAL TOWER LOCATION................................

5-6 5.6 FUEL STORAGE C t

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5-6 rainage.....................................................

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5-6 5.

COMPONENT CYCLIC OR TRANSIENT LIMIT..........................

5-6 WASHINGTON NUCLEAR UNIT 2 X11 Amendment No. i43

INDEX ADMINISTRATIVE CONTROLS SECT IOlf PAGE 6.

. ESPONSIBILITY.............................................

6-1

~6.2 IIA AAIIATI...............................................

6-2 6.2.1 6.2.2 6.2.3 OFFSITE AND ONSITE ORGANIZATIONS......................

6-1 NIT STAFF............................................

6-1 U

NUCLEAR SAFETY ASSURANCE GROUP........................

6-7 UNCTION ~ ~

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6 7 RESPONSIBILITIES o ~

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o 6-7 ECORDS...............................................

6-7 R

6.2.4 SHIFT TECHNICAL ADVISOR...............................

6-7 6.3 UNIT STAFF UALIFICATIONS.................................

6-7

.4 TRAINING....................................................

6-8 6

6.5 REVIEW AND AUDIT.........................................'..

6-8 6.5.1 PLANT OPERATIONS COMMITTEE (POC)......................

6-8 UNCTION ~ o o ~

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COMPOSITION....................................

6-8 ALTERNATES............................................

6-8 MEETING FREQUENCY.............................

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6 8 RESPONSIBILITIES......................................

6-9 ECORDS...............................................

6-10 R

6.5.2 CORPORATE NUCLEAR SAFETY REVIEW BOARD (CNSRB).........

6-10 UNCTION..............................................

6-10 F

COMPOSITION...........................................

6-10 ALTERNATES............................................

6-10 CONSULTANTS...........................

. 6-11 WASHINGTON NUCLEAR-UNIT 2 X11i Amendment No. 94,143

NDEX DMINISTRATIVE CONTROLS SECTION PAGE CO ORATE NUC AR SAFETY REVIEW BOARD (Continued)

MEETING FREQUENCY....................................

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EVIEW...............................................

6-11 R

UDITS......~........................................

6-12 A

ECORDS..............................................

6-13 R

6.6 REPORTABLE OCCURRENCE ACTION..............................

6-13 6.7 SAFETY LIMIT VIOLATION.........................

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6 14 6.8 PROCEDURES AND PROGRAMS...................................

6-14 6.9 REPORTING RE UIREMENTS....................................

6-16 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...........

6-16 STARTUP REPORT...........................

6-16 ANNUAL REPORTS.......................................

6-16 MONTHLY OPERATING REPORTS 6-17 REPORTABLE OCCURRENCES...............................

6-17 PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP............

6-17 THIRTY DAY WRITTEN REPORTS...........................

6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING EPORT...............................................

6-18 R

RADIOACTIVE EFFLUENT RELEASE REPORT..................

6-19 6.9.2 SPECIAL REPORTS.........................................

6-20 6.9.3 CORE OPERATING LIMITS REPORT............................

6-20 6.10 RECORD RETENTION.........................................

6-22 6.11 RADIATION PROTECTION PROGRAM.............................

6-24 6.12 HIGH RADIATION AREA......................................

6-24

6. 13 PROCESS CONTROL PROGRAM..................................

6-25 6.14 OFFSITE DOSE CALCULATION MANUAL..........................

6-25 WASHINGTON NUCLEAR UNIT 2 Xiv Amendment No. 94-,98, 143

LIST OF FIGURES IGUR INDEX PAGE 3.1.5-1 3.1.5-2 3.2.1-1 3.2.1-2 3.2.1-3 3.2.1-4 3.2.1-5 3.2.1-6 3.2.1-7 3.2.1-8 3.2.3-1 3.2.4-1 3.2.4-2 3.2.4-3 3.2.4-4 SODIUM PENTABORATE SOLUTION SATURATION TEMPERATURE........

SODIUM PENTABORATE TANK, VOLUME VERSUS CONCENTRATION RE(UIREMENTS..............................................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183.............................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233.............................

MAXIMUMAVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE BUNDLE EXPOSURE ANF 8x8 RELOAD FUEL.......................................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183......'...............................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233.....................................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAE BUNDLE EXPOSURE ANF 9X9 IX AND 9X9 9X FUELo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS BUNDLE AVERAGE EXPOSURE SVEA-96 LEAD FUEL ASSEMBLIES...........................................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS BUNDLE AVERAGE EXPOSURE GEll LEAD FUEL ASSEMBLIES......................................

REDUCED FLOW MCPR OPERATING LIMIT.........................

LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE ANF 8x8 RELOAD FUEL...............

LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE ANF 9x9-IX FUEL.'..................

LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE ANF 9x9-9X FUEL...................

LINEAR HEAT GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE SVEA-96 LEAD FUEL SSEMBLIES................................................

A 3/4 1-21 3/4 1-22 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted WASHINGTON NUCLEAR UNIT 2 xv Amendment No. 94, 143

LIST OF FIGURES Continued

~U~R 3.2.4-5 LINEAR HEAT GENERATION RATE (LHGR) LIHIT VERSUS AVERAGE PLANAR EXPOSURE GEl 1 LEAD FUEL ASSEHBLIES............................................

PAAG Deleted 3.2.6-1 3.2.7-1 3.2.8-1 OPERATING REGION LIMITS OF SPEC. 3.2.6................

3/4 2-6 OPERATING REGION LIHITS OF SPEC. 3.2.7................

3/4 2-8 OPERATING REGION LIHITS OF SPEC. 3.2.8................

3/4 2-10 3.4.1.1-1 OPERATING REGION LIHITS OF SPEC. 3.4.1.1..............

3/4 4-3a 3.4.6.1A 3.4.6.1B 3.4.6.1C MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE........................

MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE........................

PRESSURE/TEMPERATURE LIMITS FOR 8 EFPY TESTING AND NONNUCLEAR HEATING CURVES.................

3/4 4-20 3/4 4-21 3/4 4-22 4.7-1 3.9.7-1 HEIGHT ABOVE SFP WATER LEVEL VS.

HAXIHUH LOAD TO BE CARRIED OVER SFP......................................

3/4 9-10 SAMPLE PLAN 2)

FOR SNUBBER FUNCTIONAL TEST............

3/4 7-15 5.1-1 5.1-2 5.1-3 EXCLUSION AREA BOUNDARY...............................

LOW POPULATION ZONE...................................

UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LI(UID EFFLUENTS..............

5-2 5-3 5-4 WASHINGTON NUCLEAR UNIT 2 XV1

LIST OF TABLES INDEX TABLE PAGE SURVEILLANCE FRE(UENCY NOTATION..;......................

1-9 1.2 OPERATIONAL CONDITIONS..................................

1-,10 2.2.1-1 3.2.3-1 3,3.1-1 3.3.1-2 4.3.1.1-1 3.3.2-1 3 ~ 3 ~ 2 2

3

~ 3 ~ 2 3 REACTOR PROTECTION SYSTEM INSTRUMENTATION...............

REACTOR PROTECTION SYSTEM RESPONSE TINES................

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE(UIREMENTS...............................

3/4 3-2 3/4 3-6 3/4 3-7 ISOLATION ACTUATION INSTRUMENTATION.....................

3/4 3-12 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS...........

3/4 3-16 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME.....'.....

3/4 3-19 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS.....

2-4 HCPR OPERATING LIMITS FOR RATED CORE FLOW...............

Deleted 4.3.2.1-1 ISOLATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-22 3.3.3-1 3 ~ 3 ~ 3 2

3

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4.3.3.1-1 3.3.4.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.........................................

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS..............................

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EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES...

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE(UIREMENTS......

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.........................................

3/4 3-26 3/4 3-30 3/4 3-33 3/4 3-34 3/4 3-38 3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS......................

4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE RE(UIREMENTS...............

3/4 3-39 3/4 3-40 WASHINGTON NUCLEAR UNIT 2 XV11 t

Amendment No. 94-,139, 143

LIST OF TABLES Continued NDE 3.3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUHENTATION.......................................

PAGE 3/4 3-43 3.3.4.2-2 3.3.4.2-3 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TINES........................................

3/4 3-45 END-OF-CYCLE RECIRCULATION PUMP TRIP SETPOINTS........

3/4 3-44 4.3.4.2.1-1 3.3.5-1 3.3.5-2 4.3.5.1-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS.............................

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.......................................

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS.............................

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE(UIREHENTS.............

3/4 3-46 3/4 3-48 3/4 3-50 3/4 3-51 3.3.6-1 3.3.6-2 4.3.6-1 3.3.7.1-1 4.3.7.1-1 3.3.7.3-1 4.3.7.3-1 3.3.7.4-1 4.3.7.4-1 CONTROL ROD BLOCK INSTRUMENTATION.....................

3/4 3-53 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS...........

3/4 3-55 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................

3/4 3-56 RADIATION MONITORING INSTRUMENTATION..................

3/4 3-59 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-60 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE RE(UIREHENTS.............................

3/4 3-66 REMOTE SHUTDOWN MONITORING INSTRUMENTATION............

3/4 3-68 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-69 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-65 WASHINGTON NUCLEAR UNIT 2 XV111 Amendment No. 48k, 143

LIST OF TABLES Continued

~NO E

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3.3.7.5-1 4.3.7.5-1 3.3.7.12-1 4.3.7.12-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-74 EXPLOSIVE GAS MONITORING INSTRUMENTATION..............

3/4 3-80 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-81 PAGE ACCIDENT MONITORING INSTRUMENTATION...................

3/4 3-71 3.3.9-1 FEEDWATER SYSTEM/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.............................

3/4 3-85 3.3.9-2 FEEDWATER SYSTEM/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS...................

3/4 3-86 4.3.9.1-1 FEEDWATER SYSTEM/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................

3/4 3-87 3.4.3.2-1 3.4.3.2-2 3.4.4-1 4.4.5-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES......

3/4 4-11 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS.....................................

3/4 4-11 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM......................................

3/4 4-17 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS...............

3/4 4-14 WASHINGTON NUCLEAR UNIT 2 Xix Amendment No. 67-,98,143

IST OF TABLES Continued NDE

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4.4.6.1.3-1 3.6.3-1 3.6.5.2-1 3.7.8-1 4.8.1.1.2-1 4.8.2.1-1 3.8.4.2-1 ELETED ~ ~ ~ o ~ ~ o

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D PAG 3/4 4-22 BATTERY SURVEILLANCE RE(UIREHENTS................

PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES........................

3/4 8-14 3/4 8-23 PRIMARY CONTAINMENT ISOLATION VALVES..................

3/4 6-21 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES............................

3/4 6-39 AREA TEHPERATURE MONITORING...........................

3/4 7-31 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-9 3.8.4.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION............................................

3/4 8-26 5.7.1-1 6.2.2-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..................

5-7 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY..................................

WASHINGTON NUCLEAR UNIT 2 XX d tN.~,1431

ML17291B133

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