ML17291A840

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Proposed Tech Specs Index,Deleting Ref to Bases Pages
ML17291A840
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 06/06/1995
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A839 List:
References
NUDOCS 9506140362
Download: ML17291A840 (16)
v • d • e


Text

ATTACHMENT1 Proposed Changes to WNP-2 Technical Specification Pages iv through xxiv 4O3b2 q5ObOb O5OOO397 h

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ComaOiseD Core INDEX

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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION

2. 1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low Flow........... 2-1 THERMAL POWER, High Pressure and High Flow 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 8ASES 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or L~' 2"1 THERMAL POWER, High Pressu .'low.. 8 2-2 Reactor Coolant Sysi 8 2-5 Reactor Vesse> ~&+@ 8 2-5
2. 2 LIMITING . .(STEM SETTINGS Reac r Protection System Instrumentation Setpoints....... 8 2-6 WASHINGTON NUCLEAR UNIT 2 iv

cowmo<<cocovv INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY..................................:......... B 3/4 O-l 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN.................................. B 3/ 1-1 3/4.1. 2 REACTIVITY ANOMALIES............................. /4 1-1 3/4.1.3 CONTROL RODS................................... . B 3/4 1-2 3/4.1.4 CONTROL ROD PROGRAM CONTROLS................ .... B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM.....,.............. B 3/4 1-4 3/4.1. 6 FEEDWATER TEMPERATURE............. .......... 8 3/4 1"5 3/4.2 POWER D ISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GF RATE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

ge ~ ~ ~ ~ ~ ~ B 3/4 2-1 3/4. 2. 2 APRM SETPOINTS.........,.'INIMUM B 3/4 2-2 3/4.2.3 CRITICAL POW" B 3/4 2-3 3/4.2.4 LINEAR HEAT GENER',E................

I B 3/4 2-4 3/4. 2. 5 (RESERVED FOR P

3/4. 2. 6 POWER/FLOW CTY..................... B 3/4 2"4 3/4. 2. 7 STABILITY h.,.,>RING - TWO LOOP OPERATION.. B 3/4 2-5 3/4.2.8 STABILI MONITORING - SINGLE LOOP OPERATION..... B 3/4 2-5 3/4.3 INSTRUMENTAT N 3/4.3. 1 R TOR PROTECTION SYSTEM INSTRUMENTATION........ B 3/4 3-1 3/4.3.2 ISOLATION ACTUATIUi< INSTRUMENTATION.............. B 3/4 3-2 3/4. 3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................. 8 3/4 3"2

/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION.................................. B 3/4 3-,3 3/4. 3. 5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................ B 3/4 3-4 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION......................... B 3/4 3-4 WASHINGTON NUCLEAR " UNIT 2 X11 Amendment No. 77 h1AR 1 590

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Q CONTROLLED COPY IND X BASES SECTION PAGE

~Illa'UM NT TIGN (C ti d) 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......... B 3/4 3-4 Meteorological Monitoring Instrumentation.. ... B 3/4 3-5 Remote Shutdown Monitoring Instrumentati ..... B 3/4 3-5 Accident Monitoring Instrumentation... ........ B 3/4 3-5 Source Range Monitors.......... B 3/4 3-5 In-Core Probe Sysf 'raversing B 3/4 3-5 Loose-Part Detection B 3/4 3-6 Gas Honitorin'I1entation.......

Syste'xplosive B 3/4 3-6 i

3/4.3.8 TURBINE OVERSPEED PRi ~'SYSTEM............ B 3/4 3-6 j

3/4.3.9 FEEOWATER SYSTEH/F rINE TRIP SYSTEH ACTUATION INSTRU'...................... B 3/4 3-6

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3 4.4 REACTOR COOLANT SYST P

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3/4..4.1 RECIRCULATI '...........................

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B 3/4 4-1 3/4.4.2 SAFETY/RELI VALVES........................... B 3/4 4-1 3/4.4.3 REACTOR OLANT SYSTEH LEAKAGE Leakag Detection Systems...................... B 3/4 4-la Oper ional Leakage............................ B 3/4 4-2 3/4.4.4 CH ISTRY o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-2 3/4.4.5 ECI FIG ACTIVITY................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-3 3/4.4.6 PRESSURE/TEMPERATURE LIMITS....... B 3/4 4-4 3/4.4. HAIN STEAM LINE ISOLATION VALVES.. B 3/4 4-5 WASHINGTON NUCLEAR UNIT 2 X111 Amendment No. ~, -98I-, 13$

mezaOC<mCOf YO INOEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN.......... 8 /4 5-1 3/4.5. 3 SUPPRESSION CHAHBER............ -.... - -. - .. -. -. -. 8 3/4 5-2 3/4. 6 CONTAINHENT SYSTEMS 3/4.6. 1 PRIMARY CONTAINMENT Primally Containment Integrity....... 8 3/4 6-1 Primary Containment Leakage....... 8 3/4 6-1 Primary Containment Air Locks.... 8 3/4 6-1 MSIY Leakage Central System... 8 3/4 6-1 Primary Containment Structur' qrity......... 8 3/4 6-2 Drywell and Suppression Ct',,Eternal Pressur e...............g e s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ 8 3/4 6-2 Drywell Average Air Te'e..................

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8 3/4 6-2 Orywell and Suppres. A ,ner Purge System..... 8 3/4 6-2 3/4. 6. 2 DEPRESSURIZATION '

8 3/4 6-3 3/4. 6. 3 PRIMARY CONTAIh., VOLATION VALVES............. 8 3/4 6-4 3/4. 6. 4 VACUUM RELIEF.................................... 8 3/4 6-5 3/4. 6.5 SECONDARY C TAINMENT............................ 8 3/4 6-5 3/4.6.6 PRIMARY NTAINHENT ATMOSPHERE CONTROL........... 8 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 SER CE WATER SYSTEMS............................ 8 3/4 7"1 3/4.7.2 NTROL ROOM EMERGENCY FILTRATION SYSTEM......... 8 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEH............ 8 3/4 7-1 3/4.. 4 S NUBBERS......................................... 8 3/4 7-2 WASHINGTON NUCLEAR - UNIT 2 Xiv Amendment No. 100

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BASES SECTION PAGE PLANT SYSTEMS (Continued)

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3/4. 7. 5 SEALED SOURCE CONTAMINATION....... B 3/4 7-3 3/4.7.8 AREA TEMPERATURE MONITORING.................... B 3/4 7-4 3/4.7.9 MAIN TURBINE BYPASS SYSTEM...................-. B 3/4 7"4 3/4.8 ELECTRICAL POMER SYSTEMS 3/4. 8. 1, 3/4. 8. 2, and 3/4. 8. 3 A. C. SOURCES, 0. C. SOURCES', anr'OWER DISTRIBUTION SYSTEMS......... ~ ~ ~ B 3/4 8-1 3/4.8. 4 ELECTRICAL E(UIPMENT PROTF' VICES...... B 3/4 8-3

/ 4/9 3/4. 9 REFUELING OPERATIONS 3/4.9. I REACTOR MODE SMITCH: B 3/4 9"1 3/4.9.2 INSTRUMENTATION.i B 3/4 9-1 3/4.9.3 CONTROL ROD PP B 3/4 9-1 3/4 9-1

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9. 4 DECAY B TIME'/4.
9. 5 COMMUNICA'I B 3/4 9-1 3/4.9.6 'REFUELIN PLATFORM........................ B 3/4 9-2 3/4.9.7 CRANE RAVEL - SPENT FUEL STORAGE POOL.......... B 3/4 9"2 3/4.9.8 and /4.9.9 MATER LEVEL - REACTOR VESSEL d MATER LEVEL - SPENT FUEL STORAGE POOL....... B 3/4 9-2 3/4.9.1 CCNTROL ROD REMOVAL....-............ B 3/4 9-2 3/4..11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION... B 3/4 9-2 MASHINGTON NUCLEAR - UNIT 2 XV Amendment No. 47 MAY 2 g tggg

mm~ot~cD co~v INDEX BASES SECTION PAGE 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.................. B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM..-. B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATI~ B 3/4 10-1 3/4. 10. 4 RECIRCULATION LOOPS.... B 3/4 10"1 3/4. 10. 5 OXYGEN CONCENTRATION B 3/4 10-1 3/4. 10. 6 TRAINING STARTUPi 8 3/4 10-1 3/4. 11 RADIOACTIVE EFFLUENT'/4.

11. 1 LI(UID EF." B 3/4 ll-l 3/4. 11. 2 GAS EO',i\,

yV T B 3/4 11-1 3/4. 12 RADIOLOGICAL .ONMENTAI MONITORING Entire secti relocated to ODCM.

WASHINGTON NUCLEAR " UNIT 2 XV) Amendment No. 98

CONTROLLED COPY=~'IS, NNC I=-:-.~ S---.

INDEX Duly 14, 1994 LIST OF FIGURES FIGURE PAGE 3.2,4-5 LINEAR HEAT .GENERATION RATE (LHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE GE11 LEAD FUEL ASSEMBLIES . . . . . . . . . . . . . . . . . . . . . Deleted

3. 2. 6-1 OPERATING REGION LIMITS OF SPEC. 3.2.6 3/4 2-6 3.2.7-1 OPERATING REGION LIMITS OF SPEC.3.2.7 3/4 2-8 3.2.8-1 OPERATING REGION LIMITS OF SPEC.3<<2.8 ....... 3/4 2-10 3.4.1.1-1 OPERATING REGION LIMITS OF SPEC.3.4.1.1 3/4 4-3a 3.4.6.1 MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE 3/4 4-20
3. 4. 6.1.C PRESSURE/TEMPERATURE LIMITS FOR 8 EFPY TESTING AND NONNUCLEAR HEATING CURVES 3/4 4-21 a 4.7-1 SAMPLE PLAN') FOR SNUBBER FUNCTIONAL TEST . 3/4 7-15 3.9.7-1 HEIGHT ABOVE SFP MATER LEVEL VS. MAXIMUM LOAD TO BE CARRIED OVER SFP . 3/4 9-10 5.1-1 EXCLUSION AREA BOUNDARY . . . . . . . . , . . . . . . . 5-2 5.1-2 LOW POPULATION ZONE . . . . . . . . , . . . . . . . . . 5-3 5.1-3 UNRESTRICTED AREAS AND SITE BOUNDARY FOR

,RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS . . . . . . . . 5-4 MASHINGTON NUCLEAR UNIT 2 xx(a) Amendment No. 44; -H6-, 122

+CONTROLLED COPY

~INDE LIST OF TABLES PAG SURVEILLANCE FREQUENCY NOTATION . . . . . . . . . . . . . 1-9 1.2 OPERATIONAL CONDITIONS . . . . . . . . . . . . . . . . . 1-10 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS ... 2-4 3.2.3-1 MCPR OPERATING LIMITS FOR RATED CORE FLOW Deleted 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-2 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES 3/4 3-6 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-7 3.3.2-1 ISOLATION ACTUATION INSTRUHENTATION .......... 3/4 3-12 30302-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS . 3/4 3-16 3.3.2-3 ISOLATION SYSTEM" INSTRUMENTATION RESPONSE TIME . 3/4 3-19 4.3.2.1-1 ISOLATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-22 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION . 3/4 3-26 3 ~3 3 2

~ EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS . 3/4 3-30 3 ~3 ~3 3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES . 3/4 3-33 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-34 3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION . 3/4 3-38 3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS . 3/4 3-39 4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-40 WASHINGTON NUCLEAR UNIT 2 XX1 Amendment No. 94

CONTROLLED COPY INDEX LIST OF TABLES Continued TABLE PAGE 4.4.6.1.3-1 DELETED . 3/4 4-22 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES . 3/4 6-21 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES............. 3/4 6-39 3.7.8-1 AREA TEMPERATURE MONITORING . 3/4 7-31 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE 3/4 8-9 4.8.2.1-1 BATTERY SURVEILLANCE REQUIREMENTS . 3/4 8-14 3.8.4.2-1 PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES........... 3/4 8-23 3.8.4.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION . 3/4 8-26 5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.......... 5-7 6.2.2"1 SINGLE UNIT FACILITY..................

MINIMUM SHIFT CREW COMPOSITION 6-6 WASHINGTON NUCLEAR UNIT 2 XX1V Amendment No. ~, ~, ~ 122

I ATTACHME<NT2 Ba is F<or No Si nificant Hazards Consideration Determlriation In accordance with the criteria for a significant hazards consideration established in 10 CFR 50.92, the Supply System has evaluated the proposed amendment to the WNP-2 Technical Specification Index and determined that it does not represent a significant hazards consideration.

The following discussion is provided in support of this conclusion.

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed changes are administrative and do not remove 'or modify existing Technical Specification requirements or safety limits. There will be no changes to the physical design of the plant as a result of the proposed change. The Bases information, per 10 CFR 50.36(a), is not part of the Technical Specifications and will be consolidated into a controlled plant document. Future changes to the Bases will be evaluated per 10 CFR 50.59. Therefore, the proposed changes to the Technical Specification Index do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed changes are administrative and do not remove or modify existing Technical Specification requirements or safety limits. There will be no changes to the physical design of

- the plant or alteration of any operational practice as a result of the proposed change. The Bases information, per 10 CFR 50.36(a), is not part of the Technical Specifications and will be consolidated into a controlled document. Future changes to the Bases will be evaluated under 10 CFR 50.59. Therefore, the proposed changes to the Technical Specification Index do not create the possibility of a new or different type of accident.

3. Does the change involve a significant reduction in a margin of safety?

Plant safety limits are established through I.COs, limiting safety system settings, and safet limits specified in the Technical Specifications. There will be no changes to either the physical design of the plant or to any of these settings and limits as a result of modifying the Technical Specification Index. The ability to mitigate the consequences of all accidents previously evaluated will be maintained and nuclear safety is not impacted. The Bases information, per 10 CFR 50.36(a), is not part of the Technical Specifications and will be consolidated into a controlled document. Future changes to the Bases will be evaluated under 10 CFR 50.59.

Therefore, the proposed amendment does not significantly reduce any margin of safety.

In preparing this request, the Technical Specifications Bases were reviewed for impact N cch anges n are necessary to address this proposed administrative amendment to the Technical Specifications Index.

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