ML17300A772

Amends 14 & 8 to Licenses NPF-41 & NPF-51,respectively, Deleting Sections of Tech Specs Re Fire Protection Program & Substituting Std Condition Delineated in Generic Ltr 86-10

ML17300A772
Person / Time
Site:	Palo Verde
Issue date:	04/08/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17300A773	List: ML17300A772 ML17300A774
References
GL-86-10, NUDOCS 8704230693
Download: ML17300A772 (76)

Text

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Cy Y/+o +p*yW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

14 License No.

NPF-41 1.

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

A.

The application for amendment, dated July 14,

1986, as supplemented by letters dated December 2, 1986, and February 9, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),

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 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; 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; 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.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 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. 14, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

In addition, paragraph 2.C(7) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

(7) Fire Protection Pro ram (Section 9.5.1, SSER 6, SSER 7 and SSER 8

APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety analysis Report for the facility, as supplemented and

amended, and as approved in the SER through Supplement 8, subject to the following provision:

APS may make changes to the approved fire protection program, without prior approval of the Comnission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

4.

The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.

The period of time during changeover shall be minimized.

5.

This license amendment is effective as of the date of issuance.

Enclosure:

Changes to the Technical Specifications Date of Issuance:

April 8, 1987 FOR THE NUCLEAR REGULATORY COMMISSION 4~

&8'orge

. Knighton irector PWR Prospect Direc rate No.

7 Division of PWR Licensing-B

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April 8, 1987 ENCLOSURE'O LICENSE AMENDMEHT NO.

14 FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.

STN 50-528 Overleaf Pa es 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.

Also to be replaced are the following over leaf pages to the amended pages.

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V VIII XIII XXI XXII 3/4 11-14 B 3/4 3-5 B 3/4 7-7 6-20 VI VII XIV 3/4 11-13 6-19 In addition, the following pages dealing with the fire protection program are to be deleted.

3/4 3-61 thru 3/4 3-68 3/4 7-29 thru 3/4 7-44 The remaining pages in the affected sections have been renumbered and are to be replaced with the specified insertion pages.,

Old Pa es thru 3/4 3-80 3/4 7-45 3/4 7-46 B 3/3 3-6 B 3/4 7-8 New Pa es thru 3/4 3-72 3/4 7-29 3/4 7-30

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INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3/4.2.5

'3/4.2.6 3/4.2.7 3/4.2.8 RCS FLOW RATE.........................,..........,,...,.

REACTOR COOLANT COLD LEG TEMPERATURE....................

AXIAL SHAPE INDEX............................,,......,,.

PRESSURIZER PRESSURE.........................,...,...,,.

3/4.3 INSTRUMENTATION 3/4.3. 1 REACTOR PROTECTIVE INSTRUMENTATION............

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.............................

3/4.3. 3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION..............,...

INCORE DETECTORS..........................,,,...,...,

SEISMIC INSTRUMENTATION............,.......,...,.....,

METEOROLOGICAL INSTRUMENTATION......................,

REMOTE SHUTDOWN SYSTEM...............................

POST-ACCIDENT MONITORING INSTRUMENTATION...........

LOOSE-PART DETECTION INSTRUMENTATION.................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.......................,............

3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.............................

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HOT SHUTDOWN...................,.........;..............

COLD SHUTDOWN -

LOOPS FILLED.......................,...,

COLD SHUTDOWN -

LOOPS NOT FILLED..................,....,

SECTION 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.

1 LINEAR HEAT RATE..................,......,....,....,....

3/4.2.2 PLANAR PADIAL PEAKING FACTORS....................... ~...

3/4.2.3 AZIMUTHAL POWER TILT...............;....................

3/4o2o4 DNBR MARGINt ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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PAGE 3/4 2-]

3/4 2-2 3/4 2-3 3/4 2-5 3/4 2-8 3/4 2-9 3/4 2-11 3/4 2-12 3/4 3-1 3/4 3-17 3/4 3-37 3/4 3-41 3/4 3-42 3/4 3-45 3/4 3-48 3/4 3-57 3/4'-61 3/4 3-63 3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-5 3/4 4-6 PALO VERDE - UNIT 1 AMENDMENT NO. 14

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INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4.4.2 SAFETY VALVES PAGE SHUTDOWN.

OPERATING.

3/4 4-7 3/4 4-8 3/4.4. 3 PRESSURIZER PRESSURIZER.

AUXILIARYSPRAY 3/4.4.4 STEAM GENERATORS.

3/4. 4. 5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS OPERATIONAL LEAKAGE 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-18 3/4 4-19 3/4.4.6 CHEMISTRY.

3/4. 4. 7 SPECIFIC ACTIVITY..

3/4. 4. 8 PRESSURE/TEMPERATURE LIMITS REACTOR COOLANT SYSTEM.

PRESSURIZER HEATUP/COOLDOWN LIMITS OVERPRESSURE PROTECTION SYSTEMS 3/4 4-22 3/4 4-25 3/4 4-29 3/4 4"32 3/4 4-33 3/4. 5. 2 3/4

~ 5. 3 ECCS SUBSYSTEMS - Tc ld

> 350 F

ECCS SUBSYSTEMS -

T ld

< 350 F....

cold 3/4.5.4 REFUELING WATER TANK.

3/4. 4. 9 STRUCTURAL INTEGRITY.

3/4.4. 10 REACTOR COOLANT SYSTEM VENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.

1 SAFETY INJECTION TANKS 3/4 4-34 3/4 4-35 3/4 5-1 3/4 5-3 3/4 5-7 3/4 5-8 PALO VERDE - UNIT 1 VI

INDEX LIMITING>>CONDITIONS FOR OPERATION AND "SURVEILLANCE RE UIREMENTS SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6. 1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY CONTAINMENT LEAKAGE..

CONTAINMENT AIR LOCKS INTERNAL PRESSURE.

AIR TEMPERATURE CONTAINMENT VESSEL STRUCTURAL INTEGRITY.........

CONTAINMENT VENTILATION SYSTEM.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM.

IODINE REMOVAL SYSTEM..

3/4. 6. 3 CONTAINMENT ISOLATION VALVES.

3/4.6 '

COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS..

ELECTRIC HYDROGEN RECOMBINERS HYDROGEN PURGE CLEANUP SYSTEM.

PAGE 3/4 6-1 3/4 6-2 3/4 6-4 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-14 3/4 6-15 3/4 6-17 3/4 6-19 3/4 6-36 3/4 6-37 3/4 6-38 PALO VERDE " UNIT 1 VII

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k INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE SAFETY VALVES..............,.....

AUXILIARY FEEDWATER SYSTEM.......

CONDENSATE STORAGE TANK..........

ACTIVITY.........................

HAIN STEAM LINE ISOLATION VALVES.

ATMOSPHERIC DUMP VALVES..........

3/4.7.2 3/4.7.3 3/4.7.4'/4.7.5 3/4.7.6 3/4.7.7 3/4.7.8 3/4.7.9 3/4.7.10 3/4.7.11 STEAM GENERATOR PRESSURE/TEMPERATURE LIMI ESSENTIAL COOLING WATER SYSTEM...,.......

ESSENTIAL SPRAY POND SYSTEM..............

TATION.........

ULTIHATE HEAT SINK......................................

ESSENTIAL CHILLED WATER SYSTEM...........

CONTROL ROON ESSENTIAL FILTRATION SYSTEM.

ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEH................

SNUBBERS................................................

SEALED SOURCE CONTAMINATION.............................

SHUTDOWN COOLING SYSTEM.................................

PAGE 3/4 7-1 3/4 7-4 3/4 7-6 3/4 7-7 3/4 7-9 3/4 7-10 3/4 7-11 3/4 7-12 3/4 7-13 3/4 7-14 3/4 7-15 3/4 7-16 3/4 7-19 3/4 7-21 3/4 7-27 3/4 7-29 3/4.7. 12 CONTROL ROOH AIR TEMPERATURE.........;..................

3/4 7-30 3/4.'8 ELECTRICAL POWER SYSTEMS 3/4.8. 1 A.C.

SOURCES OPERATING.....,.......................................

3/4 8-1 SMUTDOWNt ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~

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3/4 8 8 PALO VERDE - UNIT 1

VIII AMENDMENT NO.

14

BASES INDEX SECTION

.3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE...........

PAGE B 3/4 7-1 3/4. 7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.........

B 3/4 7-3 3/4.7.3 ESSENTIAL COOLING WATER SYSTEM...........'...............

B 3/4 7-3 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM.

3/4. 7. 5 ULTIMATE HEAT SINK....

3/4 7.6 ESSENTIAL CHILLED WATER SYSTEM.

3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM.

3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM.

.'.3/4.7.9 SNUBBERS..

B 3/4 7-4 B 3/4 7-4 B 3/4 7-4 e 3/4 7-5 B 3/4 7-5 B 3/4 7-5 3/4.7. 10 SEALED SOURCE CONTAMINATION........................,.....

B 3/4 7-7 3/4.7.11 SHUTDOWN COOLING SYSTEM.........................

3/4.7. 12 CONTROL ROOM AIR TEMPERATURE...........

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3/4.8 ELECTRICAL POWER SYSTEMS 3/4. 8. 1, 3/4. 8. 2, and 3/4.8. 3 A. C.

SOURCES, D. C.

SOURCES ONSITE POWER DISTRIBUTION SYSTEMS

, and B 3/4 7-7 B 3/4 7-7 B 3/4 8"1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.................

B 3/4 8-3 3/4. 9. 2 INSTRUMENTATION..................

3/4. 9. 3 DECAY TIME........

3/4. 9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION........

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 3/4. 9. 4 3/4. 9. 5 COMMUNICATIONS B 3/4 9-1 CONTAINMENT BUILDING PENETRATIONS..................... -.

B 3/4 9-1 PALO VERDE - UNIT 1 XIII AMENDMENT NO. I4

BASES SECTION 3/4. 9. 6 REFUELING MACHINE INDEX PAGE 8 3/4 9-2 3/4.9.7 CRANE TRAVEL -

SPENT FUEL STORAGE POOL BUILDING.........

8 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM..

3/4. 9. 10 and 3/4. 9. 11 WATER LEVEL -

REACTOR VESSEL and STORAGE POOL 3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM....

3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN.

3/4 ~ 10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS 8 3/4 9-2 8 3/4 9-3 8 3/4 9-3 8 3/4 9-3 8 3/4 10-1 8 3/4 10-1 3/4. 10.3 REACTOR COOLANT LOOPS.

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8 3/4 10"1 3/4.10,4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLO LEG,TEMPERATURE 8 3/4 10"1 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........

8 3/4 10-1 3/4. 10. 6 SAFETY INJECTION TANKS.

8 3/4 10-2 3/4. 10.7, SPENT FUEL POOL LEVEL..............

3/4-10.8 SAFETY INJECTION TANK PRESSURE.

3/4. 11 RADIOACTIVE EFFLUENTS 8 3/4 10-2 8 3/4 10-2 3/4. 11. 1 SECONDARY SYSTEM LI(UID WASTE DISCHARGES TO ONSITE EVAPORATION PONDS..

8 3/4 ll-l 3/4. 11.2 GASEOUS EFFLUENTS 3/4. 11. 3 SOLID RADIOACTIVE WASTE 3/4. 11. 4 TOTAL DOSE

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3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM....

3/4. 12. 2 LAND USE CENSUS...................

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM......................

8 3/4 11-2 8 3/4 11-5 8 3/4 11 5

8 3/4 12-1 8 3/4 12"2 8 3/4 12-2 PALO VFRDE - UNIT 1 XIV

LIST OF TABLES INDEX 4.3"6 3.3"10 4.3-7 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....

POST-ACCIDENT MONITORING INSTRUMENTATION................

PAGE 3/4 3-56 3/4 3-58 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-59 3.3-11 LOOSE PARTS SENSOR LOCATIONS..

3/4 3-62 3.3 12

4. 3"8

4. 4-1

4. 4-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION...........................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE'EQUIREHENTS...............

MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION.............................

STEAM GENERATOR TUBE INSPECTION.

3/4 3-64 3/4 3"69 3/4 4-16 3/4 4-17

<<3. 4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES........

3/4 4"21

3. 4-2

4. 4-3

4. 4-4

4. 4-5

4. 6-1

4. 6-2

3. 6-1 3.7 1 REACTOR COOLANT SYSTEM CHEMISTRY.....................,..

REACTOR COOLANT SYSTEM CHEMISTRY LIHITS SURVEILLANCE REQUIREMENTS.............

PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM......

REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE.....

TENDON SURVEILLANCE - FIRST YEAR TENDON LIFT-OFF FORCE - FIRST YEAR....

CONTAINMENT ISOLATION VALVES STEAM LINE SAFETY VALVES PER LOOPS 3/4 4-23 3/4 4-24 3/4 4-27 3/4 4-31 3/4 6"12 3/4 6"13 3/4 6-21 3/4 7-2 PALO VERDE - UNIT 1 XXI AHENDMENT NO. 14

LIST OF TABLES INDEX

- 3. 7-2 MAXIMUM ALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES PAGE 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.

4.8-1 DIESEL GENERATOR TEST SCHEDULE..........................

3.8-1 D.C.

ELECTRICAL SOURCES...

4.8-2 BATTERY SURVEILLANCE RE(UIREMENTS....................

3/4 7"8 3/4 8"7 3/4 8"11 3/4 8-12 3.8-2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES..........................

3/4 8-19 3.8-3 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES 3/4 8-41 4.11"1 RADIOACTIVE LI(UID WASTE SAMPLING AND ANALYSIS PROGRAM..

3/4 11" 2

<<4.11"2 RADIOACTIVE GASEOUS, WASTE SAMPLING AND ANALYSIS PROGRAM.

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3/4 11-8

3. 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........

3/4 12" 3

3. 12" 2

4. 12-1 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 3/4 12-7 3/4 12-8 B 3/4.4-1 REACTOR VESSEL TOUGHNESS........

5. 7"1

5. 7-2

6. 2-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.....................

PRESSURIZER SPRAY NOZZLE USAGE FACTOR...................

MINIMUM SHIFT CREW COMPOSITION..................

B 3/4 4-8 I

5-7 5-9 6"5 PALO VERDE - UNIT 1 XXII AMENDMENT NO.

14

INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The loose-part detection system shall be OPERABLE with all sensors specified in Table 3.3-11.

APPLICABILITY:

MODES I and 2.

ACTION:

'a

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b.

With one or more loose-part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.7, Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of:

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C.

a CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a

CHANNEL CALIBRATION at least once per 18 months.

PALO VERDE - UNIT I 3/4 3-61 AMENDMENT NO.

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TABLE 3.3-11 LOOSE PARTS SENSOR LOCATIONS INSTRUMENT NO.

JSVNYE -

1 JSVNYE -

2 JSVNYE - 3 JSVNYE - 4 JSVNYE -

5 JSVNYE -

6 JSVNYE -

7 JSVNYE - 8 LOCATION UPPER VESSEL A (STUD BOLTS)

UPPER VESSEL B

(STUD BOLTS)

LOWER VESSEL A (INCORE NOZZLE)

LOWER VESSEL B

( INCORE NOZZLE)

SG-1A (HOT LEG)

SG-1B (COLD LEG 1A)

SG-2A (HOT LEG)

SG-28 (COLD LEG 2A)

PALO VERDE - UNIT 1 3/4 3-62 AMENDMENT NO.

14

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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification

3. 11.2. 1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCY;.

APPLICABILITY:

As shown in Table 3.3-12.

ACTION:

a.

With a.low range radioactive gaseous effluent monitoring instrumenta-tion channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioac-tive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.8 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

PALO VERDE - UNIT I 3/4 3-63 AMENDMENT NO.

TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM a.

Noble Gas ActivityHonitor-Providing Alarm and Automatic Termination of Release

¹RU-12 b.

Flow Rate Monitor MINIMUM CHANNELS OPERABLE APPL ICABILITY ACTION 35 36 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen Yonitor b.

Oxygen Monitor 39 39

TABLE 3.3-12 (Continued)

RADIOACTIVE GASEOUS

'EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION 3.

CONDENSER EVACUATION SYSTEM A.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-141 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device B.

High Range Monitors a.

Noble Gas Activity Monitor ¹RU-142 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device 4.

PLANT VENT SYSTEM A.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-143 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device 1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

37 40 40 36 36 42 42 42 42 37 40 40 36 36

TABLE 3.3-12 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION 4.

PLANT VENT SYSTEM (Continued)

B.

High Range Monitors a.

Noble Gas Activity Monitor ¹RU-144 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device 42 42 42 42 5.

FUEL BUILDING VENTILATION SYSTEM A.

B.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-145 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device High Range Monitors a.

Noble Gas Activity Monitor ¹RU-146 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device

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TABL'E 3.3'-12 (Continued)

TABLE NOTATION

• At al 1 times.

• • During GASEOUS 'RADWASTE SYSTEM operation.

0 During waste gas release.

8A'n MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Othe~wise, suspend release of radioactive effluents via this pathway.

ACTION 36-ACTION 37-ACTION 38-ACTION 39-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of {A) or (8) are performed:

a.

Initiate the Preplanned Alternate Sampling Program of Specification

6. 16 to monitor the appropriate parameter(s).

b.

Place moveable air monitors in-line or take grab samples at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RADWASTE SYSTEM may continue provided grab samples are taken and analyzed daily.

With both channels inoperable operation may continue provided grab samples are taken and analyzed'(1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations, and (2) daily during other operations.

PALO VERDE - UNIT I 3/4 3-67 AMENDMENT NO.

I4

TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 40-ACTION 41-ACTION 42-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are contin-uously collected with auxiliary sampling equipment as required in Table 4. 11-2 within one hour after the channel has been declared inoperable.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, comply with the ACTION b of Specification 3.9. 12 or operate the fuel building essential ventilation system while moving irradiated fuel.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement restore the channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or:

a.

Initiate the Preplanned Alternate Sampling Program of Specification 6. 16 to monitor the appropriate parameter(s)'hen it is needed.

b.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action(s)

taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

PALO.VERDE - UNIT 1 3/4 3-68 AMENDMENT NO. 14

TABLE 4.3-8 e

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM CHANNEL CHECK SOURCE CHANNEL CHECK CAI IBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST I

HEIR i EO a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release RU-12 b.

Flow Rate Monitor N.A.

R(3)

Q(1),(2),P¹¹¹

¹ Q,P¹¹¹

¹ 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen Monitor (continuous) b.

Hydrogen Monitor (sequential) c.

Oxygen Monitor (continuous) d.

Oxygen Monitor (sequential)

N.A.

N.A.

N.A.

N.A.

Q(4)

Q(4)

Q(5)

Q(5)

ID m

C)

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 3.

CONDENSER EVACUATION SYSTEM (RU-141 and RU-142)

CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST IS REQUIRED GO I

CD

a. Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(7)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

Q(2)

N.A.

N.A.

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

1, 2, 3, 4

CD 4.

PLANT VENT SYSTEM (RU-143 and RU-144) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(7)

N.A.

N.A.

N.A.

~N.A.

R(3)

N.A.

N.A.

Q(2)

N.A.

N.A.

m

%7 CD Pl

.TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT 5.

FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146) a.

Noble Gas Actvity Monitor

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(Z)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST IS REQUIRED Q(Z)

N.A.

N.A.

TABLE 4.3-8 (Continued)

TABLE NOTATIONS

¹

¹¹

¹¹¹ (I)

(2)

(3)

(4)

(6)

At all times.

During GASEOUS RADWASTE SYSTEM operation.

During waste gas release.

During MODES I, 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards. certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One-volume percent

hydrogen, balance nitrogen, and 2.

Four volume percent

hydrogen, balance nitrogen.

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l.

One volume percent

oxygen, balance

nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

The channel check for channels in standby status shall consist of verification that the channel is "on-line and reachable."

(7)

Daily channel check not required for flow monitors in standby status.

PALO VERDE - UNIT I 3/4 3-72 AMENDMENT NO.

>4

~

~

I PLANT SYSTEMS 3/4.7. 11 SHUTDOWN COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 11 Two independent shutdown coolina subsystems shall be OPERABLE, with each subsystem comprised of:

a.

One OPERABLE low pressure safety injection pump, and b.

An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold leg injection lines.

APPLICABILITY:

MODES I, 2, and 3.

ACTION:

a.

With one shutdown cooling subsystem inoperab'le, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within I hour, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and continue action to restore the required subsystem to OPERABLE status.

b.

With both shutdown cooling subsystems inoperable, restore one subsystem 'to OPERABLE status within I hour or be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and continue action to restore the required subsystems to OPERABLE status.

c.

With both sutdown cooling subsystems inoperable and both reactor coolant loops inoperable, initiate action to restore the required subsystems to OPERABLE status.

SURVEILLANCE RE UIREMENTS 4.7. 11 Each shutdown cooling subsystem shall be demonstrated OPERABLE:

a.

At least once per 18 months, during shutdown, by establishing shutdown cooling flow from the RCS hot legs, through the shutdown cooling heat exchangers, and returning to the RCS cold leos.

b.

At least once per 18 months, during shutdown, by testing the automatic and interlock action of the shutdown cooling system connections from the RCS.

The shutdown cooling system suction valves shall not open when RCS pressure is greater than 410 psia.

The shutdown cooling system suction valves located outside containment shall close auto-matically when RCS pressure is greater than 500 psia.

The shutdown cooling system suction valve located inside containment shall close automatically when RCS pressure is greater than 700 psia.

PALO VERDE - UNIT I 3/4 7-29 AMENDMENT NO.

14

PLANT SYSTEMS 3/4.7. 12 CONTROL ROOM AIR TEMPERATURE LIMITING CONDITION OF OPERATION 3.7. 12 The control room air temperature shall be maintained less than or equal to 80'F.

APPLICABILITY:

ALL MODES ACTION:

With the control room air temperature greater than 80'F, reduce the air temperature to less than or equal to 80'F within 30 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.7. 12 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that the control room air temperature is less than or equal to 80'F.

PALO VERDE - UNIT 1 3/4 7-30 AMENDMENT NO 14

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION

3. 11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EX8AUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figures

5. 1-1 and 5, 1-3),

when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mra'd for beta radiation.

The VENTILATION EX8AUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures

5. 1-1 and 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a; b.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

l.

Identification of the inoperable equipment or subsystems and the reason for inoperability,,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE

status, and 3.

Summary description of action(s) taken to prevent a recurrence.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at

'east once per 31 days, in accordance with the methodology and parameters in the ODCM.

PALO VERDE - UNIT 1 3/4 11" 13

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE 1

LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume whenever the hydrogen concentration exceeds 4X by volume.

APPLICABILITY: At al 1 times.

ACTION:

a ~

b.

C.

With the concentration of oxygen in the waste gas holdup system greater than 2X by volume but less than or equal to 4X by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas holdup system greater than 4X by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4X by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

'SURVEILLANCE RE UIREMENTS

4. 11.2.5 The concentration of hydrogen or oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.8".

PALO VERDE UNIT 1 3/4 11-14 AMENDMENT NO. 14

INSTRUMENTATION BASES

,POST~ACCIDENT MONITORING INSTRUMENTATION (Continued)

In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and reactor vessel head are removed.

It is not feasible to repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core.

If both channels are inoperable, the channels shall be restored to OPERABLE status in the nearest refueling out-age.

If only one channel is inoperable, it is intented that this channel be restored to OPERABLE status in a refueling outage as soon as reasonably

,'possible.

43/4. 3. 3. 7 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation 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-Water-Cooled Reactors,"

May 1981.

3/4. 3. 3. 8 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 set-

'points 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 GASEOUS RADWASTE SYSTEM.

The OPERA-BILITY 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.

There are two separate radioactive gaseous effluent monitoring systems:

the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents.

The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions.

The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors.

PALO VERDE - UNIT 1 B 3/4 3-5 AMENDMENT NO.

14

PLANT SYSTEMS BASES 3/4.7. 10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak test-ing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct,

source, and special nuclear material, sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are required to be tested more often than those which are not.

Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.

V 3/4.7. 11 SHUTDOWN COOLING SYSTEM The OPERABILITY of two separate and independent shutdown cooling sub-systems ensures that the capability of initiating shutdown cooling in the event of an accident exists even assuming the most limiting single failure occurs.

The safety analysis assumes that shutdown cooling can be initiated when conditions permit.

The limits of operation with one shutdown cooling inoperable for any reason minimize the time exposure of the plant to an accident event occurring concurrent with the failure of a component on the other shutdown cooling subsystem.

3/4.7. 12 CONTROL ROOM AIR TEMPERATURE Maintaining the control room air temperature less than or equal to 80'F ensures that (I) the ambient air temperature does not exceed the allowable air temperature for continuous duty rating for the equipment and instrumentation in the control room and (2) the control room will remain habitable for opera-tions personnel during plant operation.

The 30 days to return the control room air temperature to less than or equal to 80'F in the Action Statement is con-sistent with the equipment qualification program for the control room.

PALO VERDE - UNIT I B 3/4 7-7 AMENDMENT NO, 14

~

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P,

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include 'an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind

speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.*

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside'he SITE BOUNDARY (Figure 5. 1-1) during the report period.

All assumptions used in making these assessments,

i. e., specific activity, exposure time and location, shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL.

The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and ga'seous effluents are given in Regula-tory Guide

1. 109, Rev.

1, October 1977.

The Semiannual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a.

Container

volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Source of waste and processing employed (e. g.,

dewatered spent resin compacted dry waste, evaporator bottoms),

"In lieu of submission with the first half year Semiannual Radioactive Effluent Release

Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

PALO VERDE " UNIT 1 6"19

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) e.

Type of container (e.g.,

LSA, Type A, Type 8, Large guantity),

and f.

Solidification agent or absorbent (e.g.,

cement, urea formaldehyde).

The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED, AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification

3. 12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with 10 CFR 50.73.

6. 10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6. 10. 1 The following records shall be retained for at least 5 years:

a ~

b.

C.

d.

e.

g.

h.

Records and logs of unit operation covering time interval at each power level.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

All REPORTABLE EVENTS submitted to the Commission.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

Records of changes made to the procedures of Specification 6.8. 1.

Records of radioactive shipments.

Records of sealed source and fission detector leak tests and results.

Records of annual physical inventory of all sealed source material of record.

PALO VERDE - UNIT 1 6-20 AMENDMENT NO.

14

pe REGS P

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0 I

0O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

++*++

ARIZONA PUBLIC SERVICE COMPANY, ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No.

NPF-51 1.

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

A.

The application f'r amendment, dated July 14,

1986, as supplemented by letters dated December 2, 1986, and February 9, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Souther n California Public Power Authority (licensees),

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 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; 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; 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 Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 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. 8, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The changes in the Technical Specification are to become effective within 30 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.

The period of time during changover shall be minimized.

4.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY CONYiISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

April 8, 1987 George Knighton rector PWR Pro ect Direct rate No.

7 Division of PWR Licensing-B

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April 8, 1987 ENCLOSURE TQ LICENSE AMENDMENT NO.

8 FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 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.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa es V

VIII XIII XVII XXI XXII 3/4 11-14 B 3/4 3-5 B 3/4 7-7 6-20 6-21 6-22 6-23 Overleaf Pa es VI VII XIV XVIII 3/4 11-13 6-19 6-24 In addition, the following pages dealing with the fire protection program are to be deleted.

3/4 3-61 thru 3/4 3-68 3/4 7-29 thru 3/4 7-44 The remaining pages in the affected sections have been renumbered and are to be replaced with the specified insertion pages.

Old Pa es thru 3/4 3-80 3/4 7-45 3/4 7-46 B 3/4 3-6 B 3/4 7-8 New Pa es thru 3/4 3-72 3/4 7-29 3/4 7-30

I

~

~

I

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2.2 3/4.2.3 3/4.2.4 PLANAR PADIAL PEAKING FACTORS -

Fxy'''

AZIMUTHAL POWER TILT - T...............................

flkBR MARGIN 3/4.2.5 RCS FLOW RATE.....,...,...........,,,...,...,....,......

3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE.......,,....,......

3/4.2.7 AXIAL SHAPE INDEX..........................,,.....,.....

3/4.2.8 PRESSURIZER PRESSURE...................,...,..........,.

3/4.3 INSTRUMENTATION 3/4.3. 1 REACTOR PROTECTIVE INSTRUMENTATION..........,......,...,

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.................................,.....

3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION.................

INCORE DETECTORS.....................................

SEISMIC INSTRUMENTATION........................,.....

METEOROLOGICAL INSTRUMENTATION.......................

REMOTE SHUTDOWN SYSTEM........................

POST-ACC IDENT MONITORING INSTRUMENTATION......

LOOSE-PART DETECTION INSTRUMENTATION.................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....................................

3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.............................

HOT STANDBY.............................................

HOT SHUTDOWN..............,......................

COLD SHUTDOWN -

LOOPS FILLED.....................

~

~ ~

~ ~ ~ ~

COLD SHUTDOWN -

LOOPS NOT FILLED........................

SECTION 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.

1 LINEAR HEAT RATE.....,,...,...,,,,.............,,...,...

PAGE 3/4 2-1 3/4 2-2 3/4 2-3 3/4 2-5 3/4 2-8 3/4 2-9 3/4 2-11 3/4 2-12 3/4 3-1 3/4 3-17 3/4 3-37 3/4 3-41 3/4 3-42 3/4 3-45 3/4 3-48 3/4 3-57 3/4 3-61 3/4 3-63 3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-5 3/4 4-6 PALO VERDE - UNIT 2 AMENDMENT NO, 8

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 4. 2 SAFETY VALVES PAGE SHUTDOWN.

OPERATING 3/4 4-7 3/4 4-8 3/4.4.3 PRESSURIZER PRESSURIZER AUXILIARYSPRAY 3/4.4.4 STEAM GENERATORS..

3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS OPERATIONAL LEAKAGE 3/4.4.6 CHEMISTRY............

3/4.4.7 SPECIFIC ACTIVITY.

3/4.4.8 PRESSURE/TEMPERATURE LIMITS 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-18 3/4 4-19

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3/4 4 22 3/4 4-25 REACTOR COOLANT SYSTEM...........

PRESSURIZER HEATUP/COOLDOWN LIMITS OVERPRESSURE PROTECTION SYSTEMS 3/4.4.9 STRUCTURAL INTEGRITY...

3/4.4.10 REACTOR COOLANT SYSTEM VENTS..

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS 3/4.5. 1 SAFETY INJECTION TANKS.................

3/4 4-28 3/4 4-31 3/4 4-32 3/4 4-34 3/4 4-35

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3/4 5 1 3/4. 5. 2 3/4. 5. 3 3/4. 5. 4 cold-

'coid ".

REFUELING WATER TANK.

3/4 5-3 3/4 5-7 3/4 5-8 PALO VERDE - UNIT 2

'NDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY..

PAGE 3/4 6-1 CONTAINMENT LEAKAGE 3/4 6-2 CONTAINMENT AIR LOCKS INTERNAL PRESSURE AIR TEMPERATURE 3/4 6-4 3/4 6-6 3/4 6-7 CONTAINMENT VESSEL STRUCTURAL INTEGRITY..............

3/4 6-8 CONTAINMENT VENTILATIONSYSTEM.......................

3/4 6-14 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT'PRAY SYSTEM.

IODINE REMOVAL SYSTEM................................

3/4 6"15 3/4 6-17 3/4. 6. 3 3/4. 6. 4 CONTAINMENT ISOLATION VALVES.........:..................

3/4 6-19 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS 3/4 6-36 ELECTRIC HYDROGEN RECOMBINERS;.......................

3/4 6-37 HYDROGEN PURGE CLEANUP SYSTEM.

3/4 6-38 PALO VERDE - UNIT 2

/

VII

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE SAFETY VALVES..................................

AUXILIARY FEEDWATER SYSTEM.....................

CONDENSATE STORAGE TANK........................

MAIN STEAM LINE ISOLATION VALVES...............

ATMOSPHERIC DUMP VALVES........................

3/4.7.2 3/4.7.3 3/4.7.4 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION...

ESSENTIAL COOLING WATER SYSTEM....................

ESSENTIAL SPRAY POND SYSTEM.............................

3/4.7.7 3/4.7.8 3/4.7.9 3/4.7.10 3/4.7.11 3/4.7.12 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................

ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM................

SNUBBERS................................................

SEALED SOURCE CONTAMINATION.............................

SHUTDOWN COOLING SYSTEM.................................

CONTROL ROOM AIR TEMPERATURE.........,..................

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK.............................,,...,...

3/4.7.6 ESSENTIAL CHILLED WATER SYSTEM..........................

PAGE 3/4 7-1 3/4 7-4 3/4 7-6 3/4 7-7 3/4 7-9 3/4 7-10 3/4 7-11 3/4 7-12 3/4 7-13 3/4 7-14 3/4 7-15 3/4 7-16 3/4 7-19 3/4 7-21 3/4 7-27 3/4 7-29 3/4 7-30 3/4.8. 1 A.C.

SOURCES PERATING............................................

0 CATHODIC PROTECTION..................................

3/4 8-1 3/4 8-8 3/4 8-Ba PALO VERDE - UNIT 2 VIII AMENDMENT NO. 8

BASES

'INDEX SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE...............,......,...,,...,.....,,....

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.........

3/4.7.3 ESSENTIAL COOLING WATER SYSTEM...,.....,...,,...,...,...

PAGE B 3/4 7-1 B 3/4 7-3 B 3/4 7-3 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM.............................

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK.........,...,,,.......,...,...,,.....

3/4 7.6 ESSENTIAL CHILLED WATER SYSTEM....................,.....

3/'4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................

3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM................

3/4.7.9 SNUBBERS................................................

B 3/4 7-4 B 3/4 7-4 B 3/4 7-5 B 3/4 7-5 B 3/4 7-5 3/4.7. 10 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-7 3/4.7. 11 SHUTDOWN COOLING SYSTEM....................,........,...

3/4.7.12 CONTROL ROOM AIR TEMPERATURE..........'.........,.....,,.

3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 7-7 B 3/4 7-7 3/4.8. 1, 3/4.8.2, and 3/4.8.3 A.C.

SOURCES, D.C.

SOURCES ONSITE POWER DISTRIBUTION SYSTEMS........

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B 3/4 8-1 3/4.8.4 ELECTRICAL E(UIPMENT PROTECTIVE DEVICES.................

B 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4.9.2 3/4.9.3 INSTRUMENTATION.........................................

ECAY TIME...........................,...,...,,.........

D 3/4.9. 1 BORON CONCENTRATION.....................................

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

B 3/4 9-1 3/4.9.5 C01 MUNICATIONS ~ ~

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B 3/4 9-1 PALO VERDE - UNIT 2 XIII AMENDMENT NO. 8

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B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION.

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.

B 3/4 9-3 3/4.9. 10 and 3/4.9. 11 WATER LEVEL -

REACTOR VESSEL and

,STORAGE POOL B 3/4 9-3 3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM..............

B 3/4 9-3 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN.

3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS 3/4.10.3 REACTOR COOLANT LOOPS....

3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLO LEG TEMPERATURE B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........

B 3/4 10-1 3/4.10.6 SAFETY INJECTION TANKS 3/4.10.7 SPENT FUEL POOL LEVEL 3/4. 10.8 SAFETY INJECTION TANK PRESSURE 3/4. 11 RADIOACTIVE EFFLUENTS 3/4.11.1 SECONDARY SYSTEM LIQUID WASTE DISCHARGES TO ONSITE EVAPORATION PONDS

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3/4. 11.2 GASEOUS EFFLUENTS...

3/4. 11. 3 SOLID RADIOACTIVE WASTE............. ~...................

3/4. 11. 4 TOTAL DOSE 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM.

3/4.12.2 LAND USE CENSUS 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM....................

B 3/4 10-2 B 3/4 10-2

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3/4 10-2 B 3/4 11-1 B 3/4 11-2 B 3/4 11"5 B 3/4 11-6 B 3/4 12-1 B 3/4. 12-2 B 3/4 12-2 PALO VERDE - UNIT 2 XIV

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ADMINISTRATIVE CONTROLS INDEX SECTION

, 6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION...

COMPOSITION..

CONSULTANTS PAGE

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6-12

'. 6 REPORTABLE EVENT ACTION.........................

6-12

. 6. 7 SAFETY LIMITVIOLATION.......................................

6-13 "6.8 PROCEDURES AND PROGRAMS..............

6-13

" "6.9 REPORTING RE UIREMENTS

,6.9.1 ROUTINE REPORTS............................................

STARTUP REPORT.........................;...................

ANNUAL REPORTS MONTHLY OPERATING REPORT...........

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT......

6-16 6-16 6-17 6-18 6-18 6-19

6. 9. 2 SPECIAL REPORTS

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6.10 RECORD RETENTION.

6-21 6.11 RADIATION PROTECTION PROGRAM.............................

6-22 6.12 HIGH RADIATION AREA........

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6. 13 PROCESS CONTROL PROGRAM (PCP)..

6-23 PALO VERDE - UNIT 2 AMENDMENT NO. 8

ADMINISTRATIVE CONTROLS INDEX SECTION PAGE 6.14 OFFSITE DOSE CALCULATION MANUAL..

6-24 6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AN L 0 MAS R

A M N S

MS 6-24 PALO VERDE - UNIT 2 XVIII

LIST OF TABLES INDEX 3.3-9C

4. 3-6

3. 3-10

4. 3-7

3. 3-11 3.3"12

4. 3-8 4.4-1

4. 4-2

3. 4-1

3. 4-2

4. 4-3

'4.4-5 4.6-1" 4.6-2

3. 6-1

3. 7"1 REMOTE SHUTDOWN CONTROL CIRCUITS..

REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS...

POST-ACCIDENT MONITORING INSTRUMENTATION................

POST" ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE(UIREMENTS...............................

LOOSE PARTS SENSOR LOCATIONS............................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.............................

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE(UIREMENTS...............

MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION..........................

I STEAM GENERATOR TUBE INSPECTION...........

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REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES........

REACTOR COOLANT SYSTEM CHEMISTRY..

REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE RE'gUIREHENTS i

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PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM....................................

REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAH-WITHDRAWALSCHEDULE.....................................

TENDON SURVEILLANCE - FIRST YEAR.

TENDON LIFT-OFF FORCE - FIRST YEAR......

CONTAINMENT ISOLATION VALVES..............

STEAH LINE SAFETY VALVES PER LOOPS......................

PAGE 3/4 3-53 3/4 3-56 3/4 3"58 3/4 3-60

'/4 3"62 3/4 3-64.

3/4 3"69 3/4 4-16 3/4 4-17

'3/4 4-21 3/4 4-23 3/4 4"24 3/4 4-26 3/4 4-30 3/4 6-12 3/4 6-13 3/4 6-21 3/4 7-2 PALO VERDE - UNIT 2 XXI AMENDMENT NO. 8

LIST OF TABLES INDEX 3.7"2 "MAXIMUMALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES PAGE 3/4 7-3

4. 7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.

3/4 7-8 4.8-1

3. 8-1

'4. 8-2

3. 8-2 DIESEL GENERATOR TEST SCHEDULE 3/4 8-7 D.C.

ELECTRICAL SOURCES 3/4 8-11 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES...

3/4 8-19 BATTERY SURVEILLANCE RE(UIREMENTS.

3/4 8-12 3.8-3 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES.'................

3/4 8-41

..4. 11-1

4. 11-2

3. 12" 1

3. 12-2 4.12-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM.

3/4 11-8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........

3/4 12-3 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES................................

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE 3/4 12-7 RADIOACTIVE LI(UID,WASTE SAMPLING AND ANALYSIS PROGRAM..

3/4 11-2 ANALYSIS ~

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B 3/4.4-1 REACTOR VESSEL TOUGHNESS...

3/4 12-8 B 3/4 4-8 5.7-1 5.7-2

6. 2-1 PRESSURIZER SPRAY NOZZLE USAGE FACTOR.

MINIMUM SHIFT CREW COMPOSITION.

5-9 6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS 5-7 PALO VERDE - UNIT 2 XXII AMENDMENT NO.

8

INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The loose-part detection system shall be OPERABLE with all sensors specified in Table 3.3-11.

APPLICABILITY:

MODES I and 2.

ACTION:

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Vith one or more loose-part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0".4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.7 Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of:

a.

a CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

a CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

a CHANNEL CALIBRATION at least once per 18 months.

PALO VERDE - UNIT 2 3/4 3-61 AMENDMENT NO.

8 I

TABLE 3.3-11 LOOSE PARTS SENSOR LOCATIONS INSTRUMENT NO.

JSVNYE -

1 JSVNYE -

2 JSVNYE - 3 JSVNYE - 4 JSVNYE -

5 JSVNYE -

6 JSVNYE -

7 JSVNYE - 8 LOCATION UPPER VESSEL A (STUD BOLTS)

UPPER VESSEL B (STUD BOLTS)

LOWER VESSEL A ( INCORE NOZZLE)

LOWER VESSEL B

( INCORE NOZZLE)

SG-1A (HOT LEG)

SG-1B (COLD LEG 1A)

SG-2A (HOT LEG)

SG-2B (COLD LEG 2A)

PALO VERDE - UNIT 2 3/4 3-62 AMENDMENT NO. 8

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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMI TING CONDITION FOR OPERATION 3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3. 11.2. 1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3-12.

ACTION:

a b.

ce With a low range radioactive gaseous effluent monitoring instrumenta-tion channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioac-tive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.8 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

PALO VERDE - UNIT 2 3/4 3-63 AMENDMENT NO.

8

TABLE 3.3-12 I

ED(

m m

I INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release O'RU-12 MINIMUM CHANNELS OPERABLE APPLICABILITY b.

Flow Rate Monitor RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTION 35 36 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen Monitor b.

Oxygen Monitor 39 39 m

m ED

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I INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABILITY TABLE 3.3-12 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTION CONDENSER EVACUATION SYSTEM A.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-141 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device B.

High Range Monitors a.

Noble Gas Activity Monitor ¹RU-142 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device PLANT VENT SYSTEM 3*** 4***

3*** 4***

2 3*** 4***

3*** 4***

3*** 4***

3*** 4***

2 3*** 4***

3*** 4***

3*** 4***

37 40 40 36 36 42 42 42 42 m

C7 m

A.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-143 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device 37 40 40 36 36 C)

= TABLE 3.3-12 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION C7 I

INSTRUMENT 5

4.

PLANT VENT SYSTBI (Continued)

B.

Hi h Ran e Monitors MINIMUM CHANNELS OPERABLE g

9 a.

Noble Gas Activity.Monitor ¹RU-144 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device e.

Sampler Flow Rate Heasuring Device B.

High Range Monitors a.

Noble Gas Activity Monitor ¹RU-146 b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flow Rate Measuring Device 5.

FUEL BUILDING VENTILATION SYSTEM A.

Low Range Monitors a.

Noble Gas Activity Monitor ¹RU-145 b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor APPL ICABILITY

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¹¹

¹¹ ACTION 42 42 42 42 37,41 40 40 36 36 41,42 42 42 C)

TABL'E 3.3-'2 (Continued)

TABLE NOTATION At all times.

• • During GASEOUS RADWASTE SYSTEM operation.

• • • Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

f-During waste gas release.

A'n MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

ACTION 35-ACTION 36-ACTION 37-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (a) or (b) or (c) are performed:

a.

Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s).

b.

Place moveable air monitors in-line ACTION 38-ACTION 39-c.

'Take grab samples at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RADWASTE SYSTEM may continue provided grab samples are taken and analyzed daily.

With both channels inoperable operation may continue provided grab samples are taken and analyzed (I) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations, and (2) daily during other operations.

PALO VERDE - UNIT 2 3/4 "3-67 AMENDMENT NO.

8

TABLE 3.3-12 (Continued)

TABLE NOTATION 0

ACTION 40-ACTION 41-ACTION 42-With the number of channels OPERABLE less than required by the h>inimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are contin-uously collected with auxiliary sampling equipment as required in Table 4. 11-2 within one hour after the channel has been declared inoperable.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, comply with the ACTION b of Specification 3.9. 12 or operate the fuel building essential ventilation system while moving irradiated fuel.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement restore the channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or:

a.

Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) when it is needed.

b.

Prepare and submit a Special Repor't to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action(s)

taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

PALO VERDE - UNIT 2 3/4 3-68 AMENDMENT NO.

8

TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.

GASEOUS RADWASTE SYSTBI CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST IS REQUIRED

a. Noble Gas ActivityHonitor-Providing Alarm and Automatic Termination of Release RU-12

b. Flow Rate Monitor N.A.

R(3)

Q(I),(2),P¹¹¹

¹ Q,P¹¹¹

¹ 4R 2 ~

GASEOUS RADWASTE SYSTBI EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen Monitor (continuous)

b. Hydrogen Monitor (sequential)

c. Oxygen Monitor (continuous) d.

Oxygen Monitor (sequential)

N.A.

N.A.

N.A.

N.A.

Q(4)

Q(4)

Q(5)

Q(5)

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I

INSTRUMENT 3.

CONDENSER EVACUATION SYSTEM (RU-141 and RU-142)

CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES JN WHICH FUNCTIONAL SURVEILLANCE TEST IS REOUIRED GO I

C) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(7)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

O(2)

N.A.

N.A.

3*** 4***

2 3*** 4***

3*** 4***

P 3*** 4**+

]

2 3*** 4***

4.

PLANT VENT SYSTEM (RU-143 and RU-144) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(7)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

g(2)

N.A.

N.A.

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT 5.

FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)

CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST IS REQUIRED a.

Noble Gas Actvity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor

e. Sampler Flow Rate Measuring Device D(6)

N.A.

N.A.

D(7)

D(7)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

Q(~)

N.A.

N.A.

¹¹

TABLE 4.3-8 (Continued)

TABLE NOTATIONS Ph (I)

'2)

(3)

(4)

(6)

At all times.

During GASEOUS RADWASTE SYSTEY operation.

Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

During NODES I, 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAi TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate

'mode.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l.

One volume percent

hydrogen, balance nitrogen, and 2.

Four volume percent

hydrogen, balance nitrogen.

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent

oxygen, balance nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

The channel check for channels in standby status shall consist of verification that the channel is "on-line and reachable."

Daily channel check not required for flow monitors in standby status.

PALO VERDE - UNIT 2 3/4 3-72 AMENDMENT NO, 8

f

PLANT SYSTEMS 3/4.7. 11 SHUTDOWN COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 11 Two independent shutdown cooling 'subsystems shall be OPERABLE, with each subsystem comprised of:

a.

One OPERABLE low pressure safety injection pump, and b.

An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold leg injection lines.

APPLICABILITY:

MODES I, 2, and 3.

ACTION:

a

~

With one shutdown cooling subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within I hour, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and continue action to restore the required subsystem to OPERABLE status.

b.

With both shutdown cooling subsystems inoperable, restore one subsystem to OPERABLE status within I hour or be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and continue action to restore the required subsystems to OPERABLE status.

c.

With both sutdown cooling subsystems inoperable and both reactor coolant loops inoperable, initiate action to restore the required subsystems to OPERABLE status.

SURVEILLANCE RE UIREMENTS 4.7. 11 Each shutdown cooling subsystem shall be demonstrated OPERABLE:

a.

At least once per 18 months, during shutdown, by establishing shutdown cooling flow from the RCS hot legs, through the shutdown cooling heat exchangers, and returning to the RCS cold legs.

b.

At least once per 18 months, during shutdown, by testing the automatic and interlock action of the shutdown cooling system connections from the RCS.

The shutdown cooling system suction valves shall not open when RCS pressure is greater than 410 psia.

The shutdown cooling system suction valves located outside containment shall close auto-matically when RCS pressure is greater than 500 psia.

The shutdown cooling system suction valve located inside containment shall close automatically when RCS,pressure is greater than 700 psia.

PALO VERDE - UNIT 2 3/4 7-29 AMENDMENT NO.

8

PLANT SYSTEMS 3/4.7. 12 CONTROL ROOM AIR TEMPERATURE LIMITING CONDITION OF OPERATION 3:7. 12 The control room air temperature shall be maintained less than or equal to 80'F.

APPLICABILITY:

ALL MODES ACTION:

With the control room air temperature greater than 80'F, reduce the air temperature to less than or equal to 80'F within 30 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS l

4.7. 12 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,'verify that the control room air temperature is less than or equal to 80'F.

PALO VERDE '- UNIT 2 3/4 7-30 AMENDMENT NO.

8

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION

3. 11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figures

5. 1-1 and 5. 1-3),

when averaged over 31 days, would exceed 0.2 mrad for gamma radiatio'n and 0.4 mrad for beta radiation.

The VENTILATION EXHAUST TREATMENT SYSTEH shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures

5. 1-1 and 5. 1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At al 1 times.

ACTION:

1

~II a

~

With radioactive gaseous waste being discharged without treatment and in excess of 'the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification

6. 9. 2, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action(s) taken to restore the inoperable equipment to OPERABLE

status, and 3.

Summary description of action(s) taken to prevent a recurrence.

b.

The provisions of Specifications

3. 0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.4 Doses due t'o gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCH.

PALO VERDE - UNIT 2 3/4 11"13

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPL ICASILITY: At all times.

ACTION:

a.

C.

With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas holdup system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.5 The concentration of hydrogen or oxygen in the waste gas holdup sys-tem shall be determined to be within the above limits by monitoring the waste gases in the waste gas holdup system in accordance with Specification 3.3.3.8.

PALO VERDE - UNIT 2 3/4 11-14 AMENDMENT NO.

8

INSTRUMENTATION BASES 3/4.3.3. 7 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation 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-Water-Cooled Reactors,"

May 1981.

3/4.3.3.8 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 set-points 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. 'his instrumentation also includes provisions for monitoring (and controlling) the concentrations of

" potentially explosive gas mixtures in the GASEOUS RADWASTE SYSTEM.

The OPERA-BILITY 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.

There are two separate radioactive gaseous effluent monitoring systems:

the low range effluent monitors for normal plant radioactive gaseous effluents and the high range, effluent monitors for post-accident plant radioactive gaseous "effluents.

The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions.

The high range monitors only operate when the concentration of radioactivity in

--the effluent is above the setpoint in the low range monitors.

PALO VERDE - UNIT 2 B 3/4 3-5 AMENDMENT NO. 8

PLANT SYSTEMS BASES 3/4.7. 10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak test-ing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct,

source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are required to be tested more often than those which are not.

Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.

3/4.7. 11 SHUTDOWN COOLING SYSTEM The OPERABILITY of two separate and independent shutdown cooling sub-systems ensures that the capability of initiating shutdown cooling in the event of an accident exists even assuming the most limiting single failure occurs.

The safety analysis assumes that shutdown cooling can be initiated when conditions permit.

The limits of operation with one shutdown cooling inoperable for any reason minimize the time exposure of the plant to an accident event occurring concurrent with the failure of a component on the other shutdown cooling subsystem.

3/4.7. 12 CONTROL ROOM AIR TEMPERATURE Maintaining the control room air temperature less than or equal to 80'F ensures that (1) the ambient air temperature does not exceed the allowable air temperature for continuous duty rating for the equipment and instrumentation in the control room and (2) the control room will remain habitable for opera-tions personnel during plant operation.

The 30 days to return the control room air temperature to less than or equal to 80'F in the Action Statement is con-sistent with the equipment qualification program for the control room.

PALO VERDE - UNIT 2 B 3/4 7-7 AMENDMENT NO.

1 I

~

I*

,gt

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison

Program, required by Specification

3. 12.3; discussion of all deviations from the sampling schedule of Table 3. 12-1; and discussion of all analyses in which the LLD required by Table 4. 12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 6.9. 1.8 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July '1 of each year.

The period of the first repbrt shall begin with the date of initial criticality.

The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide

1. 21, Measuring, Evalu-

ating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind

speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability*".

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5. 1-1) during the report period.

All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL.

"A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to, all units at the station;

however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material from each unit.

""In lieu of submission with the first half year Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

PALO VERDE - UNIT 2 6-19

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from"liquid and gaseous effluents are given in Regula-tory Guide

1. 109, Rev. I, October 1977.

The Semiannual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a.

Container

volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Source of waste and processing employed (e.g.,

dewatered spent resin, compacted dry waste, evaporator bottoms),

e.

Type of container (e.g.,

LSA, Type A, Type B, Large guantity),

and

'\\

f.

Solidification agent or absorbent (e.g.,

cement, urea formaldehyde).

The'Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3. 12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

, 6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain'afe shutdown in the event of a fire shall be reported in accordance with 10 CFR 50.73.

PALO VERDE - UNIT 2 6-20 AMENDMENT NO.

8

ADMINISTRATIVE CONTROLS 6.IO RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10. 1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures of Specification 6.8. 1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6. 10.2 The following records shall be retained for the duration of the unit

.Operating License:-

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the FSAR.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released beyond the SITE BOUNDARY.

e.

Records of transient or operational cycles for those unit components identified in Tables 5.7-1 and 5.7-2.

f.

Records of reactor tests and"experiments.

g.

Records of training and qualification for current members of the unit staff.

PALO VERDE - UNIT 2 6-21 AMENDMENT NO, 8

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.

k.

m.

n.

0 ~

P 6.1I RA Records of inservice inspections performed pursuant to these Technical Specifications.

Records of quality assurance activities required by the gA Manual not listed in Section 6.10.1.

Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

Records of PRB meetings and of NSG activities.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.9 including the date at which the service life commences and associated installation and maintenance records.

Records of audits performed under the requirements of Specifications 6.5.3.5 and 6.8.4.

Records of analyses required by the radiological environmental moni-toring program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and gA records showing that these procedures were followed.

Heteorological

data, summarized and reported in a format consistent with the recommendations of Regulatory Guides 1.21 and 1.23.

Records of secondary water sampling and water quality.

DIATION PROTECTION PROGRAM

6. 11. 1 Procedures for personnel radiation protection shall be prepared consis-tent with, the.requirements of 10 CFR Part 20 and shall be approved, maintained,.

and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA

6. 12. 1 In lieu of the '-'control device" or "alarm signal" required by paragraph 20,203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a hi.gh radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Expo-sure Permit (REP)*.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

• Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the REP issuance requirement during the perform-ance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

PALO VERDE - UNIT 2 6-22 AhfENDhlENT NO 8

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a.

A radiation monitoring device which continuously indicates the radia-tion dose rate in the area.

b.

C.

A radiation monitoring device which continuously integrates the radia-tion dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

A radiation protection qualified individual (i.e., qualified in radia-tion protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation sur-veillance at the frequency specified by the facility Radiation Protec-tion Supervisor or his designated alternate in the REP.

6. 12.2 In addition to the requirements of Specification

6. 12. 1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the

- administrative control of the Shift Supervisor on duty and/or radiation protec-tion supervision.

Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the

, immediate work area and the maximum allowable stay time for individuals in that

, area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems*, that are located within large areas, such as PMR containment, where

,,no enclosure exists for purposes of locking, and no enclosure can be reasonably

. constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by per-sonnel qualified in'adiation protection procedures to provide positive exposare control over the activities within the area.

6. 13 PROCESS CONTROL PROGRAM PCP

6. 13. 1 The PCP shall be approved by the Commission prior to implementation.

" 6. 13.2 Licensee-initiated changes to the PCP:

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

1)

Sufficiently detailed information to totally support the ration-ale for the change without benefit of additional or supplemental information; and 2)

A determination*that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

• Measurement made at 18 inches from source of radioactivity.

PALO VERDE " UNIT 2 6-23 AMENDMENT NO 8

ADMINISTRATIVE CONTROLS

6. 14 OFFSITE DOSE CALCULATION MANUAL ODCM

6. 14. 1 The ODCM shall be approved by the Commission prior to implementation.

'. 14.2 Licensee-initiated changes to the ODCM:

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

This submittal shall contain:

1)

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

and 2)

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.

6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

6. 15. 1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PRB.

The discussion of each change shall contain:

1)

A summary of the evaluation that led to the determination that-the change could be made in accordance with 10 CFR 50.59.

2)

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3)

A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

• Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.

PALO VERDE " UNIT 2 6-24