ML17306A955

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Amends 64,50 & 37 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Deleting Iodine Removal Sys from TS 3/4 3.6.2.2
ML17306A955
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 09/08/1992
From: Quay T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17306A956 List:
References
NUDOCS 9209170109
Download: ML17306A955 (21)
v • d • e


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+**y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 9209170109'20908 PDR ADOCK 05000528 ci P

PDR 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.64 License No.

NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Publi.c Service Company (APS or the licensee) 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 dated June 25,
1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will, operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C,

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2,C(2) of Facility Operating License No.

NPF-41 is hereby amended to read as follows:

3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 64, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protecti'on

Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 8,

1992 Theodore R. quay, Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

64 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 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.

Remove VII 3/4 6-17

,3/4 6-18 B 3/4 6-3 Insert VII 3/4 6-17 3/4 6-18 B 3/4 6-3

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XNDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT PAGE CONTAINMENT INTEGRITY.........................,...

3/4 6"1 CONTAINMENT LEAKAGE....

3/4 6-2 CONTAINMENT AIR LOCKS..........................

3/4. 6-4 INTERNAL PRESSURE AIR TEMPERATURE 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 SPRAY SYSTEM......

3/4. 6. 3 CONTAINMENT ISOLATION VALVES......

3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS ELECTRIC HYDROGEN RECOMBINERS 3/4 6"15 3/4 6-19

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3/4 6 37 HYDROGEN PURGE CLEANUP SYSTEM;.....

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3/4 6-38 PALO VERDE - UNIT 1 VII AMENDMENT NO. 64

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLA'NCE REQUIREMENTS 3/4.7.2 3/4.7.3 3/4. 7. 4 3/4. 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 f'RESSURE/TEMPERATUftE LIMITATION..

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

ESSENTIAL, SPRAY POND SYSTEM.

ULTIMA'l'E HEAT SINK.

ESSENTIAL CHILLED WATER SYSTEM.

CONTROL ROOM ESSENTIAL FILTRATION SYSTEM..

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

SNUBBERS SEALED SOURCE CONTAMINATION.

SHUTDOWN COOLING SYSTEM........'/4.7.

12 CONTROL ROOM AIR TEMPERATURE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4. 8. 1 A. C.

SOURCES SECTION 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCI E SAFIETY VALVES AUXILIARYFEEDWATER SYSTEM CONDENSATE STORAGE TANK ACTIVITY.,

MAIN STEAM LIliE ISCILATIGN VALVES.......,.........

ATMOSP'HERIC DUMP VALVES PAGE 3/4 7-1 3/4 7-4 3/4 7-6 3/4 7-7 3/4 7'"9'/47-10 3/4 7-11 3/4 7-12 3/4 7-13 3/4 7-14 3/4 7-lc) 3/4 7-16 3/4 7-19 3/4 7-21 3/4 7-2/

3/4 7-29 3/4 7-3O OP ERAT ING 3/4 8-1 SHUTDOWN...........................,'...'...........

3/4 8-8 CATHODIC PROTECTION.....'..'

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

27

CONTAINMENT SYSTEMS BASES 3/4. 6. l. 7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

To provide assurance that the 42-inch valves cannot be inadvertently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevent power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 42-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.

The 0'0 L

leakage limit shall not be exceeded when the leakage rates determined Ey the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4. 6. 2. 1 CONTAINMENT SPRAY S'STEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.

The containment spray system and the containment cooling system are redundant to each other in providing post-accident cooling of the containment atmosphere.

However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.

PALO VERDE - UNIT 1 B 3/4 6"3 AMENDMENT NO. 64

CONTAINMENT SYSTEMS BASES 3/4. 6. 3 CONTAINHENI'SOLATION VALVES The OPERABILITY of the containment automatic isolation valves ensures

that, the containment atmosphere will be isolated from the outside environment in th6 event of a release of radioactive material'to'he containment atmosphere or pressurization of the containment and is consistent'ith the requirements of GDC 54 through GDC 57 of Appendix A to 10 (lFR Part 50.

Containment 'isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of i'adjoactive material to the environ-ment will. be consistent with the assumptions used in the analyses for a LOCA.

The only valves in Table 6.2.4-1 of the PVNGS'FS'AR'that are not requireH to be listed in Tab'le 3.6-1 are the followingt main steam safety valves, main steam atmospheric dump valves, and ma'in steam isolation valves.

The main steam safety valves have very high piressure setpdints 'to'actuate and are cove'red b'

Specification 3/4.7.,1. 1.

The atmospheric dump valves and the main stealn isola tion valves are covered by Specifications 3/4.7. 1.6 and 3/4.7.1.5, respectively.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems

) equired for the dete'ction'nd control of hydrogen gas ensures that t6is eQuipme'nt will be available to maintain the hydrogen concentration within conta'intinent belbw its flammable limit during post-LOCA conditions.

Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of water anted (3) corrosion of metals within containment.

Thyrse'hy'drogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment'ollowing a LOCA," March 1971.

The use of ANSI Standard N509 (1980) in hindu hf ANSI Standard N509 (1.97li) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6. a and C.6.b, has been found,acceptable as documented i'n Revisiion 2 to Section 6.5. 1 of the Standard Review Plan (NURI:G-0800).

PALO VERDE - UNIT 1 B 3/4 6"4 AMENDMENT NO. - 27

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UNITEDSTATES 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. 50 License No.

NPF-51 The Nuclear Regulatory Commission (the 'Commission) has found that:

A.

The application for amendment by the Arizona Public Servi'ce Company (APS or the licensee) 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 dated June 25,
1991, 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 Part I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission',s regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the.public; and E.

The issuance of this amendment is in accordance with 10 CFR -Part 51 of the Commission's regulations and all-applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-51 is hereby amended to read as follows:

3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 50, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the faci.lity in accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Theodore R.

quay., Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance:

September 8,

1992

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

50 TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 Replace the following pages of the Appendix A Technical Specifi.cations with the enclosed pages.

The revised pages are identi,fied by amendment number and contain vertical lines indicating the areas of change.

Remove VII 3/4 6-17 3/4 6-18 B 3/4 6-3 Insert VII 3/4 6-17 3/4 6-18 B 3/4 6-3

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 PAGE 3/4 6-1 3/4 6-2 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 SPRAY SYSTEM......

3/4.6.3 CONTAINMENT ISOLATION VALVES...,

3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS'..........

ELECTRIC HYDROGEN RECOMBINERS..

HYDROGEN PURGE CLEANUP SYSTEM..

3/4 6-15 3/4 6-19 3/4 6-36 3/4 6-37 3/4 6-38 PALO VERDE " UNIT 2 VII AMENDMENT NO. 5O

i' INDEX L}t'I TING COND}. IOf45 FOR OPERATIOhf AND SURVEILI,ANCE,REQUIRE"ENTS SFC JON 3/4.7 PLANT SYSTEYS 3/4. 7. 1 TURBINE CYCLE SAFETY VALVES....................

AUXILIARY FEEDWATI R SYSTEM....,...

CONDENSATE STORAGE TANK ACTIVITY ~

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hlAIN STEAH LINE ISOLATION VALVlES..

ATMOSPHERIC DUh'ip VALVES...........

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3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIhfITATI 3/4.7.3 ESSENTIAL COOLIlVG WATER SYSTE~...,..........

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0 3/4.7.4 3/4.7.5 3/4.7.6 3/4.7.7 3/4.7.8 3/4.7.9, 3/4.7.}0 3/4.7.11 3/4.7.12 ESF PUVP ROOf'IR EXHAUST CLEANUP SV'STE'hf..

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SEALED SOURCE CONTAh'}NATION.,......

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

CONTROL ROOhl AIR TEMPERATURE.....

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3/4.8 ELECTRICAL POl4ER SYSTEMS ESSENTIAL SPRAY POND SYSTEM..........................

ULTIMATE HEAT SINK...................,,.........,.......

ES.ENTIAL CHILLED WATER SYSTEM........,................

CONTROL ROOhf ESSENTIAL FILTRATION SYSTE.H....'...'...'...',....

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-If,}

l 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 7-2}

3/4 7-27 3/4 7-24 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 VII I

.AhfE~DMEhfT NO. 8

CONTAINMENT SYSTEMS BASES 3/4. 6. 1. 7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or.steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

To provide assurance that the 42-inch valves cannot be inadvertently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevent power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 42-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will al.low the opportunity for repair.before gross leakage failure develops.

The 0.60 L

leakage limit shall not be exceeded when the leakage rates determined Ey the leakage integrity tests of these valves are added to the-previously determined total for all valves and penetrations subject to Type B and C tests.

3/4. 6. 2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4. 6.2. 1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.

The containment spray system and the containment cooling system are redundant to each other in providing post-accident cooling of the containment atmosphere.

However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to,OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.

PALO VERDE - UNIT 2 B 3/4 6"3 AMENDMENT NO. 50

CONTAINMENT SYSTEMS BASES 3/4. 6. 3 CONTAINMENT ISOLATION VAILVES The OPERABILITY of the containment.

automatic isolation valves ensures that the containment atmosphere will be isolated, from the outside enyiro'nment'n the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirem6nt's of GDC 54 through GDC 57 of Appendix A to 10'FR Part 50.

Containment isolation within the time limits,speci fied f'r thosie iso'latior> valves designe'd to Blase automatically ensures tlhat the release of radioactive material to the environ-ment will be consistent with the assumptions u.;ed in tlhe analyses fbr a ILOCA.

The only valves in Table 6.2.4-1 of 'the PVNGS FSAR that are not keqkired to be listed in Talble 3,.6-1 are the following:

main s'team safety valves'ain steam atmospheric dump valves, and main steam isolation valves.

This ataik steam safety valves have very high pressure setpoints to actuate and are cov'ered by Specification 3/4.7. 1. 1 The atmosplheric dump valves and the main steam isola-tion valves are covered by Specifications 3/4.7.1.6 and 3/4.7".1.5, respectivelly.

3/4.6.4 COMBUSTIBILE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the Ihydlrogen concentration within containment belo~ its flammable limit during Ipost-LOCA conditions.

Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of'wa'ted and (3) corrosion of metals within containm'en(.

'hese hydrogen control systems are consistent with the recommendations of Re)ulktdry'Gu'id6 1.7, "Control of Combustible Gas Concentrations

'in Conta'inkent Following a LOCA,," March 1971.

The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory -Guide. 1..5

, Reiiision 2, Pos'itions C.6.a and C. 6. b, has been found acceI>table as docium6ntkd in Revision 2 to SectioIi 6. 5.l 1 of the Standard Review Plan (NUREG-0800).

'ALO VERDE - UNIT 2 B 3/g 6l4 I

AMENDMENT NO.'

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No.

NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) 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 dated June 25,
1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and'he Commission's regulations set forth in 10 CFR Chapter I; B.

The facility wil-l operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not.be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-74 is hereby amended to read as follows:

3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

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

Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Theodore R. quay, Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance; September 8,

1992

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

37 TO FACILITY OPERATING LICENSE NO.

NPF-74 DOCKET NO.

STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages'he revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove VII 3/4 6-17 3/4 6-18 B 3/4 6-3 Insert VII 3/4 6-17 3/4 6-18 B 3/4 6-3

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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 PAGE 3/4 6-1 3/4 6"2 3/4 6-4 3/4 6-6 3/4 6-7 CONTAINMENT VESSEL STRUCTURAL INTEGRITY..............

3/4 6-8 CONTAINMENT VENTILATION SYSTEM.

3/4. 6. 2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4 6-14 CONTAINMENT SPRAY SYSTEM.............................

3/4 6"15 3/4.6.3 CONTAINMENT ISOLATION VALVES.

3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS 3/4 6-19 3/4 6"36 ELECTRIC HYDROGEN RECOMBINERS....

3/4 6-37 HYDROGEN PURGE CLEANUP SYSTEM.

3/4 6"38 PALO VERDE - UNIT 3 VII AMENDMENT NO. 37

0 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE R~EUIREMEN'll'S SECTION 3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE SAFETY VALVES..........

AUXILIARYFEEDWj(TER SYSTEM..

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

ACTIVITY MAIN STEAM LINE ISOLATION VALVES...

ATMOSPHERIC DUMP VALVES.

PAGE 3/4 7-:i 3/4 7-4 3/4 7-6 3/4 7-7 3/4 7-9 3/4 7-3.0 3/4. 7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.......,.. 3/4 7-11 3/4.7.3 ESSENTIAL COOI ING WATER SYSTEM........................

3/4 7"12 3/4.7.4 ESSENTIAl SPRAY POND SYSTEM...........................

3/4 7-13 3/4.7. 5 ULTIMATE HEAT SINK.......

3/4. 7. 6 ESSENTIAL CHILLEiD WATER SYSTEM.

3/4 7-14 3/4 7-15 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM....,......,......

3/4 7-16 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SY4TEH................

3/4 7-19 3/4.7.9 SNUBBERS 3/4. 7. 10 SEALED SOURCE CONTAMINATION..........

3/4.7. 11 SHUTDOWN COOLING SYSTEM.

3/4. 7. 12 CONTROL ROOM AIR TEMPERATURE.........

3/4.8 ELECTRICAL POWER SYSTEMS

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3/4 7-21 3/4 7-27 3/4 7-29 3/4 7-30 3/4.8. 1 A. C.

SOURCES OP ERATING.

3/4 8"1 SHUTDOWN 3/4 8-8 CATHODIC PROTECTION............

3/4 8-Ba PALO VERDE - UNIT 3 VIII

CONTAINMENT SYSTEMS BASES 3/4. 6. 1. 7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

To provide assurance that the 42-inch valves cannot be inadvertently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevent power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 42-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage fai lure develops.

The 0. 60 L

leakage limit shall not be exceeded when the leakage rates determined Ey the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

3/4. 6. 2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2. 1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.

The containment spray system and the containment cooling system are redundant to each other in providing post-accident cooling of the containment atmosphere.

However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.

PALO VERDE - UNIT 3 B 3/4 6-3 AMENDMENT NO. 37

CONTAINMENT SYSTEMS BASES 3/4. 6. 3 CONTAINMEN'I'SOLATION VALVES The OPERABILITY of the containment automatic isolation valves ensures tthat the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment, atmosphere or pressurization of the containment and is consiistent, with the requirements'f GDC 54 through GDC 57 of Appendix A to 10 CFR Part 50.

Containment isolation within the time limits specifi'ed fair those isolation valves designed to close automatically ensures that the.release of radioactive material to the environ-ment will be consistent with the assumptions iused iin the analyses for a LOCA.

The only valves in liable 6.,2.4-1 of the PVNGS FSAR that are not requ'ired

'o be listed in Table 3. 6-1 are the. following:

imaiin !steam safety valves, main steam atmospheric dump valves,,

and main steam Holhtion valves.

The main steam safety valves have very high ~iressure setpoinits itoi actuate and are covered by Specification 3/4.7,. 1. 1.

The atmospheric dump valves and the main steam isola tion valves are covered by Specifications 3/4.7. 1.6 and 3/4.7.. 1..5,, respectiVely.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment anid systems required for the detection and control of hydrogen gas ensures that thisi equipment will be available to maintain the hydrogen concentration withiin containment below its flammable limit during post-LOCA conditi'ons.

Either recokbiher'nit (or the purge system) is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions,

(,'

radiolytic decomposition of water and (3) corrosion of metals within containment These hydrogen control systems are consistent'ith the recommendations of Regula'to>'y Guide 1.7, "Control of Combustible Gas Concentrations i n Containment'ollowing a LOCA," March 1971.

The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1. 52, Revisi'on 2, Positions C. 6. a and C.6;b, has been found acceptable as documented in Revision 2 to Sec-

'ion 6.5. 1 of the Standard Review Plan.(NUREG-.0800).

PALO VERDE - UNIT 3 B 3/4 6-4

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