ML17303A318
| ML17303A318 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/09/1987 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17303A319 | List: |
| References | |
| NUDOCS 8702270093 | |
| Download: ML17303A318 (37) | |
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COYPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 1
ANENDt'.ENT TO FACILITY OPERATING LICENSE Amendment No.
13 License No.
NPF-41 1.
The Nuclear Reoulatory Commission (the Commission) has found that:
A.
The application for amendment, dated November 6, 1986, 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 wf 11 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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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paraoraph 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. 13, 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.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION "zw E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-B
Enclosure:
Chanoes to the Technical Specifications Date of Issuance:
February 9, 1987
~ ~
February 9, 1987 ENCLOSURE TO LICENSE AMENDMENT NO.
13 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.
Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pa es 3/4 6-38 3/4 6-39 3/4 7-20 3/4 9-]5 B 3/4 6-4 B 3/4 7-5 B 3/4 7-6 B 3/4 9-3 6-3 6-4 Overleaf Pa es 3/4 6-37 3/4 7-19 3/4 9-16 B 3/4 6-3
CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two portable independent containment hydrogen recombiner systems shared among the three units shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or meet the requirements of Specification 3.6.4.3, or be in at least 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 />."
SURVEILLANCE RE UIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:
a.
At least once per 6 months by:
1.
Verifying through a visual examination that there, is no evi-dence of abnormal conditions within the recombiner enclosure and control console.
2.
Operating the air blast heat exchanger fan motor and enclosed blower motor continuously for at least 30 minutes.
At least once per year by:
1.
Performing, a CHANNEL CALIBRATION of recombiner instrumentation.
Performing a "Low-Level Test-Heater Power Off" and "Low-Level Test-Heater Power On" test and verifying that the recombiner temperature increases to and is maintained at 600 a 25~F for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
With power off and a simulated input signal of 1280 F, verify the OPERABILITY of all control circuits.
When this test is conducted, the air blast heat exchanger fan motor and enclosed blower motor shall be operated continuously for at least 30 minutes.
c.
At least once per 5 years by performing a Recombiner System "High-Level Test" and verifying that the recombiner temperature increases to and is maintained at 1200
+ 50 F for at least one hour.
- Prior to March 30, 1986 or until the completion of the environmental qualifi-cation modifications to the hydrogen recombiner
- system, whichever occurs first, the provisions of 'Specification
- 3. 0.4 are not applicable during implementation of the environmental qualification modifications to the hydrogen recombiner system when the containment hydrogen purge cleanup system described in Specifi-cation 3.6.4.3 is OPERABLE.
PALO VERDE - UNIT 1 3/4 6-37 Amendment No.
5
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.
3.
Verifying a system flow rate of 50 scfm f 10K during system operation when tested in accordance with ANSI N510-1980.
I After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,"
meets the laboratory testing criteria of Regulatory Position C. 6. a of Regulatory Guide 1.52, Revision 2, March 1978."
d.
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined HEPA filters, pre-filters and charcoal adsorber banks is less than
2.
Verifying that the heaters dissipate at least 0.5 kW when tested in accordance with ANSI N510-1980.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or'equal to 99K of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 50 scfm +
10X.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.0X of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 50 scfm t 10K.
"ANSI N509-1980 is applicable for this specification.
PALO VERDE - UNIT 1 3/4 6-39 AMENDMENT NO. l3
PLANT SYSTEHS 3/4.7.8 ESF PUHP ROOH AIR EXHAUST CLEANUP SYSTEH LIHITING CONDITION FOR OPERATION 3.7.8*
Two independent ESF pump room air exhaust cleanup systems shall be OPERABLE.
APPLICABILITY:
HODES 1, 2, 3, and 4.
ACTION:
With one ESF pump room air exhaust cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least 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 UIREHENTS 4.7.8 Each ESF pump room air exhaust cleanup system shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA fi'lter or charcoal adsorber
- housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:
~CAUT ON Refere-nce Specification 3.9.l2 page 3/4 9-14 PALO VERDE - UNIT 1 3/4 7-19
REFUELING OPERATIONS SURVEILLANCE RE UIREHENTS Continued 1.
Verifying that the cleanup system satisfies the in-place testing acceptance'riteria and uses the test procedures of Regulatory Positions C.5. a, C. 5. c and C. 5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6000 cfm a 10X.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, Harch 1978,* meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*
3.
Verifying a system flow rate of 6000 cfm k 10K during system operation when tested in accordance with ANSI N510-1980.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6. a of Regulatory Guide 1.52, Revision 2, March 1978.~
d.
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined HEPA filters, pre-filters, heaters, and charcoal adsorber banks is less than 8.4 inches Water Gauge while operating the system at a flow rate of 6000 cfm + lOX.
2.
Verifying that on a high radiation test signal, the system automatically starts (unless already operating) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the system maintains the fuel building at a measurable negative pressure relative to the outside atmosphere during system operation.
"ANSI N509-1980 is applicable for this specification.
PALO VERDE - UNIT 1 3/4 9"15 AMENDMENT NO. 13
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 resil.ient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.
The 0.60 L
leakage limit shall not be exceeded when the leakage rates determined 3y 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 'EPRESSURIZATION 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.
3/4.6.2.2 IODINE REMOVAL SYSTEM The OPERABILITY of the iodine removal system ensures that sufficient NzH~
is added to the containment spray in the event of a LOCA.
The limits on NzH~
volume and,concentration ensure adequate chemical available to remove iodine from the containment atmosphere following a LOCA.
l PALO VERDE - UNIT 1 B 3/4 6-3
PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM The OPERABILITY of the control room essential filtration system ensures that the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radia-tion exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM The OPERABILITY of the ESF pump room air exhaust cleanup system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calcula-tions was assumed in the safety analyses.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
3/4.7. 9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adver'se effect on any safety-related system.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Review Board.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e. g., temperature, atmosphere, location, etc. ), and the recommedations of Regulatory Guides 8.8 and 8. 10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
PALO VERDE " UNIT 1 B 3/4 7-5 AMENDMENT NO. 13
t l'
REFUELING OPERATIONS BASES A shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during surveillance testing of ECCS pumps.
This is necessary to meet Surveillance 4.5.2, flow testing of the HPSI pumps without other pumps
- running, and 4.3.3.5, testing of the containment spray pumps and LPSI pumps during surveillance of the remote shutdown system.
3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9. 10 and 3/4.9. 11 MATER LEVEL -
REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth (at least 23 feet above the top of the spent fuel) is available to remove a nominal 99'f the assumed 10X iodine gap activity released from the rupture of an irradiated fuel assembly for a maximum fuel rod pressurization of 1200 psig.
The minimum water depth is consistent with the assumptions of the safety analysis.
3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
PALO VERDE - UNIT 1 B 3/4 9"3 AMENDMENT NO. 13
PRES IOEHT EXECUTIVE V.P.
V.P.
HUCLEAR PROOUCT ION ASST.
V.P. NUCLEAR PRODUCTION PVHGS PLANT MANAGER MGR.
NUCLEAR SAFETY ISEG/NSG OIR.
TECHNICAL SERVICES OIR.
CORPORATE OA
- MGR, EMERGENCY PLAN MGR.
OPERATIONS MGR.
TRANSITION MGR.
NUCLEAR ENGINEERING ASST. MGR.
CORPORATE OA LlGR.
AOMINISTRATIVE SERVICES MGR.
MAIHTEHANCE MGR.
NUCLEAR COHSTRUCTIOH LlGR.
QUALITYSYSTEMS/
ENGJHEERIHG MGR.
TRAINIHG
- MGR, OUTAGE MANAGELIENT MGR.
NUCLEAR FUELS MGR.
PROCUREMENT OUALITY.
WRF SUPERIHTEHOEHT
+
MGR.
PLANT SERVICES LlGR. RECOROS MGR.
OUALITYAUOITS/
MONITORING
+ LOCATEO ONSITE
+
MGR.
TECHNICAL SUPPORT LIANAGER COMPLJAHCE FIGURE 6. 2-1 OFFSITE ORGANIZATION LIGR. LICENSING LlGR.
QUALITY COHTROL
J
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O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. 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.
7 License No.
NPF-51 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated November 6, 1986, by the Arizona Public Service Company (APS) on behalf of itself and the Salt Piver Project Agricultural Improvement and Power District, El,Paso Electric
- Company, Southern California Edison Companv, Public Service Companv 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 Eneroy Act of
'1954, as amended (the Act) and the Commission's reoulations 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 complia'nce with the Commission's reaulations; 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.
Accordinaly, the license is amended by chanaes to the 'Technical Specifications as indicated in the enclosure to this license amendment, and paraaraph 2.C(2) of Facility Operatina 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 throuah Amendment No. 7, and the Environmental Protection Plan contained in Appenaix 8, are hereby incorporated in this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COYMISSION E. A. Licitra, Project Manaaer PWR Project Directorate No.
7 Division of PWP Licensina-R
Enclosure:
Chanaes to the Technical Specifications Date of Issuance:
February 9, 1987
February 9, 1987 ENCLOSURE TO LICENSE AMENDMENT NO.
7 FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace the followino 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 chanoe.
Also to be replaced are the followirg overleaf pages to the amended pages.
A~ff
~ff PP 3/4 6-38 3/4 6-39 3/4 7-20 3/4 9-15 B 3/4 6-4 B 3/4 7-5 B 3/4 7-6 B 3/4 9-3 6-3 6-4 3/4 6-37 3/4 7-19 3/4 9-16 B 3/4 6-3
CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two portable independent containment hydrogen recombiner systems shared among the three units shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or meet the requirements of Specification 3.6.4.3, or be in at least 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 />.
SURVEILLANCE RE UIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:
At least once per 6 months by:
l.
Verifying through a visual examination that there is no evi-dence of abnormal conditions within the recombiner enclosure and control console.
2.
Operating the air blast heat exchanger fan motor and enclosed blower motor continuously for at least 30 minutes.
b.
At least once per year by:
1.
Performing a
CHANNEL CALIBRATION of recombiner instrumentation.
2.
Performing a "Low-Level Test-Heater Power Off" and "Low-Level Test-Heater Power On" test and verifying that the recombiner temperature increases to and is maintained at 600 f 250F for at least one hour.
With power off and a simulated input signal of 1280'F, verify the OPERABILITY of all control circuits.
When this test is conducted, the air blast heat exchanger fan motor and enclosed blower motor shall be operated continuously for at least 30 minutes.
C.
At least once per 5 years by performing a Recombiner System "High-Level Test" and verifying that the recombiner temperature increases to and is maintained at 1200 k 50'F for at least one hour PALO VERDE - UNIT 2 3/4 6-37
4
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.
3.
Verifying a system flow rate of 50 scfm 2 10K during system operation when tested in accordance with ANSI N510-1980.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,*
meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*
d.
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined HEPA filters, pre-filters and charcoal adsorber banks is less than 8.4 inches Water Gauge while operating the system at a flow rate of 50 scfm + lOX.
2.
Verifying that the heaters dissipate at least 0.5 kW when tested in accordance with ANSI N510-1980.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99K of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 50 scfm
+ 10'.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.0X of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 50 scfm t 10K.
- ANSI N509-1980 is applicable for this specification.
PALO VERDE - UNIT 2 3/4 6-39 AMENDMENT NO, 7
PLANT SYSTEMS 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one ESF pump room air exhaust cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least 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 4.7.8 Each ESF pump room air exhaust cleanup system shall be demonstrated OPERABLE:
a.
b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
At least once per 18 months or (1) after any structural maintenance on the KEPA filter or charcoal adsorber
- housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:
CACUCON Reference Specification 3.9.12 page 3/4 9-14 PALO VERDE - UNIT 2 3/4 7"19
REFUELING OPERATIONS SURVEILLANCE RE UIREMENTS Continued l.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5. a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6000 cfm t 10K.
C.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978," meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978."
3.
Verifying a system flow rate of 6000 cfm t 10K during system operation when tested in accordance with ANSI N510-1980.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory'Position C.6. a of Regulatory Guide 1.52, Revision 2, March 1978."
d.
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined HEPA filters, pre-filters, heaters, and charcoal adsorber banks is less than 8.4 inches Water Gauge while operating the system at a flow rate of 6000 cfm + 10K.
2.
Verifying that on a high radiation test signal, the system automatically starts (unless already operating) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the system maintains the fuel building at a measurable negative pressure relative to the outside atmosphere during system operation.
"ANSI N509-1980 is applicable for this specification.
PALO VERDE - UNIT 2 3/4 9-15 AMENDMENT NO. 7
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 failure develops.
The 0.60 L
leakage limit shall not be exceeded when the leakage rates determined 3y 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.
3/4. 6. 2. 2 IODINE REMOVAL SYSTEM The OPERABILITY of the iodine removal system ensures that sufficient N~H~
is added to the containment spray in the event of a LOCA.
The limits on N~H~
volume and concentration ensure adequate chemical available to remove iodine from the containment atmosphere following a LOCA.
PALO VERDE UNIT 2 B 3/4 6-3
PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM The OPERABILITY of the control room essential, filtration system ensures that the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radia-tion exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM The OPERABILITY of the ESF pump room air exhaust cleanup system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calcula-tions was assumed in the safety analyses.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Review Board.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,
temperature, atmosphere, location, etc. ), and the recommedations of Regulatory Guides
- 8. 8 and 8. 10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
PALO VERDE - UNIT 2 B 3/4 7-5 AMENDMENT NO.
7
REFUELING OPERATIONS BASES A shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during surveillance testing of ECCS pumps.
This is necessary to meet Surveillance 4.5.2, flow testing of the HPSI pumps without other pumps
- running, and 4.3.3.5, testing of the containment spray pumps and LPSI pumps during surveillance of the remote shutdown system.
3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9. 10 and 3/4.9. 11 WATER LEVEL REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth (at least 23 feet above the top of the spent fuel) is available to remove a nominal 99'f the assumed 10K iodine gap activity released from the rupture of an irradiated fuel assembly for a maximum fuel rod pressurization of 1200 psig.
The minimum water depth is consistent with the assumptions of the safety analysis.
3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION'SYSTEM The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) 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 in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).
PALO VERDE - UNIT 2 B 3/4 9-3 AMENDMENT NO. 7
P RES IOENT EXECUTIVE V.P.
V.P.
NUCLEAR PROOUCT ION ASST'.P.HUCLEAR PRODUCT IOH PVHGS PLANT MAHAGER MGR.
HUCLEAR SAFETY ISEG/HSG DIR.
TECHNICAL SERVICES OIR.
CORPORATE OA MGR.
EMERGENCY PLAN MGR.
OPERATIONS MGR.
TRANSITION MGR.
NUCLEAR ENGIHEERING ASST. MGR.
CORPORATE OA MGR.
AOMIH)STRATIVE SERVICES MGR.
MAINTEHANCE MGR.
HUCLEAR COHSTRUCTION MGR.
OUALITYSYSTEMS/
EHGINEERIHG MGR.
TRAINIHG MGR.
OUTAGE MANAGEMENT MGR.
NUCLEAR FUELS MGR.
PROCUREMEHT OUALITY.
HRF SUPERINTENDENT 4
MGR.
PLANT SERVICES MGR. RECOROS MGR.
QUALITY AUOITS/
MOHITORIHG MGR.
TECHNICAL SUPPORT MGR. LICENSING MGR.
OUALITY CONTROL
+ LOCATEO OHSITE MANAGER COMPLIANCE FIGURE 6.2-1 OFFSITE ORGANIZATION
HT IC)(
m Cl m
EXECUTIVE V.P.
V.P.
HUCLEAR PRODUCTION ASST.
V.P. NUCLEAR PRODUCTION PVHGS PLANT MAHAGER MGR.
NUCLEAR SAFETY ISEG/NSG DIR.
TECHNICAL SERVICES DIR.
CORPORATE OA MGR.
EMERGENCY PLAN MGR.
OPERATIOHS MGR.
TRANS IT IOH MGR.
NUCLEAR EHGIHEERIHG ASST. MGR.
CORPORATE OA MGR.
ADMIHISTRATIVE SERVICES MGR.
MAIHTEHANCE MGR.
HUCLEAR CONSTRUCTION MGR.
QUALITYSYSTEMS/
EHGIHEERIHG MGR.
TRAINING MGR.
OUTAGE MAHAGEMEHT MGR.
NUCLEAR FUELS MGR.
PROCUREMENT QUALITY.
WRF SUPERINTENDENT MGR.
PLANT SERVICES MGR. RECORDS MGR.
QUALITY AUDITS/
MONITORING MGR.
TECHNICAL SUPPORT MGR. LICENSING MGR.
QUALITY CONTROL
+ LOCATED ONSITE MAHAGER COMPLIANCE FIGURE 6.2-1 OFFSITE ORGANIZATION
O ICl(
m CD m
OUTAGE MANAGEMENT MAHAGER TECHNICAL SUPPORT MAHAGER PVNGS PLANT MANAGER OPERATIONS MANAGER MAINTEHANCE MAHAGER PLANT SERVICES MANAGER MANAGER COMPLIANCE MAHAGER OPS ENGINEERIHG SUPERINTEHDEHT UNIT I SUPERINTENDENT ISC MAIHTEHAHCE MANAGER OPERATIONS SECURITY SUPERVISOR STA SUPERINTENDENT UNIT 2 SUPERINTENDENT MCC SUPERVISOR FIRE PROTECTION MAHAGER RAD. PROT. I CHEM.
SUPERIHTEHOEHT UNIT 3 SUPERIHTENOENT ELEC. MAINTEHANCE SUPERINTENDEHT OPS COMPUTER SYSTEM SUPERVISOR OPERATIONS SUPPORT SUPERIHTEHDENT STATION SERVICES CD SUPERINTENOEHT MECHANICAL MAIHTEHANCE FIGURE 6.2-2 ONSITE ORGANIZATION