ML17300A363
| ML17300A363 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/11/1986 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300A365 | List: |
| References | |
| RTR-REGGD-01.052, RTR-REGGD-1.052 NUDOCS 8608210093 | |
| Download: ML17300A363 (19) | |
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UNITED STATES NUCLEAR REGUI ATORY COMMISSION WASHINGTON, O. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
7 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated August 3, 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, Publ.ic 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
'onducted 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 the Facility Operating License No. NPF-41 is hereby amended to read as follows:
86082100'V3 860811 PDR ADOCK 05000528 I, P PDR
/
~'
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, 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 August 5, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Change to the Technical Specifications Date of Issuance:
QQQ g y yy~
George
. Knight Director PWR Project Directorate No.
7 Division of PWR Licensing-B
AUG Zygo ENCLOSURE TO LICENSE AMENDMENT NO.
7 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 7-17 B 3/4 7-5 Overleaf Pa es 3/4 7-18 B 3/4 7-6
0 I
l l
l
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 1.
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 28,600 cfm a lOX.
2.
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".
3.
Verifying a system flow rate of 28,600 cfm + 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 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:
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 28,600 'cfm + lOX.
2.
Verifying that on a Control Room Essential Filtration Actuation Signal and on a SIAS, the system is automatically placed into a filtration mode of operation with flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the system maintains the control room at a positive pressure of greater than or equal. to 1/8-inch Water Gauge relative to adjacent areas during system operation at a makeup flow rate to the control room of less than or equal to 1000 cfm.
4.
Verifying that the emergency chilled water system will maintain the control room environment at a temperature less than or equal to 80 F for a period of 30 minutes.
"ANSI N509-1980 is applicable for this specification.
PALO VERDE - UNIT 1 3/4 7-17 AMENDMENT NO.
7
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued 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 OOP when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 28,600 cfm + 10K.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95K 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 28,600 cfm + 10K.
PALO VEROE - UNIT 1 3/4 7"18
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 radioacti,ve 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 o'n offsite dosage calcula-tions was assumed in the safety analyses.
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 shal]
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.
The visual inspection frequency is based upon maintaining a constant level of snubber protec5ion.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number PALO VERDE - UNIT 1 B 3/4 7"5 AMENDMENT NO.
7
~
~
PLANT SYSTEMS BASES SNUBBERS (Continued) of inoperable snubbers found during an inspection.
In order to establish the inspection frequency for each type of snubber, it was assumed that the fre-quency of failures and initiating events is constant with time and that the fai lure of any snubber could cause that system to be unprotected and to result in failure during an assumed initiating event.
Inspections performed before that interval has elapsed may be used as a
new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25K) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
The acceptance criter ia are to be used in the visual inspection to determine OPERABILITY of the snubbers.
E To provide assurance of snubber functional reliability one of three func-tional testing methods are used with the stated acceptance criteria:
1.
Functionally test 10K of a type of snubber with an additional 10K tested for each functional testing failure; or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was developed using "Maid's Sequential Probability Ratio Plan" as described in "equality Control and Industrial Statistics" by Acheson J.
Duncan.
Permanent or other exemptions from the surveillance program for 'individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal
- replaced, spring replaced, in high radiation area, in high temperature
- area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statis-tical bases for future consideration of snubber service life.
PALO VERDE - UNIT 1 8 3/4 7-6
j
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i+l7 +**~0 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'mendment No.
1 License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated August 3; 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 reasonab'le 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 the 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.',
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 August 5, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Change to the Technical Specifications Date of Issuance:
AUG I g George
. Knighton rector PWR Project Directorate No.
7 Division of PWR Licensing-B
ENCLOSURE TO LICENSE AMENDMENT NO.
1 FACILITYOPERATING 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 3/4 7-17 B 3/4 7-5 Over leaf Pa es 3/4 7-18 B 3/4 7-6
~
n p
~
PLANT SYSTEMS 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 28,600 cfm + lOX.
2.
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".
3.
Verifying a system flow rate of 28,600 cfm 2 1'uring 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 representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision.2, March 1978",
meets the 1'aboratory testing criteria of Regulatory Position C. 6. a of Regulatory Guide 1.52, Revision 2,.March 1978".
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined HEPA filters, pre-filters, and charcoal adsorber banks's less than 8.4 inches Water Gauge while operating the system at a flow rate of 28,600 cfm a 10K.
2.
Verifying that on a Control Room Essential Filtration Actuation Signal and on a SIAS, the system is automatically placed into a filtration mode of operation with flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8-inch Water Gauge relative to adjacent areas during system operation at a makeup flow rate to the control room of less than or equal to 1000 cfm.
Verifying that the emergency chilled water system will maintain the control room environment at a temperature less than or equal to 80 F for a period of 30 minutes.
"ANSI N509-1980 is applicable for this specification.
PALO VERDE " UNIT 2 3/4 7-17 AMENDMENT NO.
1
~
~
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.
After each complete or partial replacement of a HEPA fil.ter 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 28,600 cfm t lOX.
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'NSI N510-1980 while operating the system at a flow rate of 28,600 cfm + 10K.
PALO VERDE - UNIT 2 3/4 7-18
~
~
U 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 (3,976) 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'XHAUST 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.
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'f the system on which they are installed, would have no advei 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 snubber's 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'nubber 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'nubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number PALO VERDE - UNIT 2 B 3/4 7-5 AMENDMENT NO.
1
~
~
PLANT SYSTEMS BASES SNUBBERS Continued of inoperable snubbers found during an inspection.
In order to establish the inspection frequency for each type of snubber, it was assumed that the fre-quency of failures and initiating events is constant with time and that the failure of any snubber could cause that system to be unprotected and to result in failure during an assumed initiating event.
Inspections performed before that interval has elapsed may be used as a new reference point to.determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25K) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
To provide assurance of snubber functional reliability one of three func-tional testing methods are used with the stated acceptance criteria:
l.
Functionally test 10K of a type of snubber with an additional '10X tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "guality Control and Industrial Statistics."
by Acheson J.
Ouncan.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completi'on of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal
- replaced, spring replaced, in high radiation area, in high temperature
- area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statis-tical bases for future consideration of snubber service life.
PALO VEROE " UNIT 2.
B 3/4 7"6