ML17300A742
| ML17300A742 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/08/1987 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300A744 | List: |
| References | |
| NUDOCS 8704200184 | |
| Download: ML17300A742 (18) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUIBLIC SERVICE COMPANY ET AL DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
15 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated January 19,
- 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Rater and Power, and Southern Ca'lifornia Public Power Authority (licensees),
complies with the standards and requirements of the Atomic Energy Act of
- 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
lg 8704 OCy, 05000528
C
2.
Accordingly, the license is amended hy changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 15, 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'OMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
April 8, 1987 E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-B
April 8, 1987 ENCLOSURE TO LICENSE AMENDMENT NO.
15 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 6-30 B 3/4 6-4 Overleaf Pa es 3/4 6-29 B 3/4 6-3
TABLE 3. 6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBER PENETRATION NUMBER FUNCTION E.
SAFETY/RELIEF VALVES MAXIMUM ACTUATION TIME (SECONDS)
SIA-PSV 1518'3 SIB-PSV 1408 24 SIB-PSV 189 26 SIA-PSV 179 27 SIE-PSV 474 28 Co'ntainment recirculation sump to containment
- spray, LPSI and HPSI headers lA & 1B Containment recirculation sump to containment spray, LPSI and HPSI headers 2A & 2B From shutdown cool ing RC Loop 2 From shutdown cooling RC Loop 1 Safety injection drain relief N.A.
N.A.
N.A."
N.A."
N.A.
"Valves also covered by Specification 3/4.4.8.3 ONot Type C Tested PALO VERDE - UNIT 1 3/4 6 QR
TABLE 3 6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBER PENETRATION NUMBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)
SGE-UV 169¹ 1
84 2 SGE"UV 183¹ 3
8( 4 SGA-UV 1133¹ SGA-UV 1134¹ SGB" UV 1135A¹ 1-4 SG8" UV 1135B¹ 1"4 SGB" UV 1136A¹ 1"4 SGB" UV 1136B¹ 1-4 SGA"UV 174¹ 8
SGA"UV 132¹ 8
SGB"UV 137¹ 10 SGA"UV 177¹ 10 SGB-UV 130¹ 11 SGA"UV 172¹ 11 SG8-UV I35¹ 12 F.
NORMALLY OPEN - ESF ACTUATED CLOSED Main steam isolation bypass Main steam isolation bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam generator feedwater Steam generator feedwater Steam generator feedwater Steam generator feedwater Downcomer FIV Downcomer FIV Downcomer FIV N. A.
N. A.
N.A.
N.A.
N.A.
N.A.
N. A.
N. A.
N.A.
N.A.
N. A.
N.A.
N.A.
N.A.
N.A.
¹Not Type C tested PALO VERDE - UNIT 1 3/4 6"30 AMENDMENT NO.
15
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.
Haintaining 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 valve 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.
E 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 5y 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 SYSTEHS 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-accideht 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 REHOVAL SYSTEM The OPERABILITY of the iodine removal system ensures that sufficient NqH<
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.
I PALO VERDE - UNIT 1 B 3/4 6-3
CONTAINMENT SYSTEMS BASES 3/4. 6. 3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment automatic isolation valves ensures that 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 consistent with the requirements of GDC 54 through GDC 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive 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 FSAR that are not required to be listed in Table 3.6-1 are the following:
main steam safety valves, main steam atmospheric dump valves, and main steam isolation valves.
The main steam safety valves have very high pressure setpoints to 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 and systems required for the detection and control of hydrogen,gas ensures that this equipment will be available to maintain the hydrogen 'concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit (or the purge system) is capable of control ling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of water and (3)"corrosion of metals within containment.
These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
There is a hydrogen monitor and a oxygen monitor in the Post Accident Sam-pling System (PASS).
There is a line from the two containment hydrogen monitors to the PASS which allows the licensee to monitor hydrogen concentration in the containment following an accident with the PASS.
An OPERABLE hydrogen monitor in the PASS allows the licensee to enter Modes 1 and 2 with one containment hydrogen monitor inoperable.
For the hydrogen monitor in PASS to be OPERABLE, the valves in the piping to the monitor must be OPERABLE.
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-OBOQ).
PALO VERDE " UNIT 1 B 3/4 6-4 AMENDMENT NO.
15
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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.
9 License No. NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment, dated January 19, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
complies with the standards and requirements of the Atomic Energy Act.of
- 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of Act, and the regulations of the COIImIission; 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; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; The issuance of this amendment.is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-51 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, 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
Enclosure:
Changes to the Technical Specifications Date of Issuance:
April 8, 1987 E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-8
April 8, 1987 ENCLOSUPE TO LICENSE AYiENDtIEHT NO.
9 FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Also to be replaced are the following overleaf pages,to the amended pages.
Amendment Pa es 3/4 6-30 B 3/4 6-4 Overleaf Pa es 3/4 6-29 B 3/4 6-3
TABLE 3. 6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBER PENETRATION NUMBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)
SIA-PSV 151¹ 23 SIB-PSV 140¹ 24 E.
SAFETY/RELlFF VALVES Containment ;.<<;irculation sump to containmenlt...nray, LPSI and HPSI headers 1A 4 1B Containment recirculation sump to containment
N.A.
SIB-PSV 189 SIA-PSV 179 SIE-PSV 474 26 27 28 From shutdown cooling RC Loop 2 From shutdown cooling RC Loop 1 Safety, injection drain relief N.A."
N.A."
N.A.
"Valves also covered by Specification 3/4.4.8.3.
¹Not Type C tested.
PALO VERDE " UNIT 2 3/4 6-29
TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBER PENETRATION NUMBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)
F.
NORMALLY OPEN - ESF ACTUATED CLOSED SGB-UV SGB-UV SGB-UV SGA-UV 1135B¹ 1-4 1136A¹ 1-4
'136B¹ 174¹ SGE-UV 169¹ 1 4 2 SGE-UV 183¹ 3
8c 4 SGA-UV 1133¹ 1"4 SGA-UY 1134¹ 1-4 SGB-UV 1135A¹ 1-4 Main steam isolation bypass Main steam isolation bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam generator feedwater N. A.
N.A.
N.A.
N.A.
N.A.
N.A.
N. A.
N.A.
N.A.
SGB-UV 132¹ 8
Steam generator feedwater N.A.
SGB-UV 137¹ 10 SGA-UV 177¹ 10 SGB-UV 130¹ 11 SGA-UV 172¹ 11 SGB"UV 135¹ 12 Steam generator feedwater Steam generator feedwater Downcomer FIV Downcomer FIV Downcomer FIY N.A.
N. A.
N.A.
N.A.
N.A.
¹Not Type C tested.
PALO VERDE - UNIT 2 3/4 6-30 AMENDMENT NO. 9
CONTAINMENT SYSTEHS BASES 3/4.6. 1.7 CONTAINMENT VENTILATION SYSTEH 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'perations.
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 5y th'e 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 SYSTEH 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 REHOVAL SYSTEH 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 NqH<
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
CONTAINMENT SYSTEMS BASES 3/4. 6. 3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment automatic isolation valves ensures that 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 consistent with the requirements of GDC 54 through GDC 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive 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 FSAR that are not required to be listed in Table 3.6-1 are the following:
main steam safety valves, main steam atmospheric dump valves, and main steam isolation valves.
The main steam safety valves have very high pressure setpoints to 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 and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below 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 and (3) corrosion of metals within containment.
These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment 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. 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 6-4 AMENDMENT NO.
9