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{{#Wiki_filter:Technical Specification 5.5.14 | {{#Wiki_filter:Technical Specification 5.5.14 Palo Verde raps Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Mail Station 7636 102-06689-TNW/RKR/CJS Tel (623) 393-5774 April 16, 2013 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | ||
==Dear Sirs:== | ==Dear Sirs:== | ||
==Subject:== | ==Subject:== | ||
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Technical Specification (TS) Bases Revision 57 and Technical Requirements Manual (TRM) Revision 57 Pursuant to PVNGS TS 5.5.14, "Technical Specifications Bases Control Program," Arizona Public Service Company (APS) is submitting TS Bases Revision 57. In addition, APS is submitting TRM Revision 57. TRM Revision 57 was implemented April 10, 2013 and TS Bases Revision 57 was also implemented on April 10, 2013.Electronic files of the revised TS Bases and TRM are provided as Enclosure | Palo Verde Nuclear Generating Station (PVNGS) | ||
Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Technical Specification (TS) Bases Revision 57 and Technical Requirements Manual (TRM) Revision 57 Pursuant to PVNGS TS 5.5.14, "Technical Specifications Bases Control Program," | |||
J. K. Rankin NRC NRR Project Manager for PVNGS (enclosures) | Arizona Public Service Company (APS) is submitting TS Bases Revision 57. In addition, APS is submitting TRM Revision 57. TRM Revision 57 was implemented April 10, 2013 and TS Bases Revision 57 was also implemented on April 10, 2013. | ||
M. A. Brown NRC Senior Resident Inspector for PVNGS (w/o enclosures) | Electronic files of the revised TS Bases and TRM are provided as Enclosure 1. The summary of changes for each document is provided in Enclosure 2. | ||
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 San Onofre 0 South Texas 0 Wolf Creek IJk4C ENCLOSURE 2 PVNGS Technical Specification Bases Revision 57 and TRM Revision 57 Summary of Changes I Summary of Changes Technical Specifications Bases Revision 57 TRM Revision 57 Technical Specification Bases Revision 57 includes the following changes:* LDCR 10-B012 reflected removal of Unit 3 Post-Accident Sampling System (PASS)containment isolation valve (CIV) RDB UV-407 from TS Bases 3.3.10, Post-Accident Monitoring Instrumentation, as described in the LCO Section, item 8, Containment Isolation Valve Position. | No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241. | ||
License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. | Sincerely, | ||
The Unit 3 valve was removed during the past Unit 3 outage." LDCR 12-B008 clarified TS Bases 3.1.7, Regulating Control Element Assembly (CEA)Insertion Limits, Background Section, that the CEA fully withdrawn position is specified in the COLR. This is an editorial enhancement." LDCR 12-B009 removed specific surveillance frequencies stated in various TS Bases which were missed during the implementation of TSTF-425 and License Amendment 188. This is editorial correction. | (,t)614 (-J | ||
* LDCR 12-BOll corrected and clarified the description of the emergency diesel generator (EDG) performance requirements during starting under loss of power (LOP), with or without safety injection actuation plant conditions. | / | ||
The changes clarified that the EDG is to start and close the EDG breaker within a 10 second window.Technical Requirements Manual (TRM) Revision 57 includes the following changes:* LDCR 10-R012 removed Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (CIV) RDB UV-407 from the TRM Component List T7.0.300, Containment Isolation Valves. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. | A Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/CJS/hsc Enclosure 1: Optical Storage Media (OSM) Electronic Files of PVNGS TS Bases Revision 57 and TRM Revision 57 Enclosure 2: PVNGS Technical Specification Bases Revision 57 and TRM Revision 57 Summary of Changes cc: A.T. Howell III NRC Region IV Regional Administrator (enclosures) | ||
The Unit 3 valve was removed during the past Unit 3 outage.* LDCR 12-RO01 removed overpressure protection valves AFB PSV-0106 and 0107 from containment isolation valves (CIVs) AFB UV-034 and 35 from TRM Component List T7.0.300, | J. K. Rankin NRC NRR Project Manager for PVNGS (enclosures) | ||
The TRM requirements were redundant to Inservice Testing requirements defined in Technical Specification 5.5.8.3}} | M. A. Brown NRC Senior Resident Inspector for PVNGS (w/o enclosures) | ||
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 San Onofre 0 South Texas 0 Wolf Creek IJk4C | |||
ENCLOSURE 2 PVNGS Technical Specification Bases Revision 57 and TRM Revision 57 Summary of Changes I | |||
Summary of Changes Technical Specifications Bases Revision 57 TRM Revision 57 Technical Specification Bases Revision 57 includes the following changes: | |||
* LDCR 10-B012 reflected removal of Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (CIV) RDB UV-407 from TS Bases 3.3.10, Post-Accident Monitoring Instrumentation, as described in the LCO Section, item 8, Containment Isolation Valve Position. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. The Unit 3 valve was removed during the past Unit 3 outage. | |||
" LDCR 12-B008 clarified TS Bases 3.1.7, Regulating Control Element Assembly (CEA) | |||
Insertion Limits, Background Section, that the CEA fully withdrawn position is specified in the COLR. This is an editorial enhancement. | |||
" LDCR 12-B009 removed specific surveillance frequencies stated in various TS Bases which were missed during the implementation of TSTF-425 and License Amendment 188. This is editorial correction. | |||
* LDCR 12-BOll corrected and clarified the description of the emergency diesel generator (EDG) performance requirements during starting under loss of power (LOP), | |||
with or without safety injection actuation plant conditions. The changes clarified that the EDG is to start and close the EDG breaker within a 10 second window. | |||
Technical Requirements Manual (TRM) Revision 57 includes the following changes: | |||
* LDCR 10-R012 removed Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (CIV) RDB UV-407 from the TRM Component List T7.0.300, Containment Isolation Valves. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. The Unit 3 valve was removed during the past Unit 3 outage. | |||
* LDCR 12-RO01 removed overpressure protection valves AFB PSV-0106 and 0107 from containment isolation valves (CIVs) AFB UV-034 and 35 from TRM Component List T7.0.300, ContainmentIsolation Valves. The valves were replaced by a pressure equalizing line from the valve bonnets to the process piping. | |||
" LDCR 12-R005 updated the applicable industry standard edition date for Unit 1 (ASTM E185-79) and Units 2 and 3 (ASTM E185-82) in TRM Appendix TA, Reactor Coolant System Pressure and Temperature Limits Report (PTLR), Section TA6.2, Evaluation of Surveillance Data Credibility. | |||
" LDCR 12-R006 corrected the description of the responsible organizations for the Inservice Inspection (ISI) and Inservice Testing (IST) programs in TRM Section 5.0.500.8, Inservice Inspection and Testing Programs. | |||
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Summary of Changes Technical Specifications Bases Revision 57 TRM Revision 57 LDCR 12-R008 deleted the High Pressure Safety Injection (HPSI), Low Pressure Safety Injection (LPSI) and Containment Spray pump miniflow differential pressure test requirements from the TRM (Sections 5.0.500.8.e, 5.0.500.8.f and 5.0.500.8.g). The TRM requirements were redundant to Inservice Testing requirements defined in Technical Specification 5.5.8. | |||
3}} | |||
Revision as of 19:05, 4 November 2019
| ML13120A500 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/16/2013 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06689-TNW/RKR/CJS | |
| Download: ML13120A500 (4) | |
Text
Technical Specification 5.5.14 Palo Verde raps Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Mail Station 7636 102-06689-TNW/RKR/CJS Tel (623) 393-5774 April 16, 2013 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Technical Specification (TS) Bases Revision 57 and Technical Requirements Manual (TRM) Revision 57 Pursuant to PVNGS TS 5.5.14, "Technical Specifications Bases Control Program,"
Arizona Public Service Company (APS) is submitting TS Bases Revision 57. In addition, APS is submitting TRM Revision 57. TRM Revision 57 was implemented April 10, 2013 and TS Bases Revision 57 was also implemented on April 10, 2013.
Electronic files of the revised TS Bases and TRM are provided as Enclosure 1. The summary of changes for each document is provided in Enclosure 2.
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.
Sincerely,
(,t)614 (-J
/
A Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/CJS/hsc Enclosure 1: Optical Storage Media (OSM) Electronic Files of PVNGS TS Bases Revision 57 and TRM Revision 57 Enclosure 2: PVNGS Technical Specification Bases Revision 57 and TRM Revision 57 Summary of Changes cc: A.T. Howell III NRC Region IV Regional Administrator (enclosures)
J. K. Rankin NRC NRR Project Manager for PVNGS (enclosures)
M. A. Brown NRC Senior Resident Inspector for PVNGS (w/o enclosures)
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 San Onofre 0 South Texas 0 Wolf Creek IJk4C
ENCLOSURE 2 PVNGS Technical Specification Bases Revision 57 and TRM Revision 57 Summary of Changes I
Summary of Changes Technical Specifications Bases Revision 57 TRM Revision 57 Technical Specification Bases Revision 57 includes the following changes:
- LDCR 10-B012 reflected removal of Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (CIV) RDB UV-407 from TS Bases 3.3.10, Post-Accident Monitoring Instrumentation, as described in the LCO Section, item 8, Containment Isolation Valve Position. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. The Unit 3 valve was removed during the past Unit 3 outage.
" LDCR 12-B008 clarified TS Bases 3.1.7, Regulating Control Element Assembly (CEA)
Insertion Limits, Background Section, that the CEA fully withdrawn position is specified in the COLR. This is an editorial enhancement.
" LDCR 12-B009 removed specific surveillance frequencies stated in various TS Bases which were missed during the implementation of TSTF-425 and License Amendment 188. This is editorial correction.
- LDCR 12-BOll corrected and clarified the description of the emergency diesel generator (EDG) performance requirements during starting under loss of power (LOP),
with or without safety injection actuation plant conditions. The changes clarified that the EDG is to start and close the EDG breaker within a 10 second window.
Technical Requirements Manual (TRM) Revision 57 includes the following changes:
- LDCR 10-R012 removed Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (CIV) RDB UV-407 from the TRM Component List T7.0.300, Containment Isolation Valves. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. The Unit 3 valve was removed during the past Unit 3 outage.
- LDCR 12-RO01 removed overpressure protection valves AFB PSV-0106 and 0107 from containment isolation valves (CIVs) AFB UV-034 and 35 from TRM Component List T7.0.300, ContainmentIsolation Valves. The valves were replaced by a pressure equalizing line from the valve bonnets to the process piping.
" LDCR 12-R005 updated the applicable industry standard edition date for Unit 1 (ASTM E185-79) and Units 2 and 3 (ASTM E185-82) in TRM Appendix TA, Reactor Coolant System Pressure and Temperature Limits Report (PTLR), Section TA6.2, Evaluation of Surveillance Data Credibility.
" LDCR 12-R006 corrected the description of the responsible organizations for the Inservice Inspection (ISI) and Inservice Testing (IST) programs in TRM Section 5.0.500.8, Inservice Inspection and Testing Programs.
2
A
.
Summary of Changes Technical Specifications Bases Revision 57 TRM Revision 57 LDCR 12-R008 deleted the High Pressure Safety Injection (HPSI), Low Pressure Safety Injection (LPSI) and Containment Spray pump miniflow differential pressure test requirements from the TRM (Sections 5.0.500.8.e, 5.0.500.8.f and 5.0.500.8.g). The TRM requirements were redundant to Inservice Testing requirements defined in Technical Specification 5.5.8.
3