ML17304A686
| ML17304A686 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/24/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17304A687 | List: |
| References | |
| NUDOCS 8811030223 | |
| Download: ML17304A686 (30) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC'ERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated September 6, 1988, 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 Mater 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; 2.
B.
The facility will operate in conformity with the application, the provisions of the 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 publ'ic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by a change 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:
8811030223 881024 PDR ADOCK 05000528 P
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
39, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specif ications George W
Knigh on, rector project irectorat Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:
October 24, 1988
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
39 TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with th'e enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 6-6 6-7 INSERT 6-6 6-7 The following corresponding overleaf pages are also provided:
6-5 6-8
0 l
TABLE 6.2-1 MINIMUM SHIFT GREIGE COMPOSITION POSITION NUMBER OF INDIVIDUALS RE/VIREO TO FILL POSITION MODE 1, 2, 3, OR 4 MODE 5 OR 6 SS SRO RO AO STA 1
1 2
2 None 1I None SS
- Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO
- Individual with a Reactor Operators License AO
- Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided iasediate action is taken to resotre the Shift Crew Composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room coaeand function.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.
PALO VERDE - UNIT 1 6-5 AMENDMENT NO.
27
ADMINISTRATIVE CONTROLS
- 6. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his field.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of 'plant activities to provide independent verification* that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised-procedures, equipment modifications, maintenance activities, operations activities or other meaas of improving plant safety to the Director, Nuclear Safety and Licensing, Plant Manager, and the Manager, Nuclear Safety Group (NSG)..
RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-
- tained, and forwarded each calendar month to the Director, Nuclear Safety and Licensing.
C 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating character-istics, including transients and accidents.
An additional exception is that the "Not responsible for sign-off function.
PALO VERDE - UNIT 1 6"6 AMENDMENT NO.
39
ADMINISTRATIVE CONTROLS
- 6. 3 UNIT.STAFF UALIFICATIONS (Continued)
Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.
The holder of the SRO license shall direct the licensed activities of the licensed operators.
6.4 TRAINING 6.4. 1 A training program for the unit staff shall be maintained under the di-rection of the Director, Site Services or his designee and shall meet or exceed the requirements and recommendations of Section 5.0 of ANS 3.1-1978 and Appen-dix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A
and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD PRB FUNCTION 6.5.1. 1 The Plant Review Board shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Engineering Evaluations Manager Operations Standards Supervisor Mechanical Maintenance Standards Supervisor Electrical Maintenance Standards Supervisor Operations Managers for Unit 1, Unit 2, Unit 3 STA Supervisor I8C Standards Supervisor Radiation Protection and Chemistry Manager equality Systems/Engineering Manager The Vice President-Nuclear Production shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard
- 3. 1, 1978.
ALTERNATES 6.5.1. 3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;
- however, no more than"two alternates shall participate as voting members in PRB activities at any one time.
MEETING FRE UENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE - UNIT 1 6-7 AMENDMENT NO. 39
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB respon-sibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:
aO b.
C.
d.
e.
AUTHORITY Review of all administrative control procedures and changes.
Review of all proposed changes to Appendix "A" Technical Specifications.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recoaeendations to prevent recurrence to the Nuclear Safety Group (NSG).
Review of REPORTABLE EVENTS.
Review of unit operations to detect potential nuclear safety hazards.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production.
Review and documentation of )udgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PRB meeting.
6.5.1.7 The PRB shall:
aO b.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6c.
above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Nuclear Production, Plant Hanager and HSG of disagreement between the PRB and the Plant Hanager; however, the Plant Hanager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.
.~RE lRDS 6.5.1.8 The PRB shall maintain written minutes of each PRB Neeting that, at a minimum, document the results of all PRB activities per foried under the responsi-bility and authority provisions of these Technical Specifications.
Copies shall be provided to the Plant Manager, Vice President-Nuclear Production and NSG.
PALO VERDE - UNIT 1 6-8 AMENDMENT NO. 27
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t 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.
26 License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated September 6, 1988, 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 the 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change 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:
fl
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
26, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of amendment and the effective date of the-new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
October 24, 1988 George Knighton irector Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
26 TO 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 area of change.
REMOVE 6-6 6-7 INSERT 6-6
. 6-7 The following corresponding overleaf pages are also provided:
6-5 6-8
0 E
TABLE 6.2-1 MINIHUH SHIFT CREW COHPOSITION POSITION NUHBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE1,2,3,0R4 MODE 5 OR 6 SS SRO RO AO STA 1
1 2
2 1
1 None 1
1 None
~
SS - Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO - Individual with a Reactor Operators License AO - Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or a>sent.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room command function.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room coamand function.
PALO VERDE - UNIT 2 6-5
0 ADMINISTRATIVE CONTROLS
- 6. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his fiel d.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to. provide independent verification" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY
- 6. 2. 3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means. of improving plant safety to the Director, Nuclear Safety and Licensing, Plant Manager, and the Manager, Nuclear Safety Group (NSG).
RECORDS
- 6. 2. 3. 5 Records of activities performed by the ISEG shall be prepared, main-
- tained, and forwarded each calendar month to the Director, Nuclear Safety and Licensing.
- 6. 2. 4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.
6 ~ 3 UNIT STAFF UALIFICATIONS 6.3.1-Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating character-istics, including transients and accidents.
An additional exception is that the
- Not responsible f'r sign-off function.
PALO VERDE - UNIT 2 6-6 AMENDMENT NO.
26
ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF UALIFICATIONS (Continued)
Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.
The holder of the SRO license shall direct the licensed activities of the licensed operators.
- 6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the Director, Site Services or his designee and shall meet or exceed the requirements and recommendations of Section 5.0 of ANS 3. 1-1978 and Appen-dix A of 10 CFR Part 55 and the supplemental requirements specified in Sec-tions A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
- 6. 5 REVIEM AND AUDIT
- 6. 5.1 PLANT REVIEW BOARD PRB FUNCTION
'6.5. l. 1 The Plant Review Board shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5. 1.2 The PRB shall be composed of the following personnel:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Engineering Evaluations Manager Operations Standards Supervisor Mechanical Maintenance Standards Supervisor Electrical Maintenance Standards Supervisor Operations Managers f'r Unit 1, Unit 2, Unit 3 STA Supervisor I8C Standards Supervisor Radiation Protection and Chemistry Manager guality Systems/Engineering Manager The Vice President-Nuclear Production shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard 3.1, 1978.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FRE UENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE - UNIT 2 6-7 AMENDMENT NO. 26
ADMINISTRATIVE CONTROLS QUDRUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:
a.
b.
C.
Review of all administrative control procedures and changes.
Review of all proposed changes to Appendix "A" Technical Specifications.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).
d.
Review of REPORTABLE EVENTS.
e.
Review of unit operations to detect potential nuclear safety hazards.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production.
Review and documentation of )udgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PRB meeting.
AUTHORITY 6.5.1.7 The PRB shall:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6c.
above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Nuclear Production, Plant Nanager and NSG of disagreement between the PRB and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.
RECURDS 6.5.1.8 The PRB sha11 aaintain vnitten ainotes of each PRB seating that, at a ninimum, document the results of all PRB activities performed under the responsi-.
bility and authority provisions of these Technical Specifications.
Copies shall be provided to the Plant Manager, Vice President-Nuclear Production, and NSG.
PALO VERDE - UNIT 2 6-8 AMENDMENT NO.
14
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
15 License No. NPF-74 1.
The Nuclear Regu'Iatory Commission (the Commission) has found that:
A.
The application for,amendment, dated September 6, 1988, 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 Hater 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 the 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.
E.
The issuance of this amendment wi 11 not be inimical to the common defense and security or to the health and safety of the public; and 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.
I 2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:
I
2 (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 into 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.
The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
'l FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications George Knighton Project Directora e
Division of Reactor IV, V and Special irector V
Projects - III, projects Date of Issuance:
October 24, 1988
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
15 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.
STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 6-6 6-7 INSERT 6-6 6-7 The following corresponding overleaf pages are also provided:
6-5
'-8
I I
I
TABLE 6.2-1 MINIMUM SHIFT CREM COMPOSITION POSITION SS SRO RO AO STA NUMBER OF INDIVIDUALS RE(UIRED TO FILL POSITION MODE1, 2, 3, OR4 MODE 5 OR 6 1
None 1
1 None SS
- Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO
- Individual with a Reactor Operators License AO - Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be
~manned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room command function.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.
PAI0 VERDE - UNIT 3 6-5
ADMINISTRATIVE CONTROLS 6.2. 3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his
-. fleld. ---
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification* that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.
AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities,,operations activities or other means of improving plant safety to the Director, Nuclear Safety and Licensing, Plant Manager, and the Manager, Nuclear Safety Group (NSG).
RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-
- tained, and forwarded each calendar month to the Director, Nuclear Safety and Licensing.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3. 1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3.1-1978 and Regulatory Guide 1.8, September
- 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September
- 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating character-istics, including transients and accidents.
An additional exception is that the "Not responsible"for sign-off function.
PALO VERDE - UNIT 3 AMENDMENT NO.
15
ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF UALIFICATIONS (Continued)
Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.
The holder of the SRO license shall direct the licensed activities of the licensed operators.
- 6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the Director, Site Services or his designee and shall meet or exceed the requirements and recommendations of Section 5.0 of ANS 3. 1-1978 and Appen-dix A. of 10 CFR Part 55 and the supplemental requirements specified in Sections A
and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT
- 6. 5. 1
. PLANT REVIEW BOARD PRB FUNCTION 6.5. 1.,1 The Plant Review Board shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Engineering Evaluations Manager Operations Standards Supervisor Mechanical Maintenance Standards Supervisor Electrical Maintenance Standards Supervisor Operations Managers for Unit 1, Unit 2, Unit 3 STA Supervisor I8C Standards Supervisor Radiation Protection and Chemistry Manager equality Systems/Engineering Manager The Vice President-Nuclear Production shall designate the Chairman and Vice-Chairmen in writing.
The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard
- 3. 1, 1978.
ALTERNATES 6.5. 1.3 All alternate members shall be appointed in'writing by the PRB Chairman.
to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FRE UENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.
PALO VERDE - UNIT 3 6-7 AMENDMENT NO. 15
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5. 1.6 The PRB shall be responsible for:
aO Review of all administrative control procedures and changes.
b.
Review of all proposed changes to Appendix "A" Technical Specifications.
C.
d.
e.
g.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).
Review of REPORTABLE EVENTS.
Review of unit operations to detect potential nuclear safety hazards.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production.
Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PRB meeting.
AUTHORITY 6.5. 1.7 The PRB shall:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6c.
above constitutes an unreviewed safety question.
b.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Nuclear Production, Plant Manager and NSG of disagreement between the PRB and the Plant Manager; however, the Plant Manager shall have re-sponsibility for resolution of such disagreements pursuant to Specifi-cation 6.1.1 above.
RECORDS 6.5.1.8 The PRB shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsi-bility and authority provisions of these Technical Specifications.
Copies shall be provided to the Plant Manager, Vice President-Nuclear Production and NSG.
PALO VERDE - UNIT 3 6-8