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{{#Wiki_filter:ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF UALIFICATIOHS (Continued)
{{#Wiki_filter:ADMINISTRATIVE CONTROLS
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 operator s.6.4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the'irector, 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. 3   UNIT STAFF   UALIFICATIOHS           (Continued)
Senior Reactor Operator             (SRO) license requirement for the Operations Manager shall   be met if either a valid SRO license.
the Operations Manager or the Operations Supervisor holds The holder of the SRO license shall direct the licensed activities of the licensed operator s.
: 6. 4   TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the'irector, 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 all matters related to nuclear safety.
                                                                                      ~~m on COMPOSITION 6.5.1.2    The PRB  shall          be composed  of the following personnel:
Member:                              Engineering Evaluations Manager Member;                              Operations Standards Supervisor Member:                              Mechanical Maintenance Standards Supervisor Member:                              Electrical Maintenance Standards Supervisor Member:                              Operations Managers for Unit 1, Unit 2, Unit 3 Member:                              STA  Supervisor Member:                                IKC Standards  Supervisor Member:                              Radiation Protection and Chemistry Manager Member:                              quality Systems/Engineering Manager P.R~~  Qiw c.
The                                                  shall designate the Chairman and Vice-in writing.            The Chairman and Vice-Chairmen may be from outside the cC'hairmen 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 UEHCY 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 4
040g0~r~3 9003)6 05000528 l~
PDR    ADOCK PDC


===6.5 REVIEW===
4 INSERT The PRB shall be composed of nine members from 'the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.
AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the Plant~~m 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: The P.R~~Qiw c.cC'hairmen in writing.ALTERNATES 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 IKC Standards Supervisor Radiation Protection and Chemistry Manager quality Systems/Engineering Manager shall designate the Chairman and Vice-The Chairman and Vice-Chairmen may be from outside the provided that they meet ANSI Standard 3.1, 1978.6.5.1.3 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 UEHCY 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 4 040g0~r~3 9003)6 l~PDR ADOCK 05000528 PDC 6-7 AMENDMENT NO.39 4
INSERT The PRB shall be composed of nine members from'the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.  


AOMI HI STRATI VE CONTROLS QUORUH'r 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.
AOMI HI STRATIVE CONTROLS QUORUH
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for: w h.b.X.C.4.a..'g.AUTHORITY Review of all proposed changes to Appendix"A" Tcchnical Specifications.
                                                        'r 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.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recoenendations 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~~
RESPONSIBILITIES 6.5.1.6     The PRB shall   be responsible for:
>%~CMw~~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.6.5.1.?The PRB shall: a~b.Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6lr,.
w h.       Review of all proposed changes to Appendix "A" Tcchnical Specifications.
above constitutes an unreviewed safety question.b.Provide written notification within 24 hours to the Vice President-Huclear Production, Plant and NSG of disagreement between the PRB and the Plant, ho ever, the Plan shall have Dirc.eMC RECOROS 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.
b.X.      Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recoenendations to prevent recurrence to the Nuclear Safety Group (NSG).
Copies shall er~4ivo gicp (casecr r-<<chsnC'N P,ca<koc PALO VEROE-UNIT 1 6-8 AMEHOMEHT NO.27 k p l V*
C.4.      Review of REPORTABLE EVENTS.
CONTROLLED BY USE ADMINISTRATIVE CONTROLS.6.5.2 TECHNICAL REVIEW ANO CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure and program required by Specification 6.8 and other procedures'hich affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization.
Review of unit operations to detect potential nuclear safety hazards.
Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepar'ed the proce-dure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.6.5.2.2 Phase I-IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Manager as previously designated by the" Vice President-Nuclear Production.
a..'g. Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President"Nuclear Production~~ >%~
Test results shall be approved by the Direc-tor, Standards and Technical Support or the Engineering Evaluations Manager.6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/organization.
CMw~~
Each such modification shall be reviewed by an individual/group other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification.
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.
Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by thy, lant Manager;or by the Director, Standards and Technical Support as previousl designated by the Vice President-Nuclear Production.
AUTHORITY 6.5.1.?     The PRB   shall:
',a.'~0~C',<)4 a.6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the super-visory staff, previously designated by the to perform such reviews.Each such review shall i elude a determination of whether or not additional, cross-disciplinary, review i necessary.
a ~   Render determinations     in writing with regard to whether or not each item considered under Specification 6.5.1.6lr,. above constitutes an unreviewed safety question.                     b.
If deemed necessary, such review shall be performed by the appropria designated review personnel.
: b. Provide written notification within 24 hours to the Vice President-the PRB and the    Plant, Huclear Production, Plant             and NSG of disagreement between ho ever, the Plan           shall have Dirc.eMC RECOROS 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 er~4ivo gicp       (casecr   r -<<chsnC'N                         P,ca<koc PALO VEROE     - UNIT 1                     6-8                       AMEHOMEHT NO. 27
oi(c~4ow saba 4.~4s a~vvrQA"6.5.2.5 Proposed tests and experiments which affect station nuclear safety and're not addressed in the FSAR or Technical Specifications shall be, reviewed by the A2lwk C>it'Q.ck&C 6.5.2.6 The station security program and'implementing procedures-shall-b~e-viewed.Recommended changes shall be approved by the Director, Site Services d ig 1'i<<d t i P id and to the NSG.P oh'hio~6.5.2.7 The station emergency plan and implementing procedures shall be re-viewed.Recommended changes shall be approved by the Director, Site Services or designate alternate and transmitted to the Vice President-Nuclear Production and to the NSG.Q>6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
PALO VERDE-UNIT 1 6-9 AMEHDMEHT HO.25 A,
M&l AOMIHISTRATIVE CONTROLS ARJLJ C.LJ 0 k UQCri~o c.~~Q IQ.d TECHNICAL REVIEM ANO CONTROL ACTIVITIES (Continued}
6.5.2.9 The Director, Standards and Technical Support shall assure the perfor-mance of a review by a qualified individual/organization of changes to the PRO-CESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment.
systems, and the Pre-planned Alternate Sampling Program.6.5.2.10 Reports documenting each of the activities performed under Specifica" tions 6.5.2.1 through 6.5.2.9 above shall be maintained.
Copies shall be provided to the Vice President-Nuclear Production and the Huclear Safety Group.6.5.3 NUCLEAR SAFETY GROUP (NSG}FUNCTION 6.5.3.1 The NSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of: a.nuclear power plant operations b.nuclear engineering
*~c.chemistry and radiochemistry d.metallurgy e.instrumentation and control f.radiological safety g.mechanical and electrical engineering h.quality assurance practices COMPOSITION 6.5.3.2 The HSG shall consist of a Manager and at least four s aff specialists.
The Manager shall hav'e a Bachelor's Degree in Engineering or the Physical Sciences.He will also have a minimum of 10 years experience in the po~er field with at least 3 of those years in the nuclear field.The HSG Manager will have at least 2 years of supervisor/managerial experience.
Each staff specialist will have at least one of the following requirements:
a.Eight years experience in one of the designated areas in Specifica-tion 6.5.3.1.One of these 8 years will be at Palo Verde Nuc'lear Generating Station.b.Bachelor's Degree in Engineering or a related science and 3 years of professional experience.
CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the HSG Manager to provide expert advice to the HSG.REVIEW 6.5.3.4 The HSG shall review: The safety evaluations program and its implementation for (1}changes to procedures, equipment, systems or facilities within the power block, and (2)tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;PALO VERGE" Ut(IT i 6-10 AtlEhGMEHT ttO.Z5 CONTROLLED BY USER 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===
k p l
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.
V
 
CONTROLLED BY USE ADMINISTRATIVE CONTROLS        .
6.5.2    TECHNICAL REVIEW ANO CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure and program required by Specification 6.8 and other procedures'hich affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepar'ed the proce-dure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.
6.5.2.2    Phase    I - IV tests described in the FSAR that are performed by the plant operations    staff shall be approved by the Director, Standards and Technical            "
Support or the Engineering Evaluations Manager as previously designated by the Vice President-Nuclear Production. Test results shall be approved by the Direc-tor, Standards and Technical Support or the Engineering Evaluations Manager.
6.5.2.3    Proposed modifications to unit nuclear safety-related structures, systems
                          ',a.
and components shall be designed by a qualified individual/organization.            Each such modification shall be reviewed by an individual/group other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by thy, lant Manager; or by the Director, Standards and Technical Support as previousl designated by the Vice President-Nuclear Production.                                      '~ 0              4 a.
                                                                  ~C',  <)
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the                                      super-visory staff, previously designated by the                                              to perform such reviews. Each such review shall i elude a determination of whether or not additional, cross-disciplinary, review i necessary.            If deemed necessary, such review shall be performed by the appropria          designated review personnel.
oi(c~4ow saba 4.~4s a ~vvrQA "6.5.2.5 Proposed tests and experiments which affect station nuclear safety and
're    not addressed in the FSAR or Technical Specifications shall be, reviewed by the A2lwk C>it'Q.ck&C 6.5.2.6    The  station security program and'implementing procedures-shall-b~e-viewed. Recommended    changes shall be approved by the Director, Site Services d  ig        1 i<<d      t  i P id and  to the  NSG.                                                            P oh'hio~
6.5.2.7    The  station  emergency plan and implementing procedures    shall be re-viewed. Recommended  changes shall be approved by the Director,    Site Services or designate alternate      and transmitted to the Vice President-Nuclear Production and to the NSG.Q>
6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
PALO VERDE    -  UNIT 1                      6-9                      AMEHDMEHT HO. 25
 
A, M&l      ARJLJ  C.LJ  0    UQCri k
                                                          ~o c.~~ Q IQ.
d AOMIHISTRATIVE CONTROLS TECHNICAL REVIEM    ANO CONTROL ACTIVITIES (Continued}
6.5.2.9    The  Director, Standards  and Technical Support  shall assure the perfor-mance  of a review by a qualified individual/organization of changes to the PRO-CESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment. systems, and  the Pre-planned Alternate Sampling Program.
6.5.2.10 Reports documenting each of the activities performed under Specifica" tions 6. 5. 2. 1 through 6.5.2.9 above shall be maintained. Copies shall be provided to the Vice President-Nuclear Production and the Huclear Safety Group.
6.5.3 NUCLEAR SAFETY GROUP (NSG}
FUNCTION 6.5.3.1    The NSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of:
: a. nuclear power plant operations
: b. nuclear engineering    *
    ~
: c. chemistry and radiochemistry
: d. metallurgy
: e. instrumentation and control
: f. radiological safety
: g. mechanical and electrical engineering
: h. quality assurance practices COMPOSITION 6.5.3.2 The HSG shall consist of a Manager and at least four s aff specialists.
The Manager shall hav'e a Bachelor's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the po~er field with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisor/managerial experience. Each staff specialist will have at least one of the following requirements:
: a. Eight years experience in one of the designated areas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuc'lear Generating Station.
: b. Bachelor's Degree in Engineering or a related science and 3 years of professional experience.
CONSULTANTS 6.5.3.3 Consultants shall be utilized        as determined by the HSG  Manager  to provide expert advice to the HSG.
REVIEW 6.5.3.4    The  HSG  shall review:
The  safety evaluations program and its implementation for (1} changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERGE    " Ut(IT i                    6-10                      AtlEhGMEHT ttO. Z5
 
CONTROLLED BY USER 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  REVIEW AND AUDIT 6.5.1    PLANT REVIEW BOARD    PRB FUNCTION Oic~d ~c.
6.5.1.1    The Plant Review Board shall function to      advise the Plant AaAagm on all  matters related to nuclear safety, COMPOSITION 6.5.1.2    The PRB  shall  be composed  of the following personnel:
Member:                      Engineering Evaluations Manager Member:                      Operations Standards Supervisor Hember:                      Hechanical Maintenance Standards Supervisor Member:                      Electrical Maintenance Standards Supervisor Member:                      Operations Managers for Unit 1, Unit 2, Unit    3 Member:                      STA Supervisor Member:                      I8C Standards Supervisor Member:                      Radiation Protection and Chemistry Manager Member:                      equality Systems(Engineering Hanager The Z4~Q  ~'C~                          shall designate the Chairman and Vice-Chairmen  in writing. The Chairman and Vice-Chairmen may be from outside the 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                      AHENOHEHT HO. 26
 
~ = ~
      ,~


===6.5 REVIEW===
AND AUDIT 6.5.1 PLANT REVIEW BOARD PRB FUNCTION Oic~d~c.6.5.1.1 The Plant Review Board shall function to advise the Plant AaAagm on all matters related to nuclear safety, COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:
Member: Member: Hember: Member: Member: Member: Member: Member: Member: Z4~Q~'C~The Chairmen in writing.ALTERNATES Engineering Evaluations Manager Operations Standards Supervisor Hechanical 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 Hanager shall designate the Chairman and Vice-The Chairman and Vice-Chairmen may be from outside the provided that they meet ANSI Standard 3.1, 1978.6.5.1.3 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 AHENOHEHT HO.26
~=~,~
INSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.
INSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.
a'A 4 4t l4 C.ONTROLLED BY USE 0 ADMINISTRATIYE CONTROLS 6.5.2 TECHNICAL REYIEM AHD CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure'and program reqdired by Specification 6e8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organizations Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the in-dividual/group which prepared the procedure, or changes thereto.6.5.2.2 Phase I-IY tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Tech-nical Support or the Engineering Evaluations Manager as previously designated by the Vice President-Nuclear Production.
Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Manager.6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed b'y a qualified individual/organization.
Each suc'h modification shall be reviewed by an individual/group-other than the indi-vidual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.
Proposed'odifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Hanager;or by the Director, Standards and Technical Support as previousl designated by the Vice President-, Nuclear Production.
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1,'.6.5.2.2, and 6.5.2.3 shall be members of the super-visory staff, previously designated by the to perform such reviews.Each such review shall nclude a determination of whether or not additional, cross-disciplinary, revie is necessary.
If deemed necessary, such review shall be performed by the appropr'ate designated review personnel.'t~a.c.4 r Ska~cka, o 4m',~A S pjcs r 6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the phew Wtccr c-WC'.5.2.6 The station security program and implementing procedures shall be reviewed.Recommended changes shall be approved by the Di'rector, Site Services or designated alternate and transmitted to the Vice Pre'sident-Nuclear Production and to the NSG.WV 6.5.2.7 The station emergency plan and implementing procedures shall be reviewed.Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Yice President-Nuclear Production and to the NSG.6.5.2.8 The Oirector, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
s PALO VERDE-UHIT 2 AMEHDMEHT HO.14
~I~4 s+II r~J'~'l ,.l>
AOHINISTRATIVE CONTROLS gUOltUM 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: AUTHORITY 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 (HSG).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~~~
~~u Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variabIes placed in bypass since the last PRB aeeting.6.5.1.7 The PRB shall: a.Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6g above constitutes an unreviewed safety question.b Provide written notification within 24 hours to the Vice President-.
Huclear Production, Plant and NSG of disagreement between the PRB and the Plant~~;h ever, the.Plant shall have i1N c i~a.~%ac.RECORDS..6.5.1.8 The PRB shall rmaintain written ainutes of each PRB meeting that, at a ainimum, document the results of all PRB activities performed under the responsi-bility and authority provisions of these Technical Specifications.
Copies shall~~~i~~~'c-a Mwi4~c-~c~Ha 4 Ui~4ar 7 PALO VERDE" UNIT 2 6-8 AHEHOHEHT NO.
, ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHO CONTROL ACTIVITIES (Continued) 6.5.2.9 The Oirector, Standards and Technical Support shall assure the perform-ance of a..review by a qualified individual/organization of changes to the PRO CESS CONTROL PROGRAM, OFFSITE OOSE CALCULATIOH MANUAL, radwaste tr'eatment sys-tems, and the Pre-planned Alternate Sampling Program.6.5.2.10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained.
Copies shall be p<<vided to the Vice President-Nuclear Production and the Nuclear Safety Group.6.5.3 NUCLEAR SAFETY GROUP (NSG)FUNCTION 6.5.3.1 The HSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of: a.nuclear power plant operations b.nuclear engineering c.chemistry and radiochemistry d.metallurgy e.instrumentation and contro1 f.radiological safety g.mechanical and'electrical engineering h.quality assurance practices COMPOSITION 6.5.3.2 The NSG shall consist of a Manager and at least four staff specialists.
The Manager shall have a Bachelor's Oegree in Engineering or the Physical Sciences.He will also have a minimum of 10 years experience in the power tield with at least 3 of those years in the nuclear field.The HSG Manager will have at least 2 years of supervisori'managerial experience.
Each staff specialist will have at least one of the following requirements:
a.Eight years experience in one of the designated ar eas in Specifica-tion 6.5.3.1.One of these 8 years will be at Palo Verde Nuclear Generating Station.b.Bachelor's Oegree in Engineering or a related science and 3 years of professional experience.
CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the HSG Manager to provide expert advice to the HSG.REVIEW 6.5.3.4 a.The HSG shall review: The safety evaluations program and its implementation for (1}changes to procedures equipment, systems or facilities within the power block and (2}tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;P""0 VERDE-UNIT 2 6-10 AMEHOMEHT HO.14 l'I ,s'c, 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===
a
6.4.1 A training program for the unit staff shall be maintained under the di-rection of the'irector, 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.
      'A 4
4t l4
 
C.ONTROLLED BY USE 0
ADMINISTRATIYE CONTROLS 6.5.2 TECHNICAL REYIEM AHD CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure'and program reqdired by Specification 6e8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organizations Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the in-dividual/group which prepared the procedure, or changes thereto.
6.5.2.2 Phase I - IY tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Tech-nical Support or the Engineering Evaluations Manager as previously designated by the Vice President-Nuclear Production. Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Manager.
6.5.2.3    Proposed modifications  to unit nuclear safety-related structures, systems and components shall be designed b'y a qualified individual/organization.                    Each suc'h modification shall be reviewed by an individual/group- other than the indi-vidual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed to nuclear safety-related structures, systems and components shall                  'odifications be approved prior to implementation by the Plant Hanager; or by the Director, Standards and Technical Support as previousl designated by the Vice President-,
Nuclear Production.
6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1,
'.6.5.2.2, and 6.5.2.3 shall be members of the                                              super-visory staff, previously designated by the                                                      to perform such reviews. Each such review shall nclude a determination of whether or not additional, cross-disciplinary, revie is necessary.      If deemed necessary, such review shall be performed by the appropr'ate designated review r Ska~cka, o 4m',~A S pjcs r personnel.'t~a.c.4 6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the phew    Wtccr The station security program and implementing procedures shall be c-WC'.5.2.6 reviewed. Recommended changes shall be approved by the Di'rector, Site Services or designated alternate and transmitted to the Vice Pre'sident-Nuclear Production and to the NSG.                                  WV 6.5.2.7 The station emergency plan and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Yice President-Nuclear Production and to the NSG.
6.5.2.8 The Oirector, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.                                                              s PALO VERDE  - UHIT 2                                              AMEHDMEHT HO.                14
 
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AOHINISTRATIVE CONTROLS gUOltUM 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:
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 (HSG).
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~~~ ~~u Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variabIes placed in bypass since the last PRB aeeting.
AUTHORITY 6.5.1.7    The PRB  shall:
: a. Render determinations    in writing with regard to whether or not        each item considered under    Specification 6.5.1.6g above constitutes        an unreviewed safety question.                        b Provide written notification    within 24    hours  to the Vice President-.
Huclear Production, Plant the  PRB  and the i1N Plant ~~;        h and  NSG  of disagreement between ever, the. Plant            shall have c i~a.~%ac.
RECORDS
..6.5.1.8  The PRB shall rmaintain written ainutes of each PRB meeting that, at a ainimum, document the results of all PRB activities performed under the responsi-bility  and authority provisions of these Technical Specifications.          Copies shall
                  ~~~i~~      ~'c-a Mwi4~c-    ~c~      7 Ha 4  Ui~4ar PALO VERDE  "  UNIT 2                      6-8                          AHEHOHEHT NO.
 
, ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHO CONTROL ACTIVITIES    (Continued) 6.5.2.9 The Oirector, Standards and Technical Support shall assure the perform-ance of a..review by a qualified individual/organization of changes to the PRO CESS CONTROL PROGRAM, OFFSITE OOSE CALCULATIOH MANUAL, radwaste tr'eatment sys-tems, and the Pre-planned Alternate Sampling Program.
6.5.2.10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained. Copies shall be p<<
vided to the Vice President-Nuclear Production and the Nuclear Safety Group.
6.5.3    NUCLEAR SAFETY GROUP (NSG)
FUNCTION 6.5.3.1    The HSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of:
: a. nuclear power plant operations
: b. nuclear engineering
: c. chemistry and radiochemistry
: d. metallurgy
: e. instrumentation and contro1
: f. radiological safety
: g. mechanical and'electrical engineering
: h. quality assurance practices COMPOSITION 6.5.3.2 The NSG shall consist of a Manager and at least four staff specialists.
The Manager shall have a Bachelor's Oegree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power tield with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisori'managerial experience. Each staff specialist will have at least one of the following requirements:
: a. Eight years experience in one of the designated ar eas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuclear Generating Station.
: b. Bachelor's Oegree in Engineering or a related science and 3 years of professional experience.
CONSULTANTS 6.5.3.3    Consultants shall be utilized  as determined by the  HSG  Manager to provide expert advice to the HSG.
REVIEW 6.5. 3.4  The  HSG shall review:
: a. The  safety evaluations program and  its implementation for (1} changes to procedures equipment, systems or facilities within the power block and (2} tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; P""0  VERDE  UNIT 2                    6-10                        AMEHOMEHT HO. 14
 
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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'irector, 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 Q4'cc-cN<
6.5. 1. 1 The Plant Review Board shall function to advise the Plant            M~er on all matters related to nuclear safety.
COMPOSITION V~@.yak 6.5. 1.      The  PRB  shall  be composed  of the following personnel:
Member:                        Engineering Evaluations Manager Member:                        Operations Standards Supervisor Member:    OaveVe              Mechanical Maintenance Standards Supervisor Member:                        Electrical Maintenance Standards Supervisor Member:                        Operations Managers for Unit 1, Unit 2, Unit      3 Member:                        STA Supervisor
            ~
Member:                        I8C Standards Supervisor Member:                        Radiation Protection and Chemistry Manager Member:                        equality Systems/Engineering Manager Plack 'Diccchoc The                                              shall designate the Chairman  and  Vice-Chairmen b
in writing.
p The Chairman and id d  h  th  j'NSi Vice-Chairmen S
may be d
from outside the 3.1,  1 78.
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                                                    AMENDMENT NO. 15
 
~ 1 I XNSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.
 
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        ~
CONTROLLED BY USER Sr ADHINISTRATI VE CONTROLS gUORUM 6.5.                        f
: 1. 5 The quorum o the PRB necessary for the performance of the PRB                                                                              fi respons i b i 1 i ty and authority p r ov i s i ons of these Technical Spec i cati ons shall consist of the Chairman , Yice-Cha i rmen, or hi s designated a 1 te rnate and five member s i ncl udi ng alternates .
RESPONS  I 8 ILI TIES 6.5.1.6    The PRB    shall  be  responsible for:
Review    of all proposed changes to Appendix "A" Technical Specifications.
bL        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}.
c 4,      Review    of REPORTABLE EYENTS.
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"Muciear Productionnor o"0 CHi~ic~o ~o 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.
s ~
    ,ra*
AUTHORITY 6.5.1.7    The PRB    shall:
: a.      Render determinations      in writing with. regard to. whether-or not-each    --  .-
item considered under Specification 6.5.1.6$ . above constitutes an unreviewed safety question.                              b sponsibilityy
: b.      Provide written notification within 24 hours to the Yice President-Nuclear Production, Plant 4am~ and NSG of disagreement between the PRB and the    Plant~~          however the Plant for resolutio f such(disagree nts, shall have re-O'IfC.C- CCjt 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 h
                                  +<~CX~O. AC.O Piqi.gt~k t4utha.aX'                          ~
PALO VERDE      - UNIT 3                          6-8                        NENDHENT NO. 3
 
  ~      4 4 e
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a
  ~ w CONTROLLED BY USEI as
        ~  sf  sr ADHINISTRATIYE CONTROLS 6.5;2 TECHNICAL REVIEM AND CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure 'and program required by Specification 6.6 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the indi-vidual/group which prepared the procedure, or changes thereto.
6.5;2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager as previously designated by the Vice President-Nucl'ear Production. Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager.
6.5.2.3    Proposed modifications to unit nuclear safety-related structures, systems and. components  shall be designed by a qualified individual/organization. Each such modification shall be, reviewed by an individual/group 'other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures., systems and components shall be approved prior to implementation by thePlant Hanager'; or by the Director, Standards and Technical Support as previously designated by the Vice President-Nuclear Production.                                    igcu. AC W>
p y
          .6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the                                super" visory staff, previously designated by the                                        to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, revie is necessary.      If deemed necessary, such review shall be performed by the approp ate designated review personnel.
                                                            ~t~~4~ Sgg 4~g~a 4m~~i~ Supp r      g 6.5.2.5 Proposed tests and experiments which affect station nuc'lear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Wa 4 mrna    Qt,c 6.5.2.6    The station security program and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alter'nate and transmitted to the Vice, President-Nuclear Production and to the NSG.
6.5.2.7 The station emergency plan and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the NSG.
6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned on-site release of radioactive material to the environs including the preparation .
and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
PAlO VERDE  " UNIT 3                    6-9                      AHENDHENT NO.
 
4 ~
          ~ ~
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===6.5 REVIEW===
                                                        ~   <<<<<<Ag&CrC N W W't5 QC4CA,P a .  <<                      ~ ~       l ~
AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)FUNCTION Q4'cc-cN<6.5.1.1 The Plant Review Board shall function to advise the Plant M~er on all matters related to nuclear safety.COMPOSITION 6.5.1.The PRB shall be composed of the following personnel:
                                ~
V~@.yak Member: Engineering Evaluations Manager Member: Operations Standards Supervisor Member: OaveVe Mechanical Maintenance Standards Supervisor Member: Electrical Maintenance Standards Supervisor Member: Operations Managers for Unit 1, Unit 2, Unit 3 Member: STA Supervisor Member: I8C Standards Supervisor Member: Radiation Protection and Chemistry Manager Member: equality Systems/Engineering Manager Plack'Diccchoc The shall designate the Chairman and Vice-Chairmen in writing.The Chairman and Vice-Chairmen may be from outside the b~p id d h th j'NSi S d 3.1, 1 78.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.
O C We OC Wa C~ow Ow
PALO VERDE-UNIT 3 AMENDMENT NO.15
"   ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHD CONTROL ACTIVITIES     (Continued}
~1 I XNSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.
6.5.2.9 The Director, Standards and Technical Support shall assure the perfor-mance of a'review by a qualified individual/organization of changes to the PRO-CESS CONTROL PHOGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-planned Alternate Sampling Program..
.)~.!L+
6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained. Copies shall be pro-vided to the Vice President-Nuclear Production and the Nuclear Safety Group.
~Sr CONTROLLED BY USER ADHINI STRATI VE CONTROLS gUORUM 6.5.1.5 The quorum o f the PRB necessary for the performance of the PRB respons i b i 1 i ty and authority p r ov i s i ons of these Technical Spec i fi cati ons shall consist of the Chairman , Yi ce-Cha i rmen, or hi s designated a 1 te rnate and fi ve member s i ncl udi ng alternates
6.5.3     NUCLEAR SAFETY GROUP   HSG)
.RESPONS I 8 ILI TIES 6.5.1.6 The PRB shall be responsible for: bL Review of all proposed changes to Appendix"A" Technical Specifications.
FUNCTION 6.5.3.1     The HSG shall function to provide independent revie~ and shall be responsible for the audit of designated activities in the areas of:
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}.c 4, Review of REPORTABLE EYENTS.Review of unit operations to detect potential nuclear safety hazards.s~,ra*AUTHORITY Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President"Muciear Productionnor o"0 CHi~ic~o~o 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.6.5.1.7 The PRB shall: a.Render determinations in writing with.regard to.whether-or not-each---.-item considered under Specification 6.5.1.6$.above constitutes an unreviewed safety question.b b.RECORDS Provide written notification within 24 hours to the Yice President-Nuclear Production, Plant 4am~and NSG of disagreement between the PRB and the Plant~~however the Plant shall have re-sponsibilityy for resolutio f such(disagree nts, O'If C.C-CCjt 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.
: a. nuclear power plant operations
Copies shall h+<~CX~O.AC.O Piqi.gt~k t4utha.aX'
: b. nuclear engineering
~PALO VERDE-UNIT 3 6-8 NENDHENT NO.3
: c. chemistry and radiochemistry
~4 4 e 1~c'/I k I~e
: d. metallurgy
~w a as CONTROLLED BY USEI~sf sr ADHINISTRATIYE CONTROLS 6.5;2 TECHNICAL REVIEM AND CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure'and program required by Specification 6.6 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization.
: e. instrumentation and control
Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the indi-vidual/group which prepared the procedure, or changes thereto.6.5;2.2 Phase I-IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager as previously designated by the Vice President-Nucl'ear Production.
: f. radiological safety
Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager.6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and.components shall be designed by a qualified individual/organization.
: g. mechanical and electrical engineering
Each such modification shall be, reviewed by an individual/group
: h. quality assurance practices
'other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification.
, COMPOSITIOH 6-5.3.2 The NSG shall consist of a Manager and at least four staff specialists.
Proposed modifications to nuclear safety-related structures., systems and components shall be approved prior to implementation by thePlant Hanager';or by the Director, Standards and Technical Support as previously designated by the Vice President-Nuclear Production.
The Manager shall have a Bachelor's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power field with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisor/managerial experience. Each staff specialist will have at least one of the following requirements:
igcu.AC p W>y.6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the super" visory staff, previously designated by the to perform such reviews.Each such review shall include a determination of whether or not additional, cross-disciplinary, revie is necessary.
: a. Eight years experience in one of. the designated areas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuclear Generating Station.
If deemed necessary, such review shall be performed by the approp ate designated review personnel.
: b. Bachelor's Degree in Engineering or a related science and .3 years of professional experience.
~t~~4~Sgg 4~g~a 4m~~i~Supp g r 6.5.2.5 Proposed tests and experiments which affect station nuc'lear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Wa 4 mrna Qt,c 6.5.2.6 The station security program and implementing procedures shall be reviewed.Recommended changes shall be approved by the Director, Site Services or designated alter'nate and transmitted to the Vice, President-Nuclear Production and to the NSG.6.5.2.7 The station emergency plan and implementing procedures shall be reviewed.Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the NSG.6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned on-site release of radioactive material to the environs including the preparation
CONSULTANTS
.and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.
: 6. 5.3. 3   Consultants shall be utilized as determined by the       NSG   Manager to provide expert advice to the HSG.
PAlO VERDE" UNIT 3 6-9 AHENDHENT NO.
REVIFM 6.5.3.4     The HSG shall review:
4~~~~g~
: a. The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems   or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE   - UNIT 3                   6-10}}
~a.<<~<<<<<<Ag&CrC N W W't5 QC4CA, P~~l~O C We OC Wa C~ow Ow" ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHD CONTROL ACTIVITIES (Continued}
6.5.2.9 The Director, Standards and Technical Support shall assure the perfor-mance of a'review by a qualified individual/organization of changes to the PRO-CESS CONTROL PHOGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-planned Alternate Sampling Program..6.5.2.10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained.
Copies shall be pro-vided to the Vice President-Nuclear Production and the Nuclear Safety Group.6.5.3 NUCLEAR SAFETY GROUP HSG)FUNCTION 6.5.3.1 The HSG shall function to provide independent revie~and shall be responsible for the audit of designated activities in the areas of: a.nuclear power plant operations b.nuclear engineering c.chemistry and radiochemistry d.metallurgy e.instrumentation and control f.radiological safety g.mechanical and electrical engineering h.quality assurance practices , COMPOSITIOH 6-5.3.2 The NSG shall consist of a Manager and at least four staff specialists.
The Manager shall have a Bachelor's Degree in Engineering or the Physical Sciences.He will also have a minimum of 10 years experience in the power field with at least 3 of those years in the nuclear field.The HSG Manager will have at least 2 years of supervisor/managerial experience.
Each staff specialist will have at least one of the following requirements:
a.Eight years experience in one of.the designated areas in Specifica-tion 6.5.3.1.One of these 8 years will be at Palo Verde Nuclear Generating Station.b.Bachelor's Degree in Engineering or a related science and.3 years of professional experience.
CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the NSG Manager to provide expert advice to the HSG.REVIFM 6.5.3.4 The HSG shall review: a.The safety evaluations program and its implementation for (1)changes to procedures, equipment, systems or facilities within the power block, and (2)tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;PALO VERDE-UNIT 3 6-10}}

Latest revision as of 04:01, 4 February 2020

Proposed Tech Specs Revising Section 6.5.1.2 Re Plant Review Board Composition
ML17305A632
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 03/16/1990
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17305A631 List:
References
NUDOCS 9004060353
Download: ML17305A632 (27)


Text

ADMINISTRATIVE CONTROLS

6. 3 UNIT STAFF UALIFICATIOHS (Continued)

Senior Reactor Operator (SRO) license requirement for the Operations Manager shall be met if either a valid SRO license.

the Operations Manager or the Operations Supervisor holds The holder of the SRO license shall direct the licensed activities of the licensed operator s.

6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the di-rection of the'irector, 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 all matters related to nuclear safety.

~~m on COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:

Member: Engineering Evaluations Manager Member; Operations Standards Supervisor Member: Mechanical Maintenance Standards Supervisor Member: Electrical Maintenance Standards Supervisor Member: Operations Managers for Unit 1, Unit 2, Unit 3 Member: STA Supervisor Member: IKC Standards Supervisor Member: Radiation Protection and Chemistry Manager Member: quality Systems/Engineering Manager P.R~~ Qiw c.

The shall designate the Chairman and Vice-in writing. The Chairman and Vice-Chairmen may be from outside the cC'hairmen 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 UEHCY 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 4

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4 INSERT The PRB shall be composed of nine members from 'the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.

AOMI HI STRATIVE CONTROLS QUORUH

'r 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:

w h. Review of all proposed changes to Appendix "A" Tcchnical Specifications.

b.X. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recoenendations to prevent recurrence to the Nuclear Safety Group (NSG).

C.4. Review of REPORTABLE EVENTS.

Review of unit operations to detect potential nuclear safety hazards.

a..'g. Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President"Nuclear Production~~ >%~

CMw~~

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.? The PRB shall:

a ~ Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6lr,. above constitutes an unreviewed safety question. b.

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-the PRB and the Plant, Huclear Production, Plant and NSG of disagreement between ho ever, the Plan shall have Dirc.eMC RECOROS 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 er~4ivo gicp (casecr r -<<chsnC'N P,ca<koc PALO VEROE - UNIT 1 6-8 AMEHOMEHT NO. 27

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CONTROLLED BY USE ADMINISTRATIVE CONTROLS .

6.5.2 TECHNICAL REVIEW ANO CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure and program required by Specification 6.8 and other procedures'hich affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepar'ed the proce-dure, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Technical "

Support or the Engineering Evaluations Manager as previously designated by the Vice President-Nuclear Production. Test results shall be approved by the Direc-tor, Standards and Technical Support or the Engineering Evaluations Manager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems

',a.

and components shall be designed by a qualified individual/organization. Each such modification shall be reviewed by an individual/group other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by thy, lant Manager; or by the Director, Standards and Technical Support as previousl designated by the Vice President-Nuclear Production. '~ 0 4 a.

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6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the super-visory staff, previously designated by the to perform such reviews. Each such review shall i elude a determination of whether or not additional, cross-disciplinary, review i necessary. If deemed necessary, such review shall be performed by the appropria designated review personnel.

oi(c~4ow saba 4.~4s a ~vvrQA "6.5.2.5 Proposed tests and experiments which affect station nuclear safety and

're not addressed in the FSAR or Technical Specifications shall be, reviewed by the A2lwk C>it'Q.ck&C 6.5.2.6 The station security program and'implementing procedures-shall-b~e-viewed. Recommended changes shall be approved by the Director, Site Services d ig 1 i<<d t i P id and to the NSG. P oh'hio~

6.5.2.7 The station emergency plan and implementing procedures shall be re-viewed. Recommended changes shall be approved by the Director, Site Services or designate alternate and transmitted to the Vice President-Nuclear Production and to the NSG.Q>

6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.

PALO VERDE - UNIT 1 6-9 AMEHDMEHT HO. 25

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d AOMIHISTRATIVE CONTROLS TECHNICAL REVIEM ANO CONTROL ACTIVITIES (Continued}

6.5.2.9 The Director, Standards and Technical Support shall assure the perfor-mance of a review by a qualified individual/organization of changes to the PRO-CESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment. systems, and the Pre-planned Alternate Sampling Program.

6.5.2.10 Reports documenting each of the activities performed under Specifica" tions 6. 5. 2. 1 through 6.5.2.9 above shall be maintained. Copies shall be provided to the Vice President-Nuclear Production and the Huclear Safety Group.

6.5.3 NUCLEAR SAFETY GROUP (NSG}

FUNCTION 6.5.3.1 The NSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering *

~

c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION 6.5.3.2 The HSG shall consist of a Manager and at least four s aff specialists.

The Manager shall hav'e a Bachelor's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the po~er field with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisor/managerial experience. Each staff specialist will have at least one of the following requirements:

a. Eight years experience in one of the designated areas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuc'lear Generating Station.
b. Bachelor's Degree in Engineering or a related science and 3 years of professional experience.

CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the HSG Manager to provide expert advice to the HSG.

REVIEW 6.5.3.4 The HSG shall review:

The safety evaluations program and its implementation for (1} changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERGE " Ut(IT i 6-10 AtlEhGMEHT ttO. Z5

CONTROLLED BY USER 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 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD PRB FUNCTION Oic~d ~c.

6.5.1.1 The Plant Review Board shall function to advise the Plant AaAagm on all matters related to nuclear safety, COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:

Member: Engineering Evaluations Manager Member: Operations Standards Supervisor Hember: Hechanical Maintenance Standards Supervisor Member: Electrical Maintenance Standards Supervisor Member: Operations Managers for Unit 1, Unit 2, Unit 3 Member: STA Supervisor Member: I8C Standards Supervisor Member: Radiation Protection and Chemistry Manager Member: equality Systems(Engineering Hanager The Z4~Q ~'C~ shall designate the Chairman and Vice-Chairmen in writing. The Chairman and Vice-Chairmen may be from outside the 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 AHENOHEHT HO. 26

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INSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.

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C.ONTROLLED BY USE 0

ADMINISTRATIYE CONTROLS 6.5.2 TECHNICAL REYIEM AHD CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure'and program reqdired by Specification 6e8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organizations Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the in-dividual/group which prepared the procedure, or changes thereto.

6.5.2.2 Phase I - IY tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Tech-nical Support or the Engineering Evaluations Manager as previously designated by the Vice President-Nuclear Production. Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Manager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed b'y a qualified individual/organization. Each suc'h modification shall be reviewed by an individual/group- other than the indi-vidual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification. Proposed to nuclear safety-related structures, systems and components shall 'odifications be approved prior to implementation by the Plant Hanager; or by the Director, Standards and Technical Support as previousl designated by the Vice President-,

Nuclear Production.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1,

'.6.5.2.2, and 6.5.2.3 shall be members of the super-visory staff, previously designated by the to perform such reviews. Each such review shall nclude a determination of whether or not additional, cross-disciplinary, revie is necessary. If deemed necessary, such review shall be performed by the appropr'ate designated review r Ska~cka, o 4m',~A S pjcs r personnel.'t~a.c.4 6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the phew Wtccr The station security program and implementing procedures shall be c-WC'.5.2.6 reviewed. Recommended changes shall be approved by the Di'rector, Site Services or designated alternate and transmitted to the Vice Pre'sident-Nuclear Production and to the NSG. WV 6.5.2.7 The station emergency plan and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Yice President-Nuclear Production and to the NSG.

6.5.2.8 The Oirector, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence. s PALO VERDE - UHIT 2 AMEHDMEHT HO. 14

s+ ~ I ~4 II r ~ J'

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AOHINISTRATIVE CONTROLS gUOltUM 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:

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 (HSG).

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~~~ ~~u Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variabIes placed in bypass since the last PRB aeeting.

AUTHORITY 6.5.1.7 The PRB shall:

a. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6g above constitutes an unreviewed safety question. b Provide written notification within 24 hours to the Vice President-.

Huclear Production, Plant the PRB and the i1N Plant ~~; h and NSG of disagreement between ever, the. Plant shall have c i~a.~%ac.

RECORDS

..6.5.1.8 The PRB shall rmaintain written ainutes of each PRB meeting that, at a ainimum, document the results of all PRB activities performed under the responsi-bility and authority provisions of these Technical Specifications. Copies shall

~~~i~~ ~'c-a Mwi4~c- ~c~ 7 Ha 4 Ui~4ar PALO VERDE " UNIT 2 6-8 AHEHOHEHT NO.

, ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHO CONTROL ACTIVITIES (Continued) 6.5.2.9 The Oirector, Standards and Technical Support shall assure the perform-ance of a..review by a qualified individual/organization of changes to the PRO CESS CONTROL PROGRAM, OFFSITE OOSE CALCULATIOH MANUAL, radwaste tr'eatment sys-tems, and the Pre-planned Alternate Sampling Program.

6.5.2.10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained. Copies shall be p<<

vided to the Vice President-Nuclear Production and the Nuclear Safety Group.

6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION 6.5.3.1 The HSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and contro1
f. radiological safety
g. mechanical and'electrical engineering
h. quality assurance practices COMPOSITION 6.5.3.2 The NSG shall consist of a Manager and at least four staff specialists.

The Manager shall have a Bachelor's Oegree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power tield with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisori'managerial experience. Each staff specialist will have at least one of the following requirements:

a. Eight years experience in one of the designated ar eas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuclear Generating Station.
b. Bachelor's Oegree in Engineering or a related science and 3 years of professional experience.

CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the HSG Manager to provide expert advice to the HSG.

REVIEW 6.5. 3.4 The HSG shall review:

a. The safety evaluations program and its implementation for (1} changes to procedures equipment, systems or facilities within the power block and (2} tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; P""0 VERDE UNIT 2 6-10 AMEHOMEHT HO. 14

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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'irector, 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 Q4'cc-cN<

6.5. 1. 1 The Plant Review Board shall function to advise the Plant M~er on all matters related to nuclear safety.

COMPOSITION V~@.yak 6.5. 1. The PRB shall be composed of the following personnel:

Member: Engineering Evaluations Manager Member: Operations Standards Supervisor Member: OaveVe Mechanical Maintenance Standards Supervisor Member: Electrical Maintenance Standards Supervisor Member: Operations Managers for Unit 1, Unit 2, Unit 3 Member: STA Supervisor

~

Member: I8C Standards Supervisor Member: Radiation Protection and Chemistry Manager Member: equality Systems/Engineering Manager Plack 'Diccchoc The shall designate the Chairman and Vice-Chairmen b

in writing.

p The Chairman and id d h th j'NSi Vice-Chairmen S

may be d

from outside the 3.1, 1 78.

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 AMENDMENT NO. 15

~ 1 I XNSERT The PRB shall be composed of nine members from the Palo Verde management staff These positions will be designated by the Plant Director in Administrative Procedures.

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CONTROLLED BY USER Sr ADHINISTRATI VE CONTROLS gUORUM 6.5. f

1. 5 The quorum o the PRB necessary for the performance of the PRB fi respons i b i 1 i ty and authority p r ov i s i ons of these Technical Spec i cati ons shall consist of the Chairman , Yice-Cha i rmen, or hi s designated a 1 te rnate and five member s i ncl udi ng alternates .

RESPONS I 8 ILI TIES 6.5.1.6 The PRB shall be responsible for:

Review of all proposed changes to Appendix "A" Technical Specifications.

bL 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}.

c 4, Review of REPORTABLE EYENTS.

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"Muciear Productionnor o"0 CHi~ic~o ~o 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.

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AUTHORITY 6.5.1.7 The PRB shall:

a. Render determinations in writing with. regard to. whether-or not-each -- .-

item considered under Specification 6.5.1.6$ . above constitutes an unreviewed safety question. b sponsibilityy

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 Yice President-Nuclear Production, Plant 4am~ and NSG of disagreement between the PRB and the Plant~~ however the Plant for resolutio f such(disagree nts, shall have re-O'IfC.C- CCjt 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 h

+<~CX~O. AC.O Piqi.gt~k t4utha.aX' ~

PALO VERDE - UNIT 3 6-8 NENDHENT NO. 3

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~ sf sr ADHINISTRATIYE CONTROLS 6.5;2 TECHNICAL REVIEM AND CONTROL ACTIVITIES 6.5.2.1 The Director, Standards and Technical Support shall assure that each procedure 'and program required by Specification 6.6 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified indivi-dual/organization. Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group which prepared the proce-dure, or changes thereto, but who may be from the same organization as the indi-vidual/group which prepared the procedure, or changes thereto.

6.5;2.2 Phase I - IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager as previously designated by the Vice President-Nucl'ear Production. Test results shall be approved by the Director, Standards and Technical Support or the Engineering Evaluations Hanager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and. components shall be designed by a qualified individual/organization. Each such modification shall be, reviewed by an individual/group 'other than the indi-vidual/group which designed the modification, but who may be from the same or-ganization as the individual/group which designed the modification. Proposed modifications to nuclear safety-related structures., systems and components shall be approved prior to implementation by thePlant Hanager'; or by the Director, Standards and Technical Support as previously designated by the Vice President-Nuclear Production. igcu. AC W>

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.6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the super" visory staff, previously designated by the to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, revie is necessary. If deemed necessary, such review shall be performed by the approp ate designated review personnel.

~t~~4~ Sgg 4~g~a 4m~~i~ Supp r g 6.5.2.5 Proposed tests and experiments which affect station nuc'lear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Wa 4 mrna Qt,c 6.5.2.6 The station security program and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alter'nate and transmitted to the Vice, President-Nuclear Production and to the NSG.

6.5.2.7 The station emergency plan and implementing procedures shall be reviewed. Recommended changes shall be approved by the Director, Site Services or designated alternate and transmitted to the Vice President-Nuclear Production and to the NSG.

6.5.2.8 The Director, Standards and Technical Support shall assure the perform-ance of a review by a qualified individual/organization of every unplanned on-site release of radioactive material to the environs including the preparation .

and forwarding of reports covering the evaluation, recommendations and disposi-tion of the corrective action to prevent recurrence.

PAlO VERDE " UNIT 3 6-9 AHENDHENT NO.

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" ADMINISTRATIVE CONTROLS TECHNICAL REVIEM AHD CONTROL ACTIVITIES (Continued}

6.5.2.9 The Director, Standards and Technical Support shall assure the perfor-mance of a'review by a qualified individual/organization of changes to the PRO-CESS CONTROL PHOGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-planned Alternate Sampling Program..

6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2.1 through 6.5.2.9 above shall be maintained. Copies shall be pro-vided to the Vice President-Nuclear Production and the Nuclear Safety Group.

6.5.3 NUCLEAR SAFETY GROUP HSG)

FUNCTION 6.5.3.1 The HSG shall function to provide independent revie~ and shall be responsible for the audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices

, COMPOSITIOH 6-5.3.2 The NSG shall consist of a Manager and at least four staff specialists.

The Manager shall have a Bachelor's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power field with at least 3 of those years in the nuclear field. The HSG Manager will have at least 2 years of supervisor/managerial experience. Each staff specialist will have at least one of the following requirements:

a. Eight years experience in one of. the designated areas in Specifica-tion 6.5.3.1. One of these 8 years will be at Palo Verde Nuclear Generating Station.
b. Bachelor's Degree in Engineering or a related science and .3 years of professional experience.

CONSULTANTS

6. 5.3. 3 Consultants shall be utilized as determined by the NSG Manager to provide expert advice to the HSG.

REVIFM 6.5.3.4 The HSG shall review:

a. The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 3 6-10