ML17304B361

Proposed Tech Specs Re Administrative Controls

ML17304B361
Person / Time
Site:	Palo Verde
Issue date:	07/26/1989
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17304B360	List: ML17304B361
References
NUDOCS 8908020123
Download: ML17304B361 (8)

Text

5) ~ CONTROLLED BY USER

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AOMINISTRATIVE 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 REVIEM AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

FUNCTION 5.5.1.1 Th Rl 1 '5 5 hf1 Voce O'cL<~g~u.c

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all matters related to nuclear safety.

COMPOSITION 6.5. 1.2 The PRB shall be composed of the following personnel:

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K Member: Radiation Protection* and Chemistry Manager Hember: n ac<T, eh~5'+ Manu,ta.mc CL The Ch1 PL@.~(

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meet@ANSI 5 f Standard 3. 1, 1978.

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NOL pQ OO 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman o lA to serve on a temporary basis; however, no more than two alternates shall F00 participate as voting members in PRB activities at any one time.

HV wO MEETING FRE UENCY 8(0 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.

0)LL, PALO VERDE - UNIT 1 AMENDMENT NO. 39

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CONTROLLED BY USED 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:

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 PR.~ %4m~~

Review and documentation of judgment concerning prolonged operation in bypass, channel trip, andlor 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. 1.6g. 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 Manager however, the Plant+aaager- hall have responsibility for resolution of such disagreements.

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'.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+aaag~ Vice President"Nuclear Production and HSG.

D;~~Roc PALO VERDE - UNIT 1 6-8 AMEHQMFHT HO. 27

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CONTROLLED BV USE 0

. ADMINISTRATIVE CONTROLS 6.5.2 TECHNICAL REVIEM AND CONTROL ACTIVITIES -l 6.5.2;1 The Director, Standards and Technical Support shall assure that each l 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 prepared .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 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 individ'ual/group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant or by the Director, Standards and'echnical Support as previously designate by the Vice President-Nuclear Production. z) t~4~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 station nuclear production ~pase-

~isaay-staff, previously designated by the to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

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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

'bl~c~d elks.

P~Q i Q 6.5.2.6 The station security program and'implementing procedures-shall bg re-viewed.

and ig to the HSG.

1<<d<<i<<d Recommended changes shall be approved by the Director, Site Services h fi P Pro W~4i~~

6.5.2.? The station emergency plan and implementing procedures shall be re-viewed. Recommended changes shall be approved by the Director, Site Services or designate lternate and transmitted to the Vice President-Nuclear Production and to the HSG. j r

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 NO. 25

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~OXTROLLFD BV USeR jar 'wp a.ho~ ~g ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued}

6.5.2.9 The Directors 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 CALCULATIOH 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 Nuclear 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

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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 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.

REVIEM 6.5.3m 4 The.HSG shall review:

a. ihe 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 1 6-10 AHENOHENT NO. 25

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