ML17291A844

Proposed Tech Specs Section 6.0, Administrative Controls.

ML17291A844
Person / Time
Site:	Columbia
Issue date:	06/06/1995
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A843	List: ML17291A842 ML17291A844
References
NUDOCS 9506140373
Download: ML17291A844 (18)

Text

REQUEST FOR AMENDMENTTO TECHNICAL SPECIFICATIONS SECTION 6.0 ADMINISTRATIVECONTROLS Attachment 3 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES INDICATED 950hi40373 950606 PDR ADOCK 05000397 P PDR

REQUEST FOR AMENDMENTTO TECHNICAL SPECIFICATIONS SECTION 6'.0 ADMINISTRATIVECONTROLS Attachment 3 INSERT A The POC shall be composed of individuals from each of the following functional areas:

Operations Administration and Records Management Maintenance Radiation Protection Engineering Technical Services Quality Chemistry Planning/Scheduling/Outage The Plant General Manager shall appoint, in writing, the POC Chairman, Vice Chairman, and individual members from the designated functional areas.

CONTROLLED COPY

6. 0 ADMINISTRATIVE CONTROLS

6. ] RESPONSIBILITY

~s.'r 6.1. 1 The Plant~Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Hanager (or during his absence from the control room, a designated individual) shall be responsible for the control room command func-tion. A management directive to this effect, signed by the Assistant-Managing 4irecaor-for Operations shall be reissued to all station personnel on an annual basisMil,<< Pres,g~g

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a a Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions. These requirements are documented in the WNP-2 FSAR and updated in accordance with 10 CFR

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50.71.

b. The fscepro(.

Plant Nanager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

C. Tt responsibility for r9-&'op V lCf - PgeSi La4q 4u f.(u W overall i 1 11 1 plant nuclear safety and shall take any p

measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

e. The organization responsible for the overaTl quality assurance functions shall report to the 4sHa

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'utcr Operations.

0 Is'-C gCg,l y 4llClMP 6.2.2 UNIT STAFF Each on duty shift shall be composed of at least the minimum shift crew composition shnwn in Table 6.2.2-1; WASHINGTON NUCLEAR - UNIT 2 6-1 Amendment No. +4 126

CONTROLI.ED COPY AI3MINISTRATIYE CONTROLS UNIT STAFF (continued)

4. Except during extended shutdown periods, the use of overtime should ba considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the

~J ~plant manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly b the Plant Manager or his designee to assure that excessive hours have no been assigned. Routine deviation from the above guidelines is not authorized.

f. The Shift Managers and Control Room Supervisors shall hold a senior reactor operator license. In addition, the Operations Manager 'or the Assistant Operations Manager'shall also hold a senior reactor operator license. The Reactor Operators shall hold either a senior reactor operator license or a reactor operator license.

WASHINGTON NUCLEAR - UNIT 2 6-3 Amendment No. 87, 101

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ADMINISTRATIVE CON S 6 RT 6.4 TRAINING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained to meet or exceed the requirements and recommendations of Sec-tion 5.5 of ANSI/ANS N18.1-1971 and AppenNx-A-o$ 10 CFR Part 55 and the sup-plemental requirements specified in Sections A and C of Enclosure 1 of the Narch 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 OPERATIONS COHNITT (POC)

FUNCTION'.5.1.

1 The POC shall function to advise the Plant Nanager on all matters related to nuclear safety. Lg <ncaa. [

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6.5.1. 2 -The-PQG-shaQ be-composed-of the.:

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b S tv-i-ces-N-v-t-s4on-Nanagm g a-'i-nte nance-Nm-s-ion-Nanager-dmi-@Man-and-Reoo&s-Nanagement-Nanager-uaVi4y-Assessments-viwi-on-Nanager II -n~eer-'N g-Serv-i-Ges-D~Aen-Nanagev ALTERNATES 6.5.ib3 All alternate members shall be appointed in writing by the POC Chairman or Vice Chairman to serve on a temporary basis.

MEETING FRE UENCY 1.4 The Plant Operations Committee shall meet at least once per calendar month and as convened by the POC Chairman or his designated alternate.

QUORUH 6.5. 1.5 The quorum of the POC necessary for the performance of the POC responsibility and authority provisions of these Technical Specifications sha11 consist of the Chairman or Vice Chairman and four members including alternates. No more than two alternates shall make up the quorum.

WASHINGTON NUCLEAR UNIT 2 6-8 Amendment No. 49, 126

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.ADMINISTRATIVE CONTRO d

~IIE I T E 6.5.1.6 The POC shall be responsible for:

Review of (I) all proposed procedures required by Specification 6.8 and changes thereto, (2) all proposed programs required by Specifica-tion 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; <s- -(

b. Review of all proposed tests and experiments that affect nuclear safety;

c. Review of all proposed changes to the Appendix A Technical Specifications;

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to pr event recurrence, to the Assi~nt-Managkag g~ge~+pdwtcarNeeator-for Operations and to the Corporate Nuclear Safety Review Board;

f. Review of all REPORTABLE EVENTS;

g. Review of unit operations to-detect potential hazards to nuclear safety;

h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Corporate Nuclear Safety Review Board;

i. Review of the Security Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board; J. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board;

k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, I*f Eh~~

recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the 4saistantAcegcesichP~

Review Board; and Ed I "d I I E I I T

1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

AUTHORITY 6.5.1.7 The POC shall:

a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a. through d. prior to their implementation.

MASHINGTON NUCLEAR - UNIT 2 Amendment No. 6

P ADNINISTRATIVE CONTROL AUTHORITY (Continued)

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6a. through e. constitutes an unreviewed safety question as defined in 10 CFR 50.59.

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c. 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 4s&~~anagmg ot~w Operations and the Corporate Nuclear Safety Review Board of disagreement between the POC and the Plant Manager; however, the Plant Manager shall have responsibility for r solution of such dis-agree ants pursuant to Specification 6.1. 1.

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ECORDS 6.5.1.8 The POC shall maintain written minutes of each POC meeting that, at a minimum, document the results of all POC activities performed under the respon-sibility provisions of these Technical Specifications. Copies shall be provided to the AM+stant Managiq~jreetor-far Operations and the Corporate Nuclear Safety Review Board. "i<<<<~tcLB~+j ~~~

6.5.2 CORPORATE NUCLEAR SAFETY REVIEW BOARD CNSRB FUNCTION 6.5.2. 1 The CNSRB shall function to provide independent review and 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, and

h. guality assurance practices.

I/ice- tees A/eclcer The CIISRB shall report to and advise the Vtssietwlh-4anag+ng-girecto~r Operations on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

MASHINGTON NUCLEAR - UNIT 2 6-10 Amendment No. gf,118

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CONTROLLED COPY ADMINISTRATIVE CONTROLS COMPOSITION ~

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6.5.2.2 The CNSRB shall be composed of nine members appointed in writing by the Ass~aok-Managm~ire ~ Operations from his senior technical staff and/or from outside the Supply System. He shall designate from the members a Chairman and an Alternate Chairman. The. qualifications of all members shall meet the minimum requirements of Section 4.7 of ANSI/ANS 3.1-1981 and have, cumulatively, expertise in the areas listed in Specification 6.5.2.1, as a minimum.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNSRB Chairman.to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CNSRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNSRB Committee to provide expert advice to the CNSRB.

MEETING FRE UENCY 6.5.2.5 The CNSRB shall meet at least once per calendar quarter during the initial year of uni t operation following fuel loading and at least once per sibilityty 6 months thereafter.

gUORUH 6.5.2.6 The quorum of the CNSRB necessary for the performance of the CNSRB review and audi functions of these Technical Specifications shall consist of t

the Chairman or the alternate Chairman and at least four CNSRB members includ-ing alternates. No more than a minority of the quorum shall have line respon-for operation of the uni t.

REV IEM 6.5.2.7 The CNSRB shall review:

a. The safety evaluations for (I) changes to procedures, equipment or systems 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;

b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; WASHINGTON NUCLEAR UNIT 2 6-11 Amendment No. ~, 126

CONTROLLED COPY ADMINISTRATIVE CONTROLS 4

AUDITS (Continued)

h. The fire protection equipment and program implementation, at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once every third year; and Any other area of unit operation considered appropriate by the CNSRB or the A.i~:-ant-Ma~ 'hq~v.Operations. rVuc.leav Vlcc j RCSI y The radiological environmental monitoring program and the results thereof at least once per 12 months.

k. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

m. The performance of activities required by the guality Assurance Program for effluent and environmental monitoring at least once per 12 months.

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RECORDS C

6.5.2.9 Records of CNSRB activities shall be prepared, approved, and distri-buted as indicated below:

a. Minutes of each CNSRB meeting shall be' prepared, approved, and f dd.t h gtp f Op 1 each meeting. Vtc~-0'ncsu4 >

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b. Reports of reviews encompassed by Specification"6.5.2.7 above, shall

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Ace- I'e i~, @~de C. Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the 'anag+ngWH ecto~a- Operations and to the I management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION 6.6. 1 The following actions shall be taken for REPORTABLE EVENTS:

a.

b.

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The Commission shall be notified the requirements of Section 50.73 to and a report submitted pursuant to 10 CFR Part 50, and Each REPORTABLE EVENT shall be reviewed by the (POC), and the results of this review shall ll L/gg- g~>~~ A/hcfe.r WASHINGTON NUCLEAR UNIT 2 be submitted to the CNSRB and the 4~-stan@

lip tt 6-13 Amendment No. -&, 118

'DMINISTRATIVE CON d

6.7 SAFETY LIMIT VIOLATION 6.7. I The following actions shall be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Ass+stan4-Nana~gV<ce.-PaesiLA~

Aluc,lear Mme4omfor Operations and the CNSRB shall be notified.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POC. This report shall describe (I) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence. il

c. 'The Safety Limit Violation Report shall be submitted to the Commission, the CNSRB, 'and the Ass-'iMan4-Nana~g-~ester fox Vice- Rt~~~y 4J~v Operations.

d. Critical operation of the unit shall not be 'resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737.

C. Refueling operations.

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

Emergency Plan implementation.

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

OFFSITE DOSE CALCULATION MANUAL implementation.

guality Assurance Program for effluent and environmental monitoring.

6.8.2 Each procedure of Specification 6.8. 1, and changes thereto, shall be reviewed by the POC and shall be approved by the Plant Manager prior to imple-mentation and reviewed periodically as set forth in a inistrative procedures.

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WASHINGTON NUCLEAR - UNIT 2 6-14 Amendment No.

1 1

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CONTROLLED COPY

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AOMINISiMTIVECONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.3 Temporary changes to procedures of Specification 6.8. la. through I

j. may be made provided:

a~ The intent of the original proceduro is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Ooerator license on the unit affected;,and

c. The change is documented, reviewed by the POC, and approved by the Plant Manager within 14 days of implementation.

T gt-~n l 6.8.4 The following programs shall be established, implemented, and maintained:

a. Prima Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the LPCS, HPCS, RHR, RCIC, hydrogen recombiner, process sampling, containment, and the standby gas treatment systems. The program shall include the following:

Preventive maintenance and periodic visual inspection requirements, and In:egrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Moni torin A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the ollcwing:

Training of personnel, Z. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

c. Pos -accident Samolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and oarticulatas in olant gaseous eiflu-ents, and containment atmosphere samoles under accident conditions.

The program shall include the following:

Training of personnel, Procedures for sampling and analysis, and Provisions for maintenance of samoling and analysis equioment.

MA~HI%TON 'IUCL"=OR - UNIT P.

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mmaou~o m~v ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) where no enclosure exists for purposes of locking,,and no enclosure can be reasonably constructed around the individual areas, then that area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RMP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide posi-tive exposure control over the activities within the area.

6. 13 PROCESS CONTROL PROGRAM PCP Licensee-initiated changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.3n. This documentation shall contain:

1) Sufficient. information to support the change 'together with the appropriate analyses or evaluations justifying the change(s) and

2) A determination that the change will maintain the overall confor-mance of the solidified waste product to existing requirements of Federal, State or'ther applicable regulations.

b. Shall become effective after review and acceptance by the POC and the approval of the Plant Manager.

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6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.3n. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) 'and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20. 106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and

'ot adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b. Shall become effective after review and acceptance by the POC and-the approval of the Plant~Manager.

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c. Shall be submitted to the Commsssion in the form of a complete, 1egible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report f'r the period of the report in which any changes to the ODCM were made. Each change shall be iden-tified by markings in the margin of the affected pages, clearly indi-cating the area of the page that was changed, and shall indicate the date (e. g., month/year) the change was implemented.

MASHINGTON NUCLEAR " UNIT 2 6-25 Amendment No. 98

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