ML20118B080

Proposed Tech Spec Section 6.0 Re Organization & Position Title Changes

ML20118B080
Person / Time
Site:	Wolf Creek
Issue date:	09/22/1992
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20118B078	List: ML20118B077 ML20118B080
References
NUDOCS 9209290395
Download: ML20118B080 (8)

Text

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Attachment 7V to NA 92-0054 Page 1 of 6 ATTACHMENT IV PROPOSED YECHNICAL SPECIFICATION C.11ANGES I:

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Attachment IV to M 92 0354 Page 2 of 8 ACHIN!sTRATIVE CONTROLS 6.1 RESPONSIBILITY _

6.1.1 The ok t0 rations shall be responsible for overall Unit l operation and shall delegatt in writing the succession to this responsibility 4

during ',is absence.

6.1.2 The Supervising Operator, under the Shift Supervisor, shall be responsible '

for the control room comand function. A nanagement directive to this effect, signed by the President and Chief Executive Officer shall be reissued to all

, station personnel on an annual basis.

6.2 DRGANIZATION 6.2 1 Onsite and Operatino Corporation Organization Onsite and operating corporation organizations shall be established for unit i operation and corpora +e management, respectively. The onsite and operating corporation organizations shall include the positions for the activities affect-ing tne safety of the nuclear power plent.

a. Lines of authority, responsibility, and c:mmunication shall be estab- '

lished and defined for the highest management levels through inter-mediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of depart-mental responsibilities and relationships, and job descriptions for key personnel positions, or equivalent forms of documentation. These requirements shall be documented in the Updated Safety Analysis Repo t-ice Pro igent)

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b. The an F0perations shall be responsible for overall unit l safe operation and shall have control of those onsite activities necessary for safe operation and maintenance of the plant.

c. The President and Chief Executive Officer shall have corporate respon-sibility for overall plant nuclear safety and shall take any measures needed to ens've acceptable performance of the staff in operating, maintaining, and providing technical support to tM slant to ensure nuclear safety.

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

6.2.2 Unit Staff

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; WOLF CREEK - UNIT 1 6-1 Amendment No. 4, 24, 45 l

Attathnent IV to NA 92-0054

, Page 3 of fi ADMINISTRAllVE CONT,R,,QLS ,,

0,3 UNIT STfff OVAllfICATION (Continued)

. b. The position of Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

c. 1he NSRC members shall meet or exceed the requirements of ANSI /ANS 3.1-1981.

L _4 JRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager Training and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1978 with the following exceptions:

a. The training program for Licensed Operators and Senior Operators ,

shall meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision i 2, and 10 CFR Part 55.

b. Training shall include familiarization with relevant industry operational experience identified by the ISEG or another plant group.

6.5 REVIEW ANQ. AVpjT 511 PLANT SAFETY REVIEW COMMITTE1 (PSRC) f3!NCT10N _

6.5.1.1 gicePreLidenn The PSRC shall function to advise the Jrecten Plan 1J t Operatfons on ,

, all matters related to nuclear safety.

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l 6.5.1.2 The PSRC shall be composed of the:

Member: Manager System Engineering l l

Member: Manager Operations Member: Manager Technical Support Member: Manager Maintenance and Modifications Member: Manager Instrumentation and Control Member: Supervisor Reactor Engineering Member: Manager Radiation Protection Member: Manager Chemistry Member: Supervisor Results Engineering Chairman: Manager " ant Support ALT.fRNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.

WOLF CREEK UNIT 1 6-7 Amendment No. - 20, 25, A5, 5A, 56

Attachment IV to NA 92-0054 Page 4 of 8 ADMINISTRATIVE CONTROLS ,

MEETING FREQUENCY

6. 5.1. 4 The PSRC shall meet at least once per calendar santn and as convened by the PSRC Chairsan or his designatef/ alternate.

QUORUM 6.5.1.5 The quorum of the PSRC necer.sary for the performance of tne PSRC responsibility and authority previs onso of these Technical Specifications shall consist of the C.uirman or his dtsignated alternate and four sesbers including alternates.

RESPQNSIBILITIES

6. 5.1. 6 The PSRC shall be respon11ble for:

a. Review of: (1) all procedures required by Specification 6,8 and changes thereto, (2) all programs required by f dicat. ion 6.8 and y changes thereto, and (3) any other proposed p- .es or changes thereto as determined by the ggagla,rlt,0ps. ,ons to affect l

nuclear safety; g d

b. Review of all proposed changes, tests and experiments which may -

involve an unroviewed safety question as defined in Section 50.59, 10 CFR;

c. Review of all proposed changes to Technical SpecifPations or the Operating License;

d. Review of all safoty evaluations performed under the provision of Sect'on 50.59(a)(1), 10 CFR, for changes, tests and experiments;

e. Investigation of t11 violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendatior.s to prevent recurrence to the Vice President -

klh0perations,and*otheNuclearSafetyReviewCommittee(NSRC);

f. Review of .:11 REPORTABLE EVENTS;

g. Review of reports of operating abnormalities, deviations from exp6..ad performance of plant aquipment and of unanticipated deficiencies in the dealgn or operation of structures, systems or components that affect nuclear safety; g

h. Performance of special reviews, investigations er ant lyr.r; and

,4 reports thereon as requested by the Chairman, NSRC;

1. 'teview of the plant Security Plan and implementing procedures and snall submit recotr.aended changes to the NSRC;

j. Review of the Emergency Plan and implementing procedures and shall submit reco nended changes to the NSRC; WOLF CREEK UN1' 1 6-8 Amendment No. 4, 45

WF At.tachment IV to NA 92-0054 i .

Page 5 of 8 ADMihlSTRATIVE CONTROLS RESPONSIBILITIES (Continued)

k. Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION .W'JAL and the Radwas .e Treatment Systems, and

1. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparit don of reports covering evaluation, recommendations, and disposstie if the corrective action to prevent recurrence and the forwar6ng "" chese reports to the lan Operations and to the Nuct t Safety Review Committee. Vice Prest _ ent

m. Review oi ene Fire Protection Pro ram and shall submit recomended changes to the Nuclear Safety Rev ew Committee.

6. 5.1. 7 The PSRC shall:

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a. Recommeid in writing to the 7t w Plant Operations approval or disapproval of items considered under Specification 6.5.1.6a. through

d. and m. above,

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a. through e. above constitute, an unreviewed safety question, and c.

p M ef 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-ViS~"TE57K5t) Executive

-opwat4ene- and the Nuclear Safety Review Committee of disagreement (Of ficer between the PSRC and the 0,imet& Plant Operations; however, i the- te-Plant Ograt ons shall have responsibility for reso-lution of such distgreem nts pursuant to Specification 6.1.1 above.

RECORDS Vice President,

6. 5.1. 8 The PSRC shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activities pu formed under the respon-sibility provisions of these Technical Specifications. Copies shall be provided to the Vice PresidentAerations and the Nuclear Safe'v Review Comittee.

6.5.2 NUCLEAR SAF VIEV CO MITTEE (NSRC)

. FUNCTIOS 6.5.2.1 The NSRC 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. Instrumentaticr. and control,

f. Radiological safety, WOLF CREEK UNIT 1 6-9 Amendment No. 4, I5, 45

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Attachment IV to NA 92-0054 Page 6 of 8 i ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

e. Process Control Program implementation;

f. 00CM implementation; and

g. Quality Assurance Program implementation for effluent and environ-mental monitoring.

h. Fire Protection Program implementation.

Major Procedures, supported by appropriate Minor Procedures (such as checkoff lists, operating instructions, data sheets, alarm responses, etc.), shall be provided for the above activities.* A Major Procedure is a procedure which con-trols safety-related activities, and establishes one or more basic controls, overe.ll responsibilities, authority assignments or administrative and opera-tional ground rules at the Wolf Creek plant. Major Proceduros are writtan to meet the requirements of ANSI N18.7-1976/ANS 3.2 and generally are supported by Minor Procedures which provide delineation of details such as for valve lineups, calibration procedures, operating instructions, data sheets, alarm responses, and other procedures identified as " supporting." Major Procedures requ -

nature approval in all cases by the DirectertPlant Operations or a Call e Presiden Superintendent in his absence. A Minor Procedure is a procedure whi h_ con safety-related activities in support of a Major Procedure. It addresses a specific topic or sub-topic established by its ' parent' Major Procedure, expan-ding on it by providing working level instructions. Minor Procedures are not permitted to contradict rsquirements contained in their governing Major Procedure.

Minor Procedures require signature approval by the Oirector ,P_1a!Lt 0 erations, or -l a Call Super-intendent in his absence, only at Revision '0.'

6.8.2 Approval of Procedures

a. All Major Procedures of the categories listed in Specification 6.8.1 and modifications to the intent thereof shall be reviewed by the PSRC and approved by the Circcter Plant Operations prior to implementation and reviewed period al s set forth in Administrative Procedures.

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b. Minor Procedures (c ecko iskElks, vcerating instructions, data sheets, alarm responses, chemistry and analytical procedures, technical instructions, special and routine maintenance procedures, laboratory manuals, etc.) shall, priur to 11itial use, be approved by the'PSRC or a Subcommittee thereof.

c. Corporate Emergency Plan implementing procedures shall be reviewed by appropriate corporate and plant personnel and approved by the Presi-dent and Chief Executive Officer as-set forth in General Procedures.

" Wit.h the exception of Corporate Emergency Plan implementing procedures.

Corporate Emergency Plan implementing procedures shall be provided but shall not be designated as major or minor procedures.

WOLF CREEK UNIT 1 6-14 Amendment No. 4, IS, 45 ,

Attachment IV to NA 92-0054

. Page 7 of 8 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.3 Changes to Procedures

a. Temporary changes to Major Procedures, of the categories listed in Specification 6.8.1 which do not change the intent or generate an unreviewed safety question of the original t,c subsequent approved procedure, may be made provided such changes to operating prcs.edures are approved by the Shift Supervisor (SR0 licensed) and one of the Call Superintendents. For temporary changes to Major Procedures under the jurisdiction of groups other than Operations (e.g.,

Maintenance, Instrumentation and Contr,1, Reactor Engineering, Chemistry, Health Physics) which do not change the intent or generate an unreviewed safety question, changes may be made upon approval of the Cognizant Group Leader and a Call Superintendent.

All temporary changes to Major Procedures (made by a Cail Superintendent and either a Cognizant Group Leader or tha Shift

- .wm Supervisor) shall subseque,itly be reviewed by the PSRC and approved

( Vice President l by theAnte Plant Operations within 14 days, except that w' .emporary changes to Major Procedures made Caring a refueling outage may be reviewed and approved at any time prior .0 initial 2

criticality of the reload core. All permanent changes to Major Procedures shall be made in accordance with Specification 6.8.2.a.

b. All temporary or permanent changes to Minor Operating Procedures (checkoff lists, alarm responses, data sheets, operating instructions, etc.) shall be approved by the Shift Supervisor, and shall be subsequently reviewed and approved by the Operations PSRC Subcommittee. All temporary or permanent changes to other Minor Procedures under the jurisdiction of groups other than Operations (e.g., Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, Health Physics) shall be approved by a Cognizant Group Leader and shall be subsequent'y reviewed and '

approved by the appropriate PSRC Subcommittee.

c. Temporary changes to Corporate Emergency Plan implerrenting procedures may be made provided that: (1) the intent of the original procedure is not altered. (2) the change is approved by the Manager Technical Services, and (3) the change is documented, reviewed by appropriate Corporate and plant personnel and approved by the President and Chief Executive Officer within 14 days of the implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a. Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containm?nt that cauld contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the appropriate portions of the Containment Spray System, Safety Injection System, Chemical and Volume Control System, RHR System, and the Nuclear Sampling System (PASS only). The program shall include the following:

WOLF CREEK - UNIT 1 6-15 Amendment No. V, %',56 l

Attachment IV to NA 92-0054 Page 8 of 8 4

ADMINISTRATIVE CONTROLS _

HIGH RADIATION AREA (Continued)

For individual high radiation areas accessible to perwnnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a. Shall be documented and records of reviews parformed shall be reteined as required by Specification 6.10.2.0. 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 conformance of the solidified waste product to existing requirements of Federal, State, or other applicab'e regulations.

b. Shall become effective after review and acceptance by the PSRC and the approval of theAitecteMJaqt Operations. l QUc LPresident 6.14 0FFSITE DOSE CALCULATION MANUAL 1 R M)) m Changes to the 00CH:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o. This documentation shall contain:

1) Sufficient information to suppo*t the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determinatio,1 that the change will maintain the level of radioactive e t fluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and apendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations.

b. ShcIl become effective after review and acceptance by the PSRC and the approval of the D M eg g Plant Operations. l b b"h WOLF CREEK UNIT 1 6-24 Amendment No. 42, 45

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