ML20070F671

Proposed Tech Spec Section 6.0 Re Responsibility & Organization of Plant Operations & Composition of Plant Safety Review Committee

ML20070F671
Person / Time
Site:	Wolf Creek
Issue date:	03/05/1991
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20070F670	List: ML20070F666 ML20070F671
References
ET-91-0045, ET-91-45, NUDOCS 9103080389
Download: ML20070F671 (8)

Text

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' Attachment IV to ET 91-0045 Page 2'of 9 ADNNISTRATIVE CONTROLS 6.1 RESPONSIBILITY _ -

LDirectorPlant_0peratio@

6.1.1 The ":y M:n:tr shall be responsitne for overall Unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1. 2 The Supervising Operator, under the Shif t Supervisor shall be responsible for the control room command f unction.

Amanagementdirectlvetothiseffect, signed by the President and Chief Executive Officer shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZAT13 6.2.1 Onsite and Operating Corporation Orcanization Onsite and operating corporation organizations shall be established for unit operation and corporate management, respectively.

The onsite and operating corporation organizations shall include the positions for the activities affect-ing the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be estab-lished and defined for the highest management levels through inter-

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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 Report.,_

LDirector Plant OperationT) jhnt M:.n:ge shall be responsible for overall unit safe operation b.

The 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 rneasures needed to ensure acceptable performance of the staf f in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operat'ng staff and those who carry out the health physics and quality assurance functions may 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;

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j WOLF CREEK - UNIT 1 6-1 hendment No. i, 24 9103080389 910305 PDR ADOCK 05000482 P

PDR i

Aftachment IV to El 91-0W 5 Page 3 of 9 9

ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staf f shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1978 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements speci-fied in Section 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 identified by the ISEG or another plant group.

6. 5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)

FUNCTION The PSRC shall function to advise t(he Nut ":r;;;r en all catters DirectorPlantOperati_o@

6. 5.1.1 related to nuclear safety.

COMPOSITION

6. 5.1. 2 The PSRC shall be composed of the:

Member:

Manager Nuclear Plant Engineering Wolf Creek l

Member:

Manager +( Operations Member:

Manager +( Technical Support Fember:

Manager +4 Maintenance and Modifications Member:

Manager Instrumentation and Contr_o1 -

Member:

-h 5 c t y.- Ogi : ri q_ Suoervisor (Reactor EngineerIRD Pember:

un!!h Bhy fcitt (Manager Radiation Protection)

Member:

Ch:r!:t (Manager Chemistry) _ _

Member:

%: A t: Engher're Supervisor (ReTults Engineer!M Chairman:

Manager e+ Plant Support ALTERNATES

6. 5.1. 3 All alternate membert, 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 Acendment No. 20,25 l

Attachment IV to ET 91-0045 Page 4 of 9 1

%v aCMINISTRATIVE CCNTROLS wtETING FREQUENCY

6. 5.1. 4 The PSRC shall meet at least once per calencar monta and as c nvenee ty the PSRC Chairman or his cesignated alternate.

QUCRUM

6. 5.1. 5 The quorum of the PSRC necessary for the performance of the PSRC responsibility, and authority provisions of these Technical Specifications shall consist of the Chairmsn or his designated alternate and four members including alternates.

it$FCNSIBILITIES

6. 5.1. 6 The PSRC shall te responsible for:

a.

Review of: (1) all precedures required by Specificaticn 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and_(3) any other proposed precedures or changes thereto as determined by th

• N-t ":n:::r to affect nuclear saf ety; Director Plant Operationl) d, Review of all propcsed changes, tests and experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR; Review of all preposed changes to Technical $pecificaticos or the c.

Operating License; Review of all safety evaluations perfor?.ed uncer t?e proviticn of d.

!*ction 50. 59(4)(1),10 CFR, for changes, tests and ex;eri:ents; Investigation of all violations of the Technical Specifications 4.

including the preparation and forwarcing of reports covering evalua-tion and reccomendations to prevent recurrence to the Vice Presidenty,.{

";cher Operations, and to the Nuclear Safety Review Ccesittae (NSRC);

f.

Review of all REPCRTABLE EVENTS; Review of reports of operating abnormalities, deviations from escected g.

performance of plant equipment and of unanticipated deficitocies n the design or operatten of structures. systems or cr conents that affect nuclear safety; h.

Performance af >pecial reviews, investigations or analyses and c

reports thereon as requested by the Chairman, NS AC; i

1 Review of the plant Security Plan and implementing procedures and shall submit recommenced changes to the NSAC;.

J.

Review of the ' Emergency Plan and implementing' procedures and shall submit recornended changes to the NSRC;

'CLF CREEK UNIT 1 6-d Amendment No.

4

At,tachment IV to ET 91-0045 Page 5 of 9 10MINISTRATLVE CONTROLS RESPON5191th1ES(Continued) i k.

Review of changes to the PROCESS CONTROL FROGFAM, the OFFSITE DOSE CALCU1.ATION MNUAl. and the Raowaste Treatment Systess, and 1.

Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recoseendations, and disposition of the corrective action to prevent recurrence and the forwarcing of these reports to the *knt "4r4;;r and to the Nuclear Safety Review Committee.(Director Plant Operations Review of the Fire Protection Program and shall submit reconeended e.

changes to the Nuclear Safety Review Committee.

6.5.1.7 The PSRC shall:

ff rector Plant OperationD Recoemend in writing to the Phnt "4 rag;r approval or disapproval of a.

items considered ut. der Specification 6.5.1.6a. through d. and s. above, l

b.

Render determinations in writing with regard to w+iether or not each ites considered under Specification 6.5.1.6a. through e. above constitutes an unreviewed safety question, and 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 c.

%:h:r Operations and the Nuclear Safety Review Committee of dis-agreement between the PSRC and the Phnt 5:g:r; herever, the 44*4

":r4;;r shall have responsibility for resolution of such disagreeement pursuant to' Specification 6.1.1 above.

hlrector]lant Operations)

RECOR05

6. 5.1. 8 The PSRC shall maintain written sinutes of each P5RC meeting that, at a minism, document the results of all PSRC activities perfereed under the responsibility provisions of'these Technical Specifications. Copies shall be provided to the Vice President hch:r Operations and the Nuclear $afety Review Cosuittee.

6.5.2 WUCLEAR SAFETY REV1EV CO*ITTEE (NSRC),

FUNCTION 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.

Instrumentation and control, f.

Radiological safety, VOLF CREEK UNIT 1 69 Aaeneent No. d.15 1

i At'tachment IV to ET 91-0045 Page 6 of 9 ADMINIST2ATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) e.

Process Cont ~' regram implementation; f.

ODCM implementation; and 9

Quality Assurance Prc. gram implementation for effluent and environ-mental monitoring, h.

Fire Protection Prep as implementation.

l Fajor Procedures, supported by appropriate Minor Procedures (such as checkof f lists, operating instructions, cata sheets, alars respw

<s 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, overall responsibilities, authority assignments or administrative and opera-tional ground rules at the Wolf Creek plant. Major Procedures are written to meet the requirements of AN51 N18.71976/ANS 3.2 and generally are supported by Minor Procedures which provide delineatic? of details such as for valve lineups, calibrationprocedures,operatinginstructions,datasheets,alareresponses!g-and other procedures identified as " supporting." Major Procedures require s Director Plant ) his absence.

nature approval in all cases ey tne41;nt P4=;;r or a Call Superintendent in Operations y A Minor Procedure is a procedure which controls safety-related activities in support of a Majer Procedure. It addresses a specific tepic or sub-topic established by its parent' Major Procedure, expanding on it by pro-viding working level instructions. Minor Procedures are not permitted to con-tradict requirements contained in their governing Major Procedure. Minor Procedures require signature approval. by the Plert Fe=;;r, or a Call Super-intendent in his absence, only at Revision '0.'

DirectorPlantOperations]

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6.8.2 Approval of Procedures All Major Procedures of the ' categories listed in Specification 6.8.1 a.

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__and modifications to the intent thereof shall be reviewed by the P5RC hirector Plant Operationsjand approved by theHent ;';=;;r prior to implementation and reviewed periodically as set fcrth in Acainistratise Procedures.

b.

Hinor Procedures (checkoff lists, operating instructions, data sheets, alars responses, chesistry and analytical procedures, technical instructions, special and routine saintenance procedures, laboratory manuals, etc.) shall, prior to initial use, be approved by the P$RC or a Subcommittee thereof.

c.

Corporate Emergency Plan isolamenting 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.

"With the exception of Corporate Emergency Plan implementing procedures.

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

VOLF CREEK UNIT 1 6-14 Amendment No.4,15

i Attachment IV to E1 91-0045 P, age 7 of 9 ADMINISTRATIVE C0ATROLS 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 or subsequent approved procedure, may be made provided such channes to operating procedures are approveo by the Shift Supervisor (SR0 licensed) and one of the Call Superintendents.

For temporary changes to Major Procedures under the jurisdiction of Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, or 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 Call Super-intendent and either a Cognizant Group Leader or the Shif t Supervisor) shall subsequently be reviewed by the PSRC and approved by the M ee Director Plant)

• "eneger within 14 days, except that temporary changes to Major Pro-Operations

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j cedures made during a refueling outage may be reviewed and approved at any time prior to initial 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 Mir.or Operating Procedures (checkoff lists, alarm responses, data sheets, operating instructions, etc.) shall be approved by the Shift Supervisor, and shall be subse-quently reviewed and approved by the Operations PSRC Subcommittee.

All temporary or permanent changes to other Minor Procedures under the jurisdiction of Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, or Health Physics, shall be approved by a Cognizant Group Leader and shall be subsequently reviewed and approved by the appropriate PSRC Subcommittee, c.

Temporary changes to Corporate Emergency Plan implementing procedures may be made provided that: (1) the intent of the original procedure is Manager Technical not altered. (2) the change is approved by the bergency Ilenning a rdin: tor, and (3) the change is documented, reviewed by appropriate b8NC85 Corporate and plant personnel and approved by the President and Chief 4

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 containment that could 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. 4

Mtachment IV to El 91-0045 Page 8 of 9 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the

" control device" or " alarm signal" required by Paragraph 20.203(c)(2), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radia-tion source or from any surface which the radiation penetrates shall be barri-caded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties-in high radiation areas with exposure rates equal to or less

_than 1000 mR/h, provided they are otherwice following plant radiation protec-tion procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or a

accompanied by one or more of the following:

.a.

A radiation monitoring device which continuously indicates the radiation dose rate in'the area, or

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b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them, or c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Site Health Php ici t in'the RWP. E k N OeM~

i 6.12.2 In addition to the requirements of Specification 6.12.,

fras accestiine to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.)

from the radiation source or from any surface which the radiation penetrates shall be p'rovided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift

' Supervisor / Supervising Operator oa duty and/or health physics. supervision, y

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP, direct or remote (such as closed-circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

ll WOLF CREEK UNIT 1 6-23 Amendment No. 42 L

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' Attachment IV to ET 91-0045 Page.9'of 9 ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) for. individual high radiation areas accessible to personnel 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 performed shall be retained as required by Specification 6.10.2.o.

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

.nr other t.pplicable regulations.

b.

Shall become effective after review and acceptance by the PSRC and the approval of the Phat ". ":;;;r. Fgtor Plant Operatio%

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6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)

L Changes to the ODCM:

Shall beLdocumented and records of reviews performed shall be.

a.

retained as required by Specification 6.10.2.o.

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 i

Part-190,-10_CFR 50.36a, and Appendix I to 10 CFR Part 50 and not. adversely impact the accuracy or reliability of ef fluent dose,- or setpoint calculations.

.1 b.

Shall become effective after review and acceptance by the PSRC and

L the approval of thef'" "'"Qlrector Plant 0peratio@

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WOLF CREEK UNIT 1 6-24 Amendment No. 42 u

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