ML20203B582

Proposed Tech Specs Allowing Licensed Activities to Be Under Control of Wolf Creek Nuclear Operating Corp

ML20203B582
Person / Time
Site:	Wolf Creek
Issue date:	04/15/1986
From:	KANSAS GAS & ELECTRIC CO.
To:
Shared Package
ML20203B548	List: ML20203B544 ML20203B559 ML20203B582
References
TAC-61304, NUDOCS 8604180211
Download: ML20203B582 (11)

Text

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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 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 Supervising Operator, under the Shift Supervisor, shall be responsible for the control room command function. A management directive to this effect, signed by the " iceorecident uu ! cary shall be reissued to all station personnel on an annual basis, pfcSidenf ON CNefficcuNm OfReer 6.2 ORGANIZATION OFFSITE Operabj CorporaNon 6.2.1 The off itegorganization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2 The Unit organization shall be as shown in Figure 6.2-2 and:

a. Each on duty shift shall_be composed of at least the minimum shift crew composition shown in Table 6.2-1;

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the Unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room;

c. An individual from the Health Physics Group *, qualified in radiation protection procedures, shall be on site when fuel is in the reactor;

d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. A site Fire Brigade of at least 5 members

• shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor, and the two other members of the minimum shift crew necessary for safe shutdown of the Unit and any personnel required for other essential functions during a fire emergency; and

• May be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the rennited positions, h

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nutr CREEK - UNIT 1 6-1

Chairman of the Board Vice Chairman of the Board Board of Directors President and Chief Executive Officer Nuclear Safety General Counsel &

Review Committee Secretary

. Vice President Vice President Vice President Engineering &

l Nuclear Operations Quality Technical Services

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( Manager i Nuclear Manager Manager Supt Manager Director Manager Manager Manager '

! Operr.tions . Nuclear Procurement Quality Quality Administrative Nuclear Management Constructiori Support Training & Materials Control Assurance Services Services Systems (WCGS)

Manager Manager l Manager Plant Planning Quality Engineering Manager Manager & Assurance & Technical Nuclear WCGS Scheduling (Home Services- Plant Office) Support Engineerina l

Figure 6.2-1 Operating Corporation Organization (Proposed)

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1 ADMINISTRATIVE CONTROLS l

l MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated alternate.

! QUORUM i

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 Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for:

a. Review of: (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety;

b. Review of all proposed changes, tests and experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR;

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

d. Review of all safety evaluations performed under the provision of Section 50.59(a)(1), 10 CFR, for changes, tests and experiments; i

e. 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 M r::ter,%

Nuclear Operations, and to the Nuclear Safety Review Committee f (NSRC); g pm;g

f. Review of all REPORTABLE EVENTS;

g. Review of reports of operating abnormalities, deviations from expected performance of plant equipment and of unanticipated deficiencies in l the design or operation of structures, systems or components that affect nuclear safety;

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman, NSRC;

i. Review of the plant Security Plan and implementing procedures and shall submit recommended changes to the NSRC;

j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the NSRC; WOLF CREEK - UNIT 1 6-8 l

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

k. Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL and the Radwaste Treatment Systems, and

1. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent-recurrence and the forwarding of these reports to the Plant Manager and to the Nuclear Safety Review Committee.

, 6. 5.1. 7 The PSRC shall:

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

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a. through e. above ,

constitutes an unreviewed safety question, and j Vice. Preidemt

c. Provice written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the30ir eter Nuclear Operations and the Nuclear Safety Review Corrmittee of disagreement between the PSRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 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 performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Circ teryNuclear Operations and the Nuclear Safety Review Committee. Vice Presic/ eof-6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (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, WOLF CREEK - UNIT 1 6-9 J

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ADMINISTRATIVE CONTROLS FUNCTION (Continued)

g. Mechanical and electrical engineering, and l

h. Quality assurance practices.

PresWen+ and Chief Execub O$.ce r TheNSRCshallreporttoandadvisethegice"recident""r!erronthoseareas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.

1 COMPOSITION I 6.5.2.2 The NSRC shall be composed of at least the following:

Chairman: Manager Nuclear Services l Member: Vice]resMir::ter Engineering and Technical Services Member: Manager Quality Assurance (Home Office)

Member.Vice. Resided Cir::t:r Nuclear Operations Member: Manager Licensing rrd " die'c;ier' % ~' ~ r it-Member: "i : "r::id::t-Engin::r r; Kc.p4g Senior Dir,c,4, c,{ /%c/eu i

i Member: Manager Nuclear Safety Aff;g +

Additional members and Vice Chairman may be appointed by the Chairman. .

ALTERNATES 4r Chany prevkas/y propseM M gMLN4C F4-037 ddY" N86 6.5.2.3 All alternate members shall be appointed in writing by the NSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advice to the NSRC.

MEETING FREQUENCY 6.5.2.5 The NSRC shall meet at least once per calendar quarter during the t initial year of unit operation following fuel loading and at least once per 6 months thereafter.

QUORUM 6.5.2.6 The quorum of the NSRC necessary for the performance of the NSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least two-thirds of the NSRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the Unit.

WOLF CREEK UNIT'1 6-10

l l ADMINISTRATIVE CONTROLS AUDITS (Continued)

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months;

e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA or ISEG personnel;

f. The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee j fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year;

g. The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; I

h. The ODCM and implementing procedures at least once per 24 months; j

i. The PROCESS CONTROL PROGRAM and implementing procedures for processing l

and packaging of radioactive wastes at least once per 24 months; I

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

k. The Emergency Plan and implementing procedures at least once per l 12 months; l

1. The Security Plan and implementing procedures at least once per 12 months; and I m. Any other area of Unit operation considered appropriate by the NSRC

'ic Pre;ident-Muc! ear.

l or the@Presiden+ and Chief Ewuhve Cliocre RECORDS l l l 6.5.2.9 Records of NSRC activities shall be prepared, approved, and distributed l l

as indicated below: I

a. Minutes of each NSRC meeting shall be prepared, reviewed by partici-pating members and forwarded to the@'ic: Pr ;fd:nt-Mu ! car within 14 days following each meeting; Presided ad CNe /' Exeue,_ dhw l

i b. Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared, reviewed by participating members and forwarded to the

'!i c: Pr ;ident-Hec!earpithin 14 days following completion of the review; and 8e>Idrab a d Chief Eiecu hve. 06?cm WOLF CREEK - UNIT 1 6-12 l

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ADMINISTRATIVE CONTROLS RECORDS (Continued) fy,s@[ ad Ch;,,[ E'wudk MIccr-

c. Audit reports encompassed by Specification 6.5.2.8 above, shall be forwarded to theVice P esident t;ucl r and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant )

to the requirements of Section 50.73 of 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PSRC and submitted Vice Prc:ider.t t :le:r to the NSRC and the'PresMec and cues Ekewh Mccr 6.7 SAFETY LIMIT VIOLATION I

e 6.7.1 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The "i e I.esident ??uci---

and the NSRC shall be notified within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sf kresid,# owl CWeID'#VA,##-

b. A Safety Limit Violation Report shall be prepared. The report shall M ker be reviewed by the PSRC. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective ACTION taken to prevent recurrence;

c. The Safety Limit Violation Report shall be submitted to the Commission, the NSRC and the y Vice Presidert--!!uclear within 14 days of the violation; and Y<estdod and Chld Euedlye_ d@lar

d. Critical operation of the Unit shall not be resumed until authorized by the Commission. I 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained  !

covering the activities referenced below:

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a. The applicable procedures recommended in Appendix A, of Regulatory 1 Guide 1.33, Revision 2, February 1978;

b. The emergency operating procedures required to implement the require-ments of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Sec-tion 7.1 of Generic Letter No. 82-33;

c. Security Plan implementation;

d. Emergency Plan implementation; WOLF CREEK - UNIT 1 6-13 1

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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.

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-relat.?d activities, and establishes one or more basic controls, overall respensibilities, authority assignments cr administrative and opera-tional ground rules at the Wolf Creek plant. Major Procedures are written 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 require sig- 1 nature approval in all cases by the Plant Manager or a Call Superintendent in his absence. A Minor Procedure is a procedure which controls safety-related

- activities in support of a Major Procedure. It addresses a specific topic 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 Plant Manager, or 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 Plant Manager prior to implementation and reviewed periodically as set forth in Administrative Procedures.

b. Minor Procedures (checkoff lists, operating instructions, data sheets, alarm responses, chemistry and analytical procedures, technical instructions, special and routine maintenance procedures, laboratory manuals, etc.) shall, prior to initial 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 Wee "n d ;.t-t ': r asy set forth in General Procedures. f

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• With the exceptioit of Corporate Emergency Plan implementing procedures.

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

i 6-14 WOLF CREEK - UNIT 1

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} ADMINISTRATIVE CONTROLS j PROCEDURES AND PROGRAMS (Continued) 6.8.3 Changes to Procedures

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a. Temporary changes to Major Procedures, of the categories listed in

! Specification 6.8.1 which do not change the intent or generate an i unreviewed safety question of the original or subsequent approved j procedure, may be made provided such changes to operating procedures i are approved by the Shift Supervisor (SRO licensed) and one of the i 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 j upon approval of the Cognizant Group Leader and a Call Superintendent.

l All temporary changes to Major Procedures (made by a Call Super-1 intendent and either a Cognizant Group Leader or the Shift Supervisor) j shall subsequently be reviewed by the PSRC and approved by the Plant j Manager within 14 days, except that temporary changes to Major Pro-

! cedures made during a refueling outage may be reviewed and approved j at any time prior to initial criticality of the reload core. All i permanent changes to Major Procedures shall be made in accordance j with Specification 6.8.2.a.

b. All temporary or permanent changes to Minor Operating Procedures ,

j (checkoff lists, alarm responses, data sheets, operating instructions,  !

i etc.) shall be approved by the Shift Supervisor, and shall be subse-

quently reviewed and approved by the Operations PSRC Subcommittee.

j 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 i Cognizant Group Leader and shall be subsequently reviewed and approved  !

by the appropriate PSRC Subcommittee.

4 l l c. Temporary changes to Corporate Emergency Plan implementing procedures j may be made provided that: (1) the intent of the original procedure is

not altered, (2) the change is approved by the Emergency Planning i Coordinator, and (3) the change is documented, reviewed by appropriate j Corporate and plant personnel and approved by the,j!k; N;; M

r,7 j i ; h:n within 14 days'of the implementation. pyy g Q Emd.h 6.8.4 The follcwing programs shall be established, implemented, an k nfained:

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a. Reactor Coolant Sources Outside Containment j 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 l i systems include the appropriate portions'of the Containment Spray

! System, Safety Injection Systeni, Chemical and Volume Control System,

{ RHR System, and the Nuclear Sampling System (PASS only). The program 4

shall include the following

WOLF CREEK UNIT 1 6-15 l i'

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ATTACHMENT 3 Safety Evaluation t

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Attschm;nt 3 Safety Evaluation The proposed changes to the Wolf Creek Generatin6 Station (WCGS), Unit No.

1, Technical Specifications involve changes to titles and minor reporting relationship changes resulting from the formation of the Wolf Creek Nuclear Operating Company. The proposed changes are provided as Attachment 2.

The proposed amendment does not increase the probabilicy of occurrence or the consequences of an accident or malfunction of equipment important to sa fety previously evaluated in the safety analysis report. These changes involve organizational enhancements and as such, have no effect on plant equipment or the technical qualifications of plant personnel.

The proposed amendment does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the sa fety analysis report. These changes do not change the number or qualifications of personael who operate WCGS, nor do they involve any change to installed plant systems or the overall operating philosophy of WCGS.

The proposed amendment does not reduce the margin of safety as defined in the basis for any technical specification. These changes do not involve any changes in overall organizational commitments or individual job responsibilities. Organizational modifications alone do not reduce any margin of safety.

Based on the above analysis, the proposed amendment to the WCGS Technical

Specifications does not involve an unreviewed safety question.

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