ML20115A348

Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee

ML20115A348
Person / Time
Site:	Cooper
Issue date:	10/08/1992
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20115A346	List: ML20115A342 ML20115A348
References
NUDOCS 9210140249
Download: ML20115A348 (5)

Text

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6.0 6DJTNISTRAI.IVE CONTROLS 6.1 ORGA_HIJATION 6.1.1 Pennonsibility The Plant Mana u er is directly responsible foc the safe and efficient operatica of the plant by providing direction for operation, radiological, engineering, and maintenance support activities. The Plant Manaper reports to the Site Manager who has overview and coordination respor bility for ensuring the safe and efficient operation ,f Cooper Nuclear Stacion. During periods of time when the Plant Manager ic unavailablo, his responsibilities automatically shift to the Senior Manager of Operations. During periods of a time when the Plant Manage r and the Senior Manager of Operations are not available, the responsibilities of the Plant Manager may be delegated in writing to one of the managers on the Cooper Nuclear Station Site staff qualified for this pocition.

6.1.2 Offsite and Onsite Orranizations y Unsite and offsite organizations shall be established for unit < peration and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

A. Lines of authority, responsibility, and communication shall be established and detined for the highest management levels through s intermediate levels to and including all operating org eization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms i

of doctunentation. These requirements chall be documented in the USAR.

L. The Site Manager shall have overview ar.d coordinate the activities of

% the following positions:

B.1 The Plant Manager who is renponsible for overall safe unit operation and who has control over those onsite activities necessary for safe operation and maintenance cf the plant.

B.2 The Senior Manager of Site Support who is directly respansible for supporting the sale and efficient operation of the plant by providing direction for training, outage and modification _

coordination, station security, and administrative support.

C. The Nuclear Power Group Manager sbd.1 have torporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff ir. operating, mai~i-ining, md providing technical support to the plant to ensure nuciser safety.

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

6.1.3 Hant Staff - Shift Complement The shift complement at the starion shall at all times meet the following requiremento. Note: Higher grade licensed operators may take the place of lower grade licensed or unlicensed. operators.

A. A licensed senior reactor operator (SRO) shall be present at the station at all times when t-here is any fuel in the reactor.

B. A licensed reactor operator shall be in the control room at all times when there is any fuel i1 tk reactor.

C. Two l! censed reactor operators shall be in the control room during all startup, shutdown and other periods involving significant planned control rod manipulations. A licensed SRO shall either be in the control Room or lumediately available to the Control Room during such periods.

9210140249 921008 ~219~

PDR ADOCK O$000298 P PDR _ _ _ _ _ ______ _ _ _ _ ___ _ _.

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- 6.2:; B.EVIEW : ANDf AUDI,I T

6;2 1 The organization and duties of comnittees for the' review and audit of- station operation shall be=as outlined below:

A, = Station Operationst Review Committee m. W g

1, SORC shall have a minimum of eight voting members - comprised' of . the-folk wing:

a. Chairman: Plant Manager or alternate

b. Individuals from'the following disciplines: -

Operations Radiological (Chemistry / Health Physics)

Maintenance Engineering. >

Koacter Engineering

+

Instrumentation and Control The above, according to individual job title, shall meet '

4 requiremeury , .

as described in Sections 4,2, 4.3,1, or 4.4 of the ' Arnerican National . '

Standards Institute 1;-18.1 1971, " Selection and Tretning of Personnel for -

Nuclear Power Plants."

Non-voting members rnay also serve on SORC- to broader. . its expertise in other areas (e.g.,. Quality Assurancs).

All alternate members shall be appointed in wrf ting by the SORC Chairmans to serve on a ternporary basis; however, no more ithan two alternates shall .

• participate as voting members in SORC at any one time.

2. Meeting Frequency: Monthly, and as required.on cal 1~of the Chairman.

3. Quorum

SORC chairman plus such a number es to constitute a majority of -

the voting members. ,

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4. Responsibilities:

a. Review all proposed normal,- abnormal, maintenance and ernergency -

operating procedures specified in 6. 3.1, 6.3. 2, 6. 3. 3, ' and 6. 3. 4 and l

proposed changes thereto: .and . any other proposed procedures or changes thereto deterrnined by any member to= effect nuclear safety, p

'b. Review all proposed tests and experiments and their results, which involve nuclear hazards not previously reviewed for conformance with technical specifications. Submit - tests which may 3 onstitute - an  :

unreviewed safety question to the NPPD Safety Review and Audit Board -

for review.

c. Review proposed changes to Technical Specifications.

-d. Review proposed changes or modifications to station - systems or equipment as discussed in the USAR or which involves an unreviewed l- safety question as defined in 10CFR50.59(c), Submit changes to equipment or syst. ems having safety significance to the NPPD Safety ,

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Review and Ar.oit Board for reniew.

i .e . Review station operation to detect potential nuclear safety hazards.

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6;2 -(cont'd)

f. . Investigate- .all violations of- Technical - Specificatiions, ' including; reporting evaluation' and recommendations to prevent recurrence,- to the Nuc1 car.. Power Group Manager and to the Chairman of the NPPD Safety .

Rrview and Audit Board,

g. Perform special: reviews and investigations and render reports thereon-as requested by the Chairman of the Safety Review and-Audit-Board,

h. Review all reportable events specified -in' Section 50.73 to - 10CFR

-Part 50.

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Review drills on emergency procedures (including plant evacuation) and' ao pv of communication with off site groups.

j, Periodically review procedures required by .Specificarions; 6.3,1, :

6.3.2, 6.3.3, and 6.3.4.as set forth in administrative procedures.

5. Authority

e. The Station Operations Review Committee shall be advisory,-

b. The Station Operations Review Committee shall recommend to the SORC Chairman approval or disapproval cf proposals under items 4, a through e and j above. In case of disagreement between the recommendations of L the Station Operations Review Committee and $.he Plant Manager, the courso determined 'by the Plant Manager to be the more s.onnervative will be.followed. A written summary of the disagreement wil.1 be'sent -

to the Site Manager, Nuclear Power Group Manager, and - to the NPID l-Safety Review and Audit Board.

c. The Station Operations Review Committoe shall report to the Chairman of the NPPD Safety Review and Audit Board on . all reviews and.

investigations conducted under items 4.f, 4.g. 4.h, and 4.1.

d. The Station Operations Review Committee shall make determinations regardi.ng whether or not proposals considered by the Committee involve unreviewed_ safety questions. This determination shall be subject to review by the NPPD Safety Review and Audit Board.

6. Records:

Minutes shall be kept for all. meetings of the Station Operations Review-Committee and shall include identification of - all documentary material reviewed. Copies of the minutes shall be-forwarded to the Chairman of the NPPD - Safety Review and Audit Board 'and the liuclear Power Group Manager vithin one month.

.7. Procedures:

Written administrative procedures for Coumittee operation sha, t be prepared and maintained describirg 'the method for submission ano -content of <

presentations to the committee, provisions for use of. subcoimnittees, -review -

and approval by members of written Committee evaluations - and l recommendations, dissev . on of minutes, and such other matters as may be appropriate.

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7 O " 6.2 J(cont'd)?

w Proposed tests or experiments which involve an unreviewed: safety!

question.as= defined in Section 50.59, 10LCFRi

'd. Proposed changes to Appendix A Technical Specifications or;the-CNS: Operating License.

c'. Violations of-applicable codes, regulations, orders, Technical Specifications, license requirements, or of internal- procedures?

or instructions:having nuclear safety significance,

f. Significant operating abnormalities or deviations from normal' and' expected performance of plant equipment _ that affect nuclear safety.

g. All -reportable events specified in Section:50.73 to '10CFR Part 50,

h. Any indication of an unanticipated, deficiency in some-aspect of. '

' design or operation of safety related : structures :- systems , .or components.

i. hinutes of meetings of the Station Operations Review Committee.

j, Disagreement betwean the recommendations of he Station Operations Review Committee and the SORC Chairman,

k.  : Review of events covered under e,f,g, and ;h . above L include reporting to appropriate members of management on the results of:

investigations and recom.nendations to prevent or rnduce D the r probability of recurrence,

5. Authority: The-NPPD Safety Review and Audit' Board shall report to and.be edvisory to the Nuclear Power Group Manager' on. thosel areas of-responsibility specified in Specifications 6.2.1.B,4:and-6',2,1.B;7,

6. -Records:

Minutes shall be recorded for all meetings of the NPPD -Safety Reviaw and

-Audit Board and shall identify-all documentary material reviewed, Copies of the minutes shall be forwarded :to ;the Nuclear - Power Group Manager, Sit'e

-Manager, and the Plant Manager, and such others as the Chairman - may .

designate within one month of the meeting.

, 7. Audits:

Audits of selected aspects of plant operation shall be perf- ned undet the: .

cognizance of SRAB with a frequency commensurate with their : s'afety-significance. Audits. performed by the Quality Assurar :e Depart ant which -

meet this specification shall be considered J to heet the SRAB audits requirements if the audit results are reviewed by'SFAB. .'A representative

-portion of-procedures and records of the activities performed during.the audit period shall- be audited and, in addition, observations of performance of operating and maintenance activities shall be included. These audits >

shall encompass: .

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-.i-6.3) - (cont'd)

-- 6 . 3 . 5 l lIrpporary Chances:

Temporary changes to procedures which do not change the intent of the original:

procedure may be made, provided such changes are approved by two members of the

' operating staff holding SR0' licenses. Such changes shall be documented and subsequently reviewed by'the Plant Manager'within one month.

-6.3.6 Exercise of Procedures Drills of the Emergency Plan procedures shall be conducted annuallyi including a check of communications with offsite support groups. Drills on ' the l procedures specified in 6.3.2. A, B, and C above shall be conducted as part of I the retraining program.

6.3.7 Programs The following programs shall be established:

A. Systems Intenrity Monitorinn Program A program shall be-established to reduce leakage to as low as practical.

levels from systems 'outside the primary - containment during a seriousL accident that would or could contain highly radioactive fluids. .This-program shall include provisions establishing preventive' maintenance and' periodic visual inspection requirements / and leak testing requiremento for each system at a frequency not to exceed refueling cycle intervals. ,

.q B. ' Iodine Monitorinn Pronram )

A program shall -be established to ensure the capability to ' accurately determine the airborne lodine concentrstion in. vital areas under accident-conditions. This program shall include training of personnel, procedures

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. for -monitoring and provisions for - maintenance of sampling and analysis .

equipment.

C. Post-Accident Samplinn System (PASS) ,

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- A program shall be established to ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates jn plant gaseous - effluents, and containment atmosphere samples under i accident conditions. - This. program shall include training-of personnel, procedures .

for sampling and analysis and= provisions . for operability of sampling and analysis equipment, 9

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