ML20247R835

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Proposed Tech Specs Re Administrative Controls
ML20247R835
Person / Time
Site: Cooper Entergy icon.png
Issue date: 07/31/1989
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20247R826 List:
References
NUDOCS 8908080114
Download: ML20247R835 (6)
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6.0 ADMINISTRATIVE CONTROLS 6.1 R O_RfANIZATION 6.1.1 Responsibility The Division Manager of Nuclear Operations shall have the over-all fulltime onsite responsibility for the safe operation of the Cooper Nuclear Station. During periods when the Division Manager of Nuclear Operations is unavailable, this responsibility automatically shifts to either the Senior Manager of Operations, or the Senior Manage) of Technical Support ' Services (in that order). During periods when none

of these individuals are available, the responsibility may be delegated in writing to one of the managers in the Nuclear Operations Division.

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6.1.2 offs 1tr The portion of the Nebraska Public Power District management which relates to the operation of this station is shown in Fir,,ure 6.1.1.

6.1.3 Plant Staff - Shift Complement The organization for conduct of operation of the station is shown in Fig. 6.1.2. The shift complement at the station shall at all times meet the following requirements. Note: Higher grade licensed operators may  !

take the place of lower grade licensed or unlicensed operators.

l A. A licensed senior reactor operator (SF.0) shall be present at the station at all times when there is any fuel in the reactor.

B. A licensed reactor opei'ator shall be in the control room at all times j when there is any fuel in the reactor.  !

i C. Two licensed reactor operators shall be in the control rooie durin5 all startup, shutdown and other periods involving significant planned )

control rod manipulations. A licensed SRO shall either be in the Control Room or immediately available to the Control Room during such periods. l D. A licensed senior reactor operator (SRO) with no other concurrent duties shall be directly in charge of any refueling operation, or alteration of the reactor core.

A licensed reactor operator (RO) with no other concurrent duties shall be directly in charge of operations involving the handling :of irradiated fuel other than refueling or reactor core alteration operations.

E. An individual who has been trained and qualified in health physics techniques shall be on site at all times that fuel is on site.

8908080114 890731 N PDR ADOCK 05000;?98' P PNU;

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F. Minimum crew size during reactor operation shall consist of four. 1 7' '

licensed reactor operators (two of.whom shall be licensed SRO) and. j three unlicensed operators. Minimum crew size during. reactor cold-shutdown conditions shall consist-of two licensed reactor operators

-(one of whom shall be licensed SRO) and one unlicensed 1 operator.

In the-event that-any member of a. minimum shift crew is absent or incapacitated due.to illness or injury a qualified replacement shall, be designated to report on-site within tw hours. j I

G. A Fire Brigade of at least' 5 members : shall be maintained at all~ l

. times., . This excludes the '3 members - of the minimum i shif t crew

- necessary for s&fe shutdowns, and other personnel required for other*

. essential functions ' during a fire emergency. - Three Fire t Brigade -

members shall be from the Operations Department and 2 support members may be from other departments inclusive of. security personnel. j Fire Brigade composition 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'secommodar.e '.)

unexpected absence .of Fire Brigade members provided immediate action-is taken' to restore the Fire -Brigade to within the minimum-requirements.

H. A Shift Technical Advisor shall bed available, except ~during cold shutdown. conditions, to serve in an advisory capacity to.the' shift ,

crew on matters. pertaining to the engineering aspects assuring safe -l operation of the plant. )

6.1.4 Plant Staff - Qualifications  !

1 The- minimum qualifications, training, replacement training, and 1 retraining of plant personnel at the time of fuel loading or appointment q to the active positions shall meet the' requirements asJdescribed in the- 1 American National Standards Institute N-18;1-1971, :' Selection and~ j Training of. Personnel for Nuclear Power Plante" . [The Radiological i Manager shall meet or exceed the qualifications of Regulatory Guide 1.i, Sept. 1975; personnel qualification equivalency ' as ' stated in the- .)

Regulatory Guide may be proposed in' selectedicases. The minimum )

frequency of' the retraining program shall be every two years. The- 3 training program shall be under the direction , of - the' Training Manager.  ;

- . i A. A training program for the fire brigade will be. maintained under the -  ;

direction of the' Training Manager ! and shall meet or exceed the ,

requirements of Section 27 of the.NFPA Code 1976,:except for' Fire l

Brigade training sessions which shall.be held at least quarterly, y The' training program requirements will be provided by a qualified -l fire protection engineer. j l

B. The Shift Technical Advisor 'shall' .have a bachelor's degree or j equivalent in a scientific or engineering discipline and.shall have H received specific training in plant design, and response and analysis - I of the plant,for transients and. accidents. l

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. j 6,2 REVIEW AND AUDIT ~^ - " - - " -

6.2.1 .The organization and duties of committees for the review and audit of station operation shall be as outlined below:

A. Station Operations Review Committee (SORC)

1. SORC 'shall have a minimum of eight voting members comprised of the  ;

following:

a. Chairman: Division Manager of Nuclear Operations, or alternate
b. Individuals from the following disciplines:

o Operations  ;

o Chemistry / Health Physics o Maintenance o Engineering o Reactor Engi0eering o Instrumentation and Control The above, according to individual job title, shall meet the requirements as described in Sections 4.2., 4.3, and 4.4 of the I American National Standards Institute N-18.1 1971, " Selection end Training of Personnel for Nuclear Power Plants."

Non-voting members may also serve on SORC to broaden its expertise in other areas (e.g., Quality Assurance).

2. Meeting Frequency: Monthly, and as required on call of the Chairman.
3. Quorum: SORC chairman plus such a number of other voting members to be equal to or greater than one-half the total authorized voting membership.
4. Responsibilities:
g. Review all proposed normal, abnormal, maintenance and emergency operating procedures specified in 6.3.1, 6.3.2, 6.3.3 and 6.3.4 and proposed changes ,thereto: and any other proposed procedures or changes thereto determined by any member to effect nuclear safety.
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 constitute an unreviewed safety question to the NPPD Safety Review and Audit Board for review, i
c. ' Review proposed changes to Technical Specifications.
d. Review proposed changes or modifications to station systems or j equipment as discussed in the USAR or which involves an unre-viewe.d safety question as defined in 10CFR50.59(c), Submit changes to equipment or systems having safety significance to l

the NPPD Safety Review and Audit Board for review.

l e. Review station operation to detect potentfal nuclear safety hazards

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f. , Investigate.all violations of Technical Specifications, includingi reporting evaluation and recommendations to. prevent recurrence, to-the Nuclear Power Group Manager and to the Chairman of the NPPD l

' Safety' Review-and. Audit Board.

g. Perform'special reviews and investigations and'ren' der reports' thereon as requested by1 the Chairman of the Safety Review and Audit Board,
h. Review all reportable events specified in Section 50.73 to'10CFR Part 50.

.i. Review. drills on emergency procedures.(including plant evacuation).

and adequacy of communication with off site groups.

j. . Periodically. review procedures cequired by Specifications 6.3.1, 6.3.2, 6.3.3,.and 6.3.4 as set forth in administrative procedures.
5. Authority
a. The Station Operations Review Committee shall be advisory.
b. The Station Operations Review Committee'shall recommend to the SORC Chairman approval or disapproval of proposals'under items 4', a through e and j above. In case'of disagreement between the recommendations' of the Station Operations Review Committee and the

-Division Manager of Nuclear Operations, the' course determined by the RDit a n Manager of Nuclear Operations .to be: the more conservative wil be followed. A written summary of the disagreement will be sent to tia huclear Power Group Manager and to the NPPD' Safety Review and l Audic Board.

c. The Station Operations Review Committee 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.i.

d. The Station Operations Review Committee shall make: determinations regarding 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: j 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 bc forwarded'to the Chairman of the NPPD Safety Review and Audit Board arid the Nuclear Power Group Manager within one month.-
7. Procedures:

Written administrative procedures for. Committee operation shall be prepa' red and maintained describing the + thod for submission and content l ' of presentations to the committee, provisions for use of subcommittees, review and approval by members of written Committee evaluations and recommendations,- dissemination of minutes, and such other matters as may be. appropriate.

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3, .c. J Proposed tests: or ' experiments whichlinvolve an 'unreviewed -

C safety; question'as' defined in Section 50.59, 10 CFR.

Ld. ' Proposed changes to' Appendix'A Technical Specifications.or the CNS' Operating License.

e. Violations of; applicable codes, ~ regulations, orders , . Technical Specifications, license requirements,~ or of internal-procedures or instructions having nuclear safety significance.

s 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.

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

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design or operation;of safety related structures, systems, or.  !

components.  ?!

1. Minutes 'of meetings. of the 1 Station -Operations Review Cormittee.

j, Disagreement between the recommendations of the Station Operations Review' Committee and the SORC Chairman. j 'I

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k. Review of events covered'under e,f,g, and.h above include i reportinr, to appropriate members of management on the results of investigations- and recommendations to prevent or reduce the probability of recurrence.
5. Authority: Thr NPPD Safety Review and Audit Board shall report to and be advisory to th Nuclear Power Group Manager on those areas of l responsibility specified in' Specifications 6,2.1.B.4'and 6.2.1.B.7.
6. Records:

i Minutes shall be recorded for ell 1 meetings of the NPPD Safety Review ans  :

Audit Board and sht.11 identify-all-documentary material' reviewed. . Copies of the minutes shall be forwarded to thesNuclear Power Group Manager and l the-Division Manager of Nuclear Operations, .and;such'others as the

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Chairman may designate within one month of the' meeting. l

7. Auditsi  :

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Audits of selected as,pects:of plant operationishall be performed under l the cognitance of.SRAB'with"a frequency commensurate with their safety

. significance. Audits performed'by the Quality Assurance Department whien meet this. specification shall be. considered to meet the SRAB audit R requirements if the audit.resu.ts'are reviewed by SRAB. A representative  ;

portion of procedures and records of the' activities performed'during the i E ,

audit period shall be audited and, in addition, observations of l-

- performance of operating .and maintenance . activities shall . be included. ,

l These audits shall encompass:  ;

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6.5.2 Reportable Events A Reportable Event shall be any of those conditions specified in Section -

50.73 to 10CFR Part 50. The NRC shall be notified and a report submitted \

pursuant to the requirements of Section 50,73. Each Reportable Event shall be reviewed by SORC and the results of this review shall be submitted to SRAB and the Nuclear Power Group Manager. l l

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