ML20151M254

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Proposed Tech Specs Formalizing Changes in Organizational Structure
ML20151M254
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/15/1988
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20151M247 List:
References
NUDOCS 8804250005
Download: ML20151M254 (10)
v • d • e


Text

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5.0 A0till11STRATIVE C0t4TROLS 5.1 Responsibility 5.1.1 The flanager - Fort Calhoun Station shall be responsible fer overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

5.2 Organization lok ekn huMt 5.2.1 i

tion 5.2.2 lant Staff The plant staff organization shall be as sha:. in rigur; 5 2 u d I

function as follows:

dcsc ci be3 m W UAAR.

The minimum number and type of licensed and unlicensed operating a.

personnel required onsite for each shift shall be as shown in Table 5.2-1.

b.

An Operator or Technician qualified in Radiation Protection Proceoures shall be onsite when fuel is in the reactor.

All core alterations shall be directly supervised by either a c.

licensed Senior Reactor OperLtor or Senior Reactor Operator limited ta fuel handling who has no other concurrent responsi-bilities during the operation.

d.

Fire protection program responsibilities are assign t

positions and/or groups designated by asterisks in Figures 5-4

. A ttsAR

. nd 5 2 according to the procedures specified in Sec n

o gy the Technical Specifications.

C.l M A fire brigade consisting of 5 members shall be maintained onsite e.

at all times.' The fire brigade shall not include the minimum shift crew necessary for safe shutdown of the unit (2 members).

  1. Fire Brigade composition may be less than the minimum requirements for a period or time not to cxceed 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 of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

5-1 Amendment Ito. 9,J9,29,36,33,76,7B, 101 88052'50005 080415 PDR ADOCK 05000285 P

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Attachment A Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

Lines of authority, responsibility, and camunication shall a.

be catablished and defined for the highest managenent levels through intennediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appronriate, in the form of organizational charts, functional descriotions of departmental responsibilities and relationshios, sid job descriptions for key personnel pocitions, or in ecuivalent fonns of docunentation. These requirements shall be documented in the USAR.

b.

The Manager - Fort Calhoun Station shall be respttsible for overall unit safe operation std shall have control over those ensite activities necessary for safe operation and maintenance of the plant.

The Senior Vice President - Nuclear Operaticns, Producticn c.

Operations, Production Engineering, and Quality and Environmental Affairs shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical suoport to the plant i

to ensure nuclear safety, d.

The individuals who train the operating staff and those who carry out health physics and cuality arsurance functions may reacre to the aporopriate onsite manager; however, they shall mye sufficient organizational freedcxn to ensure their independence from coerating pressures.

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5.0 ADMINISTRATIVE CONTROM 5.2 or:;ani:ation (Continued) l f.

Administrative procedures shall be developed and i=plemented to limit the working hours of plant staff who perform safety-related funcrions.

administrative procedures shall reflect the personnel whose working hours will be affected.

Shifc coverage shall be =r.intained without routine heavy use of overt 1=e.

The objective shall be to have operating personnel wo k a nor=al 8-hour _ day, 40-hour week while th'e plant is ope:ating.

However, in the event that unforeseen problems require substantial amounts of overti=e to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modifications, on a temporary basis, the guidelines identified in the ad=fnistrative procedures shall be followed.

Deviations from the guidelines shall be authorized by tha Depart =ent Manager, Plant Manager, or their designated alternates,.or higher levels of sanagement, in accordance with established procedures and 1

with docu=entation of the basis for granting the deviation.

Routine deviation from the administrative guidelines shall not be authorized.

5.3 Facility Staf' oualification 5.3.1 Each =e=ber of the plant staff shall meet or exceed the sinimum qualifications of ANSI N18.1-1971 for comparable positions, with i

the exception of the Supervisor - Chemical and Radiation Protection (SCRP) and the Shif t Technical Advisor (STA). The SCRP shall =eet the require =ents set forth in Regulatory Guide 1.8 dated September 1975, entitled "Personnel Selection and Train'ing".

The SCRP is considered to meet the educational and experience qualifications set forth in Regulatory Guide 1.8 with at least five years of experience in applied radiation protection and extansive formal training in radiation protection.

The Shift Technical Advisor shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the 9 ant for transients and accidents.

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g. The Supervisor - Operations, the Shift Supervisors and Licensed Senior Operators shall hold a senior reactor operator license. The Licensed Operators shall hold a reactor operator license.

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QURLITT CONTROL FORT CALHOUN FORT CALHOUN STATION FIGURE TECHNICAL ORGANIZATION CHART 5-2 SPECIFICATIONS Amendment No. M O,35,56,78,84,101 HE pc$tos,0RArin.9 j

5.0 ADMINISTRATIVE CONTR0'LS

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m c-Teni ni n 2 5.4 Training 5.4.1 A retraining and replacement training p

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C_t-hni nd shall meet or exceed the: requirements of Section 7 o1 NFPA Code-A 75, except that the meeting freque'ncy may be quarterly.

55 Review and Audit s

5.5 1 Plant Review Co=nittee (PRC)

Function 5.5.1.1 The Plant Review Cornittee shall function to advise the Manager - Fort Calhoun Station on all matters related to nuclear safety.

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5.51.2 Th 4 ' fi -: : a '.

lant Review Cc =ittee shall he ::.p: ~ -.

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l Alternates 5.5.1 3 Alternate members shall be appointed in writing by the Plant Review Committee Chairman to serve on a temporary basis; however, no more than s

two alternates shall participate in Plant Review Comnittee activities at any cne time.

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Meetinc Frequency

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55.1.4 The Plant Review Committee shall meet at least once per calendar month and as convened by the Plant Review Committee Chairman.

Quorum

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5. 5.1. 5 A quorum of the Plant Review Committee shall consist of the Chairman and four members including alternates.

5-3 Amendment No. 9, 17, 86, 84

5.0 AOMINISTRATIVE CONTROLS Resconsibilities 5.5.1.6 The Plant Review Comittee sh 11 be responsible for:

Review of 1) all procedures required by Specification 5.8 and a.

changes thereto, 2) any other proposed procedures or changes thereto as determinec by the Manager - Fort Calhoun Station to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

Review of all proposed changes to the Technical Specifications.

c.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications e.

and shall prepare and forward a report covering evaluation and recome

, prevent recurrence.to the Division Manager -

t Nuclear

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~.an of the Safety Audit and Review Comit

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. f.

Review of facility operations to detect potential safety hazards.

1 g.

Performance of special reviews and investigations and reports thereon as requested by the Chaiman of the Safety Audit and Review Comittee.

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h.

Review of the Site Security Plan and implementing procedures and shall submit recomended changes to the Chairman of the Safety Audit and Review Comittee.

Review'of the Site Emergency Plan and implementing procedures i.

and shall submit recomended changes to the Chairman of the Safety Audit and Review Comittee.

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j. Review of all Reportable Events.

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5.5.1.7 The Plant Review Comittee shall:

Recomend in writing to the Manager - Fort Calhoun Station approval a.

or disapproval of items considered under 5.5.1.6.(a) through (d) above.

5-4 Amendment No. 3.J3.3A 99

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5.0 ADMINISTRATfVE CONTROLS 5.5.1.7 b.

Rencer deteminations in writing with regard to whether or not eact item considereo under 5.5.1.6(a) througn (e) above constitutes an unrevi afety ouestion.

C\\le.cocWons c.

Provide mediate wri n notification to the Division Manaoer -

Nuclear 4 cal-and the Safety Audit and Review Coninittee of disagreement between the Plant Review Comittee and the Manager -

Fort Calhoun Station; however, the Manager - Fort Calhoun Stat 1on shall have responsibility for resolution of such disagreements pursuant to 5.1.1 above.

Records 5.5.1.3 The Plant Review Comittee shall maintain written minutes of each y::i,nq and copies shall be provided to the Division Manager - Nuclear m ::::.+. a net f.haicman the Safety Audit and Review Comittee.

- Q rcWon 5.5.2 Safety Audit an ev ew comittee (SARC)

Funct1:n 5.5.2.1 The Safety Audit and Review Comittee shall function to provide the independent review and audit of designated activities in the areas of:

a.

nuclear power plant operation b.

nuclear engineering c.

chemistry and radiocnemistry d.

metallurgy e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering

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5-5 knendment No. 9 JS,69,75,86,93,99,101

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i 5.0 ADMINISTRATIVE C0t#ROLS C

5. 5. 2. 8 e.

The Fort Calhoun Station Emergency Plan and implementing procedures at least once every twelve months, f.

The Site Security Plan and implementing procedures at least once every twelve months.

l g.

The Safeguards Contingency Plan and implementing procedures at least once every twelve months.

h.

The Radiological Effluent Program including the Radiological Environ-mental Monitoring Program and the results thereof, the Offsite Oose l

Calculation Manual and implementing procedures, and the Process

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Control Program for the solidification of radioactive wastes at least once per 2 years.

i.

Any other area of facility operation considered appropriate by the Safety Audit and Review Comittee or the Senior Vice President -

I m "ucicar 'r;ducticn, Pr; duction Oper;;icas, Tucis, unu ad iiy

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' A52uiance & Resuloivi, Affair;.

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5. 1.2.9 The Safety Audit and Review Comittee shall report to and advise the i

Senior Vice President - i'ucieec Preduction, Pr:ducti:n Operati:n:. Fueir, I

Med Ou;l i ;j A=aus ence & Rewu ia Lui f Affairs on those areas of responsi-(

bility specified in Sections 5.5.2.7 and 5.5.2.8.

Records 5.5 2.10 Records of Safety Audit and Review Co'hnit, tee activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each Safety Audit and Review Comnittee meeting shall be prepared, approved and fomarded to the Senior Vice President -

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""^ ~ Pred-ciivn, Fivuuctivo Operauuns. Tuuls, and Ou;lity

".:;u,onsu & Reguiatory arrairs within 14 days following each meeting, b.

Reports of reviews encompassed by Section 5.5.2.7e, f, g, h, and i above shall be prepared, approved and fomarded to the Senior Vice I

President - A cico. Prvuuudun, Tceduction Op;r: tion:, "uch. 2"d r_

> Quality,t;urence a Roguietcry "f:i within 14 days following completion of the review.

Audit reports encompassed by Section 5.5.2.8 above shall be forwarded c.

to the Senior Vice Presidaat - Nucicar Produc;;vn, Fivduviivo Opcia-l 7 tions, Iuci;, end Qu;lity t:ur:n : ! Dayl e ry m u s and to the responsible management positions designated by the Safety Audit and Review Comittee within 30 days after completion of the audit.

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gdons, Amendment no. 9,Js,aa,so,76,aA,86,92,101 En s n W A h s% cm3 g g e r g and h d

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5.6 Reportable Event"Action:", -

l 5.6.1 The following actions shall be taken in the event of a REPORTABLE EVENT:

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a.

The Comission shall be notified pursuant to the requirements of 10 CFR 50.72, if applicable, b.

Each Reportable Event shall be reviewed by the Plant Review Comittee and submitted to the Chairman of the Safety Audit F W t+ea the Division Manager - Nuclear

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Qtix.ge.catio ns c.

Submit reports of Reportable Events pursuant to the requirements j

of Specification 5.9.2.

5.7 Safety Limit Violation 5.7.1 The following actions,shall be taken in the event a Safety Limit is violated:

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a.

The unit shall be placed ir T SHUTDOWN within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

l b.

The Safety Limit V 1 i

all be reported to the Division Manager - Huclea

",u' We. nd to the Chairman of the Safety Audit and Review Comittee SARC) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the Plant Review Comittee. This report shall describe (1) applicable circumstances preceding the viola -

tion, (2) erfects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

i d.

The Safety' Limit Violation Report shall be submitted to the Chairman'of the Saf dit and Review Committee and the Division Manager - Nuclea r: r tier ithin 14 days of the violation.

's eco b 5.8 Procedurg 5.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the minimum requirements of sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1.33 except as provided in 5.8.2 and 5.8.3 below.

5.8.2 Each procedure and administrative policy of 5.8.1 above, and changes thereto, shall-be reviewed by the Plant Review Comittee and approved by the Manager - Fort Calhoun Station prior to implementation and periodically as set forth in each document.

5.8.3 Temporary changes to procedures of 5.8.1 above may be made provided:

5-9 Amendment No. S.JS,38,EA,99

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