ML18022A593

Proposed Tech Specs,Including Tech Spec 6.2.1 Initially Deleted in 870612 Request & Expanding Tech Spec 6.2.2 to Specify Required Operator Licenses for Manager - Operations & Operations Supervisor

ML18022A593
Person / Time
Site:	Harris
Issue date:	12/30/1987
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18022A592	List: ML18022A591 ML18022A593
References
NUDOCS 8801050144
Download: ML18022A593 (7)

Text

IROEX

6. 0 AOMIH'ISTRATIVE CONTROLS SECTION PAGe.

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SHEARON HARRIS - UNIT 1

.xviii

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6;1.1 The Plan: General Hanag r shall be respcnsible for cve.aI) un.'t ace.a-tion and shall delegate in writing the suc=essian tc this respcnsibili y du.

ing his absenc 6.1.2 TheShif Foreman (cr, during his absenc f,m the c"n mi roam, a

designated individual) shall be responsible for. the c"nt.Ir"ca ca~and func ticn.

A marage en direc=ive ta this eifec-> signed by t.".e Vice President-HarHs Huc'.ear P. je shall be reissued tc ail st;an personnel on an annual basis.

6. 2 QRG~iVIZATiOH

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A= Ieas one Iic n ed 0pe.a.

"". shall be in t".e c"n.Ir ~ when fuel i in

".e r ac="r.

In addition, wnile t.".e uni is in,".CQ=" 1, 2,

"., cr'4, a-I+as-cne Iic"nsed 6enicr Opera--r shall b

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natl be cn si~ when fuei is in t.".

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All C"R~ AL>~Ai~QHS shall be observed and d;r ctly supervised by ei~.er a I,icansed 6en;cr Opera

"". cr lian ad 6cnicr Qpera

"", Liai-d t" F ei Handling whc has nc o-".er c"nc...

n-r spcnsib>11ties during t.",is operaticn;~ fY)an cr-gacrah'one rnus~hold P

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re;ui~n~ for a pericd cf time nc t" ax~ 2 hcu~, in order tc acc"~ace date unaxpec

~d absence, pr vided imedia~

ac= cn fs taken ta fill the re-quired positions.

6HEARCH HARRIS - UNIT L

Insert 1

6.2.1 Onsite and Offsite Or anization An onsite and operation and shall include nuclear power an offsite organization shall be established for unit corporate management.

The onsite'and offsite organization the positions for activities affecting the safety of the plant.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an individual executive position (corporate, officer) in the offsite organization having corporate responsibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

C.

There shall be an individual management position in the onsite organization having responsibility for overall unit safe operation and shall have control over those onsite resources necessary for safe ooeration and maintenance of the plant.

Although the individuals wno train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager on site, they shall have sufficient organizational freedom to be independent from operating pressures.

e.

Health physics individuals may report to the appropriate manager on site, however, for matters relating to radiological health and safety of employees and the public the health physics manager has direct access to that on site individual having responsibility for overall unit management.

Health physics personnel have the

'uthority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

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ot FICillAE 6. 2"2

Qualified Safe i Reviewe.s (Ccn inuedi C

These individuals shall have a baccalaureate degree in an engine ring or related field or equivalent, and 2 years of related expe.ienc uch desiana-tian shall include the disciplines or proc dur categories far which each indi-vidual is qualified.

guaIified individuals or graucs nat an the plant swf may he relied u cn ta perform safety reviews 1f sa designated by the Plant Generai Hanager.

6.5.1.<

Safety Evaluations and Aper vals 6.5.3 4.1 The safety evalua ian prepared in ac""r"ance with Spec fication 6.5.1.1.1 shall include a vri~~n de4rmina icn, wi 0 basis, af whether ar no the proc dures ar chanc s thereto proposed t s4 and exper'.ments and changes the~w and mcdificzt-'ons cons<<itute an unrevised safety ques ian as defined in Paracraoh 0.59 af 19 C."-R Par 5Q, or whether they involve a change ta t".e Final Safety Analysis Repar'he Tec."'.nical Spec-'c=-ticns, ar

.e Operating Llcense>>

6.5.1.4.2 The safety evalua-ion shall he pre"ared by a qualified individual.

The safety evaluation shall he reviewed by a second qualified individual..

6.5.1.4.3 A safety evaluation and subsequent review tha c nclude-t",a the s>>" le~ ac=;cn may involve an unrevised safety c~ esticn, a chance ta the Tec."'.-

nicai Scec-

-cz--'cns cr a ~".ance t" ~ e Qce~:inc License, wiII be referred

.".e Plan-Nuclear Safety C"i=~

(PN i".) for ~".eir r view in aces-.-'anc wi 0 Seer f-,ca= an 6.5.2.6.

Ii the PHSC r c-<<dation is t."'.at an i>>~m is an unr vie~ed safe r qua~ ion, a c."'.ance tc

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.".n czI Scar.';ca=.cps, cr a

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g ci c'rcn t, e OcnwaT,'f enate t e ac<<cn

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'IKen~.cn Ay ra>> pi c un<<aI a=-r r view bv t.".e C=-.". ~:a Nuclear Sa-.e.i Se=:a in ac=a-.=-nc" ~--"'. ce;-

I Ic<<>> ~ an 6r <<o<<o>>

6-5.~.4.4 I

a sa a

~ evaiua-;on ard suh eq en-r view c"rciuc that "he suc-je~ ac=;on does no<< involve an unr viewed safe-y q es-;"n, a change tc t.e Technical Soec:

-,cat;on, cr a c."'.area '" t",.e Qperat;ra

License,

".e ac=-an may be approved by the Plan-General Hanacer cr his designe cr, as appiicahle, by the Hanager of the primary func 4onai ar a affected by the a~;cn.

ine individ-ual approving the ac ion shall assure that the reviewers c"Ilec-iveiy possess the background and quali icatian in all af the disciplines nacassary and important to the specific review far both sa. ety and technical aspecw-6.5.I.4.5 A safety evaluation and subsequent review that conclude that the suhjec ac ian involves a change in the Final Safety Analysis Repor>> shall be.

referred to the Corporate Nuclear Safety Sec ian far review in accordance>>th Specification 6.5.3.9, hut implementation may proceed prior to the campleti<<

of that revie~.

6.5.XA.G Qe individual approving the proc dure, tes, or experiment or change thereto shall be other than those wha prepared tNe safety evaluation <<

performed the safety review.

SHFARON HARRIS UNIT 1 6"8