ML17201N833

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Proposed Tech Specs,Changing Administrative Controls Section 6.0,per Generic Ltr 88-06,to Include Removal of Organizational Figures & Position Change from Radiation Chemistry Technician to Radiation Protection Technician
ML17201N833
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 02/17/1989
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17201N781 List:
References
NUDOCS 8902240142
Download: ML17201N833 (44)
v • d • e


Text

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ATJ:ACHMENT A PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSES DPR-19 and DPR-25 /scl:5428K:14 8902240142 890217 PDR ADOCK 05000237 P PDC DRESDEN STATION UNIT 2 Revised Pages: 6-1 6-2 6-3 6-4 6-6 6-7 6-8 6-9 6-11. 6-12 6-13 6-14 6-16 6-p UNIT 3 6-1 6-2 6-3 6-4 6-6 6-7 6-8 6-9 6-11 ,, 6-12 '6-13 6,-14 ' 6-16 6-17

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  • L r =.: ~*.u ----3
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The shift

T..a~n!:1 fort.he station shall be as shoWT'l in.!at:e 6.1.l.

)iQ_e Assistant Superintendent eratin Operating Engineer~Shift Engineers, and Shift For~~hall have a Senior C7erating License. The Fuel Handlingllifore;nan has a limited Se:ii*:>r :.perating License. Tr.e A!!~!tant 't'iee.

'!"eJ:de.1t !:-.d 5e.. ec !l l!ar.a~er Nuclear 3tatio11s on the
  • or;ora':.e :evel has responsibility for the Fice Protection

_ Frog.:-am. .~. ':-;:e:-ating Er.gi'.'leer at the s*_ation will be*

-espcns~~le for imp:e~ent~tion of the Fi:e Protection Program.

-A (}re brigade of at least.5 ~embers shall be maintafoed. on-sit_e at all - ti:nes. - This e_xcludes the-s~:ift cr-e.w

e*
e$iii:"Y :_:::- s.afe s'huUc~ of t'h-e plar,t a:-.c any per.s~:-,:-.e:
-e*;'.;ire:! :_;:- e;ser.tial f;.;n..:':.:.Jns

.:lurin~ a ::.:-e e:;-.e.:-~er.:y.

i... Q1:.:a::.fi:a:i*:r.s of the.station ::,a~aie~e:--,*. 3-'"'.d o~e:atir.g s:aff shall :r.eet :r,fr,i.::iu;n a.:ceptable* levels -as d~s.:*:-i.:.~t:\\... i.n A.."lS:

lH8.l, "Selection and Training of Nuclear Fewer Plant Personnel," dated March 8, 1971, with the exception of the Ra~ielagieal ~eJl\\ieal ~peevi9ee who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, Sep':.a~ber-, 1975, and the Shift Technical Advisor shal: ~a~e a bachelor-'s deg:ee or equiva:ent in a scientific or e~s~nee:-ing dis~iplir.e with S?ecific :raining in plan: . desi~n and respcnse and analysis of the p~ant for-tonsia:".ts. and acci\\!ents. The individual filling ':.~e position of A39iJt.erit 3::ipHi11le.rdellL - Te'-'111.i1_a1 Se. v1ees shall :11eet the mini.11~ ac.:=;:.-table *level for.. *Technical Ma:.ager" as described in 4. 2. 4 of A.'l S !. N 18. 1 - 19 71. E. Retraining ar.d

eplac~ent tr-aining of Station personnel s~all

'be in acc;,r-*~a~ce..,.i':.h ANSI NJ.8.1, "Sele*:tion and !raini:'lg of '!luc leat" ?*;*er ?lant ?er-sonnel." dated !':arch 8, 1971. 6-1

,,. \\. Insert i A. Onsite and offsite organizations shall be established for the 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. /scl:5428K:l5

1.

Lines of authority, responsibility, and communication shall "be established and defined for the highest management levels throu~h the intermediate levels to and including all operating organization positions. Thes* relationships shall be documented and updated, as appropriate, in the form or organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent fornis of documentation... The requirements shall be documented inthe Quality Assurance Manual or the Management Plan for Nuclear Operations, section 3 Organizational Authority, Activity; section 6 Interdepartmental Relationships.

2.

The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of plant.

3.

The Senior Vice President-Nuclear Operations shall have the 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 support to the plant to ensure nuclear safety.

4.

The individuals who train the operating staff and ~hose who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall sufficient organizational freedom to ensure their independence from operational pressures.

6. 0 A QM IN I ST RA Tl *; :: : ~ 7 P. 0 L 3 ( : ~ n t ' j. : A traini.1'.~ Fc:gca:- f*:r t~e ~ice l;iri!ade shall t<? mai.nt.ain>.?*1 under thr ~:c,.,:*_i*:n cf the ':'r*:*;i*_ing Engin<'"r.111<J slqll n1<'*'l exceed thi::> re1*.ii.re:-.ent.s of ~c;.:t.i-:>n 27 of the !IFPA Code - 197~. except foe fire briga~e train~ng sessions which shall be helJ at least ~~;rt.erly. F. Retrainin~ shall be con~uctej at intervals not exceeding two years. The Revie...., 3nd Investigative Function and the Audit Function

  • activities affecting quality during facility operations shall be constit.~t.ed and have the responsibilities and authoritie outlined ~el-::w:

? c-{ S""i> CY*'>'l'fe V\\d*o1::V

1.

The 6-P?-Yi3-r of the Off-Site Review nd Investigative Functi:-n shall be aFpoint.ed by the ¥i_f! Ft~!id!!nl l!ocl~er Ope~a~i:R9. The ~u~i~ f~nction shall be the responsibility of th'e ~anager of Quali~y Assurance nd shall be indefendent of operations.;' 1.,.,s<,. t ( c.L ) 1

a.

O!f-Site Review and Investi~ative Function Tr. e - o f the 0 ff - S i t e Re *J i e w and Inv es t i g a t i f*.;nc':.ion shall: Cil rrovide~ directions for the revie*.* an1 J.nvestigative foJncUon and appoint a senior-F;rti-:ipant to prov~:!e appropriate dire*ct-ion,c(ii)-- s~~~c':.* eacS F~:-ti:~~a~':. for this r~nc':.i::n, Ciiil sel* a ::~rle~ent ~f Der~ ':.~a~* one participant w~6 c : l le c ~ i *; e l y v~ s s es ~ tack~ r :: u n d a r. ':l, qua 1 if i c a t ions i r. ':.he subject ~atter ~nder review to provide compre-h~nsive interdisciplinary review coverage under th~s function, (iv) indeFendently c-eview and appc-ove the findings and recommendations developed by personnel performing the c-evie~ and investigative function. (v) approve and repoc-t in a ti~ely manner all findings of n*.:nc:::.,pl!.ance with :r;;: re uire:nents and provide reco:-~endations to t~e Station Ha~ager, AsJiStl!nt Vic U \\C.C. t'n::.11.kt'\\t ~ W~ C'pe~'\\~\\"1$ I ~~flA!(Y' fresdeflt e:-d :e:-.ee!I: !!a!".eger !Ll_lesr Ststious, t!!..!~er of Q:Jstit} .l,!:!:J~!ll"l-e, !'ll"ld tnl! Viel! During periods when th* of the Off-Site Review and Investigative F~nction is unavailatle, h~ shall designate this r~sr0nsibili':.y to an established alternate who satisfies t~e for..al training and experience ,, C).Ajl'IS) AS.SlS"'fC\\~1 Ji'c.i:. P'f"C~*de"'l1 (,.,vP) (.2 *.,( '1 h 'T'1 Yt'<15"' m $.;\\ "'d ~~c;,<t. If\\ c.nj ;;.."'d "~~ ~c. (\\\\6..,. V\\ce. p... e~1d e"'1 1'1!.Acle:..r"' ~pcr'\\~toY'lS 3699a 3124A

~~,;~~::~~:.~~~. '~:0:~;;~~*.,.r. of the off-site.Review 6-2 I

Insert ii The Manager of QA/NS rep:>rts directly to the Chief Executive Officer and has the resp:msibility to set Corp:>rate Policy for tx>th the areas of Quality Assurance and Nuclear Safety. Policy is pranulgated through a central pJlicy ccmnittee directed by the rranager of QA/NS. Tiie K:tnager of Q.l\\/NS has the respJnsibility for the p:rformance of p:ricd.ic audits of each nuclear station.

  • and coq:orate depa.rt.m:nt to deter:mine that QA.INS pJlicy is being carried out.

IWWiER STATIClt aJNSTROCTUll SYS TE" POLA SlJIPt.Y MNAGER <<ffRAI l<lfS NtALYSIS MNAGER I ENVIRONflENTAL I NFAIRS MHAGER MTERIALS ANALYSIS MNAGER STAtlON ELECIRICAl ENGINEERING MHAGER

  • ASSISINtl VICE PRESIDENT DIPEC:TM I tlJClEAA LICENSING PRESI~

EXEClJTIVE VICE PRESIOEN1 (CONS1RUC1ION,* PROOUCllON AHO ENGINEERING VICE J'RES IOENT NUCLEAR OPERA110NS ASSISll\\NT

  • VICE PRES IOENT AHO GENERAt 1'1:R.

NUCLEAR STATIONS NUCLEAR STATIONS SlffRIHJENOEHT SIA HON MHAGER ASSIS1AHI VICE PRESIDENT NUCLEAR SEClltlTY OIRECJOO _. Figure 6.1-1 ' OPP!IT! OK~ANllAllON .{)~.£> 6-3 MNl\\GER Of SUPERINTENDENT ONSITE SAFElY & ENGINEERING Sll'PMT OIREClOO Cl' (1.IAllTY ASSlJWfCE (ENGINEERING/ CONS TRUCHON ~ ONSllE SAFEIY ENGINEERING SUPPOOT I ur~uu~n ll DrR-1~ Amendment No. ~. 8£ OPERATION CJJAl HY ASSIJWIC£, MNAGER DIRECTOO Cl' OIREC100 Cl' (JJAllTY (JJAllJY ASSLIWfCE ASSlllAHCt [OPERA HONS] [MINTENAHCt NUCLEAR F~L INSPECT<ll I --- FIRE PROJECTION IHSPEClOO SUPERVISOO

  • AEJIM'ft!lhle FeF Fife Pre,a£li9A P~9Pa111

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ASSISTANT

  • SIJ>ERINTENDENT MINTENANCE STORES SlffRVI S<lt MSTER IEOWUC MST ER INSTIUUT IEOWUC tEOWHCS

\\ STATION fWfAGER I IH~$Uc, hrendTL ~ Ot'R ~I~

  • "°* ¢... ~

~ MSTER ELECTRICIAN / FOREMN ELECTRICIANS ASSISTANT FC~EMN SRO IN** <XWTROL RCXlt so NUCLEAR STATION OPERATOR 0 OPERATOR~ INIXJSTRIAL RELATIONS SUPERVISOR SHIFT FOREMN SO AS~ TRAINING SlffRVISOR STATION SEOJRITY AI>>tlNISTRATOR Figure 6. 1-2 . 1) lli7E: !> GU.TIQN QAGANUATIQN 6-4 SERVICES SUPERINTENDENT RAD (}tEpt I SUPERVISOR L_ I oo:l1sT I PHYSICIST FOREMN J I FOREKAH I I I 0 - Reactor Operator's Lie se TErn STAFF SUPERVISOR Q.C. SlffRVIS<lt SO - Senior Reactor Operator's lcense

  • - Fuel Handling Foreman has SO SO (Limited)

Required only during fuel handl1

    • - ftay be filled by a *sCRE.
      • - Responsible for lrrplementation of Fire Protection Program.
  • 9*

TABLE 6.1. l "INillA.JM SHIFT KAHNlNG ~T (1) CtWOITI~ OF M.JPl!BER OF lllEN IN EA~ POSlTI~ I.JUTS FIRJr lJolIT STA.or '°'- RAD W!TH Fl.U SE~O \\JIIT: THIRD l.JllT SR0(2) R0(3) SCRE ill.:. l'EN Cold Shutdown Cold Shutdown Cold Shutdown 0 5 Above Cold Shutdown Cold Shutdown Cold Shutdown 2 2 5 1 Cold Shutdown Cold Shutdown. Cold Shutdown 2 0 5 TW Above Cold Shutdown Cold Shutdown Cold Shutdown 2 3 5 1 N>ove Above Cold Shutdown Cold Shutdown Cold Shutdown 2 3 1 5 Cold Shutdown Cold Shutdown Cold Shut.dowro 3 0 5 T~E Above Cold Shutcbfn Cold Shutdown Cold Shutdown 2 4 1 5 1 Above N>ove Cold Shutdown Cold Shutdc:Mn Cold Shutdown 2 4 l 5 1 N>ove Above Pbove Cold Shutdown Cold Shutcbtn Cold Shutdown 2 4 5 SRO - Senior Reactor Operator. At least one SRO 111.1st remain in the Control Roan at all times ~en *one or 1TDre units h above cold shutdown. This person may, hOli!ever,

  • --,leave the Control Romi for peri~ not to exc~ 10 minutes, provided another SRO ac_ts as* relief operator. The SCRE or shift s~rvisor can fulfi 11 this requ i l"9l2fl t.

RO - Reactor Operator (For each reactor containing fuel. one RO will be in the Control Roan at all tines.) STA - Shift Technical Advisor. SCRE - Station Control RoaD Engineer (STA with Senior Reactor Operator's License). . ll>N-LIC. - Equiprent Qper*tors.S Equis:-nt Attendants. RAD f£H - Radiation Protection fllen. NOTES: (1) - Shift c~ ccnix>sition may be less than the miniriun requirements for a period of time not to exceed 2 hours in order to accCJllTOdate unexpected absence of on-<Lity shift er~ ~rs provided imrediate action is taken to restore the shHt crew ~sition to within the ~inillll!I requ~renents. (2) - Does not include the licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling. supervising ~E OPERATIONS. (3) - Sha 11 not cperate uni ts on lllhich they are not 1i censed. ADOITIOOL REQUIRU.ENTS

  • A.

SRO can be RO at controls. . B. SRO in Control Roan cannot provide relief to SRO/RO at controls. C. SRO in Control Roan llLISl be in sight of or audible range of operator at all t;me~ or be ;n audible range of annunciators. 6-5

C~E** II >.Jrie, nt Yo. ~, DPR-19 ¥*~ 6.0 ADMINISTRATIVE CON1'ROLS (Cont'd.) 3699a 3124A The responsibilities of the perscr:nel peC"fonning this function are stated below. The Off-Site Review and Investigative Function shall review: (1) The safety evaluations for l/ changes to pro-cedures, equipment or syster.s as described in the safety analysis report and 2) tests or experi-ments completed under the pr~vision of 10 CFR Section 50.59 to verify that such actions did not constitute unreviewed safety questions. Pro-posed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of ~Q1::1alHy Anural"tee. (QA/ tv'D (2) Proposed changes to procedu:es, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59. (3) Proposed tests or experiments.,..hich involve an unreviewed safety question as defined in Section 50.59 10 CFR. (4) Proposed changes in Technic:.: Sfecifications or NRC oper_ating~ licens_~s. (5) =Noncampfi*a-~ce with _require~er.ts, -or of-:- infernal pr 0 c e d \\.Jr es '. 0 r ins t ni c t i. 0 n s ~- ;._*; :. :: ~ :1 u-c !. ear s a : e t y si~nificance, (6) Significant operating abnor..a:itl.es or deviations. from nonnal and expected per:or:nance of plant equipment that affect nuclear safety as ref e~red to it by the On-Site Reviev and Investigative Function. (7) All reportable events repor~able under 10 CFR so. 73. (8) All recognized indications of an uhanticipated deficiency in some aspect of design or operation of safety related str-uctures, systems o* components. (9) Review and report findings and reco~mendations

  • egarding all chariges to the ~enerating Stations Eme*gency Plan prior to i!ll1'l~entation of such changes.

6-6

ORES. lI A.men ent No. OPR-19 ¥** "*Y 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) (10) Review and report findings and recommendations regarding all items referred by.the Technical Staff Supervisor, Station Manager,~A99i9lanl Vice Pte9idenl and General Manager NbteleaF 6tetieA9 and MaAageP ef ~caiit)' A9!ucance.

+A Vf> 'SiJal i ty p

r"l ~o.-is !'.-cl

4c;
,L~S "1 ~.f\\ i The~Audit Function shall be the resp6nsibility of the~---.

,---------, ~MaAa!eli" of ~al Hy A.*1S1.1n1H1e independent of-,_ ___.,_.c c.v' ~ pcodpctioo Department. Such responsibility is .9,.~,-o_fiv~S. 3699a 3124A ~JP Q;al*1y p(C;~(Q11\\~.A(\\J delegated to the PireGt.er ef Q'dality AsSt1FaFtee

  • ~aC'at.~ORi} aRJ\\uia Oili"~t.oC' of Ql.oalHy A.sswFaR"'a
)

(MaiAt.ar:iani;a).

  • l:'I ~.;.le:.v-Q.'"""i~~ f\\<>~**:.~s M:q;cJ~J

""-Either of the above, or designated Corporate Staff or Supet"vis ion approved bY'*nanager-ef Quali l::y A99ttf'8Aee, shall appt"ove the audit agenda and checklists, the find in gs and the t"epor"t of each a*Jd it. Aud its sha 11 be pet"fonned in accot"dance with the Company Quality Assut"ance Program and Procedures. Audi ts shall be perfor.ned to assure that safety-related functions are covet"ed within the period designated below: (1) Audit of tl)e GonfOcnanc*~ of facility operaticn _to - -p~ovl.sions co!'.':.air-.~d within**:he Tech-hical Spe-ci-_ fications~and.appli~able li~anse conditions at least once per year. (2) Audit. of the adherence to procedures, training and qualification of the station staff at. least once per rear. (3) Audit of the results of actions t.aken*t.o correct deficiencies occut"ring in facility equipment., st.ructut"es, systems Or' meth*~ds of operation that affect nuclear safety at. least once per six months. (4) Audit of the performance of activities t"equit"ed by the Quality Assurance Program to ~eet. the. CC"i t.eria of Appendix "B", 10 CFR SO. (5) Audit of the Facility Emergency Plan and implementing procedures at least once per' 12 months. 6-7

6.0 0146W OOHn DRE:>. II DPR-19 ¢ A.11e n . n t ti o : ~, ~, ~ '/ ADMINISTRATIVE CONTROLS (Cont'd.)

c.

(6) Audit of ~he Facility Security P~an and implementing procedures at least onie per 12 months. (7) Audit On-Site and Off-Site reviews. (8) Audit of Facility Fire Protection Program and implementing procedures at least once.per 24 months. (9) The radiological environmental monitoring program and the results thereof at least once per 12 months. (10) The ODCH and implementing procedures at least once per 24 months. (11) The PCP and implementing procedures for solidifi~ cation of radioactive waste at least once per 24 months. (12)

  • ~ -

Report all findings of noncompliance ~ith NRC requirements and recor.:mendations and results of each audit to the Station Manager, the~* Yi~_e PFesiEi~At aA_Ei GeRerel Me~ger: NueJe~f' Stations: !fana_ger

  • of Q\\2a li ti As sunnce,-=-+:he-General Su-pe1"i'rite.1e!ent eE j'.reduetion Syste~!

Analysis, and t.o t"Q VicQ P*es; !?,...* N.. c~ear r Opet al ions. 'J'(l.;:::.-r i Authority C(lC) The Manager of~A~;l.ee reports to th~Sfte.Ho-..... ---.. 1 maA aA4 Pl"e"ideAt. 'Phe ~perwi9er ef t~e gff Site t"hier Review and Investigatiwe Function reports to the £~e~~- ~~ Manager ef Nueleer Safety whe Pepeets te the Cl=laira:an 0 __ ~~,.. and Pns ideAt. 6itfief' H-.e~anager of Quali t)I' QA/Ni> ~T_-__ Ass~f'BAee ev t~e SYfeFvisaF af t~e Off Site Review and lMesti:gative F1:1neHeA has the authority to OC"deI" unit shutdown or C"equest any other action which he dearns necessary to avoid unsafe plant conditions.

d.

Records (1) Reviews, audits and recomtr.endations shall be documented. and distributed as covet"ed in 6.1.G.l.a and 6.1.G.l.b. 6-8

. Insert iii Manager of QA/NS, the Vice President BWR ~ratioris, AVP Quality Programs and Assessrrent, the Senior Vice President-Nuclear Operations and the Chief Op2rating Officer.

Insert iv The AVP Quailty Programs and Assessment reports to the Senior Vice President-Nuclear Operations. The AVP Qua.lity Programs and Assessment has the authority to recaT11End unit shutdcwn or request any other action which he deen.5 necessary to avoid unsafe p~ant conditions. All such disagreerents shall be reported i.rrmediately to the Manager of QA/NS and the Chief Operating Officer.*

OREsA r r knenJ!fnt No. 6.0 ADMINISTRATIVE CC!r.'ROLS (Cont'd.)

  • (2)

Copies of documentation, reports, and correspondence shall be kept on file at the station.

e.

Procedo,.;res (1) Written admin1strative procedures shall be prepared and maintained for the Off-Site Reviews and Investigative Functions described in Specifications 6.1.C.l.a. These procedures shall cover the foll~wing: Content and method of submission of presentations to f ) the"S*Jr"'" 11lsot of the Off-Site Review and \\.... S'°"~'"" 1 c.,..d~ll\\1"J 4 ____ I __ n_v-estigative Function. 0146'W 0014n (2) Use of committees and consultants. (3) Review and approval. (4) Detailed listing of items to be reviewed. (5) Method of (a) appointing peC'sonnel, (b) perfonr,ing reviews, investigations, (c) C'eporting. findings and recorrsend~tions of reviews and investigations, (d) ap_pr_oving C'e~oC't-g, _and (e? ~~i_str..ibuting C'_epoC'ts: (6/ Deter.:-.:.:-.ir.~ _satisfactoc-y completion -~f actic-r. r;;:qui::-ed ba_sed-~n appr-oved f.ind in gs~ anq t"~*:*.;:".r..~:-,d_ati*~r,_;; r-epor~ed'by peC'sonnel per-forming t~e ::-eview and investigative function.

f.

PeC'sonnel (1) The persons, including consultants, performing. the C'eview and investigative function, in addition to the Supec~isot of the Off-Site Review and Investigative Function, shall have axpertise

  • in one OC' moC'e of the follcwing dis~iplines as appC'opriate foC' the subject or subj~cts being reviewed and investigated.

(a) nuclear power plant technology (b) reactor opeC'ations (c) utility operations (d) power plant design (e) reactor enginee~ing ( f) radiolo~ical safety 6-9

CRE:SC;jl I I A.'Tlen~t No. .6.~ ~:N!STRATIVE CONTROLS (Cont*~.) 0146W 0014n (g) Safety.A.r:alysis &ngineeri~g graduate or equivalent with at least 5 years of experience in nuclear engineering. (h) Instr..i::-.e~:t.ation and Control Engineer~~g graduate or equivalent with at ~east 5 years of axrierience in instr.ur.entation and control design an~/or operation. (i) Metallurgy Engineering graduate or equivalent with at least 5 \\ "") years of experience in the metallurgical field. \\ ) u, p n. " 1 o*'ld Pd _i-+-----.\\, (3) The SuperYi3eP of ~he Off-Site Review and Investigative Function shall have experience and training which satisfy ANSI lill8. l - 1971 requirements for plant. managers.

2.

The On-Site Review and Investigative Function shall be supervised by the Stat.i*:>n Manager. The Station Manager. can designate this respons~bility to an alternate who satisfies the ANSI NlB.l (March 8, '...371) experience requirerr,ents for Plant -~Manager. a: Cnsite Review* *an*: :~westi5aU.ve Function The Station Managa~ (or designee) sball*: (i) provide direction for t.he ~eview and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate direction; (ii) approve participants for this function; (iii) assure that a complement of more than one participant who collectively possess background and qualifi-cations in the subject ;natter under review are selected to provide comprete::s:.*1e inter-disciplinary review covera~e under this functi~n; (iv) independently review and approve the findings and recommendations developed by personnel performing the Rev:.ew and Investigative Function; (v) report all findings of ncncompliance with NRC requirements, and provide recorxiendations te tl:le J.,;;6istaRt Viee Fl"e!idetlt and 1 CeReFal Mana!er Nu~lear SlatiQAS aRd tbe iwpervige~ ef the OH Site Re'>'iew !!k!".d In~e!tigati11e Function;* and (vi) submit to the Off-Site Review and Investigative Function for concurrence in a tL~ely manner, those items described in Specification &.1.G.l.a which have been approved by the On-Site Review and Investi~ative Function. &-ll

6.0 ADHINISTRATI'JE CONTROLS (Cont'd.) DR~ II Alne~nt *No. n-.e responsibilities of the persi:.~:.el perfonning this function are stated belcw: (1) Review of:

1) procedures re;~ired by Specifica-tion 6.2 and changes theret~. 2) any other pro-posed procedures OC" changes
~.ereto as detec-mined by the Station ManageC" (or ~esignee) to affect nuclear safety.

(2) Review of all proposed tests ind ex-;eriments that affect nuclear safety. (3) Review of all pC"opcsed changes to t~e Technical Specif i c.ations. (4) Review of all pC"oposed chan~es or modifications to plant systems OC" equipment that affect nucleaC" safety. (5) Investigation of all noncomy:iance with NRC requirements and shall prepa~e and focward a report covering evaluation a~..:! reco..-.mendations to prevent recurrence,te the A!!~~tant Viee Pt eside11t and Oerier-al Har.a~e. !iac_lear-StstiaF1s and tot~ Super-'fi9or-of_U\\e C.ff $ite Revi'e** sAti Irwest:"igeth*e-FuAelieA. . (&~- R~view of tacility 6?e~atic~s te 1etect pot~nt~al safety hazar:d*s. ( 7) Performance of special revi.:*s and investigati*ons

..c--,....:::a:.:..n:..:d:........:c-:..e~p..:o..:r..:t~s the c-eon as requested by the S

-~c ~1. S~peEVi'H~""lrof the Off-Site Review and .l.r\\ rc1 l't\\,~"'°~" Investigative Function. (S) Review the Station Secucity ?lan and shall submit cecoanended changes

    • .~

0 *.. <: c.10Y" 0, ( ".rporate. (9) Review the E:necgency Plan an*~ station implementing pr-ocedures and shall 9u~111i t cecommended changes to the ?i.vis ieFI PeesideAt NYeleaF Stat~Qn~.

  • ~ ;'c_,.; 1'0...,

Sec. 1..tr1...,y ~"'d -+~e !+:JP ~~~ 111 '1 e,.0jt"Ctrrisafld ~'5l:i~'>~mt'"1 '"' l1e:>O' 0,5.,nbv..,"'l'I "' ~ccorcia11c! N1ih (,, J. ~- ~. C.,(1) Ol46W 0014n Review of cepoc-table events ~;d actions taken to prevent cecurrence. 6-12

DRE:& II AJne~en t No. ~, 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) ( 11) Vic.c. Pf'(~' dtrii Review of any unplanned on-9ite release of radioactive material to the environs including the preparation and forw'arding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the AssistaA~ Vi~e Pre~ideR~ aRd CeAeeel Manager N~elear S(atien9, and to the Su~en*i9er-ef the OH 9ite Reoiew &Hd !flve9ti~etive Funetie~. sw~ Vic~ ?Nsid.:\\1\\-; 'bW R Oper" ~*o..,f. 0146W 0014n (12) Review of changes to the PCP and ODCM and major changes to the radwaste treatment systems.

b.

Authority The Technical Staff Supervisor is responsible to the Station Manager (or.designee) and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation and administrative procedures relating to facility operations. The Technical Staff Supervisor shall have the authority to request the action necessary to ensure compliance with

rules, regulations*~ and procedures.wh~n in his op1n1on such action.is ne~essary.~ The Station-Manager (or~

designee) -shaft follow such recomm~n~alions-or select i.course of action that is more co~servative ~egarding safe operation -of the facil_ity.. Ali 5u<:h disagr-ee::nents shall be reported irr.~ediately tc the ~ A**i*tac:i* 1Ji1*e '"Qi;:i~ent. aRd Ceneral MaAagee Uue:eer St.at..i.ORs and the S1:1Jlf' 1<'iserjl of the Off-Site Review and Investigative Function. ct-;p-e-,.,*.... 1'-.--de"'-i)

c.

Records p*ff>"'"'ed ""'d pe.-{o,.fl" .. ~r-E ~ p e C.; ~ \\ ' -" r I () l""I 1.o, 1. !;. * ~ * (.(... (1) Reports, reviews vestigat1ons, an recommendations l be doc~~ented with copies ...._ ____ __.t._.o...__t.._h.........,e,.Assistant Vice President and EJer.e_al ~"'per'"~~:.rt Manger N1:1eleef' StetieA.S, the StipeP¥i9er~he Off-Site Review and Investigative Fun~tion, ~ Statieft M*R*Se-t= (Qr ~es~gAee~ and the ManageF Qf Qdality J.sg~eeneeis:p..vP &v."'l1~'f fre~l"oiW!~... ~d ~~~~,,~ (2) Copies of all records and docwnentation shall be kept on file at the station. 6-13

.( ~RE-II AJne ndroen t No. DPR:~ ~* ?I'*/.

6. 0 ADMINIS:RATIV{ CO.NTROLS. (Cont'd.)

Ol46W 0014n ~. Proceduresi Written administrative procedures shall be prepared and maintained for conduct of the On-Site Review and Investigative Funct.ion. These procedures shall include the follcwing: (l) Content and method of submission and presentation to the Station Manager (or designee), Assistan~ Vi~Q ~:rf ~.. ~,ck.11\\-~-.,,..1--""~ Pt"esideAt and GeAeral Ma!'lageP Nuelear Staeidfl9 _?nd I the Supet"viset" of the Off-Site Review and G w~ Opt1"U jlO~ I Investigative Fune t ion. ~ r ~..... r*e-.-:...,.,ende111t (2) Use of committees. (3) Review and approval. (4) Detailed listing of items to be reviewed. (5) Procedures for administration of the quality control activities. (6) Assignment of responsibilities,

e.

Personnel (l) The pei.-s_onnel performing the On-Site -Review..and* - Investig~tive Function, in addition to the Stati9n Manager <-cir designee), shall consist of ?ersons having expert.ise in: (a) nuclear power plant technology (b) reactor operations (c) reactor engineering (d) radiological safety (e) chemistry (f) instr-umentation and control (g)

nechanical and electric systems.

(2) Personnel perfor.ning the on-Site Review and Investigative Function shall meet minimum acceptable levels as described in ANSI Nl8.l-1971, Sections 4.2 and 4.4. H. Fire Protection.

1.

An independent fire protection and loss prevention program inspection and audit sha 11 be perfor.ned at least once per 12 ~onths utilizing either qualified off-site licensee person~el or an outside fire protection firm. 6-14 I

.\\ DRESI II bPR-l~ A.'tlen. ent Yo. -~, ¥3, ~, I 6.0 .'.DMINISTR.ATIVE CONTROLS (Cont'd.) B. Radiation control procedures shall be maintained, ~ade available to all station personnel and adhered to. These ?rocedures shall sho~ permissible radiation expos~re and shall be consistent with t~e requirements of 10 CFR 20. This radiation pr-otection progr-am shall be organized t*:> :neet the I. requirements of 10 CFR 20.",.

c.
1.

Procedures for-ite~$ identified in Specification 6.2.A and any changes to such procedures shall be reviewed and appr-oved by the Operatin~ Engineer-and the Technical Staff~~~~~, Supervisor in the areas of operation, fuel handling, oc- ~~-... *(,-.:.~,r:: instrument maintenance, and by the Assistant Superinten ent-MaiRtenj~~e and Technical Staff Supervisor in the areas of plant maintenance and plant inspection. Procedures for items identified in Spec~fication 6.2.B and ~ny changes to such procedures shall be reviewed and approved by the Re~ielegieel ~e~ieal Supervisor. At least one person approving each of the above procedures shall hold a valid senior operator's license. In addition, these pr-ocedures and changes thereto must have authorization by the ST"<\\..., ;;11 Feet4ueliaA Qr" SOQ'""i696 :;"7ednt.endent before ':>eing implemented.

2.

'ioiork and instruction type procedur~s '"'hich i:::pJ.ement approved -ma~nt.enance or modification procei:iur_es shall be l e!'."'*1_ 1-1'1~..,,-t,.:.*"'<0 approved and authorized by~_ the.,Assis~a~t Supedn-tend~t1t-' ~aintQn;nc~ where the wr~tten autho~ity has ~ean pr~vided by the Product.ion _Superi:-1t.e,i11fon-t. The "Mairi~:r.ance7 Modificatioh *?rocedure" *Jtilized -for safety re:ated-work shall be so\\appr-oved only if procedures refere~ced in the "Maintenanc~/Modification Procedure" :.ave* 'been. approved as required by 6.2.A. Pr-ocedures which do not fall within the requirements of 6.2.A or 6.2.B may be approved by the Depactment Heads. D. Te..rnporary changes to pr-~cedures 6.2.A and 6.2.B above may be

n.ade provided:
l.

The intent of the ori~inal procedure is not altered.

2.

The change is approved by two members of the plant management staff, at least one of *horn holds a Senior Reactor Operator's License on the unit affected.

3.

The c~ange is documented, revie*,.,.ed by the.On-Site Review and Investigative Function and approved by the ?ee~ueti9A S-.a-norl Me111a~~,. I (Jr ae~*~..,(.~./ -~__,..-- or Sec-..-iees Su~eL"intendent within 14 days of implementation. 0146W 0014n 6-16

  • c"-

V'C..C 6, 0 *. CRE 0.>. l I DPR-U Ar.le. n t !i o. ~, r3, f;>, / ADH:!USTRAT!Y'E CONTROLS (Cont'd.) E. Drills of the emergency procedures described in Specification 6.2.A.4 shall be conduc~ed at the frequency specified in the ~enerating Station ~~ergency Plan. These drills will be planned so that during the course of the year, communication links a~e tested and outside agencies are contacted. 6.3 Action to be :aken in the E~ent of a Reportable Event in Plant 6.4 Operat. i.on ?> ~*ce Pr~.s*d~ll'I-; 8wl\\ D,H'""~'~ Any reportat:e event shall ~e promptly reported to theZAssistaAt Vice ~ce*idQc* and Cenar~l ManageF Nueleap Statiens or his designated alternate. The incident shall be promptly revie~ed pursuant to Specification 6.l.G.2.a(5) and a separate report for each reportable event shall be prepared in accor~ance with the requirements of Specification 6.6.B. Action to be Taken in the Eve~t a Safety Limit is Exceeded

  • If a safety limit is exceeded, the reactor shall 'be shut down irranediately and reactor operation shall not be resumed until authorized by the NRC.

Tr.e conditions of shutdown shall be promptly reported to th ftssis~ant. Vi~e President and CenQral. )4.ar:a~et' Wi.J~:Qat' Stat.i.Qr:s n* l=lis desi~natef! altero.iate. The "~ inc~dent shall be reviewed ?U~suant to Specification 6.1.G.l.a and 6.1.G.2.a and a separate ~eport for each event shall be prepared in accor¢ance with Spec~ifi:;at~-=on 6.&.B. 6. 5 ? l ant. Op e r a t i...,-~ Rec 6 rd s -

  • Ol46W 0014n A.

Records a~d/or logs re:ative*to the-foll:wing it~ms sh~ll be kept in a :i.anner cor.-1e;:ie:;t for review ar-;d shall be r-etained for at

e~st five ye~~s.
l.

Records of normal plant operation, including power levels and pe~iods of opet"ation at each power level.

2.

Records of principal 11.aintenance activities, including inspection and re?air, regarding principal items of equi?=ent pertai~ing to nuclear safe:y.

3.

Records and reports of reportable and safety limit events.

4.

Records and periodic checks, inspection and/or calibrations perfor.ned to verify the Surveillance Requir-e.ments (See Section 4 of these Specifications) are being ~et. All equip~ent failing to ~eet surveillance requirements. and the corr-ecti..ve action taken shall be recorded. &-17 I

6.0 6.1 0141W 0014n DRE-~ III DPR-25 Ame~nt No. ~*.~* y ADMINIS!RATIVE CONTROLS Organization, Review, Investigation and Audit C. The shift manning for the station shall be as shown in Table 6.1.1. Th~ssistant Superintendent~peratinil Operating Engineer1!~ Shift Engineers, and Shift Forem~n shall have a Senior Operating License. The Fuel. Handli~ge Foreman has a D. E. limited Senior Operating License. The Assistant Viee Vice. P"e,,,dc'i'\\t Pre!ideftt and GeAe~al MaRase~ ~ucleac Stations on the corporate level has responsibility for the Fire Protection---=-~----""' Pro5ram. An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program. A fire brig.ade of at least S members shall be mainfained on-site at ail times. This excludes-the-shift ccew necessary io-r safe shi.itdown of the-plant and ~ny-perscrnnet requi~ed for e~sential functi6ns d~ring a fire em~rgency. Qualifications of the station manag~~ent and operating s~aff shall meet minimum acceptable levels as described in ANSI N18.l, "Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, with the exception of the Radielegieal CAe~ieal Supervisor who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory._ Guide 1.8, September, 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of.the plant for trans-ients and accidents. The individual filling the position of AssistaRt~Superintendent TeehAieal Secviees shall meet the minimum acceptable level fot" "Technical Manager'" as desct"ibed in 4.2.4 of ANSI Nl8.l - 1971. Retr~ining and replacement training of Station personnel shall be in accordance with ANSI Nl8.l, "Selection andTt"aining of Nuclear Power Plant Personnel," dated March 8, 1971. 6-1

Insert i A. Onsite and offsite organizations shall be established for the /scl:5428K:l5

  • 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.

1.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through the intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form or organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the* equivalent.forms of documentation. The requirements shall be documented inthe Quality Assurance Manual or the Management Plan for Nuclear Operations, section 3 Organizational Authority, Activity; section 6 Interdepartmental Relationships.

2.

The Station Manager shall be responsible for overall unit.. safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of plant.

3.

The Senior Vice President-Nuclear Operations shall have the 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 support to the plant to ensure nuclear safety.

  • 4.

The individuals who train the operating staff and those wh_o carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, th~y shall sufficient organizational freedom to ensure their independence from operational pressures.

~=- =~--=-~~- DRE9' III Amend.'Tlent Yo. DPR-25 716. 0*? 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) A training program for the fire brigade shall be maintained under the direction of the Operating Engineer and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for fire brigade training sessions which shall be. held at least quarterly. F. Retraining shall be conducted at intervals not exceeding two years. G. The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and Qave the responsibilities and authorities outlined below: """"""'~e,.. :i' Cs Keer i'°\\ t< !"\\den-+~

1.

The Supen*isaF of the Off-Site Review and Investigative Function shall be appointed by the \\!iee PFesideAt Nuelear. OpQcatioc>> The Audit Function shall be the responsibi-GA/NS lity of the Manager of Quality s~h~a~l~l~.._ ______ ___ independe.nt of ope rat ions. I / tV*.Ac.leav-s~~c::-t'f

a.

Off-Site Revie"' and Investigative (Cl.~ (NS} rs' -:=...,-(\\"'I e *...de'"'::;;?-.; '2 "'e !neSupennset' of the Off-Site Review and Investigative Function shall: (i) prov_ide directions for -the ~eview and~investigative function and appoint. a se~ior*participant to provide ~?propriat~ direction, (ii) select each participant for ~his function, (iii) select ~ co~ple~ent of mor~ than ~ne participant who collectively possess background and qualifications in. the subject *matter under review to provide compre-hensive interdiscipli~ary review coverage under this function, (iv) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations to the Station Mar,ager, Assistant Viee Peesident and GeneFal Managee NueleaF StatieR9, KaAaseF ef Quality A9sueaRee, snd the Vice Q.t>./NS, A~~1~itlV1i° Vi<:.<:- Pre.cc,idcY'lt(AVPl PFesi~ent NueleaF GpeFatieAs. During periods when the s~p9FYiseF of the Off-Site Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate who satisfies the formal training and experience requirements for the SupeFvisee of the Off-Site Review and Investigative Func~ion. av..,. 1 l"" '1 p~~ ('Qr'l\\S a. r1" A!>~~>~ r(I ev'\\-t: !4Vld. t~c. 5 e_.'r\\\\c}t v)\\_e p,..es1d-rnt-W 1.1,c. \\ e\\.\\ r C>pera+1ons 0141W OOlAn SI.A p c.r \\\\"\\i'C..V1tieY1t 6-2

*--~ -

'I

Insert 11 The Manager of QA/NS r=-p:irts directly to the Chief Executi*.re Officer and has the resrnnsibility to set Corp::>rate Policy for roth the areas of C)Jality .;'.\\ssurance and Nuclear Safety. Policy is prr-..m.ilgated t.hrougti a central p:>licy ccmnittee directed by Llie rranager of QA/NS. The K3.nager of QA/NS has the resp::msibility for the £=rfonra.nce of p:?rio::iic audits of each nuclear station

  • and coq:orate depa.rtrrent to deteonine that QA/NS p::ilicy is being carried out.
  • ---~::"- -
  • ---:::;......=-_

--*~---- :.._.:;..:._-___ :_. __ _.::__-::-=-::=. ~-=

f'ANAGER S1A1ION aitSTROCllON ASSISTANT VICE PRf.SIOENl ENGINEERING OPERAllONS ANALYSIS MNAGER ENVIRONf'ENlAL AFFAIRS MHAGER MlERIALS ANALYSIS MNACER STATION ELEC1RICAL ENGINEERING twtAGER / ASSISlAHT VICE PRESIDENT STATION 11.JCLUI!_ ENCJINEERING MHAGER DIREC100 tU:lEAR l ICENS INCJ / / EXECU11VE VICE PflESIOEN1 ( COffi HIUC 11 ON, PROO IC 11 ON ANO ENGIN£ERIN<<i VICE f'RFS IOENl MJCl.EAR OJ'ERA110NS ASSIS1AH1

  • VICE PRES IOENl AHµ GENERAL ftGff.

MJCLEAR STAHONS DIVISION VICE PRESIDENT 11.JCLEAR STATIONS REW~lOOY ~s~ lffRINTENIJENT SlATIOH MHAGER ASSIS1AH1 VICE PRESIOENl TEOIHCAL SERVICES MNAGER 11.JCLEAR Fll:L SERVICES MNAGER. * / ~TIOH .--TRAINING OIRECl<J:I RADIATION

  • PROlECTIOH llJCLEAR SE~llY OIRECTCJt Figure 6.1-1 QFF61T8 9R6ANl2ATIBN j) L&'n;£b 6-3
  • -***---~
  • t*

MHAGER (J' NUCLEAR SAFElY SlJ>ER I NTENIJENT (J'fSl1E REVIEW / ,/ _,-*SUPERINlENOENT ONSJIE SAFEIY & ENGINEERING SlFPOOT OIREC1Clt <J' (lJAlJIY ASSllU\\HCE (ENGINEERING/ CO.S lROCf ION OHSllE SAFElY ENGINEERING SUPPOOT L Dresden 11 I lll'l!-?'i _ / Amendment No. JS, Jlf Jin

  • ----*-***----*** -----****-**--**--... -__,...-+-

MNAGER (J' ~ll.lY AS SlllAHC£ - OPERAllON ~LITY AS SlJU\\HCE MNAGER // /'/ OJRECIOO (J' OIRECIOO (J' ~llTY ~llTY ASSIJW<<:E ASSLflAHCE OPERA 1 JCJfS MIN1ENAHCE NJCLEAR FtJ:l INSPECTCJt FIRE PR01ECI JOH INSPECIOO "~... <Dfl.ITER, SPECIALIST

ASSISTANT SlftRINTENDENT KAINTENANCE STCl~ES SUPERVISOO MSTER PEOWUC FOOEHAN KASTER INS TRI.JENT PEOWUC PRODUCTION SUPERINTENDENT ASSIStN(! SlJ>ERINTE.N~ limK PLANNING FOO HAN ELECTRICIANS ASSISTANT SUPERINTENDENT OPERATING SO FlEL

  • HANDLING FOOEMN SRO IN**

roNTROL NUCLEAA STATION OPERATOO 0 OPERATOOS Dresden 111 DPR-*25 SlATI~ ~~R - -~ ____ !_ndnent Ho. ~,~# INDUSTRIAL RELATIONS SUPERVISOO STA** SHIFT FOOEHAN SO TRAINING SUPERVISOO STATION SECllUTY AOtUNISTRATOO Figure 6. 1-2 .D£<.E7e"°6 6TATI8N 0R8ANIZATf6N 4 SERVICES SUPERINTENDENT . RAD <M" SUPERVISOO CH."IST ~LTH PHYSICIST FOOEtwf ~ TECH STAFF SlffRVISOO Q.C. Sl.ffRVISOO O - Reactor ~rator's L1cen~ so - Senior Reactor ~rator's -~nse

  • - Fuel Handling For~n has so ~r'-.SO (Limited Required only during fuel handling*...,
    • - ftdy be f i II ed by a srnE.
      • - Responsible for Int>lementation of Fire '

Protect ion Program. ~-----*------------***-

.A..,. ORESDEJI III OPi-25

  • Am_endment No.

~, 7fa 92 TABLE 6. 1. 1 .. INIIU'I SHIFT MHNING own ( 1) CDIOITICJI a= . tuEER *~ ll£H IN ~ POSITICJI ~ITS WITH FLU FIRST ~IT SECDIO ~IT THIRD ~IT SRQ(2) R0(3) STA or 0-IWl SCRE LIC. '° -sRO RO STA ~ o:..uc. RAD !EN Cold Shutdown Cold Shutcbtn Cold Shutcbtn 0 s lbove Cold Shutcbm Cold Shutcbtn Cold St.utcbtn 2 2 s Cold Shutdown Cold Sh\\Jtdown Cold Shutcbtn 2 0 s N>>ve Cold Shutdown Cold Sh\\Jtcbtn Cold Shutcbtn ~ 3 s lbove lbove Cold Shutcbtn Cold Shutcbtn Cold Shutcbtn 2 3 s Cold Shutdown Cold Shutcbtn Cold Shutcbtn 3 0 5 libove Cold Shutdown Cold Shutcbtn Cold Shutdown 2 4 s N>>ve libove Cold Shutdown Cold Shutcbtn Cold Shutdown 2 4 N>ove libove lbove Cold Shutdown Cold Shutcbtn Cold*Shutdown 2 4 5 - Senior Reactor Operator. At least one SRO 111.JSt remain in the Control.Roan a*t all times llthen one or mre uni ts is apove cc Id shutdotm. This person may, however, leave the Control Roan for periods not to exceed 10 ininutes, provided another SRO ~cts u relief operator. The SCRf or shift supervisor can fulfi 11 this req.Jirenent. .. Reactor Operator (For each rwctor *containing fue 1, one RO wi 11 be In the Contro 1 Rocm at all times.) - Shift Technical Advisor. - Station Control Roan Engineer (STA with Senior Reactor Operator's License). - Equipnent Operators and E~i?Ent Attendants. - Radiation Protection fllen. NOTES:. (1) - Shift crew c:mix>sitlon may be less than the miniaun requiranents for a period of time not to exceed 2 hours in order to accaml>date unexpected absence of on-duty shift ~ tneni>ers provided inrrediate action is taken to restore the shift c~ carposltion to within the minin11n requiranents. (2) - Does not include the licensed Senior Reactor Operator or Senior Reacto~ Operator 1 imited to fuel handl Ing, supervising CXlR£ OPERATIONS. (3) - Sl\\all not operate units on which they are not ltc:ensed. ADOITICWAL REC)JIREfENTS A. SRO can be RO at controls. B. SRO. in Control Roan cannot provide re1'ef to SRO/RO at con~rols.

c.

SRO in Control Roan 111.JSt be in sight of or audible range of operator at all times or be in audible range of annunciators. 6-5

..
..:__ =--=-~

-==-~--.-:::*-.:::-::::_-___ -_.:,. ___ ;:..:_ - __ -._: __ ~.:.:::: _.:,_:;-_*-~-;.;~ ----- ---.....'..::..- -=--.--

DRE~ III DPR-25 Ame-ent Yo. ~* ~*/ 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) OHlW 0014n

~ -=-----::-~*::_~_-._.. "':.

The responsibilities of the personnel perfor.ning this function are stated below. The Off-Site Review and Investigative Function shall review: (1) (2) (3) (4) (5) (6) The safety evaluations for 1) changes to pro-cedures, equipment or systems as described in the safety analysis report and 2) tests or experi-ments completed under the provision of 10 CFR Section 50.59 to verify that such actions did not constitute unreviewed safety questions. Pro-posed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of,Qual.i.ty AsiuFanee. GA/ND Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59 10 CFR.

  • Proposed tests or experiments which involve an _

unreviewed safety question as defined in Section 50.59 10 CFR. Proposed changes in Technical Spe~ifications or NRC operating. licenses. Noncompliance with NRC t"equir-err,ents,* or of inter-nal proce-dur:"es or instructions having nuclear:" safety significance. Significant operating abnormalities or deviations from nonnal and expected per:"fonnance of plant equipment that affect nuclear safety as refert"ed to it by the On-Site Review and Investigative Function. (7) Reportable Events r-eported under:" 10 CFR SO. 73. (8) All recognized indications of an unanticipated deficiency in some aspect of ~esign Ot" operation of safety related stc-uctur:"es, systems or components. (9) Review and repot"t findings and reco~~endations regarding all changes to the Generating Stations Emergency Plan prior to imple.:nentation of such changes. 6-6

~ :._-_!:_ __.::._ 6.0 0141W 0014n DREAJ III DPR-25 AmerZent Mo. ~, ~, 92 ADMINISTRATIVE CONTROLS (Cont'd.) V"K..c Pn:s1:.i'.fl 't (10) 11.WP. 0 ~l'!.~*oll'IS Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Assistant Vice Peesident and CeAeeel HeAege~ Nueleee Stetiens and Manage~ of Qualit' Assu~ance. Audit Function ~UP Qu;.A \\,;y Pro3'f!A"""- al'\\C "s s e. s '!'l t1"I e. n i of the Either of the above, or Supervision approved b)l'!otMeFtegee ef QwalHy A.ssucanc.e, shall approve the audit agenda and checklists, the findings and the report of each audit. Audits shall be performed in accoC"dance with the Company Qual i.t.Y Assurance Program and ProceduC"es. Audits shall be performed to assure that safety-related functions are covered. within the period designated below: Cl) Audit of the Conf<:mni~ce.of facirlty _operation t:o p*ovisions contairied within the Technical S~eci f ications and applrcab~e license conditions at least once per year. (2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year. (3) Audit of the results of actions taken to con*ect deficiencies occurring in facility equipment, stC"Uctures, systems or methods of operation that affect nuclear safety at least once per six months. (4) Audit of the. performance of activities required by the Quality Assurance Program to :neet the Criteria of Appendix "B", 10 CFR SO. (5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 months. 6-7

-*-:....:._-__ ""'.".- --=- ":'...:::~--*~-=--- -- DRE~ III DPR-25 Ame~ent No. Y.,,. ;/', 7/1, ~ 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) 0141W 0014n *

c.

(6) Audit of the Facility Security Plan and implementing procedures at least once per 12 months. (7) Audit On-Site and Off-Site Reviews. (8) Audit of Facility Fire Protection Program and implementing procedures at least once p~r 24 months. (9) The radiological environmental monitoring program and the results t~ereof at least once per 12 months. (10) The ODCH and implementing proced~res at least once per 24 months. ( 11) The PCP and i.mp.lementing procedures for solidifi-cation of radioactive waste at least once per 24 months. (12) Report all findings of noncompliance with NRC requir.ements and recommendations and results of .e.ach aUdi t t~ the Station.Manager, tth* Asa is**\\' tJiee Presit!eAt aAa -CeAeeal MaAageF - lhH:leat" ii'oationio, Managec= of Q11a 1 i ty Ass11i=acce, the Ce.. eral Sureri:nt;:endef'll:: ~ef Peeduetieil Systeffis

  • Allal)'sis,

~rnd te the Viee Pr=esidrmt ~ucl'1ar Jr\\S~r""'t Opera'eiof'ls. c-.. )

  • . LLl Authority The Manager of QttelHy Ass1:1ranee reports to the Ch1e(

E.~(01t-~ "Cnait ma:n and Pr-es ident. The S1:1peFvi.soC' of tbe Off-Site Review and Inuest:igati~e tuAetieA eepeF'os ~o !:he HaflageF ef loh.ieleaC' ~afety who reports to the ~airaaA ana PFe9 ii:!e11t.

  • Either El'1ewManager of 'Quality... QA/W5 hssueanee ee H'le 5ut'er"4isor of t1'1e OH Sit::e RaJiew and lAvastoisa~ive F~AetieA has the authority ~o oc-der unit shutdown or req~est any other action ~hi.ch he deems necessa~y to avoid unsafe plant conditions.

11'1.5~ iJ---..lt.

d.

Recor;ds (1) Reviews, audits and recommendations shall be documented and distributed as cover;ed in 6.1.G.l.a and 6.1.G.l.b. 6-8 -- =---. - --.*:-:.. *:..:.. --. --- =----*-=--: - _.-_- __ *::.... ;,:,.;-:; ___ ~ -----

Insert iii Manager of QA/NS, the Vice President BWR Operations, AVP Quality Programs and Assessrrent, the Senior Vice President-Nuclear Operations and the Chief Operating Officer. - - -* -=---- ---=-.::.*_..!" --* _-_: ':.....__-___ -~--***'==-

Insert iv The AVP Quailty Programs and Assessrrent refX>rtS to the Senior Vice President-Nuclear Operations. The AVP Quality Programs and Assessrrent has the authority to recarrrend unit shutdown 0r request any other action which he deans -necessary.to avoid unsafe plant conditions. All such disagreerents shall be refX>rted irmlediately to the Manager of QA/NS and the Chief Operating Officer. __ ::._.:---...=._:..:: _____. __ -~--

=::~ _:__:_-:_

DRE3. III DPR-25 / A.7ien , n t No. JP, "fl, "JA, ~ 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) 0141W 0014n (2) Copies of documentation, ~eports, and correspondence shall be kept on file at the station.

e.

p-rocedures Written administrative procedures sha11 be prepared and maintained for the Off-Site Reviews and Investigative Functions described in Specifications 6.1.G.1.a. These procedures shall cover the following: (1) Content and method of submission of presentations o e S'lpQC".i.iQF_of the Off-Site Review and Investigative Function. (2) Use of committees and consultants. (3) Revlew and approval. (4) Detailed listing of items to be reviewed.

    • cs>

Method of (a) appointing personnel, (b) perfor.ning reviews, investlgations,_ (c) reporting f indil}gs and r~commendations of reviews and. -_investiga~ions,- (d) approving~*C'epoC'ts, and (e) distributing reports. (6) Determining satisfactory c*~r.:ipletion of act.ion requiC'ed based on approv~d findings and C'ecommendat"ions C'epoC'ted by peC'sonnel peC'forming the Review and Investigative Function.

f.

Personnel (1) The persons, including consultants, perfor.ning the review and investigative function, in addition to the Su~ee~i3er of the Off-Site Review and Investigative Function, shall have expeC'tise in one or more of the following disciplines as appropriate foe the subject or subjects being reviewed and investigated. (a) nuclear power plant technology (b) reactor operations (c) utility operations (d) power plant design (~) reactor engineering (f) radiological safety 6-9

...=."'.:.:.

=- - DRE-N I I I DPR-25 _ // Ame-ent !ilo. ~. f"* ~* ;n 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) 0141W 0014n (g) Safety Analysis Engineer-ing graduate or equivalent with at least S years of experience in nuclear engineer-ing. (h) Instri.lmentation and Control Engineer-ing graduate or-equivalent with at least 5 years of experience in instr-umenta-tion and contr-ol design and/or operation. ( i) Metallur-gy S4 pen'l'\\H <1dQn-t t---. Engineer-ing graduate or-equivalent with at least 5 year-s of exper-ience in the metallur-gical field.

2.

(3) The Super~iser of the Off-Site Review and Investigative Function shall have exper-ience and tr-aining which satisfy ANSI Nl8.l - 1971 requir-ements for-plant manager-s. The On-Site Review and Investigative Function shall be super-vised by -the Station Manager-. The Station Hanaget-can designate this r-esponsibility to an alter;nate who .satisfies the ANSI Nl8. l. (Mar-c:h 8, 1971), Expet"ience R~quir-ements for-Plant.Manager:

a.

On-Site:Revlew an~ Investigative Function The Station Manager- (or designee) shall: (i) pr-ovide dir-ection for-the Review and Investigative Function and appoint the Technical Staff Super-visor-, or-other comparably qualified individual as a senior-participant to provide appropriate direction; (ii) appr-ove participants for this function; (iii) assure that a complement of mor-e lhan one participant who collectively possess background and qualifications in the subject matter under review are selected to pr-ovide comprehensive inter--disciplinary review coverage under-this function; (iv) independently review and approve the findings and r-ecomrnendations developed by personnel performing the Review and Investigative Function; (v) report all findings of noncompliance with NRC r-equir-ements, and provide recommendations te the A99isteAt \\'i~e Peesit!eAt. a.Ad ~ eenec al Manager - Nuclear Stations aud l::he Su-peed.sor e{ the Off Site Review aA~ IRvesti~ative FwRG~ioA; and (vi) submit to the Off-Site Review and Investigative Function for-concur-rence in a timely manner, those items descdbed in Specification 6. l.G.1. a which have been appr-oved by the On-Site Revie~ and Investigative Function. 6-11

...:._;._:~_:-.:. -=----~..:_-:::.__::-*_._

':.... -==-.

...= :__ __ -~*::...: _;;::-_
----=-

=--=- :. -...:....:....._..:._ -

DRE~~N III DPR-25 ~ Ame nt No. ~. 1", 7/1. / 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) The responsibilities of the personnel performing this function are stated below: (1) Review of:

1) procedures required by Specifica-tion 6.2 and changes thereto, 2) any other pro-posed procedures or changes thereto as determined.

by the Station Manager (or designee) to.affect nuclear safety. (2) Review of all proposed tests and experiments that affect nuclear safety. (3) Review of all prbposed changes to the Technical Specifications. (~) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. (5) Investigation of all noncompliance with NRC requirements and shall prepare and f onward a report covering evaluation and reconunendations to prevent recurrence to the AssistaAl Viee President eAd GeAeeal MaAagee N~eleaF StatieR& and to the Supeevi3ee ef t~e Off Site Review aAd ~"Q$t; igatiuQ i'1.1AQt.ieR. -.; (6) Review o( facility operations to d~tect potential safety hazards. (7) Perfonnance of special reviews and investigations ( r ~- and reports thereon as C'eques ted by the _ S\\.\\fHintenden~ S1:1pee.. *isee of the Off-Site Review and ~. Investigative Function. D 1~e._:tor "' (ofporc..-1~ Sec.v<<'~'I "'"'a ~f..e AVV Q1..u.l1"f ~rO~('ams a'fld <l ~~""';,ti"'.,.* on ll'I ~.1.G.. 2. (.(i\\ OHlW 0014n ~~:.........-":..~- ---* -:::'.'

  • -~

~ *-- - -

.~*_:___

--.....:..=.._~--....:. (8) Review the Station Security Plan and shall submit (9) recommended changes to the....*3-9-2~~~-¥~~ Review the Emergency Plan and station implementing procedures and 91'tall 9'2htn1t recommended changes ee tl~e Dh*isieA Viee Pc es id en L-tfuc l eac 3 La Li 011s. (10) Review of reportable events and actions taken to prevent recurrence. 6-12 -~ - ~:...=.._::::_-_:.:.

DRE~ III DPR-25 oh Ame-ent No.~* r. 711,/L 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) (ll) Review of any unplanned on-site release of radioactive material to the environs including the preparation and fonotarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Assistant Viee Pre9ident and

......\\.-__ __,General Manager Hueleaf' Stations, and te the

\\}1u. rr:>~ 1 devrt Super11 isGC" ef Off Site Re*;ie*w and InuesHgath*e &uJR Op({'q 11 <? t1.f:. Fune&ien

b.

(12) Review of changes to the PCP and ODCM and major changes to the radwaste treatment systems. Authori t.y The Technical Staff Supervisor is responsible to the Station Manager (or designee) and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation and administrative procedures relating to facility operations. The Technical Staff Supervisor shall have the authority to request th~ action necessary to ensure compliance with 'rules_, -.regulation-S' _and prccedures wnen i_!l-his opinion .su.ch acti*on is necessary: 'Ole *station Manager (or _ designee)* shall follow such recommendations. or select a course of action that is =more cons_ervat~ve ::-egarding. n Vic~ rreside"'t safe oper~tion o( the facility. All such disagree-ments.shall be r-eported immediately to the i\\ss i3tane Viee Peesident and General Manaser NuclQaC' Stations and the Su~eevisee f the Off-Site Review and

  • 01.nw 0014n

~WI\\ Opera"TI&'~

c.

Investigative Function. ef "i'Tend~.,, "-=-mwo-.~-;:=~~~~~~~-. Records fr<fl"'~~d o."'d pe"ormc.d b,.

~~pE.c..1f1c~~11?1"\\

~.1.(,.. ~- c., (1) Reports, reviews, investi~ations, an recommendations hall be documented with copies ......... ----.,.------~ ~------~.....J to the l Meftegee Off-Site &eetion \\IP a... u.11.,y P~ost'"l....,S Q"'d A11se.~s.l""le.,.,.,s (2) Copies of all records and documenta ion shall be kept on file at the station. 6-13 .=- _____ :;-___ ~-- =-*----~-::_::::.~--- -- -*---~-~-- --~ -=- -~=--~:.* -

DRES-III Amendment No. DPR-25 ?P* 14*/1 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) OlUW 0014n ---=-_::..__ - -_:_ _:-

d.

Procedures Written administrative procedures shall be prepared and maintained for conduct of the On-Site Review and Investigative Function. These procedures shall include the following: ( 1) (2) Content and method of submission and presentation to the Station Manager (or designee), A!!i!tsne Viee Peesi~ene 8nd Geneeal MaAageF WYcl~~r St8tiaR9 and the S~pee¥isa~ f the Off-Site Review and Investigative Function. i-----~--~~--- Use of committees. (3) Review *and approval. (4) Detailed listing of items to be reviewed. (5) Procedures for administration of the quality control activities. (6) Assignment of responsibilities. e--; Personnel.- Cl)

  • The pet"sonnel perfor.ning the. Or.-Site Revie*,.. and rn_:vestigaU.:ve Function, in addition to the Station Manager (ot" designee); shall consist of pet"sons having expertise in:

(a) nuclear power plant technology (b) reactor operations (c) reactor engineering (d) radiological safety (e) chemistcy (f) instrumentation and cont~ol (g). mechanical and electdc systems. (2) Personnel perfonning the On-Site Review and Investigative Function shall ~eet m1n1mum acceptable levels as described in ANSI Nl8.l-1971, Sections 4.2 and 4.4. H. FiC"e Protection

1.

An independent fiC"e protection and loss pC"evention program inspection and audit shall be perfor:ned at least once per

  • 12 months utilizing either qualified off-site licensee personnel or an outside fire protection finn.

6-14 =-- ~-~ -- -*-:.. - - __::_:..=~ *.:: -*

ORES. III DPR-25 Amen.* ent Yo. ~. r I ~/ 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) B. Radiation control procedures shall be maintained, made available to all station personnel and adhered to. These -procedures shall show permissible radiation exposure and shall 'be consistent with the requir~ments of 10 CFR 20. This radiation protection program shall be organized to ~eet the requirements of 10 CFR 20. C.

1.

Procedures for items identified in Specification 6:2.A and any changes to such procedures shall be reviewed and approved by the Operating Engineer and the Technical Staff ,-~ Supervisor in the areas of operation, fuel handling, or / :!<._tc. instrument maintenance, and by the~Assistant Superintendent-I ~inte~an<G) and Technical Staff Supervisor in the a.reas of l plant maintenance and plant inspection. Procedures for items identified in Specification 6.2.B and any changes to such procedures shall be reviewed and approved by the Redielegieal C~emieal Supervisor. At least one person approving each of the above procedures shall hold a valid senior operator's license. In addition, these procedures and change.s thereto must have a*uthorization by the S-tG\\1tOV1'* 0,,. dtsljft'Fr-oduelien et" Sep*,*iees Su-peFiAtendent_ before being implemented.

2.

~ork and instruction type procedures which implement 1 1e _ appro.Y~~- maintenance or rnodif i_cation-.,proce_?ur_es shall be/ de '- approved and authorized by the~Assistant Superintenden.j:.- ~ai~teiiifiillwhere the '"ritten.. authori'ty has been provided y he Pro-duct ion Supet"ir.!::.endent. The "Maintenance/ Modification Procedure" utilized fo* safety related work shall be so approved only if procedu*es referenced in the "Maintenance/Modification Procedure" have been approved as required by 6.2.A. Procedures which do not fall within the requirements of 6.2.A or 6.2.B may be approved by the Department Heads. D. Temporary changes to procedur-es 6.2.A and 6.2.B above may be made provided:

1.

The intent of t~e original procedure is not altered;

2. *.The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

S-to...,'c:i"' Mo...,11~u* dSt~l"lee.

3.

The change is documented, reviewed by the On-Site Review and Investigative Function and approved by the Pr-oduetieA eF*SeFviees SwpeFiAteAdeRt within 14 days of implementation. 0141W 0014n --=* ---= *---= - .:..:.-1 -= 6-16 -=-.__:_ =--- -- -....::: __ _

~-=:...-,:-_ - DRE-III A:wnd..'Tlen t No. DPR-25 ?P ' y'l ' 71'. /1' 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) E. Drills of the emergency procedures descrlbed in Specification 6.2.A.4 shall be conducted at the freq~ency specified in the Generating Stations Emergency Plan. These drills will be planned so that during the course of the year, communication links are tested and outside agencies a~e contacted. 6.3 Action to be Taken in the Event of a Reportable Event in Plant Operation Any reportable event shall be promptly reported Viee PresideAl aAd GeAeral Manage~ Nuelea. Stations or his designated alternate. The incident shall b promptly reviewed pursuant to Specification 6.1.G.2.a(S) and a separate report for each reportable event shall be prepared in a~cordance with the requirements of Specification 6.6.B. 6.4 Action to be Taken in the Event a Safety Li..2it is Exceeded If a safety limit is exceeded, the reactor 5hall be shut down i!lUllediately and reactor' operation shall not be r-eswned until

  • authot"ized by the NRC.

The conditions of shutdown shall be ~W~ OpHQ"i*Ol'I) promptly reported Spec:f icatio~ and a separat:;.e repot"t_ fot" each event shall be-4>*ep.ar-ed in accordance with Specification 6.6.B. 6.5 Plant Operatkng Recot"ds 0141W 0014n -=:; _-:-~-:: - -- A. Records and/or logs t"elative to the foliowing ite.rr.s shall be kept in a manner convenient fot" C'eview a.nd shall be retained* for at least fiv~ years.

1.

Records of normal plant operation, including power levels and periods of operation at each power level.

2.

Recot"ds of principal maintenance ac:ivities, including inspection and repair, regarding pr:ncipal items of equipment pertaining to nuclear safety.

3.

Recot"ds and reports of reportable and safety limit events.

4.

Records and periodic checks, inspection and/or calibrations pet"fonned to verify the Surveillance Requit"ements (See Section 4 of these Specifications) are being met. All equipment failing to meet surveillance requit"ements and the cot"C'ective action taken shall be C'eCOC'ded. 6-17 -=-*~- - - =- --=-: :...- -- --- - ---------=

. -*----=--- - --*-- ---- - -- -

AT:rACBMENT B DETAILED DESCRIPTION AND

SUMMARY

The proposed amendment requests several changes to the Administrative Controls Section 6.0 of the Technical Specifications which include: (1) Removal of Organizational Figures 6.1-1 and 6.1-2,,(2) several position title changes due to reorganization, and (3) a clarification to the distribution requirement for Onsite Reviews. Following is a description of each of the changes.

1)

In accordance with Generic Letter.88-06, we propose replacing the Organizational Figures 6.1-1 and 6.1-2 in Technical Specifications with* more general organizational requirements. These general requirements capture the essence of those organizational features depicted on the figures that are necessary for ensuring safe operation. The proposed revision to the Technical Specifications will require that lines of authority, responsibility and communication be established and defined for the highest management levels through intermediate levels and including all operating organization positions. These relaticinships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities arid relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships. The Technical Specifications are not specifically required to contain organizational figures by 10 CFR 50.36. Organizational figures in themselves do not have a significant s~fety relevance. Howev~r, specific operational requirements that bear more diiectly on safety matters of concern, than organizational figures, are required elsewhere in the Technical Specifications (TS). For example, the organizational element responsible for the control room command function is identified in TS 6.1.C, and the requirements for minimum staffing under various operating conditions is identified in Table 6.1.1. The organizational management functions for review investigations and audits, and onsite and offsite review and investigative groups, and shift technical advisors are also specified in other TS.

2 - The important features identified on the organizational figures, but not currently included in the Technical Specifications as identified by Generic Letter 88-06, have been proposed to be added to TS 6.1.A. The organizational figures in the Quality Assurance Manual or Management Plan are of a level of detail consistent with that shown on the organizational figures in TS. The proposed change will permit changes to the onsite and of fsite organizational structures to be implemented without first obtaining NRC approval through issuance of a license amendment to update the TS. We believe changes to these figures have resulted in processing unnecessary amendments by both Commonwealth Edison Company and the NRC and, therefore, deletion will eliminate needless expenditure of resources for both organizations without affecting safe operation of the plant.

2)

Several places in the Administrative Section 6.0 of TS, position title

  • changes are required due to reorganization.

The title revisions include changing "Assistant Vice President and General Manager - Nuclear Stations"

  • to "Vice President BWR. Operations", and "Vice President - Nuclear Operations" to "Senior Vice President *-

~ucle.ar Operations",. and "Chairman and President" to "Chief Executive Of'.ficer"* and the addition of' the "Assistant Vice President Quality Programs and Ai>sessment". These changes are required to accurately reflect current.organizational titles and functiona,l responsibilities.

3)

Changes are proposed to TS 6.l~G.2 to clarify the distribution requirements of reports, reviews, investigations and recommendations that have been prepared and performed as part of the Onsite Review and Investigative Function. Currently TS 6.l.G.2a lists the responsibility of the Onsite Review and Investigative F~nction. Of the list of 12 items, several specify that recommendations should.be submitted and reports forwarded to specific groups or individuals. However, TS 6.1.G.2c(l) also requires that reports, reviews, investigations and recommendations be d9cumented and sent to several individuals. TS 6.l.G.2c(l) requires distribution to more people than TS 6.1.G.2a. Therefore, to remove any ambiguity, we propose deleting the distribution listings from TS 6.l.G.2a and thereby allowing TS 6.l.G.2c(l) to address the.distribution requirements. /scl:5428K:16-17

A'ITACBMENT C EVALUATION OF-SIGNIFICANT HAZARD CONSIDERATIONS Commonwealth Ec1ison has evaluated this propose.a. amendment and determined that it involves no significant. haz*ards cons.ideration. According to 10 CFR 50.92(c), a proposed ame.ndment to an operating license involves no significant hazards considerations if operation of the facility in accordance with the proposed amendment would not:

1.

Involve a significant increase in the* probability or consequences of an accident previously evaluated; or*

2.
  • Create the possibility of a new or different kind of accident from any accident previously evaluated; or
3.

Involve a*significant reduction in a margin of safety. The proposed Technical Specification amendment requests several changes. The first change involves the removal of organizational Figures 6.1-1 and 6.1-2 and the revision of TS 6.1.A, 6.1.B, and 6.1.C in accordance with the guidance provided in Generic Letter 88-06. The second proposed revision corrects several position titles that changed d~e to corporate reorganization. The third change clarifies the distribution requirements for onsite review documentation discussed in TS 6.2. None of the proposed changes are initiating events for an accident,

  • therefore, the *probability of an occurrence of an accident is not affected.

Even though the organizational figures are being removed, TS 6.1.A is being revised to require the organizational figures, functional ~escriptions of departmental responsibjiities and relationships and job descriptions for key personnel positions be maintained for the Qualfty Assurance manual or the Management Plan for Operations, Sections 3 and 6. Therefore, safe plant operation is not affected and the consequence of any accidents presented in the UFSAR are not imparted by the first change. The remaining changes address organizational ch.anges, and clarification for documentation distribution. All these changes are administrative in nature and the consequences of an accident as described in the UFSAR are not affected.

~*1* .~ v ~J ~

  • l The proposed changes do not revise any functional or design parameters used at the Station.

These changes *do. not* modify any equipment or systems or cause the unit to be operated in.a different manner. Therefore, the possibility of a new or different kind of accident is not created. All the proposed changes are adn)inistrative or editorial and, as such, do not affect any margins of safety. The prbposed organization.changes do not affect safe operation of the plant. Updating position titles, clarifying documentation distribution requirements, editorial and typographical changes, facilitate pla,nt operations but.do not affect safe operations. For the preceding reasons, Commonwealth Edison believes all the changes proposed for the Technical Specification amendment do not involve any significant hazards considerations. /scl:5428K:l8-19

. \\ - - l\\TTACHMENT D SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT Typically onsite and offsite organizations are defined by organization charts included under administrative control requirements of the Technical Specification (TS). This requires the processing of a license amen&nent to change an organization chart before implementing a change in organizational structure. The guidance provided in Generic Letter 88-06 addresses amen&nents that may be proposed for removing organization charts from the a&ninistrative control requirements of the TS. The staff has previously determined that with appropriate changes to these administrative control requirements, the onsite and offsite organization charts may be removed. The changes involve the addition of general requirements that capture the essential aspects of the organizational structure that are defined by existing onsite and offsite organization charts. to Generic Letter 88-06 provides guidance for license amendment requests to remove organization charts from TS. to Generic Letter 88-06 provides an example of this change that was made to the administrative control requirements of the existing Westinghouse Standard Technical Specifications (STS). The staff has found that this change will not reduce plant safety and it is generically applicable to all power reactors. The removal of organizati~n charts is a line item improvement that was proposed on a lead-plant basis for the Shearon Harris plant and was endorsed by the Westinghouse Owners Group. This change was reviewed as part of the NRC's program for improvements in TS. The objectives of that program were establish~d by the Commission's Interim Policy Statement on Technical Specificati6n Improvements. The staff concludes that the removal of organi~ation charts from TS will provide greater flexibility for licenses to implemen~ changes in both the onsite and offsite organizational structure, consistent with Commission policy. Commonwealth Edison has eva,luated the propos.ed amendment against the criteria for and identification of licensing and regulatory actions requiring environment*assessment in accordance with 10 CFR 51.21. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided for under 10 CFR l.22(c)(9). This determination was based on the fact that changes are being proposed as an amendment to a.license issued pursuant to 10 CFR 50. The changes are of an administrat~ve nature only. The.changes involve no significant hazards, there are no significant changes in the types or amounts of off-site effluents, and there are no significant increases in individual or cumulative occupational exposure. /scl:5428K:9

  • ...........:: __ :_ __.:....-..... :.. : *. :.:--~:;...:.... :.: _:....}}
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