ML17054B185

Amend 65 to License DPR-63,revising Tech Specs to Make Changes to Section 6.0, Administrative Controls

ML17054B185
Person / Time
Site:	Nine Mile Point
Issue date:	10/29/1984
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Niagara Mohawk Power Corp
Shared Package
ML17054B186	List: ML17054B185 ML17054B187
References
DPR-63-A-065 NUDOCS 8411190030
Download: ML17054B185 (54)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No.

65 License No.

DPR-63 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated January 31, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and.

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-63 is hereby amended to read as follows:

84i.ii90030 84i029 PDR. ADOCK,05000220 P' DR

1 (2) Technical S ecifications The Technical Specifications contained in Appendices A and B,'s revised through Amendment No. 65-, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications y

C' c~~~/

Domenic B. Yassallo, Chief Operating Reactors Branch P2 Division of Licensing Date of Issuance:

October 29.',

1984

1 ~

ATTACHMENT TO LICENSE AMENDMENT NO.

65 FACILITY OPERATING LICENSE NO.

DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the following pages:

Existing

~Pa e

iv Revised

~Pa e

iv 245 through 264 The revised areas are indicated by marginal lines.

245 through 266

I

SECT IOtl 5.0 Oesign Features OESCR IPTlON

( nnE 24?

5.1 Site 5 ~ 2 Reactor 5.3 Reactor Vessel

5. 4 Con tainmen t 5.5 Storage of Unirradialerl and Spent Fuels 5.6 Seismic Design

?4?

?42 24?

243 244 6.0 hrhrrinistrati ve Controls 245 O

.6. l Respons-ib i l ity--

6. 2 Organ ization 6.3 Facility Staff qualifications 6.4 Training 6.5 Review arrd Audit Reoortahle Event Action 6.7 Safety Limit Violatiorr 6.0 Procedures 6.9 Reporting Requirements 245 245 251 251 251 259 259 260 260

SECT IOf)

OES CR IPT ION PAGE 6.10 Record Rete'ntion

6. 11 Radiation Prolection Program

6. 12 lligh Radiation brea 6.13 Fire Protection Inspection 6.14 Systems Integrity 6.15 Iodine Monitoring 263 264 264 266 266 266

6. 0 Al)HlNISTRAT I VE CONTROLS

6. I llespons ib i 1 i Ly 6.1.1 The General Superi>>tendent

- Nuclear Generation sliall be responsible f'r overall faciliLy operatio>>

and sliall delegati in writing the succession to Lfiis responsibiliLy during liis absence.

6.1. 2 The Station Sliift Siipervisor - Nuclear (or during his absence from L'lie control

room, a ilesigriateii individua1) shall Iie responsible for tlie control room command fiinction.

A mailagemenl. iiiiecL'ive Lo this eff'ect, signed by the Vice President

- Nuclear Generation sliall be re-issued to station personnel on an a>>>>ua1 basis.

6.2 Org iijzation Offsite 6.2.1 The offsite orga>>ization for facility management and technical support sliall be as sliown o>> Figiire

6. 2-1.

Facility Staff 6.2.2 Tlie facility orga>>ization shall be as sliown on Figure 6.2-2 and:

a.

Eacli on-duty shift shall be coiiiposed of at least the minimum shift crew conipositio>>

sliown in Table 6.2-1.

b.

C.

d.

At least one licensed Operator shall be in the control room wlien fuel is i>> Lhe reactor.

Ouring reactiir operatior).

this licensed operator shall be present aL the controls of Llie fac i 1 i ty.

At least Lwii licensed Operators sha11 be present in tlie control room ihiring reactoi

startiip, sclieduled rnictor shutdown and dur)ng recovery from reactor trilis.

An individual qualified in radiation protectiori* procedures shall be on site when fuel is in tlie reactor.

flic Radiation ProtecLion qual if ii.d individual a>>d Fire Brigade composition may be less Llia>> tlie mi>>iiinim iequiie>>ieiits for a lieriod of Li<<ie not Lo exceed two hours in order to accommodate iiiiexperteil abse>>ce, iiioviiieil immediate actioii is taken to filI Llie requireil positions.

la, J>

1

Facility Staff (Cont'd) e.

A licensed Senior Reactor Operator shall be required in the Control Room duri>>g power operaLio>>s a>>d when the emergency plan is activated.

This may he the Statio>> Shiit Supervisor

- fiuclear or the Assistant Station Shift Supervisor

- Nuclear duri>>g power operatio>>s.

When the emergency plan is activated, the Assistant Station Shift S<<pervisor-Nuclear becolnes the Shift Technical Advisor anil the Station Shift Supervisor - Nuclear is restricted Lti the control room until an additional licensed Se>>ior Reartor Operator arrives.

g ~

n licensed S<.<<for Reactor Operator shall be respons ihle for all

<ao<<e<aent nf new an<i irradiated f<<el within the site boundary.

All core alterations shall be directly s>>pervised by a lice>>snail senior reactor operator who has no other concurre>>t resp>>>>sibilities

~luri>>g this operatior~.

A Licensed Operator will be required to man/pulate the controls of all fuel handling equipment except Aovement of new fuel from receipt through dry storage.

All fuel moves withi>> the core shall be directly monitored by a member of the reactor analyst gro>>p.

A Fire Origaile of five (5) members shall be maintained on site as defi>>ed by 5.l at all times.

h.

Administrative procedures shall be developed and implemented to limit Lhe worki>>g hours of facility staff who perform safety-related functions; e.g.,

licensed Se>> ior Operators, licensed Op>>rators, health physicists, auxiliary operators and key mainte>>a>>ce pers>>n>>el.

Adequate shilL coverage shall'be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while Lhe faciliLy is operating.

llowever, in the event that unforeseen problems require substantial amounts of overtime ho be used, or during extended periods of shutdown for refueling, major maintehance or major plant modifications on a temporary basis, the following guide1ines shall be followed:

The Radiation Protection qualif ied individual and Fire Brigade composition may be less Lha>>

Lhe mi>> i>>nnm requireine>>ts for a period of ti>>le not to exceed four hours in order to acco>><no<late unexpected ahse>>ce, provided immediate action is Laken to fill the required positions.

246

Facility Staff (Cont'ri) 1)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (exclucling shift turnover time).

2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour-periocl, nor more than 24 ltours in any 48-hour periocl, nor more than 7? hours in any 7 clay period (a11 excluding shift, turnover time).

3)

A break of at least 8-hours should be allowed between work. perio<ls (inclucling sliift turnover time).

4)

Except cturing extended shutdown periods, the use of overtime st>outd be considerecl on an indivi<lual basis and not for tl>e entire staff on a shift.

Any deviation from the above guidelines shall be authorized hy the Genera1 Superintendent-Huclear Generation or designee, or higher levels of management, in accordance with estahlisl>ed procedures and with documentation of the basis for granting the deviation.

Controls shall be inclucled in the procedures such that individual overtime sha11 be reviewed monthly by the Station Superintendent

- thtctear Generation or designee to assure that excessive hours have not bren assigned.

Routine deviation from the above guidelines is not authorizecl.

247

Figure 6.2-1 Nine Nile Point Nuclear Station Management Organization Chart President Vice President

()uality Assuranc>>

Seniov Vice President Vice Pres idenl.-

Nuclear Engineering 5 Licensing Vice Presidenl.

Nuclear Generation Genera 1 Super in teniii!>>I.-

Huc lear Generation 5 ta t Ion Super in I.i nylont-Nuclear Generation Iinii.

1 240

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Table 6.2-1 MINIMUM SillFT CREW COMPOS ITION(1) (6)

License Senior Operator Operator Unlicensed(2)

Normal 0~)era tion Shutdown Condition 1(5)

Operation(3)

W/0 Process Cpm~>uter lleacLor SLartups Asst. SLation Shift Supervisor (Shift Technical Advisor Function) l (Senior Operator License)( 7)

I(4)

Notes:

( 1)

At any one time, narc licensed or unlicensed operating peop1e could he present for maintenance,

repairs, refuel

outages, etc.

(2)

Tt~ose operating personnel not holding an "Operator

" or "Senior Operator" License.

(3)

For operation longer than eighL hours without process computer.

(0) llot shutdown condition only.

(5)

An additional senior reactor operator who has no other concurrent responsibilities shall supervise all core alterations.

(6)

The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of tin~e not Lo exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided inun diate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-I.

This provision does not permit any shift crew position to be unmanned upon shifL change due to an oncoming shift crewman being late or absent.

(7)

The Assistant Station Shift Supervisor performs the Shift Technical Advisor function and shall hold a senior reactor operator license.

250

6.3 Fact l i~tSta~f'f ual lFlcat irma 6.3.1 Eacli member of the iiriit staff shall meet or exceed the minimum qiral1fications of ANSI NIA. 1-1971 for conrparahle posiLions, except for the Shift Technical Advisor who sliall liave a liactielnr's degree or equivalerit in a scientific or engineeririg discipline with sprcif'ic training in plarit.

design, and respons(i and analysis of tlie plant for transients and accidents.

6.6 T~rainln 6.4.1 6.4.2 A retraining and relilacement training program for the facility staff shall lie maintained uiider Llie directiori of the Siilierintendent-Training 'Hirclear an(l shall meet or exceed Lire requirements a(Id reconrinendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10CFA Part 55.

A training program l'or tlie Fire Brigade shall be maintained under tlie direction of Lire Superintendent-Trai>>ing Nuclear and Supervisor-Fire Protection, Nuclear aiid shall meet or exceed tlie requirements of Appendix R to. IOCFR50.

6. 5 Aev iew and Audit 6.5.1 Site 0 erations Review Conimittee (SORC)

Fiinc t ion 6.5.l.l The Site Operations Review Corrinittee sliall function to advise Lire General Superint(ndent-Nuclear Generation on all matters related to nrrclaar safety.

Coinpos i t ion 6.5.1.2 Tlie Site OperationS Review Corrrnittee shall be composed of Lhe:

Cha irma(i:

Member:

Member:

Meiiiber:

Member:

Member:

Member:

General Superintendent

- Nuclear Genera'tion Station Superintendent

- Nuclear Generation Technical Superintendent

- Nuclear Generation Superintendent Technical Services

- Nuclear Site Superintendent Maintenance

- Nuclear Supervisor Instrunient and Control -Nuclear Superintendent Chemistry and Aad ia t iori Man aqenieri L 251

R I terna l.es 6.5.1.3 hlternati members shall be appointeii in writing hy tlie SORC Chairman to serve nn a

temporai.~

basis;

however, no more than two alternates sliail participate in SOAC activitii s at any one time.

Hee ting FreiIue~nc 6.5.1.4 The SORC sliall meet at least once per calendar month and as convened by the SORC Chairman.

giiorum 6.5.1.5 A quorum of the SORC shall consist of the Chairman and four members incliiiiing alternates.

Responsibilities 6.5.1.6 The Site Operations Review Committee shall be responsible for:

a.

Review of all REPORTABLE EVENTS.

b.

Review of facility operations to detect potential safety hazards.

C.

Performance of special reviews investigations or analyses

-and reports tliereon as reqiiested by the Cliairman of the Safety Review anil Audit Board.

investigation yf violations of the Technical Specifications anil sliall prepare anil foiiiard a report covering evaluation and recomnendations to prevent recurrence to the Vice President

- Nuclear Generation and to the Chairmaii of the Safety Review anil Rudit Board.

~AU<hori <

6.5.1.7 Tlie Site Operations Review Committee shall:

a.

Ren<ler determinations in writing with regaril to wlietlier or nnt eacl>

iLeiu cons iileieil u>>iler 6.5.1.6 (a) through (d) aIIove constitutes an unreviewed safety qiiestion.

b.

Pr>>vide immediate written notification to tlie Vice President

- Nuclear Gener ation>

a>>il Chairman of the Safety Review and Audit Board of disagreement between tlie SORC ar<<I the General Superintendent

- Nuclear Generation; liowever, tlie General Suii<~rintendent - Nuclear Generation shall have the responsibility for resolution of s<<cl> disagreements pursuant to 6.1.1 above.

Records 6.5.1.8 The Site Operations Review Committee shall maintain written minutes of each meeLinil aiid copies slial1 be provided to tlie Vice President

- Nuclear Generation

<1>>iI Chalrm<ln of tile Safety I(<<view and Audit Board..

6.5.2 Technical Review and Contro1 Activities 6.5.2.1 Eacli procedure and program requ i red by Spec'i fication 6.0 and other procedures whicli affect nuclear safety, and changes

thereto, shall be preiiared by a qualified individual/organization.

Eacli sucli procedure, and changes tliereto, sliall be revieweil by an Indiviilua)/group other than the individual/group which prepared tl>e proceilure, or changes tliereto, but who may be from the same organization as tlie In>livid<<al/group whicti prepared tlie procedure, or changes thereto.

Approval of proceili<res anil programs anil changes Ihereto and their safety evaluations, shall be conLrol led by administrative procedi>> i.s.

6.5.2.2 Proposeil changes to the Technical Specifications sliall be prepared hy a qual ifieil indiviili>>il/organization.

The preparation of each proposed Technical Specifieatin>>s cliange sh;ill be reviewed by an individual/group ottier than the indlviilual/grouii wliicli prepared Ihe proposed

change, but who may be from the same organization as Llu.

indivhl<<il/group which prepared the proposed change.

Proposed changes Lo tlie I'eclinical Specific.it;ions sI>all be approved by the General Sui)erintendent-Nuclear Generatioii.

Activities (Cont'd) 6.5.2.3 6.5.2.4 6.5.2.5 6.5.2.6 6.5.2.7 6.5.2.8 Proposed modifications to unit structures, systems and components that affect nuclear safety

'ba11 be designed by a qualified individual/organization.

Each such modificatio>>

shall Iie reviewed by an individual/group other than the Individual /group which designed the modification, but who may be from the same organization as tlie Individual/group which designed the modification.

Proposed modifications to structures, systems and components and the safety evaluations sha11'be approved prior to impiementation hy the General Superinl..ndent-Nuclear Generation; or the Station Superintendent-Nuc lear Generation:

or the Technical Superintendent-Nuclear.

Generation as previously designatgd hy the Generai Superinte>>dent-Nuclear Generation.

Indivi~luals responsible for reviews performed in accordance with Specifications 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be numbers of the station supervisory staff, previously designated by the Genera) 'Superintendent-Nuclear Generation to perform such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary such review shall he performed by tlie appropriate designated station review personnel.

Proposed tests and experiments which affect station nuclear safety and are not addressed in the I'SAR or Technical Specifications and their safety evaiuations shall he reviewed hy the Gener>>1 Superintendent-Nuclear Generation; or by the Station Superintendent-Nuclear Generation, or the Technical Superintendent-Nuclear Generation as previously designated by the G.>>eral Superintendent-Nuclear Generation':.

The Genei ai Superintendent-Nuclear Generation shal1 assure the performance of special reviews u>d investigations, and the preparation and submittal of reports

thereon, as requested by the Vice President-.Nuclear Generation.

The facility security program, and. implementing procedures, shall.be reviewed at least every 12 months.

Recommended changes sha11 be approved by the General Superintendent-Nuclear Generation and transmitted to the Vice President-.

Nuclear Generation, and to the Chairman of the Safety Review and Audit Board.

The facility emergency

plan, and implementing procedures shall be reviewed at least every 12 months.

Recommended changes shall be approved by the General Superintendent-Nuclear Generation and transmitted to the Vice President-Nuclear Generation and to the Chairman of the Safety Review and Audit Board.

~'SO

ActiviLies (Cont'd) 6.5.2.9 l

The Genej.al Superintendent-Nuclear Generation shall assure Llje per for>nance nf a review l>y a qualified individual/organization of changes to the Radiological Waste Treatjjjej>L systems.

6.5.2.10 Reports documenting each of Lhe activities performed under Specifications 6.5.P.I Lhrn<<qh 6.5.2.9..I>all be maintained.

Copies shall be provided to tlje Vice President-Hjjclear Generati'on and the Safety Review and Audit Board.

F<jnc t ion 6.5.3.1 The Safety

>tevtew and lludit lloard shall function to provide independent review and audit jO of desigj>ated activities in the areas of:

a.

nuc lear power plant operat.ions b.

nuclear engineering c.

chef>ji s try and radiochemistry d.

meL<il lurgy e.

ins Lrumentation and control f.

radiological safety g.

mecljanical and electrical engineering h.

q<<ality assurance practices i.

(oLI>a

~r appropriate fields associated with the unique characteristics of tlje >jj>clear pow

>- plant)

l.'oinpos i t ion 6.5.3a2 The Safely Review and Audit Board shall be composed of the:

Chairman:

Member:

Heinber':

Heinber:

Member:-

Hemher:

Staff Enginrei or Manager or Vice President General Superintendent-Nuclear Generation Staff Engineer - Nuclear Staff Engineer - Hechanical or Electrical

. Staff Engineer - Environmental Consultant (See 6.5.3;4)

Alternates 6.5.3.3 Alternate numbers shall be appointed in writing by the SRAll Chairman Lo serve on a.

tenporary basis;

however, no more than two alternates shall participate in SRAO activities at any one time.

Consultants 6.6.3.4 Consultants shall be utilized as determined by the Sltith Chairnaan to provide expert advice to the SRAI3.

il~t 6.5.3.5

'The SRAD hall meet at least once per six months.

fjuorum 6.5'.3.6

.A quorum of.SRAB shall consist of the Chairman or his designated alternate and a ma.jority of SRAB inembers including alternates.

Ho niore than a minority of the quorum shall have line resl'inis ihility for operation of the facility.

256

Ilev iew 6.5.3.7 The SRAB shall review:

a 0 The safety evaluations for 1) changes to proceilures, equipment or systenis and 7) tesls or experiments completed under ttIe provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

Prop>>sed changes to procedures, equipment or systems which involve an unrevi>>wed saf>>cy question as defined in Section 50.59, 10 CFR.

c.

Proi>I>sed tests or experiments which involve an unreviewed safety question as defined in.'.i.ction 50.59, 10 CFR.

d.

Proi>osed changes in Technical Specifications or operating license.

e.

Violations of applicable statutes,

codes, regulations,

orders, Technical Specifications, license iequirements, or of internal procedures or instructions hav ing nuc lear sa fety s igni fican ce.

f.

Significant operating abnormalities or deviations from normal and expected periormance of'lant equipment that affect nuclear safety.

Iuidits g.

Al I RfPORTAOI.E fVFNTS..

h.

Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures,

systems, or components.

d i.

Repoi Ls and meeting minutes of the Site Operations Review Cone>ittee.

6.5.3.8 Audits of facility activities shall be performed under the cognizance of tho SIIAII.

I'heso audits shall encompass:

. ~

a.

The ronformance of facility operation to all provisions contained within th>>

Tecllnical Specifications and applicable license conditions at'>>ast onc>> p>>r year.

h 257

~ ~,

Aiidits (Cont'd) b.

The lierformance, training and qualifications of the entire facility stafl at least onci. per,year.

c.

The results of all actions taken to correct deficiencies occuring in facility equiliment, structures, systems or metliod of operation tliat affect nuclear safety at least once per six months.

d.

Ttie performance of all activities required by tlie guality Assurarice Prograiu lo meet the criteria of Appendix "8", 10 CFR 50, at least once per two years.

a e.

Ttie facility Emergency Plan and implementing procedures at least orice every 12 moil ills ~

f.

Ttie facility Security Plan and implementing procedures at least once every 12 nionths.

g.

The facility fire Protection Program and implementing procedures at least once per two years.

h.

Any other area of facility operation considered appropriate by tlie SRAB, the Vice Presiilent - Nuclear Generation or the Vice President

- Nuclear Engineering a>>il L icens ing.

<<u~thorit 6.5.3.9 Tlie SRM shall report to and advise the Vice President

- Nuclear Generation and Vice President

- Nuclear, Engineering and Licensing on those areas of responsibility specified in Sectioii 6.5.3.7 and 6.5.3.8.

Records 6.5.3.10 iiecor<is or S<tAII activities shaii be prepared, approved and distributed as indicated halo>>:

a.

Hinutes of each SRAO meeting shall be prepared, approveil anil forwariled to the Vice Pr es iilent - Nuclear Generation and Vice President

- Nuclear Engineering and Licensing within 30 days following eacli meeting.

0

Records (Cont'd)

Reports of reviews encompassed by Section 6.5.3.7 e,f,g a>>d h above, shall he

prepared, approved and forwarded to the Vice President

- Nuclear Genei ation and Vic>>.

President

- Nuclear Engineering and Licensing within lh days following coiniilet,iun of the review.

c ~

Audit reports encompassed by Section 6.5.3.8

above, shall he forwarded to the Vice President

- Nuclear Generation and Vice President

- Nuclear Engineering and Licensing within 14 days following completion of the review.

6.6 Reportable Event Action 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of'ections 50.72 and 50.73 to 10CFR Part 50, and b.

Each REPOAThllLE EVENT shall be reviewed by the SOAC and the results of this review submitted to the SRAO and the Vice President

- Nuc1ear Generation.

6,7 Safety Limit Violation 6.7.1 The following actions sha11 be taken in the event a Safety Limit is violated:

a.

The provisions of 10 CFA 50.36(c)(1)(i) sha11 be complied with immediately.

b.

The Safety Liuiit violatjon shall be reported to the Coenission, the Vice President

- Nuclear Generation an I to the SAM immediately.

c ~

A Safety Limit Violation Report shall he prepared.

The report shall he reviewed by the SORC.

This report shall describe (1) applicable circumstances preceding the violation, (7) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall he submitted to the Commission, the SRAO and the Vice President Nuclear Generation within 10 days of the vio1ation.'59

6.8 Procedures 6.ft.l Written procedure.

and administrative policies shall be established, implrn)ented arid lllallltai>>ed that meet or exce(id the requirements arid recorenendations of Sections 5.1 arid 5.3 of ANSI NI8.7-1()72

~

and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 helnw.-

6.8.2 Each procedure and arfministrative policy of 6.8.1

above, anil changes Lliereto, sliall Iie ievirwed

<llld approved by the G(irieral Superintendent-Nuclear Generation or designee pi ior to iniplenie>>tation. a>>d periodically as set fortii in each document.

6.8.3 Temporary changes Lo procedures of 6.8.1 above may be made provided:

a.

Tlie intent of'he original procedure is not altered.

b.

Tire change is approved hy two numbers of the plant manageinent staff, at least one nf wlinm holds a Sent>>r Reactor Operator's License on tlie unit affected.

c.

The ciiaiige i., documented, reviewed and approved hy the General Superinteiide>>t-Nuclear Generation iir designee witliin I4 days of implementation.

6.9 ReRorti~nne utrenients In addition to tlie applicalil(. reporti>>g requirements of Title 10, Code of Federal Regiilations, the following identified reports sliall be siibmitted to. Lire Oirector of inspection and Enforceiiient Regio>>al Office I, Kirrg of Prussia, Pennsylvania

19406, unless otlierwise noted.

6.9. I Routine~Re

>orts e

a.

Startu Re oi.L.

A summary report of plant startup and power escalation testi>>g slial I Iie siilimitte(

(ii'lowing (I) receipt of an operating license, (2) amendtnenL Lo tlie license involving a I)lanned increase power level, (3) installation of fuel Liiat has a differeiit desig>>

ol Ilas been lllailllfactured by a di fferent fuel supp l ier, and (0 ) mo(l i f i ca t io>>s Lliat inay trave significantly altered Lire nuclear, thermal, or Iiydraulic per forinance of tlie I)lant.

1I)e repoi L

sliall address eacli of the t.ests identified in tlie FSAR and sliall in geiieral iiiclir(fe a description

<<if tiie measured values of the operating coridit.ions or ciiaracter.isLics olitai>>ed during tiie L(.st program and a comparison of tiiese values witt) desig>>

pr edicLiofis arid specificatioiis.

Any corrective actions tliat were required to obtain satisf'actory op(ratioii sf)all also h< ~ described.

Any additional specific (ietails reqiiire> lice>>se coii(liti(ins has(sd on otlier cor(R)iitments slial I be included in this report,.

260

E

6.9.1 Routin~eBe orts ((:<mt'd)

Startup repo) Ls st)all be submitteii within (I) 90 days following cumpleLion'of the start>>i)

LesL progran),

(2) 90 days following resiimption or commencement of cominercial power ope)'aLio>>,

or (3) 9 months following initial criticality, whichever is earliest.

If ti)e SLartlli) Repol't iloes not cover all. Lf)ree events (i.e., initial criticality, completior) of startup test progran),

a>>ii resumption or commencement of cons))ercial power operation),

supplementary reports si)all be submitteii at least every tt)ree monLhs until all three events have i)ee>> comi)leteii.

h.

Annual Occul)ational Ex osure Re ort.

A tabulation shall be submitted on an annual basis wl)ich exposures gri)<)ter than 100 mrem/yr and their associated A)an rem exposuri accordinq Lo.work ai)ii job functioi)s, 1/ e.g., reactor operations and surveillance, i>>se) vire inspectio>>,

routii)e rnai>>tenance, special maintenance (describe maintenance),

waste process i>>g, anil refuel ing.

Ti)e dose assigniu<)>>L to various duty f))nctions may be estimates baseii on pocket iiosimeter, TI.O, or film badge

))))asurements.

Small exposures totaling less than 20K of the iniiividi)al total iiose need not be

)i:counted for.

In the aggregate, at least OOX of ti)e total wiiole body iiose received froi>> external sources sf)all be assigned to specific>>)ajor work fi)ncLio>>s.

c ~

Honthly 0 eratin Re ort.

Routine reports of operating statistics and shutiiown experience

)nc ui)ng ocumentat on of challenges to the safety relief valves or safety valves, shall be submitted or) a monthly basis, wl)ich will include a narrative of operatir)g experience, to the Di) ector, Of) ice of Ha>>agement Information and Program Control, U.S. H))clear Regi)latory Cominission, Washington, O.C.

20555, with a copy to the Regio>>al Office of IEF.,

no later Li)an the 15tl) of i..)ci) month following the calendar month covered I)y Li)e.report.

1/

This tabulation si)))plements the requirements of 20.407 of 10 CFR Part 20.

4

Fire Protection Program Reports a.

Submit a special report to the appropriate Regional Office as follows:

Notify Lhe Director of the appropriate Regional Office by telephone wiLhin 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

Confirm hy telegraph, mai lgram or facsimile transmission no laLer Lhan Lhe firsL work ing day fol I ow ing the even t, and Follow-<

> equipment -to <<n operable status. Unique Reporting Requirements Special reports shall be submitted to the Director of Regulatory Operations Regional Offire within the time period sin.cified for each report. These reports shall he submitted covering Lhe activities identified below lnirsuant to the requi rement.s of the applicable reference specification: a. Reactor Vessel Haterial Surveillance Specimen Examination, Specification 4.7.7(c) (12 mo>>ths) b. Safety Class I Inserv ice Inspection, Specification (See Table 4. 2.6(a)) ( Three monLhs ) c. Safety Class 2 Inservice Inspections, Specification (See Table 4.?.6(b)) (Three months) d. Safety Class 3 Inservice~,inspections; Specification (See Table 4.2.6(c)) (Three mo>>Lhs). e. Primary Cont.~inment Leakage Testing, Specification 3.3.3 (Three months) f. Secondary Co>>lainnant Leakage Testing, Specification 3.4.l (Three months) g. Sealed Source i.eakage In Excess Of Limits, Specification 3.6.5.2 (Three months) 6.10 Aechrd Retention

6. I O. I The following records shal I be retained for at least five years:

a. Records and Ings of facility operation covering time interval at each power level. Records and lugs of principal maintenance activities, inspections, repair and replacement of principal it<<its of equipment related to nuclear safety. C. REPORTABLE EVI.'IIT REPORTS. d. Records of surveillance activities, inspections and calibrations require~i hy these Technical Speci ficatious. e. Records of reactor tests and experiments. f. Records of changes made to Operating Procedures. g. Records of ra<lioactive shipments. h. Records of sealed source leak tests and results. 6.10. 2 Records of annual physical inventory of all source material. of record. The following recoils shall be retained for the duration of the Facility Operating License: a. b. C. Record and drawing changes reflecting facility design modifications made to systems an~i equipment described in the Final Safety Analysis Report. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. Records of facility radiation and contamination surveys. ii. Records of radiation exposure for all individuals entering radiation control areas. 26% 6.10 Record Retention (Continiir<l) J e. Records of gaseous and liquid radioacLive material releaseii to tlie envii.ons. f. Recoriis of li.ansient or operational cycles for those facility components desigiieil for a limilecl nuinber of Lraiisients or cycles. g. Records of tl <lining anil qualification For current members of thie plant sLaff. Records of iii-service inspections performed pursuant to these Teclinical Specifications. I Records of (Iuality Assurance activities required by the gA Manual. j. Records of reviews performed for changes made to procedures or eiluipnient or reviews of LesLs arii exper imen ts pursuant to 10 CFR 50. 59. k. -Records of meetings of the SORC and Llie SRAB. I

6. 11 Radiation Protection Pro ram Procedures for l)ersonnel raiiiation protection sliall be prepared consistent witli Llie reqiiirements of 10 CFR Part 20 and siiall be approved, maintained and adliered to for all operations-involving personnel raiiiation exposure.

6.12 ~lli h Radiation Area 6.12.1 In lieu of the "ciintrol device" or "alarm signal" required hy paragraph 20.?03(c)(?) of 10 CFR 20, each liigli radiatiiin area normally accessible* by personnel in wliicli Llie intensity of railiation is greater than 100 iniem/hr** byt less than 1000 mrem/hr*~ shall be tiarricadeii anil conspiciioiisly posted as a liigii radiatiiin area and 'entrance tliereto shall be controlled by requiring issuaiice of a Radiation Work Peimit in accordance with site approved procedures. Any iniliviilual or groiip of indiviiluals perinitted to enter such areas sliall be provided with or acconipanieii by oiie or niore of Lh following: 3 CD D CD O 6.12 ~llii li Radiation Area (Con tinuril) a. A radiation n>>riitoring device wliich continuously indicates the railiat.ion ilose rate iii Llu! area. b. A radiation monitoring device which continuously integrates ttie raiiiation dose raLe iri.Llie area and a1arms wliiiii a preset integrated dose is received. Entry into such areas witli Lliis monitoring device may be maile aFter the dose rates in ttie area have been establisheil a>>rl personnel liavii been made knowledgeabie of them. C. An individual qualified in radiation protection, witli a radiation dose rate uioniLoriiig iirvice, wlio is respo>>sible for providing positive control over the activities witliiri the area anil shall perform perioilic radiation surveil larice at the frequency specifieii by tlie Raiiiation 1'riitection Supervisor oi ifesignate in the Radiation Work Permit.

6. 12. 2 In addition to tlie requirements of 6.12.1 areas accessible to personnel witli railiation levels siich that a uiajor portiiin of the body could receive in one hour a iiose greater tlian 1000 mrem*" shall be provided witli lockeil doors to prevent unauthorized entry, and tlie hard keys or access proviiieii by magnetic keycard slial1 be maintained uniler the ailministrative control of.tlie Station Sliift Supervisor or designate on duLy and/or tlie Radiation Protection Supervisor or designate.

Ooors slia11 iemain locked except duriiig periods of access by personnel under an appioved RWP whicli slia11 specify in accordance with siLe approved procedures accordingly, tlie dose rate levels iri the ioiinediate woik area and tlie maximum allowable stay time for individuals in that area. In lieu of tlie stay tinie specificatiori of Llie RWP, continuous surveillarice, direct or remote, sucli as use of closeil circuiL TV

canieras, may be made by personnel qualified in radiation protection proceilpres to proviile positive exposure control over the activities within the area.

for individua1 areas accessilile-to personnel with radiation levels such that a major portion of the body coulil receive in one lioiir a ihise ili excess of 1000 mrem*" tliat are located within large areas, sucli as tlie drywell, wliere no enr.losuie exists for purposes of locking, and no enclosure can be reasonably constructed around tlie indiviilual

areas, tlien that ai ea sha11 be roped off, conspicuously posted and a flasliiiig liglit sliall lie activated as a warning device.

by accessible passage and permanunL'Iy fixed la(lders IlleasurcllK.'nt maile at 18" from soiii ce of raiiioact i v ity 265 6.13.1 6.13. 2 An independent fir>> protection.and'loss prevention inspection anii audit shall he performed an>><<ally utilizing either ii<<alified off-site licensee personnel or an outside fire protection fir<<i. An inspection and audit by an outside qualified fire consultant shall he performeii aL intervals no greater than 3 years. 6.14 Systems Inte~ri t Proceiiure shall be establislied, implemented and maintained to meet or exceed the requirements anil recommeniiations of Section 2.1.6.a of NUAEG 0578. 6.15 iodine Non i torso I'roceiiures shall be establis!ied, implemented and maintained to meet or exceeii the requiremenLs anil recommeniiations of Section 2.1.8.c of NUREG 0578. F66