ML19275A043

Amend 40 to License DPR-16,revising Administrative Controls

ML19275A043
Person / Time
Site:	Oyster Creek
Issue date:	08/06/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:
Shared Package
ML19275A044	List: ML19275A043 ML19275A049
References
NUDOCS 7908300621
Download: ML19275A043 (21)

Text

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[o UNITED STATES g

NUCLEAR REGULATORY COMMISSION yg p,

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DOCKET N0. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 40 License No. DPR-16 1.

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

A.

The applications for amendment by Jersey Central Power & Light Company (the licensee) dated April 10, 1979 and June 15, 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, 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.

2032 09 7 90g g g Qbp \\,

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. 2.

Accordingly, the license is amended by changes to the Technical Speciff cations as indicated in the attachment to this license amendment, and paragraph 3.B of Provisional (perating License No.

DPR-16 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 40, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

(**

M Dennis L. Ziemann, ief Operating Reactors Branch #2 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: August 6,1979 2032 0G6

ATTACHMENT TO LICENSE AMENDMENT NO. 40 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET N0. 50-219 Replace the following pages of the Appendix A with the enclosed pages.

The revised pages are identified by the captioned amendment number and contain margir,al lines indicating the area of change.

PAGES 6-1 6-2 6-2a 6-2b (new page) 6-3 6-4 6-5 6-6 6-7 6-8

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6-9a 6-9b 6-9c 6-10 6-11 6-28 6-29 (new page)

• includes only an editorial change 2032 057

ADMINSTRATIVE CONTROLS 1

F.E3PZS:SILITY

.1 Tne Station Vanager shall be responsible for overall facility operation and j

shall delegate in writing the succession to this responsibility during his ab sence.

.2 CRGA":ZATION rFSITE

.2.1 Tne Offsite crsanization for facility management and technical support-shall be as shown on Figure 6.2.1.

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.2.2 freility organization shall be as shown on Figure 6.2.2 and:

T.5 Each on duty shift shall include at least the shift staffing indicated on..

a.

Fli;ure 6.2.2.

le=st one licensed operator shall be in the control room when fuel is in b.

At

he re20 tor.

licensed operators shall be in the control rocm during all reactor O.

Tw stir;u, s, shutdown s, and other periods involving planned control rod mar.ipulations.

ALL CORE ALTERATI0:.~S shall be directly supervised by either a licensed d.

Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who Senior has no other concurrent responsibilities during this operation, individual qualified in radiation protection measures shall be on site e.

Ar.

ten fuel is in the reactor.

all time.

A Fire Brigade of at least 5 members shall be maintained onsite at f..7e r re Erigade shall not include the minimum shift crew necessary for safe shutcown cf the unit or any personnel required for other essential functions durir-a fire emergency.

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.::*_:TY "T*r C'J '.LIFICATIONS 203z U58 m

er exec d the following Tc+

. embers of the facility staf f shall n,eet Amendment No. 29, 40 6-1

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. u.:cr *:cnager D

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uire.ents:

Ten years total power plant experience of which th 2e years m;st

..u: lear po'.nr piar.t experience.

A maximun of four years of academic trair.ing f.' fill four of the remaining seven years of required experience. Tne

a:icn ' anager must be capable of obtaining or possess a Senior Eeac:.or

. -rnor's License.

_ cit Superintencent

quirements:

Eight years total power plant experience of which three years

s

be r.uclear power plant experience.

A maximun of two years of academic or els:cd technical training may fulfill two years of the remaining five years of ec.uired experience.

The Unit Superintendent must be capable of obtainir.3 or p:ssess a Senior ficactor Oparator's License.

21~.r.t Sucpert Superintendent Escui e.cnts: ' Eigh. years of responsible positions related to power generation,

f..icP tb ee yctrs shell b2 nuclear pouar plant experience.

A mcximun of four

f the remaining five years of experience may be fulfilled by satisfac.ory

plc icn of actdsmic cr relcted techr.ical training.

ircc:cr cf Staticr L.d:'.inistrction

e:cire:r.ents :

Ei3ht years total pcuer plant experience of which four years must

.cVe been spent in nuclezr power plant experience.

The Cirec cr of St:-ion 2 or equivalar. in A:r.inistration should possess a four yecr college dc3r:

O sin ss i.dministration or an Engineering discipline.

I : ervis:r Stnicn Operatiens

-;uir=n nts:

Eight years tots 1 power plant exoerience of 1:hich three f:srs

s. te nuclear power pitr.t experience.

A mEximum of tuo yecrs of academic or eland.echnical training may fulfill tuo of the remaining five years of ec.:irca a p2 -ience.

Tne Soparvisor Staticn Operations must pcssess a Senicr

2acter Cperator's License.

Ir.agea cr.t Cor. trol Supervisor

.e cuir e:aents :

Eight years total power plant experience of which three years us:. 52 r.uclear power plant experience.

A maximun of two years of academic or

~ 1=.cd technical training may fulfi11 two of the remaining five years of

_ c. ir d ex perience.

Tne Management Control Supervisor must possess a Ser.ior

- :a::cr Cp:rator's License.

e:tr. ice'. Supervisor (Reactor Engineering and Physics) l

in of ini:ial ::re lor.dir.; or appoir.tment to the posi.izn,..hiche. :- is

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r-esponsible persor shall have Bach 21or's 2 Gree in Engineerin or i cl Sci:.;es ar.; fcar years cxperi:nce or

t. Gr juc.:- darce :.c :

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m : -icr. e.

T r, cf :n2se yecrs shall be :ualecr po;;2r plcn e x pe r ie'. : 2.

2039

%"9 Amendment No. 70, 25, 6-2

Tne exp2rience shall be in such areas as reactor physics, core messurements, cer<.. cat transfer, and core physics testing progrz:ns. Successful ecmpletica of a ru.ctor engineering training program (such as the 12 wee,< concentrctec grogrt.ms offered by USS Vendors) may be equiva ent to one year's nuclecr power l

plan experience.

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o Supervisor Station Mechanical Maintenance ew 6

Fequirtments:

Seven years of total power plant experience cf which one ye.r t

.ust be nuclear powsr plant experience.

Tuo years of accdemic or rela ca tecPnical training may fulfill two of the remtining six years of requirec exp3rience.

Suoerviser Station Instrument & Electrical Maintenance Five years of experience in instrumentation and control, of which Requirements:

3 minimum of one year shall be in nuclear instrumentation and control at an operating nuclear power plant. ' A maximum of four years of this five year experience may be fulfilled by related technical or academic truining.

Eng neering Supervisor The engineer in charge of technical support shall have a Bachelor's Cegree in

~Er.ginc:rin; cr th? Physical Sciences cnd have three years cf pr:fessicnal level experience in.nuclecr services, nt. clear plant operation, or nuclear enginering, unc.tne necessary Overall nuclear background to determine..en to ecll censul, ants and cor.tracters for cealing with ecmplex proble s beycnd the scope of ouner-crganization expertise.

Superviscr ricolth Physics F.e quir eme nt s : Eachelcr's degree er the equivelent in c science Or engineering cucjcet, including semc formal trcining in rtdiation protection.

Five' years of professional experience in applice radia-ion protecticn.

J. aster's cegree egnnien, to one year exparience and Doctor's degree equivalen:

.o two years exp;rience where coursework relatec to radiation protecticn is involved.) Tnrce ynrr cf,his professional experience should be in applied rcdit-icr protecticn

.:c r ? _n c nuclsar facility dealln;. ith radiological problems similar tc those encountered in nuclesr pou2r stations.

Chemical Supervisor Requirements:

Five years experience in chemistry of which a minimum of one year shall be in radiochemistry at an operating nuclear power plant.

A maximum of four years of this five year experience may be fulfilled by related technical or academic training.

u.....u 2032 0^0 4.41 A retraining progran for operators shall be maintained under the direction of the Director of Station Administration and shall.ee the equirenen,s snt ecommend etien of Appsn;..x i. of 10:FF ?crt 55 a;1c:r en..rcining prcgrz..s, ne content of which snall meet.he requiremer.:s cf F?. rt 55, shzl1 be Ocncuc.ed un cr the direc-ice of M : Director cf S.2.icr i Linis..et 2n, er icanced ccerc.ces end fenior Ecceter 'perctors.

Amendment No. U, 40 6-2a

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j. training progrcn for ohe Fire Erigade shall be maintained under the direction of the Cirector of. Station Administration.

5 SAFETY REVIE'<? A':D AU' IT D

The Stction Mantier and three organizational units, the Plant Cperations Rcview Dr.ittee (PORC), the Independent Safety Review Groups (ISRG) and the General Cffice Review Board (GDRE) function to accomplish nuclear safety review and sudit of the Cyster Creek Station.

[3 [$ddkm 2032 061 6.2b Amendment No. 40

PRESIDENT

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GENERAL OFFICE DIRECTOR VICE-PRESIDENT REVIEW BOARD (G0RB)

MATERIAL PERSONNEL & SERVICES MANAGEMENT VICE-PRESIDENT GENERATION INDEPENDENT SAFETY REVIEW GROUP (ISRG)

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MANAGER

}!ANAGER MANAGER MANAGER MANAGER ASSISTANT MANAGER ENVIRONMENTAL GENERATING GENERATION GENERATING OPERATIONAL VICE-PRESIDENT

'lENERATION AFFAIRS STATIONS ENGINEERING STATIONS QUALITY GENERATION ADMINISTRATION FOSSIL /IlYDRO NUCLEAR ASSURANCE SUPERVISOR NUCLEAR SAFETY DIRECTOR

& LICENSIN(;

CENERATION CONSTRUCTION, Y

MAINTENANCE &

CONTRACTOR y

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MANAGER (ON SITE) p E?e.)

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c Amendment No. JD, J7, 40 hd 6-3 D

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'6-4 Amendment No.10, 40

.5.1 Station Manager qm m

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. 5.1.1 The Station Nnager shall ensure that:

proposed changes to equipment or systems have been evaluated to a.

All determine if they constitute a change to the facility or precedures as described in the Safety Analysis Report, All propo. sed changes to equipment or systems that constitute a change of the b.f acility or procedures as described in the Safety Analysis Report have been evaluated t<:) determine whether they involve an unreviewed safety question as defined in paragraph 50.59, Part 50, Title 10, Code of Federal Regulations.

All proposed tests and expcriments have been evaluated to determine whether c.

they involve unreviewed safety questions as defined in paragraph 5C.59, or not Part 50, Title 10, Code of Federal Regulations.

ACTHORITY 5.5.1.2 Tne Station./ nager has the authority to:

'2

ake a deternination as to whether proposed chstges to equipment, cr systems a.involve a change to the procedures or facility as described in the Safety Analysis Report.

ake a determination as to whether or not proposed tests or experiements and b.

changes to equipr.ent or systems involve an unrevie.:ed safety question.

Direct the Plant Operations Review Committee to revie: safety evalutions of c.proposed changes to equipment or systems and safety evaluations of proposed tests and experiements to determine whether or not such changes, tests or experiments involve v~eviewed safety questions.

NOTE:

Each determination that a proposed test, experiment, or change to a system or equipment that does not involve an unreviewed safety question shall be reviewed by the Independent Safety Review Groups to verify that the determination was correct.

This review shall be documented but is not a pre-requisite of the test, experiment, or change to a system or equignent.

ECCRCS Ny strety evaluations done in accordence i:ith C.5.1.1 'b) and (c) and cny de termin ati3r.s made pursuant to 6.5.1.2'b) must bc door.ented.

Copies of thes, deternir.rtions shril be proviced to the ISRG Co er d ir. a tc r and the Chairm:n of

.he Gsneral Cffice Revieu Board.

Records of all tests ar.; experiments perfc~ed c.; LH c.

nges to equipment or systems r.ade undcr.h3 pro. _siens of 10 CFF F rt 2032 0A4 6-5 Amendment No. JD, J7, 40

50.59 shall also be maintained at the station.

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.5.2 Plant Operations Review Committee (PORC)

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. 5. 2.1 Tne PDRC shall function to advise the Station Panager.

~~,FPOSITIO!1 E.5.2.2 The PORC shcIl consist of the following plant personnel:

Unit Superintendent Management Control Supervisor Engineering Supervisor i

Plant Support Sup3rir.tendent Health Physics Supervisor Tne. Station !'anager shall designste the Chairman and Vice-Chairman frc:

among the PORC members.

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Alternate members shall be appointed in..riting by the PORC. Chairman and will have the type of experience and training rec.uired of regular members.

However, they need not have the extensive longevity in the desigr.ated fields as long as in the opinion of the Chainnan, their experier.ce and judgement are adequate.

-EETI::3 FREQUEllCY i.5.2.4 The PCRC shall meet at least once per calendar month and as convened by the PORC Chainnan or the Station Manager.

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" quorun of the PORC shall consist of the Chair.an or Vice Chairman end three m er:ber s/ v' t ern ates.

"o more than tw: citer.r.te members shall be counted in establishing a quorun.

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The responsibilities of the PORC are included in Table 6.5-1.

2032 065 Amendment 110. 70, 77, 40 6-6

O' Y b

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un mMAA e

D THCFITY

. :.. c. ;

Tne PGRC shall be advisory to the Station .anascr.

Nothing herein shall relieve the Station Manager of his responsibility or authority for overall a.

De terminations safety operations including taking immediate emergency action.

on Items a and b of Table 6.5-1 shall be docunented in writins.

The PORC 01 airman shall immediately notify the Panager, Generating Stations b.- "uclear and the Chairman of the GORB of any disagreements between the PORC and However, the Station Panager shall have the responsibility l

the Station Panager.

for resolution of such disgreements pursuant to 6.1.1.

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.c.c.-

~he PORC shall mainto a written minutes of each -ectin; and copies of minut'.s ar.d detenninations shall be provided to the Station Fanager; L' nager, Generating l

cations-Nuclear; ISEG Coordinator and the Chairman cf the GCR3.

. 5.3 Ir.cependent Screty Review Groups (ISRG) 3 CTIC:! -?D C0FPOSITIOlj

.5 3 1 The ISRG shall function under the direction of an ISE Cecrdinator, who shall be "Ihe appointed by the Vice President-Generation, to provide safety reviews.

Coordinator shall have available the competen:e to review problems in the following crea:

a.

Nuclear Pow 2r Plant Operations b.

Nuclear Engineering Chemistry and Radiochemistry c.

d.

Metellurgy Instrunentation and Control e.

f.

Radiological Safety Mechenical and Electrical Engineering g.

h.

Quality Assurance Practices The Coordinator shall establish, as needed, groups of two or more individuals with the expertise required for each tcpic to be reviewed.

I;.sd tr.:s shall be u ilized as necessary to suc;.menc -hc expertisc :<2.ilac'.c ir the Co gany.

2032 046 6-7 Amendment No. 70, J7,40

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.-.:.2 Tne specific responsibility to ensure accomlishment of independent safety review of the Station anager's determinations involving screty ousstions is assi;ned l

to the ISRG Coordinator and is accomplishd by utilizir.3, as.5:essary, th: full scope of expertise available in the generation department staff, consultants, contractors and vendors as appropriate.

Table 6.5-1 defines the specific independent safety review responsibilities.

.UT'-:ORITY

. 5. 3. 24 The ISRG advises the Vice President-Generation It has the authority to conduct reviews and investigations, which will be docr ented.

'.CITS

."D. >J. C s

Audits of facility activites shall be performed under the ac;nizance of the

antser, Operatiencl Cuality Assurcnce.

Tnese audits shall er.:ompass:

a.

Tne conformance of facility operation to all provisions c:ntained within the Technical Specifications and applicable license conditions at least once p=r yecr.

The trainir.g and qualifications o[ the entire facility staff at lesat once b.

par year.

c.

Be results of all actions taken to correct deficiences c: urring in faciliy ecuipnent, structures, systems or method of operction that affect nuclear safety at least once par six months, d.

Tne Facility E tergency Plan cnd implementing procedures at least once per two years, e.

Be Facility Security Plan and implementing precedures at least once per two

years, f.

f.ny other area of facility operation considered appropriate by the GORB or the Vice President-Generation.

_C 'EDS

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"i:.-- docunent: '.ics cf all indep?ndent ssfety re. ie..

end i vestin,ctions n ;l ne for

-d ed :: the S.ation t'enacer, Vice Drcsicer.

'hnerati'.- and th-Chairn-f.'-

^ nerel.ffice :: vie. Board. In caiition, :y

ports:le occurrence er 1:r. r c :lv i r.;

n unrevieued sc rety que. tion +.i:- is ide.ifi:d b:, the IF

.il c: :: unented and reported im.edic.:1y : th? ct:ve menti:ntd persons.

2032 OA7 6-6 knendment No. JD, J7, 40

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InLa Tne audit findings which result from all audits conducted in ace:rdance with Section 6.5. 2.5 shall be doctnented and reported to the above menti:ned persons seithir. 30 days af ter completing the audit.

Reports documentin; corrective action will receive the same distribution and they will als? be forx:rded to the ISRG Coordinator.

.5.4 General Office Review Board (GORB)

J..L 1 wa 6.5.4.1 Tne technical and a ninistrative function of the GORB is to provide independent review of major safety issues, to foresee potentially significant nuclear and rad iatico safety problems, and to advise the Company President on these matters.

0!'?OSIT IC'l

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'lembers of the Ganeral Office Eeview Board shall possess extensive experience ir their individual specialities and collectively have the competence in the follo ing areas:

a.

Nuclear Power Plant Operations b.

Nuclear Engineering c.

Chemistry and Radicchemistry d.

? tallurgy c.

Ins;rtmentation and Control f.

Radiological Safety g.

'le:hanical and Elcetrical Engineering Tne CE irman and Vice Chairman shall be appointed by the Comp;r'. President.

(:.'either shall be an individual with line responsibility for cpsration of the p1_ ant).

The Chairman shall designate a minimtn of six additional members.

':o more than a minority of the Ecard shall have line responsibility for operation of Cyster Creek ';uclear GeneratinS Station.

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.5.4.-

..lterr.E.e r.etbers shall be appointed in writin', by the GCRB Chairnan and will ve the type of expcrience and trainin, recuired of e;ular.r.ters, hever,

tr.cy 922d not have the extensive longevity in the desigr.ated fiel s 2: lon, as, 2 2nd juc..2.er.t tre n::.::te t.e pinion of the Chain n, their exrcrien:

The GORB shall meet et least semi-annually and any time at the request of the Chairman or the Company President.

2032 068 6-9 Amendment No. 10, J7, 40

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A quorum shall consist of the Chairman or Vice Chairman and three No more than one alternate member shall be counted when m ember s/ alterna tes.

establishing a quorun and no more than a minority of the quorun shall hold line responsibility for operations of the Oyster Creek Station.

ESPGi:SIEILITIES

.5.4.5

'ihe primary responsibility of the GGRB is to foresee po entially si;;nificant t

a..uclear and radiation safety problems and to rec: mend to the Company Presid:nt how they may be avoided er mitigated.

Carry out the specific independent safety review responsibilities listed in b.

Table 6. 5-1.

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The GORB shall be advisory t.o the Company President and sh.=.11 have the authority -

to conduct reviews, aulits, and investigations requested by the Company President or as deemed necessary by the GGRE in the fulfillment of its responsibilities.

2.3.4.3

~'he report of t.he management review of the QA Plan, initiated by the Vice President, Generation, in accordance with the Operational Quality Assurance Plan, shall be reviewed by the CORB with respect to safety and administrative safety issues.

~.>- e.n.e "inutes of each GORB meeting shall be recorded and approved by the GGRB

.hcirn:n. G pies of approved minutes will be for.earded to the Ccc.psny President,

~

Jice President-Generation, Station F.anager, PCRC Chair:.cn and others d esignated c,. th, CDF: Chairmen.

GCEF -ecccmandrtio'

o t:.e Co cey Presid:r.t.till be i:: r.er.t o d in - letter frc: the GCRE Chair:r.er to th? ; esident.

In:luded with

=::5 letter.:i'l "a any dissentin; opinions of me%2rs of the Ecard.

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• • 3 oc w

Tne following actions shall be taken in the event of a Reportable Occurrence:

Tne Connission shall be notified and/or a reprt submitted pursuant to the a.

requirements of S;>ecification 6.9 Each Reportable Occurrence Report submitted to the Commission shall be b.reviewed by the Plant Operations Review Committee ar.d submitted to the ISRG I

Coordinator, Station Manager, and Manager, Generating Stations-Mucleer.

'.7 S.EETY LIMIT VIOLATION

'.7.1 Tne following actions shall be taken in the event a Ssfety Limit is violated:

If any Safety Limit is exceeded, the reactor shall te shut down i:renediately a.until the Commission authorizes the resunption of operation.

The Szfety Limit violation shall be reported to the Commission and the b.

':2 nager, Generatrng Stations - Nuclear.

A Safety Limit Violation Report shall be prepared.

Tne report shall be c.

revieuad by the Plant Cperations Review Committee and submitted to the Station

ana;cr and *:cnager, Generating Stations-Nuclear.

~'his report shc11 describ: I (1) cppliccble circumstar.ces preceding the violation, (2) effects of the,.

violation upon f acility components systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Comission within 10 days of the violation.

It shall also be submitted to the ISRG Coordinator.

5.E PROCEUJRES

3. F.1

'..'-itten procedures shal) be established, implemented, and.aintained that meet or exceed the requirements of Section 5.1 and 5.3 of Imerican l'ttional Standard 1:12.7-1972 and Appendix "A" of the Nuclear Regulatory Co-.ission's Regulatory Guide 1.33-1972 except as provided in 6.8.2 and 6.2.3 belo.

.c Each procedura and administrctive policy of 6.E.1 abo.a, and changes thereto, en:ll be eviewed by the Plcnt Operations R2 vie.. ::~.mittee tnd approved by the Station '.snager prior to implementation and peri::ically as specified in the 1:~i.istrativc Procedures.

~.r.;:r;ry char.;cs to preceduras 6.'.1 abovc m;y b2 madc ; cv;ded:

c 2032 172 Anendment No. 70, 25, 40 6-10

Le intent of the original procedure is not altered.

a.

Tno change is approved by two members of the supervisory s aff, at least one I

b.

of thom possesses a Senior Reactor Operator's License.

The change is documented, subsequently reviewed by the Plant Operations in the I

c.Review Committee and approved by the Station Manager as specified Administrative Procedures.

0" lD lD 30} b e n J J)U XM2 2032 073 Amendment flo. 70, 75, 40 6-11

6-2S

'D "

D D 9

.d a

66 w

h.

Records of inservice inspections performed pursuant to these Technical Specifications, i.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

j.

Records of meetings of the Plant Operations Review Committee and the General Office Review Board.

6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.

6.11 RADIATION PROTECTION PROGRAll, Procedures for personnel radiation protection shall be prepared consistent with the requiz ements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving perscnnel radiation exposure.

6.12 (Deleted) 6.13 HIGM RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10CFR20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).*

An individual or group of individuals permitted to enter such areas shall be provided with one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continously integrates the radiation dose rate in the area and alarms when a pre-set integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them, c.

A health physics qualified individual (i.e.

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive exposure control over the activities within the area and who will perform periodic radiation surveillance at the frequency specified in the RWP.

The sarveillance frequency will be establishec by the Health Physics Supervisor.

2032 074

6-29 Specification 6.13.1 shall also apply to each high radiation 6.13.2 area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition,. locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of operations and/or radiation protection supervision on duty.

2032 075

• Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high ladiation areas.

Amendment tio. 40