ML20217P012

Forwards NRC Proposed change,TSB-011,to Administrative Controls Section of STS to Accommodate Changes to 10CFR20, 10CFR50.36A,10CFR50 & 10CFR55

ML20217P012
Person / Time
Site:	Duane Arnold
Issue date:	04/09/1997
From:	Charemagne Grimes NRC (Affiliation Not Assigned)
To:	Jennifer Davis NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &
Shared Package
ML20217N937	List: ML20217N930 ML20217P012
References
NUDOCS 9708260415
Download: ML20217P012 (14)

Text

f~%1 UNTTfD STATES p

3 NUCLEAR REGULATCRY COMMISSION

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April 9,1997 Mr. James Davis Nuclear Energy Institute 1776 Eye Street, N. W.

Suite 300 Washington, DC 20006-2496

Dear M.'. Davis:

As you know, the NRC cancelled its plans to issue a Generic Letter for a line-item improvement to the technical specification administrative controls i

section, to devote more resources to conversion reviews and additional improvements to the improved standard technical specifications (STS).

However, the proposed Generic Letter would have included several chang'es to the administrative controls to accomodate changes to 10 CFR 20 and 10 CFR 50.36a.

In addition, since the issuance of Administrative Letter 95-06 on the relocation of administrative controls related to quality assurance, the staff has identified additional changes to the administrative controls to better accomodate the staffing requirements in 10 CFR Part 50 and Part 55, and to include a new staff position regarding controls for the working hours of personnel who perform safety-related functions. is an NRC proposed change, TSB-Oll, to the administrative controls section of the STS to reflect the changes described above.

In addition, the Technical Specifications Task Force (TSTF) has proposed similar changes to the a

STS in TSTF-86 and TSTF-121. We request that the TSTF modify their proposals in these travelers, or withdraw those changes and submit a new traveler, to reflect consistent changes to the administrative controls for all versions of the STS. Should you have any questions regarding this matter, please contact Bob Tjader at 301-415-1187.

Sincerely, Christopher I. Grimes, Chief Technical Specifications Branch Associate Director for Projects Dffice of Nuclear Resctor Regulation

Enclosure:

as stated cc:

C. Szabo, BWOG L. Bu'sh, WOG B. Mann, CEOG A. Maron, BWROG B. Ford, BWROG D. Hoffman, EXCEL 9708260415 970818 PDR ADOCK 0500 1

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T6B FORM 2 U.S. CUCLIAR REGULATORY COMul&&l0N PACKAtE NO.

OATE TSB-NRC Prop

• sed ChanDe to the STS.

011 04/0247 e

Originator:

R. T}ader Mgr Approved:

Date:

11/0746 Purpose of Update STS to Reflect 10 CFR 20 and 10 CFR 50.36a Chan0e8 Change:

NUREGs ChSnDed 1430: X 1431: X 1432: X 1433: X 1434: X Toehnneel S;.1.0.: Changed:

il Chenge AMn Centrole seesene SJ and EJ on wrdt stems -J.. nte 21 Change AMn Cenpole SeeWon 5.5.4. Re6eeevve Ement Centrole Program al Repleos Aerren Centrole SeeWen 5.7. Mob Radietion Aree l

Deecription of Change:

Redee STS Admin Centrole Seetiene 5.2 en Urdt Stoff and 5.3 en Urdt staff Duelineesene to temew requirements todundant estth i

eeputesene Chenge/repleee STS Admin Centrole Seetlene 5.5.4 and 5.7,: ; utdy, to toneet 10 CFR 20 and 10 CPR 50J6e ehenges, to meimein eenewtoney between the STS and regulation.

.lueeneeelon of Change-Revissen of 75 5.2J.e en ordt etaff werWne hours renects tooent CRGR epproved ehenges to the STS. Aevimon of"3 5.3 en ete%g teguirememe temovee reoairemente todundant to regulations whAe roteining elemente teSaired in TS by regulatione. Redelene of 10 CFR Port 20 and 10 CFR 50.3Se how ouperooded teleted information in the TS and other topulations, thereby prorretine NRC to propose this generne ehenge trevelle to update the STS. The model STS prev 4ded in this peeksee are speelfically intended te ohminate paesable eenhassen er improper implementation of the rev4 sed 10 CFR Port 20 ecosiremente. (See attached ketficetion.)

i Enterod Database Dete:

11/746 Filenemet g Vermswuneesendb NRC REVIEW OF PROPOSED STS CHANGE TSB Reviewer:

R. Tseder Tech Reviewer:

S.10ementewica 9f review required)

Reeemmendenen Date: 11/746 Aeesemandation:

Date: 112/96 iX l APPROVE I I MODFY I IREJECT I X l APPROVE l l M00lFY I l REJECT Comments.

Commente:

See eben Juseneesen se ettechmenes to treveller. 3/347 pke was incorporated as on ensiesure to e letter to NEl and provided to C. Grimes for signsture. This ehenge wee to have been prev 6ded 4

sador a Generic Letter which wee eenested. 4/247 TT,5.2 and 5.3 edded to peekage; peakepe forwarded to C. Grimes for disposition.

PROPOSED STS CHANGE DISPOSITION T88 Aetion /

[ 'M l Date: AM Q'$

TSTF Aetion Of applieebie)

Date:

led APPROVED IMOOlFIED I I REJ!CTED '

I l APPROVED l l AEVISED l i APPEALED Commonw:

Commente:

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4 STS Fil.E AND RECORD DATA CHANGES ACTION SY Daft ACTION SY DATE l

WP F#es Chensee Updeted Certined i

Chenees Aesoas Danebees Prooted Updated Aeoened for Comment Aseeluden CerroeWene Detebene Updated Centrol Seeke Gese.eut Latter Updated Sem to TSTF 588 Filee Peekage i

Uedeted Filed C: WORMS \\T5ELNo.Ot t

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v-Justification of Changes:

Revision of TS 5.2 and TS 5.3 on staff work hours and' staffing requirements removes requirements redundant to regulations while retaining

, elements required in TS by regulations. Revisions of 10 CFR Part 20 and 10 CFR 50.36a have superseded related infomation in the TS and other regulations, thereby prompting NRC to propose this generic change traveller to update the STS. The model STS provided in this package are specifically intended to eliminate possible confusion or improper inplementation of the revised 10 CFR Part 20 requirements.

Staffino Reauiremerr:s and Workino Hourn T5 Ciances fTS 5.2 & TS 5.3) -

Revision of TS S.2.2.e on unit sta"f worting hours reflects recent CRGR-approved changes to the STS. This change, to existing STS paragraph 5.2.2.e.

from specific working hour limits to achinistrative procedures to control working hours will provide reasonable assurance that inpaired performance caused by excessive workin) hours will not jeopardize safe 11 ant o>eration.

Specific working hour limius are not otherwise required to,)e in t1e technical specifications under 10 CFR 50.36(c)(5). Specific controls for working hours of reactor plant staff can be described in a licensee a deliberate decision makin) process to minimize the ) procedure that requires otential for 1spaired personnel performance, and Shat a licensee's estab11sied procedure control processes will provide sufficient control for changes to that procedure.

These programs have a level of detail necessary to satisfy the. policy statement (SECY 93 067) guidance and are retained in the Administrative Controls section of the TS. Therefore, the procedures and details can be i

relocated outside the TS.

Existing STS paragraph 5.2.2.b is deleted bec,ause it is redundant to l

10CFR50.54(m)(2)(111).

l Existing STS paragraphs 5.2.2.c is revised and a new STS paragraph 5.3.2 is added to ensure that there is no misunderstanding when conplying with j

10 CFR 55.4 requirements.

l Chances to TS result 11a from 10 CFR 20 Chances JTS 5.5.4 & TS !.7) l Revisions of 10 C R Part 20 and 10 CFR 50.36a have superseced related i

- infomation in the TS and other regulations, thereby prompting NRC to propose this generic change traveler to update the STS. While 10 CFR Part 20 allows licensees to inplement the rule without having to make any changes to their i

approved TS the NRC has crafted the enclosed model STS sections to provide i_

acceptable language that correlates with the wording in the revised 10 CFR Part 20 and 10 CFR 50.36a.. Additionally in accordance with i

10 CFR 20.1601(c), the proposed model STS for high radiation areas contain updated acceptable alternate controls to those given in 10 CFR 20.1601 and Regulatory Guide 8.38. Licensees may propose other alternate high radiation area controls based on their plant specific needs.

In the case of gaseous and liquid effluent release rates, the model STS were crafted to allow licensees to maintain their same overall level of i

- effluent control while retaining the o>erational flexibility that exists with l

current STS under the previous 10 CFR ) art 20. The model STS continue to l

require that radiation doses to members of the public from gaseous and liquid

- effluent releases from nuclear power plants be within the values given in Appendix I to 10 CFR Part 50 and the limits in 10 CFR Part 20.

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The model STS provided in this letter are specifically intended to eliminate possible confusion or improper inplementation of the revised 10 CFR j.

Part 20 requirements.

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5.2 Organization-3 5.2.2 Unit staff The unit staff organization shall include the following:

4 a.

A non Licensed Operator shall be assigned to each reactor containing fuel and an additional non Licensed Operator shall be assigned for each unit when a reactor is operating in MODES 1.2.3 or 4.

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[Two unit sites with both units shutdown or defueled, a total of three non Licensed operators are required for the two j

units.)

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efs"than~thimin'imum requirement of 10 CFR 50.54(m)(2)(1)ybe and 5.2.2.a for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to i

accomodate unexpected absence of on duty shift crew members provided 1 mediate action is taken to restore the shift crew corrposition to within the minimum requirements.

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A [ Health Physics Technician) shall be on site when fue' is in I

i the reactor.

The position may be vacant for not more than l

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. in order to provide for unexpected absence, provided i

inmediate action is taken to fill the required position.

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oilimitythe working"?g$1 ice;nsedeSeniorMeactorhours;tf person lated AfunctionsMe rators SR0s)R11 censed Raattorgoperators4R0s)dihealth cists j

iliaryJggrators;4ndAtyAalntenancgersonne < ~~j' Y,eA4Wfih311Pfii2!165egu18illnes en wingwifiaf re" adequate shi ftgoveragelshall ee: maintained *1thout i

ine1 heavy.vsesfavertimel

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' 5.2 Drganization 5.2.2 Unit staff (Continued)

Str51rthli11 NanRU5idMippie Vr55iaTres}such7 hit super.intendent);erdheTPlant? Superintendent 3)y thelIPl L

msure:that" excessive hours

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kvfationt lLut))orJzedy@cm Athe Wingihour t<cuidelineswhal bmot)he 4{.

The [ Operations Manager or Assistant Operations Manager] shall hol an SRO license.

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The Shift Technical Advisor (STA) shall provide adhsory i

technical support to the Shift Supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

In addition, the STA shall meet the qualifications specified by the Comission Policy Statement on Engineering Expertise on Shift.

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i Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications

[ Reviewer's Note: Minian qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications. Generally, the first method is preferable: however, the second method is adaptable to those unit staffs requiring s statements because of unique organizational structures.) pecial qualification l

5.3.1 Each menber of the unit staff shall meet or exceed the minimum i

qualifications of [ Regulatory Guide 1.8. Revision 2,1987, or more recent i

revisions, or ANSI Standard acceptable to the NRC staff). The staff riot covered by - [Regulato Guide 1.8) shall meet or exceed the minimum qualifications of (

ulations, Regulatory. Guides, or ANSI Standards acceptable to NRC staf J.

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nd sa n icensed wactor3.werator?;(RO) sare Mhose dndivi dditionito-eeet the uirements

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ief 35 5.'3J;Wrforsthe tfunctions'

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hviewer'44ioter6The minimimi'itiffffiiiiiiisj51iiihentEstipUlit~61Bi

[0 CFR 50.54(m)?.for; unit sembers: actively performing the functionsiffin pratorlonseniorioperatordcan be exceeded,py~:stip~u],atify~th(enhanced ptaffingyegtfirements;1nsaragr3p15_;3.LT-

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r.r.cy l5 5.5.4 Radioactive Efnuent tantrain Prenram i

This program senferus to le CFR 50.36a for the centrol of radioactive efnuents and for maintaining the doses to usebers of the public from radioactive efnuents as los as reasonably achievable. The program shall 6e contained in the CDCM, shall be implemented by procedures, limits are and shall include remedial actions to, be taken whenever the progran i

escaeded. 1he program shall 4melude the followleg elements:

[

.a.

68eritattens en the factional capability of redienctive 11guid and gaseous monitoring instrumentation including surveillance tests and j

eetpoint detemination in accordance with the methodelegy in the j

1. Cal; 6.

Lieltations en the concentrattens.ef radleactive material released l

in liquid ofnuents to annstr.icted areas, confomina to "_e ~ !",

l Appendix B. Table 2, Column (4.seuM: as,u.f a.av6.+--*

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u. O MonitoringIn accordance vith 10 CFR 20.1302 and with the methodolo sampling, and analysis of radioactive 11guld and gaseous c.

effluents and parameters in the 00CM; d.

Limitations on W annual and quarterly doses or dose cammitment to.

a assber of the public from radioactive materials in liquid i

efnuents released from each unit to unrestricted areas, conforming i

to 10 CFR 50, Appendix I; e.

Determination of cumulative and projected dose centributions fres l

radioactive efnuents for the current calendar quarter and current 1

calendar year in accordance with the methodology and parameters in i

the CDCM at least every 31 days; f.

Limitations en the functional capability and use of the liquid and i

gaseous effluent treatment systems to ensure that appropriate portions of these systems are msed to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 25 of the guidelines for the annual dose or dose commitment,

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confoming to 10 CFR 50, Appendix I:

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tiettattens en the dose este i resu m ng eactive enterial

'*l',ased ta,passous pnuentshto,_amas begn(p!,its,_ boundary e _......

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Liettations en the annual and guarterly air doses resulting fmm aable gases released in tapend the site boundary, gaseous efnuents from each snit to areas conforming to le CFR 50 Appendix. I; j

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Ltmitattens en the ansval and guarterly doses to a eseber of the i-geblic from lediee-131, dedine-113, tritte, and all radieneclides i

la particulate form with half lives > 8 days la gaseous ofnuents released from each unit to areas beyond the j

site boundary, conforming to 10 CFR 50, Appendix I; and I

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Liettationsfon the annuti dose cr dose ctiment to cny asuber of r

the pubite,jdue to M1sases of radioactivity and to radiation fres eranium fiel cycle sources, confoming to 40 CFR 190.,

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'5.5.4 Radioactive Efnuent Centrols Prograa l

This program confereing to 10 CFR 50.36a provides for the control of j-radioactive effluents and for antataining the doses to members of i

the public from radioactive effluents as lou as reasonably 4*klevable. The program shall be contained in the CDCM, shall be i

emplemented by operettaq precedures, and shall include remedial actions to be taken whenever the program limits are exceeded. ine j

program shall include the fellowing elements:

l a.

11mitations en W functisinal capability of radis> active 11guld and gaseous monitoring instrumentation including surveillance

' tests and setpoint deterslaation in accordance arith the

• methodology in the CDCM; i

i b.

Lleitations en the cancentrations of radioactive enterial l

released in 11guid ofnuents from the site to UNRESTRICTED I

i AREAS, conforming to 10 times the concentration values in l

Appendix S, Table 2. Column 1 to 10 CFR 20.1001-20.2402; i

l c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous ofnuents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the CDCM; d.

Limitationc on the annual and quarterly doses er dose commitment to a eseber of the public from radioactive materials in liquid effluents released from each unit to i

marestricted areas, conforming to 10 CFR 50, Appendix I;

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Determination of cumulative and projected dose contributions fres radioactive efnuents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days; 4

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f.

Limitations on the functional capability and use of the 11guld i

and gaseous effluent treatment systems to ensure that I

appropriate port. ions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 mrcent of the eutdelines for the annual dose er dose caus' taant, conforalng to 10 CFR 50, Appendix I; g.

Limitations en the dose rate resulting from radioactive

, enterial released in gaseous ofnuents from the site to areas j

at er heyond the 3LTE RDUNDARY shall be limited to the j

_ fe11 ewing:

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For amble gases: less than er equal to a dose rate of

.300 arems/yr to the total body and less than er equal to 4 dese rate of 3000 aress/yr to the skin, and I

2.

For ledine-131 todine-133, tritium, and for all radienuclides In particulate -form with half-lives j.

greater than 8 days: less than er equal to a dose rate 1

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cf 1500 ersas/yr to any organ; k.

Limitattuis on the annual and aparterly air doses resulting from noble gases released in gaseous effluents from each unit i

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to areas.at er beyond the site boundary, confoming to 30 CFR 50, Appendix 1; 2

1 1.

4tritations an the manual anJ evarterly doses to a member of 3 the public from todine-131, todine-133, tritium, and all cadiensc16de: is particulate fem with half-lives greater than 8 days in gaseous efflueets reinased from each unit to areas l

4eyond the site boundary, conforming to 10 CFR 50. Appendix I; 1

and l

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. Limitations en the annual dose er dose commitment to any l

sesser of the public beyond the 51TE SOUNDARY, due to j

teleases of radioactivity and to radiation from uranime fuel cycle sources, conforming to 40 CFR Ig0.

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c ADMIN!5TRATIVE CONTROLS i

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Wish Radiation Area i

l As provided to paragraph 20.1601(c) of 10 CFR part 20 the following controls Gall be applied to high radiation areas in place of h controls required by j

j paragraph 20.1401(a) and (b) of 10 CFR part 20:

5.7.1 Minh Radiation Areas with Deze Rates het Exceed {no Le rem / hour at 10 l

Cartimeters free the Radiation tource er frem Any surface Penetrated by the i

Rat latient I

a.

'Esch entryway to such an area shall be barricaded and l

conspicuously posted as a high radiation area. Such l

barricades may be opened as necessary to permit entry or l

exit of personnel or equipment.

l b.

Access to, and activities in, each such area shall be i

controlled by means of Radiation. Work permit CRWP) or j

equivalent that includes s scification of raddation dose rates in the immediate wort area (s radiationprotectionequipment'and) measures.and other. appropriat j

c.

Individuals qualified in radietion protection procedures (e.g., health physics technicians and personnel continuously escorted by such ind)ivittaals say be exempted i

from the requirement for an RWP or equivalent while performing their assigned duties provided that they are following plant raciation protection procedures for entry j

to, exit from, and work in such areas.

I d.

Each individual or group enterfag such an area shall possess:

1.

A radiation monitoring device that continuously j

displays radiation dose rates in the area; or l

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ICDEL SPECIFICATION 5.0-16 ADNINISTRATIVE CONTRDLS i

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5.7 Nigh Radiation Area f'

5.7.1 2.

A radiation monitoring device that continuously (continued) integrates the radiation dose rates in the area and alaras when the device's dose alare setpoint is j

reached, with an appropriate alars setpoint, or 3.

A radiatten monitoring device that continuously l

transaits dose rate and cumulative dose to a remote i

receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or i

4.

A self-reading dosimeter (s.!U) pocket tenization chamber er electronic dossme

and, i

(1)

Se under the surveillance as specified in the WP or equivalent while In the area, of an procedures, qualified in radiation protection individual i

l equipped with a radiation monitoring j

device that continuously displays radiation dose l

rates in the area; who is responsible for controlling personnel exposure within the area, or q

(11) Se under the surveillance as specified in the ItWP or eruivalent, while in the area by means of closee circuit television, of pers,onnel qualified in radiation protection procedures responsible for controlling personnel radiation exposure in the area, and with the means to j

communicate with and control every individual in i

the area.

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Except for indivlJuals qualified in radiation protection procedures, entry into such areas shall he made only after dose rates in the area have been detemined and entry personnel are knowledgeable of them, i

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< 'lish Radiation 1 <rean wit s tese mates treater than 1.0 reathaur at t

.0 centimeters < ' rem the tac iation tource er from Any surface enetrated by t 'in Radiation. but tens than 500 rads / sour at 1 leter from i ge Ladiation tource er from Any surface 4enetrated by j

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u.he Radiatient l

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Each entryway to such an area shall be conspicuously posted j

.as a high radiation area and shall he provided with a locked l

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j fl0 DEL SPECIFICATION 5.0-17 ADMINISTRATIVE CONTROLS i

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5.7 5.7 Nigh Radiation Area 5.7.2 door er gate that prevents unauthorized entry, and, in (continued) 4ddition 1.

All such door and gate keys shall be maintained under the edninistrative control of the shift supervisor, radiation protection annager, or his or her designee.

2.

Doors and gates shall remain locked except during

• periods of personnel er equipment entry or exit.

b.

Access to, and activities in each such area shall be controlled by means of an Wf or equivalent that includes specification of radiation dose rates in the famediate work and m(s) and other appropriate radiation protection equipment area easures.

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c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an WP or equivalent while w rforming radiation surveys in such areas provided that tsey are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitorinfi device that continutusly integrates the radiat<on rates in the area and alarms when the device's dose alam setpoint is reached, with an appropriate alam setpoint, or 2.

A radiation monitoring device that continuously transaits dose rate and cumulative dose' information to a remote receiver monitored by radiation protection personnel responsible for controlling nrsonnel radiation exposure within the area v' t t the means to communicate with and control every individual in the area, or tantinued O

MODEL SPECIFICATION 5.0-18 ADMINISTRATIVE CONTROLS l

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,t 1.'t Ciph Radiation Area

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5.7 Nigh Radiation Area A self-reading desienter Co.s.,) pocket ionization S.7.2 3.

chamber er electronic dos < ester and, (contieved)

(1)

Se under the serve 111ance as specified in the StP or equivalent dile In the area, of an individual quallflod in radiation protection procedures equipped with a radiation monitoring device thal continuously displays radiation dose ratas in the area do is responsible for sentrolling person;nel exposure within the area, er j

i (11) Se under the surveillance as specified in the miP er equivalent, d ile in W area, by means of closed circuit television, of personnel qualified in radiation protection procedures responsible for controlling personnel radiation axposure in the area, and with the means to

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communicate with and control every individual in j

the area, or l

4.

In those cases where options (t) and impractical or determined to be incon(3), above, are sistent with the i

'As Low As is Re'3onably Achievable' principle, a radiation monito) *.ig device that continuously displays radiation dose ra es in the area.

a.

Except for individual qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry i

l personnel are knowledgeable of them.

f.

Such individual areas that are within a larger area that is l

controlled as a high radiation area, where no enclosure axists for the purpose of locking and dere no enclosure can i

reasonable be constructed around the individual area need i

mot be controlled by a locked door er gate, but shall be l

barricaded and conspicuous, clearly visible flashing light l

shall 6e activated at the area as a warning device.

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