ML20206F935

Request for OMB Review & Supporting Statement Re NRC 398, Personnel Qualification Statement - Licensee. Estimated Respondent Burden Is 3,850 H

ML20206F935
Person / Time
Issue date:	11/16/1988
From:	Mcdonald W NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
To:
References
OMB-3150-0090, OMB-3150-90, NUDOCS 8811210405
Download: ML20206F935 (16)

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PART lli.-Complete This PartCnly if the Requestis for Approval of a Collection of Informallon Under the Paperwork Reduction Act and 5 CFR 1320.

13. Abstract-oescriboneees.usesandaffectedpudr.ein5o-wdsorie5$"Nuclear Power Plant, License, Operator" NRC Form 398 is used to collect information from licensees / applicants seeking to obtain a new renewal, or reapplication for a license to operate the controls of a nuclear power plant.

14. Type of intermation collection (check only cre)

Informathn collections not centainedin rules 10 Regv'ar submission 2 O Emergency subm>$iion(cert,featen attached) information collections containedin rules 3 3 Exist,mg regataton (no charge proposed) 6 Final or intenm final without prior NPRM

7. Enter date of espected or actual Federal 4 O not.ce of proposed rutemaiurs(NPRM)

A O Regular submiss,on Regrster pubbcation at this stage of ruemaking 5 O Final. NPRM was previous'y pubbsaied e O Emergency subm.ss,on(cert,f car.on attact ea>

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15. Ty pe cf rer e a requested (check cr/y cre) 1 O ne.c con cte 4 O Reinstatement of a prev ~cutly appruved collectiorifor wt'uch approval e

has espvH 21 Rect >on of a currentty approved collecton 3 O Estessen of trse espiration date of a current!y approved co tection 5 O Eost cg conect.on in us ithout an ous coneros numb.<

r w tnost any change in the substance or +c the method of conecien

• $. Me scy report form nurster(d (*nciuce standard / opt >onal form n:tmber(s))

22. Purpose of ~tumat>on conecte(chech as many as apply) 1 O Appucaten for benef>ts NRC 398 2 O Program evaluato

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SUPPORTING STATEMENT FOR NRC FORM 398, "PERSONAL QUAllFICATIONS STATEMENT - LICENSEE,"

10 CFR PART 55, 955.31, 55.35, 55.47 and 55.57 (OMB Clearance No. 3150-0090)

Description of Information Collection NRC Form 398 standardizes the essential informatinn needed to apply or reapply for or renew an operator's license to operate a nuclear power plant.

A.

JUSTIFICATION (1) Need for the Collection of Information NRC Regulations 10 CFR Part 55, 555.31, 55.35, 55.47 and 55.57, specifies the use of NRC Form 398 to collect information from licensee /applicauts seeking to obtain licenses to operate nuclear power plants.

(2) Agency Use of Information The completed NRC Form 398 is reviewed against the licensing criteria to ensure that a candidate meets all the requirements for taking the written examination or operating test; reapplying because of failure to pass the written examination or operating test, or both; or renewing a previous license. The NRC Form 398 also provides certification by the authorized facility representative that the applicant meets their requirements to be licensed as an operator and of the facility's need for an operator.

l l

The information provided on the NRC Form 398 is extracted by the Regional Offices and keyed into the Operator Licensing Tracking System (OLTS) data bank for tracking operator licenses and can be used for generating reports on licensing actions and issuing license and denial letters.

(3)

Reduction of Burden Through Information Technology There is no legal obstacle to the use of information technology.

lioreover, NRC encourages its use.

I (4) Effort to Identify Duplication This information does not duplicate nor overlap other information collections made by the NRC or other government l

agencies.

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2 (5) Effort to Use Similar Information This information is available only from the licensee / applicant.

(6)

Burden on Small Business This information collection does not involve any small businesses.

(7) Consequences of Less Frequent Collection The collection of information is occasional and is collected as needed.

(8) Variation from OMB Guidelines This request does not vary from OMB guidelines.

(9) Consultations Outside the NRC There have been no formal consultations outside the NRC regarding this form.

(10)ConfidentialityofInformation The NRC Form 398 is filed in the applicant's docket file. The information is also placed in a data base (Operator Licensing TrackingSystem). The information is not available for public inspection.

(11)SensitiveQuestions No sensitive information normally considered private is requested on NRC Form 398.

(12) F.stimated Annualized Cost to the Federal Government Approximately 1000 new and 800 renewal applications and 100 reapplications are expected to be submitted by the applicant /

licenses annually. This number is based on the data available from the Operator Licensing Tracking System.

It is anticipated that the nurber of renewal applications will decrease from 1700 to approximately 800 annually due to the revised Part 55 published May 1987 which extended the renewal period of an operator's license from two years to six years. As yet, not enough time has elapsed since implementation of the revised rule to allow for a definite forecast regarding the number of renewals.

To process the NRC form 398 it takes.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> per new application and.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> for each reapplication and renewal.

The NRC Form 398 processing includes data input, files

l maintenance and forms review regarding the eligibility criteria.

Data input takes longer for new applications because all data must be entered initially, whereas for reapplications and renewals, the data base need only be updated. Estimates are based on staff experience.

1,000 new applicants X.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> x $60/ hour = $45,000 annually 100 reapplications X.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> x $60/ hour = 3,000 annually 800 renewals X.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> X $60/ hour = $24,000 annually Cost for Operator Licensing Tracking System = $90,000 annually y

Therefore, the total annual cost to the Federal Government is expected to be $162.000 ($72,000 + $90,000).

(13) Estimate of Industry Burden and Costs As indicated above, approximately 1000 new, 800 renewal and 100 reapplications are expected to be submitted ar.nually.

Applications for new licenses, are to be submitted in total one time only and there is ne prespecified reporting period.

First reapplications can be filed at least two months after the date of the denial letter. Second reapplications can be filed six months after the date of the second denial letter. Third reapplications can be filed two years af ter date of the third denial letter and the date of each prior application.

Renewal applications are to be submitted no fewer than thirty days prior to the expiration of the existing license. This is l

every six years.

NRC Form 398 is required to be submitted in triplicate (original and two copies) to the appropriate Regional Office.

Records are not required to be retained by the licensees /

applicants.

The estimated burden to complete the h?C Form 398 is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per initial application,.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> per reapplication, and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per renewal application. New applications takt longer to complete because all information must be listed. After the initial 1

application, the reapplications and renewals just 9,ndate i

specific relevant items.

Estimates e based on past experience of the respondents actual time to com,iete the NRC Form 398.

3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> X 1,000 New Applications = 3000 Hours X $60/ hour =

$180,000 annually.

.50 Hour X 100 Reapplications = 50 Hours X $60/ hour = $3,000 annually.

1 Hour X 800 Renewal Applic6tions = 800 Hours X $60/ hour =

$48,000 Total Annual Industry Cost = 3,850 Hours X $60/ Hour = $231,000 (14)ReasonsforChangeinBurden The burden estimated here represents a decrease of 900 burden hours. The decrease is a result of the lower number of new applications and reapplications due to the revised 10 CFR Part 55 (copy enclosed).

(15)PublicationsforStatisticalUse This information is not published for statisitical use.

B.

COLLECTIONS OF INFOR.9T10N EMPLOYING STATISTICAL METHODS Statistical mthods are not used in this information collection.

10 CFR 55.31, 10 CFR 55.35 and 10 CFR 55.35 and 10 CFR 55.57 re tre that applicants use NRC Form 398 to apply or reapply for or renew an operator's license.

Enclosures:

1. NRC Form 398(4/87) 2.10 CFR Part 55

a 10 CFR Ch. I O-1-44 Edition) pk.A=-, a7 4 Ceansmisalen Port 55 g3,33 i

E3s F1mml deter- --ta==

5 13.30 Crisens for a Ceamminhos deterud-(b) Solely for the purpose of making matlem.

the determination required by PW NTOM* N I(a) An intual determinatinri under 3 S3.27(ax1). the Ca==i='on shall 53.27 shan be fued with the Offlee of (a) la rnaking the determinauon re-ensure the m'.intenance of a full core W Secretary of the C^mm'at^a-culred by i S3.27(aMI), the Commis-reserve at the alte of the civillan nucle-beh inical determin="an shall con-slon shan consider the existence of ar power reactor for which the request sec.

)stute the final determin="^a of the techrifcal economic, regulatory, or 6===t==taa thirty (30) days after its health and safety factors that would la being made.

55.1 Purpose.

suunnce, unless the Cor==ial-de-make the impicmentation of any alter.

(c) If the person requating the de.

n2 smpe.

553 License rwutrernents.

ldes *.o review the Initial determina-nauve to Federal interim storage of terminauon demoastrates. and the as.4 Dennitsons.

km under paragraph (b) of this sec-spent nuclear fuel set forth in C-~hion finds, that tne mainte-

• • 'I 3 S3.13(c) unreasonsble. such as-nance of a single f ull core reserve at en.

C) Within thirty days after the Ex-(1) Suttabuity of the reactor site for the reactor site is either inadequate or

%g cutive Director for Operations, r.r impicmentation of an alternettve. in-not necessary for continued orderly as.s Infon==naa conecuan requiresnenta:

belance makes an initial determtn*-

clumr.e consideration of structural in-operation of the reactor. the Commis-OMB approval.

sion may make an excepticn to the 56.9 Can plateness and accuracy of infor-lon, the C

'--* may, on its own tegrity.

"*"a" w tan review the determin="^a (2) Inability to meet the Commis.

prov*ston of paragraph (b) of this sec-l (c) The C

'aina may at its dis-ston's regn1minry requirements for im-don.

M' Fedon, extend the time for review of plementation and licensing of an alter-(d) In making the sieterminadon re-Wa Initial determin='iaa under para-nauwe due to factcrs beyond the 11-quired by i S3.27(nH2), the Comtris-SS.: Specine esempuona.

paph C) of this section; provided. censee's control and despite the licens-slon win consider whether the person 68.13 Deneral eseinpuona.

nowever that if the Cammi='^a has

,,.s dulgent and good faith efforts.

submitting the request h a demon-

^

M not completed its review or isswd a (3) Insb111ty to obtain necessary ma-strated diligent and timely efforts to terials or equipment in a t.imely initiate activities reasonably calculat-n21 Medical examwrian g

ed to implement alternatives to Feder-55.23 Ceruficatian.

manner.

this M the intual determina-(4) Modifncations that would result al interim storage of spent fuel on a 55.25 incapactrattan because of an==htuty W of the Execuuve Director for Op-in the excessive reducuon of code schedule commensurate with the need or illness.

w lda w her designee shan n27 Docuanentation.

Donautute the final determin='h of design margins.

to support the continued orderly oper-(S) Extraordinary cost.s of implemen-atton of the reactor. Including -

g come %

tation that are clearly unreasonable in (1) DL11 gent and good faith efforts to l C) No petition or other request for view of such factors as the amount of prepare and (11e eximung license 55.31 How to apply.

add 1Uonal storage capacity needed.

application (s) for spent r.uclear fuel 55.33 Disposition of an tnitial appiirarian b

'*a review of an initial deter.

E35 h *P""#*"^"=

natnarian under 153.27 will be enter. the time for which additional storage storage alternative (s) as early as possi-kined by the C^ w=i-w capacity la needed, or the cost of Fed-ble so as to provide sufficient time to I 53.29 heuce of l=====re of a f1 mal deter-eral interim storage.

allow for design, liceaminar_ and imple-I' een l

T

16) Unicreseen or unavoidable delays mentation; and

&=an=

in the l' censing or implementation of (2)

Subacquent developments net written e===inat taa-operators.

d Upon the i==uance of a final an alternative due to factors beyond beyond the control of the person sub.

55.43 Written enamination-Senior opera-c_m,==ina determination or after 88 the licensee's control and despite the mitting the request that nas'8-opnating temaa.

the expiration of the time for Cornmis.

licensee's d1Hgent and good faith ef-(1) llave changed the ortatnal esu-

'""'""""""#I'*

sion review of an initial determination mate of when and how much addition-forts.

under i S3.23. which consututes a final (7) 1Egal l'npediments to the imple-al storage capacity will be needed or 85.49 Integrt y of euaminannae and tests.

deter ta='taa_ the Secretary of the c-m *n win notify. In writing. the mentation of an alternative, such as (11) Would prevent the timely imple-r person making the request, and the State or locel laws or regulatory ac-mentation of one or more alternatives; 5=%est F n----

Offlee of Civilian Radioactive Waste tions, including preexisting agree-and Management of the Department of enents, pertaining to matters within (3) The timely preparation and im-55.53 Conditions of licensen.

Energy of the final determin='h the jurisdiction of those levels of gov-Es (b) The Secretary of the Cnmm'-taa ernment, which are valid and enforce-rm e w

will came to be published in the Pan.

able or, though not valid, cannot res-ates the feasibility of alternadves to 55.59 Requalincation.

sonably be inve.11 dated or enforcement Federal storage of spent nuclear fuel,

. mar Racastra a nouce of the issuance of the final determination.

enjoined in a timely manner.

g (c) The Secretary of the Camm'=i^a (8) Occupational or off-site rmAtation will make a zopy of the final determ!- exposures or on41te construction haz-safety factors and that includes the 66.81 Modificarian and revacarian of 11 nattart avattahle for pubtle inspection ards that are clearly unreasonable in punpt development of feasible alter-censen.

in the Camm'== taws Pubtle Document view of the amount of additional stor-nadves to Federal storage-Room.1717 11 Street NW Washing-age repneity needed or the tirae for ton. DC, and in the local Public Docu-which additional storage capacity is (50 FR 5543. Pett 11.1945; 50 F5L 8806. Mar.

4.19881 58.71 Vianarinn.

maent Fanm for the reactor site.

Deeded.

45 44

i ET % i #"M i554 13 CFR Ch.1 (1-1-88 Edition)

I 55.1 ditions to which the simulator has (bX1) The Director of Nuclear Reac-gwa s,c 1of is1. ts2. sa stat 93s.

Sn4 1Mmmuona.

t been designed to respond.

tor Regulation has delegated to the ses 953. as avnded set 234. a3 SM 444.

As used in this part-

-Reference plant" means the specif-Regional Adnunistrators of Regions I,

n. amended <42 UsC 2137. 2

-Act means the Atornic Energy Act Ic nucles.r power plant from which a II. III. IV. and V authority and respon-pke ss4t, of 1954. including any amendments to simulauon facility's control room con-sibility pursuant to the regulattans in 22 2L *

• y figuration, system control arrange-this part for the issuance and renewal 1242. as the Act.

and SSSe also

-Actively performing the functions ment, and design data are derived.

of licenses for operators and senior op-m '4g ss43.5545sEc 30s. Pub.1 97-425. as of an operator or senior operator"

• • Senior operator" means any indi-erators of nuclear reactors licensed 53 vidual Ucemed under this part to ma-under 10 CPR Part 50 and ine= tai in stas 22s2 442 USC to22st bnuon M si means that an Individual has a post.

al tasued under neca. Iss.137. as 8 tat. 955 don on the shift crew that requires nipulate the controls of a facility and these regions.

to direct the licensed activities of 11-(2) Any application for a license or u2 US C 223e. 223h the individual to be licensed as defined cemed operskrs.

license renewal filed under the regula-ywr the purpo rm et acc. 223. es Stat. ess. in t! e facility's technical specifica-

• • Simulation facility" means one or tions in this part involving a nuclear as amended 4 42 US C 2273r. ll E3. 55.21.

and that, the individual carries more of the following components, reactor licensed under 10 CPR Part 50 15 49. and 55 53 A" 1**"*d ""d" out and is responsibic for the duues 220141 alone or in combarmuon used for the and any related inquiry. -emim

• • 8'** *** "' *"'"#

"[s[s3m are covered by that poattion.

partial conduct of operating testa for tion. Inform &Uon. or report must be

• • d II S* E

^ tI sa StaL 950. u

-Cm" " '"i^n" means the Nuclear peratws senior operators, and candi-submitted by mail or in person to the amended U C 22 otto n Regulatory Commission or its duly au-Regional Administrator. The Regional thorized representauves.

(1) The pht.

Administrator or the Admirustrator's soenn 52 m D4#. MAL 25 1537-unicas

-Controls" when used with respect A

t n

sisn W*

designee will transmit to the Director to a nuclear reactor rncans apparattas 3

e gg of Nuclear Reactor Regulation any ad mechanisms the manipulation of a

ma n

n he empe M Lebpert A O[d NM*

(hich directly affects the reactivity or me a

p poacr lesel of the reactor.

cludes the following five elementa-5 El Puryone.

-Paciuty" means any uulization fa-(1) Systemauc analysis of the jobs to W If the nuclear reactor is located in I

The regulations in this part-cility as detined in Part 50 of this be performed.

d n I, su anion must be inade to (n) Establish procedures and critch chapter. In cases for which a license is (2) Isarning objectives derived from the Regional Administrator. Region I, for the issuance of licenses to opera-hsued for operation of two or more fa-the analysis which describe W U.S. Nuclear Regulatory Comm"%

tors and senior operaton of utthzadon c1htles. -facility" means all facilitaes performance after training 631 M henue. W of Prmata facilities ucenyd punuant to the identified in the bcense.

(3) Training dealen and implementa-Pennsylunta IM6.

Atomic Energy Act of 1954. as amend-Pa inty heemec" means an appli-tion based on the Icarning objectives.

U1) If the nuclear reactor is located ed, or section 202 of the Energy Reor-cant for or holder of a uceme for a fa*

(4) Evaluauon of trainee mastery of In Region II. submission must be made 4

cantzation Act of 1974. Ps ameM gggy to me Regional Administraw. Regio.a the objectives during training. and Part 50 of this chapter. ~ encans an individual 11-(5) Evaluation and revision of the IL U.S. Nuclear Regulatory Commtm. (b) Provide for the terms and condb censed operator or senior operator. training based on the performance of sion.101 Marietta Street. Suite 2900, tions upon which the Commission will "Operator" means any individual 11-trained personnel in the job setting. AUanta Gewgia 203. haue or modiry these Ucenses. and censed under this patt to manipulate a "United States." when used in a geo-(111) If the nuclear reactor is located graphical sense. Includes Puerto Rico (c) Provide for the terms and condi-control of a facility. and all territories and possesalons of in Region III. submission must be gg g, man,an and renew these 11-mfwmance tuting" means testing made to the Regional Administrator. the United States. conducted to verUy a simulation factu-Region III. UA Nuclear Regulatory cemea. ty's performance as compand to 0 55.5 8'--icadeas. Cn= = l== ton. 799 Roosevelt Road. 5E2 &*P'- actual or predkted reference p h Glen Ellyn. Illinois 60137 Oy) If the nuclear reactor is located ne @uons in Ws # dT perfonnance. cans an individual 11 Elo lee ng p ide d f S at territory Ge the onal 1 trator ) Any individual who manipulates y ter. cc can O Region IV. U.S. Nuclear Regulatory the controls of any utilization facinty United States, the O of Puerlo shall submit any communication or Commfenton. 611 Ryan Plaza Drive, Ibecmed pursuant to Part 50 of thh btm or the Commonwe report cone-rning the reguladone in Rico to dispeme drugs in the practice this part and shall submit any P stica. Suite 1000. Arlington Texas 76011. chapter. and (b) Any individual designated by a of medicine. tion filed under these reguldns to (v) If the nuclear reactor is located fac1Dty licenace to be responsible for -Plant-referenced simulator" means the Conimtanton as follows-In Region V subm*.aslon must be made og directing any Ucensed activity of a 11' a simulator modeling the sys (1) By mall addressed to-Director of to the Regional Administrator. Reston the reference plant with wh1ch Nuclear Reactor Regulauon. UA Nu. V. U.S. Nuclear Regulatory Cnmmis-censed operator. erator interfaces in the controg 7, clear Regulatory C=m68an_. Wash. sion. 1450 Maria IAne. Suite 210. e ss.2 tarease rmere=eata-including operating mnsoles. and Walnut Creek California 94596. Inston. DC 20555. or which permits use of the reft-nce (2) By Mm b pm M h h-rson must be authorized by a U-plant's procedures. A plant-refer mission offices at-41) 1717 H Street E EE4 "m" ^ A to cenac issued by the Ca="'"naa NW., Washington. DC or UD 7930 Nor-Except as specifically authorized by i form the fut tion of an operator or simut tar der.2onstrates ex t.and folk Avenue.Betheoda, Maryland. the f'ammtantaa in writing, no inter-senior operator as defined in thh plan mse De dent con-part. 47 46

D CPR Ch. 3 (1 1-48 Ed6 dea) Wi att p Comedesien f 55.31 IW pucant w the ucensee shall be com-plete and sign Form NRC-396. Certi-Information and Document Control. pretaum f me meaning of the regu-plete and accurste in au material re-fication of Medical Examination by UA Nuclear Regulatory Ca==8-% 18d8"" I" part by any officer or Facil!Ly Ilcensee." avanable from Pub-Washington, DC 20555; g me cmm i--'na other spats-11 cation Services Section. Document (2) File an original and two copies of e8SDI8I" than O *ritten Interpretauon by the 153 FM es372. Dec. 31. lss13 Management Branch. Division of Form NRC-398, together with the in-Gennal I wiu be recognised to Dm wrs-secuan 65.8 *ss Technical Information and Document formation required in paragraphs be pon the C"*'"'" 52 ru es372. Due 31. les7. effec-Control. UA Nuclear Regulatory (a)(3) (4). (5) and (6) of thia section, m u,. ywruary 1. tasa. Commission. Washington, DC 20555. with the appropriate Regional Adrnin-

gy

--a;_; - ^ - (a) Fbrm NRC-3f 4 must certify that Istrator; uhn may, by rule. regu-g.4, _,"r a physician has caiducted the medical (3) Subm!L a written request from an 1 N c~ m lauon, w own. Impone upon any H-examination of the applicant as re-authorised representative of the facill-h requirements. In addition g 33 specific eseerd**s. quired in 155.21. ty licensee by which the applicant will I to N "e-mahad in tha regulauons W N",_mo may upon applica. (b) When the cestifIcation requests a be employed that the written exami-I gn this part, as it deems appmpriate w tion by an interested person, or upon ceditimal license based on medW nation and operating test be adminta-prosat health and to t danger to Ufe or property-na own InM grant such exernp- "idem, me medical evidence must tered to the applicant-l tions run me uirements of the be submitted on NEC Porm 396 to the (4) Provide evidence that the appu-gg gafaruumm JP '*9*3'* regulat~ons in put as it deter-Commission and the C==' 'M then cant has sumanfully completed the y law and will makes a determination In accordance facility licensee's requirements to be j ts: Ong app,,at unines are u not caidang" ufe or property and are M l EM. Heensed as an operate w sentw w. (r)The Nuclear Regulatory Commie slon has su te formauon otherwise in the pubtle ing, rest, e n25 !araperhsL= h et ameWi-ator and of the facility Heensee's need fuu m e waMw w e 2 Irementa contained in EW3 mg mmpomas. (7 *' 131****- perforr. assigned duties. An author-the Office of Management and Budaet (OMIT) for approval as re-De W in this part do not If during the term of the license, laed representative of the facility 11 Paperwork Reduction require a UCCD8' f" an todividinal W licensee deveW a AM w cem sM n@ h ence on mental condition that causes the 11-Form NRC-398. This certification "Act of 930 (44 USC. 3501 et seq 1 wW OMB has *DD" ed the information (a) Under the diration and in the censee to fall to meet the require. must incliade details of the applicant's of a ucensed operator or ments of 5 55.21 of this part, the facill. qualifications. and details on courses a catained in presence r strol number 3150-sentor operatw. anant the con. ty ucenace'shan nottfr the Commds-of instruccon utministered by the fa-I conection alon within 30 days of learning of the cility licensee, and describe the nature this part g,,g,g_ Ol N g wmation coDec-(1) A research or training reactor as diagnosis. For conditions for which a of the training received at the facility. 0013 su contained in this part of the individuars training as a conditional license (as describus In and the startup and shutdown experi-155.334b) et this part) is requested, ence received. In lieu of these details, j II" " D*FT SPD**# in 1155.45. 55.53 and student, or (2) A facihty as a part of the individ. the facinty 11censee shall provide med-the Cornmisalon may accept certifica-(c) M part contains informauon uars training in a facH1 h leal certification on Form NRC 396 to tion that the applicant has successful-IM8 I f the the Commission (as described in ly completed a C==i--%-approved e in addition to training program as appro i 55.23 of this partL training program that is based on a conectim requ thcae ap 3g te control commuun to qualify for an ope systems approach to training and that in paragraph (a) of ucense under this part. E "Cum **'" "" omnbn se information coUeC-(b) Under the direct o and in the uses a simulation facility acceptable to 1 U# ulrementa and the control presence og a licensed se opnator. The facility licenace shall document the C^mm'== ion under 155.45(b) of

• I8 l

urder which they are ap-manipulates the con ts of a faciliti and m='a'aN the results of medical this part; to load or unload me fLA 1 into, out of. qualificauons data, test resi.Ita. and (5) Provide evidence that the app 11-E

• 1. ', "' g,ap ws-55.25, 55.27. 55.31 or within the reactor wsset cach operator's or senior operatora cant, as a trainee has successfully ma-pM' medical history for the current Ilcense nipulated the controls of the facility Fonn NRgge is approved under con-period and provide the documentation for which a license is sought. At a min-

_ m, trol number 31504024-Sel> ped Wel L T, _ __ to the commi--im upon request. The imum. five significant control manipu-and 55 35,55.47 facility licensee shall retain this docu-lations must be performed which III 11 55.31 t approved 5 n21 M,hsI n-SS R Form NRC-398 mentation while an individual per. affect reactivity or power level For a trol number 31504090-licant for a Heense shall h#- forms the functions of an operator or facility that has not completed preo-1 I3 In 55.45, Form NRC-4'i4 t5 SD-examination by a physician. acntor operator, perational testing and initial startup proved under control number 3% A N shall have a medical emanu-test program as desenbed in its Final r g133. nation by a physician every two years. Subperf *- ^ 7 % t Safety Analyr.ls Report, as amended - shan determine that M How to apph. and approved by the Cn==Mion. the g g g- %= and arcaracy of La-he @ gM the appt or Ucensee meets the re. Ca=='Wn may accept evidence of quirements of 155.33(aMIL (a)The applicant shalt satisfactory performance of simulated ided to the Com. (1) Complete Foran NRC-398. *"Per-control manipulations as part of a Inf cang for a ucense 5 n23 Cestancauma. nonal Qua?tfication Statement 41-Commission-approved training pro-misslw yg or by a censee or informauon re-To certify the medical fitness of the ( m ee." avenahle from Publication grara by a tralnee on a simulation ts-the Conunis. a m rtzed representa-Services Section. Document Manage-cility acceptable to the Cammimminn ston orders. o cense acility licensee shan com-8hent Branch. Division of Technical under i 66.45(b) of this part. Pbr a fa-n. 48

10 CPR Ch. 5 (1 1-88 Edhien) mds., ay 7-j r-a..z." a IMN D5.4 duty ahich hat (1 pied preoper. win base its finding upon the certtites-eraung test and talled the other may limitations and reasoas for these oper-and testing as ed in its Final tion by the facility Heensee as detailed request in a new applicadon on Form aung characterisu<m. Safety Analy e amended in 155.23. NRC-398 to be excused from re-exami-(6) Design, components, and func. and apprM the Commission and (2) Wrtiles examinafton and opemi-nation on the pordons of the examina-Mons of reactivity control mechantama ahutdown which tag test The appucant has # the tim w test which the applicant has CI I" ^ and instrumentanan_ prect pulation of the control requisite written ex min-nan and op-psased. The Commission may in its facint in the control roan, the crating test in ac a dance M discrede grant the muest. If it de-(g3 pe ggn, components. W h may process the appucm-1155.41 and 55.45 or 55.43 and 55.45. termines that sufficient justificadon is tions of control and safety systems. In-M ud may =Aminw*r the written Ihese examinadons and tests Wr-presented. cimtingr instrumentath signals. Inter- ..,,ao., u and operating test re-mine whether the appucant for an cp-locks, failure modes, and aufnmatic and muud th l quired by ll 55.41 or 55.43 and 55.45 of crator's license hu Icarned to LApert E-Wrhen Examiassione and (s) Components, capacity, sad func-mis part, but may not issue the license a facility competently and safe y. eg y*s8s tions of emergency sm untu the required evidence of control addiUona!!y. In the cue of a seh .. ninamunna ts suppued. Por licensed crator, whether the appl 3sitt Writsee enemna--sL - Oywesen. (9) Shielding. Isolation, and contain-operators applying for a sensa opm-lemmd to direct W hd ment deslan features, including access (a) Comical The written examina-limitauons. I tor w. cert 1Nuon that the oper-of licensed operators canpetengy tion for an operator wul contain a rep-(10) Administrative, normal. abnor. I stor has successfulty opented the mn-safely-I' trols of the facility as a Ucensed open-(b) Cbadificaal license. If an ap g, resentative selectJon of questions on mal, and emergency operating proce-the knowledge, akills, and abilities dures for the facility. tor shall be accepted; and cant's general medical condi needed to perform licensed operator (11) Purpose and operation of radi-1 C) Provide certificadon by the facil-not meet the minimurn duties. The knowledge. sk111s and ity ucensee of snedical mndidon and under iSmam M M M the allon monitoring systems. Including abilitics will be identified, in part-general health on Form NRC-396, to commtutan may approve the app ca. from Icarning objecuves derived i om alarms and survey equipmenL mmply with Il'55.21 55.23 and tion and include cond1Uons in gg, (12) Radiological safety puciples a systematte analysis of licensed oper* 55.33(nX 1). cense to acca="^d te the atot ud pWm (b) The a=*'"i^a may at any defect. The Commi= tan viu mnsider luties performed by each facility (13) Procedures and equipment licensee and contained in lia training time after the apnr_tranaa has been the recommena.nnna and apporting D N program ud from information in the fued. and before the ucense has ex-evidence of the factitty licensee and of Final Safety Analysis Report, system radioacuve snatch and efDuenta. pared, require futher information the c'. mining physician (provided on descripuon manuals and operaung (14) Principles of heat transfer ther. 4 under oath or affirmarinn in order to Form NRC-396) in arriving at its dect-procedures, facility license and license snodynamics and Duld mechanica. enable it to determine whether to ann amendments. IJcensee Event Reporta. grant or deny the apnHea nan or and other materials requested from whether to revoke. modify. or smpend 35&25 E: :# #-- the facility Ucensee by the Commta-the Ucense (a) An appucant whose application alon. (a) Cbatent The written examina. (c) An appucant wW WW has been denied because of a W for a ucense has been denied because (b) The written examination for an tion for a senior operator will contain of failure to pass the written examina-operator for a facility wul include a a representative selection of questions condluon or general health may or operating test. or both. inny representauve sample from among the on the knowledge, aktfle and abuities I submit a further meent repat at any time as a supplete nt to the appucm-fea new apone.nnn two months fonowing 14 items, to the catent appil-needed to perform licensed senior op. after the date of dental. The applica-cable to the facility. erator duties. The knowledge, skills de-ad) Each apaHe*"an and statement tion must be submitted on Form NRC-(1) Pundamentals of reactor theory, and abilities will be identified, in part, must contain complete and accu ate 394 and include a statement signed by including fission process, neutron mul-froso learning objectives derived from an authortr,cd representative of the fa-tiplientinn, source effecta, control rod a systematic analysis of lleensed senior disetosure as to an matters req be disclosed. The appucant shan sign cluty ucensee by whon. the appucant effecta, criticality indications. rescur-operator duues performed by each fa. statements required by paragraphs e empto*'ed that states in detau ity coefficienta, and poison effecta. cility He:ensee and contained in its f L e appucant's addition-(2) General design features of the training program and from informa-i (nx 1) and (2) cf this secuon. since the denial and certi-core, including core structure, fuel ele-tion in the Final Safety Analysis e n23 1 ' %.g Angl..ppsera-Des that the appHcant is ready for re-menta, control rods, core instrumenta-Report, sytem description manuals examination. An applicant may flied a Con, and coolant flow. and operating procedures, facility 11-l'*"- (n) Jtentrements foe the appmeal of third appucation six months after the (3) Mechanical componenta and cense and Heense amendments. IJcens-4 date of denial of the second applica-dealen features of the reactor primary ee Event Reporta and other materials sa actual appheafson. The Uon, and may file further successLve system. requested from the facility licensee by sion sul approve an initial apnHe* uons two years after the date (4) Secondary coolant and aux 111ary the Comminatan. for a license permant to the & denial of each prior appucation. systems that affect the facility. (b) The written examint.tlon for a tions in this part.11It finds W (1) HealtA. The appucan 3 he appucant shall submit each suc-(5) Pacility operating characteristics senior operator for a facility will in-cessive applicauon on Form NRC-396 during steady state and trans*mt con-clude a representative sample from condition and general heal not adversely aficct the performance of and include a statement of additloc

• d1 dons, including coolant chemistry, among the following seven items and andsned operator job duucs w "

causes and etfccts of temperature, the 14 items spe.:1 fled in i 55.41 of this operational ermm N Ac (b) An appucant she has passed pressure and reactivity changes, ef-part. to the extent appHemble to the either the written e=*mina"en or op' fecta of load changes, and operaung facility: bealth and safety. The an 50 51 l.

1 -. _.. _ _ -. _ _ _ = _. _ _ _ I l I' I O CPR Ch. I p.1-88 Edha) WE.*^ -r Commission f55A5 1 355A5 I (3) Identify annunciators and condi. license and amendmenta are not vio-Ly will conform with paragraph l (1) Conditions and 11:nitauons in h uonhacating signals and perform ap. lated. (bM1XD or (bMIX1D of this sectli.a at , gecinty license. DNPe nmedial actions where ap-(b) Iwaplementation-.(1) Aduttaistra. the time of application. I (2) Faciuty operaung lignitations in tson. The operating test will be mam:n. (11) Those appilcants which propose l me tnhnical spedfacauons and their y the instrument rtan syn. Estered in a plant walkthrough and in to conform with paragraph (bXIXD of hears. tems and the signiftemwe of faculty eRhn-this 6 mt later man M days (3) Facility 1kensee proceduns e instrument read 1*.4s. (D A simulation facility which the before the date when the appHeant ' {utred to obtain authertty for desigu i

5) Observe and safely commt the O=dW has awed for une pmposes mat the Cansnimion conduct pd opraung changes in the faciuty.

operaung behavior characteristics of after appilcation has been made by operating tests, shall submit an appil-m pm-h baards that may arise the facality laccru c.or canon for use of its simulation facility i I normal and abnormal situa-m perth cocrot manipulations (1D A simulat. a facility c "t= to the NRC. In accordance with para-I dwingincidna maintenance acuvices utnd to obtain aestred operating solely of a plant-scierenced almultator graph (bX4XD of this section. I amt various contaminattaa #"* ults during rarmal. abnormal, and ahleta has been cerufled to the Com-till) Those applicants which propose ,I d) Amnessment of facility condRions

• • 1. *"cy attuauons.

misalon by the fad 11ty licensee. to conform with paragraph (bM1X1D j mod selnUN1 riate proce-wwMpW (2) Schedale for facility licensees. (D of this section, not later than 60 days '7' dures during remov ysm including primary Within one year after the effective before the date when the appHeant and emnersency sa ency coolant. and decay date of this part, each faculty Heenace proposes that NRC conduct operaung d) Proceduns and limitations in-heat removal systems and id+ntify the which proposes to une a simulauon fa-testa, shall submit a certification for j volved in tatual core og. altn-relations of the, roper operation of cility pursuant to paragraph (bM1XD use of its almulatfor* facility to the attons in core confW C# these systems to me WCrauon of the of this section, except test and re. Commleston on Wrm NRC-4*l4. In ae-t 4 red M search reactors, shall submit a plan by cordance with paragraph (bMSXi) of (8) ety operate the facinty's aux-w hich its almulation facility will be de-this section. of various in and ternal ef-fccts on core rencOMty. 111ary an cane gency systems. includ. veloped and by which an

"Ic='t

(4) Appiscaffos for and ag'pmtel of (1) Fuct handling facin pm_ ing operat g ontrols muoci-w1L be submitted for its use. sintasfallom faciliffeJ. 'Diose facility 11 cedures. Std *RI* Dl""t ulpment that could U ' Those facility Ilcensees which censees which propose, in accordance afInt reactivity me nicane of ra-propoac to conform with paragraph with paragraph (bMIXD of this ace- ) $WS Orrmung Ansa. doncude materials to the environ-(bX1MI) of this section. not later than tion, to use a simulation facility that is 42 months after the effective date of other than solely a plant-referenced gal Coalcat. The operating tests ad-ment. em =tned to =T e=nta for openter to Ntrate or describe the use this rule, shall submit an appilcation simulator as defined in 3 55.4 shall-it W seMor operator licenses in enord-ami funcumn af the facility s radladon for use of this shnulauon facility to (D In accordance with the plan sub. tale ding fixed the r%==M'an, in accordance with mitted pursuant to paragraph (bX2XD ance m4th paragrapia tbX1) of thh see-Jl uon are generany simi'=r in scope. rad rs and h porta. paragraph (bX4 XD of this section. or (bX3XD of this section, as applica-Ihe content utn be identified. in part. ble survey lastmments, argi personnel Ulu Those faculty Mcenaces which ble submit an application for approval from learning obWes med W MW propose to conform with paragraph of the simulation facility to the Com-knowledge of hig-HaMIXtu of mis antion. not later than mission. in acewdance with the sched-l a systemt& analysis of M " nificant ramattan hazards. tr.cluding 46 months after the effective date of ute in paragraph (bX2XiD or (bM3X1D O ator or senior otator duties per-i f.wmed by each fact:ity licensee and permbsibic lev is in excess of those this rv'c shall submit a certification of this section, as appropriate. This contained in its training program and author 1=cd. y to puform for use of this simulation facility to application must inclade-t from info mation in the Final Safety omn prd n to reduce exceshgve the Commission on Wrm NRC-474 (A) A statement that the simuladon i Analysis Report, system descripUon gewh of uon and to guard

• Simulation Facility Certificadon." facility meets the plan submitted to

~ available from Fublication Services the Cama 'Mn pursuant to para-manuals and open:, ting procedures fa-against pasonneI exposure. rate knowledge of the Sectim. Docuruent Management graph (bx2XD or (bM3XD of this sec-ciuty bcense and Dcense amendmenta. l w Der.s Reports and omn ama-emnsency plan foi the facinty. in. Brancia. Divialon of Technical Infor-tion, as applicable; f terials requested from the faclMty 11-ciuding. as appNpriate the operator's mation and Document Control. U.S. (D) A descripUon of the components censee by the C-mw-The oper-or sents r*s r esponsibuity to Nucicar Reguin:.ery Commission, of the simulation facility which are in-mung test. to the entent appucabic. m sinMe

• M e Ian should be ca.

Washington. DC 20>55. In accordance tended to be used for each part of the e me appucant to demonstrate an ecuted and t duties under the plan with paragraph ibMhXD of this sec-operating test; =mf uon. i understand *ng of and the abmty to MM (C) A description of the performance { perform the actions nuessary to ac-( a2) Ntrate the knowledae and (iv) The simutauon facility portion tests as part of the application, and l compthh a representauve sample front ahthty as priate to the assigned of the operating test wtll not be ad-the resulta of such te tts. f among the fouoming t3 ttemt 906100L O t rWDugues ministered on other than a certified or (!D The Commissitn wt11 approve a i u, perform pre.atartuo procedures amecmed me are operation of an approved sir-uh.tlon facility after simulation facility 11 it finds that the May 26.1991. simulation facility and its proposed i for the facinty, including operaung d W Mub mone centrols..awinted alth pts.nt (13) trate the appilcant's (3) Sctwdade for factlify applicants. une are suitable fer the conduct of op-in the control (1) For facility licenace applications erating tests for the factilty lacensee's Wpment mat could af fect reactivity. abuity 1 te to the an. after the effective date of this rule, reference plant, in accordance with (2) Manipulate the coruole controls mm N ,ed to operate the facility be. sigwd posttion. in such a way that the except tcat and research reactorm, the paragraph (a) of this sectio a. shutdown and de= Dated power ! y rocedures are ad-applicant shall submit a plan which (IID Submit, every four years on the go i 11mitauons la its idenufles whether 1 e almulatlers facill-anniversary of the appurmelan a j ee wh. 53 i . 'd

13 Cf 8 Ch ' U-'-as Edition) Nedeer Regv8efery Comaminden gg 555A7 (1) lias had externive actual operat-(a) Neither the license nor t.ny right paratrsph (bx2Xull or (bx3xhD of ing experience at a contparable facill-under the license may be assigned or report to the C"am"^n ahich iden-this secima. as applicable. ty as determined by the Commission, otherwise transferred. tifies any unwrrected performance test fanures, and submit a schedule for u1) Submit, every four years on the

• MA L*o
• cars thrfore the date of ap-ib) The bcense is limited to the facil-correctao
• of these performance test ant.iversa y of the certificauon. a plicauon; ity for which it is issued.

report to the Commission which iden, (2) Has dhchad his or her nspon-(c) The license is limited to those fanures.1f any. (IV ) Retain the results of the per. Lines any uncorrected performance I c ntrols of the facility specif1=d in the test fatlurea. and submit a schedule for 1 o n do so license. formarn test conducted untI four correction of such performance test g g years af ter the submittal of the app 11-(d) The license is subject to, and the failures.if any. dures for and is 2uallfled to operate Icensee shall observe all app!! cable cauon under paragraph (bx4FD. each report pursuant to paragraph (11D Retain the results of the per-tempetently and safely the facility rules. ret"'*^na_ and orders of the (DMWul), or any reapplication under formance test corducted ua til four ukd in W whh pa, wraph (bm4M1v) of this mestion as years siter the sutxnittal of certifica-(b) The Commisalon may accept as (e) If a licenset has not been actively Uon t.nder paragraph (bx5xD. cach proof of W WM's M We performing the functions of an opera-appcopriate. report pursuant to paragraph ante a certification of an authorised tor or senior operator. the licensee (v) If the Comrsiasson determines, (bxSxID. or recertific stion under pam representauve of the faculty licensee bened upon the renats of performance graph (bx5xv) of this section, as a? or of a holder of an authortvattan by may not resume activities authorised testing, that an approved simulation shich the applicant was previously by a license issued under this part facility does not meet the require-W= Me. except as permitted by paragraph (f) (iv) If the Commission determines. employed. The certifiestion must con-ments of this part, the J!mulation fa-based upon the results of performance tain a description of the applicant's of this section. To maintain active cility may not be used to conduct oper-testing. that a certined simulation fa-operating experience. including an ap. status, the Hcensee shall actively per-ating testa. cnity does not meet the requirementa proximate number of hours the appH-form the functions of an oper= tor or (vil If the C==wwn determines, of this part. the simulation facility cant operated the controls of the facil. senior operator on a minimum of pursuant to paragrzph (bM4 xv) of this may not be used to conduct operating ity, the duties performed and the seven 8-hour or five 12-hour shifta per secuon. that an approved simulation extent of the applicant's responsib11 calendar quarter. Por test and re-fr.c111ty does not meet the require. If the Commiulon determines. Ity. search reactors, the licensee shall ac-testa. may again sebr. tit an spplication for pursuant to paragraph (bx5xlv) of (c) The On==i"h may accept as tively per"orm '.17 functions of an op. (v) ments of this part the facius* Ucensee proof of the appHcant's current quall-erator or senior operator for a mini-approval "Ihis appucAtlon must in-this section. that a certified simniation facility does not meet the require-fications a certificarian of an author. mum of four hours per calendar quar-tzed representative of the facility 11-ter. clude a descript.on of corrective ac-ments of this part, the facility licensee censee or of a holder of an authortza-(f) If paragraph (e) of this section is e tions taken. Including results of com-may submit a recertification to the tion where the applicant's services will not met before resumption of func-pleted performance testing as required C=="tan on Form NRC-4"J4. This be utllized. tions acthorized by a license issued for approral recertifV=rtan must include a descrip-under this part, an authorized repre-ntD Any appe=th or report sub-tion of corrective actions taken, in-8 SS lategrity of e===a=.unas w sentative of the facility licensee shall mitted pursuant to paragraphs (b114xD. (bx4M11D and (bM4Mv1, of ciuding results of completed perform-certify the following-ance testing as required for recertifica-Applicanta, licensees. Lnd facility 11-(1) That the qualifications and this section must inc1mic a descriptien Lion. censees shall not engage in any activi-status of the licensee are current and of the gerformance testing completui (vil Any certdication report, or re. ty that compromises the integrity of vano; and for the simn!= Mon facility, armi must certincation.ubautted pursuant to

• RY application. test or ex==tna"^a (2) That the licensee has completed include a description of performance testa.1f dUferent to be conducted on paragraph (bx5 xD, (bkSx tD or required by this part.

a minimum of 40 hours of shift func-(bX5Mv) of this section must include a tions under the direction of an opera-the simulauon fac31ty during the sub. description of performance testing Sub ert F-Licenses tor or senior operator as appropriate sequent four year period, and a sched. compkted for the simulation facnity. t and in the pcsition to which 'he indi-une foc the moduct of approxNat,1y anc must tactude a description cf the , M ,****mee of h vidual wul be assigned. The 40 hours 25 percent of the performance testa performance tests. If different. to be coaducted on the simulation fackhty Operator and senior opernfor 21 must have included a complete tour of per Scar for the subcquent fou= during the subequent fo -yeaf ceues. If the C^=='==h deterinines the plant and all required shift turn-y

45) Certt4cataos of smuIation facah-period, and a schedule for the conduct that an appucant for an operator 11 over procedures. hr senior coerators of approxanately

.3 percent of the cense or a senior operator license limited to fuel hand!!ng under parm-facs. ~1hore faciuty licensees s hich meets the requirements of the Act and graph (c) of this section one shift g;ropoac"in accordance with paragraph performance testa per year for the its rerMaHans.11 M11 tasue a license in must have been completed. For tcat (bulxu) of this section. to use a simu_ subequent four year.t the form and containing any cond1 and research reactors a minimum of lauon faci!!ty consisting solely of a p:antwierer ed simulator as defined e n47 Waner of es====m-ang tent re-tions and tunitations it considers ap. six hours must have been completed. repriate and necemmary. (g) The licensee shall notify the 'lairenacaca, Commission within 30 days about a m Met a certifhNo to the (a) On apetW"^n the C = =i"'^^ g u gu, __,g conviction for a felon ~. C-=wwn that the simulation taciu-may waive any or an of the require-Each license contains and is subject (5) The licensee shall complete a re-ty meets the C - = " h 's reguia-ments for a written c===in-mn and to the following conditions whether qualification program as described by Uons. The facinty Ucensee shan pro-operating test. If it finds that the ap-a ated in the license or not: 5 55.59. vide ttus certificatinn on Form NRC-m in accorr*mnce with the schedule in NW nt-- 55 54

- _ _ _ _ ~ (1) the arttien examinsuon will phases in scope and depth of cow

• rage (1)he Deensee shall have o biensdal licensee or holder of an authorizauon as.mple the flesna specified in ll S641 la needed in the fonowing sub) sets-ancescal examilnation, by which the 12ensee has been em.

and 55.43 of this part to the catent (1) Theory and principles of oper-US he tacensee shan== ply with ployed. applicable to the faculty. the licensee. anon. any other condiuons that the Comunts-(C) Prov1& certification by the facil-and any Hm!*.auon of the license under (11) General and specific plant oper-seen snay tempose to protect health or Ity Heennee of medical condition and I Wc) M mis part, ating characteristem. to unicisalme daneer to life or property. sencral health on Wrm NRC-398 to UI) The operating test will require (IH) Plant instrussentation and m comply with Il 55.21. 55.23 and 55.27.

• D*I**

8'"I*f 8 0' " 88' I* trol systeens. (blThe Ucenac will be renewed if tty ate an ur.derstanding of and gg,3 pg,,g,,,,,,g,,,,,g,,,,

6) Each operator Heense and senior Commision f1Ms mat ~

(v) Enstneered safety systeens. operator license emptres six yws after (1) he smedical condluon and the essary to acc=r =h a - m (vD Nwomal, abnoramal, and emer-m.-. _ the date of losuance. upon tersminnuen eenunue mammene of Steens specified *i i SS.46(a) sency operating am of eenployunent with the facinty licens-

• • • ** * * """ *DC'*U'"*I (2) through (13) inclusive to the (vil) Paantlan control and safety.

ee or upon deterandnauon by the factl-mws a en anger ptakic heaMh extent applicable to the facility. (vill) Tect alcal specifamilana Ity Mcensee that the licensed Individ-and safety. The Commission util base uit) In lleu of the Connaission ac. unt no longer necia to maintain a 11-mis finding upon the ceruDe='ims by cepung a ceruficadon by the facility (1x) Applicable portions of Title it. er=ame. e fac1Hty Ucensee as dentbed in licensee that the Dcensee has passed Chapter I. Code of Federal Jtcyads-c) If a Heensee fuss an anntarminMn 35533. written enamannations and operaung fions. for renewal or an upgrade of an exist-(2)The h tests administered by the facility 11-(3) On-theJob tre. infos. The requall-Ing utense on Forsa NRC-396 at least it) is capable of continutng to com-censee =tthin its r'a==n= ansi.ap-ficauon programa must include on-the-Je days before the expirauon of the pctently and safely assurc* licensed proved ptsgraan developed by using a job trainhin so that-- utsung Ucense. It e%es not expire systeens approach to training under (I) Each lleensed operator of a utili-dt>Ues; untu *=pa=atless of the appitmtlan for paragraph (c) of this sect %n. the Cona-smuon facility manipulases the plant renewal or for an upgraded Mcense has di) Has successfuny conapleted a re-miniaton may administer a comprehen-controls and each Ucensed sernlor oper-been finally determined by the Coun-quaufseation prograrn that has been sive recualificauon writtA n eMaEaIna-ator either manipulates the controls =a==ta= Fulas by saan oc telegrasa approved by the Commisatort as re. tion and an annual opermu.rg test. Or directs the acuviues of individuals win be deemed to be cosaplete at the quired by I S5.59 and (b) Addiuomal trataine. If the re. during t'. ant control man:W='" -- (kee the appilmalan is depostted in (111) Has passed the requalificulon quirennenta of paragraphs (s) (1) and during the terna M the Heensed opera-the snail or with a telegraph company. ex= ='a=U ~ns and annual operaung (2) of this section are not met, the tor's or senior operator's license. Pbr tests as required by i 55.59. Pan =8-tant may require the Ucenen reactor operators and sen.or operators. 86 Esmemmiet h (iv) Has passed a comprehensive re-to complete additional training and to these --T 'llons must consist. Of 6t he appucent for reaewal of a 11-qushficatlon written exanalnauon and submit evidence to me Cw===n==taan of the followtang control manipulations ee ine shan~ ope.mung test =d - 'a*='> red by the suaessful compleuen of tinas trainQ and plant evolutions if they are appt!- (1) Cosaplete and sign Pbrum NRC-r'~a=*=Ma durics the term of a six-before returning to licensed duues. g g, g pg,,g gg g 308 and include the====8=r of the 11-year :3 cense. (c) JteemeL/lcat60s progrens We scribed in paragraphs (cM3Xi) (A) cense for which renewalis sought. (3) There is a conWued need for a meats. A facility licensee shan have a 'hrousia (L) of this section must be (2) Puc an cristr*al and two copies of Ucensee to operate or fo-a h op-requa Dcanon progues u-- and performed annually all other items Forma NRC-398 with the appropriate crator to direct operators at the facul-appr ved by the Coom=1==8an. The e-must be perforaded on a two. year Regional Adeninistator specified in ty designated in the app!!cauon. cycle. However, the requaliftentian (4) The past perfortnance of the 11-u D'*8""" "'# C""I"I " I"'" % g_j _ ,g g cennee as sa sfacWy o the through ('l) of this accuen. In Heu of that each MM M perfwna or ar=*='it's experlerace umb the exist-C ^ ' In mak na its finding, the paragraphs (c) (2). (3). and (4) of this 8"I*I""C""

1. ' "I

'~ Eng Ucenne W the wewe U "C D E8 'V8 ""~ section the Cn==landon may approve Ity cont.*l ananipulations Jased on the nuenber of hotsrs t*nat the licensee has on infwmau"on such as notices of vio-a prosraca e.rveloped by using a sys-availalL11ty of plant equipenerst and operated the facirt, 1*f "na r letters o reprfmand in the tems approach to training. systerns. Those control riantoubtlons (C) Provide a awtrument by an au-censee's dodet. (1) Schedade. The requeuficauon which are not p(rfasmed at the. tant 9 thorised irs.-Ant *ve of the facBity program must be conducted for a con-may k perfwmed on a simulator.The Ikensee that dur".s the effecuve term I N tinuous period not to exceed two use of the Techalcal Spmificauens of the current Deense the anprir.., (at Jtaqueltftcation regairennemis. years, and upon conclus40n unust be should be maxisalmed during the almu-has saumfactortly e---- M-M the requa. 11fkation progress for' the faculty for Eacfa licensee shall-promptly fonowed. pursuant to a con. Inter contro; ananipd=**m=_ Senior op-which operator or mentor operator D-(1) Successfully complete a requaltit-unuous achedule, by successive requa-erator licensees e+e credited with cation program developed by the facil-11fication programs. these activities if they direct cos.*.rol (2) Lectures. The requalificauon pro. eense renewal is southt. (5) Provide evidence that the appu-Ity licensee that has been approved by manipuladons as thef are performed. ennt has discharsed the Heense re. the C '% This r,rogram shan gra:a must incl.:dcr pr planned le (A) Plant or reach sisrtups to in-tures on a regular and continuing basis sponsibultles coespetently and safety, be conducted for a centinuous period clude a range that reactivity feedbacit thrournout the license period in thone De Canassf==tara saay accept as ers-not to exceed 24 moaths in d aradon. from nuclear heat addition is notices-areas arhere operator and senior oper. the sce cant's having anet (2) Psas a comprehensive requa!! fica, star written examinations and facility ble and hentup rate is established. u dence 04 this swasat a certificate of an au-tion wrtite::, examination and an operating expertence indicate that em-(B) Plant shutdown. thortsed representative of the facihty annual opeas*Ing test. 57 M w m v w--w-m u-m-- --.~wv v v= s - ww wn wv-- m te-ywm--- s-wao w----e +-

m s 10 CFR Ch. I (1-1-88 Edidet) W"."^-rr"* { 55M $ 55.59

68) Each licensed operator and plished by using the control fianel of (111P ff there is a confIlet between the (C) Manual control of steam genera-the fac111tr invcited or by umsnqr a alm-Commvalon's regulattans in thIs part, tors or feedwater or both during start-senior operator has demonstrated sat,-

namfor. Where the control panel of the and any license condition, or other 1sfactory understanding of the oper. up and shutdown. allon c" the apparatus and mecna-facil;ty is used for simninth the ac-written Cosp=laulan approval or au-(D) Boration or dilution during Uons ".aken or to be taken for the thortsatlan pertaining to the retet lon nisms associated with the control ma-power operation. nipulations in paragraph (ex3x1) of emergene/ o- % normal condition period for the masse type of record, the changes in manual rod control or re-this section, and knows the operating shall be disc 4 vtual manipulat taan retention period specified for these (E) Significant 610 percent) power procedures in each area for which the of the plant con * 's is not required. If records by the regulations in th part circulatlan flow. operator or senior operator is licensed. a simulator is used in meeting the re-apply unless the 'V---*n pursu-l cent or greater where load change is (11D Each Ilcensed operator and quiremea =, paragraph (cx4x111) of ant to 5 55.11, grants a specific enesap-(P) Reactor powet ange of 10 per-performed with load limit control or senior operator is cognizant of facility this se-t - n shall accurately repro. tion from this record retention re-where flux. temperature or speed con- <lesign changes. procedure changes. duce f he %-sar' w citaracteristics of quirement. trol is on manual (for IITGR). and f acility license changes. the facility Invd n 0 and the arrange-(8) Alleenefice fraisima proprusts. tiv) Each licensed operator and ment of the last. mentauon and an-The requirements of thia section osay

40) has of coolant. Including-senior operator reviews the contents trols of the alma =lamr shall clamely par-be met by requaliftentian prograses et all abnormal and c nergency proce-allel that of the facility involved. conducted by persons other than the

(!) Strnificant PWR steam genera-torleaks dures on a regularly scheduled hamin After the prortslons of 5 55.45(b) have facility licensee if the requalification (v) A simulator may be used in meet-been implemented at a facility. the programs are aimflar to the progress (2) Inside and outside primary con-tainment ing the requirements of paingraplis (c) certlfled or apprmed simulation facill-described in paragraphs (c) (I) (3 xt) and (3xtD of this section, if it re-ty must be used to comply with this through (51 of this secuon and the al-(3) 1arge and small. including lead-l ternadve program has been approM rate determinadon produces the general operating char-paragraph. (d) Saturated reactor molant r=- by the Conamtamian acterisucs of the facility involved and (v) Provisions for each licensed oper. i l sponse (PWR). the arrangement of the instrumenta-ator and senior operator to paresempat, ('l) ApplicsMitty to research and fast (II) Loss of instrument air (if simu-tion and controls of the simulator is 1st an accelerated requauflemilan pro. resefor facilities. To meen==adar, lated plant specific). slmtlar to that of the fac111ty involved. gram where perim evaluations speciallmed esodes of opermuon and dif-ferences in control. equipenent, and (1) bss of clatrical power (or de-If the simulator or simulation device is conducted pursuant to paragrapM operator sklus and knowledge, the re-graded power sources). used to administer operating tests for (ex4) (D through Uv) of this section (J) uns of core coolrmt flow / natural qualiftentian protrass for each H-a facility, as provided in i 55.45 (bMI). clearly Indkated the need. censed operator and senior operator of circulation. (K) Ioss of feedwater (normal and the device approved to meet the re-

45) Recorda "Ihe requaHficattan pro-a research reactor or test reactor facil.

quirements of 5 55.45(bx 1) must be gram documentauon must include the Ity must conform generally but need emercency). used for credit to be given for meeung following-not be identical to the requallftentian (I ) has of service water, if required the require *nents of paragraphs (D The facf ttry licensee shall main-program outlined in paragraphs (c) (1) for safety. (ex3xD (O through AA) of this sec-ta h r rds documenUng h W. through (6) of this auction. Signifkant iM) Loss of shutdown cooling. (N) Iess of component cooling tion. pation of each Heensed operator and devimflans from the requi.wts of gystem or coonng to an individual (4) Esialuation. The requalification smlor operator in h edisc% paragraphs (c) (1) through (6) of this progr'am nus. incth progrs m. 'Ihe records must contain section will be permitted only if sup-cotaponent. (O) Iose of normal feedwater or ID Comprehensive requalification copg og g g posted by written jusuflemilan and ap-normal feedwater system failure. written esaminations and annus t oper- !s the answns sim W h U-proved by therammissaan ating tests which determine areas in g g (P)Iess of condenser vacuum. which retraining is nuded to upgrade ud& a m M e m m (Q) Ioss of protect 1re system chan-licensed operator and senior operator g na.mm. m ga peL Beweedien d Moses (R) Mispositioned control rod or knowledge. laterad in areas in elch an opentor (ID Written examinations which de-rods (or rod dropst termine licensed operators' and senlo cy,,cge,,.Ihe factllty licensee shall IKal MeetAcealse and revaeadam of 5-(S) Inabdity to drive control rods, (T) Conditions requiring use of everators' knoaledge of subjects cov-nialn mese mrds untH me opers emergency boration or standby 11guld cred in the requalification prvram Ws w senlw Wa Heense la re-(a) The terms and conditions c.! all and provide a basis for evaluating newed. licenses are subject to amendment, re-control system. (U) Puel cladding failure or high ac-their knowledge of atmormal and (11) Each record required by this part vision, or modificattan by reason of Uvity in reactor coolant or offras. emergency procedurca. must be legible throughout the reten-rules, reget='te=_ or orders issued in (V) Turbine or generator trip. E lli) Systematic observation and eval, tion period specified by each Coesmis-accordance with the Act or any (W) Malfuncilo. of an automatic untion of the performance and compe. alon regulauon.The reewd may be the amendments thereto. control system that affects reactivity. tency of licensed operators and senior original or e reproduad copy or a al-(b) Any license may be rewcAed, sus-(X). Malfunction of reactor coolant operators by supervisors and/or train-croform provided that the copy or mi-pended, or modified, in whole or in ing staff members, includ ag evalua-Wwm is aumenucated by aumor-part-pressure / volume control system. tion of acUons taken or to be taken taed personnel and that the microform (1) Pbr any material fr.Ine statement (Y) Heactor trip. during actual or simuir'ed abnormaj la capable of prodocing a clear copy in the appucation or in any statemerA (Z) Main steam line break (inalde or and emergency procedur.L Wroughout the rguired retenuon of fact required under sectica I42 of outJde.antainment). Uv) Simulation of emergency or ab. ( AA) A nuclear Instrumentation fall-period. the Act. normal conditions thkt may be amom-ure. 59 58

(3) neesume of corullUons revealed by e 6-c. -se n ~=- N

• • • "'""eman and Assemand hemme 3aeses ee t Dr,,s, temuns.

i the appilmtioen or statenment of fact or PM OF N s any W 6 inspecUort w h RASSOACTNE W"STES NG 950-es.el Freetenen et infar==sm= e0.343 asonstortas and *-=nw weste post-means that M warrant 1M h LO90CR N ORE 5 es es state review. ases-nen at a=iln tacense restese. ennesson to refuse to grant a lleense on es.e3 Par e es.e4 Mouw to Stalm Sehpast S-Omemy Assemanas an original applicatlon. es.se Heynern amn a (3) For willful wk%Llots of or failure gg_ gg a a supases.Temen.and es.151 Appilcability. to observe any of the terms and conds-g,c_ Uons of the Act, or the license, cr of es 1 Purpene and scope. smayesseems 8e.152 '- # "'-" any rule, regninflaa or order of the so 2 Definsuona. se 71 General recorditeepins and reportans sehpare IS Treamhne and rh of Coenslaulon.or 80.3 IJcense requirnt_ Peroommel '*3u (0) Pbr any conduct deterunined by 09.4 Com enunicauons. the Counndesion to be a hasard to safe 80.5 Interpretauona. g g,,,,,,,g 4,m e0.s Excenptsons. so.74 Testa-e0.tet Ivaintna and certiftranian programs. og,erauon of the facility. 403 IJwnee not resu8 nf tw wn.aast ts'*- e0.75 Inspecuana. 00.le2 Phyelcal. ~ C."a. t Se e Reports reeerditerpins. and appInen-sehpase e-Teshemsed Cseemste 3,g,,,,. - p Plummime Csdnesem [e'eservedi es.let Purpose and nature of findensa B5L71 vi.a.na utred. ee 302 Cancepts. <,) An injuncuan or outer court es.e neonorment prosecuan. ^ es Stat e'se ~ ~ 2 o'33 e ec.19 Completences and accaracy of infor-Punecessascu Omrecvives te2. order many be obtained prohibiting any violation of any provision of: 13 Performance of tw seeleste repeas-e53. es4. as amended 442 UAC. 2871. 2873 mauen. Imry operauons area throussi pennanent 2002 2e83. 2o05. 2111. 2201. 2232. 22331 (1) ne Atomic Energy Act of 1954 g,,,,,,, g, seca. 202. 208.se Stat. 1244.124e 442 UAC caemure 5842. Soest arcs. It and 14. PutA L e6-est, as amerxled, 80.112 Overall system performance ob)se. e2 Stat. 2e51 a 42 UAC 2021s and 5451 t sec. (2) Title 11 of the Energy Reorgani-Persreuem*10m Raview uve for the e.enoste repomPary after per-102. Pub. L el-loo. e3 Stat. e53 442 UAC smuon Act of 1974, as are or e015 Site characterization-unanent closure 4332t sec.121. Putt L e7-425. se Stat 222e (3) Any regulation or order lastaed e0 go s.g,charactertzauan plan required. se 313 ;w, r.= ef partacular barriers under these Acts. co.17 Contents of site characterseastaen after permanent closure. 442 UAC 10141 A Per the purpours of asc 223. es Stat. set, C) A court order snay be obtained plass. I'ans Owwensure ame Cowreat as amended a42 UAC 2273t ll40.10. 80.71 80.le Review of site charactertsadon activt. tace-80.121 ewnernhap and to 80 '~ for the payment of a civil penalty im. 2 C. 2201( posed under section 234 of the Aomic w es m 13ees. N 25. M 1. W srnes Carrumma NN 53 5 6.31.82.101 80E content of Wu-- e0.122 Siting crtteria. 103,104.107. or 109 of the Atomic 00.22 Filing and distributson of applicauon. so aminata n s 7tson. p,,,,, c,,,,,,,,,,,,, o.,,,,c,5 WA O _- - JW 2)S of the Energy Reor-e0.24 Upda*. ins of appIA *.3en and environ-RaroerTony Orniarious Amma a eg.3 Perymme ased sco, pe. gsJilaatiott Act of 197C unental report. 80.130 Stepe of demisa crita%.or the eco-This part prescrilses rtiles swerning (3) Any rule, reguladon, or order notic rempomstory opermuons area. lasued under thene Acta-es.13: Generna dee criteria for the sco-the licensing of the UJS. Department Constnocvsom Avneostrarrow (4) Any term, conditloft, or I mita-48 21 Construct $on authertsation-w repoeltory sm" arm of Energy to receive and poemees tion of any license lasued under these 80.32 Condith.as o' eunstructSon authortma-80.132.$dditional dealsn crtteris for sur-anurte. special nuclear and byproduct 180n. face fartnues an the sceneste repeastery maternal at a ecologic repository oper-Acts; or e033 Annendment of watruction authort operatsons area. adons area sited. constructed, or oper-(5) Por any violadon for which a 11, e0.133 Adotuonal crtterta for the satt,n. sted in accordance with the Nuclear cense may be revolted under sectio 186 of the Atomic Energy Act. I.scasess Immusca aps Amenessar gosi g[ calan of armis for shafta mad bore. Waste Polley Act of 1962.

• nits part does not appy to any acWity IW he es.

(c) Any persors who willfully violates se 41 Standards for immuance of a Incense' under another part of this chapter. any lon of the Atomic h ee.42 Conditsens of incen** Dunma Canvansa com vues Wasts Pacumes (St PR 27te2. July 30. leesi AC w any regulation immued uMa the 80.43 1Jcense spwificatson. sal 35 CrHer".m fw W wute W W Act, mcluding the regulations in this 60.44 Chanses, testa, and experiments. """'P""""" S ee 2 Deflaitlene. part, anay be guilty of a crirne and. 80 45 Amendment et Incense. upon, conviction, rnay be punished by 90 es Partscutar activttles requiring Incense Psaroessanca Comrisanavsom RaetussessTo 'b used in this part: fine or imprisonment, or both, as pro-amendment. 80.137 Oct eral requirementa for perform-

• • Accessible environment" means* W ance confirmation-he atmosphe c. (2) the land surface.

vided by law. Panssansser Cassoas (3) surface water. (4) oceans, and (5) S0.51 IJeanse amendment for permanent sets.sep _ e.se. m emmerA* W the portion of *he lithosphere that is outalde tne controlled area. 80.140 General requirements. to SJ of hcense 61 60

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