ML20246K357

Rev 2 to Reg Guide 1.8,Task OL 403-5, Qualification & Training of Personnel for Nuclear Power Plants

ML20246K357
Person / Time
Issue date:	04/30/1987
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-OL-403-5, TASK-RE REGGD-01.008, REGGD-1.008, NUDOCS 8907180147
Download: ML20246K357 (4)

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Revision 2*

U.S, NUCLEAR REGULATORY COMMISSION April 1987 4

1 #p/*'% GUIDE

%..m.. OFFICE OF NUCLEAR REGULATORY GUIDE 1.8 (Task OL 403 5)

QUALIFICATION AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS A. INTRODUCTION training cf nuclear power plant personnel. This standard was approved by the American National Standards Paragraph 50.34(b)(6)(i) of 10 CFR Part 50, " Domestic Institute (ANSI) Committee N18, Design Cr t for Licensing of Production and Utilization Facilities," requires Nuclear Power Plants, and designated ANSI Nis,. 1971, that an appbcation for a license to operate a nuclear " Selection and Training of Nuclear Power Plant Person-power plant include information concerning organizational nel." Regulatory Guide 1.8, " Personnel Selection and structure, personnel qualifications, and related matters. Training," endorsing ANSI N18.11971, was issued in Subpart D, " Applications," of 10 CFR Part SS," Operators' March 1971, and Revision I was issued in September Licenses," requires that operator license applications 1975. A revision of ANSI N18.1-1971 was subsequently include information concerning an individual's education approved by the ANSI Board of Standards Review and and experience and related matters. This regulatory guide designated ANSI /ANS-3.11978, " Selection and Training describes a method acceptable to the NRC staff for of Nuclear Power Plant Personnel."

complyirig with those portions of the Commission's regulations with recard to the traming and qualifications A first proposed Revision 2 to Regulatory Guide 1.8 of nuclear power picnt personnel. Persornel of test, endorsing ANSI /ANS-3.1 '1978 was issued for public traming, research, and moR'e reactors are not covered comment in February 1979. As a result of expent;nce by this regulatory guide. gained from the accident at Three Mile Island Unit 2 (TMI 2), additional public comments in the area of

( The Advisory Committee on Reactor Safeguards has personnel qualifications were requested on proposed been consulted concerning this guide and has concurred Revision 2 to Regulatory Guide 1.8 in May 1979. All

( in the regulatory position. of the comments from both requests were forwarded to the ANS 3 Subcommittee for its use during the develop-Any information collection activities mentioned in ment of a revision to ANSI /ANS-3.1-1978. Subsequent-this regulatory guide are contained as requirements in ly, Draft Standard ANS 3.1, dated December 6.1979, 10 CFR Parts 50 and 55, which provide the regulatory incorporating the upgraded requirements was issued. In basis for this guide. The information collection require- September 1980, public comments were requested on a ments in 10 CFR Part 50 have been approved under second proposed Revision 2 to Regulatory Guide 1.8 OMB Clearance No. 3150-011, those in 10 CFR Part that endorsed Draft Standard ANS 3.1. The public 55, under OMB Clearance No. 3150-0018. comments received were held in abeyance pending Commission action on proposed rules on operator B. DISCUSSION quahfications and licensing in SECY 81-84, "Qualifica-tion of Reactor Operators,"3 February 2,1981, and Subcommittee ANS-3, Reactor Operations, American SECY 81-84A, " Discussion of Revisions .to Reactor Nuclear Society Standards Committee, developed a Operator Qualifications,"8 June 15,1981. The Commis-standard contairung cnteria for the qualification and sion did not approve either of those proposah an.

directed the staff to continue to study the issue.

The substantial number of chan s in this revision has made it I knpeactical to indacste the changes wisNiines in the margin. Copics are available for inspection or e NRC Public Document Room,1717 H Street fW'.ing for a fee inDC.

, Washington, the P Q c C.

U$NRC REGULATORY GUfDES The guices are issued in the fossowing ten broad civisions:

@ A 9ulatory Guices are issued to oescribe and make available to the pubue metboos acceptabte to the NRC staff of implementing 2. Power Reactors so UG ='u t;" orth'ttasn," tit.um"t 'ru=vp=g:

a 6. Products i r=t7,".w,wa',tn l:,7es az"st,=i" es,,h NOZ tatto acc6 Guices cents { substitutes for regulationsor are no . and comprance to provice with guicance to appbcants. Peculatory

4. E'isironmental and $ sting g. Antitrust and Financial Reviem

@td thtm is not required. Methods and solutions different from those set S. Materials ana Plant Protect 6cn 10. General gg out in the guices will be acceptable if they provice a basis for the m O -tos:nse ey the Commission.sino6ngs requisite to the assuance or continuance rif a permitCopiesor of issued pulces may be purchased from the Government Printing ottice at ine current Gpo price. snferrnation on current g This sulce was issvec after cortsiceration of comrnents received from ig, the pubhc. Comments ano suggestions for improvertents in these cuEe s. U5. overrfrNent pr4Nfn*ghffee, os't f f ce ou 1

,g guio;s are encouraged at all times. and a 7082. Wasnington, DC 20033 7052, telephone (202)275 2o60 or a (202)275 2171 I iPoaf'#p'e,i n*c't. *'" **" **"""*"" '" guides * * *wlit

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.. During 1981, Draft Standard ANS 3.1 was updated to 10 CFR Part 50) and the requirement to have a shift factor in additional lessons hersed from the TMI 2 technical advisor (STA) available to the shift (NUREG-

. eccident and changing regulatory requirements. The 0737, l.A.I.1). One option in the Policy Statement, -

str,ndard was approved by the Aaserican Nuclear Society's which is preferred by the Commission, allows combining -

q' Nuclear Power Plant Standards Committee (NUPPSCO) the functions of the STA wi:h one of the required senior

.gnd the ANSI Board of Standards Review and was operators as long as specific. training and education reissued as ANSI /ANS 3.11981, " Selection, Quahfication requirements are met. The other option allows for con-and Training of Personnel for Nedear Power Plants."2 A tinuation of an approved independent STA program.

third proposed Revision 2 of Regulatory Guide 1.8 was Regulatory Position C.lj reflects the guidance provided developed to . endorse ANSI /ANS 3.1-1981 with certain in this Policy Statement, additions and exceptions and was issued for public com-ment in January 1985. As a result of the public com- C. REGULATORY POSITION

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ments and Commission actions concerning training and qualifications, this Revision 2 of Regulatory Guide 1.8 1. Positions in ANSI /ANS 3.11981 that Are Endorsed now endorses Sections 4.3.1.1, " Shift Supervisor," 4.3.1.2, by this Regulatory Guide

• Senior Operator," 4.5.1.2, "f ie==ed Operators," 4.4.8,

" Shift Technical Advisor," and 4.4.4, " Radiation Protec- For the positions listed in - ANSI /ANS-3.1 1981, ,

tion," of ANSI /ANS-3.1 1981. Endorsement for all other " Selection, Qualification and Training of Personnel for positions will remain with ANSI N18.11971, " Selection Nuclear Power Plants," as shift supervisor, senior opera-and Training of Nuclear Power Plant Personnel." The tor, licensed operator, and Shift technical advisor, the bases for the additions and exceptions to ANSI /ANS-3.1- requirements contained in the standard provide an 1981 are contained in NUREG0137, " Clarification of approach acceptable to the NRC staff for complying with TMI Artion Plan Requirements"3 which includes the the quahfications and training requirements of 10 CFR March 28,1980 letter to all power reactor applicants Parts 50 and 55 subject to the guidance regarding the and licen' sees regarding quahfication of reactor operators, STA function provided in the Commission's "Pohey gnd NUREG-0094, " Guide for the Licensing of Facility Statement on Engineering Expertise on Shift" and the Operators, including Senior Operators,"3 and the Commis- clarifications, additions, and exceptions in paragraphs a aion's " Policy Statement on Engineering Expertise on through k below. For radiation protection supervisory Shift" (50 FR 43621). The regulatory position related personnel, Section 4.4.4 of the standard contains an to the radiation protection manager is revised from what approach acceptable for the position of radiation protec-was included in Revision 1 of Regulatory Guide 1.8 (1975). tion manager (RPM) subject to the following:

The industry has adopted the requisite qualifications in )

ANSI /ANS 3.1 1981, and the current change endorses a. In lieu of the description in Section 5.1 of ANSI /

that industry position. ANS-3.1 1981, cold license examinations should be defined as those that are administered before the unit has com.

On March 20,1985, the Commission issued a " Policy pleted preoperational testing and initial operations as Statement on Training and Qualification of Nuclear described in its Final Safety Analysis Report as amended Power Plant Personnel" (50 FR 11147) that recog- and approved by the Commission. Hot examinations are nizes industry commitment to accredit training pro- those administered after this condition is attained.

grams. In the policy statement, the NRC endorsed the training accreditation program managed by the Institute b.' Hot license applicants must meet the training of Nuclear Power Operations (INFO) because it encom- elements in Sections 4.3.1.1.c, 4.3.1.2.c, and 4.5.1.2.c of passes the elements of performance-based traimng and the standard and the experience elements in Sections will provide the basis to ensure that personnel have 4.3.1.1.b, 4.3.1.2.b, and 4.5.1.2.b of the standard. Cold quahfications commensurate with the performance re- license applicants are subject to the training elements quirements of their jobs. The Commission has decided identified above, but they are exempt from the expe-to withhold action on promulgating new training and rience elements.

quahfications regulations during an evaluation period.

During that period NRC will continue to evaluate the c. Paragraph 2 of Section 4.3.1.1.s of ANSI /ANS 3.1 results of the accreditation program to determine if the 1981 is not applicable. An individual who meets the voluntary industry efforts ensure quahfications that meet Commission's " Policy Statement on Engineering Expertise or exceed the minimum standards included in this guide. on Shift" is required on all shifts to provide engineering expertise (see Regulatory Position C.I.j).

The Commission's " Policy Statement on Engineering Expertise on Shift" issued on October 28,1985 (50 FR d. The sununum educational requirement for shift 43621) provides two options for meeting nuclear power supervisors, Section 4.3.1.1.a and for senior operators, plant staffing requirements (paragraph 50.54(m)(2)(i) of Section 4.3.1.2.a. As a high school diploma or equivalent.

2 Copies may be obtained from the American Nuclear Society, e. An spplicant for a acnio'r operator (50) license j sss North Kensinston Avenue, Lecrease Park,IL sos 2s. should have 4 years of responsible power plant exper- I 3 Copies may be obtained from the Government Printina Office, Post ofhce aos 370s2, washington, Dc acon s.?os2. defined ~ as having actively performed as a designated 1.8 2

, control room operator (fossil or nuclear) or as a power STA has not actively performed, the STA should receive j plant staff engineer invahed in the day-to-day activities training sufficient to ensure that the STA is cognirant of ,

of the facihty during oc after the final year of construc- facility and procedure changes that occuned during the tion. A maalmum of 2 years of responsible power plant absence.

experience saay be fulfilled by academic or related tech- ,

nical training on a one-forene time basis. Two years should Cornbining the functions of a senior operator and the be nuclear power plant experience. At least 6 months of STA is acceptable if the provisions of the Commission's the nuclear power plant experience should be at the " Policy Statement on Engineering Expertise on Shift" I plant for which an applacant seeks a license. In addition, are met. In addition to the requirements specified in applicants for an 50 position not holding a bachelor's Section 4.4.8.c of ANSI /ANS-3.11981, the STA shoold degree in engineering or equivalent should have held an have specific training in the response to and analysis of operator's license and should have been actisely involved plant transients and accidents and training in the rela-in the performance of boensed duties for at least 1 year. tionship of accident conditions to offsite consequences and protective action strategies.

f. In addition to the requirements stated in Section 5.2.1.2.1 of ANSI /ANS-3.1-1981, classroom instruction k. The radiation protection manager should have the for all license applicants should include training in the qualifications described in Section 4.4.4 of ANSl/ANS-use of instaDed plant systems for the control and mitiga- 3.1 1981 with the clarification that 3 of the 4 yeatiof tion of an accident in which the core is severely damaged. experience in applied radiation protection should be professionallevel experience.

g. In addition to the requirements in Section 5.2.1.3.1

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of ANSI /ANS 3.1 1981, each applicant for an operator or 2. Positions in ANSI /ANS N18.11971 that Are Endorsed senior operator license sheadd serve 3 months as an extra by this Regulatory Guide person on shift in training for that position. These 3 months as an extra person on shift in training should For positions listed in the standard other than those include a!! rhases of day-to-day operations under the .under Regulatory Position 1 above, the requirements con-supervision of licensed personnel. tained in ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel," provide an approach

h. Control room operstmg experience for hot license acceptable to the NRC staff for complying with the quali-applicants, described in Section 5.2.1.3.1 of ANSI /ANS. fications and training requirements of 10 CFR Parts 50 3.11981, shmslWinclude mampulation of controls of the and $5.

• facility during a trurumum of five reactivity changes. Every effort should be made to have a diversity of reactivity D. IMPLEMENTATION changes for each applicant. Startups, shutdowns,large load changes, and changes in rod programming are some exam- The purpose of this section is to provide information pies and could be accomplished by manually using such to applicants and licensees regarding the NRC staff's systems as red control, chemical shim control, or recircu- plans for using this regulatory guide.

lation flow.

Applicants and licensees may propose means other

1. All cold license applicants should participate in than those specified in Section C of this guide for meet-practical wak assignments as described in Section 5.2.1.4 ing applicable regulations.

of ANSI /ANS-3.1-1981 for - a mmimum of 6 months.

j. In addition to the responsibilities described in Sec- Except in those cases in which the applicant or licensee ti.on 4.4.8 of ANSI /ANS 3.11981, the STA should assume proposes an acceptable alternative means of complying an active sole in shift activities. For example, the STA with the Commission's regulations specified in Section A, should review plant logs, participate in shift turnover, the guidance provided in Section C has been approved 1 and maintain awareness of plant configuration and status. ifor use by the staff after March 31, 1988, in the evalua- 1 The educational requirements for the STA specified in tion of the qualifications and traming requirements for l Section 4.4.8.a of ANSI /ANS3.11981 are not appli- (1) nuclear power plant personnel as described in appli-cable. An independent STA should have a bachelor's cations for an operating license, (2) applicants for opera-degree or equivalent in a scientific or engineering discipline. tot and senior operator licenses, and (3) replacement personnel in those positions in operating nuclear power

" Actively performing STA functbns" means perform- plants whose training programs have not yet been accred-ing at least three shifts per quarter as the STA. If an ited by an accreditation program endorsed by the NRC.

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VALUE/ IMPACT ANALYSIS V

A separate value/ impact analysis has not been prepared that time. This analysis is also appropriate to Revision 2 for this regulatory guide. A value/ impact analysis was of Regulatory Guide 1.8. A copy of the regulatory anal-included in the regulatory analysis for the amendments to ysis is available for inspection and copying fo? a fee at 10 CFR Part 55 published on March 25,1987, a copy the NRC Public Document Room,1717 H Street NW., ,

of which was placed in the Public Document Room at Washington, DC. I i

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UNITED STATES ,ine, c64.s was NUCLEAR REGULATORY COMMISSION Po87^',8,*J8s D WASHINGTON, D.C. 20555 was o c.

penurr e... om OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. 4300 I.

1.84 i

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