Regulatory Guide 1.8
| ML13350A382 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1987 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-1.008, Rev. 2 | |
| Download: ML13350A382 (4) | |
Revision 2*
U.S. NUCLEAR REGULATORY COMMISSION April 1987 REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 1.8 (Task OL 403-5)
QUALIFICATION AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS
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A. INTRODUCTION
Paragraph 50.34(b)(6)(i) of 10 CFR Part 50, "Domestic training of nuclear power plant personnel. This standard was approved by the American National Standards Institute (ANSI) Committee N18, Design Criteria for Licensing of Production and Utilization Facilities," requires Nuclear Power Plants, and designated ANSI N18.1-1971, that an application for a license to operate a nuclear "Selection and Training of Nuclear Power Plant Person- power plant include information concerning organizational net." Regulatory Guide 1.8, "Personnel Selection and structure, personnel qualifications, and related matters. Training," endorsing ANSI N18.1-1971, was issued in Subpart D, "Applications," of 10 CFR Part 55, "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-31-1978, "Selection and Training describes a method acceptable to the NRC staff for of Nuclear Power Plant Personnel."
complying with those portions of the Commission's regulations with regard to the training and qualifications A first proposed Revision 2 to Regulatory Guide 1.8 of nuclear power plant personnel. Personnel of test, endorsing ANSI/ANS-3.1-1978 was issued for public training, research, and mobile reactors are not covered comment in February 1979. As a result of experience 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
qualifications and licensing in SECY 81-84, "Qualifica- tion of Reactor Operators,"' 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,"' June 15, 1981. The Commis- standard containing criteria for the qualification and sion did not approve either of these proposals and directed the staff to continue to study the issue.
The substantial number of changes in this revision has made It Copies are available for inspection or cpylng for a fee in the impractical to Indicate the changes with lines in the margin. NRC Public Document Room, 1717 H Street NW., Washington, DC.
USNRC REGULATORY GUIDES The guides are Issued In the following ten broad divisions:
Regulatory Guides are Issued to describe and make available to the Public methods acceptable to the NRC staff of implementing 1. Power Reactors 6. Products specific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportation niques used by the staff In evaluating specific problems or postu- 3. Fuels and Materials Facilities 8. Occupational Health lated accidents or to provide guidance to applicants. Regulatory 4. En'ironmental and Siting 9. Antitrust and Financial Review Guldes are not substitutes for regulations, and compliance with 5. Materials and Plant Protection 10. General them Is not required. Methods and solutions different from those set out In the guides will be acceptable If they provide a basis for the findings requisite to the Issuance or continuance of a permit or Copies of issued guides may be purchased from the Government license by the Commission. Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of This guide was Issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for improvements In these 37082, Washington, DC 20013-7082, telephone (202)275-2060 or guides are encouraged at all times, and guides will be revised, as (202)275-2171.
appropriate, to accommodate comments and to reflect new Informa- tion or experience.
Issued guides may also be purchased from the National Technldl Written comments may be submitted to the Rules and Procedures Information Service on a standing order basiS. Details on this Branch, ORR ADM, U.S. Nuclear Regulatory Commission, service may be obtained by. writing NTIS, 5285 Port Royal: Road, Washington, 06 20555. . Springfield, VA 22161.
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 learned from the TMI-2 technical advisor (STA) available to the shift (NUREG-
accident and changing regulatory requirements. The 0737, L.A.t.l). One option in the Policy Statement.
standard was approved by the American Nuclear Society's which is pieferred by the Commission, allows combining Nuclear Power Plant Standards Committee (NUPPSCO) the functions of the STA with one of the required senior and the ANSI Board of Standards Review and was operators as long as specific training and education reissued as ANSI/ANS-3. 1-1981, "Selection, Qualification requirements are met. The other option allows for con- and Training of Personnel for Nuclear Power Plants." 2 A tinuation of anl approved independent STA program, third proposed Revision 2 of Regulatory Guide 1.8 was Regulatory Position C.I.j reflects the guidance provided developed to endorse ANSI/ANS-3.l-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
nients and Commission actions concerning training and qualifications, this Revision 2 of Regulatory Guide 1.8 1. Positions in ANSI/ANS-3.1-1981 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, "Licensed 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 N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel." The bases for the additions and exceptions to ANSI/ANS-3.1-
1981 art contained in NUREG-0737, "Clarification of TMI Action Plan Requirements," 3 which includes the Nuclear Power Plants," as shift supervisor, senior opera- tor, licensed operator, and shift technical advisor, the requirements contained in the standard provide an approach acceptable to the NRC staff for complying with the qualifications and training requirements of 10 CFR
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March 28, 1980 letter to all power reactor applicants Parts 50 and 55 subject to the guidance regarding the and licensees regarding qualification of reactor operators, STA function provided in the Commission's "Policy and 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 sion's "Policy Statement on Engineering Expertise on through k below. For radiation protection supervisory Shift" (50 FR 43621). Tile regulatory position related personnel, Section 4.4.4 of tile standard contains an to the radiation protection manager is revised from what approach acceptable for tile position of radiation protec- was included in Revision I 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, tile 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. ilot 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 tile Institute b. Hot license applicants must meet the training of Nuclear Power Operations (INPO) 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 training and the standard and the experience elements in Sections will provide the basis to ensure that personnel have 4.3.1.1.h, 4.3.1.2.b. and 45.1.2.b of the standard. Cold qualifications 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.
qualifications regulations during an evaluation period.
During that period, NRC will continue to evaluate the c. Paragraph 2 of Section 4.3.1.1.a 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 qualifications 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 minimum 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, is a high school diploma or equivalent.
2 Copies may be obtained -rom the American Nuclear Society, e. An applicant for a senior operator (SO) license
555 North Kensington Avenue, LaGrange Park, IL 6052S. should have 4 years of responsible power plant exper-
3 ience. Responsible power plant experience for an SO is Coples may be obtained from the Government Printing Office, Post Office Box 37082, Washington, DC 20013-7082. defined as having actively performed as a designated
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control room operator (fossil or nuclear) or as a power STA has not actively performed, the STA should receive plant staff engineer involved in the day-to-day activities training sufficient to ensure that the STA is cognizant of of the facility during or after the final year of construc-. facity and procedure changes that occurred during the tion. A maximum of 2 years of responsible power plant absence.
experience may be fulfilled by academic or related tech- nical training on a one-for-one time basis. Two years should Combining 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"
plant for which an applicant seeks a license. In addition, are met. In addition to the requirements specified in applicants for an SO position not holding a bachelor's Section 4.4.8.c of. ANSIIANS-3.1-1981, the STA should 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 actively involved plant transients and accidents and training in the rela- in the performance of licensed 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 ANSI/ANS-
use of installed plant systems for the control and mitiga- 3.1-1981 with the clarification that 3 of the 4 years of tion of an accident in which the core is severely damaged. experience in applied radiation protection should be professional-level experience.
g. In addition to the requirements in Section 5.2.1.3.1 of ANSI/ANS-3.1-1981, each applicant for an operator or 2. Positions in ANSI/ANS N18.1-1971 that Are Endorsed senior operator license should 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 all phases of day-to-day operations under the under Regulatory Position I 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 operating 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
3.1-1981, should include manipulation of controls of the and 55.
facility during a minimum 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 ples and could be accomplished by manually using such to applicants and licensees regarding the NRC staff's systems as rod control, chemical shim control, or recircu- plans for using this regulatory guide.
lation flow.
Applicants and licensees may propose means other i. All cold license applicants should participate in than those specified in Section C of this guide for meet- practical work assignments as described in Section S.2.1.4 ing applicable regulations.
of ANSIIANS-3.1-1981 for a minimum of 6 months.
In addition to the responsibilities described in Sec- Except in those cases in which the applicant or licensee tion 4.4.8 of ANSI/ANS-3.1-1981, the STA should assume proposes an acceptable alternative means of complying an active role 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 and maintain awareness of plant configuration and status. for use by the staff after March 31, 1988, in the evalua- The educational requirements for the STA specified in tion of the qualifications and training requirements for Section 4.4.8.a of ANSI/ANS-3.1-1981 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. tor and senior operator licenses, and (3) replacement personnel in those positions in operating nuclear power
"Actively performing STA functions" 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.
OU.S. G.P.O. 1987- 181-682,60057
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VALUE/IMPACT ANALYSIS
A separate value/impact analysis has not been prepared that timc. 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 for a fee at
10 CFR Part 55 published on March 25. 1987, a copy the NRC Public Document Room, 1717 Ii Street NW.,
of whlich was placed in the Public Document Room at Washington, DC.
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