ML20024B140
| ML20024B140 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 02/28/1979 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML20024B141 | List: |
| References | |
| TASK-*, TASK-GB, TASK-OS, TASK-RS-807-5 GPU-2258, REGGD-01.008, REGGD-1.008, NUDOCS 8307060565 | |
| Download: ML20024B140 (8) | |
Text
' W
&m 2253 W%
,,J t
Februar'" 1979 g-U.S. NUCLEAR REGULATORY CCMMISSION 9 j,hp[g,.
Division 1 j
OFFICE OF STANDARDS DEVELOPMENT Task RS 807-5
- ,Mb f
DRACT REGULATORY GUIDE AND VALL'E/ IMPACT STATEMENT g.
s, v f PROPOSED REVISICN 2* TO REGULATORY GUIDE 1.8 PERSONNEL SELECTION AND TRAINING A.
INTRODUCTION Paragraph 50.34(b)(6)(i) of 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," requires that applications for a c
license to operate a nuclear power plant include information concerning' g
organizational structure, personnel qualifications, and related matters.
This regulatory guide describes a method acceptable to the NRC staff for complying with this portion of the Commission's regulations with regard 9
to the qualifications of nuclear power plant personnel.
P B.
DISCUSSION Subcommittee ANS-3, Reactor Operations, of the American Nuclear Society Standards Committee developed a standard containing criteria for the selection and trainir.g of nuclear power plant personnel.
This standard was approved by the American National Standards Institute (ANSI) Committee N18, Design Criteria for Nuclear Power Plants, and was subsequently approved by the o1 W@O w
$O The substantial number of changes in this proposed revision has made it impractical to indicate the changes with lines in the margin.
rOO "iis requiat:ry ;uide and tre assocf ated salue/1 met statweat are teiro is:ued o
in craf t for, to involv o
a the :unitt in the early sta;es of t.' e deveic:r' ant of a racul atory ::osit:5n n inis iras.
They 9 ave ot OO
"*"eived c:"DIete s*3ff "*v+ew. ' ave not ean ** view *d by 're WC 2eguinary 2equir-ents ?eview C: rti t-
,c o tee, ma co,ot -=cresent in of ficial NPC sta f f ;cs t tten.
04 5
Nblf: c
- rents ira taiac scif:f*e1 :n to *i fr3f*:. t'e cuite
!udiac 4*: ;-cla~ -t n a c eduia' 3-1 k
O e sa :,c,.. a:t :ny,Q
- w r:3 3,
..,,4 N g e,34 c., : n,,, gre,;3.,, c..,. n q g 337.,y. y g o g.
jn3. ': rants :, ;otn :raf : : :uid t= seat to t e Irc 2ry :(
-a
. :-: ::-a.
- ...:' q r :a:v ! : :r.,
a i 3 :n. disn et:6,
]...
- 05:5 : t2nt?:n: Occ et c ira Ierv :? 3ri-c,, ;
4PQ 0 3 yj 7e *,ests 'er siaale ::stes of issa3 ;utces led tr3f t ;utets
.71cn af 5e acraducect :P 'Or 31acreat On du an ist::attc afstributi n its
'er sinc le cotes 3' 'uture ;uices anc :raf t :uices in s:ecific af v'stens should te.sce in.riting to tre J.3. Nuclear Reaul n:rf ::,,ission, Wa<nta; ten. J.. 20555. Attention:
Jiractor. 3tvisten of 7ecanical :nfor9atten ano Jccnent ent.31,
}
1 w
DRAFT ANSI Board of Standards Review and designated ANSI /ANS 3.1-1978, " Selection and Training of Nuclear Power Plant Personnel."1 6
The subject of this standard and regulatory guide is primarily the selection and training of personnel to ensure the safe operation of the nuclear power plant.
An equally important concept that is not addressed I
directly in the standard is that occupational radiation exposures should be maintained as low as is reasonably achievable (ALARA).
As recommended in I
Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations Will Be As Low As Is s
Reasonably Achievable," the concept of ALARA is an important part of the l
training program for the entire plant staff as well as for radiation health personnel.
The importance of this concept is reflected in the qualifica-tions for the Radiation Protection Manager (RPM).
The staff feels that it is important to the implementation of ALARA as well as for control of offsite releases that a highl' qualified professional manager be located at the y
plant site to supervise and coordinate the radiological health and moni-toring program.
1 C.
REGULATORY POSITION l
The criteria for the selection and training of nuclear power plant personnel contained in ANSI /ANS 3.1-1978, " Selection and Training of Nuclear Power Plant Personnel," provide an adequate basis for the selection 1
Copies may be obtained from the American Nuclear Society,.555 North Kensington Avenue, La Grange Park, Illinois 60525.
Z.r.
- X
,9 2
~
y jpmgc=.
^ -
A
%RTM f
em-- __ i" *- ^
e t,
y A.
e
)
ORAFT and training of nuclear power plant personnel as supplemented or acdified by the following:
4 1.
In some cases, plant design features or unusual operating condi-t tions may indicate that additional or more specialized expertise than the qualifications presented in ANSI /ANS 3.1-1978 is needed.
In addition, although the qualification levels of the standard are endorsed as accept-3 able minimums for each position, it is expected that the collective quali-t, y.
fications of the plant staff will be greater than the sum of the minimum individual requirements described in the standard, particularly in the area of nuclear power plant experience and for supervisory and management posi-i tions involved in the operational aspects of the facility.
In those cases h
where the collective qualifications do not exceed the sum of the minimums for individual positions, additional technical support for the plant staff i
may be required.
These determinations will be made on a case-by-case basis.
2 Y
2.
For the purposes of this regulatory guide, when the phrase
" bachelor's degree or equivalent" is used, the qualifications considered as rainimum acceptable substitutes for a bachelor's degree are a high school l
diploma or its equivalent and one of the following:
four yers of formal schooling in science or engineering; a.
b.
four years of applied experience at a nuclear facility in the area T
for which qualification is sought;
- =.? { Q {
R,.c t
jut 101973 e%.
..:.u w -
l i
' fgcq LW M
-d W
3 l
i:JLM.e.A.y, 6
sj
- 1 3 v.,
y i
[,
DRAFT
~4 c.
four years of operational or technical experience or training in
[
nuclear power; or ij d.
any combination of the above totaling four years.
Ih 3.
Section 1, " Scope," of ANSI /ANS 3.1-1978 states,"[The Standard] addresses itself to the qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants."
In addi-tion, the following minimum qualifications for personnel > responsible for preoperational and startup testing programs should be used:
e a.
Minimum qualifications for individuals that direct or supervise
- g the conduct of individual preoperational tests - At the time the test is conducted, the individual should have a bachelor's degree in engineering or
~
the physical sciences or the equivalent and one year of applicable power plar.t experience.
Included in the one year of experience should be at least 3 months of indoctrination / training in nuclear power plant systems and component operation in a nuclear power plant that is substantially similar in design to the type at which the individual will perform the function.
I b.
Minimum qualifications for individuals tha; direct or supe'rvise J
the conduct of individual startup tests - At the time the test is r
conducted, the individual should have a bachelor's degree in engineering or
?s u:
A 4
,-...---,-,------w-
- ' = = - - - - ' - ' ~ ' - = ' ' ' ' ' ~ ' ' ' " ' " '
~ " " ~ ~
rg
. _ - =- M M g h v iaA [' M2 W g Tm
~--
f r
s DRAFT the physical sciences or the equivalent and two years of apolicable power plant experience, at least one year of which should be applicable nuclear power plant experience.
Minimum qualifications for individuals assigned to groups c.
responsible for review and approval of preoperational and startup test 1
procedures or results - At the time the activity is being performed, indi-2 viduals that perform these activities should have a minimum of eight years r
T of applicable power plant experience with a minimum of tw6 years of appli-h cable nuclear power plant experience.
A maximum of four years of nonnuclear r
%AN experience may be fulfilled by satisfactory completion of acacemic training i
in engineering cr the physical sciences at the college level.
4' d.
Qualifications for other inspection, examination, and testing personnel are contained in Regulatory Guide 1.58, " Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel."
4.
Section 3.1, " General," exempts from the qualifications those l
personnel temporarily filling positions caused by absences of the principal.
l It should be understood that this exemption does not apply to temporary l
7 workers hired to assist the normal plant staff during peak workload periods.
.. i 5.
Section 4.4.4, " Radiation Protection," third paragraph, allows the individual who meets the qualifications of the first two paragraphs of I
.M 5
{
i; ORAFT the section to be located either onsite or offsite.
The Radiation Pro-tection Manager (RPM) meeting the education and experience requirements of I
the first two paragraphs of Section 4.4.4 should be located onsite. The experience in applied radiation protection should be under the direction of
$I a qualified RPM.
It should include two years of training with emphasis on T1 jf directing the radiation protection and monitoring program and three years of professional experience directing the activit 'es of radiation protection y;
1 technicians.
An individual who is certified in power reactor health physics by the American Board of Health Physics, in accordance with the Qf
" Power Reactor Health Physics Certification Program," American Board of Tf Health Physics, November 1978, and has the requisite experience as
.x
?
kl specified by the American Board of Health Physics, is considered as N
having met the qualifications tequirements specified for an RPM in this Tt
@l regulatory position.
6.
Section 4.7.2, " Staff Specialists," includes qualifications for T
individuals performing reviews in the areas of administrative control and nuclear power plant operations.
In view of the important nature of those reviews, the education and experience requirements should be a bachelor's 1
degree in engineering or the physical sciences and five years of profes-1 I
sional experience in the field of the individual's specialty; in special cases, ten years of experience in a specialized field may be acceptable.
j 7.
In Section 5.5., " Operator Retraining and Replacement
$f Training," the first paragraph should be applied to the operating
(
l1
- s. :y i
6 i
j
1 e_
J ORAFT organization, not just to the licensed operators.
Section 5.5.1 and its subsections, 5.5.1.1 through 5.5.1.6, should be applied only to licensed operators.
8.
At the time of initial core loading or appointment to the posi-tion, whichever is later, the minimum qualifications for persons performing the functions of unlicensed operators, other than in a training status, s
k should include a high school diploma or equivalent and one year of power 9
plant experience.
At least 6 months of the power plant experience should
{:
be at the plant to which the individual will be assigned or at a similar y
4 unit.
The individual should also possess a high degree of manual dexterity and mature judgment.
9.
Throughout ANSI /ANS 3.1-1978, other documents required to be d
q included as a part of this standard are identified at the point of reference.
The specific applicability of these standards listed in ANSI /ANS 3.1-1978 has been addressed in the latest revision of the following regulatory guides:
Regulatory Guide ANSI Standard 1.17 N18.17 1.134 N546.
1.33 N18.7
{'
l l
r t
"3 7
l..
Sl DRAFT i
f#
0.
IMPLEMENTATION
'M h
The purpose of this section is to provide information to applicants h
and licensees regarding the NRC staff's plans for itsing this regulatory guide.
E This proposed revision to the guide has been released to encourage public participation in its development.
Except in those cases in which an applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method to be described in the active l
guide reflecting public comments will be used in the evaluation of applications g-for operating licenses docketed after the implementation date to be specified in the active guide.
Implementation by the staff will in no case be earlier
~
than October 1979.
[
1 s
l l
3 1
k i.mi
- 3
\\ f.hi
[ -
t 4
x 8
l
' -~
~ ~ ' ~ ~