ML20213E015
| ML20213E015 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/12/1982 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0462, CON-WNP-462, TASK-1.A.2.1, TASK-1.A.2.3, TASK-1.A.3.1, TASK-2.B.4, TASK-TM NUDOCS 8203040550 | |
| Download: ML20213E015 (11) | |
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P'E!'APApntre FOP; Pchert t.. Tedusco, Assistant Director 1
Division of Licensing s
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Hugh L. Thoroson, Jr., Acting Director Division of Huran factors Safety
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SfEJECT:
OLD IfiPffT r0P l.'PPSS f't!0 LEAD PDNECT, U"IT 2 SFR plant Nare: l'PPTS fluclear Prefect, Unit 2 (!'ND-2)
Licensinn Stano: AL Docket N'rber:
50-37,7 t
Desponsit'le Pranch end Pro.icct t'anaqer: Licensino Rranch r'o, P, c. Auluc!:
Tha enclosed is our SFR input for the 1.'"P-2 Pouer Station. Our review of Section 13.'> of the F9M and T"! related renttirerents for fetion Plen Itcrt I. A.2.1, I. A.2.3, I. A.3.1 and II.04 is complete through amndmnt 17 in the FSf".
frenifrent 17 date'l Januerv la:2, was suhritted by the annifcant in response to the t'RC's reonest for additionel inforration on T!!! action Iters I. A.2.1, I.A..?.3, I.f,.3.1 anal TI R.4 The soplicant also subnitted a enr91cte reurite of Charter 13. " Conduct of Orarations" to the FSAR on Pccomber 30, I?".l.
"e hava also reviewed the apnlicant's retraining procrar and replaceront traininc program that ms updated in resoonse to the TI'I action iters.
The annlicent subnitted their retraininc and renlacement traininq orogran
- i in the pecenhcr 30, 1981 reurite of FSAR Chapter 13, Conduct of Operations.
,i l Based on 09r revico, we have concluded thet the apnlicant's initial trainina l
procran and training schedules for all operators and senior operators arc i
acceptable to support the preoperational test prooran, operator licensinn exainations, and fuc1 loadi gv Consecuently, our review is corelete except 2
verifications that all orcrating personnel beve reviend the trainino for i
il nitioatinn enre damge, as recitired by Itcr II.P.4 l'e recorrend that the 1
Decionel Administrator, Pegion V. verify that this training has hoon given,
- l prior to authorization for fuel loed.
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g There is no dissent within DHFS with the conduct or conclusions of this evaluation.
This material was prepared by S. Salah Operttor Licensing Branch, Division of Human Factors Safety.
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Hugh L. Thompson, Jr., Acting Director Division of Human Factors Safety
Enclosure:
Conduct of Operations Review of Input for WNP-2
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13.0 conduct of operations 13.2,f ' Reuhr
_:......J Operator Training " :;
The overall conduct and administration of the plant training program is the responsibility of the plant superintendent.
He has designated the training supervisor as responsible for admini-stering the training progran and monitoring the program effective-ness.
The applicant states that the training program will. provide reasonable assurance that decisions and actions during all plant conditions will be consistent with plant safety procedures and operational limits established to protect the public health and
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safety.
The program for formal education and training of the reactor operators has been designed to meet the individual needs of the participants, depending upon their background, previous training,and expected job assignment.
The program conforms to the requirements set forth in ANSI N18.1-1971,10 CFR Part 55 l
and item I.A.2.1 of the TMI Action Plan (See NUREG-0737).
l The training program for personnel who will be licensed consists of the following discrete segments:
l A.
Operational fundamentals consist of lectures on the following subjects for thirteen weeks:
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Mathematics 2.
Classical physics 3.
Atomic physics 4.
Nuclear physics 5.
Reactor core physics 6.
Heat transfer and fluid flow 7.
Health physics and radiation protection 8.
Plant chemistry 9.
Instrument and control B.
Research reactor training (eight day course conducted by university personnet at the Washington State University Nuclear Radiation Center or by Suppty System Personnel using a comparable facility).
y@gb2 BWR Systems Class (10 week hatf day classes conducted C.
by Supply System personnel is designed to provide students with detailed instruction on WNP-2 nuclear steam suppty and major balance of plant systems).
D.
Browns Ferry Simulator Training (twelve week NRC approved program is conducted by General Physics Corporation and consists of four weeks of eLassroom system training and eight weeks of simulator training.
Prior to 4979 the Simulator training program for WNP-2 was conducted at
'N the Dresden Training Center in Morris, Illinois).
E.
Browns Ferry Observation Training (a four week course is conducted by General Physics Corporation at the Browns Ferry Nuclear Station in Decature Alabama).
F.
WNP-2 Systems and Procedures Training (a sixteen week class is conducted on-site by Supply System rirsonnel and is designed to provide license candidates with a detailed knowledge of WNP-2 systems and the normal and abnormal procedures required to orerate the systems).
G.
NRC Exam Refresher (three week training course conducted on-site by General Electric just prior to the NRC Exam Analysis class).
H.
NRC Exam Analysis (two week course conducted on site by i
General Electric just prior to the scheduled NRC exadh l
l I.
Simulator Refresher Training (all license applicants wiLL be required to attend simulator refresher training in preparation for licensing exams.
Since the Supply System currently has a WNP-2 Simulator under constructions refresher training will be conducted at that facility if it is available.
If note refresher training will be conducted on the Browns Ferry simulator).
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. The applicant's plans for retraining and replacement training conform to the requirements of 10 CFR Part 50, Appendix A of 10 CFR Part 55 and follow the guidance given in ANSI N18.1-1971.
In addition, applicant's retraining and replacement training conform to the 'equirements outlined in a letter from H.
R.
Dentone NRC, to All Power Reactor Applicants and Licensees, dated G9e March 1980.
p On the basis of our review, we have concluded that the training program and schedules for alL operators and senior operators are acceptable for the preoperational test program,for operator Licensing examination,and fuel loading.
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',,5, 10 C F R Pa r t 55, Regulatory Standard Review Plan j
Guide 1.8 and ANSI 18.1-1971; and,H.
R.
Denton's March 28, 1980 Letter were used in the conduct of this review.
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TMI-RELATED REQUIREMENTS FOR NEW OPERATING LICENSES PART 4 DATED REQUIREMENTS I.A.2.1 Immediate Upgrading of Operator and Senior Operator l
Training and Qualification-Statement of Requirement Dicussion-and Conclusions sqfIittal of January 11, 1982, has The applicant in h4 established a program to assure that all reactor operator License candidates [hhethe prescribed and senior operator j
experiencer qualification, and training.
AlL Licensed operator candidates wilL be certifed competent to take the NRC License examinations by the responsible Vic e President prior to.applicatioOfor the examinations.
As an operating License applicant, WNP-2 is not subject to the one year experience requirements for cold License l
SRO candidates.
Individual s a rsplying for an SRO License i
one year after fuel load wilL be required to have been an l
l RO for.at least one years unless previously experienced l
l in an equivalent position at another nuclear plant or i
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at a military propulsfion reactor.
License appttpnts l
l in the latter category wilL be documented by the applicant on a case-by-case basis in sufficient detail so that the l
l staff can make a finding regarding equivalency.
In additions l
l SRO License applicants who possess a degree in engineering or applicable sciences are considered to meet the one year l
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.. experience requirement as an RO provided they:
1.
Satisfy the requirements set forth in Section A.1A and A.2 in enclosure 1 in the letter from H.
R. Denton to all power reactor applicants and licensees, dated March 28, 1980.
2.
Have participated in a training program equivalent to (tat of a cold senior operator applicant.
The applicant's training program has been updated to include topics in heat transfers fluid flow and thermodynamics.
Reactor and plant transient training is primarily performed at the simulator facility by the applicant, and includes classroom discussions of typical transients as well as demonstrations of casualty and transient response on the simulator.
This knowledge is test,ed in depth on the certi-fication examination given by the training facility.
Based on our review of this material, we conclude that WNP-2 has satisfied the requirements of Item I.A.2.1.
s Dj S C ttSqlo n Agd.CowC.lu.sldk5 I.A.2.3 Administration of Training Program for Licensed Operators u
" Training Engineers who teach WMP-2 License candidates and/
or licensed operators will have participated in the
-t r a ini ng classes necessary to prepare them for an SRO license examination Requests for SRO license examinations for these training engineers will be submi t t ed b y -t he b
toQky2 fuel load along with the other applicant prior license candidates.
They will also participate in appropriate requalification programs as necessary to maintain their instructor certification.
Use of guest lecturers will be limited by the applicant so that program continuity,_can be maintained.
Based on our review, we have concluded that WNP-2 has complied with the requirements of Item I.A.2.3.
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I.A.3.l Revist Scope and Criteria for Licensino Examination Discussion and Conclusions NRC has added a new category to the operator written examination entitled " Principals of Heat Transfer and Fluid Mechanics" and a new category to the senior operator written examination entitled " Theory of Fluids and-Thermodynamics".
The applicant's reactor operator and senior reactor operator training program has been upgraded as described in their January 11,1982 submittal and includes the subject material described in this requirement.
The applicant will arrange for the Browns Ferry plant simulator to be available for the simulator portion of e4 Me, f 4% T $g8Cif%L S i et 4 (a t F e'$ M o i A n#// 4 N d l
1, the examination Individual license application packages Aiikf T[ pug pp gg g g[gf, g/(fagog,pggfjppg,
will include a release by the license candidates which e4wM mailedL E
permits the NRC to inform WNP-2 management of ame= results.
Based on our review, we have concluded that WNP-2 has compliad with the requirenient s of Item I.A.3.1.
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s TMI-RELATED REQUIREMENTS SITING AND DESIGN II.B.4 Training for Mitigating Core Damage The applicant has submitted an outline of a program for training in mitigating core damage.
The program covers all of the training subjects specified in the INPO report /
STG-01, Revision 1, dated January 18, 1981.
These INPO guideliness in turns hre based upon the training program outlined in the letter from H.
Denton to all power reactor applicants and licenseese dated March 28, 1980.
The applicant's program provides for more than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of
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training.
Our review of the applicant's program outline indicates that it meets the staff requirements of TMI Action Item II.B.4 and is therefore acceptable.
We require that the training as outlined in the. program be completed prior to fuel load.
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