ML19340D556
| ML19340D556 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/24/1980 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340D550 | List: |
| References | |
| NUDOCS 8012310232 | |
| Download: ML19340D556 (9) | |
Text
- sO UNI'IED STNIES OF AMERICA i
NUCLEAR REGUIA'IO1W CCFMISSION BEFORE 'IHE ATOtiIC SAFE?lY AND LICDiSING BOARD In the tutter of
)
)
MET. R3POLITA'i EDISON (DMPANY,
)
et. al.
)
Docket No. 50-289
)
('lhree Mile Island Nuclear
)
Generating Station Unit 1)
)
NRC STAFF 'IESTIFDiY OF BRUCE A. BCGR REGARDING LICE 4 SED OPEFA'IOR TRAINING (AMODr CDITD7FICN #2)
Q.
1.
Please state your name and position with the 12C.
A.
My nane is Bruce A. Boger.
I am a Reactor Engineer assigned to the Operator Licensing Branch, Office of Nuclear Reactor Regulation.
Q.
2.
Have you prepared a statement of professional qualifications?
A.
Yes. A copy of this statement is attached to this testinony.
Q.
3.
Please state the nature of the responsibilities that you have had with respect to the Three Mile Island Nuclear Station.
'A.
A list of tny activities is attached to this testinony.
A.
4.
Wat is' the purpose of your testfrony?
8012310233
p 3 A.
The purpose of my testinony is to respond to AAMODr Contention
- 2 with respect to the testing of NRC licensed operators.
Aspects of this contention relating to non-NRC licensed personnel will be addressed in the testfrony of Lawrence Crocker.
AA'DDT Contention !2 states:
"It is contended that 7MI-1 should not open until the performance of licensee technicians and unagement can be deconstrated to be upgraded as certified by an independent engineering firm. This upgrading should include 100% test performance of job description with provision for retraining and retest, or discharge of those who cannot consistently and confidently master all necessary information for safe conduct of their job description under all anticipated critical situations as well as routine situations."
A.
5.
How will the NRC verify that licensed operator training is adequate?
A.
If the facility is allowed to restart, we plan to administer examina-tions to all licensed operators approximately 30 days prior to the restart of the facility. The NRC examinations are designed to give us reasonable assurance that the individuals can safely and competently operate the facility. As such, the examinations are structured around those items that we consider important to reactor safety as enumerated in Sections'55.20 through 55.23 of 10 CFR Part 55, Operators' Licenses. A copy of 10 CFR Part 55 is attached-to this testinony.
r
, Q.
6.
Have any changes been made to the PRC examinations since the accident at TMI-27 A.
Yes, as one result of the accident at M-2, we reviewd and revised the scope and criteria for tac licensed examinations.
Changes required in this area are identified in the NRC Action Plan, ?UREG-0660, Item I.A.3.
To irple:mnt these changes, we issued the new requirements on March 28, 1980 and began examining to the new criteria on May 1, 1980. We increased the scope of the written examinations to include a new category dealing with thert:odynamics, heat transfer, and fluid flow. Tine limits to emplete the examination were inposed. Oral examinations for senior operators have been instituted. Finally, we have increased the passing grade criteria from 70% to 80% overall and have regaired a grade of at least 70% in each category.
Q.
7.
Have any changes been unde to the licensed operator qualifi-cation and training requirements since the accident at IMI-2?
A.
Yes, as another result of the accident at TMI-2, we reviewed and revised the criteria for the training and qualifications of licensed personnel. The changes required in this area are identified in the IRC Action Plan, PUREG-0660, Item I.A.2.
We issued the neu requirements on March 28, 1980. The qualifications for applicants for a senior operator license have been nodified s
O-,
to require that the applicant be licensed as a reactor operator for one year. Training requirements for licensed operators and senior operators were nodified to include three conths on-the-job training as an extra man on shift.
In addition, training programs were rodified to provide:
(1) training in heat transfer, fluid flow and thernodynamics; (2) training in the use of installed plant systems to control or mf.tigate an accident in which the core is severely damaged; and (3) increased emphasis on anticipated critical situations.
Q.
8.
Will an independent engineering firm be used to certify operator performance?
A.
'Ihe licensee has contracted with an outside firm to evaluate the competency of licensed operators and senior operators. 'Ihe licensee will use the findings of this organization as one factor in determining who will be permitted to sit for the IRC examination.
However, in accordance with 10 CFR Part 55, the final responsibility for certification of licensed operators lies with the NRC, which will serve as an independent certification organization.
Q.
9.
Will each individual be examined on 100% of the job description or be required to receive a 100% score on the IRC examination?
A.
Ib, we believe that it is not necessary for each individual to be examined on 100% of the job description or receive a 100% score on the NRC examination for the following reasons:
& 9 A.
1.
The new criteria provide reasonable assurance that an applicant 4 0 can achieve an exam score of at least 80%
overall with no category less than 70% and 40 can successfully pass the operating test can perform licensed duties safely and capetently.
2.
The licensed operator is not alone at the facility. We require two licensed operators and two licensed senior operators on each shift. Hence, plant safety is'not dependent solely on the knowledge and understanding of one individual.
3.
The operating test varies fran one individual to another so that we can assess the overall effectiveness and scope of the training program. thile each operating test rust cover a minimin nu:nber of plant systems, operating procedures and transients, the specific topics will not be the same for each applicart. If the exam results indicate that there is a subject or systen which has not been adequately covered in the training program, we will inform facility management to provide additional training in the weak area.
Q. 10. Will each individual be evaluated on the response under stress?
h
9 l A.
While not directly evaluated, an operator's performnce under stress is observed during the licensing process. The time limits placed on the written examination and the oral operating test place stress on an individual which mst be overcome for satis-factory coupletion.
In addition, previous operating experience, simlator exercises, and training on anticipated critical situations will help overcome the stress which my be associated with off-normal s'ituations.
Q.11, What provisions exist for the retraining of individuals who pass the NRC examinations?
A.
Each individual nust pass the written examination and an oral /
operating test to receive a license to operate, or direct operations at 'IMI-1.
We will inform facility mnagement of the examination results so that individuals who pass may be enrolled in appropriate requalification programs.
Appendix A,10 CFR Part 55, requires that all licensed individuals participate in NRC approved requalification programs. These programs require annual examinations, attendance at lectures, and review of procedures, and facility design, including changes thereto, t
t ne program also require specific control runipulations and walk throughs of energency procedures to cover anticipated critical situations as well as routine situations.
We also plan to achinister the annual requalification examinations.
We passing grade on the requalification examination will be the same as the passing grade on the initial examination. Operators who fail the examination will be prohibited frcxn performing licensed duties. They may be administered reexaminations consistent with our regulations.
Q. 12. khat provisions exist for the retesting of individuals who do not pass 'the IEC examinations?
A.
We will also inform facility management of the examination results of individuals who do not pass the tac examination.
The results can be used to identify weak areas in an individual's training, which can be rectified through subsequent retraining.
Reexamiations may be administered consistent with the requirenents of 10 CFR 55.12.
1 FROFESSIONAL QUALIFICATIONS LIST BRUCE A. BOGER 9
Education June 1971 Received BSNE - University of Virginia June 1972 Received MENE - University of Virginia Work F-p erience June 1972 to Virginia Electric and Pom: Company June 1977 Surry Nuclear Power Station Assistant Engineer - Perforced startup testing on Unit No. 2.
Engineer - Assisted the Supervisor-Fagineering Services; trained for and received a Senior Reactor Operator License.
Supervisor - Engineering Services - Directed the activities of the onsite engineering staff.
June 1977 to Virginia Electric and Pcuer Company September 1977 Rich:end, Virginia Supervisor - Ibclear Engineering Services - Directed the activities of the offsite engineering staff in support of Surry Pcuer Station.
October 1977 to U. S. tbclear Regulatory Coamission Present Bethesda, Maryland Reactor Engineer in the Operator Licensing Branch - Admin-ister licensing examinations to nuclear pcrer plant and research reactor personnel.
Professional Affiliations Registered Professional Engineer - State of Virginia Me:rber - Anerican Ibclear Society
]
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A I
Participation in 'DiI Activities Bruce A. Boger November 1978, April 1980: Adninistered operator license examinations on Unit One.
November 1978, March 1979, Parch 1980: Administered operator license examinations on Unit'IW.
March - April 1979: Fember of the M-2 emergency response team, assisted in the preparation of emrgency and contingency procedares.
July 1979 - Present: Panber of the M Technical Support Staff, conducted audit examinations on post-accident installed eculpment on M-2.
Also partici-pated in the review of training and procecures in conjunction with the M-1 restart programs. 'Ihis included preparation of SER inputs and testinony.
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