ML20080K883
| ML20080K883 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/21/1983 |
| From: | Russell W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079F427 | List:
|
| References | |
| FOIA-84-35 NUDOCS 8309290474 | |
| Download: ML20080K883 (21) | |
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t SEP 21198; f'/j FEMOPANDUH FOR:
Thomas A. Novak, Assistant Director
'for Licensing
,e Division of Licensing William Russell, Deputy Directorp/
FROM:
Division of,,J.hgipn F # Safety f
SUBJECT:
SER F0 SHEARON HARRIS NUG EAR POWER PLANT -
I PLANT P. E'. TRAINING PLANT NAME:
Shearon Harris Nuclear Power Plant (SHNPP)
DOCKET NUMBERS:
50-400/401 LICE'NSING STAGE:
OL RESPONSIBLE BRANCH AND PROJECT MANAGER:
LB#3, B. C. Buckley
, REVIEW STATUS:
SER with one open issue
REFERENCE:
Letter from Carolina Power & Light Company to H. R. Denton, "Shearon Harris Nuclear Power Plant Management Capability Report," dated August 4,J,1983.
The enclosed SER for plant personnel' training ir. :
- s our review of Licensed Reactor Operator Training (SRP 13.2.1) and Trair-.
or Non-Licensed Plant Staff (SRP 13.2.2) for the Shdaron Harris Nuclear Power Plant. This SER was prepared by the Personnel Qualifications Section of the Licensee Qualifications Branch after having reviewed the applicable sections of the FSAR, an advanced copy of a revised FSAR cnd the applicant's response to the Request for Additional Information.
Based on our review, we find that the applicant's initial, requalification and replacement programs for licensed reactor operators confonn to the requirements of the applicable portions of 10 CFR Part 50, Appendix A of 10 CFR Part 55 and Regulatory Guide 1.8, as well as the Tiil Action Plan i
(NUREG-0737) and H. R..Denton's letter of-Harch 28, 1980, to all power reactor applicants and licensees.
Therefore, we conclude that the applicant's training programs for licensed reactor operators are acceptable.
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The applicant has not adequately addressed the training provided to the STA who has been absent from STA duties. As noted in the attached SER Section 13.2.2, we will require that:
(1)
STA not actively performing the STA functions for a period of thirty riays or longer shall, prior to assuming responsibilities of the position, as a minimum receive training sufficient to ensure he is cognizant of facility / procedure changes that occurred during his absence, and (2)
STA not perfonning the STA function for a period of six months or-longer _ shall, prior to assuming the responsibilities of the position, receive the annual requalification training as described in
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~2-Appendix C to fiUREG-0737. With regard to these requirements, we have expressed our concerns to the applicant over the telephone on several occasions, however, we have not been able to receive a favorable response from the applicant.
Based on our review, we find that the training given for nonlicensed plant staff personnel excluding STAS meets the requirements of 10 CFR Part 19 and Part 50 and follows the guidance given in Regulatory Guide 1.8.
Therefore, we conclude that the applicant's training program for nonlicensed plant staff with the exception of STA training program is acceptable.
It should be noted that by letter (Ref.) dated August 4,1983, the applicant submitted an updated Management Capability Report (MCR) describing in detail the new CP&L organization.
The MCR also briefly describes a training program for SHNPP plant personnel.
We reviewed the training program and found that its contents deviated from those of the training program described in the FSAR and that it significantly lacked information which we need to evaluate
'it.
We expressed (by informal conference calls) our concerns to the applicant of having two training program descriptions, which were not identical to each other, docketed in two different reports (FSAR and liCR).
Consequently, the applicant agreed to revise the FSAR to reflect the differences.
As indicated in the abbve, we have reviewed the advanced copy of the revised FSAR which was hand-carried by the applicant to the LQB on August 29, 1983. Based on our understanding that the applicant will fonnally submit the above revised FSAR and that the training program for plant personnel as described in the FSAR will supersede the training program as described in the MCR, we made the above conclusions as stated in the attached SER.
When the modified FSAR is submitted, the project manager should review it to assure that no changes were made to the informal submittal.
This review was conducted by D. Shum (x24906).
There are no known dissenting professional opinions within DHFS concerning the conduct or conclusions of this evaluation.
Od@nai sWY..wO i
/
illiam Russell, Deputy Director L
ivision of Human Factors Safety
Enclosure:
DISTRIBUTI0ti:
As stated Central Files LQB Reading cc:
G. Knighton DilFS Reading (2)
B. Buckley
.H. Bocher J. Persenskv D. Shum
- SEE PREVIOUS ORC FOR CONCURREllCE omes) LQB/DHFS '
LQB/DHFS LQB/DHFS D D / D H F S[,,,,,,,,,,,,,,,,,,,,,,,
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SAFETY EVALUATION REPORT FOR SHEARON HARRIS NUCLEAR POWER PLANT (SHNPP)
DOCKET N05.:
50-400/401 PLANT PERSONNEL TRAINING 13.2 Training The applicant's training programs for licensed reactor operators and nonlicensed plant staff were reviewed according to SRP 13.2 (NUREG-0800).
The staff acceptance criteria included applicable portions of 10 CFR Parts
- 19, 50 and 55, and Regulatory Guide 1.8, as well as the TMI Action Plan (NUREG-0737) and H. R. Denton's letter of March 28, 1980, to all power reactor applicants and licensees.
13.2.1 Licensed Operator Training. Program i
A training program for SHNPP licensed reactor operators has been implemented to develop and maintain an organization fully qualified to operate the plant and maintain the plant safety.
The initial and requalification programs which are designed to meet the requirements of 10 CFR Parts 50 and 55, and TMI Action Plan related requirements, are based on the individual employee's level of education, experience and skills as well as on the level of assigned responsibility and intended position.
Bea' Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 36UDS
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. 13.2.1.1 Initial Training Program The. initial training program for personnel who will be licensed consists of the following discrete segments:
(1)
. Basic Auxiliary Operator Training Program This course consists of nine weeks of classroom training interspersed with nine weeks of structured on-the-job plant specific system training.
The course is designed to provide theoretical training and in-plant training to provide reinforcement of the basic science and technology 1
of power plant operations.
Examinations will be given regularly throughout this phase of training to monitor the trainees' progress.
Each trainee must achieve no less than 80 percent grade in this course prior to entering the next phase of the training program.
(2)
Nuclear Auxiliary Operator Training Program This course is designed to provide those persons with little or no nuclear background with the necessary theoretical knowledge to become proficient auxiliary operators.
The program consists of approximately four weeks of formal classroom training interspersed with on-the-job training at the trainees' assigned plants.
The major areas to be i
Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2(83
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.. covered in the classroom are mathematics, nuclear theory, heat transfer, radiation protection, waste treatment, instrumentation and control, and radiation protection.
(3)
Control Operator Candidate Training Program This program is designed to follow the above Nuclear Auxiliary Operator Course for all new operator personnel with limitad or no nuclear experience.
The program consists of approximately ten weeks of classroom lectures on math reyiew, fluid flow, nuclear theory, reactor
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theory, chemistry and metallutgy.
(4)
SHNPP Cold License Theory Training This is a formal, approximately 11-week training program.
The subject areas to be covered by this training are math review, nuclear and reactor theory, heat transfer, thennodynamics, health physics, radiation protection, chemistry and PULSTAR reactor training at N. C. State.
Reviews and examinations will be given regularly throughout the program to evaluate the effectiveness of this phase of training.
Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /8EA20 9/2/83
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... (5)
' Cold License System Training and Systems On-The-Job Training This training course is designed to provide cold license candidates with an in-depth study of the SHNPP systems and equipment.
This phase of the training program is 18 weeks in duration, of which approximately nine weeks consist of formal classroom instruction with the remaining nine weeks spent in the plant identifying the equipment associated with the topic covered in the classroom sessions.
Knowledge of plant systems will also be augmented by participation in procedures development, system acceptance tasting, and later, in hot functional testing.
Effectiveness of this training will be monitored through written 1
examinations and system check'quts.
(6)
Cold License Procedure, Theory Review, and Simulator Freoaratory Training This is an approximately five-week course administered prior to going to the simulator. Topics covered in this course include procedures, theory review, mitigation of core damage, transient and safety analysis, safety and control systems review, review of industry events and station blackout.
Review and examinations will be conducted regularly to evaluate the effectiveness of this training.
Bea Rosenberg, 24816
. DS-SER FOR SHEARON HARRIS /BEA20 9/.2/83
' l (7)
Cold License Simulator Training This training program will be approximately nine weeks in length (eight weeks minimum) on the SHNPP simulator.
The training will include, but not be limited to:
1) control board familiarization; 2) control functions;3) procedure usage (including Plant Emergency Procedure Implementation);4) transient and accident analysis; and 5) control manipulations during normal, abnonnal, and emergency conditions (including multiple failures).
Fmphasis will be placed on integrated system response under nonnal and emergency conditions including control room instrument response, diagnostics, and mitigation of core damage.
1 The training staff will monitbr progress and performance during the training and instruct as required through periodic critiques.
Written and operating examinations will be administered after completion of s'mulator training to certify cold license candidates at the Reactor Operator and/or Senior Reactor Operator level.
(8)
Cold License Review Series and Audit This portion of the cold license training program will be conducted during the period between the completion of hot functional testing and the administering of NRC licensing examinations.
The review series consists of approximately two weeks of instruction including five hours per day of classroom work with the remainder of the day being used for special instruction, plant tours, and individual study.
The topics Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 312A 8 3__-_ ___ __ _- _ _ _ _ _ _ - __ _.
1
.. i covered In this lecture series include: reactor physics and kinetics; reactor control and protection systems; health physics and plant chemistry; technical specifications; transient, instrument failure, and accident analysis; normal and emergency operating procedures; heat transfer, fluid flow and thermodynamics; and pressurized thermal. shock.
The audit phase of this portion of the Cold License Traii.ing Program will consist of written and oral examinations.
(9)
Cold License. Pre-License Review I
This is an approximately four' week course designed to improve the weak areas brought out from audits-and to bring the license candidates to a peak knowledge level for the NRC examinations.
(10)
Other Cold License Training In addition to the above training courses, cold license candidates will receive training in the following areas:
Fire Brigade Training -
Emergency Plan Training Security Training Management Training for Licensed Supervisors (for personnel requiring SR0 licenses)
Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2/83
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Specific Plant Experience Fuel Handling and Operations Training (11) Training on Scecial Low Power Testing Each licensed reactor operator and senior reactor operator will participate in the initiation, maintenance and recovery from natural circulation.
Based on our review, we find that the applicant's initial training program confonns to the requirements of the applicable portions of i
10 CFR Parts 50 'and 55, and fiillows the guidance given in Regulatory Guide 1.8.
In addition, the applicant's initial training program conforms to the requirements outlined in a letter from H. R. Denton to all power reactor applicants and licensees dated March 28, 1980.
j Therefore, we conclude that the initial training program for all reactor operators and senior reactor operators is acceptable.
13.2.-l.2 Licensed Operator Recualification and Replacement Training Program Following the initial licensing of cold license candidates, a requalification and replacement training program will be implemented to maintain and demonstrate the continued competence and the level of proficiency of all licensed personnel.
Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2/83
O 13.2.1.2.1 Requalification Training The requalification training program will be conducted on an annual basis and will consist of the following areas:
(1)
Lecture Series The requalification program will includ.e planned lectures on a regular and continuing basis. Annual written examination results will indicate the scope and depth needed in the following areas as listed in 10 CFR Part 55, Appendix A:
.i Theory and Principles of Reactor Operation General and Specific Operating Characteristics of the Plant Plant Instrumentation and Control Systems Reactor Protection and Engineered Safety Systems Normal, Abnormal, and Emergency Operating Procedures l
Radiation Control and Safety Technical Specifications l
Applicable Portions of 10 CFR, Chapter I l'
In addition to the above areas, the Lecture Series will include instruction in heat transfer, fluid flow, thermodynamics and mitigation of accidents involving a degraded core, as specified in'H. R. Denton's March 28, 1980, letter.
Baa Rosenber DS-SER FOR SHEARON HARRIS /BEA20 cvara__ g, 24816
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(2)
On-The-Job Training The on-the-job training portion of the requalification program will consist of the following:
(a) Control Manipulation Licensed reactor operators shall manipulate and senior reactor operators shall manipulate or direct or evaluate the activities of those manipulating the station controls through a minimum of ten reactivity changes during,'each annual cycle.
These manipula'tions i
may consist of any of the';following, providing that' asterisked items are perfonned annually and all other items are performed on a two year cycle:
Start-up to the point of adding heat Orderly shutdown Manual steam generator control during stcrt-up and shutdown Boration and/or dilution during power operation 1
L Any significant ( 10 percent) power changes in manual rod control l
Turbine start-up and shutdown l
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t Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2/83,
. 4 Loss of coolant (a)
Including significant steam generator leaks (b)
Large and small including leak rate determination (c)
Resulting in saturated RCS Loss of instrument air Loss of electrical power and/or degraded power sources Loss of forced coolant flow / natural circulation Loss of circulating water / condenser vacuum Loss of service water Loss of shutdown cooling Loss of component cogling system or CCW to an individual i
componen't Loss of normal feedwater or normal feedwater system failure Loss of all feedwater (normal and emergency)
Loss of protective system channel Control rod misalignment or drop Inability to drive control rods i
Condi,fons requiring emergency boration High activity in reactor coolant Turbine or generator trip Malfunction of automatic control system (s) which affect reactivity Malfunction of CVCS system Reactor trip Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2/83
Main steam line break (i' side or outside containment) n Nuclear instrumentation failure (s)
The SHNPP training simulator, which reproduces the general operating characteristics of and has similar instrument and control arrangement to the SHNPP, may be used to perform these reactivity controf manipulations.
(b) Knowledge of Plant Systems Each licensed reactor operator and senior reactor operator will
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satisfactorily demonstrat'd understanding of the operation of equipment and systems and of operating procedures. This will be accomplished by a walk-through of the procedural steps required to start, stop or change conditions of the systems; manipulation of the systems and their associated equipment; or use of the SHNPP simulator.
(c) Knowledge of Facility Design, Procedure, and License Changes This program ensures that licensed reactor operators and senior reactor operators will review revisions to the Operating Technical Specifications, will review significant procedure changes, and will review completed facility design changes which would affect plant operations.
Bea Rosenberg, 24816 DS-SER FOR SHEAR 0N HARRIS /BEA20 9/2/83
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. (d) Knowledge of Emergency Operating Procedures In order to ensure a continuing awareness of the action and.
responses necessary during abnormal and emergency situations, each licensed reactor operator and senior reactor operator will review periodically the content of all Emergency Procedures and all Abnormal Procedures.
(3)
Evaluation The evaluation program for licensed personnel include the following:
.i.
(a) Annual
- ten Examination Annual examinations, comparable in scope and degree of difficulty to an NRC examination, will be given to each licensed reactor operator and senior reactor operator.
The examination will contain the categories as described under Lecture Series.
A grade of less than 70 percent in any category will require accelerated requalification in that category.
A grade of less than 80 percent
.overall requires accelerated requalification in all categories graded ~1ess than 80 percent.
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h Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEAE0 o
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. (b) Annual Observation and Written Evaluation il Observation and evaluation of the performance of licensed reactor operators and senior reactor operators by supervisors or training staff members will include evaluation of performance during actual or simulated emergency conditions.
Observation and evaluation of the perfonnance of licensed personnel during simulated emergency conditions may Le conducted by simulator training staff personnel.
Discussions of actions taken or to be taken during emergency situations may be used as evaluation tools in lieu of or in addition to the above methods. Any licensed reactor operator or i
senior reactor operator given an unsatisfactory overall evaluation will require accelerated requalification.
(4)
Accelerated Requalification Accelerated requalification will be given in the categories required or areas identified in the annual observation and written evaluation.
Persons requiring accelerated requalification as a result of annual evaluation will not perform licensed duties until successfully completing the program.
Bea Rosenber DS-SER FOR SHEARON HARRIS /BEA20 WbW5M -
g, 24816
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1 13.2.1.2.2 Replacement Training Replacement training will be conducted to fill vacancies and will prepare individuals for increased responsibility in the supervisory, technical or operating staff.
Replacement personnel will receive training comparable to that received by the initial staff.
This will ensure that the required level of proficiency is maintained.
. Based on our review, we find that the applicant's requalification and replacement training program conforms to the requirements of 10 CFR Part 50 and Appendix A of 10 CFR Part 55 and follows the guidance given in Regulatory i
Guide 1.8.
In addition, the prograhl conforms to the requirements outlined in a letter from H. R. Denton to all power reactor applicants and licensees dated March 28, 1980.
Therefore, we conclude that the applicant's requalification and replacement training program for reactor operators and senior reactor operators is acceptable.
13.2.1.3 TMI Related Requirements for New Operating License l
I.A.2.1 Imediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualification The applicant has established a program to assure that all reactor operator and senior reactor operator license candidates have the prescribed experience,-qualification and training.
DS SER FOR SHEARON HARRIS /BEA20 Bea Rosenberg, 24816
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All licensed operator candidates will be certified competent to take the NRC license examinations by the Vice President of the Nuclear Operation Department prior to application for the examinations.
As an operating license applicant, SHNPP is not subject to the 1-year experience requirements for cold license SRO candidates.
However, after 1-year of station operation, individuals applying'for en SRO license will be required to comply with the 1-year experience requirement for hot license SR0 applicants, unless previously experienced in an equivalent position at cnother nuclear plant or at a military propulsion reactor.
The experience of license applicants in the latter category will be i
documented by the applicaht on a case-by-case basis in sufficient detail so that the staff can make a finding regarding equivalency.
SRO licer.se applicants who possess a degree in engineering or applicable sciences are considered to meet the 1-year experience requi.ements as an R0 provided they:
(1) satisfy the requirements set forth in Sections A.1.a and A.2 of Enclosure 1 to the letter from H. R. Denton to all power reactor applicants and licensees, dated March 28,1980, and (2) have participated in a training program equivalent te that of a cold senior reactor operator applicant.
Also, the requirement for three months on-shift experience for
' control room operatois and SRO candidates as an extra person on shift is not required for cold license candidates and, hence, is Bea-Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 fysgra.
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. not applicable to SHNPP.
However, SHNPP will comply with this requirement for hot license candidates after three months of station operation.
The applicant's training program includes topics in heat transfer, fluid flow, and thermodynamics.
Reactor and plant transient training is primarily performed.by each license applicant at a simulator facility and includes classroom discussions of typical transients as well as demonstration of casualty and transient response on the simulator.
This knowledge is tested in-depth on the certification examination given by the training facility.
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Based on our review, we conclude that the applicant of SHNPP has satisfied the requirements of this task of the TMI Action Plan.
I.A.2.3 Administration of Training Program All instructors who teach systems, integrated responses, transient and simulator courses shall be SRO certified and will continue to participate in appropriate requalification programs.
Vendor-supplied instructors who teach the above subjects shall also be similarly certified.
Other members of the permanent or nonpermanent training staff who are responsible for teaching technical subjects, such as reactor theory, heat transfer, fluid Bea Rosenberg, 24816 05-SER FOR SHEARON HARRIS /8EA20 9/2/83
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. mechanics, thermodynamics, health physics, chemistry, and instrumentation are not expected to have an RO or SR0 license.
Guest lecturers considered to be used on a limited bases shall be monitored by a qualifiea instructor.
These guest lecturers are exempt from the SRO criteria.
Based on our review, we conclude that the applicant of the SHNPP has complied with the requirement of this task of the TMI Action Plan.
II.B.4 Training for Mitigating Core Damage 1
Shift technical advisors and personnel in the operating chain up to and including the plant manager will receive training for mitigating core damage. Managers and technicians in the instrumentation and control, health physics and chemistry departments will receive mitigating core damage training commensurate with their responsibilities.
Based on cur review, we conclude that the applicant has complied with the requirenent of this task of the TMI Action Plan.
Bea Rosenberg, 24816 DS-SER FOR SHEARON HARRIS /BEA20 9/2/ L
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13.2.2 Training for Non-Licensed Plant Staff The applicant has described in the FSAR the details of the training given to nonlicensed plant personnel.
The training program for nonlicensed personnel 411 provide training for maintenance personnel, instrumentation and control -
personnel, radiation protection personnel, radwaste personnel, nuclear physics personnel, management and supervisory personnel, technical personnel and training instructors.
All permanently employed plant perspnnel will participate in a General i
Employee Training Program consistin'g of, but not limited to Radiological Health and Safety, Quality Assurance, Industrial Safety, Plant Security, Emergency Plan, Fire Protection and other appropriate plant plans and procedures.
Shift technical advisors (STAS) will receive approxiir.ately 36 weeks of training in the areas of management and leadership, reactor theory, plant system description, plant procedures, technical specifications, transient and accident response, mitigation of core damage, simulater training.
Based on our review, we find that the training program for SHNPP STAS closely agrees with the guidance described in Appendix C to NUREG-0737.
However, the applicant has not adequately addressed the trairing provided to the STA who has been absent from STA duties.
We will require that:
(1)STAnotactively performing the STA functions for a period of thirty days or longer shall, Bea Rosenberg, 24816 DS-SER PlR SHEARON HARRIS /BEA20 9/2/83
.. prior to assuming responsibilities of the position, as a minimum receive training sufficient to ensure he is cognizant of facility / procedure changes that occurred during his absence, and (2) STA not performing the STA functions for a period of six months or longer shall, prior to assuming the responsibilities of the position, receive the annual requalification training as described in Appendix C to NUREG-0737.
The fire protection training program includes classroom instruction and training in fire fighting equipment use, strategies, techniques and periodic drills.
We conclude that the applicant's fire protection training program conforms to the guidance given in the Standard Review Plan, Section i
13.2.2.II.C.A and is acceptable.
Based on our review, we find that the training given for nonlicensed plant staff personnel meets the requirements of 10 CFR Part 19 and Part 50 and follows the guidance given in Regulatory Guide 1.8.
Therefore, we conclude
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that the applicant's training program for nonlicensed plant staff with the exception of STA training program is acceptable.
Bea Rosenberg, 24816 DS-SER.FOR SHEARON HARRIS /BEA20 h