ML20209C616
| ML20209C616 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 11/17/1983 |
| From: | Russell W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1476 NUDOCS 8312020053 | |
| Download: ML20209C616 (18) | |
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NOV 171983 IlEIIORNIDUit FOR: Thomas A. flavak, Assistant Director for Licensing Division of Licens'ing FRCil:
William T. Russell, Deputy Director Division of Iluman Facters Safety
SUBJECT:
DRAFT SER FOR WASHIflGTON NUCLEAR PROJECT 3, PLANT PERSONNEL TRAINING Plant flane: Washington Nucicar Project 3 (WNP-3)
Docket No.: 50-508 Licensing Stage: OL Responsible Branch and Project l'anager: LG #3, A. L'ietti Review Status: Draft SER With Open Items The enclosed draft $ER includes our review of Licensed Reactor Operator Training (SRP 13.2.1) and Training for Non-Licensed Plant Staff (SRP 13.2.2) for WNP-3.
This draft SER was prepared by the Personnel Qualifications Section of the Licensee Qualifications Branch after having reviewed the applicable section of the FSAR and the applicant's response to the Pequest for Additional Infortnation.
With regard to the Initial training program, the applicant has not provided (as noted in the draf t EER Section 13.2.1.1,':
(1) a program in accordance with the guidelines cutlined in En:1osure 2 of H. R. Denton's liarch 28, 1980 letter for instruction in fluid flow, thenr.odynanics and heat transfer, and (2) a progran to provide t. raining in the use of installed plant systens to control or mitigate an accident in which the ccre is severely damaged.
Therefore, we cannot conclude that the applicant's initial training progran for reactor operators and senior reactor uperators is acceptable.
With regard to the requalification progran (as noted in the draft SER Section 13.2.1.2.1(1)) the content of the Lccture Series does not ccver all the subjects as listed.in the Appendix A of 10 CFR Part 55 and Enclnsure 1 of H. R. Denton's fiarch 28, 1980 letter.
In addition, the applicant has not provided:
(1) a program for instruction in procecures and facility 11cene changes (as noted in draft SER Section 13.2.1.2.1(2)(c)), (2) a program to ensure that each licensed reactor operater and senior reactor operator will review the contents of all abnormal and cuergency procedures cr. a regularly scheduled basis (as noted in the draft SER Sec.tien 13.2.1.2.1(2)(d)),and(3) the modified passing grade (as noted in the draft SER Section 13.2.1.2(2)(3))
required for accelerated requalification. We, tnerefore, find that the apn14 ~ + - '" N tia t @ inn pycgram 1s net acceotable.
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,c f \\ j Thomas A. Hovak We find that (as noted in the draft SER Section 13.2.1.3) the applicant has not fully satisfied the requirements of the Ti!I Action Plan, itens I.A.2.1, I.A.2.3 and II.B.4.
The applicant has not provided a training program for Shift Technical Advisors (as noted in the draft SER Section 13.2.2).
Based en 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 follcws the guidance given in Rcgulatory 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.
This review has been conducted by D. Shua (X24905).
There are no known dissenting professional opinions within DHFS concerning the conduct or conclusions of this evaluation. We will be happy to r.eet with the applicant to discuss our concerns and to resolve the above open issues.
Original signed by:
Willian T. Russell, Deputy Director Division of Hunan Factors Safety
Enclosure:
DISTRIBUTION:
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DRAFT SAFETY EVALUATION REPORT FOR WASHINGTON NUCLEAR PLANT, UNIT 3 (WNP-3)
DOCKET NO.:
50-508 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 THI 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 A training program for WNP-31Icensed 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 require'ments of 10 CFR Parts 50 and 55, ana 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.
13.2.1.1 Initial Training Program The initial training program for personnel who will be licensed consists of the following discrete segments:
(1) Academic and Nuclear Plant Fundamentals This training course will be approximately twenty weeks in length and is designed to provide individuals with basic knowledge in science and
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technology of power plant 6perations.
The major areas to be covered are mathematics, physics, ' basic nuclear physics, reactor theory, radiation protection, chemistry, ins.trumentation and control, health physics, electrical theory, transient analysis, fluid flow, thermodynamics and heat transfer.
The extent of participation will be determined by the individual's experience and education Javel.' An integral part of the fundamental training program is reactor startup experience.
This is a
,a one-week training course conducted stya research reactor for cold license candidates only.
t With respect to instruction in the top,1cs of fluid flow, thermodynamics and heat transfer, we require the applicant to provide a program in accordance with the' guidelines as outlined in Enclosure 2 of
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We will review the program when H. R. Denton's March' 28, 1980 1etter.
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it is received and report our findings in the final SER.
I (2)
Plant Systems - Classroom This training course is des'fyne,d to provide cold license candidates with an in-depth study of the WNP-3 systems and equipment.
The course'
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consists of approximately ninrIweekd of classroom lectGres on nuclear steam supply system and balance of the plant system des'ign, components and operation; instrumentation, control and electrical system design and operation; safety analysis and technical specifications; and operating i
and emerger.cy experienca.
Effectiveness of this training will be monitored through examinations.
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In addition to the above topics, we require (as specified in Enclosure 1 of H. R. Denton's March 28, 1980 letter) the applicant to modify the '
program to provide training in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
s We will review this modification, when it is received, and report our findings in the final SER.
(3) Plant Systems - Observation This segment of the training progran consists of four weeks of plant observation.
The major objective of this program is to familiarize each cold license candidate with the daily routine involved in the operation of a PWR of similar design.
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(4) Simulator Training
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This training program will be approximately ten weeks in length on the WNP-3 simulator, and will consist of classroom lectures, simulator control room lectures and demonstration, and simulator control room exercises.
The training will include, but not be limited to the following; Classroom sessions consisting of lectures, seminars, and examinations.
Demonstrations of how to control individual systems and the integrated plant.
Practice of normal and emergency plant operations, including recognition of emergency conditions and response to malfunctions by the license candidate.
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i Exercises during which the license candidates operate the simulator without instructor assistance and receive evaluation of ability to safely. and efficiently operate the plant.
Simulator sessions will also include all the control manipulations as listed in Section~13.2.1.2.1(2)(b) of this report. At the conclusion of the simulator training phase, each candidate will be given examinations to determine his ability to control the operations of the pla'nt in a safe and competent manner.
(5) Onsite Experience Training'in the form of practical work assignments at the WNP-3 will be provided for approximately 26 weeks.
Work assignments may include:
plant operating procedure preparation and verification, preoperational testing of plant systems, participation in hot functional testing program, low power physics and escalation to power test programs, and preparing and providing instruction on plant systems.
Emphasis shall be on the license candidate gaining thorough knowledge of WNP-3.
(6)
Senior Operator and Shift Manager Duties This training phase, designed to train senior reactor operators and shift managers, is approximately one to three weeks in duration.
The program consists of:
leadership, communication, motivation of personnel, problem analysis, decision analysis, command responsibility and limits, and administrative requirements for the particular SR0 position.
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(7) License Review Training This is an approximately four week course designed to improve the wedk areas brought out from a comprehensive examination and to bring the license candidates to a peak knowledge level for the NRC examinations.
(8) Training Program Evaluation The performance of employees participating in the cold license training program are monitored and evaluated throughout the program.
Frequent examinations are given to. license candidates in order to determine the effectiveness of the training and knowledge of the trainees.
Based on our review, we find that the applicant's initial training program conforms to the requirements of the applicable portions of 10 CFR parts 50 and 55, and follows the guidance given in Regulatory Guide 1.8..However, as noted in the above Sections 13.2.1.1(1) and (2) of this report, the applicant's initial training program does not satisfy the requirements as outlined in H. R. Denton's March 28, 1980 letter to all power reactor applicants and licensees.
Thus, we have not been able to conclude that the applicant's initial training program for reactor operators and senior reactor operators is acceptable.
13.2.1.2 Licensed Operator Requalification and Replacement Training Programs Following the initial licensing of cold license candidates, requalification and replacement training programs will be implemented to maintain and demonstrate the continued competence and the level of proficiency of all licensed personnel.
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13.2.1.2.1 Requalification Training Program A requalification training program conducted by the applicant for all licensed reactor operators and senior reactor operators will be implemented shortly after receipt of cold licenses.
This program will be conducted on a repetitive two-year cycle and will consist of the following:
(1) Lecture Series The applicant has indicated that at least six pre-planned requalification training lectures will be scheduled throughout the year.
Lecture sub'jects and content will be based on the results of the an.nual examination administered to licensed reactor operators and senior reactor operators.
However, the content of the examination described in the FSAR by the applicant does not cover all the subjects as listed in Appendix A of 10 CFR Part 55. ~ We will require the cont'ent of the annual examinations to be modified to include the following subjects as listed in Appendix A of 10 CFR Part 55 as well as in Enclosure 1 of H. R. Denton's March 28, 1980 letter:
Theory and principles of operation General and specific plant operating characteristics Plant instrumentation and control systems Plant protection systems l
Engineered safety systems Normal, abnormal, and emergency operating procedures l
Radiation control and safety Technical specifications j
Applicable portions of Title 10, Charter I, Code of Federal Regulations
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Heat transfer, fluid flow, thermodynamics and mitigation of accidents involving a degraded core.
The annual written examination results will indicate the scope and depth of training needed by each individual in the above areas.
We will review the applicant's modification to include instruction of the above subjects in the Lecture Series and report our findings in the final SER.
(2) On-the-Job Training The on-the-job training portion of the requalification program will consist of the following:
(a) Simulator Training Each licensed reactor operator will spend 40' hours annually in a simulator training program.
The program will contain instruction in facility changes, recognition of emergency conditions, and operating experience at WNP-3 and similar plants.
(b) Control Manipulations Licensed reactor operators will manipulate and direct or evaluate the activities of those manipulating the station controls through the following reactivity changes during the term of their licenses.
The asterisked items will be performed annually and all other items will be performed on a two-year cycle.
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Plant or reactor start-ups to include a range that reactivity feedback from nuclear heat addition is noticeable and heat.up rate is established
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Plant shutdown Manual control of steam generators and/or feedwater during start-up and shutdown Boration and/or dilution during power operation Any significant (> 10%) power changes due to manual changes in control rod position or boron concentration Loss of coolant including:
1)
Significant PWR steam generator tube leaks 2)
Inside primary containment
- 3) Large and small, including leak-rate determination
- 4) Saturated Reactor Coolant response (PWR)
Loss of instrument air Loss of electrical power (and/or degraded power sources)
Loss of core coolant flow / natural circulation Loss of condenser vacuum Loss of service water if required for safety Loss of shutdown cooling Loss of component cooling system or cooling to an individual component Loss of normal feedwater or normal feedwater system failure Loss of all feedwater (normal and emergency)
Loss of protective systems channel Mispositioned control rod or rods (or rod drops)
Inability to drive control rods l
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Conditions requiring use of emergency boration of standby liquid control system Fuel cladding failure or high activity in reactor coolant or offgas Turbine or generator trip Malfunction of automatic control system (s) which affect reactivity Malfunction of reactor coolant pressure / volume control system Reactor trip Main steam line break (inside or outside containment)
Nuclear Instrumentation failure (s)
The above control manipulations will be performed on the simulator and/or the plant.
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('c) Knowledge of Facility Design, Procedure, and License Changes The applicant has not addressed the instructions of procedure changes and facility license changes. As described in Appendix A of 10 CFR Part 55, we require the applicant to provide a training program to ensure that each licensed reactor operator and senior e
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reactor operator will be cognizant of facility design changes, procedure changes, and facility license changes.
We will review the applicant's modification of the program to include instructions of these subjects and report our findings in the final SER.
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t (d)
Knowledge of Abnormal and Emergency Procedures In order to ensure a continuing awareness of the actions and responses necessary during abnormal and emergency situations, as described in the Appendix A of 10 CFR Part 55, we require the applicant to provide a program to ensure that each licensed reactor operator and senior reactor operator will review the contents of all abnormal and emergency procedures on a regularly scheduled basis.
We will review this program when it is received and report our findings in the final SER.
(3) Evaluation
'The evaluation program for licensed personnel includes the following:
(a) Annual Written Examinati6n An annual written examination will be given to each licensed reactor operator and senior' reactor operator. -The examination will contain the categories a: described under Lecture Series.
The applicant has indicated that a grade of less than 70% in any category shall require accelerated requalification in that category. A grade of less than 75% overall requires accelerated requalification in all categories graded less than 75%.
As specified in H. R. Denton's March 28, 1980 letter, we require the above criteria for accelerated requalification to be modified to be consistent with the new passing grade for issuance of a license; 80% overall and 70% each category.
We will review the
' 3 applicant's modification to the above criteria and report our findings in the final SER.
(b) Annual Oral Examination and Performance Observation An annual oral requalification examination will be given.
In addition, each licensed reactor operator and senior reactor operator will be evaluated annually on his performance.
The evaluation will include observation of performance during actual or simulated plant conditions.
Any individual given an unsatisfactory overall evaluation will require accelerated requalification.
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(4) Accelerated Requalification Individuals requiring accelerated requalification as a result of annual examination will not perform licensed-duties until successfully completing the program. Accelerated requalification will be given in the categories required or areas identified in the written or oral examination.
Successful completion of the program will be measured by a reexamination of the individual categories, repeating an entire written examination or repeating the oral examination.
Successful completion of an accelerated requalification program will be by grade criteria identified in the written and oral sections above.
13.2.1.2.2 Replacement Training Program Replacement training will be conducted to fill vacancies and will prepare individuals for increased responsibility in the supervisory, technical or
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o 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.
As noted in the above Sections 13.2.1.2(1), 13.2.1.2.1(2)(c) and (d), and 13.2.1.2.1(3)(c) of this report, we find that the applicant's requalification and replacement training programs do not satisfy the requirements specified in Appendix A of 10 CFR Part 55 and in the letter from H. R. Denton to all power reactor applicants and licensees dated March 28, 1980.
Therefore, we have not been able to conclude that the applicant's requalification and replacement training programs for reactor operators and senior reactor operators are acceptable.
13.12.1.3 TMI Related Requirements for New Operating License I.A.2.1 Immediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualifications The applicant has established a program intended to assure that all reactor operator and senior reactor operator license candidates have the prescribed experience, qualification and training.
The applicant has indicated that certifications completed pursuant to Section 55.10(a)(6) and 55.33a(4) and (5) of 10 CFR Part 55 shall be made by the Plant Manager.
However, as specified in Enclosure 1 of H. R. Denton's March 28, 1980 letter, we require that all licensed operator candidates will be certified competent to take the NRC license examinations by the highest level of corporate canagement for plant operation (for example, Vice President for Operations) prior to application for the examinations.
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As an operating license applicant, WNP-3 is not subject to the one year experience requirements for cold license SR0 candidates. However, after one year of station operation, individuals applying for an SR0 ifcense will be required to comply with the one year experience requirement for hot license SR0 applicants, unless previously experienced in an equivalent position at another nuclear plant or at a military propulsion reactor.
The experience of license applicants in the latte.r category will be documented by the applicant or. a case-by-case basis in sufficient detail so that the staff can make a finding regarding equivalency.
SR0 license applicants who possess a degree in engineering or applicable sciences are considered to meet the one year experience requirements as an R0 provided they:
(1) satisfy' the requirements set forth in Sections A.I.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 to that of a cold senior reactor operator applicant.
The applicant has not committed to comply with the above requirements.
Also, the requirement for three months on-shift experience for control room operators and SR0 candidates as an extra person on shift is not required for cold licerise candidates and, hence, is not applicable to WNP-3.
- However, WNP-3 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 i
flow, and thermodynamics.
However, the applicant has not provided a program i
for the instruction of these topics in accordance with Enclosure 2 of I
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H. R. Denton's March 28, 1980 letter.
We require the applicant to provide this program for review, and we will report our findings in the final SERJ 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 during the certification examination given by the training facility.
Based on our review, we have not been able to conclude that the applicant of WNP-3 has satisfied the requirements of this item of the TMI Action Plan.
I.A.2.3 Administration of Training Program As specified in Enclosure 1 of H. R. Denton's March 28, 1980 letter, we require that all instructors who teach systems, integrated responses, t'ransient and simulator courses shall be SR0 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 t'he permanent or nonpermanent training staff who are responsible for teaching technical subjects, such as reactor theory, heat transfer, fluid mechanics, thermodynamics, health physics, chemistry, and instrumentation are not expected to have an R0 or SR0 license.
Guest lecturers considered to be used on a limited bases shall be monitored by a qualified instructor.
These guest lecturers are exempt from the SR0 criterion.
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Based on our review, we find that the applicant of the WNP-3 has not committed to comply with the above requirements of this item of the THI Action Plan.
II.B.4 Training for Mitigating Core Damage As specified in Enclosure 3 of H. R. Denton's March 28, 1980 letter, we require that 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 our review, we find that the applicant has not complied with the above requirements.
In addition, the applicant has not provided, for NRC review, a training program for mitigating core damage in accordance with the guidance as specified in Enclosure 3 of H. R. Denton's March 28, 1980 letter.
We will review this training program when it is received and will report our findings in the final SER.
13.2.2 Training for Nonlicensed 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 will provide training for maintenance personnel, equipment operators, health physics and chemistry technicians, management and supervisory personnel, technical personnel and training instructors.
All permanently employed plant personnel will participate in a general employee training program consisting of, but not limited to radiological
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health and safety, quality assurance, industrial safety, plant security, station emergency plan, fire protection and other appropriate plant plans and procedures.
The applicant has not provided a training program for the Shift Technical Advisors (STA). We require the applicant to provide for our review a training program for the STA in accordance with the guidance as specified in NUREG-0737, Appendix C.
We will report the results of our review in the final SER.
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 13.2.2.II.C.A and is acceptable.
Based on our review, we find that the training given for nonlicensed plant I
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 i
that the applicant's training program for nonlicensed plant staff, with the exception of the STA training program, is acceptable.
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