ML20041C896
| ML20041C896 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/25/1982 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-82-165, NUDOCS 8203020644 | |
| Download: ML20041C896 (16) | |
Text
v KANSAS GAS AND ELECTRIC COMPANY THF ELECTAC COMPANV l
1 i
GLENN L KOESTER v.<<
es.w.,
uct..
February 25, 1982 O
g Mr. Harold R. Denton, Director t
Office of Nuclear Reactor Regulation ND U.S. Nuclear Regulatory Commission
. S-- g I ISO 2b $
F Washington, D.C.
20555
~
KMLNRC 82-165 Re:
Docket No. STN 50-492 N
g Subj: NRC Management Structure and Technical Resources Review Team Commitments
Dear Mr. Denton:
The NRC's Management Structure and Technical Resources Review Team visited KG&E offices in Wichita and at the Wolf Creek Site during the week of January 18, 1982. During the visit KG&E committed to revise or clarify several items in the Wolf Creek FSAR and to provide some additional information.
The attachments document KG&E's resolution of the meeting's commitments, except for those related to our training described in FSAR Section 13.2.
A complete revision of FSAR Section 13.2 will be forwarded to the NRC by March 5,1982 to document our revised training commitments.
Attachment I provides revised FSAR pages which include:
- 1. A description of the Wolf Creek Plant Safety Review Committee's (PSRC) review of major and minor designated procedures (Section 13.5.1.2).
- 2. A description of how the PSRC and Joint Test Group review pre-operational test procedures and results (Sections 13.4.1.1, 14.2.3.2.1).
- 3. Wolf Creek Fire Plan revisions to document annual hands-on training for fire brigade members (WCGS Fire Protection Program Section 2.1).
- 4. An amplified description of KG&E's program to 1) upgrade the academic qualifications of our Senior Reactor Operator and F203020644 820225 l
PDR ADOCK 05000482 i
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A PDR 201 N. Market - Wichita, Kansas - Mail Address: PO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451
Mr. Harold R. Denton KMLNRC 82-165 February 25, 1982 Shift Supervisor personnel, 2) review the Wolf Creek Control Room to make information and controls more useful to operators,
- 3) provide shift consultants with operating experience, and
- 4) use of a WCGS specific simulator for training. These sections describe KG&E's present and long-term solution to the issue of a shift technical advisor in the control room. As described in the FSAR change, it is KG&E's strongly held opinion that the augmented training program for our operators better serves public safety than does adding a separate shift technical advisor i
(Sections 18.1.1.2, 18.1.1.3).
- 5. Contingent upon the acceptability of 4) above, KG&E's commitment to an operating shift crew compliment of 10 personnel including an individual trained in chemistry procedures (Radiological Emergency Responso Plan Table 1.1-1).
- 6. An updated resume for the plant Maintenance Supervisor which describes his experience and training. In addition, KG&E commits to sending the Maintenance Supervisor for additional training on ASME Code Sections III and XI to expand his previous code knowledge.
This training will be complete at least six months prior to fuel load (Section 13.1.3.2).
The revised FSAR material will be formally incorporated into the Wolf Creek Generating Station, Unit No.1, Final Safety Analysis Report in Revision 9.
The information herein is hereby incorporated into the Wolf Creek Generating Station, Unit No.1, Operating License Application.
Yours very truly,
_ fry fD GLK:bb Attach cc: Mr. J.B. Hopkins (2)
Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Thomas Vandel l
Resident NRC Inspector f
P.O. Box 311 Burlington, Kansas 66839
[
Mr. Eric Johnson i
U.S. Nuclear Regulatory Commissioa, Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 I
l
OATH OF AFFIRMATION STATE OF KANSAS
)
) SS:
COUNTY OF SEDGWICK )
I, Glenn L. Koester, of lawful age, being duly sworn upon oath, do depose, state and affim that I am Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of transmittal, know the contents thereof, and that all statements contained therein are true.
KANSAS GAS AND ELECTRIC COMPMJY By ry d24 Glenn L. Koester Vice President ' Nuclear W.B. Walker, Secretary STATE OF KA'ISAS
)
) SS:
COUNTY OF SEDGWICK )
BE IT REMEMBERED that on this 25th day of February, 1982 be fore me, Evelyn L.
Fry, a Notary, personally appeared Glenn L. Koester, Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, who is personally known to me and who executed the foregoing instrument, and he duly acknowledged the execution of the same for and on behalf of and as the act and deed of said corporation.
IN WITNESS WHEREOF, I have hereunto set my hand and affixed my seal the date and year above written.
f s.&!I h
--Eystyn te. Fry, Notary A
d entsv $ $ W s.,m.y.
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l' y g Q ec,5mnission expires on August 15, 1984.
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SNUPPS-WC procedures for that activity.
The actual preparation of procedures may be performed by other KG&E personnel or by outside contractors, but the final responsibility lies with the designated responsibic position.
Temporary changes can be made to approved procedures.
Tem-porary changes must be approved by a cognizant Group Leader and the responsible Section Supervisor.
At least one of these members shall have a Senior Reactor Operator license for all procedures affecting plant operation.
Procedures are classified by the Plant Safety Review Commit-tee (PSRC) as Safe ty-Related (SR) or Non-Nuclear Safety-Related (NNSR).
The SR procedures are further subdivided into Major and Minor procedures.
All procedures are reviewed and the reviews documented by qualified personnel.
All major SR procedures shall be reviewed by at least one individual other then the preparer, by the Plant Safety Review Committee (PSRC), and by the Plant Superintendent.
Review by the PSRC may be conducted and documented by indi-vidual members outside of formal meetings.
Tempo rary changes to major procedures which do not change the intent of the approved procedure revision may be made provided such changes are approved by the Cognizant Group Leader and one of the Duty and Call Supervisors.
At least one of these members shall have a Senior Reactor Operator license for all procedure affecting plant operation.
These changes shall subsequently be reviewed by the Plant Safety Review Committee (PSRC) and approved by the Plant Superin-tendent and shall then become permanent changes if appropri-ate.
Permanent changes to major procedures will be reviewed and approved as per the previous revision.
All temporary and permanent changes to minor SR procedures shall be approved by a cognizant group leader and reviewed and approved by the PSRC or an assigned subcommittee of the PSRC.
All tempora ry and permanent changes to NNSR proce-dures will be approved by a cognizant group leader and re-viewed and approved by the responsible section supervisor.
13.5.1.3 Procedures The Plant Superintendent will develop and implement station administrative procedures that provide a clear understanding of operating philosophy and management policies.
As stated in 13.5.1.2, administrative procedures will be inplemented that provide methods for preparation, review and approval of all other station procedures including permanent procedures, temporary procedures or any procedures that might be of a transient or self-cancelling nature.
Rev. 9 13.5-2
e SNUPPS-WC 13.4 REVIEW AND AUDIT A program for review and audit _ of activities affecting station safety during the operational phase has been estab-lished.
The program provides a system to insure that these activities are performed in accordance with company policy and rules, approved procedures and license provisions.
This program will provide review of safety-related plant changes, tests, and procedures.
13.4.1 ONSITE REVIEW Proposed physical changes to nuclear-safety-related systems, changes to nuclear-safety-related procedures, any new or modified tests or experiments involving nuclear-safety-related systems, and unplanned events that have operational nuclear-safety significance will be reviewed by the Plant Safety Review Committ'ee.
13.4.1.1 Plant Safety Review Committee (PSRC)
The PSRC is composed of certain supervisory and technical personnel as described in the Administratve Controls Section of the lechnical Specifications.
The PSRC is charged with reviewing those nuclear-safety-related activities described in the Technical Specifications and with advising the Plant Superintendent on the disposition of those items reviewed.
The PSRC may also review other nuclear-safety-related activ-ities as deemed appropriate by the Plant Superintendent.
A subcommittee of the PSRC, the Joint Test Group (JTG) is established for the review of preoperational test procedures in accordance with Section 14.2.3.2.
13.4.2 INDEPENDENT REVIEW Activities affecting station safety occurring during the operational phase will be independently reviewed by the Nuclear Safety Review Committee.
13.4.2.1 Nuclear Safety Review Committee (NSRt The NSRC will function as an independent body to review safety-related station matters.
It shall report its find-ings and recommendations to the Vice President - Nuclear.
The membership of the NSRC and. the subject matter to be reviewed is detailed in the Administrative Controls Section of the Technical Specifications.
The MSRC may also review other safety-related activities as deemed appropriate by the Vice President - Nuclear.
Rev. 8 13.4-1 2/82
SNUPPS-UC 14.2.2.6 Qualifications of Key Personnel The qualifications for key plant operating personnel are described in Chapter 13.0.
The qualification requirements for startup personnel involved in the WCGS startup program conform to capability levels per ANSI N45.2.6 and Regulatory Guide 1.8 recommen-dations.
All test personnel will be indoctrinated in the startup administrative procedures, methods and controls.
14.2.3 TEST PROCEDURES i
14.2.3.2 Procedure Review and Approval 14.2.3.2.1 Joint Test Group (JTG)
A subcommittee of the - PSRC, the JTG will be organized by l
KG&E to review preoperational test procedures and preopera-tional test results.
The primary JTG functions will be to:
1.
Review preoperational test procedures and recommend their approval by the Plant Super-intendent and the Startup Manager.
2.
Evaluate and authorize changes to preoper-ational test procedures as detailed in the Startup Administrati, Manual.
3.
Evaluate preoperational test procedure re-sults and present those results to the PSRC for its approval.
4.
Recommend that the Startup Manager and the Plant Superintendent approve for system turn-over purposes the preliminary preoperational test results.
By his approval of the pre-liminary test results, the Plant Superintend-ent accepts turnover of the tested system from Startup.
I Membership in the JTG will include the following personnel or their designated representatives:
i Rev. 8 14.2-7 2/82
a c.
The toxic characteristics of expected pro-ducts of combustion.
d.
Identification of the location of fire fight-ing equipment for each fire area and famil-iarization with the layout of the plant, including access and egress routes to each area.
e.
The proper use of available fire fighting equipment and the correct method of fighting each type of fire.
The types of fires in cables and cable trays, hydrogen fires, fires involving flammable and combustible liquids or hazardous process chemicals, construction fires, and record file fires.
f.
The proper' use of communication,
- lighting, ventilation, and emergency breathing equip-ment.
g.
The proper method for fighting fires inside buildings and confined spaces.
h.
The direction and coordination of the fire fighting activities (Fire Brigade Leaders only).
NOTE:
Fire Brigade Leaders and all other operations personnel, assigned to Fire Brigade duty, will also recieve train-ing in the following areas:
i.
Detailed review of fire fighting strategies and procedures.
j.
Review of the latest plant modifications and corresponding changes in fire fighting plans.
2.1.3 Practice Sessions All Fire Brigade members will participate in training exer-cises designed to provide experience in actual fire extin-guishment and the use of emergency breathing apparatus under strenuous conditions, as those which may be encountered in fire fighting.
These exercises will be included in each Fire Brigade member's initial training.
Practice sessions will be provided on an annual basis for all Fire Brigade members.
2.1.4 Assignment to Fire Brigade Duty I
Upon the completion of the training outlined in Section 2.1.2 and 2.1.3 the individual's name will be placed on the Rev. 9,
i Fire Brigade roster.
He may then be assigned to Fire Brigade duty as needs require.
2.1.5 Complete Training for Fire Brigade Members l
Over a two year period following initial qualification, Brigade members will receive periodic refresher training such that all areas of Section 2.1.2 are covered within the two year period.
The training may consist of a combina-tion of classroom work and drills as described in Section 2.6.
Training sessions will be conducted at least once every three months.
To maintain active status on the Fire Brigade
- Roster, each member must complete all of the refresher training, practice sessions and must participate l
in at least two fire drills per year.
2.2 Training for Personnel Authorized Unescorted Access to WCGS i.
t 1
Rev. 1
-6a-
SNUPPS-WC 18.1.1.2 KG&E Response 1
4 4
General As stated in NUREG-0737 and the above position statement, the requirement for an STA qualified person in the power plant in addition to an SRO licensed Shift Supervisor is a temporary requirement until the qualifications of the Shift Supervisor are upgraded and control boards are reviewed and modified to make information and controls more useful to the operators.
This is consistent with the industry consensus established by INPO standard GPG-01, " Nuclear Power Plant Shif t Technical Advisor Position Description Qualifications, Education and Training" which refers to the fact of this position being " eliminated" when certain additional actions are completed and the December 17, 1981 approved copy of ANSI /ANS 3.1 which also referred to this position as "in-terim."
Two members' of the NRC staff participated in the preparation and approval of ANSI /ANS 3.1.
Control Room Review The SNUPPS plants have retained a consultant to conduct control board
" human factors" reviews.
Results of these reviews have already partially been submitted to the USNRC.
Four significant actions have been undertaken and will be completed by fuel load to improve the operator-control board interface and the decision making process by the Shift Supervisor.
1.
Extensive rearrangement of switches, recorders and indicators is being undertaken to improve location relationship of equipment controls and associated indications.
s 2.
The location of all annunciators have been re-viewed and an extensive hierarcaical prioritiza-tion arrangement has been developed to assist the operator in recognizing independently significant and dependent annunciator alarms.
3.
Panels of status and permissive lights have been rearranged into functional groups and methods of designating different plant safeguards modes have been considered to improve the operator's ability to understand and respond to these indications.
4.
The SNUPPS utilities, in conjunction with the l
Westinghouse Owner's
- Group, have developed an i
extensive Safety Parameter Display System with an ability to display critical parameters, both quan-titatively and graphically.
The Senior Reactor Operators in the control room will have these Safety Parameter Display Systems available to l
Rev. 9 18.1-3
SNUPPS-WC them to monitor plant conditions during any incident.
The original SNUPPS control board design had significant Prairie Island and Ginna plant operating experience input from Northern States and Rochester Gas and Electric during the initial design phases and had more extensive mimicking than most nuclear plant control boards.
The above modifica-tions are improving upon one of the better pre-TMI control board designs and should result in the control board sup-plying relevant, easy to comprehend information to all con-trol room personnel.
College Program KG&E.is conducting an extensive college education program to i
upgrade the academic. qualifications of its SRO candidates.
If the 60 semester credit hours of college level courses in mathematics, reactor physics, chemistry, materials, reactor thermodynamics, fluid mechanics, heat transfer, electrical and reactor control theory are necessary for nuclear power plant control room operations, it is the strongly held opin-ion of KG&E that this training should be invested in one or more personnel responsible for the shift operations as opposed to adding a technical advisor position.
KG&E is of the opinion that the public safety is much better served if appropriate personnel responsible for safe operation of the plant have all the prerequisite knowledge for plant opera-4 tions and safety, rather than having to rely on an advisor.
The placement of increased knowledge in line supervisory personnel is far more effective in the decision making pro-cess than a separate " advisor" who has specialized technical training but far less, if any, operating experience than any of the individuals that he is " advising."
Human engi-neering dictates a solution based on utilization of line management.
KG&E engaged the services of the faculty of Emporia State University and Kansas State Unive rsity to conduct college level courses for college level credit in the following subjects (semester credit hours in parentheses):
College Algebra (3)
Trigonometry (2)
Calculus I and Calculus II (6)
Applied Differential Equations (3)
Chemistry I and Chemistry II with labs (8)
Physics I and Physics II with labs (8)
Statics (3)
Properties of Engineering Materials (2)
Electrical Circuit Technology with lab (4)
Energy Conversion Technology (Thermodynamics) (3)
Mechanics of Fluids (3)
Materials of Reactor Systems (2)
Rev. 9 18.1-3a
SNUPPS-WC Radiation Detection and Monitoring with lab (3)
Nuclear Reactor Technology I and II (neutron physics, reactor theory, control theory) (6)
Nuclear Reactor Thermal Technology (reactor fluid systems and heat transfer) (3)
Radiation Protection (2)
The above classes are part of the Kansas State University curriculum to obtain a Bachelor of Science in Engineering Technology, Nuclear Reactor Technology option, degree.
This program is accredited by the ABET /ECPD (Accreditation Bureau fo r Engineering and Technology of the Engineering Council of Professional Development).
This program has been submitted to INPO and certified in writing by INPO as meeting all the college level academic requirements for the Shift Technical Advisor.
This program addresses every topic in the December 17, 1981 ANSI 3.1 standard for Shif t Super-visor academic training.
This program provides college level training in every topical requirement of any proposed 10CFR55 draft revision that has come to public view.
The Kansas State-Emporia State University program provides training in every topic proposed to date and should more than satisfy any final requirements for college level training.
As of February 1, 1982, 28 credit hours of the college level program have been completed.
The remainder of the program will be taught in four more 8-week segments to be completed by January, 1983.
KG&E has 16 personnel participating in this program full time and seven others participating part time depending on previous college experience.
These per-sonnel are all shift supervisors, supervising operators, or control room operator candidates.
Additional plant staff-engineers will participate in many of the nuclear courses.
Academic results to date have been exec 11ent, and this pro-gram should provide a significant pool of personnel with appropriate academic qualifications on shift.
In recognition that a program to provide college level training to future operators will be required, KG&E has con-tracted Emporia State University and Kansas State University to provide continuing services in the future.
All the loc-tures by faculty members have been videotaped and these will be edited and supported with workbooks that reference the videotapes, textbooks and examples to reduce the oncite pro-fessorial participation in the future.
- However, Emporia State University and Kansas State University will continue to administer examinations, teach a reduced number of lectures and provide counseling for the conduct of these courses for future SRO candidates.
Rev. 9 18.1-3b
SNUPPS-WC Shift Consultants KG&E has committed to augmenting each on-shif t crew during plant startup and the first year of operation with personnel who have previously held an SRO or RO license on a large commercial PWR.
These personnel will be consultants to the Shift Supervisor and will provide advice and recommenda-tions to him based upon their previous operating experience.
Simulator Training KG&E has purchased a WCGS specific simulator which is planned to be installed at the plant and tested in 1982 with operator training utilizing this simulator to commence in 1983.
The simulator design contains standard SNUPPS power block systems and WCGS site specific systems.
KG&E is com-mitted to Regulatory Guide 1.149 (ANSI 3.5 - 1979) which provides that the simulator be continuously updated to keep it within eighteen months of the WCGS plant control.
All human factors modifications to the WCGS control board will be included in a timely manner into the simulator control l
board.
At the completion of the preoperational test program, data that is appropriate to the simulator will be reviewed and included in the simulator data base.
Prior to the availability of the WCGS simulator, WCGS oper-ator training utilizes SNUPPS simulators operated by Westinghouse.
These simulators duplicate the pre-human factors reviewed control room for WCGS's sister plant Callaway.
Therefore, WCGS operator training and retraining involving a simulator has been or will be accomplished utilizing a simulator which duplicates or very closely duplicates the control room environment and design characteristics of WCGS.
This provides valuable exposure of the WCGS operator to simulated situations which are nearly identical to those he may experience in the WCGS control room and, therefore, gain valuable knowledge for diagnosing and properly responding to actual control room situations.
In the event that a shift crew does not contain one SRO who fulfills the educational guidelines established by the above training program, the Technical -Specifications will req uire that the crew will be supported onshift by a Duty /
Call Technica1' Advisor (DCTA).
These DCTAs will serve as assistants to the Shi.t Supervisor.
The DCTA will be present on all shifts when required and l
available to report to the control room within 10 minutes of notification of an "off normal" event.
The DCTAs will be designated from the engineering and scientific personnel at the Wolf Creek Generating Station (WCGS).
The DCTA will not Rev. 9 18.1-3c l
SNUPPS-WC have the authority to perform or direct plant control manip-ulation, unless, the DCTA is a licensed SRO and is authori -
ed by the Shif t Supervisor to do so.
Specific responsibilities of the DCTAs will be delineated in administative procedures and emergency plan implementing procedures.
Specific personnel available as DCTAs will be designated in call lists also presented in procedures.
Bo-cause the DCTAs are selected from the normal f acility oper-ating organization, they report to their regularly assigned supervisors during normal operations when not on duty assignment.
In an emergency situation, the DCTA reports initially to the Shift Supervisor and the Duty / Call Super-intendent when the latter arrives onsite to assume responsi-bility as Duty Emergency Director.
(See the WCGS Radiologi-t cal Emergency Response Plan. )
DCTAs will possess fu'ndamental knowledge of reactor physics, chemistry, materials, fluid mechanics, heat transfer, and specific knowledge of safety analyses, transient analyses, and plant response as applicable to WCGS.
DCTAs will be familiar with plant design; plant layout; and operating, emergency operating, and emergency plan implementing proced-ures.
DCTAs will possess a bachelor's degree in engineering or science.
Because the DCTAs will be members of the reg-ular plant operating organization, they will be involved in activities associated with normal plant operation, including review and evaluation of operating experience.
18.1.1.3 Conclusion 1
J KG&E's commitments to:
i a.
human factors review of the WCGS control room, b.
providing the educational background necessary for a more effective control room decision making i
process in shift supervisory personnel, c.
temporary use of shift consultants, and d.
extensive use of WCGS control room simulators in the operator training program is consistent with the intent and specifics of the long-term solution to item I.A.1.1 of NUREG-0737.
4 I
l Rev. 9 18.1-3d
1 TABLE 1.1-1 MINIMUM STAFFING REQUIREFENTS.FOR WCGS FOR NUCLEAR POWER PLANT EMEFGENCIES t
Position Title On Capability for Additions Major Functional Area Major Tasks or Expertise Shift 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 hours iN Y,f j
Plant Operations and Shift Supervisor (SRO) 1 Assessnent of Operational Supervising-Operator (SFO) 1 Aspects Reactor Operator (RO) 2 Nuclear Station Operator 4
l Emergency Direction and Duty Energency Director 1**
Control *
(Shift Supervisor until
{
relieved)
Notification /Canmunication Notify licensee, State Energency Connunicator 1**
2 1
local and Federal personnel and maintain comnunication Radiological Accident Emergency Operations EOF Coonlinator 1
2***
Assessnent and Support Facility (EOF) Director (until relieved by Duty 4
I of Operational Accident Offsite Dose Emergency hkinager)
Assessment Assessment-Sr llealth Physics (IIP) 1 Expertisc Offsite Surveys 2
2 Onsite (out-of plant) 1 1
In-plant surveys IIP Personnel 1
1 1
Chemistry /Radicy-Chan Personnel 1
1 l
J chemistry Plant System Tedinical Support Shift Todmical Advisor 1**
l Engineering, Repair Core /Thennal Ilydraulics 1
and Corrective Actions Electrical 1
Mechanical 1
1
-Rev. 9 4
SNUPPS-WC Cooled Fast Breeder reactor where decommissioning, decon-tamination and fast breeder health physics experience was obtained.
Reactor Engineering Supervisor
'W.
B.
- Norton, Reactor Engineering Supervisor, has been employed by Kansas Gas and Electric Company since June, 1979.
IIe obtained a Bachelor of Science degree in Nuclear Engi-neering from Kansas State University in 1979.
Mr. Norton has three years of experience in the nuclear field.
He has attended and received certification from the Westinghouse Station Nuclear Engineer Course and has also attended var-ious computer sof tware courses at Westinghouse.
Mr. Norton gained refueling and startup experience at the Trojan Nuc-lear Plant outage of 1981.
Plans are being nade for him to gain additional experience during the initial core loading and startup testing at the V.
C.
Summer Nuclear Station.
In his three years with KG&E, he has been involved with review of preoperational tests, startup tests, Technical Specifica-tions and preparation of operating procedures.
Maintenance Supervisor M.
D. Rich, Maintenance Supervisor, has been employed by Kansas Gas and Electric Company since June, 1964.
Ile ob-tained a Bachelor of Science degree in Electrical Engineer-ing from Wichita State University in 1964.
Mr. Rich has seventeen years of engineering experience.
lie has served in various positions with KG&E including Results Engineer, Coordinating Engineer-Central Maintenance, Plant Mainte-nance Engineer, and Mechanical Supervisor-Central Mainte-nance.
Ilis responsibilities included performance of tests; evaluation of test results; maintenance scheduling; super-vision of maintenance crews on major maintenance jobs such as turbine generator overhauls, major boiler modification /
repair; and responsible for the total mechanical and elec-trical maintenance program at a fossil plant.
Mr. Rich has been working in KG&E's Nuclear Department since February, 1976.
From February, 1976 until the present, he has served as KG&E's representative on the SNUPPS Spare Parts Group and served as Chairman of that group from 1977 until 1981.
As KG&E's representative on the Spare Parts Group he had the responsibility of selecting and ordering all of the operational spare parts for the WCGS.
As a part of this process, he became heavily involved in rpecifying and reviewing the Engineering and QA requirements for the spare parts.
Considerable time has been spent by Mr. Rich in studying the ASME Section II code as well as associated Regulatory Guides, ANSI and IEEE Standards in order to per-form his job.
Mr. Rich was already familiar with the ASME Section VIII code as well as having a good working knowledge of NDE techniques from his years of maintenance experience in KG&E's fossil plants.
Rev. 9 13.1-19
~ -
...-.a
SNUPPS-WC Mr.
Rich has served as the Maintenance Supervisor at the site since March, 1979.
In this capacity, he has been re-sponsible for establishing the Maintenance Program at the plant.
All maintenance on equipment turned over to the Startup Organization is under the Operations Maintenance organization, therefo re,
the Maintenance Supervisor is responsible for maintenance on equipment starting at initial turnover from Construction to Startup.
In addition to the above, Mr. Rich has participated in a complete refueling outage at Paint Beach Nuclear Plant in the Spring of 1981.
During this outage, Mr. Rich worked very closely with the Maintenance Superintendent at Point Beach.
The following is a list of related training which Mr. Rich has completed:
Reactor Engineering Nuclear engineering course taught by Kansas State University - NE 580 PWR Information Course 2 weeks IRD Vibration Analysis 2-day seminar Qualification of Safety-3-day seminar Related Equipment for Nuclear Power Generation Stations Maintenance and Operation 1-week seminar - Pacific of Centrifugal Pumps l
Executive Introduction to 3 days -
Nuclear Power Plant 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> contact with Operations Simulator SNUPPS simulator l
Courses - Pittsburg SNUPPS l
Simulator l
Plant Support Supervisor D.
R.
- Smith, Plant Support Supervisor, has been employed l
'by Kansas Gas and Electric Company since July, 1981.
He obtained a Bachelor of Science degree in Electrical Engi-neering from the University of Kansas in 1964 and a Master of Business Administration from the University of Washington in 1980.
Mr. Smith has 15 years experience in the nuclear field.
He served 20 years in the U.S.
Navy, receiving a commission in 1964 and retiring in 1975.
His duties /posi-tions have included reactor operator, Electrical Officer, Reactor Control Officer, Engineering Officer of the Hatch and Command Duty Officer during shipyard nuclear power plant Rev. 9 13.1-19a
_ _ _ _ _ _ _ _ - _ _ - _