ML20032E813
| ML20032E813 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/18/1981 |
| From: | Wuller G ILLINOIS POWER CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| U-0335, U-335, NUDOCS 8111230314 | |
| Download: ML20032E813 (61) | |
Text
fil/ND/S POWER COMPANY U-0335 y
L34-8 UH 7TH S REET, OECATUR, lLLINOIS 62525 November 18, 1981 N
g Mr. James R. Miller, Chief (F (
}
9 Standardization & Special Projects Branch p
Division of Licensing j;.
p NOV.2 01981>@--
Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission gvau gnw. /
Washington, D. C.
20555
Dear Mr. Miller:
6 Clinton Power Station Unit 1 Docket No. 50-461 Based on recent meetings and telephone conversations with the CPS-FSAR Chapter 13 Reviewers, Illinois Power Company wishes to make certain changes to Chapter 13 of the Clinton Power Station FSAR..
Certain of these changes have been included in Amendment 9, November, 1981.
Attached to this letter are the pages of Chapter 13 which were included in Amendment 9.
Also enclosed herewith are additional changes to Chapter 13 which will be incorporated into the Clinton operating license application by revision to the FSAR in the next amendment (planned, as Amendment 10, November, 1981).
Sincerely,
~/
G. E. Wuller Supervisor - Licensing Nuclear' Station Engineering GEW/em Attachments cc:
J. H. Williams, NRC Clinton Proj ect Manager H. H. Livermore, NRC Resident Inspector M. M. Holzmer, NRC Region III Paul Collins, NRC Operator Licensing Branch 8111230314 811118 PDR ADOCK 05000461 A
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CPS-FSAR AMENDMENT 9 NOVEMBER 1S81
.e Security provisions in accordance with applicable NRC regulations were incorporated into the overall site development by developing security criteria and incor-porating these criteria into design drawings and speci-fications.
Overall responsibility for the preparation of the FSAR rests e.
with IP.
Preparation of individual sections was assigned to the cognizant technical groups within IP, to Sargent &
Lundy for balance-of-plant systems, and to General Electric Company for nuclear steam supply systems.
f.
Preparation of material and component specifications for Unit 1 is essentially complete except for post-TMI requirements.
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g.
Procurement of materials and equipment for Unit 1 is essentially complete.
Equipment is scheduled for delivery in accordance with the requirements of the construction schedule.,
h.
Management control and review of construction activities are currently exercised routinely during construction of the plant.
Actual completion of construction depends more on external factors such as strikes, delayed equipment de-liveries, and revisions to construction schedules by man-power availability than on internally controllable factors.
13.1.1.1.2 Preoperational Activities The following preoperational activities have occurred or are planned:
a.
Review of Human Engineering Design Review of the Human Engineering design objectives of the control panel layouts, Control Room mimics, and labeling has been completed by General Electric, Sargent & Lundy, and Illinois Power.
Further human-factors engineering reviews are planned as a resull
'of the Post-TMI.nsight into the importance of human-factors engineer.ng to safe plant operation.
These reviews will sati.fy the pcst-TMI requirements of the commission.
General Physics Corporation has completed a preliminary review of human-factors concerns in the Control Room.
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b.
Development and Imolementation of Staff Re'cruiting and Training Programs The training prograns to be utilized are described in Section 13.2.
These progrars are being implerented in accordance with the schedule fudicated ir thdt section.
Recruiting and selection of personnel to fill positions is currently taking place.
The complete staff requirel for Unit 1 startup will be available six months prior to fuel load.
Resumes of key staff personnel are provided in Appendix 13A.
13.1-3
[
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 c.
Plans for Checkout and Initial Operation Plans for Checkout and Initial Operation (C&IO) were essentially complete as of October 1, 1979.
The remain-ing plans for C&IO will be developed prior to actual need by the IP Startup Group in accordance with the pro-gram described in Chapter 14.
d.
Maintenance Activities Programs are being developed to support plant maintenance during preoperational testing.
Key maintenance programs to support station operation are scheduled to be developed throughout the preoperational test program.
These key programs include the following:
Corrective maintenance administrative controls Control and calibration of test and measuring equipment Preventive maintenance administrative controls Storeroom administrative controls the preservice inspection program is being developed in accordance with the 1974 Edition through the summer 1975 Addenda of the ASME Boilc and Pressure Vessel Code.
The inservice inspection program will be a continuation of the preservice inspection program with requirements upgraded as required by 10 CFR 50.55a throughout the life of the Program.,
13.1.1.1.3 Technical Support for Operatians Technical services and support to the Clinton Power Station operating organization are provided prior to preoperational testing and will continue throughout the life of the plant.
These services are provided by the Nuclear Station Engineering Department of IP.
The Manager of NSED is the " engineer in charge" of the technical support personnel as described in ANSI /ANS 3.1-1978, Paragraph 4.6.1.
The Nuclear Station Engineering Department has a current authorized strength of 68.
It is expected that this number will remain relatively constant or increase slightly to approximately 70 to 75 prior to CPS startup.
Except for administrative and clerical support, essentially all Department
,rersonnel are degreed engineers.
The current Department expertise includes the following in years of total experience:
CPS Experience 149 Ocher Nuclear Experience 127 Other Utility Engineering Experience 50 Other Engineering Experience 43 In general, Nuclear Station Engineering Department personnel have expertise in nuclear, mechanical, electrical, thermal-13.1-4
a CPS-FSAR AMENDMENT 9 NOVEMBER 1901 hydraulic, controls and instrumentation, structural, civil, metallurgy, and materials engineering; chemistry; maintenance support; helath physics; fueling and refueling operations; technical and engineering management; operations management; fire protection; licensing; and quality assurance.
The exact technical expertise within NSED will vary from time to time with the makeup of the Department personnel.
To the degree necessary, supplemental technical assistance will be available from consulting contracts, Sargent & Lundy, and General Electric.
With these arrangements, the specific requirements of NUREG-0731 (Paragraph II.B.2.C (2)) will be met.
Experience requirements for engineering positions in NSED vary with the position.
Entrance level engineering requirements, for example, simply require a college level engineering degree.
Additional requirements have been established both in terms of education and previous experience for the advanced engin-eering levels, supervision, and management.
These vary from three to four years of working experience plus an engineering degree for the first promotion level, Staff Engineer, to about ten years of experience plus an engineering degree for the Department Directors.
Most of the personnel currently filling these positions in the Department are considerably bette r qualified in both' education and work experience, than th; minimum requirements for the positions they are filling.
In addition, within NSED the Independent Safety Engineebing
. Group (ISEG) will be maintained to comply with the requi:e-Iments of Item I.B.l.2 of NUREG-0737.
Most NSED personnel will perform onsite technical support activities from time to time.
Some NSED engineers (such as members of ISEG) will be assigned full-time to the site.
Prior to performing site activities, or as appropriate during the initial phases of such work, training in administrative procedures, controls, and conduct of operation will be pro-vided by the plant training program to assure that such NSED personnel are familiar and adequately qualified to function safely and to perform effectively in their assignments.
Any member of the Nuclear Stat' ion Engineering Department who performs initial testing will be certified under startup procedures to the extent required.
This certification will include administrative controls training.
13.1.1.2 Organizational Arrangement The Illinois Power Company corporate structure relative to Clinton Power Station technical support for operation is as shown in Figure 13.1-1A.
The Illinois Power Company overall corporate organization structure is shown in Figure 13.1-1B.
1,3.1-4a
I CPS -FSAR AMENDMENT 9 NOVEMBER 1981 A Vice-President is responsible for providing support services through the Nuclear Station Engineering and Quality Assurance Departments.
He reports to an Executive Vice-President who in turn reports to the President of Illinois Power Company.
The Manager of Nuclear Station Engineering reports to the Vice-President and is directly responsible for CPS engineering services relative-to technical areas of nuclear, mechanical, structural, civil, electrical, thermal-hydraulic, metallurgy, materials, licensing, fuel, plant chemistry, health physics, instrumentation and controls, and maintenance.
Nuclear Station Engineering Departmental structure relative to CPS is as shown on Figure 13.1-2.
The Director - Quality Assurance reports to the Vice-President and is responsible for the IP quality assurance program, includ-ing both internal audits and audits of vendors or contractors.
13.1.1.3 Qualifications The qualifications of Headquarters. staff personnel responsible for Clinton Power Station technical support meet or exceed tho'se requirements set by ANSI /ANS 3.1, 1978.
Resumes of Head-quarters supervisory personnel'are included in Appendix 13A.
13.1.2 Operating organization The Operating organization section describes the structure, func.tions and responsibilities of the on site organization established to operate and maintain the Clinton Power Station.
13.1.2.1 Plant Organizaticn i
t The Clinton Pcwer Station organization is as shown in Figure 13.1-3.
The crganization chart indicates the title of each position, the number of personnel assigned to each position (including cormon or duplicate positions), the reporting responsibilities, and the positions for which a Reactor Operator 4
or Senior Reac tor Operator license is required.
CPS operating organization positions which are vacant as of October 1991 i
are expected to be filled according to the schedule found on Table 13.1-2.
CPS staffing will be increased as necessary for Unit 2 when such a need exists and will be based upon the experience gained through the operation of Unit 1.
j 13.1.2.2 Plar.t Personnel Responsibilities and Authorities The functions, responsibilities, and authorities of various CPS staff positions are as follows:
i 13.1-5
__________._.__________.__.__.________.______...________..____._._____.__.___._.__.___,___.______m
.m.
_. =
s.
e CPS-FSAR AMENDMENT 9 J
NOVEMBER 1981 POWER PLANT MANAGER The CPS Power Plant Manager is responsible for overall facility.
operation including industrial relations, planning, coordina-tion, and direction of the operation, maintenance, refueling, radchem, and technical activities.
The Power Plant Manager is responsible for compliance with the station's operating license, regulations, ASME code requirements, and the CPS Operational Quality Assurance Program.
He is also responsible for-final approval and distribution of station reports.
The Power Plant Manager is chairman of the Facility Review Group as outlined in Section 6.5 of the Technical Specifications and is the chairman of the ALARA committee.
The Power Plant Manager reports to the Vice-President.
Interfaces between the CPS Staff,and offsite organizations are coordinated thro _ ugh the Power Plant Manager.
He also delegates authority in specific areas during normal day-to-day conduct of operations.
ASSISTANCE POWER PLANT MANAGERS 1
1 Responsibility for day-to-day operating activities, including Maintenance, Radchem, and Operations matters is assigned to the. Assistant Power Plant Managers.
They are members of the Facility Review Group and the ALARA committee.
SUPERVISOR - TECHNICAL '
"~
The Supervisor - Technical directs a staff which provides technLeal support for operations, refueling, maintent.nce and modificacion.t.
He is responsible for evaluating equipment performance data, in-cluding nuclear core performance, and preparing reports and maki.ng recommendations in these areas.
The Supervisor - Technical coordinates the station planning, forecasting, and scheduling of reactor core nuclear activities.
He is a member of the Facilitf Review Group.
SUPERVISOR - RADCHEM The Supervisor - Radchem is responsible for providing, scheduling, and coordinating radiological control services as required to sup-port station operation and maintenance activities.
He directs the implementation of the program to control the acquisition, shipping and receiving of all by-product, source, and special nuclear material except fuel.
The Supervisor - Radchem is responsible for the operational chemistry program of the station and the operation of radwaste handling facilities.
He is a member of the Facility Review Group and the ALARA Committee.
SUPERVISOR - MECHANICAL The Supervisor - Mechanical is responsible for directing the maintenance, including repair, of all mechanical equipment
.in the station.
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13.1-6
f CPS-FSAR AMENDMENT 9 NOVEMBER 1981 b.
The re'sponsibility to determine th'e circumstance, cause,'~'~'
and limits under which operations can safely proceed before the reactor is returned to power following a trip or an unscheduled or unexplained power reduction.
J1'he Senior Reactor Operator's responsibility to be present
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c.
at the plant and to provide direction for returning the
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recctor to power following a trip or an unscheduled or unexplained power reduction.
d.
The responsibility to believe and respond conservatively to instrument indications unless they are proven tv be incor-rect.
The responsibility to adhere to the plant Technical Speci-e.
fications.
f.
The responsibility to review routine operating data to assure safe operation.
g.
The responsibility to meet the requirements of 13 CFR 50.54 (i), (k), (k), (1 ), (m) pertaining to RO a.3d SRO licensed operators.
h.
The responsibility to adhere to plant operating procedures and the requirements for their use.
In the event of an emergency not covered by an approved procedure, opera-tions personnel should take action to minimize personne]
injury and damage to the facility and to protect health and safety.
Individual shift crew position responsibilities are as follows:
SHIFT SUPERVISOR The Shift Supervisor on duty is responsible for operating the plant in compliance with license requirements and operating procedures.
He is in charge of the entire plant operation and ensures that the plant is being operated in a safe and reliable manner.
The authority to issue or cancel standing orders is reserved for the department heads.
Station procedures and organization jointly serve to relieve the shift supervisor of administrative burdens in order that he may concentrate on his primary management responsibility for safe operation of the plant.
A corporate management dir-ective will be prepared emphasizing management responsibility of the Shift Supervisor.
ASSISTANT SHIFT SUPERVISOR The Assistant Shift Supervisor assists the shift Supervisor in directing the operation of the plant.
.is assigned by the Shift Supervisor, the Assistant Shift Superviuor is responsible for 13.1-8
CPS-FSAR AMENDMENT 3
['
NOVEMBER 1981 ensuring that the plant is being operated in a' safe and reliable manner in compliance with license requirements and cperating procedures.
CONTROL ROOM SUPERVISOR The Control Room Supervisor is the first line supervision for the non-exempt operating personnel on shift.
The Control Room Supervisor directs opercting activities from the main control
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CPS-FSAR AMENDMENT 9 WOVEMBER 1981 a
in accordance with approved procedures and station technical specifications.
The Control Room Supervisor is authorized to take actions that he deems necessary for safe operation of the plant.
CONTROL ROOM OPERATOR The Control Room Operator is the senior non-exempt operating posi-tion on each shift.
The control Room Operator directs the acti-vities of the unlicensed operators (Unit Attendant and Auxiliary Operator)'to assure proper operation and monitoring of plant systems and equipment.
UNIT ATTENDANT AND AUXILIARY OPERATOR The Unit Attendant and the Auxiliary Operator perform routine inspections and operations on equipment outside of the main control Operations and inspections are performed at the direction room.
of the Control Room Operator, Shift Supervisor, Assistant Shift Supervisor or Control Room Supervisor.
SHIFT TECHNICAL ADVISOR The Shift Technical Advisor will serve the function of the advisor to the Shift Supervisor on matters of safety, and, if qualified, act as an on-shift nuclear engineer.
As an advisor to the Shift Supervisor, the Shift Technical Advisor will have no authority to direct the activities of the shift.
As an interim position, IPC will require that the Shift Technical Advisor be a graduate of a four-year college curriculum in science or engineering who has received training in the response and analysis of the plant for transients and accidents.
The size of the Technical Department was increased to accommodate this position.
Four-year college graduates are being hired to fill this position.
Over the long term, IPC intends to eliminate the Shift Technical Advisor position by upgrading shift supervisory qualifications.
However, the interim arrangement will remain in effect until the Shift Supervisors are qualified to replace the Shift Tech-nical Advisor.
SUCCESSION OF AUTHORITY The Power Plant Manager has overall responsibility for facility operations.
During periods when the Power Plant Manager is unavailable, the Power Plant Manager will state the line of succecuion of 2.uthority and responsibility.
This statement will be in writing and the line of succession will extend from the Power Plant Manager to on-shift personnel.
The requirement to make this s'_atement is contained in CPS procedures.
13.1-9
[
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 1
ADMINISTRATIVE DUTIES Administrative functions are structured such that details are 4
performed by other personnel or other departments while shif t.
supervision maintains a review / approval role for those activities important to safe operation of the plant.
Maintenance work and tagouts are preplanned by the maintenance department even to the point of requesting tagging boundaries.
An operator would review the tagout request, prepare the tags, and submit the tagout to the Shift / Assistant Supervisor for ultimate approval.
Maintenance Work Requests are similarly prepared and reviewed by maintenance supervision with ultimate approval to commence work being retained by the Shift / Assistant Shift Supervisor.
Radiation Work Permits are completed and reviewed by Radchem supervision and ultimately approved by the Shift / Assistant Shift Supervisor.
Clerical functions such as time-keeping and maintenance of procedure manuals will be performed by clerical personnel, on the day shift.
l The organization structure assists the Shift Supervisor in con-centrating on safe operation of the plant in numerous ways.
The Radchem department has supervision on shift responsible for radiation protection, radwas.te, and chemistry activities.
The radiation monitoring system is continuously monitored by radiation protection personnel, who would respond in the event of an anomaly.
The Shift Supervisor can maintain an overview of radiation protection activities.
Supervision in each main-tenance discipline is responsible for administrative aspects of the maintenance activities in progress.
An Assistant Opera-tions Superviscr and extra Shift / Assistant Shift Supervisors provide a mean~r for relieving the Shift Supervisor of burdens such as LER investigation, special activities planning, and special surveillance support.
Finally, the addition of an l
Assistant Shift Supervisor and a Control Room Supervisor pro-l vides additional supervision, with senior licenses, to aid the Shift Supervisor in handling administrative functions that must be retained on shift.
The ability of the Shift Supervisor i
to delegate certain duties will allow him to concentrate on management of the plant.
13.1.2.3 Operating Shift Crews There will be five operating shift crews.
Each operating shift crew is qualified to carry out activities related to station operations.
Position titles, license requirements and their equivalent positions listed in ANSI /ANS 3.1 1978 are as follows:
CPS Position or Title License ANSI /ANS 3.1 1978 Equivalent Shift Supervisor SRO Supervisor requiring NRC.
license Assistant Shift Supervisor SRO Supervisor requiring NRC license l
13.1-9a
4 Crd-FSAR AMENDMENT 9 j-NOVEMBER 1981 CPS Position or Title License ANSI /ANS 3.1 1978 Equivalent l
l Control Room Supervisor SRO Supervisor requiring NRC license Control Room Operator RO Operator Unit Attendant i
Auxiliary Operator I
The CPS operating shift crew will consist of the personnel as follows for Unit 1 t
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13.1-9b i
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 1
Operations, Startup, Hot Cold Shutdown, Job Title Shutdown Refueling Shift Supervisor 2 of 3 1 of 3 Assistant Shift Supervisor 2 of 3 1 of 3 2
Control Room Supervisor 2
1 Control Room Operator 2
l Unit Attendant 1
1 of 2 Auxiliary Operator 1
1 of 2 1
Radwaste Operator 1
1 Radiation Protection Personnel 1
1 Each shift crew shall include a Shift Supervisor or a person qualified and designated to act as a Shif t Super 7isor.
- Further, each shift crew shall include an individual quali:ied by educu-tion and experience to act as a Shift Technical Advisor.
Tnia j
individual may be a member of the operating shift supervision present.
CPS manning will be increased as necessary for Unit 2 when the need exists and will be based upon the experience gained through the operation of Uni _t 1.
l During refueling operations, a separate Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling will supervise these operations and will have no other concurrent duties.
i An around-the-clock radiation protection program will be imple-mented by the presence of at least one individual qualified in radiatic:: protection.
Additional personnel will be scheduled as j
required to cover special jobs or work loads as determine by" radiation protection supervision.
During normal work days, the Radchem Technicians report to radiation protection supervision.
i During off shifts and weekends, the radiation protection personnel will report to radiation protection supervision or the Shift I
Supervisor.
Shift crew composition may be less than the minimum requirenents-for a period of time not to exceed two hours in order to accommo-i date an unexpected absence of on duty shift crew members provided immediate acticn is taken to restore composition to within the minimum requirements as stated.
Clinton Power Station will have on shift one experienced indiv-idual from fuel load to 100% power operation or for one year, I
whichever occurs earlier.
This individual will have substantive l
commercial BWR-operating experience, including startups and l
shutdowns under conditions that might be expected during CPS initial startup and power escalation.
For short periods of time, up to two hours, as a result of illness or other unavoidable circumstances this individual may not be present.
13.1-10
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 Clinton Power Station currently has 38 persons in cold license training for 32 licensed positions on shift.
Five of these licensed positions represent an extra reactor operator-qualified individual assigned to nonlicensed duties on a rotating basis.
This results in an actual conmitment to 27 licensed positions i
on shift.
Illinois Power Company will begin hiring 10 Unit Attendants immediately.
As has been the practice in the past, these indi-viduals will be hired from the Nuclear Navy such that they could be licensed by January 1983, if necessary.
The license training program for these individuals will commence in February 1982 to support this goal.
The training pipeline will ultimately be filled by Richland Community College graduates preferably in the Power Generation-Nuclear curriculum or equivalent.
Acceptable graduates will be hired into entry level positions in 1982 and following years.
Commencing in the summer of 1982, Illinois Power Company will provide 15 scholarships for local high school graduates whereby the recipients will attend Richland Community College in the Power Generation-Nuclear program and will work during the vacation periods
- at Clinton Power Station.
This scholarship / work experience program should assure a continuing inflow of qualified personnel.
Total attrition in the Operations Department has been 33% for a 5 year period of time and has been lower this year than ever before.
Attrition for the 12 months ending October 31, 1981 was 53.
Except for major events such as TMI-2 and announced schedule delays, attrition of operators has been very low.
Even if 50% of the license candidates initially fail the examination and one-half of them subsequently pass, this would provide 36 people for 27 licensed positions.
Attrition of 25%
could then be acceptable over the next 15 months; it took over three years to reach this value of attrition previously.
Con-sequently, it is believed that there will be ample allowance for attrition and examination failure and that there will be adequate licensed personnel to staff five shifts at the desired
' staffing level.
13.1.3 Qualification of Nuclear Planc Personnel Qualifications for Clinton Power Station personnel are'describec'.
in the following subsections.
i 13.1.3.1 Qualification Requirements Clinton Power Station follows the guidelines set forth in Regu-latory Guide 1.8 for selection and training of management per-sonnel with the exceptions noted in.Section 1.8.
Table 13,1-1 4
lists members of the plant staff and designates equivalent ANSI /ANS 3.1 1978 titles as a comparison.
i 13.1-10a
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 13.1.3.2 Qualifications of Plant Personnel The qualifications of the initial personnel on the CPS staff holding key managerial and supervisory positions are provided in the resumes included with this rhapter as Appendix 13A.
13.1.3.3 Startup Staff Experience l
The education, training, and commensurate experience for persons who conduct or supervise pre-operational and startup testing 4
are summarized on Table 13.1-3.
Commensurate experience is considered the knowledge and skills acquired through past experience corresponding in the same relative proportions to the knowledge and skill requirements of the tasks to be assigned to that test engineer.
In ot her words, a person who had two years experience doing only electrical testing activities would not be assigned tashs of a mechanicsl or fluid nature.
How-ever, an engineer with two years experience testing a variety of pumps and fluid systems would have gathered sufficient knowledge and skills to be assigned to an HVAC system startup.
HVAC balancing would require a'dditional experience.
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13.1-10b
s CPS-FSAR AMENDMENT 9 NOVEMBER 1981 TABLE 13.1-2 STAFFING PLAN (as of October 1981)
OPERATIONS 10 Unit Attendants All 4th Quarter 1981 MECHANICAL MAINTENANCE 7
Repairmen 3 - 4th Quarter 1981 3 - 1st Quarter 1982 3
Welders 1 - 4th Quarter 1961 2 - 3rd Quarter 1982 2
Machinists 2 - 2nd Quarter 1982 1
Asst. Mech.
2nd Quarter 1982 Supervisor TEC!iNICAL 3
Engineers 3 - 4th Quarter 1981 3
Specialists 3 - 2nd Quarter 1982 i
STOREROOM f
i 1
Storehouseman 4th Quarter 1981 RADIOLOGICAI l
11 RP Techs 2 - 4th Quarter 1981 9 - 1st Quarter 1982 I
l 4
Rad Protection 2 - 1st Quarter 1982 Shif* Supervisors 2 - 2nd Quarter 1982 CHEMISTRY 3
CH Techs 1 - 4th Quarter 1981 l
2 - 1st Quarter 1982 l
l RADWASTE 3
Radweste Operators 1 - 4th Quarter 1981 2 - 1st Quarter 1982 13.1-12 I
8 P
r-CPS-FSAR AMENDMENT 9 NOVEMBER 1981 TABLE 13.1-2 (Cont'd)
CONTROL & INSTRUMENTATION MAINTENANCE 5
C& I Techs 4th Quarter 1981 PLANT SERVICES 5
Security Shift 1st Quarter 1982 Supervisor 1
Utility 3rd Quarter 1982 Supervisor 8
Utility Men 1 - 4th Quarter 1981 1 - 2nd Quarter 1982 6 - 4th Quarter 1982 i
2 Janitors 1 - 1st Quarter 1982 1 - 2nd Quarter 1982 1
S,1pervisor When a qualified Plant Services individual is available TRAINING 1
Assistant 1 - 4th Quarter 1981 Shift Supervisor-Training ELECTRICAL 2
Electricians 4th Quarter 1981 1
Assistant 4th Quarter 1981 Elec tr ical Supervisor l
l 13.1-13
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1 CPS-FSAR AMENDMENT 9 g
i NOVEMBER 1981 i
I TABLE 13.1-3 l
l STARTUP STAFF C"RTf PICATION LEVELS j
1 LEVEL I (REQUIRED FOR FLUSHING, HYDRO'S, CALIBRATIONS, ETC.)
High school graduate plus one year of commensurate experience in construction and/or preoperational testing experience.
LEVEL II (REQUIRED FOR CONDUCTING PREOPERATIONAL AND STARTUP TESTS)
Engineering or Science degree plus two years of commensurate experience.
One year of experience should be associated with nuclear facilities.
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OR High school diploma plus four years of commensurate experience.
One year of experience should be associated with nuclear facilities.
4 LEVEL III (REQUIRED FOR APPROVAL OF PREOPERATIONAL AND STARTUP TEST PROCEDURES AND RESULTS)
Engineering or Science degree plus five years of commensurate experience.
Two years of experience should be associated with nuclear facilities.
OR Hign school diploma plus ten years of commensurate experience.
Five years of this experience should i
be associated with nuclear facilities.
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13.1-14
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 G.
License Review i
Prospective lic ndidates will receive a four to eight week refresher arior to the NRC exam.
This course will review CPS syst 6 :or theory, radiation protection, and applicable CPS p ures.
The course is conducted by the CPS Training Group.
~icense applicants who completed simulator moi.' than twelve um....3 prior to fuel load shall also complete a simulator refresher course.
H.
Shift Technical Adv'.sor Training Over the long term, IPC intends to upgrade the qualifications of shift supervisory personnel, so that the STA position eventually can be eliminated.
To this end, IPC has commenced the program listed in Table 13.2-3 for certain shift super-visory personnel.
This program utilizes courses from the University of Illinois and Richland Community College.
During the interim period, until the STA position can be eliminated IPC will require that the STA be a graduate of a 4-year college curriculum in science or engineering.
The Clinton Power Station shift technical advisor (STA) training program will fulfill the training and educational guidelines as delineated in the INPO document "Recommenda-tions for Shift Technical Advisor," April 1981, with exceptions as previously documented in Appendix D, Item 1.A.l.1 of the CPS-FSAR.
In addition to the educational requirements, training will be received in the following areas:
a.
Applied fundamentals - plant specific, j
l b.
Management / supervisory skills, 1
l c.
Plant systems, d.
Administrative controls, I
e.
General operating procedures, f.
Transient / accident analysis and emergency procedures, and g.
Simulator e::ercises.
The plant-specific applied fundamentals training for STA's will be fulfilled by participation in the license review course and the licensed operator requalification training program.
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l 13.2-2a
_, _ _. - ~.. _ _, _. _.. _ _
CPS-FSAR AMEMDMENT 9 NOVEMBER 1981 All STA's will attend Illinois Power Company's supervisory development program.
This one week program is structured to enhance management / leadership skills and to provide in-sight into techniques of motivation and the decision making process.
All STA's will actively participate in the license review course and the licensed operator requalification program.
This will ensure that the STA's receive the required training and achieve proficient knowledge levels in the areas of plant systems, administrative controls, general operating procedures, and transient / accident analysis and emergency procedures.
As an integral part of the CPS training program, licensed operators shall participate in annual retraining at a simulator facility.
The STA's will also attend this annual simulator requalification training.
The initial STA training simulator shall be of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> duration (50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> classroom, 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> at the panel) with emphasis placed on plant / operator response to simulated plant conditions and events.
Performance of routine plant _ activities will ensure a pro-ficient knowledge level of plant status and conditions.
For those STA's not performing these activities for thirty days or longer, the following documents shall be reviewed prior to the resumption of STA duties.
a.
Plant modifications that affect the features of the facility design or its operating character-istics for which the licensee is responsible, b.
Changes to and newly issued safety-related procedures, c.
Changes to facility license, and d.
Reportable occurrences where the corrective action specifies that each licensee shall review the report.
I.
Core Damage Mitigation Training Clinton Power Station will develop a program to ensure that operations personnel will receive a minimum of eighty (80) contact hours of " Mitigating Reactor Core Damage" training.
Courses now exist in the areas of fundamentals, NSSS/ BOP systems, operator training (simulator), and research reactor training that cover forty -(40) hours of material pertaining to " Mitigating Ecactor Core Damage."
The remaining forty (4 0) hours is in the process of beinc contracted out to a vendor for a supplemental course in " Mitigating Reactor Core Damage."
13.2-2b
i
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o CPS-FSAR AMENDMENT 9 l
NOVEMBER 1981 4
)
Attached is an outline of the " Mitigating Reactor Core Damage" training to be taught to the operations, technical 1
and training staffs and to selected members of the nainten-ance and radiation / chemistry departments.
The training will consist of=a minimum of forty (4 0) hours of instruction in the areas covered in the outline.
The outline is based on guidance from Harold Denton's March 28,,1980 letter on i
" Qualifications of Reactor Operators", and is amended to include training on the use of emergency procedure guide-
~
lines and execution of the emergency plan.
Nonlicensed technicians will particpate in this course as followc:
I l,
and C technicians - vita 1 instrumentation; Chemistry techni-cians - primary chemistry; and Radiation Protection techni-cians - radiation monitoring.
- ~~ ~~
m s,
Outline for Mitigating Reactor Core Damage Training 1.
Incore Instrumentation i
a.
Use of fixed or movable incore detectors to determine extent of core damage and geometry changes.
a b.
Methods for calling up incore data from the plant computer.
2.
Vital Instrumentation a.
Instrumentation response in an accident environment, failure sequence, and indication reliability.
I I
b.
Alternative methods for measuring flows, pressures, levels, and temperatures.
1 3.
Primary Chemistry a.
Expected chemistry results with severe core damage; consequences of transferring small quantities of liquid outside containment; importance.cf using leak tight systems.
b.
Expected isotopic breakdown for core damage; for clad damage.
1 L
c.
Corrosion effects of extended immersion in primary water; time to failure.
4.
Radiation Monitoring Response of Process and Area Monitors to severe damages; a.
l behavior of detectors when saturated; method of detecting l
radiation readings by direct measurement at detector 7utput; expected accuracy of detectors at different
.ocations; use of detectors to determine extent of core damage.
13.2-2c
~. _ - -
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 b.
Methods of determining dose rate inside containment from measurements taken outside containment.
t I
5.
Gas Generation a.
Methods of H2 generation during an accident; other sources of gas (Xe, Kr); techniques for, venting or disposal of non-condensibles.
b.
H2 flammability and explcsive limit; and sources of 02 i
in containment or reactor coolant system.
j 6.
Procedures and Guidelines a.
Effective use of the 3mergency Guideline Procedures.
b.
Makeup and effective use of the Emergency Plan.
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13.2-2d E
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 J.
Specialist Training Personnel in the fields of radiation protection and radio-chemistry, radwaste, nuclear physics, electrical maintenance, mechanical maintenance, and instrument maintenance receive training from manufacturers, vendors, and/or departmentally designed programr,.
Such courses vary in length from one day to six months.
K.
Fire Brigade Training Fire Brigade Training is conducted by the CPS Training Depart-
-ment or a vendor for fire brigade members and members of the fire protection staff.
The training will vary in length from two to five days.
It will consist of the following subj ects :
1.
Identification of the fire hazards and associated types of fires that could occur in the plant, and an identifi-cation of the location of such hazards.
2.
Identification of the location of fire fighting equip-ment for each fire area, and familiarization with lay-out of the plant, including access and egress routes to each area.
3.
The proper ~use of svailable fire fighting equipment, and the correct methed of fighting each type of fire.
The types of fires covered shall include electrical fires, fires in cables and cable trays, hydrogen fires, flammable liquid, waste / debris fires, and record file fires.
4.
Indoctrination of the plant fire fighting plan with specific coverage of each individual's responsibilities.
5.
The proper use of communication, lighting, ventilation and emergency breathing equipment.
6.
The direction and coordination of the fire fighting activities (fire brigade leaders only).
7.
The toxic characteristics of expected products of combustion.
8.
The proper method for fighting fires inside buildings and tunnels.
9.
Detailed review of fire fighting procedures and procedure changes.
10.
Review of latest plant modifications and changes in firc fighting plans.
s 13.2-3
CPS-FSAR AMEEDMENT 9' NOVEMBER 1981 L.
General Employee Training General Employee Training is administered by the CPS Training Department to all personnel regularly and temp-orarily employed at CPS.
It is a one or two day course and consists of the following subjects:'
l.
Introduction to CPS 2.
Security plan 4.
Fire protection 5.
Radiation protection and respirator training 6.
Industrial safety 7.
Quality Assurance program A written or oral examination may be administered following 4
{
the lectures.
Temporary personnel will participate in this training to a level commensurate with their responsibilities.
In addition to the fire protection portion of General Employee Training, personnel responsible for inspection of fire protection equipment will receive additional instruction on design, inspection, and maintenance of fire suppression and extinguishing systems.
4 13.2.1.1.2 Reactor Operator Experience Reactor Operator Experience consists of the BWR Operator Training (Subsection 1.3. 2.1.1.1 D) and Observation Training (Subsection 13.2.1.1.1 E).
Individuals seeking a license who have not been previously licensed, or had experience in operating a reactor, receive this training.
13.2.1.1.3 On-Site Training Program The on-site training during the preoperational period consists of on-the-job training (0JT) for all station personnel while conduct-ing preoperational and startup testing.
This OJT is usually of an informal nature and conducted as the need arises.
OJT conducted in a formal manner will be documented in the same manner as class-room training.
Selected non-licensed individuals will also receive portions of the classes described in Subsection 13.2.1.1.
Table 13.2-1 outlines the courses provided to the various functional positions on the staff.
13.2.1.1.4 Differences in Training Program Due to Previous Excerience Personnel with previous nuclear power plant training or experience will be evaluated on a case-by-case basis and provided training in accordance with ANSI-3.1-1978, " Selection and Training of Nuclear Power Plant Personnel."
The CPS Operator License Training Program is designed to satisfy the training requirements of an individual with no previous training or experience.
Table 13.2-2 outlines the degree to which an individual with previous training or experience i
will participate in the program.
13.2-4
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 13.2.2.3.2 Specialist Replacement Training Specialist Replacement Training will be conducted in the same manner as specialty training desc ibed in Subsection 13.2.1.1.1.J.
13.2.2.3.3 Operator License Replacement Training License Replacement Training will be from twelve to twenty-four weeks duration depending on the education and experience of the student.
As a minimum it will include the following areas:
A.
~ Reactor fundamentals (or equivalent)
B.
BWR technology (or equi /alent)
C.
Balance of plant systems D.
BWR operator training (or equivalent) 13.2.2.3.4 SRO License Training SRO License Training will normally be six weeks in duration.
It
~
consists of an intensive review of the following subjects:
A.
CPS systems B.
Technical specifications C.
Procedures
~
D.
FSAR 13.2.3 Applicable NRC Documents Below is a list of documents that provided guidance in the prepara-tion and administration of the Clinton Power Station Training Pre-gram.
The only exceptions taken to the guidance provided in these documents are described in Section 1.8, Conformance to NRC Regule-tory Guides.
A.
10 CFR Part 50, " Licensing of Production and Utilization Facilities" B.
10 CFR ? art 55, " Operators' Licenses" l
C.
10 CFR Part 19, " Notices, Instructions and Reports to Workers; Inspections" D.
Regulatory Guide 1.8, " Personnel Selection and Training" E.
Regulatory Guide 8.2, " Guide for Administrative Practices I
in Rt'tation Monitoring" i
Regulatory Guide 8.8, "Information Relevant to Maintaining F.
Occupational Radiation Exposure as Low as is Reasonably Achievable (Nuclear Power Reactors)"
l G.
Regulatory Guide 8.10, " Operating Philosophy for Maintain-ing Occupational Radiation Exposures as Low as is Reason-ably Achievable" 13.2-12
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 basis; however, no more than two alternates shall parti-cipate as voting members in NRAG activities at any one.
time.
The NRAG shall be composed of individuals who are gen-erally experienced and competent in the areas of nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, controls and instrumen-tation, electrical engineering, quality assurance, nondestructive testing, radiological safety, mechanical engineering, and administrative controls.
In addition to the general engineering underst anding in the areas noted above, additional specialized expertise will be used by the NRAG director to provis.c expert advice on an as-needed basis through the use of consultants.
Nondestructive testing, radiochemistry, and metallurg;r are typically specialized fields where additional expertise may be required.
Merhership of the NRAG is identified by position tik.le n the station technical specification (Chapter 16).
The enticipated membership is as follows:
.NRAG Compositlog Director:
Vice President Manager Nuclear Stat'ori.Ungineering Clinton Power Statio: power Plant Manager Director - Design Er.yincering Director - Nuclear Sa'" y & Engrg. Analysis Supervisor - Technology Assessment Supervisor - Compliance (NSED)
Consultants may be utilized as determined by th'e NRAG Directer to provide expert advice to the NEAG.
c.
Meeting Frequency and Quorum I
The NRAG shall meet as required, but no less frequently l
than once per calendar quarter during the initial year l
of facility operation following fuel loading and at leart l
once per six calendar months thereafter.
Formal meetings shall consist of the Director or his alternate and at i
least four members, including alternates, of which no I
more than a minority of the quorum shall have line responsibility for operation of the plant.
j d.
Responsibility The NRAG shall be responsible for reviewing the following:
1.
Safety evaluations for:
i a)
Changes to safety-related procedures, equipment, or systems, and 13.4-3 L.
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 b)
Tests.or experiments completed under the pro-vision of 10 CFR 50, Section 50.59, to verify that such actions did not constitute an unre-viewed safety question.
2.
Proposed changes to safety-related procedures,
, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50, Section 50.59.
f l
13.4-3a
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 3.
Proposed tests or experiments which involve an unre-viewed safety question as defined in 10 CFR 50, Section 50.59, 4.
Proposed changes in Technical Specifications or license amendments relating to Nuclear Safety.
5.
Violations of applicable statues, codes, regulations, orders, Technical Specifications, license requirements, or of intcrnal procedures or instructions having nuclear safety significance.
~
6.
Significant operating abnormalities or deviations from normal and expected performance of plant. equipment that affect nuclear safety.
7.
REPORTABLE OCCURRENCES requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
8.
All recognized indications of an unanticipated defi-ciency in some aspect of design or operation of safety related structures, systems, or components.
9.
Reports and meeting minutes of the FRG.
e.
Records NRAG meeting minutes and written records of reviews shall be prepared and all documentary material reviewed shall be identified.
Copies of meeting minutes and documentation of reviews shall be promptly disseminated to appropriate management and the NRAG.
Illinois Power Company will establish an onsite Independent Safety Engineering Group (ISEG) to perform independent reviews of plant operations.
The principal function of the ISEG will be to examine plant l
operating characteristics, NRC issuances, Licensing Information Service advisories, and other appropriate sources of plant l
design and coerating experience information that may indicate areas for improving plant safety.
The ISEG will perform inde-pendent review of plant activites including maintenance, modifi-cations, operational problems, and operational analysis.
Where l
useful improvements can be achieved, this group will develop and present detailed recommendations to corporate management' for such things as revised procedures or equipment modifications, i
Another function of the ISEG will be to maintain surveillance of plant operations and maintenance activities to provide inde-pendent verification that these^ activities are performed cor-l rectly and that human errors are reduced as far as practicable.
l ISEG will then be in a position to advise utility management 13.4-4
CPS-FSAR AMENDMENT C NOVEMBER 1951 on the overall quality and safety of operations.
ISEG will not perform detailed audits of plant operations and shall not be responsible for sign-off functions such that it becomes involved in the operating organization.
The ISEG will not replace the Facility Review Group, which is responsible for onsite reviews at the plant operating level, or the Nuclear Review and Audit Group (:NRAG), which is indepen-dent of direct responsibility for plant operations.
The leader of the ISEG will, however, serve as a member of the NRAG.
The ISEG function will be carried out by the Technical Assessment Section of the Nuclear Station Engineering Department.
As illustrated in Figures 13.1-1 and 13.1-2, the Technical Assess-ment Section is independent from the Clinton Power Station organization and the Quality Assurance organization.
The Super-visor of Technical Assessment will report to the Director -
Nuclear Safety and Engineering Analysis.
.The Supervisor of Technical' Assessment will prepare written monthly reports and
~
submit them to the Director.- Nuclear Safety and Engineering Analysis, the Manager of the Nuclear Station Engineering Department, and the members of NRAG.
The Technical Assessment Section will have its supervisor and s
minimum of four personnel on site.
All staff members of this group will be at a level gen'erally comparable to that described in Section 4.7 of ANSI /ANS 3.1-1978 (i.e., a bachelor's degree in engineering or one of the physical sciences and three years of professional Ic. vel experience in'the field of their specialty).
The members of the group will be of varied backgrounds and disciplines related to nuclear power plants.
Disciplines not represented on the ISEG will be made available to the group as needed from other sources such as the Nuclear Station Engineer-ing Department or consultants.
By maintaining a group with diverse educational backgrounds and experience, the ISEC will increase the available technical expertise located on site and
~
will provide continuing, systematic, and independent assessment of plant activities.
l The ISEG may interface with the Quality Assurance (QA) organiza-tion, but will not be an integra1 part of the QA organization.
The functions of the ISEG require daily contact with the operat-ing personnel and continued access to plant facilities and records.
The ISEG review functions will, therefore, be carried out by a group physically located onsite.
The ISEG will be onsite and prepared to perform its functions prior to fuel loading.
i 13.4-4a
=
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 t
l.
13.4.3 Audit Program A comprehensive program of planned and documented audits shall be established and implemented by the Quality Assurance organi-zation, under the direction of the Director - Quality Assurance, to verify conformance with quality assurance requirements.
The i
audit program is fully described in Section 17.2.
Results of audits pertaining to plant operations shall be disseminated to l
appropriate management, the Facility Review Group and the Nuclear Reitiew and Audit Group for review and assessment.
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l CPS-FSAR AMENDMENT 9 NOVEMBER 1981 13.5.1.2 Preparation of Procedures Procedures needed for fuel loading will be written by the plant staff prior to fuel loading.
Procedures required for plant operations under normal and emergency conditions will be written by the plant staff, to the extent practical, for use during the initial plant testing phase to allow for correction prior to fuel loading and for use in the plant operator training program.
The responsibility for writing and preparing plant procedures is assigned to the appropriate members of the plant staff as indicated in Tabic 13.5-1.
Safety-related procedures and changes thereto are reviewed by the FRGandapprovedbythePowerPlantManagerpriartoimplementation.l They are reviewed periodically as set forth in Administrative Procedures.
Temporary changes to procedures which clearly do not change the intent of the approved procedure shall, as a minimum, be approved by two members of the plant staff knowledgeable in the areas affected by the procedure.
At least one of these individuals shall hold a senior operator's license on.the unit affected.
Sec-tion 13.4 defines types of procedures requiring FRG review.
Appropriate plant management will approve all permanent and tempor-ary procedures in accordance wi.th Administrative Procedure require-ments.
Distribution of the CPS Operating Manual _and portions there-of will be controlled as prescribed in appropriate Administrative Procedures.
Subsequent revisions, changes, or temporary changes will be controlled in accordance with the Administrative Procedures and as prescribed by the Technical Specifications.
Changes which conflict with the intent of the Operating License and/or the Technical Specifications will be made only with the approval of the FRG and authorization from the NRAG and the Nuclear Regulatory Commission.
13.5.1.3 Procedures Administrative Procedures which consist of Plant Management Proce-dures (PMP's), Department Administrative Procedurcs, and Plant Management Special Procedures define the responsibilities, method-ology, and procedural actions required to assure that the plant will be managed in a safe and dependable manner.
They include basic guidelines and controls for efficient dissemination of information and direction to plant personnel and describe the interfaces with external organizations.
Plant procedures describe the method by which operating experience information is disseminated to plant personnel.
Documents are typically received by the Administrative Supervisor and forwarded to an Assistant Plant Manager.
The Assistant Plant Manager saall determine the applicability of the information and forward it to the Operations, RadChem, Maintenance, Technical or Plant Services Departments.
The training Group is part of Plant Services Department.
Each department will then assure that appropriate people review the documents.
13.5-2
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 Department Heads are responsible for assuring that applicable operating experiences are incorporated in other plant documents, such as procedures, standing ordere, training materials and design modification packages.
By the time of fuel load, the existing program will be revised to agroe with NUREG 0737.
The Plant Management Procedures' describe station functions required to implement the Operational Quality Assurance Program and other plant activities, assign departmen*al responsibilities for performing these functions, and delineate activities and methods which are applicable to all personnel assigned' work at CPS.
Departm.2ntal Administrative Procedures describe the functions required to implement the Plant Management Procedures and assign group responsibilities.
The departmental Admini-strative Procedures are issued and include the following:
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l 13.5-2a
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 A typical listing of these procedures is provided in Table 13.5-3.
The various classifications of precedures are as follows:
Integrated Plant Operating Procedures Turbine Cycle Systems Auxiliary Cycle Systems NSSS Systems HVAC Systems Electrical Systems Fuel Handling Systems Radiological Systems The format for Plant and System Operating Procedures is provided in Table 13.5-2.
Procedures will require crane operators who operate cranes over fuel pools be qualified and conduct themselves in accordance with ANSI B30.2-1976.
Clinton Power Station is equipped with status monitoring that satisfies the requirements of Regulatory Guide 1.47.
This status monitoring provides the ability for the operator to identify most conditions that would render a safety system inoperable.
The system enables'the operator to verify that the correct system is undergoing maintenance or test; when a i
system is placed out of service an alarm provides that verifi-cation.
Periodic monitoring of the system is assured through the shift relief and turnover checklist, although routine visual checks are expected.
Independent verification of valve and electrical lineups for isolation of components for maintenance, for restoration of components following maintenance, and for surveillance procedures will be performed.
This verification will normally consist of a second visual verification, remotely when possible, that the valve / breaker is in the correct position, but may consist of functional testing where conditions such as radiation Icvols dictate.
Post-maintenance testing, addition-ally, may preclude the need for another verification that a system / component has been correctly restored.
13.5.2.1.2 Off-Normal Procedures Off-Normal Procedures describe actions to be taken during other than routine operations, which if continued, could lead to either material failure, personnel harm, or unsafe conditions.
These procedures are written so that a trained operator will know in advance the expected course of events or indications tnat will identify an off-normal situation and immediate action which should be taken.
Since off-normal situations do not follow anticipated patterns, the procedares are so written to provide sufficient flexibility for accommodating variations.
Off-Normal Procedures are written in tha format outlined in Table 13.5-4.
Symptom-oriented procedures prepared in accor-dance with the BWR guidelines are contained within this category 13.5-4
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 of procedures.
A typical list of Off-Normal Procedures is provided in Table 13.5-5.
13.5.2.1..;
Emergency Off-Normal Procedures Emergency Off-Normal Procedures are identified as Off-Normal Procedures and are listed in Table 13.5-5.
The procedure format is describe 6 in Table 13.5-7.
13.5.2.1.4 Annunciator Procedures Annunciator Procedures are identified by an alphanumeric desig-nation which coincides with the alphanumeric designation of the annunciators.
The format for Annunciator Procedures is shown in Table 13.5-6.
13.5.2.1.5 Temporary Procedures Temporary Procedures will be used to provide guidance in unusual situations not within the scope of the CPS Operating Manual and to ensure orderly and uniform operations for short periods when the plant, a system, or a component of a system is performing in a manner such that portions of existing procedures do not apply.
Review and approval of Temporary Procedures is described in Technical Specifications, Section 6.8.
i a
7 1
l 13.5-4a
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 TABLE 13.5-5 "OFF-NORMAL" PROCEDURES SYSTEMS / PLANT FAILURES Reactor Coolant Leakage (Tech. Spec. Limit)
Loss of Control Air Reactor Scram Loss c; off-Site Power Loss of Reactor Coolant Flow Inadvertent opening Safety / Relief Valve Automatic Isolation FEEDWATER PROBLEMS Loss of -Feedwater Heating Loss of Feedwater Loss of RHR Shutdown Cooling CONTROL ROD PROBLEMS Inadvertant Rod Motion Rod Drop CHEM /RADCHEM PROBLEMS Reactor Coolant High Activity Plant Chemistry NATURAL DISASTER Earthquake Tornado RADIATION PROBLEMS High Airborne Activity High Airborne Activity in the Containment Bldg.
High Airborne Activity in Occupied Spaces High Airborne Activity in Accessibic Areas High Airborne Activity in the Drywell Sheet 1 of 2 13.5-14
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 TABLE 13.5-5 (Cont ' d)
RADIOACTIVE MATERIAL RELEASES Abnormal Releases of Radioactive Liquid Abnormal Release of Radioactive Solids Abnormal Releases of Radioactive Airborne HIGH RADIOACTIVE CONTAMINATION High Radioactive Surface Contamination EMERGENCY OFF-NORMALS Level Control - Emergency Containment Control - Emergency Cooldown - Emergency Reactivity Control - Emergency i
J Sheet 2 of 2
\\
13.5-15
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 4
TABLE 13.5-7 i
EMERGENCY OFF-NORMAL PROCEDURE FORMAT Procedure Title - The title should describe the "off-normal" situation for which the procedure is provided.
1.0 Symptoms - This section consists of the entry parameters and their associated setpoints.
If applicable, the appropriate procedure entry point should be specified, based on the entry conditions actually present.
2.0 Automatic Actions - This section describes the automatic actions that occur as a result of reaching the entry conditions.
~
3.0 Operator Actions - This section specifies the operator actions necessary to respond to the emergency condition.
The decision steps are formatted as follows:
(Step f)
IF (condition)
THEN (action) 4.0 Contingencies - This section incorporates specific actions to be taken when directed to do so from else-where in the procedure.
The same format as Section 3.0 is used.
5.0 Final Conditions - This section contains a general statement of the plant condition after completion of i
Section 3.0 6.0 Discussion - This section indicates all general cautions which are not necessarily applicable to specific steps or sections of the procedure.
It also provides a brief description of the intent of the procedure including, where necessary, important definitions of terms or
- phrases used.
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13.5-17 i
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CPS-FSAR AMENDMENT 9 NOVEMBER 1981 SUPERVISOR - STARTUP Name:
Jonathan H. Greene Citizenship:
U.S.A.
Age:
36 Formal Education:
BSME, Junc 1972, University of Connecticut Training:
CPS Operator License Training Work Experience:
Illinois Power Company 1977 to Present Supervisor - Startup, Clinton Power Station Direct all Startup Group activities includ-ing scheduling, flushing, hydrotesting, preoperational tes:ing, and FSAR work.
Other Experience:
NUS Corporation 1974 to 1977 Position as Test Engineer at two PWR Tuclear facilities.
Work included electrical and mechanical system preopera-tional test procedare preparation and implementation.
Had Lead Test Engineer responsibility for cold hydro, hot func-tional, and power ascension tests.
1972 - 1974 American Electric Power Corporation Position as Results Engineer for one year at 1100 MN fossil plant.
Position as Test Engineer for one year at a PWR nuclear facility.
13.A-35
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 1
SUPERVISOR - PLANT OPERATIONS QUALITY ASSURANCE Name:
Michael E. D'Eaem Citizenship:
U.S.A.
Age:
38 Forr.al Education:
Graduated, Washington Gardner High, Albion, i
Michigan, 1960; 1 year Jackson Junior College, Jackson, Michigan, 1960-61; 1 semester University of South Carolina, 1969; 1 semester Lake Michigan Community College, 1976.
U.S. Navy:
Electronics Technician School, i
Nuclear Power School, Reactor Operator DlG Prototype.
Work Experience:
Illinois Power Company 1981 - Present Supervisor - Plant Operations Quality Assurance i
Supervise and provide technical direction to plant operations OA personnel.
- Prepare, review, and/or approve procedures, purchase requisitions, specifications, etc., ensuring i
adequacy in incorporating quality require-ments.
l Other Experience:
1979 - 1981 The Zack Company i
1.
Quality Control Manager - Midland l
Nuclear Project:
Developed, implemented, and managed a quality control program which met the requirements of 10 CFR 50, Appendix B, ANSI N45.2, and its daughter standards.
Developed, implemented, and controlled a site welding program.
1 2.
Quality Assurance Manager - Corporate:
Managed corporate quality program.
Provided technical and administrative direction to four QC Managers (i.e.,
Corporate QC Manager and three site QC Managers).
13.A-36
7 CPS-FSR AMENDMENT 9 NOVEMBER 1981 Other Experience:
(Continued) 1978 - 1979 Illinois Power Company QA Specialist - Monitored quality activities in electrical and control / instrumentation areas.
Performed Quality Assurance Audits.
Reviewed contractors' procedures for compliance to governing codes, standards, and regulations.
1977 - 1978 Bechtel Pcwor Corporation Senior QA Engineer - Monitored quality activities in piping, welding /NDE, and testing areas.
Performed Quality Assurance audits.
Reviewed quality documentation.
Initiated and coordinated revisions to quality manuals.
Ccordinated responses to client and management audits.
Investi-gated and resolved quality problems in the areas of piping, welding /NDE, and testing.
1975 - 1977 Co'nsumers Power Company QA Engineer - Established in the form of contract attachments, Quality Assurance Criteria for " Production and Transmission Departments" Contractors and/or Suppliers.
Reviewed and resolved comments on Con-tractors' and/or Suppliers' Quality Assur-ance Program Manuals.
Developed, imple-mented, and administered the Auditor and Lead Auditor Certification Program.
Conducted audits, as team leader.
Assistant Mechanical Maintenance Supervisor -
Responsible for the scheduling, coordination, documentation, and first line supervision of both maintenance and modification work at the Palisades Nuclear Station.
1975 Nuclear Energy Services, Inc.
Project Manager - Managed Conam's activities at the La Salle County Nuclear Power Plant Project.
Conam's activities encompassed the performance of RT, MT, UT, FT, and VP 13.A-37
CPS-FSAR AMENDMENT 9 NOVEMBER 1981 Other Experience:
(Continued) examinations.
All required soils and concrete testing, vendor site and source surveillance, and associated Quality Assurance activities.
Certified Level III NDE under SNT-TC-1A.
1974 - 1975 Consumers Power Company Quality Assurance Administrator - Estab-lished in the form of contract attachments, Quality Assurance Criteria for " Electric Plant Projects Departments" Contractors and/or Suppliers.
Reviewed and approved Contractors' and/or Suppliers' Quality
@ssuranco Program Manuals.
Established and implemented Project Quality Assurance Programs which met the requirements of NRC, 10 CFR 50 Appendix B and ANSI N45.2.
Performed the duties of Palisades Project Quality Assurance Administrator, Palisades Proj6ct Field Quality Assurance Supervisor, and General Office Staff Quality Assurance Engineer for nondestructive testing.
Scheduled and conducted, as team leader, quality assurance audits of major. con-tractors and suppliers.
Communicated i
l with the Nuclear Regulatory Agency on l
project-related matters.
1961 - 1973 U.S. Navy USS Tigrone (AGSS-419); Engineer Officer USS Fulton (AS-ll); QA Officer FBM Training Center, Charleston, S.C.:
Instructor USS Woodrow Wilson (SSBN 624 ) ; Reactor Operator 13.A-38I ~ tt0VEliBER 1981 N4Ef DMEilT 9 g / u / / i / / /
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___.,s_,m___-.___aa..<----_m...-L__--._."-~-- AMENDVENT 9 I NOVEMBER 1931 Director. Compliance i i Vice President Director Site Purchasing Director. Project Controls Manager of Construction 1 Manager of Nuclear Station Engineering i f Vice President Manager of Clinton Power Station l i Director Ouality Assurance I i Manager of Engineering 1 i Director Environmental Affairs I {ce President Manager of Planning t Director Real Estate Manager of Industrial Relations Manager of Customer Services Chair. nan & Presiderit Vice President Service Area Managers Manager of Energy Programs Assistant Secretary Vice President and Secretary Manager of Data Processing Manager of Accounting Manager of Rates Vice President Director-internal Auditing Executive Vice President and Treasurer Manager of Finance and Assistant Treasurer Manager of Power Production Manager of Purchasing and Stores Manager of Energy Supply Manager of Public Affairs CLINTON POWER STATION FIN AL S AFETY AN ALYSIS REPORT FIGURE 13.1-1B ILLIN0IS POWER COMPANY CORPORATE ORGANIZATION STRUCTURE
AMENDFEi!T 9 NOVEMBER 1931 o --.---n.... .-._.w. Manager of i Nucicar Station Engineering I I I I Director Director Supm sor Administrative Supervisor i Design N"C'*8' 38Y Licensing Superv sor Cornpisance Engineenng Engineering Analysis Superviser Supervisor Cleil. Structurat Plant System Engineenng Engineenng I ) i Supervisor Supervisor j ( Mechanical Nuctear Fuel Engineenng Cycle I I Supervisor Supervisor g Electncat Technical Engeneenng Ass?ssment I I. I 4 t Supervisor instrumentation 1 Control Engineenng I i Supervisor Construction Engineering g i CLINTON POWER STATION FIN AL S AFETY AN ALYSIS REPCRT FIGURE 13.1-2 t IP fl0 CLEAR STATI0il Ef!GIf1EERIf>G DEPT. STRUCTURE RELATIVE TO CLIllT0i1 POWER STAT 10tl --.--u. 7 9 .7 m ae4-., m...- ,--%y.,,,.7 w-.,, - g.--- y%%v r. --r+ r. em
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CPS-FSAR AMENDMENT 10 NOVEMBER 1981 A Vice-President is responsible for providing support services through the Nuclear Station Engineering and quality Assurance Departments. He reports to an Executive Vice-President who in turn reports to the President of Illinois Power Company. The Manager of Nuclear Station Engineering reports to the Vice-President and is directly responsible for CPS engineering services relative to technical areas of nuclear, mechanical, structural, civil, electrical, thermal-hydraulic, metallurgy, materials, licensing, fuel, plant chemistry, health physics, instrumentation and controls, and maintenance. Nuclear Station Engineering Departmental structure relative to CPS is as shown on Figure 13.1-2. The Director - Quality Assurance reports to the Vice-President includ-and is responsible for the IP quality assurance program, ing both internal audits and audits of vendors or contractors. The Quality Assurance Department is presently responsible for auditing training activities; this responsibility will continue. Additionally, the QA department will be responsible for evalu-ating the effectiveness of nuclear related training and reporting its findings to the Vice President. This responsibility will be independent of normal quality assurance functions and it will be performed by an individual experienced in training. A con-sultant may be used to perform this evaluation. Oualif caric as 13.1.1.3 t The qualifications of Headq m ters staff personnel responsible for Clinton Power Station ted.nical support meet or exceed those requirements set by AuSI/ANS 3.1,1978. Resumes of Head-quarters supervisory personnel are included in Appendix 13A. 13.1.2 Operating Organization The Operating Organization section describes the structure, functions and responsibilities of the on site organization established to operate and maintain the Clinton Power Station. 13.1.2.1 Plant Organization The Clinton Power Station organization is as shown in Figure 13.1-3. The organization chart indicates the title of each position, the number of personnel assigned to each position (including common or duplicate positions), the reporting responsibilitie s, and the positions for which a Reactor Operator or Senior Reactor Operator license is required. CPS operating organization positions which are vacunt as of October 1981 are expected to be filled according to the schedule found on Table 13.1-2. CPS staffing will be increased as necessary for Unit 2 when such a need exists and will be based upon the experience gained through the operation of Unit 1. 13.1-5
CPS-FSAR AMENDENT 10 NOVEMBER 1981 The ccmpliance Inspectors report to the Compliance Supervisor. For the CPS independent inspection piagram, if the work activity itself is an inspection, no independent inspection will be conducted or is warranted. Under these conditions four in-spectors should be adequate. However, should experience warrant the need for additional inspectors they will be added. Clinton Power Station utilizes an arrangement whereby depart-involved mental training is provided by the specific department and not by the Training Department. This allows the Training Dept, to put greater emphasis in operator training and re-training and general employee training. At present 5 instructors should be an adequate number to provide the necessary training. However, CPS will remain alert to the training needs of the station and increase the training staff as warranted. 13.1.2.2 Plant Personnel Responsibilities and Authorities The functions, responsibilities, and authorities of varicus CPS staff positions are as follows: POWER PLANT MANAGER The CPS Power Plant Manager is responsible for overall facility operation including industrial relations, planning coordina-tion, and direction of the operation, maintenance, refueling, radchem, and technical activities. The Power Plant Manager is responsible for compliance with the station's operating license, regulations, ASME code requirements, and the CPS Operational Quality Assurance Program. He is also responsible for final The Power Plant approval and distribution of station reports. Manager is chairman of the Facility Review Group as outlined in Section 6.5 of the Technical Specifications and is the chairman of the ALARA committee. The Power Plant Manager Interfaces between the CPS reports to the Vice-Presiddnt. Staff and offsite organizations are coordinated through the He also delegates authority in specific Power Plant Manager. areas during normal day-to-day conduct of operations. ASSISTANT POWER PLANT MANAGERS including Responsibility for day-to-day operating activities, Maintenance, Radchem, and Operations matters is assigned to the Assistant Power Plant Managers. They are members of the Facility Review Group and the ALARA committee. 13.1-6
CPS-FSAR AMENDMENT 10 WOVEMBER 1981 SUPERVISOR - TECHNICAL The Supervisor - Technical directs a staff which provides technical support for operations, refueling, maintenance and modifications. He is responsible for evaluating equipment performance data, including nuclear core performance, and preparing reports and making recommendations in these areas. The Supervisor - Technical coordinates the station planning, forecasting, and scheduling of reactor core nuclear activities. He is a member of the Facility Review Group. PLANT SAFETY SPECIALIST During the design phase of the plant an evaluation of the CPS Fire Protection Design was made by a senior engineer from Schirmer Engineering Corporation, a fire protection consultant. A resume for this engineer is included in the Clinton Power Station Fire Protection Evaluation Report. During the operating phase of CPS the following arrangement will be adopted. The position of Plant Safety Specialist will be created on the plant staff. This individual will report to the Supervisor - Technical and will be responsible for: a. Maintenance of fire detection, suppression, and extinguishing systems. b. Fire prevention activities Training and manual fire-fighting activities of plant c. personnel and the fire brigade. The Plant Safety Specilist will have training in fundamentals of physical science and plant systems and equipment, and he will complete the training required of the Fire Brigade Leader. The Plant Safety Specialist will prepare a monthly report of fire protection activities. Distribution will be included to NRAG members. A qualified fire protection consultant will be retained to provide an annual audit of the fire protection program. The consultant will also be available to advise the Plant Safety Specialist. M & M Protection Consultants has been the fire protection consultant for IP at our fossil fueled plants and during the construction phase of CPS. The reports of the fire protection consultant are directed to the attention of top management of the Company. It is our intention to extend this relationship into the operating phase. 13.1-6a
CPS-FSAR AMENDMENT 10 NOVEMBER 1981 SUPERVISOR - RADCHEM The Supervisor - Radchem is responsible for providing, scheduling, and coordinating radiological control services as required to support station operation and maintenance activities. He directs the implementation of the program to control the acquisition, shipping and receiving of all by-product, source, and special nuclear material except fuel. The Supervisor - Radchem is responsible for the operational chemistry program of the station and the operation of radwaste handling facilities. He is a member of the Facility Review Group and the ALARA Committee. SUPERVISOR - MECHANICAL The Supervisor - Mechanical is responsible for directing the maintenance, including repair, of all mechanical equipment in the station. 13.1-6b
AMENDMENT 10 CPS-FSAR NOVEMBER 1981 I Hot i Power Operation Startup Shutdown Job Title Normal Allowable Minimum Shift Supervisor 1 1 Assistatt Shift Supervisor 1 1 2 of 3 Control Room Supervisor 1 1 Control Room Operator 3 2 2 Unit Attendant 1 2 1 Auxiliary Operator 1 1 1 Radwaste Operator 1 1 1 Radiation Protection Personnel 1 1 1 Cold Shutdown Refueling Shift Supervisor 1 1 Assistant Shift Supervisor 1 1 ? 1 of 3 Control Room Supervisor 1 1 Control Room Operator 3 2 1 Unit Attendant 1 2 Auxiliary Operator 1 1 1 of 2 Radwaste Operator 1 1 1 Radiation Protection Personnel 1 1 1 The normal complement provides for maximum flexibility and effectiveness by providing 3 R0s and 3 SR0s on each shift.
- However, one RO is normally assigned duties outside the main control room on a rotating basis.
While it is desirable to have a licensed operator outside the control room, it is not necessary and CPS may operate with the allowable complement on certain shifts until additional licensed operators are available. The minimum complement represents Technical Specification Requirements, but it is not intended to operate with the minimum complement unless illnesa or other un-avoidable circumstances so require. Even in these unavoidable circumstances, such operation would only be for a short period of time, until the allowable or normal complement could be j reestablished. I Each shift crew shall include a Shift Supervisor or a person qualified.and designated to act as a Shift Supervisor.
- Further, each shift crew shall include an individual qualified by educa-4 tion and experience to act as a Shift Technical Advisor.
This individual may be a member of the operating shift supervision present. CPS manning will be increased as necessary for Unit 2 when the need exists and will be based upon the experience gained.through the operation of Unit 1. During refueling operations, a separate Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling will super-vise these operations and will have no other concurrent duties. 13.1-10
AMENDMENT 10 CPS-FSAR NOVEMBER 1981 An around-the-clock radiation protection program will be imple-mented by the presence of at least one individual qualified in radiation protection. Additional personnel will be scheduled as required to cover special jobs or work loads as determine by radiation protection supervision. During normal work days, the Radchem Technicians report to radiation protection super-vision. During off shifts and weekends, the radiation protec-tion personnel will report to radiation protection supervision or the Shift Supervisor. Shift crew composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommo-date an unexpected absence of on duty shift crew members provided immediate action is taken to restore composition to within the minimum requirements as stated. Clinton Power Station will have on shift one experienced indi-vidual from fuel load to 100% power operation er for one year, whichever occurs earlier. This individual will have substantive commercial BWR-operating experience, including startups and shutdowns under conditions that might be expected during CPS initial startup and power escalation. For short periods of time, up to two hours, as a result of. illness or other unavoidable circumstances this individual may not be present. Clinton Power Station currently has 38 persons in cold license training for 32 licensed positions on shift. Five of these licensed positions represent an extra reactor operator-qualified individual assigned to nonlicensed duties on a rotating basis. This results in an actual commitment to 27 licensed positions on shift. Illinois Power Company will begin hiring 10 Unit Attendants immediately. As has been the practice in the past, these individuals will be hired from the Nuclear Navy such that they could be licensed by January 1983, if necessary. The license training program for these individuals will commence in February 1982 to support this goal. The training pipeline will ultimately be filled by Richland Community College graduates preferably in the Power Generation-Nuclear curriculum or equivalent. Acceptable graduates will be hired into entry level positions in 1982 and following years. Commencing in the summer of 1982, Illinois Power Company will provide 15 scholarships for local high school graduates whereby the recipients will attend Richland Community College in the Power Generation-Nuclear program and will work during the vacation periods at Clinton Power Station. This scholarship / work experience program should assure a continuing inflow of qualified personnel. 13.1-10a
AMENDMENT 10 ' CPS-FSAR WOVEMBER 1981 I Total attrition in the Operations Department has been 33% for a-5-year period of time and has been lower this year than ever-before. Attrition for the 12 months ending October 31, 1981 was 5%. Except for major events such as TMI-2 and announced schedule delays, attrition of operators has been very low. Even if 50% of the license candidates initially fail the examination and one-half of them subsequently pass, this would provide 36 people.for 27 licensed positions. Attrition of 25% could then be acceptable over the next 15 months; it took over three years to reach this value of attrition previously. Con-sequently, it is believed that there will be ample allowance for attrition and examination failure and that there will be adequate licensed personnel to staff five shifts at the desired i staffing level. 13.1.3 Qualification of Nuclear Plant Personnel Qualifications for Clinton Power Station personnel are described in the following subsections. i 13.1.3.1 Qualification Requirements Clinton Power Station follows the guidelines set forth in Regu-latory Guide 1.8 for selection and training of management per-sonnel with the exceptions noted in Section 1.8. Table 13.1 -1 lists members of the plant staff and designates equivalent ANSI /ANS 3.1 1978 titles as a comparison. i 13.1.3.2 Qua'ifications of Plant Personnel The qualifications of the initial personnel on the CPS staff i holding key managerial and supervisory positions are provided in the resumes included with this chapter as Appendix 13A. j 13.1.3.3 Startup Staff Experience l The education, training, and commencurate experience for persons I who conduct or supervise pre-operational and startup testing are summarized on Table 13.1-3. Commensurate experience is considered the knowledge and skills acquired through past i experience corresponding in the same relative proportions to j the knowledge and skill requirements of the tasks to be assigned to that test engineer. In other words, a person who t had two years experience doing only electrical testing activi-ties would not be assigned tasks of a mechanical or fluid nature. However, an engineer with two years experience testing a variety l of pumps and flui.d systems would have gathered sufficient know ledge and skills t.s ce assigned to an HVAC system startup. NVA " t balancing would require additicnal experience. The experience of personnel will be documented prior to allowing individuals i to perform testing. t 13.1-10b 1 m.~
CPS-FSAR AMENDMENT 10 NOVEMBER 1981 Attached is an outline of the " Mitigating Reactor Core Damage" training to be taught to the operations, technical and training staffs and to selected members of the maintenance and radiation / chemistry departments. The training will consist of a minimum of forty (40) hours of instruction in the areas covered in the outline. The attached outline was generated from a review of the existing training courses and comparison with the INPO document " Guidelines for Training to Recognize and Mitigate the Consequences of Core Damage" and Harold Denton's letter of March 28, 1980 regarding " Qualification of Reactor Operators". These topics represent the areas of knowledge where additional training may be required to achieve the greater depth of knowledge required. The program also includes training on the use of emergency procedure guidelines and the execution of the emergency plan. Nonlicensed technicians will participate in this course as follows: I and C technicians - vital instru-mentation; Chemistry technicians - primary chemistry; and Radiation Protection technicians - radiation monitoring. Outline for Mitigating Reactor Core Damage Training 1. Incore Instrumentation (6 hours)* a. Use of fixed or movable incere detectors to determine extent of core damage and geometry changes. b. Methods for calling up incore data from the plant computer. 2. Vital Instrumentation (6 hours)* Instrumentation response in an accident environment, a. failure sequence, and indication reliability. b. Alternative methods for measuring flows, pressures, levels, and temperatures. 3. Primary Chemistry (4 hours)* Expected chemistry results with severe core damage; a. consequences of transferring small quantities of liquid outside containment; importance of using leak tight systems. b. Expected isotopic breakdown for core damage; for clad damage. c. Corrosion effects of extended immersion in primary water; time to failure. 13.2-2c
/ CPS-FSAR AMENDMENT 10 l WOVEMBER 1981 i 4. Radiation Monitoring (4 hours)* L i j a. Response of. Process and Area Monitors to severe damages; behavior of detectors ~when saturated; method of detecting radiation readings by direct measurement at detector output; expected accuracy of detectors at different locations; use of detectors to determina extent of core damage. b. Methods of determining. dose rate inside containment from measurements taken outside containment. 4 l 5. Gas ~ Generation (4 hours)* a. Methods of H2 generation during an accident; other sources of gas (Xe, Kr); techniques for venting or disposal of non-condensibles. b. H2 flammability and explosive limit; and sources of 02 1 in containment or reactor coolant system. 6. Procedures and Guidelines (16 hours)* a. Eff ective use of the Emergency Guideline Procedures. b. Makeup and effective use of the Emergency Plan. t 1
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4 -. 6 4 m %+ i CPS-FSAR AMENDMENT 10 WOVEMBER 1981 L. . General Employee Training General Employee Training is administered by the CPS Training Department to all personnel regularly and temporarily employed at CPS. It is a one or two day course and consists of the following subjects: I 1. Introduction to CPS 2. Emergency plan 3. Security plan 4. Fire protection 5. Radiation protection and respirator training 6. Industrial safety 7. Quality Assurance program A written or oral examination may be administered following the lectures. Temporary personnel will participate in this training to a level commensurate-4 with their responsibilities. In addition to the fire protection portion of General Employee Training, personnel responsible for inspection of fire protection equipment will receive additional instruction on design, inspection, and maintenance of fire suppression and extinguishing systems. M. Instructor Training IP training instructors engaged in licensed operator training will receive SRO certification and eventually i SRO licenses to insure their technical expertise. All instructors will undergo INPO instructor certifica-tion when this program is developed. The present staff of instructors have all completed Navy prototype instructor training and duty tours, and the Training Supervisor is an active member of the Richland Community College part time faculty. Future instructors l who join the staff prior to establishment of the INPO certification program will receive on-the-job training and evaluation based on their experience level. 4 As an operating license applicant Illinois Power Company is not subject to the one year experience j_ requirement for cold license SRO candidates.
- However, after one year of station operation, Illinois Power Company will comply with the 1 year experience i
requirement for hot license SRO applicante The requirement for three months-on shift experience for control room operator and SRO candidates as an extra-person on shift is not applicable to Illinois Power Company as an applicant for an operating license. Illinois Power Company will comply with this require-ment for hot license candidates after three months of ? station operation. i i 13.2-4
t CPS-FSAR AMENDMENT 10 ROVEMBER 1981 The Illinois' Power Company licensed operator training program has always included topics in heat transfer, fluid flow and thermodynamics. Therefore, the program does not require any major changes in this area. However, the simulator certification process has been revised to include these topics in both lecture presentations and the final written examination. Reactor and plant transient training is primarily performed at the simulator facility and includes classroom discussions of typical transients as well as demonstrations of casualtj and transient i response of the simulator. This knowledge is tested in depth on the certification examination. i l All licensed operator candidates will be certified competent to take the NRC license examination by i the responsible Vice President prior to application for the examination. This certification will be based on, recommendations from the Power Plant Manager and his staff formulated from close personal observa-tion of the individual's technical expertise, reliability, maturity and analytical ability. The passing grade for Reactor Operator and Senior Reactor Operator initial certification and annual requalification exams has been raised to a minimun i of 80% overall with at least 70% required in each section. i 13.2.1.1.2 Reactor Operator Experience Reactor Operator Experience consists of the BWR Operator Training (Subsection 13.2.1.1.1 D) and Observation Training (Subsection 13.2.1.1.1 E). Individuals seeking a license who have not been previously licensed, or had experience in operating a j reactor, receive this training. 13.2.1.1.3 On-Site Training Program The on-site training during the preoperational period consists of on-the-job training (OJT) for all station personnel while conducting preoperational and startup testing. This OJT is usually of an informal nature and conducted as the need arises. OJT conducted in a formal manner will be documented in the same manner as classroom training. Selected non-licensed individuals will also receive portions of the classes described in Subsection 13.2.1.1. Table 13.2-1 outlines the courses 4 I provided to the various functional positions on the staff. i i
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CPS-FSAR AMENDMENT 10 NOVEMBER 1981 13.2.1.1.4 Differences in Trainine Program Due to Previous Experience Differences exist in prospective operator backgrounds. Illinois Power Company has provided Navy and commercial PWR operators with BWR observation training, and on-the-job training has been augmented by extended visits to operating BWRs to participate in refueling outages and outage recoveries. In addition to this, all operators to date, regardless of back-ground, have received or will receive: BWR Technology, BOP systems and BWR training in addition to the minimum training identified in Table 13.2-2. To date no inexperienced operator candidates have been hired. However, should such candidates be hired in the future, they will receive the training indicated in table 13.2-2. Candi-dates with experience at unlicensed DOE reactors will be trained in the same manner as previous Navy operators. 13.2-4b
CPS-FSAR AFENDME TT 10 NOVEMBER 1981 13.2.2.3.2 Specialist Replacement Training Specialist Replacement Training will be conducted in the same manner as specialty training described in Subsection 13.2.1.1.1.J. 13.2.2.3.3 Operator License Replacement Training License Replacement Training will be from twelve to twenty-four weeks duration depending on thn education and experience of the student. As a minimum it will include the following areac: A. Reactor fundamentals (or equivalent) B. BWR technology (or equivalent) C. Balance of plant systems D. BWR operator training (or equivalent) 13.2.2.3.4 SRO License Training SRO License Training will normally be six weeks in duration. It consists of an intensive review of the following subjects: A. CPS systems B. Technical specifications C. Procedures D. FSAR 13.2.2.3.5 Shift Supervisor Training Training programs that include shift supervisors will emphasize responsibility for safe operation and management functions that provide for assuring safety. 13.2.3 Applicable NRC Documents Below is a list of documents that provided guidance in the prepara-tion and administration of the Clinton Power Station Training Program. The only exceptions taken to the~ guidance provided in these documents are described in Section 1.8, Conformance to NRC Regulatory Guides. A. 10 CFR Part 50, " Licensing of Production and Utilization Facilities" B. 10 CFR Part 55, " Operators' Licenses" C. 10 CFR Part 19, " Notices, Instructions and Reports to Workers; Inspections" D. Regulatory Guide 1.8, " Personnel Selection and Training" (h 13.2-12
CPS-FSAR AMENDMENT 10 NOVEMBER 1981 E. Regulatory Guide 8.2, " Guide for Administrative Practices in Radiation Monitoring" F. Regulatory Guide 8.8, "Information Relevant to Maintaining Occupational Radiation Exposure as Low as is Reasonably Achievable (Nuclear Power Reactors)" G. Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable" 13.2-12a
Qdk6 TABLE 13.2-2 TRAINING REQUIREMENTS FOR LICENSED OPERATORS OF VARIOUS EXPERIENCE GROUPS BWR LEACTOR REACTOR BWR OPERATOR OBSERVATION LICENSE FUNDAMENTALS STARTUP TECHNOLOGY BOP TRAINING TRAINING 03I REVIEW No Previous Experience X X X X X X X X Nuclear Navy Operatur Experience X X X X X Pcevious Licensed (BUR) X X X X X Previously Licensed (PWR) X X X X X X e .}}