ML20041C635

Forwards Info Addressing NRC Findings Associated W/Open Item 52, Mgt Review Contained in SER Suppl 1.Info Consists of Revisions to FSAR Sections 13.1,organizational Structure of applicant,13.2,training & 13.4,review & Audit

ML20041C635
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	01/11/1982
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-658, NUDOCS 8203020402
Download: ML20041C635 (46)

Text

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• LONG ISLAND LIGHTING COMPANY m m ,f , SHOREHAM NUCLEAR POWER STATION

. c.c 4 ~.--< w. u --s.o o P.O. BOX 618, NORTH COUNTRY ROAD

• WADING RIVER N.Y.11792 January 11, 1982 SNRC-658 m

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation O/

U.S. Nuclear Regulatory Commission TCSgg b 20555 4 [

Washington, D.C. f a Af4g l ,3 Shoreham Nuclear Power Station - Unj 1 Docket No. 50-322 ,

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Dear Mr. Denton:

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Enclosed herewith are sixty (60) copies of information which addresses NRC findings associated with Open Item Number 52,

" Management Review" as contained in Supplement No. 1 to the SER. This information consists of revisions to the following sections of the FSAR:

1. Section 13.1 - Org uizational Structure of Applicant

2. Section 13.2 - Training

3. Section 13.4 - Review and Audit Revisions have been identified with a bar in the right hand margin. Please note that these revised pages are not intended to represent a complete FSAR rewrite of these sections, but merely to document the changes that have been made in response to Open Item No. 52 specifically. The complete scope of changes to these sections will be forwarded via a formal FSAR amendment at a later date.

We trust that the enclosed information is satisfactory. Should you have any questions or require additional information, please do not hesitate to contact this office.

Very truly yours, vM W' ,

J. L. Smith ( C) l Manager, Special Projects Shoreham Nuclear Power Station RWG:mp Enclosure cc: J. Higgins 9203020402 820111 PDR E

ADOCK 05000322 FC.893 5 PDR

. SNPS-1 FSAR

. e Further information on the corporate organizations and responsibilities of S&W and of GE are contained in Section 1.4.

13.1.1.3 LILCO Technical Support for Shoreham Operations in addition to the technical and administrative support available as part of the Shorcham Plant staf f, technical and administrative support for operation will be provided by the Manager, Nuclear Engineering, the >bnager, Nuclear Operations Support, and the Vice President-Engineering and their respective organizations.

As shown on Fig.13.1.1-1, the Manager, Nuclear Engineering and the ibnager, Nuclear Operations Support report directly to the Vice President-Nuclear. The objective of this supplementary support is to assure that LILCO has the resources to discharge its responsibility for the safe operation of Shoreham Station and to have available a nucleus of personnel to provide timely technical support to the plant staff in the event of an emergency. An advisor to the Vice President-Nuclear, with substantial BWR r,ower plant operating and management experience, will be in place prior to fuel ?.oad and for a year following or until the Vice President and his staff have accrued sufficient experience.

As shown on Fig. 13.1.1-3, the Manager, Nuclear Engineering is supported by three d ivi s ions , i.e., Nuclear Systems Engineering, Nuclear Licensing, and Nuclear Fuel.

These three divisions will have as many staf f specialists as required to support initial fuel loading and the safe operation of the plant. The qualifications and experience of the key Nuclear Engineering personnel are presented in Appendix 13A.

Technical design and evaluation expertise will be provided in the areas of nuclear instrumentation, nuclear materials engineering, nuclear mechanical engineering, plant modifications, radiation protection and shielding, licensing, NRC compliance, reactor physics, transient analysis, accident analysis, and nuclear fuel management.

A continuing services contract will be obtained with a qualified architect / engineer fire prior to fuel load to provide supplementary engineering support and various consultants will be utilized as needed whenever further expertise is required. The -

Manager, Nuclear Engineering has the responsibility to engage consultants and specialists in specific areas of engineering or science to supplement the capabilities of the Nuclear Engineering staff.

The Manager, Nuclear Operations Support will have the responsibility for coordina-tion, implementation, and direction of appropriate technical and administrative support functions carried out jointly by the Nuclear Operations Support and Nuclear Engineering organizations (i.e. , " Engineer-in-Charge" as described in ANS 3.1 draft revision dated 12/6/79) . He is responsible directly to the Vice President-Nuclear for the development and administration of corporate policies and procedures required for the management of the nuclear organization and the monitoring of its performance.

As shown on Fig. 13.1.1-4, the >bnager, Nuclear Operations Support is supported by three divisions; i.e., Nuclear Regulation, Nuclear Services, and Nuclear Records

>bna g emen t . These three divisiions will have as nany staf f specialists as required to support initial fuel loading and the saf e operation of the plant. The qualifica-tions and experience of key Nuclear Operations Support personnel are presented in 13.1-4 1/11/82

o SNpS-1 FSAR Appendix 13A. Nuclear Operations Support personnel will provide operation, main-tenance, technical, and adninistrative expertise for supplementary support functions such as coordination of regulatory activities, long-range outage planning, initiation and evaluation of major proj ect s, cost control, records management and other long-term planning activities. The Nuclear Operations Support organization will be structured to accommodate future tasks which will also require supplemental support.

The Maaager, Nuclear Operations Support position will correspond to the responsi-bilities and qualfications of the " Engineer-in-Charge" as described for guidance in ANS 3.1 draft revision dated 12/6/79. He will have a minimum of a Bachelor's degree in Engineering or the Phytfcal Sciences and have a minimum of 6 years of professional level experience in nuclear services, nuclear plant operation, or nuclear engineering. A maximum of 2 years of the 6 years of professional experience may be fulfilled by related technical or graduate academic training.

The Nuclear Operations Support supervisors responsibic for the Nuclear Regulation or Nuclear Services divisions will have a minimum of a Bachelor's degree in an academic field associated with electric power production or the physical sciences related to electrical energy generation, and 6 years of experience in power plant operation and/or design.

To further supplement the technical support of the nuclear organizations, the Vice President-Engineering shall designate, prior to fuel load, a minimum of 10 engineering personnel, assigned to the Corporate Engineering Of fice, for nuclear support. The first priority for these engineering personnel will be to respond to the needs of the Shoreham Plant as required.

13.1.2 Operation Organization 13.1.2.1 Station Orcanization The Shoreham Nuclear Power Station, organization as shown on Figs. 13.1.2-1 through 3 will consist of a minimum of 165 full-time employees functioning in one of 11 main sections reporting through their respective Section Heads to one of three divisions headed by either the Chief Operating Engineer, Chief Technical Engineer, or Technical Support Manager who report to the plant bbnager. The Operating Quality Assurance Division reports to the Plant Manager through the Operating Quality Assurance Engineer, as described in Section 17.2.

The Operations Section of the station will include a minimum of 32 supervisors

, and operators, and will be responsible for operation of the station. The station will have a Watch Engineer directing the operations of each shif t through the Watch Supervisor, Nuc1 car Station Operator and Nuclear Assistant Station Operator.

The Watch Engineer will report to the Operating Engineer.

To supplement the operating experience of the operations staff, one additional person with substantive previous BWR operating experience will be retained as an on-site advisor to the Chief Operating Engineer for a period of at least one year commencing six months prior to fuel load and extending through operation at 100 percent power.

The Paintenance Sect ion of the station will have a minimum of 26 men experience in tachanical and electrical :uintenance of large stcam-electric generating; stations.

The force will be supervised by the >Sintenance Foreman who in turn reports to the ibintenance Engineer. This number of maintenance personnel will be adequate l

13.1-5

SNPS-1 FSAR ,

13.1.2.3.2 nucionr Annistant Str.tien O' orator The Nuclear I.scistant Station Operator (MASO) is responsible to the Nuclear Station Operator (:!SO) for operating or supervising the operation of all equipment in the station or substation including the starting or securing ot equipment , or systems ,

as requested; ac31 sting in reactor fueling; assisting in station radioactive vaste handling operations; anu performing operational testing.

The UASO is responsible for recognining, reporting, and analyning operating irre ularities anc assuming the responsibility for acting indepr.;dently in emerg:-ncies uhen the Nuclear Station Operator, hatch Sucervisor, ann Match Engineer are not l 1mmediately c;;.ilable.

13.1.2.3.3 rcuirment onorate-The Equipment Operator (20) is responsible to and operates station at::111ary equipment under the 61rcet supervision of the NSO or NASO. -

13.1.2.3.3 T^chnician Technicians are responsible to the engineer or supervisor to uhich they are assignaa. Technicians parfora all types o1 uorr. l asnociated u:.t h in s t r. llin< r , raint aning, repairing, and ca)ibrating all station ir a trr:rnt itic n and centrols for elec trical , machanical, and nuclear cycznas; perrona all phases of water analycis for c:cmicci and radiochemical content; porlorm radiation surveys; and operate, maintain, and calltrate radiction protection equipment and Instrumentation.

13.1.2.3.5  !!ochanic Mechanics are respannible to the I:aintenance Foreman f or properly installing, inspecting, analyning, testing, repairing, and maintaining statica mechanical cnd electrical equipment such as pumps, heat exchangars, generators, motors, b r o a r. e r a , and power -

cables. They are also responsible for the preparation or completion or required applicacle documentation to support their maintenance activitics such as completion of repair and inspection reports cn safety related equipment.

13.1.2.3.6 Security Officer The responsibilities of the Security Officers are described in Section 1.2 of the Security Plan.

13.1.2.4 shift Crow comrosition The ninimu., plant ce r ;t i:.~ shift will consist of one "atch 2.nganacr ( c.'.v) , caa n :C i. anro r (20) , ona Nuclear station Operator (RO) , one Nuclear Assistant Station Operator (RO) , three 13.1-11 Revision 21 - May 1981 i ~

SNPS-1 FSAR

• Equipment Operators (nonlicensed), one Technician trained in health physics techniques, and one Technician trained in radiochemistry techniques for a total of nine persennel. One of the Equipment Operators will be dedicated to the communication function in the event of an emergency, as described in Section 13.3.

In addition, LILCO will have at Icast one individual on site on each operating shif t with substantive previous BWR operating experience, including startup and shutdown of a BWR. This experienced person will be assigned to each shift reporting to the Watch Engineer commencing at fuel loading until the plant is operating at 100% power. At thattime, the operating personnel will have acquired suf ficient g operating experience to operate without such consultants.

During periods when the reactor vessel is fueled and shut down, the minimum plant operation staff will consist of one Watch Engineer (SRO) or, Watch Supervisor (SRO), one Nuclear Station Operator (RO) or Nuclear Assistant Station Operator (RO), one Equipment Operator, and one Technician for a total of four personnel per shift.

13.1.3 Qualification Requirements for Station Personnel 13.1.3.1 Minimum Qualification Ren,uirements This section includes tbc minimum qualification requirements for all responsible station personnel, both supervisory and nonsupervisory. ANS 3.1 Draft Revision 12/6/79 was used as guidance in developinr, these requirements. The following requirements as to experience and licenses will apply at the time of initial fuel loading or when appointed to the active position.

13.1.3.1.1 Plant Manager The Plant Ibnager shall have a minimum of 6 years of responsible power plant experience of which at least 3 years will be in nuclear power plant design, construction, start-up, operations, maintenance, or technical services.

During the (3) years of nuclear power plant experience the Plant bbnager shall have participated in the management activities of an operating nuclear power plant during:

1. Two months operation above 20 percent power,

2. Routine refueling outage (1 to 2 months),

3. Initial plant startup testing or post refueling outage startup testing.

l He shall have a 4 year degree in engineering or related scientific field. He shall acquire the experience and training necessary to be examined for the Senior Reactor Operators License but may not be required to hold such a license; or have held a license for a similar unit; or have been certified at the plant or at an appropriate simulator.

13.1.3.1.2 Chief Oneratin~ nnoineer The Chief Operating Engineer shall have a minimum of 4 years of responsible power plant experience of which at least 3 years will be in nuclear power plant design, construction, startup, operation, naintenance, or technical services.

13.1-12

SNPS-1 FSAR 13.2 TRAINING PROGRAM 13.2.1 Procram Description The objective of the Shoreham Muclear Power Station training program is to provide fully trained and qualified operating, maintenance and technien1 personnel to en-sure safe and efficient operation of the station. To accomplish this objective, the nuclear training program for the staff of the Shoreham Nuclear Power Station has beer. arranged and is being implemented to meet the needs of the individual staff member. Training received by each man is dependent upon his background, previous training and staff assignment.

The initial training program is designed to utilize experienced fossil plant operating personnel who have little or no nucicar experience. Guidance for the development of the training program was obtained using ANSI N.18.1-1971,

" Selection and Training of Nuclear Power Plant Personnel", and WASH 1094 -

November 1965, "A Guide for the Licensing of Facility Operators, Including Senior Operators".

The overall training program for the initial plant staff is divided into three areas:

1. Training programs for reactor operator, senior reactor operator, and senior reactor operator limited to fuel handling, license candidates

2. Training programs for non-licensed personnel

3. General employee training 13.2.1.1 Licensed Operator Trainine Program Licensed Reactor Operator (RO) candidates will receive formal training in the following subject areas:

1. Principles of reactor operation

2. Design features of the Shoreham Nuclear Power Station

3. General operating characteristics of the Shoreham Nuclear Power Station

4. Instrumentation and control systems

5. Safety and emergency systems ,

6. Normal and emergency operating procedures

7. Radiation control and safety provisions

9. Heat Trans fer, Therradynnnics, and Fluid Flow Licensed Senior Reactor Operator (SRO) candidates will, in addition to the above subject areas, receive technical training in the following subject areas:

-- 1/11/99

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SNPS-1 FSAR .

9. Reactor theory

10. Handling and disposal of, and hazards associated with, radioactive materials.

11. Specific operating characteristics of the Shorcham Nuclear Power Station

12. Fuel handling and core parameters

13. Administrative procedures, conditions, and limitations Licensed Senior Reactor Operator Limited to Fuel Handling (SRO-R) candidates will receive formal training in the folinwing areas:

14. Reactor and fuel characteristics

15. Equipment instrumentation and design description

16. Procedures and limitations

17. Emergency systems and safety devices

18. Health physics and radiation protection The complete initial staff training program is conducted in conjunction with contracted training services from the Cencral Electric Company, General Physics Corporation, and NUS Corporation. The program for licensed personnel as described in detail in this section is divided into the following phases:

1. Basic nuclear

2. BWR technology

3. BWR operator training (simulator)

4. BWR observation

5. Onsite training 13.2.1.1.1 Basic Nuclear Course The basic nucicar course is supplied by the NUS Corporation. This course is 13 wecks in duration and consists of a combination of video tape and classroom lectures presented by either NUS instructors or LILCO personnel. The course is designed to provide a thorough understanding of the basic principles, characteristics, and unique features of the nuclear steam supply system. The major areas covered are: basic nuclear physics, reactor operations, core performance, radiation protection, plant chemistry, instru-mentation and control, and plant and operator performance. Student performance is evaluated through the administration of periodic written examinations.

13.2.1.1.2 BWR Technology The SWR te:hnology course , presented by the Cenoral Electric Cenpeny, consists of five weeks of classroom lectures on bU; ccmpenents, core design, thermal-hydraulics, auxiliary systems, process and nuclear lastrunentation design and operation, and interfaces with the balance of plant systems. Student perfornance is evaluated through the administration of periodic written examinations.

SNPS-1 FSAR

. o 13.2.1.1.3 QWR Operator Trainine The BWP operator training course, is conducted by the General Electric Company or the General Physics Corporation and consists of up to 12 weeks of classroom lectures and simulator control room cxercises designed to provide inexperienced BWR operator and senior operator license candidates with the necessary skills to safely and effi-ciently operate the Shoreham nucicar reactor. Suggested reading and study assignments are made daily. Written and oral examinations are given to monitor the candidate's progress. During simulator control room exercises, candidates rotate through the various control room positions, including Watch Engineer, so that all candidates may have equal opportunity to perform plant evolutions from each operating position.

Sinulators used during this training phase include the Dresden EWR sinulator operated by the Ceneral Electric Company or the Limerick EWR simulator operated by the Cencral Physics Corporation.

13.2.1.1.4 , LWR Observation The EWR observation course, conducted under the guidance of a CE training engineer, consists of four weeks of guided observation on an operational EWR. The Dresden Nuclear Power Station and/or Millstone - Unit 1 Nuclear Power Station will be utilized for this observation training. The course provides exposure to plant operating and maintenance evolutions, station record keeping and station procedures.

Student performance is measured through administration of oral and written exauina-tions.

13.2.1.1.5 Onsite Training The Shoreham Onsite Training (OST) program consists of approximately 18 veeks of classroom lectures and field training. The onsite training program provides all cold license candidates with an in depth study of SNPS systens and equipment; nuclear characteristics; normal, abnormal, cuergency, and administrative procedures; and technical specifications, prior to NUC examinations. Candidates for a license limited to fuel handling will participate in those activities of the onsite training program relating to subject areas 14 through 18 as previously mentioned in Section 13.2.1.1. Licensed personnel supervising or performing fuel handling operations will receive training on fuel h andling equipment and procedures prior to performing fuel handling operations.

Instructors for the various onsite tr,ining lectures will be supplied by the SNPS Staf f, other LILCO organizations, vendors or consultants. Selection of the particular individual to conduct a specific training lecture will be based upon individual availability and knowledge of the subject matter involved. Evaluation of student performance will be accomplished through the administration of written and oral examinations.

13.2.1.1.6 BWR Refueling Observation Candidates for a license limited to fuel handling vill participate as trainees in the fuel handling activities of an operating General Electric B"R Plant similar to the Shoreham station, during a scheduleJ refueling outage.

13.2.1.1.7 p uearch Reactor Training Research R7 actor Training will be given to all cold NRC license candidates not having previous nuclear experience. This traini,c will consist of at least 10 neaningful reactor st art ups on the Brookhaven "edical Rmearch Nactor (or similar available

SNPS-1 FSAR .

facility) administered by LILCO (or consultant) personnel. In all cases cold NRC license candidates will have conpleted 10 meaningful startups on a Nuc1 car Keactor prior to rubmitting an application for a cold license examination.

13.2.1.1.8 Coordination With Precrerational Tests and Fuel Loading Figure 13.2.1-1 shows the schedule of each part of the training program for each section of plant employees in relation to the schedule for preoperational testing and fuel loading.

13.2.1.1.9 Practical Reactor Operation Practical (on the job) plant operation for license candidates will commence with the preoperational test program. Practical reactor operation for licensed per-sonnel will commence with fuel loading, continue through the startup test program.

13.2.1.1.10 Peactor Simulation Training Reactor simulator training will be conducted at the Dresden or Limerick sinulators as described in Section 13.2.1.1.3 for " cold' license candidates who require such training.

13.2.1.1.11 Previous Nuclear Training Other nuclear training programs or experience that satisfy the intent of the program outlined in Section 13.2.1.1 nay be substituted in lieu of portions of the training outlined for reactor operator and senior reactor operator candidates. Excsples of such training programs or expericace that would be permissible for substitution are:

attainment of a baccalaureate or higher degree in the fields of nuclear engineering or nuclear sciences; extensive participation in the design or design review of the station in nuclear related areas; holding or having held a reactor operator or senior reactor operator license at a comparable reactor facility subject to NRC licensing, e.g. , licensed reactor facility; or determination of such experience at a comparabic reactor facility not subject to URC licensing, e.g., reactor facilities operated by the military services; or satisfactory completion of and NRC administered written examination and operating test at a comparable licensed reactor facility without issuance of a reactor operator or senior reactor operator license; or certification of satisfactory completion of an NRC-approved training program which utilizes a complete and accurate nuclear power plant simulator as part nf this program.

13.2.1.1.12 Preparatic. of Station Operating Procedures SNPS operations personnel will participate in the writing and/or review of station operating procedures with technical assistance furnished by General Electric Company, Stone & Webster Engineering Corporation, or other consultants as may be required.

This training will familiarine personnel with the details of the reactor, turbine-generator and asscciated systems.

13.2.1.1.13 NRC Exam Preparation Aa appropriate refresher and exan preparatory period will be provided for all license candidates to ensure that they are fully prepared to satisfactorily complete the applicable NRC liccuse examination.

SNPS-1 FSAR .

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13.2.1.1.14' Preoperational Testing of Equipment This training will provide station operators with operating experience on station systens and equipment prior to fuel loading. Training enphasis will be placed, as systen and component availability permit s, in areas of component testing, system flushing, hydrostatic tests, system checkouts, and functional tests.

13.2.1.1.15 Initial Fuel Loading and Low Power Tests Fuel loading will begin when a sufficient number of operating personnel have sa~ tis-factorily conpleted their SRO or RO " cold" license exaninations. Fuc1 loading, lou-power testing, and power ascension testing, will be conducted by or under the super-vision of operating personnel who hold SRO or RO " cold" licenses.

This training 0i11 enabic operating personnel to perform all requirements for nuclear power plant operation with assistance as nay be required f rom LILCO, CE, S6W, or other consultant and vendor startup engineers and will serve as a transition period between i

the initial training progran and the operation of the plant. Participation in this program will form the initial phase of the licensed operator retraining program, t

13.2.1.2 Tr_aining P_r_ograms for Non-Licensed Personnel Cene ra l Shoreham Nuc1 car Power Station nanagers, engineers, and technicians assigned to non-licensed positions are selected and trained in accordance with ANSI N18.1-1971.

Initial non-licensed staff nenbers participate in the Basic Nuc1 car Course described in 13.2.1.1.1, to a degree comraensurate with their responsibilities, as an introduction to specific discipline training programs. Figure 13.2.1-1 shows the training schedule for non-licensed plant personnel. Specialty training for each non-licensed category i.s described below.

13.2.1.2.1 Training for Instrumentation and Control Personnel 13.2.1.2.1.1 Instrumentation and Control Supervision Supervisors in the Instrumentation and Control Section participate in the following prograns designed to prepare then for a broad range of section responsibilities.

Selection for participation in these programs.is based on supervisory needs in specialty areas.

1. General Electric Nuc1 car Instrumentation Course or equivalent

2. Cencral Electric Process Instrumentation and Control Course or equivalent

3. Vendor supplied specialized equipment training

4. SNPS Familiarization Training The Cencral Electric Nuclear Instrumentation Course is 7 reeks in duration and consists of tuo basic segn-nts; a 2 wmk c1r < room lecture cgment accompanied by equipment decon-strat icas and a S . cca Icborator . . ;'nen t .

-urir g the clacsroom sern ent, the theory of operation and equipment demonstrations for the Ce mlR nuclear, process and

SNPS-1 FSAP 9 area 'radiedion nooitoring, ccntrol rod position information, rod worth minimizer reactcr protection, prinary containmant isolation, and reactor manual control instrumentation systens are presented. The laboratory segment provides students with the opportunity to test, calibrate, and troubleshoot plant specific instru-nents using equipment similar or identical to that used at the SNPS site. Evalua- -

tion of student performance in this course is based on a written examination following the classroom segment, and subjective evaluations by assigned instructors of student skills during the laboratory segment.

The General Electric Process Instrumentation and Control Course is 4 weeks in duration and consists of classroom and laboratory presentations in process theory, analog and digital sensors, signal conditioners, and control loops associated with the SNPS NSSS.

During supporting laboratory sessions students disassemble, inspect, and calibrate plant specific equipnent. Hands-on training in the operation and naintenance of a functional three element control system is also provided. Evaluation of student performance in this course is through use of written and oral examinations.

Vendor supplied specialized equipment training is provided on selected balance of plant systems and components, and on selected NSSS components not included in 1 and 2 above. Exampics of such short duration courses are; Electro-hydraulic Control System (GE), Alterex Excitation System (CE), Computer Hardware Fundamentals (Data General) et. al.. Student performance in the courses listed is evaluated through use of written and oral examinations.

SNPS Familiarization Training consists of a combination of classroom and on-the-job training sessions designed to familiarize personnel with the purpose, major equipment, and importance of plant systems related to the instrumentation and controls area.

Classroom training is administered by the Long Island Lighting Company and is approxi-mately 3-6 weeks in length. Written examinations are used to evaluate student per-formance. On-the-job training is accomplished through participation in the prepara-tion and review of plant instrumentation calibration and surveillance procedures.

13.2.1.2.1.2 Instrumentation and Control Technicians Personnel assigned as Instrunentation and Control Technicians possess a minimum of two (2) years experience, and at least one (1) year of technical training related to instrumentation and control as a prerequisite to their assignment. Following assign-ment, technicians participate in the programs described in 13.2.1.2.1.1 as the needs for additional technical expertise are identified. In cddition to these programs, each technician participates in the I&C Technician Qua:ification Program. This program requires that each technician demonstrate skill and understanding in the following areas:

1. Plant systems related to instrumentation and control

2. SNPS specific instrunentation and control conponents, including control circuits for electrically and pneumatically operated equipment.

3. Station procedures associated with instrumentation and control.

Demonstrat ion of qualification in these areas is documented through completion of

ny of the following-

1. Successful ccmpletion of an approved topic related training course (LILCO or vendor supplied).

SNPS-1 FSAR

2. Observance of satisfactory on-the-job performance by a qualified supervisor.

3. Documented previous experience related to the topic.

Technicians initially assigned will gain additional familiarization with plant systems and equipment through participatica in plant startup and the preoperational test program.

13.2.1.2.1.3 Requali fication Training for Instrumentation and Control Personne' Requalification training for instrumentation and control personnel will consist of refresher training associated uith the General Employee Training Program (13.2.1.3) and self study of the following materials-

1. New or revised SNPS procedures related to instrumentation and control.

2. Descriptions of plant modifications related to instrumentation and control.

3. Event and operating experience reports related to instrunentation and control.

Rcqualification training will exist on a continuous basis and will include the supervisory review of the self study program described above.

13.2.1.2.2 Traininn for Radiochemistry and 1!calth Physics Personnel 13.2.1.2.2.1 Radiochemistry and llealth Physics Supervisors Personnel assigned as supervisors in the Radiochemistry and Health Physics Sections participate in the following prograns designed to prepare then for a broad range of section responsibilities. Selection for participation is based on individual background and expected position assignments:

1. General Electric EWR Chemistry Course or equivalent

2. SNPS Familiarization Training ,

The General Electric LWR Chemistry course is 12 uceks in duration and consists of classroom and laboratory sessions. Students receive instruction and practical ex-perience in the techniques associated with radiochemical and chemical analysis for process control, waste disposal, effluent monitoring, process and laboratory instru-

, ment calibrations and evaluations. Also presented are nethods for compliance with, and interpretation of the chemical and radiochemical aspects of technical specifica-tions, licenses, and plant warranties. Evaluation of student performance is accom-plished through subjective evaluations completed by course instructors.

, SNPS-1 FSAR SNPS Familiarization Training consists of a combination of classroon and on-the-job training sessions designed to familiariac personnel with the purpose, major equip-ment, and ir.portance of plant systems related to the radiochemistry and health physics areas. Classroom training is administered by the Long Island Lighting Company and is approximately 3-6 weeks in length. Written exaninations are used to evaluate student performance. On-the-job training is accomplished through participation in the pre-paration and review of plant radiochemistry and health physics procedures. Successful performance is determined through supervisory review.

13.2.1.2.2.2 Radiochenistry and llealth Physics Technicians

, Technicians specializing in health physics also participate in The Cencral Electric

!!calth Physics Technology Training Course or its equivalent. The IIealth Physics Technology Course is three (3) uceks in duration and consists of classroom and laboratory presentations. Participancs receive instruction in radiation physics fundamentals, radiation detection instrumentation, regulations pertaining to radiation and radioactive materials , biological ef fects, exposure control, dosimetry, environmental monitoring, and monitoring procedures. Written examinations are administered to evaluate student performance.

Technicians specializing in radiochenistry participate in The General Electric BWR Chemistry Technician Training Course or its equivalent. This course is six (6) weeks in duration and consists of classroom and laboratory presentations covering radio-chemical and chemical analysis for process control, waste disposal, ef fluent monitoring, process and laboratory instrument calibrations and evaluation. Uritten examinations are administered to evaluate student performance.

In addition to the programs described, health physics and radiochenistry technicians participate in The 11ealth Physics or RaJiochemistry Technician Qualification Programs.

These programs require that each technician demoastrate skill and understanding in the follouing areas:

1. Plant systems related te health physics (health physics technicians)

2. Plant systems related to radiochemistry (radiochemistry technicians)

3. Station Procedures associated with health physics and radiochemistry Demonstration of quali fication in these areas is documented through completion of any of the following:

1. Successful completion of an approved topic related training course (LILCO or vendor supplied) .

! 2. Observance of satisfactory on-the-job perfornance by supervisory personnel.

3. Documented previous experience related to the topic.

SNPS-1 FSAR Techniciads initially assigned will gain additional familiarization with plant systems and equipment through participation in plant startup and the preoperational test prcgram.

13.2.1.2.2.3 Requalification Training for Radiochemistry and Henith Physics Personnel Requalification training for radiochemistry and health physics personnel will consist of refresher training associated with The General Employee Training Program and supervised review of the following materials:

1. New or revised SNPS procedures related to radiochemistry or health physics.

2. Descriptions of plant modifications related to radiochemistry or health physics

3. Event and operating experience reports related to radiochemistry or health physics Requalification training will exist on a continuous basis and will include supervisory review of the self study program described above.

13.2.1.2.3 Training for Reactor Engineering Personnel All engineers assigned to the Reactor Engineering Section participate in The General Electric Company Station Nuclear Engineering Course or equivalent. The course is 5 weeks in duration and consists of classroom instruction in fuel loading, startup testing, power distribution ccutrol, fuel exposure, isotopic content, cycle length predictions, and discharge requirements. Student performance is evaluated through the administration of mid course and final written examinations.

Reactor engineering personnel responsibic for process computor programming also participate in the Honeywell 4000 User Programming Course or its equivalent. The course is 5 weeks in duration and consists of classroom instruction in assembly language progranning, RTMOS, Fortran IV language, scan, log and alarm programs, and the free time systen. Also presented are 4000 user programming, 4000 system softuare and analysis, and analysis of SEER sof tware. Uritten examinations are used to evaluate student performance.

In addition to the programs described, all reactor engineering personnel participate in SNPS Familiarization Training consisting of a combination of classroom and/or on-the-job training sessions. These sessions are Jesigned to familiarize personnel with the purpose, major equipment , and importance of plant systems related to the reactor engineering area. Classroom training is administered by the Long Island Lighting Company and is approximately 3-6 weeks in length. Written cxaminations are used to evaluate student performance. On-the-job training for the initial staff is accom-plished through participation in the preparation and revieu of plant and system startup test procesures. Successful performance of this assignment is documented through supervisory review.

13.2.1.2.3.1 E cualificnticn Trairinc for P.cartor Farincorine Perronnel Requalification training for reactor engineering personnel will consist of refresher training associated with the General Er.:ployee Training Progran and self study of the following naterials:

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1. New or revised SNPS procedures related to reactor engineering

2. Descriptions of plant modifications related to reactor engineering

3. Event and operating experience reports related to reactor engineering.

Requalification training will exist on a continuous basis and will include the super-visory review of the self study program described above.

13.2.1.2.4 Traininc for Maintenance Personnel Personnel assigned to The Maintenance Section possess a high degree of manual dexterity and ability and are determined to be capabic of learning and applying basic skills in maintenance operations through entry 1cvel testin>;. Personnel assigned to supervisory positions have, as a minimum, threc (3) years experience in one or more crafts. All maintenance personnel participate in the Mechanic Training Progr'an which consists of the following segments:

1. Ibintenance Skills Training

2. Power Plant Training

3. Advanced Mechanic Training The Maintanance Skills Training Course is 12 uccks in duration and consists of class-room and laboratory instruction in basic mechanic skills, shop mathematics, millwright skills, machinist skills, welding skills , and basic electricity. Satisfactory student performance is documented through the administration of oral or uritten examinations, ,

or observance of skills development by a qualified instructor. The Maintenance Skills Training Program is administered by The Long Island Lighting Company.

The Power Plant Training Course is approximately 4 weeks in duration and consists of classroom training in Station procedures related to maintenance, Station administrative policies and documents, and SNPS Systens Familiarization Training. Also provided is on-the-job training which includes the performance of preventive maintenance or maintenance repair on plant systems during the preoperational test program (initial staff only).

Evaluation of participant performance during this segment is through use of either written exaninations, oral examinations, or supervisory observance of satisfactory skills development.

Advanced mechanic training consists of vendor supplied training in the maintenance and repair of particular plant systems and components. Exampics of such short duration courses are; DeLaval Diesel Maintenance, Recirculation Pump Seal Maintenance, Target Rock Relief Valve Maintenance, Control Rod Drive Maintenance, et. al.. Courses range in duration from 1 to 10 days and may be administered by the equipment vendor or qualified Long Island Lighting Company personnel. Student performance in the courses listed may be evaluated through instructor observance of satisfactory skills develop-ment.

13.2.1.2.4.1 Requalification Training for Maintenance Personnel Requalification training for intenance personnel consists of refresher training associated with he C. ecral Enclop ,_ Trnininc Pro;; ram nad periodic supervisory Icd reviews and discussions of the following topics:

1. Scheduled and ccepicted n.aintenance courses

2. Schedulod raint enance (rehearsals)

3. Conpleted caintenance (revieu)

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In addition, all caintenance personnel will participate in a continuing program of scif study of the following naterials:

1. New or revised SNPS procedures related to naintenance

2. Descriptions of plant nodifications related to maintenance

3. Event and experience reports related to naintenance Requalification training exists on a continuous basis and includes supervisory review of the program components described above.

13.2.1.2.5 Training for Fire Protection Staff Members Personnel responsibic for the implenentation of the Station Fire Protection Program will receive Fire Brigade Training (as described in Section 13.2.1.2.6 below) and Fire Protection Technology Training. Both programs will be taught by plant training staf f with assistance f ron suitable vendors. Fire Protection Technology Trcining will include the following topics:

1. Station building layout and fire protection system design.

2. Design of and naintenance on fire detection, suppression, and extinguishing equipment.

3. Fire prevention techniques and procedures.

13.2.1.2.6 Training for Fire Bricade Members Personnel who eake up the Station Fire Brincde will be trained via a program of classroon instruction, practice sessions, and drills. The classroom phase will be taught by plant training staff in conjunction with Suffolk County Fire Training Center and suitabic vendors and will include the following topics:

1. Fire hazard identification by location and fire. type, including locations where breathing apparatus is required.

2. Familiarization with plant layout, including routes for ingress '

and egress as well as locations of all fixed and portabic fire fighting equipment. ,

3. Methods and equipment appropriate to each type of fire, including electrical fires, cabic and cabic tray fires, hydrogen fires, flannable liquid fires, waste / debris fires, and record file fires.

4. Indoctrination in the Plant Fire Protection Program.

5. Proper use of respiratory protection, communication, ligh ting ,

and portabic ventilation equipnent.

6. Review of the plant Pre-fire Plans.

7. Review of pertinent nodifications, additions, or changes to the Plant Fire Protection Plan or fire fighting equipment.

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6. Methods for fighting fires in buildings or tunnels.

, 9. Toxic and corrosive characteristics of expected combustion products.

10. Station evacuation signals and routes.

Practice sessions will be held at the Suffolk County Fire Training Center and will allow-Fire Brigade menbers to train on actual fires. Each Fire Brigade nenber will attend at 1 cast one practice session per year and will don protective equipment (including respiratory protection) at lease once per year.

Drills will be v.rformed c at least once per three conths for each Fire Brigade,,with each Fire Brigade member attending a nininum of two drills per year. At least one of these drills per year, per Fire Brigade, will be unannounced. At 1 cast one of these drills per year per Fire Brigade, will be on a backshift. At 1 cast one drill per year will involve the participation of the Wading River Fire Departnent onsite.

All drills will be preplanned and critiqued, with unsatisfactory drills repeated within thirty days.

13.2.1.2.7 Fire Brigade Chief Training Candidates for the position of Fire Brigade Chief will receive appropriate training.

This training will include Fire Brigade Training (as described in Section 13.2.1.2.6),

and Fire Brigade Leadership Training, designed to teach direction and coordination of fire fighting activities. Both programs will be taught by plant training staff with assistance from suitable vendors.

13.2.1.2.8 shif t Technical Advisor Training Personnel assigned as Shift Technical Advisors participate in an integrated program of theoretical and practical instruction. The components of this program are the following:

1. Basic theory

- 2. Plant specific theoretical training

3. Plant systens/ procedures training

4. Plant accident / transient analysis training

5. Mitigating core damage training

6. Management / Supervisory skills training The Basic theory training segment consists of university level course work presented by the Polytechnic Institute of "ev York or similar accredited institutions. Courses are offered on the graduate level and are presented to those candidates uho have not received previous university level instruction related to the following topics:

1. Basic far.denantals of nuclear and reactor engineering

2. Radiation protection

3. Th e rnodynamic s

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4. Heat transfer

5. Principles of fluid mechanics Courses are presented in a classroom instructional format with written examinations used to measure student performance.

Plant specific theoretical training is provided in the form of The General Electric Scation Nuclear Engineer Training Course. The course is 5 weeks in duration and consists of classroom instruction in fuel loading, startup testing, power distribu-tion control, fuel exposure, isotopic content, cycle length predictions and discharge requirements. Student performance is evaluated through the administration of mid course and final written examinations.

Plnnt systens/ procedures training consists of classroom instruction in SNPS specific systems and procedures. Included as instructional topics are:

1. Nuclear Steam Supply Systems and their operation

2. L'n'R steam cycle systcas and their operation 4

3. Station general operating procedures

4. Station general administrative procedures The course is 8 weeks in duration, is administered by SNPS personnel and uses periodic written examinations as the means for evaluating student performance.

Shif t Technical Advisor candidates are provided with accident / transient analysis training through participation in a 4 week sinulator training course. The initial course is provided by the General Physics Corporation utilizing the Limerick Simulator Facility. Basic plant operations including plant startup and shutdown will be denonstrated. In addition, Shift Technical Advisor candidates will observe various plant accident and transient scenarios concurrently with the examination of the technical aspects of each event in the classroon. Evaluation of student performance will be accomplished through the administration of written and oral excminations.

Training in methods for mitigating core damage for Shift Technical Advisors is de-scribed in section 13.2.1.2.9.

Each Shift Technical Advisor candidate will participate in a one week management /

supervisory skills course presented by the Long Island Lighting Company or qualified vendor. The course vill include training in techniques associated with leadership, motivation, problem solving, decision making, and organizational management under stress.

Evaluation of studeat performance in this course will be accomplished through the administration of written and/or oral examinations.

13.2.1.2.8.1 Shift Technical Advisor Requalification Training The Shif t Technical Advisor Requalification Training Program is two (2) weeks in duration and is administered annually by the Long Island Lighting Company or qualified vendor. The program consists of a one week clarsroom segment and a one week sir:ulator scrent. The classroom te m at includes presentations related to the follou'ing topics :

1. A review of plant transient and accident analysis caphasizing the Shift Technical Advisor's role in accident assessnent

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2. A review of plant related industry and license event reports

, 3. A revieu of major plant modifications and procedure changes affecting the Shift Technical Advisor po:ition.

The simulator training segnent will consist of control nanipulations and observance of plant transient / accident response. The siculator training segment will be con-ducted on 1he Limerick simulator or an equivalent facility.

5 t.'ritten examinations will be administered annually to provide a basis for deterraining Shif t Technical Advisor knowlc ige and to assist in defining topics for which additional training'is required.

t 13.2.1.2.9 Training for Mitigatine Core Damate lhe Mitigating Core Damage Training Program provides Shif t Technical Advisors and operating personnel from the Plant Manager through the operations chain to licensed operators, instruction related to degraded core recognition and methods for recovery from the degraded core condition. Managers and technicians in the instrumentation and control, health physics, and radiochemistry sections vill participate in the progran to a degree commensurate uith their responsibilities. The course is one week in duration and is administercJ by the Long Island Lighting Company, The General Electric Company, or other qualified organizations. The course serves to draw to-gether specific concepts and is considered the second phase of a tuo phase program.

1he first phase consists of participation in selected porticas of those prograns thich constitute the Licensed Operator Training Program (13.2.1.1). The following course components are included:

1. Core cooling nechanics/ accident re c ogn it ion : topics included are; adequa

• core cooling, heat sources, core cooling mechanisms, and inadequace core cooling recognition.

2. Core damage mitigation: topics included are; fixed /novabic nuclear instrument use, degraded core effects on coolant chenistry, process in s t runent response, corrosion effects, gas generation sources, and accident environment dose determina-tion.

3. Core transient identification and damage mitigation through use of emergency procedure guidelines.

The course is adninistered in a standard classroom format accompanied by instructor guided procedural walk-throughs. Evaluation of student performance is acconplished through adninistration of written examinations and instructor evaluation of student use of procedural guidelines.

13.2.1.2.10 Training for Support Engineering Personnel Support engineering personnel are assigned based on previous academic training and experience related to the assignment. Foll- lag assignment, personnel participate in the following additieaal prograns to a di arce commensurate with responsibility.

1. General uplayce Training (whcn assigned to the plant site)

2. Plant systems familiariaation training

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SNPS-1 PSAR The General Employee Training Progran is described in section 13.2.1.3.

Plant systens faniliarization training for support engineering personnel is accorplished through participation in selected portions of the licensed operator training program (13.2.1.1.5), or the Shift Technical Advisor Training Progran

(13.2.1.8) assoc:sted with plant systens. The degree of participation in thesc classroom programs is based on the systens familiarization need: of each individual to complete particular job assignments.

13.2.1.2.10.1 Roaualification Trainine for Sunnort Encineering Personnel Requalification training for support engineering personnel will consist of refresher training associated with the General Employee Training Program (13.2.1.3) and self study of the following materials :

1. New or revised SNPS procedures related to Support Engineering Staff assignments or responsibilities

2. Descriptions of plant nodifications requiring review by the Support Engineering Staff

3. Event and operating experience reports requiring review by the Support Engineering Staff Pequalification training will exist on a continuous basis and will include supervisory review of the self-study progran described above.

13.2.1.3 General Enployee Traininc ,

The SNPS General Employee Training Progran provides general plant and Station orienta-tion in formation to Long Island Lighting Coupany employees (peraanent and temporary),

contracted employees, and visitors, so that they are abic to complete a wide range of general tasks in a safe and conpetent nanner. The Ganeral Fnployee Training Progran is divided into three categories to best fit the needs of all personnel assigned to the Shorehan Nuclear Power Station. These categories are:

1. Permanent station personnel

2. Temporary station personnel -

3. Contracted personnel l

l Each listed category participates in the General Employee Training to the extent warranted by position or assignment. The complete program includes the following topics:

1. General description of the station and facilities i

2. Station Security Progran and procedures

3. Station Fire Protection Program, including evacuation routes and signal::, firr ;nd firo acard repar.ing, and basic fire

( fightino equiprcat.

i

( 4. Rad'ological h. -ith and safet y including applicabic portions of 10urt 19 and 10cFE 20

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5. Quality assurance

, 6. Industrial health and safety

7. Station caergency plan and implementing procedures The General Employec Training Program is presented in modular fcrm by Long Island

' Lighting Conpany personnel. Each module consists of video tape / slide or live instruction presentations related to cach listed topic. Instructor led discussions follow each topic presentation to clarify areas of difficulty. Student performance is documented through administration of a written examination covering applicabic topics. Personnel permanently assigned to the Shoreham Nuclear Power Station who require unescorted access to all Station areas, participate in General Employee Training which includes all topics. Personnel permanently assigned to the Shorcham Power Station whose wor % assignments involve admittance to Station administration buildings only, participate in the program to the extent necessary to assure safe execution of their duties.

Long Island Lighting Company Personnel temporarily assigned but requiring unescorted access to all Station areas participate in all topics of the General Employee Training Program. Temporarily assigned personnel whose work assignment involves admittance to Station administration buildings only, participate in the program to the extent necessary to assure safe execution of their dutics.

Contracted personnel assigned to the Shoreham Nuclear Power Station requiring unescorted access to all Station areas, participate in all topics of the General Employee Training Program. Contracted employees whose work assignments involve admittance to Station administration buildings only, participate in the program to the extent necessary to assure safe execution of their dutics. Contracted personnel who will be continuously escorted by qualified Station personnel while working within the Station boundary for short periods of time, will not be required to participate in the General Employee Training Program.

13.2.1.3.1 Security Personnel Fire Protection Training In addition to training required to carry out their normal tasks, security personnel will be trained in the following areas related to the Station Fire Protection Program:

1. Entry procedures for Uading River Fire Department

2. Crowd Control (exiting personnel during an evacuation).

3. Fire llazard reporting.

13.2.1.3.2 Wading River Fire Department Personnel Training The Wading River Fire Department may be called in to assist the SNPS fire brigade in an emergency. In order that Fire Department personnel may safely carry out their tasks, they will be trained in the following arcas:

1. Site security entr:. and exit procedure

2. U alth ;hysics (basic radi.: tion principles and pr'actices and typical radiation hacards).

3. Station 1,yout f -i!!arit ,t ion.

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4. Station fir'e fighting procedures applicable to the Wading River Fire Department.

This training will be performed under the direction of the plant training staff.

In addition to the above training, one station fire drill per year will involve assistance from the Uading River Fire Departcent.

13.2.1.3.3 Ceneral Employee Refresher Training Personnel uho receive instruction in the following General Employee Training Program topics, receive repeat instruction and are examined on these topics annually as part of the refresher training program:

1. Radiological health and safety including applicable portions of 10CFR 19 and 10CFR 20

2. Station energency plan and implementing procedures

3. Station Fire Protection Program including evacuation routes and signals, fire and fire hazard reporting, and basic fire fighting equipment.

13.2.2 Licensed Personnel Requalification A continuing requalification program for licensed operators and senior operators will be established and implemented, in accordance with 10CFR55, Appendix A, for Shoreham Nec1 car Power Station not later than three months following the issuance of an operating license for the station.

Licensed operators and senior operators will participate in the requalification program as described in Sections 13.2.2.1 and 13.2.2.2.

Licensed senior operators limited to fuel handling vill participate in the re-qualification program as described in Section 13.2.2.1, in those areas applic-abic to the technical requirements of their license as der.cribed in Section 13.2.1.1 items 13 through 17, uith the exception of Sectiens 13.2.2.1.2 and 13.2.2.1.6; and as described in Section 13.2.2.2.

The requalification program cycle shall be based on a tuo year period with training distributed over that period as required.

Plant Staff personnel whose normal dutics are at the station on a day-to-day basis and who hold a license to provide backup capability for the operating staff will participate in the requalification program except to the extent that their normal duties preclude the need for retraining in specific areas.

As a minimum they shall:

1. De administered the annual requalification exam and participate in the requalification lecture series based upon results of the annual requali fication em a :ation.

2. Perform reactivity centrol anipulatiens as specified in Section 13.2.2.1.2.

3. Review chan"es to stctien d:cirn, precedures and license as specified id S.ction 13.2.2.1.4.

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4. Review station abnormal and evere ency procedures as specified in Section 13.2.2.1.5.

5. Be evaluated at least once during the term of the license by oral examination.

13.2.2.1 Program Description 13.2.2.1.1 Program Content A planned lecture series will be presented covering, as a minimum, those areas where written examinations indicate the need for additional training in the following subjects:

1. Theory and principles of operation,

2. General and specific plant operating characteristics,

3. Plant instrumentatica and control systems,

4. Plant protection systems,

5. Engineered safety systems,

6. Normal, abnormal, and emergency operating procedures,

7. Radiation control and safety,

8. Technical specifications,

9. Applicable portions of 10CFR, Chapter I, and

10. Station QA progran as related to station operations.

The lecture series will be presented primarily by Shoreham Station personnel with some assistance by others, either live or on videotape or film. Video-tape or film presentations shall be used for not more than 50 percent of the lecture series. The lecture series will, with the except. ion of special acti-vity periods such as refueling outages or heavy vacation periods, be distri-i buted throughout each 2 year retraining program. Lectures uay be deferred due to unanticipated shutdown uith provisions being made for conducting de-

! ferred lectures at a later date. A minimum of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of preplanned lectures l

will be scheduled each year. '

l 13.2.2.1.2 Reactivity Control Manipulations Each licensed operator will, during the term of his license, perform a mini-l mum of 10 reactivity control manipulations in any combination of reactor start-I ups, reactor shutdoens or other control manipulations which deuonstrate his l skill and/or familiarity with reactivity control systems. Each licensed senior operator vill either nanipulate the controls or direct the activities of others during 10 reactivit; eentrol . :ipulations. R m e,able effort consirtent with

[ the operating requircrm ts of d ;tatiu ' rill be mie to provide a variety of l

reactivity changcu for each operator.

Control nanipulations chich rect the requirer.ent s of ene or any cerbination of the follouing are considertd v acceptable re act ivit y centrol ranipulations:

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. Any plant or reactor startup, to include a range such that re-activity feedback f rom heat addition is noticeabic.

i 2. Any temperature chaage, heatup or cooldown, >100 F

3. Plant or reactor shutdown

4. Plant shutdown to reactor hot standby

5. Control rod sequence changes

6. Shutdown margin checks

7. Control rod scram insertion tine tests S. Any reactor pouer change of 10 percent or greater including testing of equipment where load changes are performed with control rods, the " load selector" of the E!!C system or where the recirculation systen is in nanual speed control.

9. Plant and reactor operation that involves emergency or trans-icnt procedures where reactivity is changing.

10. Refueling operations chere fuel is coved within the core.

If necessary to provide a mininum of 10 reactivity control manipulations or a reasonabic diversity in reactivity control manipulations, an appropriate simulator nay be used to ncet the reactivity control nanipulation require-ments of the requalification program.

13.2.2.1.3 Station Design Features -

Each licensed operator or senior operator, or senior operator limited to fuel handling, will demonstrate in the performance of his duties, satisfactory understanding of the operation of systens , components, and other apparatus in I areas for which he has been licensed; and his knowledge of operating procedures pertaining to those systems or components.

l 13.2.2.1.4 Station Desinn, Procedure, and Facility Changes Each licensed operator, senior operator or senior operator limited to fuel handling will be kept advised of station design changes, proccdure changes, and station license changes appropriate to the technical requirements of an individual's license as defined in Section 13.2.1.1. To insure the individual's cognizance of such changes, any of the following methods of communication cay be utilized:

1. Brief lectures conducted by the Watch Engineers.

l 2. Staff or section meetings.

3. Uritten cor unications to each liensed individual.

4. Preplanned itcrure :,e r i e s .

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SNPS-1 FSAR 13.2.2.1.5 [@nornal and Emercency Procedure Review Each licensed operator or senior operator will review the abnormal and emergency operating prceedures on an annual basis. To ensure the indi-vidual's review of these procedures, any of the following motheds may be utilized:

1. Actual performance under abnormal or emergency operating conditions.

2. Simulated walk-through of the procedural steps necessary to cope with the sitration.

3. Brief Icetures conducted by the Watch Engineer.

4. Drills utilizing a simulator.

5. Preplanned lecture series.

6. Self study.

13.2.2.1.6 Fequalification of Inactive Licensed Operators and Senior Operators Licensed operators or senior operators whose normal duties are at the station on a day-to-day basis and who are involved in the daily activi-ties at the station will be considered on " active status".

A licensed operator or senior operator who has been inactive for four or more nonths vill, before resuming licensed activities, demonstrate adequate knowledge of current station operations. This demonstration will be accom-plished by satisfactory completion of a written examination and/or oral ex-amination given by a qualified member of station management.

An unsatisfactory result in one or both of these exaninations uill require that the individual receive additional training in areas of weakness and/or obcerve station operations for a minimum of 40 hrs prior to re-exa:aina t ion . The nature of the additional training provided will be deter-mined based on the initial requalification examination results. .

13.2.2.2 Requalification Evaluation of Operators and Senior Operators 13.2.2.2.1 Annual Requalification Examinations Annually, written requalification examinations will be given to all licensed operators, senior operators, and senior operators limited to fuel handling, to dete rmine areas in which retraining may be needed to maintain or upgrade licenced operator or senior operator knowledge. Th is examination may be administered as two annual examinations to be given within a three month period. If the examination is administered in two parts, the annual grade will be the average of the two quarterly grades. These exaninaticas may be prepared and evaluated by ?ither Share :n personnel or an outside o r c an i ~.a -

tion. A r.i n i:.;um g rada o f RJ xc 't cer: at . . xtica will c: pt r.n opera-tor or senior operator from required attendance at requali fication lectures per-tinent to that section. One licenced individual rho is directly involved in the preparation and grading of the exan m,y be exenpt fren t Aing the exan.

1 1

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. o 13.2.2.2.2 petraining Program Examinations Written examinations will be given covering material presented in the retraining program. These examinations will provide the basis for evaluating knowledge of emergency operating procedures, and will be prepared and evaluated by members of the Shorehaa Station staff cr other persons who are knowledgeabic in the material and its presentation in the requalification program.

A grade of less than 80 percent correct on any lecture series examination shall require an operator or senior operator to be rescheduled for Icetures on that subject the next time such lectures are scheduled.

13.2.2.2.3 Practical Operator Performance Evaluation Annually, the performance of licensed operators and senior operators will be evaluated and documented by supervisors and/or training staff members. An oral examination will be administered at least once during each two year qualifica-tion prior to operators, senior operators and senior operators 'imited to fuel handling and will include evaluation of actions taken or to be taken during actual or simulated abnormal and emergency conditions.

1his oral examination may constitute one of, or be in addition to, the annual practical operator performance examination. The Shoreham Station control room panels may be utilized to accomplish the simulation of these conditions or an appropriate simulator nay be used to meet this requirenent.

When the Shoreham Station control room facilities are utilized for these simula-tions, the actions taken, or to be takcn, for the condition under simulation will be discussed. If an appropriate simulator is used, the simulator will reproduce the operating characteristics of the Shoreham Plant. ihe instrucentation and controls of the simulator utilized will closely parallel those of the Shoreham Station.

13.2.2.2.4 Accelerated Requalification Program An accelerated requalification program will be provided for those individuals who do not perform satisfactorily on their annual requalification examination. Any operator or senior operator who receives an average grade of less than 70 percent on an annual written rcqualification examination will be examined orally by a -

qualified member of station management to determine whether or not the individual can safely continue practicing his licensed duties. This oral examination will be administered within 14 days of the determination that the operator or senior operator has received a grade of less than 70 percent. An individual demonstrat-ing on the oral examination that he can operate the plant safely will be permitted i to continue performing licensed duties uhile participating in an accelerated re-

! qualification program. An individual who does not demonstrate on the oral examination that he can operate the plant safely will be relieved of all dutics requiring the use of his license and will participate in an accelerated requalification program. An operator who is relieved of his licensed duties will be so advised by station manage-ment. lie may return to his licensed duties following attainment' of an average grade of 70 percent or greater on a uritten quali fication examination of the same format as the annual re,u lification namination.

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. e Training provided to operators or senior operators participating in an accelerated requalification program cay include preplanned lectures, self study, on the job instruction, or other training as required.

13.2.2.2.5 Requalification Exats Formats

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There will be three separate requalification exams administered as follows:

Reactor Operator - this exam vill be adminictered to holders of NRC Reactor Operator Licenses and will contain questions in the follouing categories:

1. Principles of Reactor Operation This category contains questions relating to basic nuclear reactor behavior, elementary nuclear reactor theory, techni-cal terninology and an appreciation of processes taking place in a reactor.

2. Features of Facility Desien This category contains questions about the design features of the particular f acility, ':ith cnphasi s on the reactor and auxiliary systems. It also inquires into design in-tent and the more itapo rtan t design paraneters.

3. General Operating Characterictics This category contains questions on controlled and variabic parame te rs of the reactor and auxiliary systetas. Values which are expressed as norcal or operating para:..eters or values which are measured as resultant characteristics (e.g., temperature coe f ficient , reactivity worth, pressure drop) are investigated in this category. Questions relating to the nanner in which power, reactivity, rod worths, or other paraneters of this facility would change in response to rod mani-pulations, heatup, core burnup, experinent insertion, or other stinuli are also in this category. Further included are questions relating to the traces that one would see on recorders, with the emphasis of the question of f acility behavior rather than instru- .

ment characteristics.

4. Instruments and controls This category contains questions on the characteristics and interrelationships of the nuclear and process instrumentation and control systens. These questions vill inquire into the principles of operatien of detectors, location and settings of instruments, diagrammatic representation of instrument and control systems, and details of control red drive design and operation.

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. D ,

S. Safety and Emergency Systens This category contains questions on the design, construction, operation, and interrelationships of the systens nost directly associated with reactor safety, such as scram and other power reduction systems, pressure relief, suppression and containment, poison systems, spray systems, emergency power systems, and annun-ciated malfuncticas.

6. Standard and Emergency Operatine Procedures This category contains questions on the procedures for the operation of the reactor and auxiliary systens, including administrative controls. Op~c rating restrictions in the facil-ity license may be included herein, to the extent they are directly applicable to an operator.

7. Radiation Control and Safety This category contains questici.s on terminology, radiation hazards, radiological safety practices and fixed and portable radiation nonitoring equipment.

Senior Reactor Operator - this exam will be administered to holders o1 NRC Senior Peactor Operator Licenses and will contain questions in the following ca t ego rie s :

8. Reactor Theory This category contains questions on princip1cs of reactor theory including details of the fission precess, neutron nultiplication, source and control rod effects and critically indications. It has more advanced content than the operator Category 1 but is not advanced to the level of a nuclear physicist or engineer.

Further, this category may contain questions, as applicable to the facility, concerning some aspects of basic reactor engineer-ing, e.g., heat transfer and fluid flow which affect the safety of the reactor core and vessel.

9. Radioactive Material Handling, Disposal, and Hazards This category contains questions on radiation hazards which nay*

arise during operating or the performance of experinents, shield-ing alterations, or maintenance activities. Close familiarity with the provisions of 10CFR Part 20 and supplementary facility regulations is required as well as a good common sense approach to radiological safety situations. Questions may include calcu-lations involving inverse square law, decay rates, half-value thicknesses, and conversions of measured radiation intensities to rem, as well as other calculations of a similar nature.

Also included are questiens relat'ng to procedures and equipment (processing c ad * ,nitorinn) avcilable for handling and disposal of radioactive ia.terials e,nd effluents.

SNPS-1 FSAR

• 10." _Syecific Operating Characteristics This category contains questions on specific operating characteristics of the reactor and auxilia:y sys tems, including nuclear, hydraulic, thermal, pneumatic, electrical, and cooland chemistry. Questions re-garding quantitative as well as qualitative explanations of causes, limitations, ef fects, and consequences of changes are included.

11. Fuel Handling and Core Parameters This category contains questions regarding fuel, fuel handling and core loading, including procedures and limitations concerning core -

loading and alteration, fuel transfer and storage, and detection and prevention of criticality. Questions relating to inc1 element characteristics and limitations include consideration of reactivity worths, burnup, hot spots, rupture detection, ef fects of boiling, and programming.

12. Administrative Procedures, Conditions, and Limitations This category contains questions on administrative, procedural and regulatory items which affect operation of the facility.

Restricted Senior Peactor Operator - this exam will be administered to holders of liRC Senior Operator limited to fuel handling and will be limited to questions in the following categories:

13. Reactor and Fur i Characteristics

14. Equipment, Instrumentation, and Design Description This category will contain questions sinilar to Categorics 2, 3 and 4 (above), but will be limited to areas that are directly related to refueling operations.

15. Procedures and Limitations This category will contain questions similar to Category 12 (above) but vill be limited to those areas that are directly related to fuel handling operations.

16. Emergency Systems and Safety Devices This category will contain questions similar to Category 5 (aboss) but will be limited to areas that are directly related to fuel handling.

17. Health Physics and Radiation Protection This category will contain questions similar to Category 7 (above),

but will be limited to areas that are directly related to fuel handling operations. .

OF

SNPS-1 FSAR 13.2.2.3' Requalificat ion Training _ Records Records of the requalification pregram will be maintained to document the participa-tion of each licensed cpcrator n.d senicr operator in the requalification program.

1hese records will contain: ,

1. Copics of uritten examinations administered.

2. Answers given by the licensee to written examinations

3. Results of performance evaluations

4. Documentation of additional training administered to operators and senior opccators in areas Where deficiencies have been demonstrated.

5. Records of attendance at preplanned lectures.

6. Documentation of operator and senior operator cognizance of changes made to station design; appropriate procedures', and the station license.

7. Documentation of operator and senior operator review of abnormal and emergency procedures.

8. Documentation of operator and senior operator participation in reactivity control manipulations.

13.2.3 Non-Licensed Personnel Requalification The requalification programs for Station non-licensed personnel are described in Sections 13.2.1.2 and 13.2.1.3.

13.2.4 Replacement Training The purpose of the Shoreham Guelear Power Station replacement ttaining progran is to ensure that replacement personnel satisfy the training requirements stipulated in ANSI N-18.1, 1971 for the various plant positions.

13.2.4.1 Licensed Personnel Peplacement Personnel who have satisfactorily completed a reactor operator selection program and uho are designated as "in training" for a reactor operator or senior reactor operator license will be given formal technical training and practical on the job training.

13.2.4.1.1 Replacement Personnel Technical Trainiac Formal technical training for reactor operator license candidates will be given

! in the following areas:

1. Princip1cs of reactor operatien.

2. Dasign features of the Shoreham Nuclear Power Station.

3. General eperating characteristics of the Shortham ::uclear Power Station.

SNPS-1 FSAR .

. +

4. Instrument and control systems. .

5. Safety and emergency systems.

6. Normal and emergency operating procedures.

7. Radiation control and safety provisions /

In addition to the above areas, formal technical training for senior reactor operator license candidates will be given in the following areas:

8. Reactor theory.

9. Handling and disposal of, and hazards associated with, radioactive materials.

10. Specific operating characteristics of the Shoreham Nuclear Power Station.

11. Fuel handling and core parameters.

12. Administrative procedures, conditions, and limitations.

Reactor Operator and Senior Reactor Operator candidates who have not had previous nuclear training or operating experience at a reactor facility, as outlined in ANSI 18.1, 1971 Sect ion 5.2.1, will receive formal technical training in the follow-ing areas:

1. Basic Nucicar - equivalent to the Basic Nuc1 car Course conducted for initial training.

2. Onsite Training of Shoreham Nuclear Power Station systems and procc-dures - equivalent to initial staff Onsite Training Program.

3. License Study Time - three to four veeks - supervised study program prior to license examination.

13.2.4.1.2 Feplacement Personnel Practical Reactor Operation Training Comprehensive, practical on the job training for reactor operator and senior reactor operator candidates will include the follot.ing areas:

1. Performance of at least two reactor startups conducted at SNPS-1 or an approved simulator facility prior to the demonstrative portion of the license examination under the direction of appropriate licensed personnel, fo11 cued by a startup or simulated startup of the reactor as part of the operating test; or

2. Manipulation of the controls of the SNPS reactor facility during five significant reactivity changes, as described in Section 13.2.2.1.2, hich may or aay not include reactor startups; and rarticipation in en approv. d .": C nuel s a r -m 7r plant 'inulator t: :in c' proaran with subsequent certification frc ,the simulator training center; and

SNPS-1 FSAR ,

. +

3. Instruction on the appropriate lay to day station administrative activities and procedures. Re _eipt of such instruction will be documented in the traince's training folder; and

4. Thorough self study program under the guidance of more experienced station personnel to facilitate the candidate's knowledge and under-standing of plant operating characteristics and station operating and emergency procedures. A minimum of four vecks will be designated for the scif study pregram. Completion of the self study program vill be documented in the traince's training folder.

13.2.4.2 Restricted Licensed Personnel Replacement Personnel who are designated as "in training" for a restricted (fuel handling) license will be given formal technical training and practical on the job training.

13.2.4.2.1 Replacemen t Personnel Technical Training Formal technical training for all restricted licensed replacement candidates will be given in the following areas:

1. Radiation control and safety provisions.

2. llandling and disposal of, and hazards associated with, radioactive materials.

3. Fuel handling and core parameters.

4. Administrative procedures, conditions, and limitations.

5. Onsite training of Shorehan Nuclear Power Station systems and pro-cedures. Selected portions of this program will be given as required.

Those portions selected will be equivalent to that given to initial restricted licenced candidates.

In addition, candidates for restricted (fuel handling) licenses who have not had previous nuclear training will recieve the following:

1. Basic Nuclear - equivalent. to that given for Reactor Operator and Senior Reactor Operator replacement candidates.

13.2.4.2.2 Replacement Personnel Practical Fuel Handling Training Each restricted licensed candidate will have conprehensive, practical on the job training in the following areas:

1. Manipulation of SNPS fuel handling equipment, including periodic surveillance testing, using real or simulated fuel.

2. Participation in an actual refueling outage either at SNPS or a cinilar L m.

SNPS-1 FSAR

3. Instruction on the appropriate day to day station administrative activities and procedures. Receipt of such instruction will be documented in the trainee's training folder; and

4. Thorough scif study program under the guidance of more experienced station personnel to facilitate the -andidate's knowledge and under-standing of plant operating characteristics and station operating and emergency procedures. A minimum of four weeks will be designated for the self study program. Completion of the self study program will be documented in the trainec's training folder.

13.2.4.2 Restricted Licensed Personnel Replacement Personnel who are designated as "in training" for a restricted (fuel handling) license will be given formal technical training and practical on the job training.

13.2.4.2.1 Replacement Personnel Technical Training Formal technical training for all restricted licensed replacement candidates uill be given in the following areas:

1. Radiation control and safety provisions.

2. 11andling and disposal of, and hazards associated with, radioactive materials.

. 3. Fuel handling and core parameters.

4. Administrative procedures, conditions, and limitations.

5. Onsite training of Shorehcm Nuclear Pe mr Station systems and pro-cedures. Selected portions of this program vill be given as required.

Those portions selected will be ccuivalent to that given to initial re-stricted licensed candidates.

In addition, candidates for restricted (fuel handling) licenses who have not had previous nuclear training vill receive the follouing:

1. r>asic Nuclear - 12 to 16 veeks - equivalent to that given for Reactor

• Operator and Senior Reactor Operator replacement candidates.

13.2.4.2.2 Replacement Personnel Practical Fuel 1?andling Training Each restricted licensed candidate will have comprehensive, practical on the job training in the following areas:

1. Manipulation of SNPS fuel handling equipment, including periodic surveillance testing, using real or simulated fuel.

2. Participation in an actual refueling outage either at SNPS or a sinilar TA'R.

,7

SNPS-1 FSAR

3. Instruction on the appropriate refueling and station emergency procedures, kcceipt of such instructions will be documented in the trainee's training folder.

13 .2 .4 . 3 Non-Licensed Personnel Replacement Personnel filling positions not requiring an NRC operator or senior operator license shall meet the requirements stipulated in Section 13.1.3.1 and will receive training as outlined h1 Section 13.2.1.2.

13.2.5 Corporate Training Responsibility - Nuclear Each department of the Long Island Lighting Company which performs or provides support for safety-related activities in support of Shoreham plant operation, is responsible to provide adequate training for their personnel in accordance with the support function

[erformed. Individual departments are responsible to develop and administer training programs for their personnel, and to maintain training records and documentation.

The overall coordination and evaluation of the Long Island Lighting Company Corporate ruclear training program is the responsibility of the Ibnager, Nuclear Operations Support Department. Direct responsibility for coordination of the corporate nuclear training program and monitoring its ef fectiveness is delegated to the Nuclear Training C oordinator under the direction of the Nuclear Services Supervisor.

13.2.5.1 Corporate Nuclear Trainine Administrator The Corporate Nuclear Training Coordinator assumes the following responsibilities:

1. Develop the policy for corporate nuclear training and establish standards for each department to utilize for development of department training programs.

2. Provide assistance to company departments as requested to develop nuclear training programs.

3. Monitor, evaluate, and recommend improvements to nuclear training programs conducted by and for ccapany departments.

4. Provide coordination and interface for interdepartmental nucicar training programs. -

5. Audit department nuclear training records and documentation.

6. Audit the training qualifications / programs of consultant personnel performing work in support of nuclear plant operation.

The development of Corporate nuclear training programs is undertaken using subj ect matter and program content input from throughout the Long Island Lighting Company.

13.2.6 Station Training Responsibility The overall conduct and administration of the SNPS Training Program is the responsi-a b il i t:, of the plant Manager. Direct responsibilit, for administration of the train-ing program and monitoring its ef f ectiveness is delegated to the Station Training Section under the direction of the Station Training Supervisor.

SNPS-1 FSAR .

13.'2.6.I station Training Section Or:;anization and Responsibilities The Station Training Section consists of the Station Training Supervisor; specialists in the areas of licensed personnel training, non-licensed personnel training, and Station support training; and an administrative and clerical support staff. The Station Training Section assumes the following respc.nsibilities:

1. Development, implementation, and irprovement of Station li.cnscd personnel training and requalification training programs.

2. Development, impicnentation and improvement of Station non-licensed personnel training and requalification training programs.

3. Development. implementation, and improverent of the Station General Employee Training Program.

4. Maintenance of all Station training records.

5. Evaluation and counseling of Station training program participants.

The development of Training progroms by the Station Training Section is undertaken using subject natter and program content input from Station section supervisory personnel.

13.2. Training Records Records docur.enting the qualification, training, and retraining of all Station staff personnel (licensed and non-licensed) vill he maintained in accordance with the following:

1. A :SI I:45. 2. 9 - 1974 -

2. A!;SI N28.1 - 1971

3. 10 CFR 50 Appendix A Station staf f trair.ing records will be naintained by the Station Training Section l under the direction of the Station Training Supervisor. Records will be kept in order to document the training history of both licenced and nca-licensed personnel and programs. Licensed personnel records kept will include the following:

1. Current resume of qualifications and experience

2. Licenses

3. Certified history of Station training received l

4. Requalification training documents according to 10CFR 50, Appendix A l Non-licensed personnel records kept will include:

1. Currcut re: t:ne c f quali ficatious and c:q erience i

l i 2. Certified history of Station training received

S:;PS-1 FSAR Licensed and non-licensed program records will include those naterials required to support the administration and completion docuncatation of each program.

Training records will be used to nonitor the effectiveness of Station tralaing prograns and will be periodically reviewed by the Station Trcining Supervisor and quality assurance personnel.

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SNPS-1 FSAR 13.4 RE'lIC.! AND AUDIT A review and audit program, including inplant and independent reviews, has been developed to provide a system to determine that plant design, construction, startup, and operation are consistent with company policy and rules, approved procedures, and license provisions; to review important proposed plant changes, tests, experiments, and procedures; to assure that unusual events are promptly investigated and corrected in a canner which reduces the probability of recurrence of such events; and to detect trends which may not be apparent to a day to day observer. For convenience of administration of the program, the review and audit program is divided into the construction phase and the operation phase.

13.4.1 Review And Audit - Construction Review and audit during design and construction of the Shoreham Nuclear Power Station is a part of the quality assurance program which is described in Chapter 17.1. This program does not utilize a formal review and audit committee, as such; however, through a comprehensive system of planned audits, compliance with all aspects of the quality assurance program are verified. Audits are performed on the design organizations, the construction site, and vendor facilities. The review and audit function during design and construction is fully described in Chapter 17.1.

13.4.2 Review And Audit - Test And Operation Review and audit during test and operation of the Shoreham Plant is an integral part of the LILCO quality assurance program. Provisions are established for a comprehensive system of planned and periodic audits to verify implementation of quality assurance program requirements. These review and audit functions are fully described for the operational phase in Chapter 17.2, and for the transition phase from construction to operation, in Chapter 17.lD. In addition, LILCO will utilize a formal committee method for review and audit, functioning at two levels: (1) at the station operation level, the Review of Operation Committee (ROC); and (2) at the corporate level, the Nuclear Review Board (NRB), which is Independent of direct responsibility for plant operation.

Normally, the audit functions of these committees will be carried out by subcommittees which ma under the cognizance of the particular committee.

The review and audit progran has been established to assure that the operation of the plant is in conformance with established operating procedures, license provisions, and quality assurance requirements, and to review and approve changes to station systems /

equipment and procedures as described in the FSAR, or tests and experiments, which may not constitute an unreviewed nuclear safety question, as defined in 10CFR Part 50.59. All unreviewed safety questions and changes to Technical Specifications will

• be reviewed by NRB as described below.

A csntinuing review is performed by the ROC to monitor plant operations, to plan future activities, and to screen subjects that might be of interest to the NRB.

Guidance in the development of the essential elements in LILCO's review and audit program for tests and operations was derived from ANSI standard N18.7 " Standard for Administrative Controls for Nuclear Power Plants" (1972). Devclopment of the LILCO Quality Assurance Audit program is described in Chapter 17.

13.4-1 1/11/82

. ,- o SNPS-1 PSAR 13.4.2.1 Administration of Review of Coerations Cenmittee The Review of Operations Coccittee (ROC) has been established and will be functional approximately six months prior to initial fuel loading. The ROC will provide a centinuing review of plant operation to assist the Plant Manager or his designated alternate in keeping abreast of general plant operating conditions. The ROC will serve to screen subjects of potential concern to the NRB or to perform preliminary investigations as requested by the NRB. It is not the purpose of the committee to relieve the Plant Manager of the responsibility for overall safety of plant opera-tions or for the referral of appropriate matters to the NRB.

1. Written Charter A written charter has been prepared covering such areas as group responsibility, subjects rcquiring review, reporting requirements, and organization.

2. Membership Membership of ROC is as follows:

a. Plant Manager--Chairman

b. Chief Operating Engineer--Vice Chairman

c. Chief Tochnical Engineer--Vice Chairman

d. Operating Enginecr

c. Maintenance Engineer

f. Instrument and Control Engineer

g. Radiochenistry Engineer

h. flealth Physics Engineer

i. Reactor Engineer

j. Operating Quality Assurance Engineer

k. Technical Support Manager

1. Training Supervisor

m. Security Supervisor and alternates as designated in writing by the Plant Manager. In addition to the above designated members, the Plant Manager may assign as required additional plant engineers fren the plant staff; other consultants, either in house or frec outs.de t , cer:'any, as required.

2 The responsibility for selecting qualified personnel, and their alternates, rests with the Plant Manager.

13.4 -2

, , , SNPS-1 PSAR A quorum is at least five of the permanent members and may include no more than two of their designated alternates, and includes either the chairman or one of the vice chairmen.

3. Meeting Frequency The ROC will meet on call of the Chairman or one of the Vice Chairmen or as requested by the individual members on an as regs red basis and at least once per month.

4. P.ecords The Review of Operations Committee shall maintain written minutes of each ROC meeting that, at a minimum, document the results of all ROC activities perforned under the responsibility and authority provisions of the Tech-nical Specifications. Copics shall be provided to the Vice President-Nuclear and the Nuclear Review Board.

5. Responsibilities The ROC shall be responsible for:

a. Review of (1) all procedures and programs required by Technical Specification 6.8 and changes thereto, (2) any other proposed procedures or changes thereto as determined by the Plant !bnager to affect nuclear safety,

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to the approved Shoreham Technical i Specifications.

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

c. Investigation of all violations of the Shoreham Technical Specifica-tions including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice-President-Nuclear and to the Nuclear Review Board.

f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission /by regulations or Technical Specifications,

g. Review of station operations to detect potential nuclear safety hazards,

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the Nuclear Review Board.

i. Review of the Security Plan and implementing procedures.

13.4 3

13.4-4

j. Review of the Emergency Plan and implementing procedures,

k. Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommended actions and disposition of the corrective actions to prevent recurrence to the Vice President-Nuclear and to the Nuclear Review Board.

1. Review of major changes to radwaste systems.

6. Authority The Review of Operations Conmittee shall:

a. Recommend to the Plant Manager approval or disapproval of items considered under 13. 4. 2.1. 5 (a) through (d) above. -

b. Render determinations in writing with regard to whether or not each item considered -'er 13.4.2.1.5(a) through (e) above consti-tutes an unreviewed 2ty question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice-President t Nuclear and the Nuclear Review Board Chairman of disagreement between  !

the ROC and the Plant Manager; however, the Manager shall have I responsibility for resolution of such disagreements pursuant to 3 Shoreham Technical 6.1.1.

7. Procedure Generally an agenda is prepared prior to each formally scheduled meeting of the ROC listing those items of concern requiring review by the ROC.

The agenda may consist of proposals submitted by committee members; dis-cussions of past agenda items, current or future station operations; request of the NRB, or review of applicable items described in Section

13. 4. 2. l ( 5) .

Records of the committee recommendations on those agenda items discussed during the meeting will normally be included in the minutes of the meeting. .

The Plant Manager, who is Chairman of the ROC, has the authority to approve or disapprove proposals or recommendations of the ROC. If there is disagreement between recommendations of the ROC and the Plant Manager on matters pertaining to nuclear safety, written notification of the disagreement will be provided to the Vice President-Nuclear.

The Plant Manager, or his designated alternate may make a change and/or authorize interim remedial action involving nuclear safety related matters, as deemed necessary, without prior review of the NRB, Providing the intent of the facility operating license or the technical specifications are not altered and there are no unreviewed safety questions involved.

The ROC may assign subecmmitteoa as deemed required to: conduct studies, discuss items of operational or safety significance which nay not be within the technical expertise of some of the committee members, revicw selected agenda items, witness tests, observe plant operations, review procedures and other such similar matters as it considers appropriate. A subconmittee may consist of any number of committee members, may include other members of the plant staff 'tho are not acabers of the ROC, and may include, when necessary, consultants to assist the subcensittee in its assigned task.

Subcommittee members are appointed by the Plant Manager.

SNPS.1 FS AR 13 .*4 . f . 2 Nucle $rReviewBoard The Nuclear Review Board (NRB) will be established and functional a minimum of six l conths prior to initial fuel loading. The NRB will have a majority of members that are not directly responsible for plant operation and reports directly to the Vice President-Nuclear. The NR3 will be established to verify that operation of the plant is performed in a saf e manner and is consistent with company policy and rules, approved operating procedures, and licensed provisions; to review it,ortant plant changes, test, I experiments, and procedures; to verify that unusual events are promptly investigated, and corrected in a manner which reduces probability of recurrence of such events; and to detect trends which may not be apparent to a day to day observer.

1. Written Charter A written charter will be parpared covering such areas as group responsibility, subj ects requiring review, reporting requirements, and organization.

2. Membership The NRS will consist of a minimum of five permanent members. As a group, they will collectively have the competence required to review problems in the follow-ing areas; nucicar power plant operations, nuclear engineering, chemistry and radiochemistry, netallurgy, non-destructive testing, instrumentation and control I systems, radiological safety, mechanical and electrical systems, admin ist ra t ive controls and quality assurance practices, emergency plans, and any other appro- l priate fields required by the unique characteristics of the facility.

I The Chairman will be appointed by the Vice President-Nuclear. The Chairman {

of the Nuclear Revieu Board is responsible for appointing individuals to l Board Membership . Membership appointments are to be such that the collective i nembership includes the expericace and capability noted in the foregoing f subsection. Membership appointments are subj ec t to cor.currence by the Vice President-Nuc1 ar.

In the event a regular member is not able to participate in NRB activities, designated alternates are authorized to act in the place of the regular member.

Any noninated alternates shall be appointed in writing by the Chairman of the Nuclear Review Board to serve on a temporary basis. l l

No more than a minority membership will hold line responsibility for day to day operation of the Shoreham Nuclear Power Station. The NRB may obtain recommenda-tions from scientific or technical personnel employed by LILCO or other consultant organizations whenever the NRB Chairman considers it necessary to obtain further scientific or technical assistance in carrying out its responsibility. Such indi-viduals shall function as Staff to the NRS, performing tasks and submitting reports a assigned by the action of the Board.

Minimum qualifications of NRB members are as follows:

a. The Chairman will be a college graduate or equivalent, and will have at least 10 years of professional level experience in the power generation field,

b. Other nember:, of the NRB and their designated alternates will be graduate engineers or equivalert, and uill have at least five years experience in the appropriately related scientific, technical, engineering, or power 13.4-5

. e o generating field. Members or their designated alternates may possess competence in more than one specialty area,

c. If sufficient competence in the specialty areas as described in this subsection is not available from within LILCO, the review and audit functions will be performed or supplemented through outside consultants or organizations.

The minimum quorun of the NRB necessary for the performance of review and audit functions shall consist of the Chairman, or his designated alternate, and at least four (4) members, including alternates. Less than a majority of the quorum shall have line responsibility for the operation of the Shoreham Nuclear Power Station. A quorum shall be considered filled if conference telephone communications are established with the requisite number of members or alternates at remote locations. No more than two (2) alternates shall participate as voting members in NRB activities at any meeting.

3. Meeting Frequency l I

The NRB shall meet at least once per calendar quarter during the initial year of the Shoreham Station operation follouing fuel loading and at least once per six months thereafter. )

Any member may request a special Board meeting to consider a matter believed to involve a safety or radiological environmental problem.

4 Records

a. Minutes will be recorded for all meetings of the SRB. The minutes will ident fy all documentary material revicred and the findings or recommen-dations and actions taken by the NRB. Meetings will be numbered in sequence, and minutes of meetings will be distributed to the Vice President-Nuclear and NRB members within two weeks following each meeting.

b. Reports of audits submitted to or conducted under the cognizance of the NRB including recomnendations of the NRB will be made in writing to the Vice President-Nuclear and to the management positions responsible for the areas audited within thirty days af ter completion of the audit.

5. Review Responsibilities The NRB shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59 of 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR Section 50.59.

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SNPS-1 FSAR

c. Proposed test or experiments which involve an unreviewed safety question as defined in Section 50,59, 10 CFR.

d. Proposed changes to the Shoreham Technical Specifications or the Shoreham Station Operating License.

c. Violations of applicable codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from nornal and expected performance of station equipment that affect nuclear safety. , t

g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notific.ation to the Commission /by regula-tions or Technical Spe'cifications.

h. Significant recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

1. Reports and meeting minutes of the Shoreham Review of Operations Committee.

6. Audit Responsibilities Audits of Shoreham station activities shall be performed under cognizance of-the NRB. These audits shall encompass:

a. The conformance of station operation to provisions contained within the Shoreham Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire station staf f at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in station equipment, structures, systems or method of operation that affect nu-lear safety at least once per 6 months. ,

d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. The Emergency Plan and implementing procedures at least once per 24 months.

f. The Security Plan and inplementing procedures at least once per 24 months.

g. Any other area of station operation considered appropriate by the NRB or the Vice President-Nuclear.

h. The Fire Protection Program and implementing procedures at least once per 24 months. L 13.4-7

• • • O SNPS-1 FSAR

i. An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.

k. The radiological environmental nonitoring program and the results thereof at Icast once per 12 months.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

m. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.

n. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or an acceptable substitute at Icast once per 12 months.

7. Authority The NRB is advisory to the Vice President-Nuclear.

8. Procedure Written administrative procedures for the operation of the NRB will be prepared and maintained.

Those items submitted to the NRB as described in paragraph 5b through 5d above, I reviewed and accepted by the NRB, uill be resolved as follows:

a) If the NRB is of the opinion that a proposed change, test, or experiment does not require approval by the NRC under the terms of the license pro-visions, it so reports in writing to the Plant >bnager, together with a statement of the reasons for its decision. The Plant Manager may then proceed with the change, test, or experiment.

b) If the NRB is of the opinion that approval of the NRC is required, the SNPS staff, assisted by other LILCO nuclear organizations, or consultants, will prepare a request for such approval, including an appropriate safety analysis in support of the request in accordance with approved procedures.

If in the course of their review of facility operations, the NRB determines that a variation f rom the technical specifications or an unreviewed safety question exists, the NRB will immediately notify the Plant bbnager, who will take the necessary steps to ensure nuclear safety.

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s o' 4 13.4.3 Shorehan Independent Safety Enaineering Group The Shorehan Independent Safety Engineering Group (ICEG) will be established and functional a minimum of three ranths prior to initial fuel loading. The ISEG will be composed of a Chairman and five dedicated nulti-disciplined personnel, the najority of which shall not be recent college graduates and will report to the Manager, Nuclear Operations Support.

1. _Functionn The principal functions of the ISEG chall include:

a. Assessment of the operating experience of the station and stations of similar design.

b. Examination of appropriate plant operating characteristics and industry /NRC issuances,

c. Review of plant activities such as maintenance, ncdification, operational problens and operational analysis.

d. Surveillance of plant operations and maintenance activities to provide verification that thasc activities are performed correctly and with ni:;inum human error.

c. Review other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

2. Composition The ISEG shall consist of a Chairman, located offsite, and five dedicated personnel, locatod onsite. The Chairman shall provide overall direction to the committce and shall maintain communications with the oncite comnittee through regularl'/ scheduled onsite nectings and other informal contacts. One nenbar of the onsite committee shall be assigned as leader to coordinato day-to-day assignnents and activities.

3. Authority Where useful improvements can be achieved, the ISEG shall develop and present detailed recommendations for such things as revised pro-cedures or equipment nodifi cations to corporate management through the Manager, Nuclear Operations Support.

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