ML20151J304
| ML20151J304 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/11/1988 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8804210089 | |
| Download: ML20151J304 (94) | |
Text
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'3 Lg George S.Thorr os NYN- 88048 Meh4NxMt N ggggg April 11, 1988 New Hampshire Yankee Division United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Reference:
Facility Operating License NPF-56. Const;:uction Fermit CPPR-136, Docket Nos. 50-443 anc 50-444
Subject:
Changes to FSAR Section 13.1, 13.2. 13.3, and 13.4 Gentlemen:
Enclosed for your information are marked-up copies of Seabrook Station Final Safety Analysis Report Chapter 13, Sections 13.?. 13.2, and 13.3 at.d 13.4, which reflect recent organizatiUnal ch:utes, revised training prcgram descriptions, and miscellaneous clari(icaticns. Soc.ticni 13.1, 13. 2, tad 13. 3 are provided in their entirety for ease of refereneet only the affected pages of Section 13.4 are provided. These changas will bn reflected in a future amendment to the Seabrook Station FSAR.
Should you have any questions regarding this matter, pisase contact Mr. Richard R. Belanger at (603) 476-9574, extension 4C46.
Vory truly yours,
/
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voorg /S, Thot.ac th rG Enclosures cc Mr. Victor Nerses, Project Monapr Project Directorate I-:3 Division of Reactor Projects United States Nuclear Regulatory ConAis:sf.on Washington, DC 20555 Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Connissden Region 1 g{
425 Allendale Road /O V
King of Prussia, PA 19406 :
Mr. A. C. Cerne
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NRC Senior Resident Inspector Seabrook Station 3 Seabrook, NH 03874 8804210089 880411 PDR ADOCK 05000443 P DCD P.O. Box 300. Seabrook, NH 03874 . Telephone (603) 4 F 4 9'iT4 l
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ENCLOSURE 1 TO NYN-88048 Changes to FSAR Section 13.1 l
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, SB 1 & 2 Amendmsnt 58 FSAR April 1986 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE This section describes the organizations of the New Hampshire Yankee (NRY)
Division of Public Service Company of New Hampshire (PSNH) and the Yankee Nuclear Services Division (YNSD) of Yankee Atomic Electric Company (YAEC).
NHY is responsible for the management of Seabrook Station and YAEC provides support as requested by NHY. We qualifications of both organizations are g ef fered as supporting evidence that the operational responsibilities for Seabrook Station can and will be discharged in a competent and efficient D manner.
13.1.1 Management and Technical Support Organization The New Hampshire Yankei (NRY) Division of Public Service Company of New Hampshire is responsible for the construction and operation of Seabrook Station. De overall responsibility for all activities associated with Seabrook Station resides in descending order with the PSNH President and Chief Executive Of ficer, che gNHY Rresident and Chief Executive Of ficer, and the NHY S::ier Vice President', Ufo'fsNilgnated as management official in overall charge of the station.
An integrated project organization has been ggtablished g working under the direction of the NHY Senter Vic: Pr e s id e n t7t o "e Usl5 N Tf((ct iv e p roj e c t management control. -31s-integrated-organization-is ccgrised-of the "ice
" ::ident -Nuclear-Productionet he-Vi c e -Pr es iden t- a n d-Di rec to r-o f-Qia lity p no Prograsset he-Di r ec t o r-o f-En g inee ri ng ,-t-he-Di r ec tor-o f-Ma nagement-Co-n t roly-t-h e -
Director-of-Corporate-Services read-e n-Enecutiv e-Assis t en t .
The-Di r ec to r -o f -Ma na g eme n t -Co n t rol-i s-r e s pone i ble-for-p r e pa ra t ion-o f-b ud ge t s ,
%gr 40s t-cont rol-aoni t or i n g rPu rchae i n g-an d-con t ra c t-ad mi n is t ra t ionreeteriel-end equipment-expediting,--insurance -mediagraphice r r employee-relationer and-information-resources.
l The Vice President - Nuclear Production is responsible f or s tation operations, maintenance, security , outage management , health physics , chemistry, plant s tores and inventory, industrial s af ety, t raining, 1-icensing r-**e rgency-planning, and system / component testing. The Production organization is further described in Section 13.1.1.1 y ,p ,,,g ,L.< 4 3 d The Vice President an,. Dir cter ef-Quality Programs is responsible f or quality assurance and quality control. Operational quality assurance is described in Section 17.2. Co n s t ruc t ion-Q A-a c tivi tie s - a re-a c compli shed-b y-t he-Y AEC-Cons t ruc t i on-QA-Mana g e r-wh o- re po r t s -<ii rec t l y-t o- t h e-YAE C-Di re c t o r-o f-42a l.1 ty Aeaur4nce , -but-interf aces-wi th-t he-NHY-Vi ce-Pr e sident-a nd-Di rector-o f-Qu ali ty-Progra ms-a s-s hown-i n-Fi gu re -13.1-2. -
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J Prasmes (,w ~te The Dir: ter of Engineering 31s the f ocal point f or all, engineering activities.
Middle level managers provide the direction needed for implementation of engineering progrecs , configuration management, reliability and-performanca.
engineering, special projects , field engineering and design, and ssf aty evaluations.
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- Nuclear This integrated organization is comprised of the Vice Presidentand Licensing, Quality Production, the Vice President of Engineering, Programs, the Comptroller and Chief Administrative Officer, and the Executive Director of Emergency Preparedness and Community Relations.
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INSERT AA This integrated organization is comprised of the Vice President - Nuclear Production, the Vice President of Engineering, Licensing, and Quality Programs, the Comptroller and Chief Administrative Officer..and the Executive Director of Emergency Preparedness and Consnunity Relations.
i INSERT BB The Comptroller and Chief Administrative Officer is responsible for providing accounting and financia.1 services. Other areas reporting to the Comptroller and Chief Administrative Officer include Management- Services,- which encompasses employee relations, mediagraphics, and information resources:
Purchasing, Contracts and Insurances and Budget and Controls.
The Executive Director of Emergency Preparedness and Connunity Relations has overall responsibility for the development and implementation of both the on-site and off-site emergency response plans for Seabrook Station.
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SB 1 & 2 Am2ndmint 59 FSAR May 1986 The-Oi rec to r-of-Co rpo ra t e-Se rv ic e s-i s-re s pon s i ble- fo r-con s t ru c t i on - ma n a geme n t ,-
cpecial-project -management rproject-ecntrolsr-development- of--cost-forecasts-cnd -sched ule s ,-and-mai n t ena nce-of- co rpo r a t e-f aci li t ies -and - eeu i pmen t- no t c on t ro l led-by-t he-S ea b rook-4 t e t-ten-he f4.
The-E xec u t i ve-As s i s t a n e -is -ac eou n t a b le-t o-ad m in is t e r-s pee fel-ma nag emen t
.proj e c t s ,-canage-t he-I nd e pe nden t-S a f e ty-E ng i nee ri ng -G rou p r-a nd -3e r f o rm-o t he e seeh-act i v i trie s-as-ma y-be-s pec i f ied-by-t he--Sen io r-Vice-P res iden t . The resumes of appropriate corporate management personnel are contained in Appendix A.
The internal corporate organizational relationships are shown in Figure 13.1-1.
NHY and YAEC have signed an agreement that delineates the specific operational support services supplied by YNSD for NHY. The responsibilities delineated in the agreement can be changed or added to with the mutual consent of NHY and YAEC. Amendments to this agreement must be signed by an of ficer of NHY and YAEC. The corporate organizational relationships between YAEC and PSNH (NHY) are shown in Figure 13.1-2.
Westinghouse, United Engineers & Constructors (UE&C) and General Electric are three other organizations having major responsibilities for the design and construction of the Seabrook Project. Westinghouse ia responsible for the construct 4on-phase design, fabrication and delivery of the nuclear steam supply system, related auxiliary systems and the nuclear fuel. Technical direction for the installation of the equipment and technical assistance throughout the pre-operational testing, initial core loading and power cscalation testing programs are further responsibilities of Westinghouse.
United Engineers and Constructors (UE&C) is responsible for construction phase cngineering, design and certain construction activities of the station.
Included in their services is the furnishing of the balance of plant systems cnd components, structures and switchyards such that a complete and f.ntegrated f acility will result. General Electric is responsible for the design, f abrication and delivery of the turbine-generator unit.
58 13.1.1.1 NHY Production Organizatica, Responsibilities and Authority The Production organizatica is under the overall direction of the Vice 33 President - Nuclear P.oduction, who has full time responsibility for the
- 3 operation and operational suppor?. For Seabrook Station. To assist him in the secomplishment of these responsibilities, the Vice President - Nuclear Production has the Seabrook Station Manager, the-At-artuo-Nnagar, the Training Ccntcr- Manager, the Regulatory Services Manager, and the Wid14dr"Services l Manager reporting directly to him. Alse-e*eorting-to-the-Vice-President - T Nuclear-Production-are-the-Radiological-Assessment ManagerAlo-respons41e l
fo r-eme rg ency -pl a n n i n g t -and - t he- Ope ra t ion a i-P roj e c t s -Su pe rv i so r r who-is-res pons i ble-f o r-t he-developmen t-a nd - ma i n t ena n ce -o f- a d m i n i s t r a t i ve - p ro g ram s .-
The Vice President - Nuclear Production reports to the 6enior-VidI/PresidentmJCkd 18 cnd has the necessary cuelifications and job position to cualify as "E n g i n e e r '""" 0" ' b "~
in Charge" as defined in ANSI / ANS 3.1 - 1978.
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SB 1 & 2 Amsndmsnt 59 FSAR May 1986 4
,The responsibilities, training, organization and qualifications of the Station Staff are discussed in Section 13.1.2. The-res p e n c i b i l i s tee-ef--the-Ge ebeeek E S4artup-Teet-Department :: discus;;d in S::ti:n !^.2.2. The responsib;11 ties of the Training Center Staff are discussed in Section 13.1.1.2. The Nucle:r A/ote Services and Regulatory Services organizations are described below.
SV Regulatory Services functions in direct support of Seabrook Station in the licensing and training areas and is composed of a manager and at least three engineers. The Regulatory Servicas Manager will have a minimum of ten years experience in the area of nuclear plant operations with at least two years related to interf acing with reguintory agent ies. The engineers will have 3 to 5 years experience with at least one year of power plant experience.
Regulatory Services personnel vill receive the General Employee Training and the Training for Supervisors as described in Section/3.2,'..
59 h eleer-services-is co; posed-of a :snager end a staff of et leest twc engineere-or-eelent4eto. The-Nuelear-Gervieee-Henegee-wi41 h ve : =6eimin-ef eight-yeare pcuer plent-exper4eace-with-te: yeare-of-th: : paienee-aseeeieted-gt d wi4h-start-up-or-operet4eeel-supporty--The-seaff-enginee s er setentis ts will l have-3-te 5 yeare--experien c wFeh at -least one yees of power ptsat experience. #M g 4 The grcup fenettene-le-dkreet cuppcet---of-the-etet4;n in th: ::::: c f e n vd-c o e -
aantel -enitostag A a14h-physiesy-training-and-operatiene. Nuc1::: Servicee d ec sennel "i11-receive-the C::::al-Employee-Trefning-end-the-Treieing for Supervisors-described in Section=F3.2. The-Vice-President -- Nuclear-Prod ** W :nd th: Mucles: Services !knager will else receive a piece operstions crientation course which includes treining fm mitig.titrf"core t . ;0 13.1.1.2 Seabrook Training senece organization, Resoonsibilities and Authority NHY has recognized the importance of speeet+e. training by establishing 4 tr**~f J3 i ['gM6 T-retning-Center-facility andl,' organization which is independent of t "e s tation f acilities and management, by providing a Seabrook site specific siuulator, and 'uy having the Trair.ing Gentee Manager report to the same level of manage- D I
ment as the Station Manager. The Training Center is located on the Seabrook site outside of the protected area.
Ge ,w h The Trainkage,thCenter facility-contains , classrooms. office space, a library, study areas, en instructor material preparation room { a computer room, administrative areas, and a simulated Seabrook control room with a full dize main control board and various main control room panels. The simulator con-trol board is manufactured by Link, a division of the Singer Company. Link has had extensive experience with nuclear simulators and a myriad of simula-tors for military applications. Seabrook represents the eighteenth simulator built for the nuclear industry by Link. The simulator control room is not only similar to the actual control room in appearance, but is also operated under the same working conditions as the actual main control room to penvide a l
realistic atmosphere for operator training. The-Seabrook-simuistor-meets-the~
l req u i r eme n t s -o f-Reg u l a t o ry-Guide-lvl 49 r1981-ex c ept- as -not ed -in- FS AR - S tet i on hfh 13.1-3
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4 INSERT CC Production Services provides backfit, general administrative and project support. Reporting to the Production Services Manager are Production Administrative Services, Project Controls, Construction Services, and Nuclear Services functions.
4 SB 1 & 2 Amandmsnt 59 i FSAR May 1986 _
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13.1.1.3 YNSD Operational Organization NHY has contracted with the Yankee Nuclear Services Division (YNSD) of Yankee l Atomic Electric Company for certain operational support services and wi41 58 l
depend on YNSD's cualifications and organizational expertise for certain statim support services. NHY has delegated to YNSD the necessary authority and organizational freedom to accomplish these support services. 5351 1
Yankee Atomic Electric Company, an electric utility company, was incorporated j
es a Massachusetts electric company in 1954 under provisions of the Massachu-i setts utility law which permits two or more electric companies to join in the construction and operation of a generating plant to service their common
( needs. The Yankee Atomic Electric Company was sponsored by twelve New England utilities for the purpose of constructing and operating New England's first nuclear power plant. In addition to the corporate functions of 13.1-4
INSERT A The Training Manager reports to the Vice President - Nuclear Production as shown by Figure 13.1-1. Th9 training organization is shown in Figure 13.1-4.
Operator training is performed under the cognizance of the Operations Training Manager who is responsible for implementation of the License Training and Requalification Training Programs as discussed in Section 13.2.1. The training program for instructors is identical in scope to the Seabrook operator training required for a Senior Operator license, except that instructors are provided additional training on simulator control functions and to improve teaching skills.
Training for technical and management staff is performed by the Technical Training Department, which consists of a manager, supervisors, and instructors. This function is further discussed in Section 13.2.2.
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SB 1 & 2 Am ndesnt 59 FSAR May 1986 generating, tuY1aig, and selling electricity, it has broad related function.s.
including conducting research and assisting others engaged in the nuclear -
powet business, The twelve (now eleven) sponsoring utilities own the entire common capital Jtock of Yankee Atomic in the percentages indicated below.
peonsoring Comoany Percent of Stock New England Electric System New England Power Company 30.0 Northeast Utilities The Connecticut Light & Power Co. 15.0 The Hartford Electric Light Co. 9.5*
Western Massachusetts Electric Co. 7.0 New England Gas & Electric Assoc.
New Bedford Gas & Electric Light 2.5 Cambridge Electric Light Co. 2.0 Boston Edison Company 9.5 Central Maine Power Company 9.5 Public Service Co. of New Hampshire 7.0 Eastern Utilities Associates Montaup Electric Company 4.5 Central Vermont Public Service Corp. 3.5 100%
- Includes 0.5% originally allocated to the Connecticut Power Co. which subsequently merged into The Hartford Electric Light Company.
In the construction and operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts, a group of engineering, operating and support per- 51 sonnel with valuable knowledie and experience in nuclear plant matters was assembled. Personnel were later assigned from this group to the Connecticut Yankee project. Since completion of the Connecticut Yankee project, other nuclear projects have been completed, including the jointly sponsored Maine Yankee and Vermonc Yankee projects. Other projects have also been undertaken individually by several of the sponsoring utilities of Yankee Atomic. With
- this increase in the number of nuclear projects in New England, it became
) apparent that a nuclear services organizattor, was desirable to develop the required support for the major New England utilities.
The purpose of YNSD is to provide a vehicle and a place for the assembly of a l
group of engineering, licensing, and operations support personnel that is 1) l under the common control of New England sponsors of the various nuclear plants 53 being built in the New England area and, 2) available to provide general j advice on nuclear power matters to the sponsoring companies. This group of j personnel is located at the corporate headquarters of the company in Massachusetts. ,3 The expertise and experience gained by YNSD during the design and construction 3
phase of Seabrook Station, as well as their considerable operating experience j on the three Yankee plants, will be utilized to its fullest in the operational support of Seabrook Station. The organizational interface and responsibility l
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SB 1 & 2 Amsndment 58 FSAR April 1986 reporting lines between NWY and YNS.D are shown on Figure 13.1-2. The l necessary administrative and technical authority for YNSD to carry out this responsibility has been extended to them.
YNSD uses the Project Manager concept to oversee and control work undertaken for Seabrook Station. The YNSD Seabrook Project Manager has direct respon-sibility for the overall coordination and implementation of many of the cperational support services outlined in the NNY-YAEC Interf ace Agreement. l These operational support services, as well as requests from NHY for other 51 special services are controlled by the Project Manager in the following manner. The Project Manager authorizes the appropriate YNSD department / group to provide the support service in accordance with the terms of the NHY-YAEC Interface Agreement and authorized budgets. A cognizant engineer, which is
'I the fundamental organizational element for the accomplishment of work within YNSD, is assigned by the appropriate line department / group manager / lead cugineer to assume the responsibility of assuring that the task is completed on schedule. The Project Manager and appropriate department / group management 53 cre kept informed of the task progress and development by the cognizant engineer. Various forms of communications, including working level discussions, between the active YNSD and NNY participants for the assigned task occur directly and with whatever frequency is deemed necessary.
Conflicts that cannot be resolved at the YNSD/NRY working level are brought progressively to the attention of increasingly higher levels of line manage-ment of each organization with ultimate resolution, if required, by the NNY President and Chief Executive Officer and the YAEC President. 93b lT The Ycnkee Nuclear Services Division is organized to provide a complete spectrum of expertise for the operational support of Seabrook Station. The specific areas of potential YNSD support for Seabrook Station are:
o Nuclear Engineering o Mechanical Engineering o Electrical Engineering o Instrument and Control Engineering o Systems Engineering ;
o Materials and Welding Engineering o Environmental Engineering and Environmental Laboratory Services o Ruman Factors ?,ngineering ,
o Quality Assurance and NDE o In-Service Inspection o Accident Analyses o Transient Analyses o Seismic Analyses o Reload Analy1es o Probabilistic Risk (Safety) Assessment o ALARA and Health Physics Support o Dose Assessment and Dispersion Modeling o NRC Licensing (Generic and Plant Specific) o NPDES Persit Acquisition and Renewal ,
o Meteorology '
51 13.1-6
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/ s s SB 1 & 2 Am:ndment 58 FSAR April 1986 o Hydrolc3y l o ' Aquatic Ecology o Fuel Ftbrication and Procurement o Fire Protection o Equipment Qualification o Systess Interaction / Failure Modes and Ef fects Analysis o Vendor QA Audits / Surveys o Emergency Preparedness Support o Performance and Reliability Analyses o Document Control and Records Retention The experience and qualifications of YNSD engineering personnel that may be 51 assigned to support Seabrook would typically encompass the qualifications required for the positions of Graduate Engineer, Associate Engineer, Engineer, Titled Engineer, Senior Engineer, Senior Titled Engineser, or Principal Engineer. To provide an indication of the minimum education, training, and experience required for these positions, job classification descriptions are provided in Table 13.1-1.
There are several advantages that accrue to Seabrook as a result of the utilization of Yankee, includings o An awarenets of problems and their resolutions at several operating plants that could aid in preventing similar situations at Seabrook; An increased knowledge of the capabilities of, and the estab'lishment o
of, good working relationships with a variety of consultants and contractors who could also provide support services to Seabrook; o A broadening of the experience of YNSD's cadre of engineers; and o The maintenance of a greater staff awareness of the various regula-tory requirements imposed upon operating pcwer reactor f acilities.
It is also YNSD's operational philosophy to maintain sufficient flexibility in the allocation of its manpower resource to meet the priority support needs of each of its plants. Thus, based on over 20 years of providing operational support services, YNSD has never failed in meeting the support needs of its plants; a record which YNSD fully intends to uphold in meeting the operational support needs of Seabrook Station.
N 13.1-7 J
SB 1 & 3 Amendment $8 0 FSAR April 1986 13.1.2 Coerating Orgin1:acion 13.1 2.1 Station Oreanization The Seabrook Station organization chart is shown in Figure 13.1-5. This chart depicts the titles and the minimum number of employees assigned to each pos ition. The station organization includes all the technically trained personnel necessary to support all aspec ts of Unit 1 operation. }
S1 The key supervisory positions for the station organization vote filled in 1979. Personnel to meet the operational requirements of Unit I have t e en r-*P- !
will-be hired on a phased basis consistent with the training and licensing O *I requirements of the individual positions. The schedule for this expansion is d I
shown in Figure 13 1-6, which also shows the fuel loading and other key alle-stones for Unit 1. M The Unit 1 on-duty operating shif t crews will be cesposed as shown in Technical Specification Table 6.2-1, and will meet the requirements outlined in Technical Specification Section 6.2.2 describing the plant organization.
Manpower necessary to staf f five shif t crews will be provided. Each member of the station organization wLil meet) or exceed,5 the minimum qualifications recommended for comparable positions in Regulatory Guide 1 8, Revision 1-R, except ANSI /ANS 3.1 - 1978 will tf used as the standard rather than ANS 3.1 ANSI 18.1 - 1971.
ko kee n The employees assigned to the station organization will-be trained aa des-cribed in Section 13.2. l M
13 1 2.2 Station Personnel Responsibilities and Authorities
- a. Overall Station Management The Station Manager of the Seabrook f acility is responsible for overall management of Unit 1. In his absence, the Assistant Station Manager assumes this responsibility. In the event of unexpected contingencies of a temporary nature, occurring during the absence of these two managers, the Operations Manager will be responsible for overall station operations. The Shift Superintendent assumes the responsibility for overall management of Unit I when the above station management is not within the station. In addition, the Station Manager may designate in writing other qualified personnel to assume overall station responsibility in his absence.
The Station Manager reports to the Vice President - Nuclear Pro-duction for all activities related to the station. Reporting to the Station Manager, or his assistant, are seven managers: l 9
- 1. Operations Manager: Responsible for the operation of the station. l 5%
- 13.1-8 i
t
a SB 1 & 2 Amendment 60 FSAR September 1986
- 2. , Chemistry and Health Physics Manager: Responsible to provide support for chemistry and health physics activities at the station.
sanet
- 3. Technical Servi::: Manager: Responsiblo to provide tschnical support f or the operation and refueling of the static a.
- 4. Maintenance Manager: Responsible to provide support for maintenance and radwaste activities at the station.
- 5. T :ining " ::::: R::p:::ibl f:: th: :::ining ;f :::ti:n perre---! in ::tivitie net :: qui-in; :n :;;;;t::': li::n;;. f Training Of Operatiene pereere:1 1: p::f::::d d:: th: dir::t supervieler ef the T::ining C: ter M::::::.
- 6. jj:tnietectie: Servi 2:: ":::::r- R;;;;ncible f : ;;n ::1- l rdritirtretier retivitie: Of th: et: tier. 3 C
- 1. Security and Computer Systems Manager: Responsible to provide support f or security and special and process control computers.
Tv;<Rf B 6.
The Seabrook Station staff has assumed several responsibilities in support of the Initial Test Program in order to increase staf f awareness of the Preoperational Test Program details, provide staff contribution to the program implementation details and procedures, insure staf f readiness to accept the completed systems and derive as much training benefit as possible f rom the Initial Test Program effort. These support efforts included the loan of staff personnel to the Start-Up Test Department, the assumption of assigned preoperational testing responsibilities, the verification of design and installation, chemistry support, procedure review, evaluation of test data and operational as well as maintenance support of plant systems prior to final acceptance turnover of the systems. j 16 The functions, responsibilities and authorities for station positions under the direct cognizance of these managers are defined below.
- b. Operations The Operations Manager is responsible for the operation of the i l
station. He ve; :t: te th: Stati:n M:n:;::, :nd maintains close l communications with the other managers with regard to all activities (8 i at the station.
l He is responsible for the safety and operation of r.ne unit's l equipment in accordance with written and apptoved station rs procedures. He has tho authority to order the shutdown of the reactor, when in his judgement such action is required to protect the l safety of the station or the health and safety of the public. The .d l
Operations Manager will hold a Senior Reactor Operator's License. He l l
also supervises the Assistant Operations Manager and the Fire Fighter g Supervisor. ,
r3 l
13.1-9 i
INSERT 3
- 6. Plannina. Schedulina. and Outane Manamer Responsible to provide Planning 1
and Scheduling of day to day work activities as well as annual and outage s chedu?,e s .
- 7. Technical Proiects Manamer Responsible to provide the interface between the Station Staff and other NHY functional areas.
i i
t i
i I
i l
l l
r
. SB 1 & 2 Amendment 58
, FSAR April 1906 The Assistant Operations Manager directs the activities of the Shif t l Superintendents. He reports to the Operations Manager and will 53 l assume the responsibilities of the Operations Manager in his 54 absence. He is responsible for the safety and operation of the unit's equipment, in accordance with written and approved station procedures. He has the authority to order the shutdown of either reactor, when in his judgement such action is required to protect the safety of the station or the health and safety of the public. The Assistant Operations Manager will hold a Senior Reactor Operator's License.
- 1. Operating Shift Crew An operating shift crew will normally consist of a Shift Superintendent and one Unit Shif t Supervisor, two Control Room Operators and three Auxiliary Operators. The Shift Superin-tendent and Unit Shif t Supervisor will possess a Senior Reactor Operat: 's License; Supervisory Control Room Operator and the Control Room Operator will possess a Reactor Operator's License. The minimum shif t crew composition for various modes *T of unit operation is shown in Technical Specification Table 6.2-1.
(a) Shift Superintendent Each Shift Superintendent reports to the Assistant Oper-ations Manager. He is responsible for the safety and operation of the station's equipment, in accordance with l vritten and approved station procedures. Each Shift 51 Superintendent has the authority to order the shutdown of the reactor when in his judgement such action is. required l to ptctect the safety of the unit or health and safety of M the public. The Shift Superintendent shall possess, in addition to a Senior Reactor Operator's License, the training and qualifications of a Shif t Technical Advisor or a qualified Shif t Technical Advisor will be assigned to his shift. The Shift Superintendent will function as the Shift
{
Technical Advisor and provide requisite technical expertise si to the Unit Shift Supervisor in the event of any abnormal operational occurrences.
l l (b) Unit Shif t Supervisor l
The Unit Shift Supervisor is responsible for all unit operations being conducted in accordance with appropriate station orders, procedures and technical specifications.
He te responsible for maintaining a record of all shift activities and establishing unit electrical load, as directed by the Shift Superintendent or as emergency conditions dictate. He has the authority to order the l shutdown of the unit reactor, when in his judgement such l
13.1-10 ,
1 e
--r..
.. SB 1 & 2 Amandmant 58
-FSAR April !!'S action is required to protect the safety of the unit or the health and safety of the public. Each Unit Shift Supervisor will hold a Senior Reactor Operator's License.
(c) Supervisory Control Room Ooerator The Supervisory Control Room Operator is responsible for all control room activities. He directs the control room operator and the auxiliary operators in their daily activities. He directs these activities in accordance with approved station orders, procedures and technical specifications. Most of his activities are confined to the control room, however, he may perform specific activities in other areas of the station under the direction of the Unit Shift Supervisor. He has the authority to order the shutdown of the unit reactor when in his judgment such action is required to protect the safety of the unit or the health and safety of the public. Each Supervisory Control Room Operator will hold a Reactor Operator's License.
(d) Control Room Oce stor 51 The Control Room Operator monitors the unit's status and makes adjustments, as needed, to maintain control of the various plant process:1. Most of his duties are confined to the control room although he may perform specific activities in other areas of the station under the direc-tion of the Supervisory Control Room Operator. The Control i 51 Room Operator will hold a Reactor Operator's License.
l (e) Auxiliary Goerator l ss The Auxiliary Operator parforms routine inspections and l surveillance activities in other areas of the unit. He maintains various logs and records as required by station l
procedures. In the 2bsence-of-a-Heelch-Physics-Technitisn, b 4m --'e- red 14; ion-4-4 cent s-inetien- erreye rithi the c00 r:14 d crc::,- During periods when the unit is shut down, he makes routine tests and clears and returns j
equipment to service as directed by the Supervisory Control Room Operator. The Auxiliary Operator is unlicensed.
1
- c. Chemistry and Health Physics The Chemistry and Health Physics Manager report +-diceetly to the
-Scacion-Manager-and-is responsible for the coordination and direction of the Chemistry and Health Physics Departments.
M 5A c d so p e r o s m es d.l,u o r speaid r adAG.s survey.s cc.mmens rste Atk the
~
ddes of Mt job, 13.1-11
- 1. Chemistry Deoartment Suoervisor l
The Chemistry Department Supervisor is charged with the direct responsibility for ensuring that the nuclear and steam portions of the station operate within the approoriate water cualiev specifications. He is responsible for water treatment and conditioning for specific st ation needs. He is responsible for verifying that all liquid, resin and gasecus vastes are properly analyzed and processed for station reuse or disposal.
- 2. Realth Physics Department Suoervisor ll 53 s%
The Realth Physics Department Supervisor is the Station Radia-tion Protection Manager and as such has the responsibility and authority to report to the Station Mane.ger (as shown on Figure 13.1-5) on any aspect of the Radiation Protection Program or its implementation as he deems necessary. He normally reports directly to the Chemistry and Health Physics Manager and is responsible for monitoring station activities for cono11ance 65 with Realth Physics relaced regulations and programs. The entire station staff, from the Station Manager on down, recog-nizes and honors this responsibility, thereby ensuring that the Realth Physics Departnent Suoervisor, in concert with the members of his approoriately trained and experienced staff, will fully implement the station radiation protection progran. He is responsible for monitoring devices used by personnel at the station and the maintenance of recuired radiation exposure records for station and visiting personnel. He ensures that appropriate monitoring devices and protective clothing are available. Re is responsible for verifying that solid radioac-tive materials, other than radioactive waste neet nackaging and shipping reauirements of the station and federal regulations.
During an extended absence of the Realth Physics Deoartment Supervisor, a Health Physics Supervisor is designated to temoo-
- rarily assure those responsibilities as discussed in Section 12.5.1.
s,rpet '
i
- d. Technical Serviese-The Technical SServices.
u c e.4 i
i Manager Peeert: :: the Acci44mt St2 tion-l u nneger : d is responsible for technical support functions for the station. He renitere the retivitie ef end provides overall direction for the Technical S$ NiN e Group Departments which Ne-technical and engineerine activities at the station.
aur mp,e y
- 1. Reactor Engineering Deoartment Suoe rvis or The Reactor Engineering Deoartment Supervisor is resoonsible for 5I l the analysis of core performance to ensure operation of the l station within the facility license limitations. He will I calculate reactivity requirements, evaluate the thermal-13.1-12
i SB 1 & 2 Amandmant 58 )
FSAR April 1986 i
i 1
1 hydraulic performance of the reactor cores, specify control rod l patterns, prepare fuel aovement sequences, and be responsible l for fuel accountability. He is responsible for preparing and maintaining reactor engineering related detailed plans, procedures and records required for safe and efficient operation ;
of the reactor. l
,.,yy,.4 r c
- 2. Technical- Su;;::: 0:;::::: : Superviser l The Technical Support 00 pert:::: Sup :vi :: is respen;ible for 6T the genersi engineering 2nd q lity :ngin:::ing ;upport ;;rvice perfer=ed ca-site. H: cupeevise:-a multi-disciplined st.ff vf g::duc: engine::: who p::fer; a wid; sps ;ruc of a ;1vicies 1 incinding: initiatier : d pr:perstica cf d::ign c5:ag
- q ::te, prep : tien :nd :: view-cf :sf 07 : lated preceduras , j teet perform:nce end inepectien, end 2errying cet e=eigned engineerin; prege:::.
- e. Maintenance ;
The Maintenance Manager reperte te the St:44:r M:n:gur and is responsible for the coordination and direction of the "ain;anance
! Servicee, Radioactive Waste and Utilities, Instrumentation and Control, and Maintenance Departments.
1 w=1acenanca Servicee Ment;:r-1
' Ehe-Maintenance-Services-Manager-is-responsible for the technicel end adminiet stive cupper Of the-Maintenance Orcup by davaloping end rintaining fer=:1 peeg:::: f: preventiv 1
- inte---^e, :::::::ive ::ia:cann : and surraillance ;asting, ne p=*H cipeter in the :intenance p:::::: by providing-recheateel, electrie:1, rel ying, ::d ::co, and inet:;; n:::ica and centrel-engine: ing f:: ::::ica :: r;;;iva and preventive 1 l
maint:nene: :::ivi:ie:.
l
! 19. Instrumentation and Control Department Supervisor i
l
! The Instrumentation and Control Department Supervisor is l responsible for the maintenance of all instrument and control l l equipment associated with the reactors, their auxiliary systems i He and the conventional steam portions of the station. i maintains station process and control instrumentation in proper operating condition, as well as the maintenance of all station radiation monitoring equipment. He also maintains and directs the repair of all control circuitry associated with the reactor, turbine and auxiliary systems. He utilizes a program of i preventative maintenance, corrective maintenance, surveillance ;
testing and record keeping, as required by the station license, I approved station procedu.es, and/or other station requirements. I Sq i
, i l
l 13.1-13 ,
f
INSERT C
- 2. System Suecort Department Manager The System Support Department Manager is responsible for providing technical support of system-related activities. This support involves providing system engineers and other technical expertise to implement work control activities, design change implementation, and resolution of operating problems.
- 3. Program Support Department Manager The Program Support Department Manager is responsible for technical and programmatic support of Station activities. These support activities include test control, ASME B&PV Section XI inservice inspection, and surveillance testing.
SB 1 & 2 Amandmanc $8 r . FSAR April 1986 13[. Maintenance Department Supervisor The Maintenance Department Supervisor is responsible for all station mechanical and electrical maintenance work required for safe, efficient and dependable service. He utilizes a program of preventative maintenance, corrective maintenance, surveillance testing and record keeping, as required by the station license, approved station procedures, and/or other station requirements.
JAf. Radioactive Waste and Utilities Department Supervisor The Radioactive Waste and Utilities Department Supervisor is responsible for the operation of the radioactive waste processing system and the collection, processing, packaging and loading of radioactive vaste. He is also responsible for the upkeep of buildings and grounds within the protected area. He augments the Maintenance Group by providing staging erection, decontamination services, shielding installation and labor support,
- f. Fire Protection Program Management O
- 1. Fire Fighter Supervisor The Fire Fighter Supervicor reports to the Operations Mattager.
He is responsible for implementation of the fire protection 53 program on-site. He will develop the procedures for testing and surveillance of all fire protection equipment and systems, and is responsible for all fire prevention and protection activities on-site.
- 2. Fire Brigade Leader.
The Fire Brigade Leader is responsible for directing the fire brigade during a fire emergency on-site. This duty will be performed by a systems trained individual who shall be qualified to fire fignting standards and who is responsible to the Fire Fighter Supervisor.
63 53
- 3. Fire Brigade The Fire Brigade is responsible for firefighting on-site. Each shift fire brigade will have a minimum of five persons, including the Fire Brigade Leader. The responsibilities of the fire brigade members under normal conditions will not conflict with their responsibilities during a fire emergency.
4 13.1-14
SB 1 & 2 Amsndmant 60 FSAR September 1986 I
- g. Other Station Managers I ss The following are the managers reporting to the Station Manager or Assistant Station Manager, other than those managers in the opera-tions or technical service areas, who have responsibilities for various station functions.
- 1. Training Men ::r-The Training Mancger repert tc th; A :istant Statica Managcr
?"A fe reepeneible fer 211-treining cnd rctraining activitics with the enception Of operatcr training. l 4
- 2. Ad-inictrati c Scrvicc: Monaccr The Ad=inke4rativ: Servicc: Managcr reports to the Assisteat- l Statien Mens;cr, and 10 reopensibic for administrativ; support-oE-the etatien,-including etcrec, rccords, Office sopport sud l
'o etatien m2ree.
- 3 1 3'. Security and Computer Systems Manager The Security and Computer Systems Manager reporte to the Stette^
Maa ger 2nd is responsible f or security services and f or controlling hardware and software for process control and ,
special purpose computers. !
INM R T D l 13.142.3 Ogerating Shift Crews 6o The position titles, applicable operator licensing requirements, and the minimum numbers of personnel planned for each shift are described in detail in Section 13.1.2.2b and Technical Specification Section 6.2.2. A-ncr;;l busq wer4I opu#f ess, a n operating shif t will consist of five Auxiliary Operators, a Control Room l Operator, a Supervisory Control Room Operator, a Unit Shif t Supervisor, and a Shift Superintendent for the station.
l .
During unit refueling operations, when the reactor core configuration is being altered, an individual having a Senior Reactor Operator's license will directly supervise the refueling activf ties in the reactor containment.
Auxiliary Operators are trained in applicable station radiation protection procedures to perform routine or special radiation surveys commensurate with
! the duties of their job. They receive radiation worker training which includes the use of protective barriers and signs, protective clothing and breathing apparatus and limits of personnel exposure. The Shift Superintendent is responsible for implementing the radiation protection fy program in the absence of the Health Physics Department Supervisor or his designated alternate. When fuel is in the unit reactor, a qualified health l physics technician is assigned to the onsite shift to provide additional re support to the Shift Superintendent.
l I
13.1-15 l'
INSERT D
- 2. Planning. Schedulinn, and Outane Manager The Planning, Scheduling, and Outage Manager is responsible to provide planning and scheduling of day-to-day work activities as well as annual and outage schedules.
- 3. Technical Proiects Manager The Tecnical Projects Manager is responsible for providing coordination between the Station Staff and other NHY functional areas. He also serves as Chairman of the Station Operation Review Committee (SORC) in the absence of the Station Manager and Assistant Station Manager.
SB 1 & 2 Amendmsnt 60
. FSAR Ssptember 1986
^
, When the unit is in operational modes 1 through 4, .a chemistry technician qualified in primary and secondary chemistry analysis is assigned to the onsite shift to provide additional support to the Shift Superintendent.
13.1.3 Qualification of Nuclear Plant Personnel 13.1.3.1 Qualifications Reauirements The recommendations of Regulatory Guide 1.8, "Personnel Selection and Training", Revision 1-R, have been used as the basis for establishing minimum qualifications' for all management, supervisory and professional-technical personnel in the station organization, with the exception that ANSI /ANS 3.1 -
1978 will be used as the standard in lieu of ANS 3.1/ ANSI 18.1 - 1971.
The education, training and experience requirements for operators, technicians and mechanics will equal or exceed the qualifications for the positions stated in ANS 3.1-1978 and Regulatory Guide 1.8. Established company training programs include documented academic and on-the-job training plus comprehen-sive qualification examinations applicable to the skill level of the position tssignment. Where desirable, off-site facilities may be used for specialized training.' Records of the scope,_ general content and level of accomplishment for each person' attending off-site-training are retained at the station.
The titles of plant management and supervisory personnel who will meet the minimum requirements of ANS 3.1-1978 and Regulatory Guide 1.8 are listed below with their equivalent ANS 3.1-1978 title.
Station Title ANS 3.1 Title
- a. Station Manager Plant Manager
- b. Assistant Station Manager Plant Manager
- c. Operations Manager Operations Manager
- d. Assistant Operations Manager Operations Manager 3 sec ,-6
- e. Technical Ser'icce Manager Technical Manager
- f. Maintenance Manager Maintenance Manager JJ
- g. Maincan.n,.. c a rf4c-e w y, q g u;g;;;;;;;; .,;;;z;7 3)(. Chemistry and Health Physics Supervisor without NRC Manager License a
bl. Security and Computer Systems Supervisor without NRC Manager License
. La i f. Shift Superintendent Supervisor with NRC License s3 18 13.1-16
~
. SB 1 & 2 Am2ndm2nt 58 FSAR April 1986 k Unit Shift Supervisor Supervisor with NRC License f 3
55 A 1. Supervisory Control Room Operator Supervisor with NRC License lm. Chemis try Department Supervisor Professional-Technical a d. Maintenance Department Supervisor Supervisor without NRC License
- c. Teehaie*1 Surrert Department "reft:sional Technicat Supervisoe-a g. Reactor Engineering Department Professional-Technical Supervisor o cr. Instrumentation and Control Professional-Technical Department Supervisor p r. Realth Physics Department Professional-Technical Supervisor
%ls ute /0EI tln Supervisor without NRC g.g Radic :ti:: " :t e- Supervisor License r t. Computer Engineering Department Supervisor without NRC Supervisor License u- T-ainian N : Superd eer eithcut "C- .
-Lic::::
v,--Administrau ve-Servhes-Waager S m ed e 1e - w'c-htwee. 53 yyg 7 ; 55 13.1.3.2 Oualifications of Station Personnel The kcy mana: ament, supervisory and technical positions in the station organ-ization have been filled by individuals thoroughly trained in their specialty. In addition, most of the individuals have had extensive experience at operating nuclear power plants in their specialty. The nuclear experience of seator personnel at the time of startup will generally he in the range of 8 l co 20 years. These personnel include thg Sta Station 53 Manager, Operations Manager, Technical SeEdle, tion Manager, se Manager, Trainin: Assistant Center Maaa~er, Shift Superintendents, Technical S ::::t 0 ;;rtacnt Supc-eisor, c l Instrumentation and Control Department Supervisor, Chemistry Department 55 Supervisor and Health Physics Department Supervisor. Many of the key personnel will have had Senior Operator Licenses or Operator's Licenses at other operating plants or have had extensive nuclear submarine operational responsibilities. Most of the Unit Shift Supervisors and Control Room Oper-ators and at least one individual in each of the maior technical disciplines (nuclear engineering, chenistry, health phvsics, instrumentation and controls) will have had at least five years of similar experience.
Resumes for personnel holding key positions in the initial plant organization are included in Appendix 13D.
13.1-17
INSERT E
- s. Planning, Scheduling, and Professional-Technical Outage-Manager
- t. Program Support Department Professional-Technical Manager 4 u. System Support Department Professional-Technical Manager
- v. Technical Projects Manager Professional-Technical l
1;
~
L l
(
SB 1 & 2 Amsndment 58
- FSAR April 1986' TABLE 13.1-1 (Sheet 1 of 2)
- 5 YANKEE ATOMIC ELECTRIC COMPANY JOB CLASSIFICATION CLASSIFICATION - Graduate Engineer Education, -
(1) Completion of a Bachelor's degree in an appropriate Training and discipline from an accredited college or university.
Experience CLASSIFICATION - Associate Engineer Education, -
(1) Satisfact on of educational requirecents of a Graduate Training and Engineer (i.e'., completion of Bachelor's Degree Experience requitecents in an appropriate discipline and graduation from an accredited college or university) or educationni and experience requirements of an
! Engineering Associate (i.e., completion of Bachelor's l Degree raquirements in a math or science field and i gradustion from an accredited college or university,
( or sufficient experience to attain equivalent knowledge and skills);
l () Satisfactory completion of at least one year of employment at a professional level in the field for l
l which employed or completion of an advanced. degree; l and (3) Actainment of Engineer-In-Training qualification is
! desirable as a first step in obtaining certification as a Registered Professional Engineer.
53 a CLASSIFICATION - Engineer , l 51 Education, - (1) Satisfaction of educational and experience Training and requirements f or an Associate Engineer; Experience (2) Satisfactory completion of at least three years of l
employment at a professional level in field for which employed which demonstrates a progression of I coc.petence in field of expertise (Note: advanced education may be sul.scicuted for work experience); and 51 (3) Attainment of Profess Lonal Engineer's License is desirable.
m 4 y
" $31&2 Amandmant 58 FSAR April 1986 TABLE 13.1-1 ',
(Sheet 2 of 2) Si CLAS$ITICATION - Titled Engineer Education, -
(1) Satisfcetion of educational and. experience reauire- l Training and ments for an Engineer; and 5%
s Experisces (2) Satisfactory completion of at least five years of employment at a professional level in field of expertise which ~ demonstrates a progressive competence (Note: advanced education may be substituted for work exoerience).
^
CLASSIFICATION - Senior Engineer Education, -
(1) Satisfaction of educational and experience reouire-Training and ments for Titled Engineer; Experience (2) Satisfactory completion of at least seven years of employment at a professional level in field of l expertise which demonstrates a progressive development l of competence; and
\ .
l (3) Completion of an advanced degree in area of expertise is desirable when appropriate.
^$
CLASSIFICATION - Senior Titled Engineer Education, -
(1) Satisfaction of educational and experience recuire-Training and ments for Senior Engineer; Experience (2) Satisfactory completion of at least nine years of employment in field of exoertise which demonstrates a
! progressive develoonent of competence.
l (3) Completion of at least one advanced degree in area of expertise or equivalent experience and original work.
CLASSIFICATION - Principal Engineer Education, -
(1) Satisfactory completion of at least twelve years of l Training and employment at a professional level in field of l Experience expertise which has demonstrated a oroeression in competence to a level of marked prominence.
l (2) Completion of at least one advanced degree in field or sufficient experience to be deemed equivalent.
(3) Membership in orofessional societies.in field of exoertise as well as professional licenses are
. desirable.
51
I
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MANAGER MANAGER
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- -1 CARD Aleo AvnL11e On Aperture Card C00@ TROLLER APC CHIEF VICE PRESIDENT ADMIMISTRATIVE OFFICER ENGIhEERINS, LICDWING AND QUALITY PROGRAMS MANAGER 74)CLE/A 0F QUALITY ENSINEERIt4 MANAGER 8804210089-C/
PUBLIC SERVICE COMPANY OF NEV HAMPSHIRE SEABROOK STATION - UNITS 1 & 2 NEW HAMPSHIRE YANKEE DRGANIZATION FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-1
J v %
P O ALSO CHAIRMAN OF M YW. BOW PRESIDENT C CEO Peti PRESIDENT 4 CEO HHY a . . _ _ _ _ _
l na -.
EXECUTIVE DIRECTOR VICE PAESIDENT COMPTR(t.LER AND CHIFf EMERGENCY PREPAAEDNESS S NUCLEAR PRODUCTION ADMINISTRAT!YE OFFICER COMNLHITY RELATIONS .
REC 1 ATORY PRODUCTION STATION TRAINING SERVICES SERVICES MANAGER MANA$ER MANAGER HANAGER MM
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Also AvaRahle On Aperture Card V8CE PRESILE,NT DIAECTCA VICE PAESIDENr m
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A2 OUALITY PROG 4.ny.3 "nasu w m.un am WANASG IMIN8 QUALITY MANAGER 8804210089"dA l SEABROOK PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK STATION - UNIB 1 & 2 ORGANIZA110NAL INTERFACE FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-2
4 SB 1 & 2 Amendment 58 FSAR April 1986 (Figure Deleted)
- h f
I I
Figure 13.1-3 1
- w. m OPERATI0tG TRAINING MANAGER SIMULATOR BYSTEMS OPERATI N 1 DEPARTMDIT TRAINING SUPERVIGOR SLPEN d.MR ENGINEERS TEQMCIANS SINULATOR PR SIMULATOR DESIGN g INSTRUCTORS INST C00R0INATOR ,
M
, . . . . ~ . . , - ~ .~
.r TRAINING NANAGER TEOt(ICAL TRAININS SUPPORT TRAINING SERVICES NANAGER MANAGER TRAINING TRAINING TRAINING TRAINING S'JPERVISOR SUPERVISOR SUPERVISOR SLPERVISOR DF 4 CNEN.) 'NFM. 4 ELEC.) ( I & C) (DENERAW Tl
. APERT M -
CARD BERAN DSTRUCTORS INETRUCTORB INBTRUCTORS INSTRUCTORS
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Also AvaEmble 06 Apertar Card 8804210089'O PUBLIC SERVICE COMPANY OF NEV HAMPSHIRE SEABROOK STATION ,
SEABROOK STATION - UNITS 1 & 2 TRAINING ORGANIZATION FINAL SAFETY ANALYSIS REPORT FIGURE 13,1-4 L __
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l FU3LjC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK STATION ,
SEABROOK STATION - UNITS 1 & 2 ORGANIZATION FINAL SAFETY ANALYSIS REPORT l FIGURE 13.1-5 ;
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60 48 POSITION STATION MANAGER $ KEY STAFF SELECTION
/RST. STATION M ANAGER $
ADMIN. SERVICES MANAGER 4 LICE g
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OPERATIONS MANAGER $ SELECTION TECH. SERVICES MANAGER $
REACTOR ENGINEERING DEPARTMENT SUPERVISOR SHIFT SUPERINTENDENT (6) $
UNIT SHIFT SUPERVISOR (6) $
CONTROL ROOM .g OPERATORS (12)
STAFF SELE TRAINING MANAGER $
ENGINEERli:G SERVICES .g DEPARTMENT SUPERVISOR PARTHENT V SO
$ SPECIAL TP HEALTH PHYSICS
- DEPARTMENT SUPERVISOR MAINTENANCE DEPARTMENT .g SUPERVISOR I & C DEPARTMENT .g SUPERVISOR TECHNICIANS MECHANICS AUXILIARY OPERsTORS
$ COMMENCE POSITION RESPONSIBILITIES NOTE: ACTIVITIES ENCLOSED WITHIN BOXES APPLY TO APPROPRIATE POSITIONS.
ACTIVITIES NOT ENCLOSE 0 WITHIN BOXES APPLY TO ALL POSITIONS.
- ~
Amendment 58 April 1986 CORE LOAD l MONTHS PRIOR TO CORE LOAO y )
36 24 12 0 FUNOAMENTAL DETAILED SYSTEM AND NUCLEAR AND SIMULATOR TRAINING, OBSERVATION, FREOPERATIONAL TESTING, TRAINING FINAL PROCEDURE VRITING TION DEVELOP STATION PROCEOURES PREOPERATIONAL TESTING
- INING PROGRAMS
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PREOP. TEST PROGRAM PREPARATION FINAL PROCEDURE WRITING TI APERTURE
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- TRAIN 1HG
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PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK STATION UNIT
- I l
SEABROOK STATION - UNITS 1 & 2 KEY OPERATIONAL MILESTONES FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-6 l
ENCLOSURE 2 TO NYN-88048 Changes to FSAR Section 13.2 i
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SB 1 & 2 Amsndmsnt 59 FSAR Mty 1966 13.2 TRAINING lsce nse/ Op erdo r Operator 13.2.1 License-Training Program-
- a. General Discussion j,eeneJaoedu k m5i'.V m sol > cdA'swldt e
The program will provide personnel eeeecia c? ;-ith the operation of Seabrook Station suicin; in fericus disciplinae necessary to ensure that each individual can safely and effectively perform various assignments.. The-d eg ree-t o- wh i c h -a n -em p loy ee-i s-t ra i n ed- w i l l-be -
cons is t en t- wi t h - the-ind ivid uall s -ex pe rie nce ,-in t ended - pos i t io n-and 4 regulatory-requirc ente. Eligibility of individuals to license or renew a license pursuant to the requirements of 10CFR55 and. 46 NUREG-lO21 will be certified by the Vice President - Nuclear Production. g The -Sea b rook-s pec i f i c- s imu l a t o r- wi l l-be-cad e-sva i-l a bl e- to - NRC '
personnel-to-conduct-Seabrook Operator-License -examinations.
Q uali f ie d -s t a f f- membe r s -will-be - availab le-fo r - assis t a n ce--i f requested. '
i,uiaed spm tc'< iro<id <arc a AS The overall objectives of the Operator-License-Tr[ining-Program are:
o To train a staff to operate and maintain the units safely, dependably and economically.
o To prepare shift superintendents, unit shift supervisors,
,yffy,,, ,[ g/,, control room operators and selected, station-managers for the NRC St.to $1Jy licensing examinati n f r Reactor Operator (RO) and Senior Reactor Operator (SRO).
The safe, efficient operation of a nuclear power plant depends ,
on the qualifications and proficiency of its personnel. Several basic categories of training are necessary to provide licensed 45l
. personnel with a high degree of competence and profession-
! alism. Specifically, these categories of training are as follows: 43 1.
- Goeratoe41 cowdOp '< cense-Tralh t'or %fal X,r;@,
All personnel requiring NRC operating licenses, as epeci-
/cWF( fied in ANGIVANS-3&t9&ti'#111 heve to undergo intensive training which will meet or exceed the minimum recuirements of 10CFR55". 3trior-to-d o-initial-criticality, operator. 4h,l g
li ce ns e -t ra ini ng-come s -unde r - the -I ni t ia l-Ope ra t o r - Lic e ris e j .T ra ini n g-P rog ram .-O pe r a tor -li c e ns e - t r a i ning - comp l e t ed -
l af ter-the-fitst-criticality-is -given- by-the-Replacement
-O pe r a t o r4 Lc ense-T re i n i ng-Erog r4m .
< 53 1
13.2-1
. l SB 1 & 2 Amtndm2nt 58 FSAR April 1986
- 2. Shift Technical Advisor Training New Hampshire Yankee he$ upgred:d the training program for l the Shift Superintendents or Unit Shift Supervisors to meet 9 the long term plan of satisfying the need for a Shift Technical Advisor on shift. The Shift Technical Advisor ,
Training is designed to meet or exceed the recommended guidelines referenced by NUREG-0737. ,*.
- 3. Licensed Operator Requalification Training Program l
~
sg This category describes the training necessary to maintain the proficiency of all Seabrook licensed personnel. This Program will meet or exceed the minimum requirements of 10CFR55, Appendix A.
- 4. Replaeocent-0,eratoe-Lieenne-Tealein; "rcgeee-Operacors-joining- the Seabrook-organlaation-after-the-seset-o f-powe r-c oe r a t ion-will-be-g i ven-a pp rop eis t e-tra ining-to
. -satisfy-their-job-classificat-ioner-The-ertent-and-duration-
-o f-t he-c ra inin g-pe r iod-d e pends-upon-t hei t previous
.e xp e r ience-and-f o b-ap ett ude 41-a p plic an t s-fo r-e-se n io r
-o pe ra co r-or-con t rol-o pe ra tor-lice nee-will-have-t h ree-mo n e he-
-on-shif t = der-instruetion-in-the-License-position-they-are-seeking.--Senior-operator-epplicanes-vi-11, in-addition ,
have-held-aanpe ra to r to-licenae-fo r-one-yea rr--If-en-NRG-O pe ra t o r 's-License-is-req u i red- f o r-a-s pec i f io-job-c a t ego ryr as suit able-clas s rooe-and-p rac t ic al-t raining-is-p rovid ed e y 49
- f. Program Accreditation and Instructor Certification New Hampshire Yankee is committed to the IN"O develepcd l w,Jtati a pre.scu ead"5kaeoredi-tetien progene. To meet this commitment, the 9 e -d) ; 2. I e (( company instituted a procedurally administered 4.tre& ,ht hud accreditation procsss. The process is carried out by an accreditation team working under a supervising committee known as the Steering Committee.
It is Seabrook Training Center policy that all training instructors who provide instruction in safety systems, I integrated response, transients, and simulator courses will M y MciAusdor$ b N m/ maintain-a-cu r ren t-fa oility-SRO-1-ic e nse-t h rou g h-pa rt ic i pe-t ion-in-the-req ual if4c a cion-t ra ining-pro g rea . Staff instructors who have not obtained a facility SRO-license l may be certified for specific subjects in which they have i demonstrated SRO-license level comprehension and skill.
The determination of this certification is the responsi-bility of the, Training Center- Manager.
Op n 6 <.ns > As l
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13.2-2 l
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SB 1 & 2 Amendment 58 FSAR April 1986 Guest lecturers considered to be experts by nature of their '
work responsibilities will be used on a limited basis to
'supplemenc the training center staff instructors. These guest lecturers are exempt from the senior operator criteria.
Prior-to-the-initial-licensing-of-instructors and operators f o r-6eab rook -Uni t -I ,- p revious ly - s eni or -li cens ed ;-s e nior license-certified-or-Training-Center-Manager certified-instructors-will* teach-syscean -integrated r response--
transients r and-simulator-courses.
46
- b. Resoonsibilities The following Seabrook personnel are responsible for various areas of Seabrook's Opereter tirrere Training Program.
u rmcs cp w It?/SER 7 /;n
- 1. s tation-Mansiree
-The-Sea b rook-S t a c ion-Menets e-haa -t he-ove rail-re s pon s ibility-f o r-qualificacion-and-profietency-of-its-personnel. - As-suchy-the-Scation-Manager-will-review-and-spprove-al-1 planr training-
-Programe.-
2 Assistant-Station-Manager-T he- Ass is e an t-S t a t ion- Manage e- is - res po ns ible -to - the -S e a c ion -
l Manager-for-administration of all-the general and spacia1ty cr Aning-courses-given-by-the-Training-Departmenc.-The-
-AJsistant-Station-Manager-vi-11 review-chose training ~coursas-annually. g
- 3. Traininir-Cenrer-Mana g 4
l .T he-T rai ning -Ca n c e r-Mana ge r -io- re s po ns i b le - f o r- d eve lo pme n er i implementation,-and-adsinistration-of-licensed operator-training and -auxiliary-operator-craining.-This wi}1-include-initisi, replacement -and-requalification-trainingr n e,,s d OpmL W e n t Ghin
- ST 13.2.1.1 Program Descriotion -Initial-Ocetocor-bitans. Taindig 3i,/1 This program will provide an individual with the knowledge and espost4ase
,_ level necessary,to.,obtain an NRC Senior Operator's I.icense or Operator's I.icense. The-program-has-been-developed-and-sc heduled-in -a-modula r-f a s h io n-to W implemented-in-segments. In-mos e-ca s es T-each-1-iten sing-catid icd a t e -will
.participace-in-each-segac.nt.-However,-whether-an-individual parcicipates in'
-all-segrened-will-depen.'-upon-previous-nuclear-experience-and prerf.ous-iteense
.qualificacion.-Program participation-bas-been-categorised-on-Tame-Mr2- 2.
- dspy <ar me < L c < en ad f.fo rap ,4,rr e,i6 <//oG M SS~
}yf c,per ah %l wk Und 1 ded 13.2-3
INSERT A
- 1. Vice President - Nuclear Production The Vice President - Nuclear Production has overall responsibility for qualification and proficiency of Seabrook Station personnel.
- 2. Training Manager The Training Manager provides direction and control for the conduct of training at Seabrook Station. The Training Manager reports to the Vice President - Nuclear Production.
- 3. Operations Training Manager The Operations Training Manager is responsible for the development and implementation of training conducted in support of the operator training programs, including licensed operator, non-licensed operator, technical training for engineering staff, simulator training, and fire protection training.
- 4. Technical Training Manager The Technical Training Manager is responsible for general employee training and for supporting organizational training, including maintenance, chemistry, health physics, instrumentation and control, and quality assurance and supervisory / management training.
- 5. Training Support Services Manager The Training Support Services Manager is responsible for the administrative support of training activities, including program development, evaluation, and accreditation activities.
i
SB 1 & 2 Amendrant 59 FSAR May 1986 The license training program schedule will insure that a sufficient number of licensed personnel will be available prior to fuel load, and will continue to meet applicable technical specification conditions with respect to the number of licensed operators on shift crews.
A program for effectiveness monitoring is established for all areas of license training. Evaluation of program effectiveness shall be perfor[ed by: (1) l Training Centee management periodic assessment of classroom presentation and 58 simulator instruction; (2) independent -third parey-oral end descasrtretive audite cenducted c et leaet : j;;.riy4atir;-H student generated evaluations.
ll 41 54 Revisions are made tothelicensetrainingprogramtostrengthenweakare) identified through the evaluation process.
AS The following paragraphs provide a general description of the various train-ing segments:
- 4. Int roduetery--Teeinier-in add ition te the -- inicia1-or-ientetien-and-generei-emp4eyee-tra ining
.daacribed in See tion 13.2.2, - those-indiv44uala-spec 4 fically-deeigned-to-becone-license-holdere-wi41-4t tead-an-introduetocy-pregre;;; ;n PWR-ey s t ems ,--The-f i rs t-por t ion-o f-t he-program-is--a-ge neric-cours e- O covering-chehlear-Steau Supply-System-fNSSS-) . Iricense-eandidates-
-w i4-414044-given-a n-in t rod uc to r y-c ou r se-c ove r i n g-t he-ba i a nc e-o f-Seabrook1s -systems.
A 2cc&r b Nuclear Fundaesntals Training "scises-p l 45 Fundamente4e-1--
e ght t. t.we lve-ihis is an e4ghteen to-twenty week program presented by the l Training Center Staff or an outside vendor. 'The program pro- O l
vides the license candidates with a thorough understanding of I the basic principles, characteristics and unique features of 41 59 a nuclear system. The major areas to be covered are -eathe--
natics -ad classical-physic +r- basic nuclear physics, reactor operations, core performance, radiaMon-peete+t4eer plant chemistry, instrumentation and control, fluid flow, thermo-dynamics, heat transfer, and plant performance. M-integea4-pa r t-o f-the-Fund ame n t al s-I--t ra in ine-p rog r ee-i-s-re se ter-s ta rt--
-up-experience ---Thie-is-a-one-week- preg ram-presented-at-e-4esearch-or-training-fac44ity -by-ar -eutside-vendoe.
Experime'nts d iesuosione-and-demonstrations-are-conducted-to-c omp lime n t-t he-p r i nc i p le s -a nd-t he o ry- t a u gh t-in- t h e-f und a-eenca ls-prog r am .--Speoi f ie--t r a in ing-objee e ives-are-selec ted-wh ich-p lace-add i t iona l-e m ph a s i s-o n-c o nc e p t s-wh ic h-a re-diR isult-to-visualise-in-the-clae J e com-environnent, rNS E 2 7 g 13.2-4 l s3
INSEhiTB
- b. Reactor Startup Experience -
This one-week course is conducted at a research or training facility for all cold-license groups. Experiments, discussions, and demonstra-tions are conducted to compliment the principles and theory taught in the Nuclear Reactor Fundamentals course. Specific training objectives place additional emphasis on concepts that are difficult to visualize in the classroom environment.
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SB 1 & ? Am2ndmsnt 58 FSAR April.1986 Fundam'antals.II This la-a-forty-to-fif ty-week-program-prese.nted-by-the-Train-ing-Ce n te r-S t a f 4--c r-en-ou t s id e-venoo r .-The-p rog ram -is -d e s igned to-provide-the-Shif t-Superintendent-and-Unit-Shif t-Supervisor-wi th-an-ad ded-de p t h-o f-k now le d ge-o f-e ng ine e r ing- p r inc ip le s --
-found-in-nue lea r- re ac ter- fund amen ta l- app lic a t ions .- Se le c t ed-courses-are-based-upon-an-analysis-of-the-Shif t-Technical -
' Advieor !a-qualifications-and-responsibilities-outlined-in-- '
l NUREG-4578 rThe-c ours e s-inc lude - the - fo llowing s -
Dif ferentia l-Ca lcu lus-al
-Integral-Calculus Advaned. Reac tor-Phy s ic s-Material-Study ~-Course
-Fracture-Hechanics-Corrosion-Processes-.
-Compu te r-Techno logy-
- E lec t r ic-Ce ne rator-and-Transm i s s ion.
Theroodynamic s-
~ Heat-Transfer-
-Fluid 2 Mechanics 9
To-supp lewen t-Fund amen t a 1-II-c ou e s e s ,- wo ek e ho p e -w i l l- be - he ld -
-co-reinforce-theore tical concepts-learned -in-the- course s- with -
practical-Seabrook-applications.--The workshops will generally-c ons is t -o f-a-c la s s room- pha se - and -u s e -o f- the -s imu la tor-whe re -
app ro p ria te . - -
An-add it iona l-ten- to-twe lve-week s-o f-spec ia liz ed -t ra in ing- is
- p rov ided-t o-s u pe rv i s o ry-le ve l-l i c e n s e-ho ld er s . These coursed ine lude--not iva e ion-o f- pe e sonne 1,-problem-and-decisitm ana-lyri3, interpersonel communication,-technical-writing,-s tress-and--
-humaa behevier.
. c. Operating Plant Observation
, ,ur,,,,J ut-J t.' e 2. id I a ens q to- t's d; This segment 3 consists of four te-ein weeks of plant observation at As a PWR similar in size and design characteristics to Seabrook. The major objective is to familiarize each license candidate with the daily routine involved in the operation of a commercial nuclear facility. Other specific areas of observation will be made in security, radiation protection, maintenance, qualify control / assurance, fuel handling, and waste disposal / management. Y " a 13.2-5
. _ _J
SB 1 & 2 Amend:ent 59 FSAR May 1986
-4 . Fo rmel-On-4L te-Scht+1-This-segment-of-approximately-14-to-18-weeks-duration-will-encompass the-on-site formal-classroom lacture-series. -The -inst ructors-for-
-chis-lacturs-series will be-permanent and -temporary -members -of- the- 45
-Se abrook- S t a t ion -T raining- Ce n t e r- s ta f f ,-Se ab rook -S ta t ion - Supe rvis o ry -
staff-and -Yankee Atomic-staff..- Other consultants--and-vendor representatives-will-be-invited to-discuss -topics- of special-interest. g The-subjects- to-be-taught-and/or-reviewed-in the-formal ~on-sice ~
school-are-listed-below:-
Mach-and-Physics-Reactor-Operations Plan t- Chemis t ry -( P rima ry - and - Se c o nd a ry ) --
Health-Physics
-Heat- Transfe r Fluid-Flow-Materials-Science-The rmodynamics Specific-Systems-& Components Ins trumentation- &- Controls Mitigating-Core-Damage-(per-Table-1-3 2-3F .ts i Tec'h nical-Specification 4 .
Adminis trative -Controls Special-Topics
! A-three-week-block-of-ins truc tion-is-inc luded-to-address -transient and-l accident-analysis-and-mitigating-core-damage.- This -three weeks' of ~ l l tra ining-con s is t s-o f-c las s room -ins t ruc t ion ,- prac t ice - se s s ions -on - the 61 s imula to r-and -s upe rv is ed-s t udy-wi th - p rob lem- s o lving .-
As 59 Included-in-the-classroom-training-segment will-be periodic simulator-1 -exercises-and demonstrations.- In addition, directed in-station tours I
will - be- conduc t e d- to - review - sys t em- and- componen t -layou t-and -in t e r-face. Th5 ER T D
- g. Simulator Training Seabrook has the distinct advantage of including a site specific 4547 simulator as part of the operator training program. The simulator was modeled and built to duplicate the Seabrook main control board as l well as real time system response. The simulator meete-the- JT ,
-requirementa-of-Regulatory-Guide-l.149,-1981,-except-as-noted-in~ FSAR-Se c c ion-148,-Con f o rmance-to-NRC-R e gula tory- Guid e s .
0 1 soJ/heuerUdJ m uscehne altk dowR sw~
l l r.#SfR T d l
l 13.2-6 l
1
A INSERT D
- d. Detailed Systems Training This ten week course is designed to ensure that license candidates acquire the systems knowiedge and skills needed to support safe and efficient plant operation. The content and structure of the course are determined through needs analysis supported by a plant-specific task list. The instruction covers the major plant systems, including the electrical distribution system, the primary and secondary systems, and balance of-plant systems. The training also covers appropriate theory review, integrated systems response, procedures, and administrative controls.
The training methods include classroom instruction, in-plant walk-throughs, and simulator demonstrations. In-plant activities are conducted during the Detailed Systems course to provide structured plant systems training under the supervision of an instructor. Systems tracing is carried on independently by the license candidates. When requested, instructors and operations personnel help license candidates who are having difficulty with in-plant assignments,
- e. Mitigating Core Damage and Transient and Accident Analysis At least three weeks of instruction are devoted to mitigating core damage and transient and accident analysis. This training consists of classroom instruction, sessions on the simulator, and supervised study with problem solving.
s INSERT E The purpose of simulator training is to give each license candidate practice in applying knowledge and skills to perform control room tasks during normal and abnormal conditions. Teamwork and diagnostics are stressed throughout'the course. Topics covered during the simulator training includes control panels, integrated plant operatien, normal procedures, reactor startups, abnormal procedures, emergency response procedures, and emergency plan.
- g. On-Shift Participation This ecurse, is designed to give each license candidate an opportunity to observe plant operations and complete work assignments in the control room alongside licensed operators. The license candidates must perform, observe, or discuss activities and tasks as specified in the Quelification Guide. In addition they will carry out any duties assigned by the operators on shift. The on-shift participation is at the level of the license being sought.
I On-shift participation is a seven-week course for cold license candidates, who also receive four weeks of Operating Plant Observation Training. For hot license candidates, on-shift participation lasts three months, i
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SB 1 & 2 Amendment 58
% FSAR April 1986
'N NRC Operator examination or Senior Operator examination, as appli-
\ cable. The second portion of the evaluation will be an oral wafk-
'N through and simulator denonstration to further evaluate practical
\ knowledge and experience.
N
'This evaluation will insure each candidate is properly pyepared for the NRC exam, and is capable of competent and safe operation of \ the plant controls.
\ '
13.2.1.2 Coordination with Pre-Operational Tests and Fuel to ding The Station Staff Training program has been developed and will be scheduled tominimizeanyconflictsinmanpowerrequirementsdurin[theunit'spre-operational testing and fuel loading. The positive tra,fning effects gained by actual participationgin the start-up will be incorp$ rated in the training program. y The scheduling interface be' tween the Operator License Training Program and the start-up is illustrated in Figure 13.2-1.
\
13.2.1.3 Licensed Operators - Requalification Training
\
A comprehensive requalification training pr/ ogram will be conducted for all licensed operators and will be implement,ed within three (3) months after the initial cold licensing of operators. \This requalification training program has been developed and will be implemented to maintain a high level of knowledge and skill in licensed react'or ' operators and senior reactor operators. The basis for this program is\to enhance safety, productivity, l
and efficiency in operating the plant during normal and abnormal situations.
TheSeabrookStationRequalific/ation Training' Program has been prepared within the framework of a systems approach to training'., The content and schedule of requalification training'is established by the seabrook s Training Center's Curriculum Development Committee (CDC). The CDC c'onsists of, but is not Supervisor, a repre-limitedto,theTrainingCenterManager,theTraini%ativefromMediaSupport.
sentative from Operations management, and a represent I
l \
A minimuct of ten weeks per two year cycle will be dedicaqed to the requalifi-l ca: ion training program. All licensed Seabrook Station ihstructors will participate in the program in order to remain cognizant of\current operating M
history, procedural changes, design changes, and administrat'(ve policies, except to the extent : hat their normal duties preclude the need for specific retraining in particular areas. Each application for renewal o'(an operator or senior operator license will be accompanied by a statement, signed by the Vice President-Nuclear Production, certifying that the applicant has satis-factorily completed the requalification program during the effectivg term of his or her current license, and that he or she has discharged licens4 responsibilities competently and safely.
M i The requalification training program consists of four interrelated elements:
1 o Requalification Examinations
,' o On-the-Job Training
/ o Pre-Planned Lecture Series
/ o Special Retraining Programs D
13.2-7
SB 1 & 2 Amendmene 58 FSAR April 1986
- f. Peeeeen-Review-end Pre-License Evaluation At-the -culminat ion-of-the-trai ning-orogram ,- each- licens e - candid a t e-will-participate-in-review-session- followed- by-ore-license -evalu --
acient
.The -review-se s s ion -will- cons i s t - o f- f o rmal- clas s room -ins t ru c t i~on , --
simulator-exercises-and -individualized- s tudy.-- The ~ review - s ession -
will -emphasize-areas -where earlier-program-information -may have-been -
shallow or unknown.
mas A final pre-license evaluation of each license candidate 4d44 be administered by an independent party. This evaluation vill be a ussah conducted in two parts: the first will be a written exam to determine the candidate's comorehension and retention. The exam contents and degree of difficulty w&&& paralliel that of a current NRC Operator examination or Senior Operator exam} nation, as aoolicable.
The second portion of the evaluation till hd an oral walk-through and simulator , demonstration to further evaluate practical knowledge and experience. -This-evalua t i on-wil4-ins u re-ea c h-ca nd id a t e-is-o ro pe el v-o r e pa red-f o r-t he-NRC-e x am,--a nd-i s-c a pa ble-o f-comoe t en t-and -s a f e-opera tion-of-the-91ent entrele, 13.2.1.2 Coordination with Pre-Ocerational Tests and Fuel Loading The Station Staff Training program has been developed and will he scheduled to minimize any conflicts in manpower requirements during the unit's pre-operational testing and fuel loading. The positive training effects gained by actual participation in the start-up will be incorporated in the training l ****** 3 :i v S E R 7' Q.
The - scheduling-in t e r f ace-be tween- the-ope ra t o r-Licens e -Trai nin g-Program - and - the-l s t a r t -up-is-illus t r a t ed-in-Figu re-13. 2-1.
W 13.2.1.3 Licensed Ooerator Recualification Training 7segrem A comorehensive recualification training program will be conducted for all licensed operators and will be implemented within three (3) months af ter the initial cold-licensing of operators. This recualification training program has been developed and will be implemented to maintain a high level of knowledge and skill in licensed reactor operacoes and senior reactor operators. The basis for this program is to enhance safety, productivity, and j efficiency in operating the plant during normal and abnormal attuations.
sS l
r l
1 13.2-8
INSERT C 13.2.1.3 Shift Technical Advisor Training This course of study, presented by the Training Staff or an outside vendor is designed to provide the Shift Superintendent and Unit Shift Supervisor with an added depth of knowledge of engineering principles found in nuclear reactor fundamental applications. Selected courses are basel upon an analysis of the Shift Technical Advisor's qualifications and responsibilities outlined in NUREG-0578. The courses include the following:
Differential Calculus Integral Calculus Advanced Reactor Physics Material Study Course Fracture Mechanics Corrosion Processes Electric Generation and Transmission Thermodynamics Heat Transfer Fluid Mechanics When Seabrook Station's STA training is included in a program of study leading to a bachelor's degree, it provides a level of technical course work that satisfies the formal education criteria specified in the NRC Policy Statement on Engineering Expertise on Shift issued in October 1985.
Individuals completing the STA training receive a Bachelor of Science or Bachelor of Professional Studies degree, includ.ng a level of technical training that meets or exceeds the usual requirements for a bachelor's degree in engineering technology. Although this training does not lead to any of the degrees specified in the NRC policy Statement on Engineering Expertise on Shift (October 1985), it does satisfy the intent of Option 1 Alternative 3 in that policy statement. (Alternative 3 calls for a bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences.) The NRC staff has
( reviewed Seabrook Station's STA training and concluded that it is equivalent to that envisioned by the policy statement.
i 1
SB 1 & 2 Amandment 58 FSAR April 1986 17/JSF R 7 t-
- The Seabrook-stesion-Requalification-Train'ing-Program-has-been-prepared-within-
-the-ftamework-of-a-systens-approach-to-traii n ng.--The-content-and-schedule-of-- ,
- requali ficat ion-treining-is-es t ablis hed -by-the- Seab rook-Training-Cent e r 's -~~
- Curriculum-Development-Committee-(CDC)rThe-CDC consists of 7-but is not~
limited-co,-the-Training-Center-Manager -the-Training-Supervisori a
. rep resen t a t ive- f roe -Ope ra t ions - sanagemen t rand-a-representative-from-Media -
Support.
A minimum of ten weeks per two-year cycle will be dedicated to the requalification training program. All licensed Seabrook Station instructors will participate in the program in order to remain cognizant of current operating history, procedural changes, design changes, and administrative policies, except to the extent that their normal duties preclude the need for specific retraining in particular areas. Each application for renewal of cn 8#
operator or senior operator license will be accompanied by a statement, signed by the Vice President - Nuclear Production, certifying that the applicant has satisfactorily completed the requalification program during the effective term of his or her current license and that he or she has discharged license responsibilities competently and safely.
The requalification training program consists of four interrelated elements:
o Requelification Examinations o On-the-Job Training o Pre-Planned Lecture Series o Special Retraining Programs Specific retraining programs may be necessary for certain licensees. Exam f ailure or unsatisf actory performance will require that the deficient licensee meet with the appenpriate acade=ic review board. The academic review process is a three tiered program of progressive corrective actions designed to upgrade knowledge and skills identified as deficient. The three levels in the academic review process are:
- 1. Staf f Counselor Interviews,
- 2. Alert Status Review Board, and
- 3. Performance Review Board. ,
Any academic review board that is convened will make recommendations as it deems necessary to upgrade deficient areas. The recommendations of the Performance Review Board may include immediate removal from licensed duties.
The following paragraphs provide a general description of the requalification program:
- a. Requalification Examinations Each licensee will be administered examinations at the end of each training module that will parallel, in content and degree of diffi-culty, segments of an NRC Licensing Exam. These examinations are 4
designed to meet the requirements of the requalification modules' 55 13.2-9
INSERT F The Licensed Operator Requalification Training Program has been prepared, within the framework cf a systems approach to training, to comply with 10CFR55
' Operators Licenses.' The content-and schedule of requalification training are established by the operations Curriculm Advisory Conunittee (CAC). The CAC includes, but is not limited to, the Operations Training Manager, the
' Operations Training Supervisor, and a representative of Operations Department management, s
i I
v 1
. SB 1 & 2 Amandm2nt 58 FSAR April 1986 obj e c tives. At the completion of each annual cycle, a sufficient number of exams will have been administered to parallel, in content and degree of difficulty, a complete NRC Licensing Exam. All graded exams will be retained as a part of the training records. The results of the exams will be used to evaluate past training, and to aid in determining future retraining. The licensee must achieve an overall grade average of 80% or greater at the completion of each annual cycle. Any licensee with an exam score of less than 70% will be required to meet with the appropriate academic review board and carry out any recommendations handed down by the board.
- 1. Written Examinations A written examination will be administered to all licensed individuals upon the completion of each requalification module.
The written examinations will be consistent with the individual's license level and will contain appropriate questions from the following topics:
o Theory and Principles of Reactor Operations o Heat Transfer, Fluid Flow and Thermodynamics o Features of Facility Dssign o General and Specific Plant Operating Characteristics o Plant instrumentation and Control System o Plant Protection Systems o Engineered Safsty Systems o Radiation Concrol and Safety o Applicable Portions of Title 10, Code of Federal Regulations o Fuel Handl146 and Core Parameters o Technical Specificaticas .
o Admialuttative Proceduree3 Conditiene and Limitations o Nualker Industry Operating Experience The-pereen(:) responsible for th; pecparatica of the exasicaeden and-answer-key-and-the-pereente) who reviewed-the-examination-w i-i l-ne e-be-e equ i red-t o-t a k e-t he-examina ritnr.
opersbon.1 '
- 2. D:::::teative Examination Opar14.vart Memonstrative examinationSwill-be-echeduled-fee-each sodule.
1 Thess-examinations can be either simulator evaluations, oral i
examinations or in-plant walk-throughs. Oral examinations are verbal question and answer sessions between student and instructor, usually in a one-on-one setting. In-plant walk-throughs are oral examinations that take place on-site, generally at. the location of the equipment being discussed.
55 l
13.2-10 M
SB 1 & 2 Amendment 58 FSAR April 1986 t
A licensee receiving a module grade of less than 70% will meet with the Alert Status Review Board and carry out the recommenda-tions handed down by the Board. A licensee ree.eiving a module grade of less than 70% more than once will meet with the Performance Review Board. The licensee must achieve an overall grade average of 80% or greater at the completion of each annual cycle. ,
- b. On-the-Job Training In order to maintein an acceptable level of skills and familiarity associated with the Seabrook Station systems, controls, and opera-tional procedures, each licensee will participate in plant evolu-tions. Each licensee will demonstrate operational proficiency through participation in the following activities:
coot..I o Required resetivity manipulations and plant evolutions o Plant simulator exercises '
o In-plant training o Design change, procedure revision, and industry experience review To maintain these skills, licensed operators will actually manipulate the controls; licensed senior operators may either manipulate or actively supervise manipulation of the controls. The simulator may also be used for this purpose. If the instructor has documented taat participation on the simulator is unsatisfactory, the licensee will L meet with the Alert Status Review Board and carry out the
- recommendations handed down by the. Board.
rom r y .
E:ch lieecm -141-annually-participete-in-the-fellowing-1ist of-plant ava19t ane and =haermal/amorgency-conditione-in-either-the i
.planc-control-rooe-or-et-the-plant-simulator:
! o Plaa c-or-reac to r-s t a r t u p-a nd-oowe r-es cala t ion- t o -a-range-whe r e -
reactivity feedback-frou-nuclear-heat-addition-is-noticeable-and
.he a cup-rate-is-es tablished- ,
o Manual-con trol-of-s t eam -gene ra t o r-wa t e r-leve l- or- f eedwa t e r- flow -
i
- d u ri ng - p lan t-s t a rtup-oe-s hu t d own ---
-o Reac to r-powe r-chan ges -o f-10%-or-grea te r- whe re-rod- con t rol-is -in-l - meneel-e Loss of-coolant-including a) - Steam-generator-tube-leaks
.b) - Pressurizer-leaks
- c ) --- La rge-and -sma ll-le aks-lo ca t ed -ins id e -and -ou t s id e -o f-p rima ry-con t ainme nt-( i nclud i ng -le ak-ra te - d e t e rmina t ion - f o r- s ma ll-
-leaks ineide-conte & ament) 4)---Saturated-Reactor-Coolant-System-response o Loas-of-coolant-flow / natural-circulation -
o Los s -o f-a ll- f eedwa t e r-( no rma l- a nd - e me r g e n c y ) -
55 13.2-11 M
a; INSERT PF Each licensee will perform or, in the case of an SRO directly supervise the performance of the control manipulations identified in 10CFR55.59. The control manipulations will be performed, as a minimum, within the intervals stated in the regulation.
SB1&2 Amendment 58
+ FSAR April 1986
-On-a-two-year-cyc le- b as ie -eac r h-li censee-wi l l-par t i c i pa t e-in-t he-
- f o l lowi ng - no rma l-p l an t-evo lu t ions -and-a bno rma l-/ eee rgency-cond i tions-
-in-either-the-pleet eent rol--vooe-or-at-the-plan t-s imu la t or t -
o Plant-shutdown-o Boration-and-dilution-during-power-operation-
-c Reac tor-power-ehengeo-of-l OX -or-g rea t e r-whe re-lo ad-change-i s-periereed-in-manus 1-o Rosator-trip-
.o Turbine-or-generator-trip-
-o Remote-safe-shutdown
- e "ealeer ia-trumentation-fsilure(a)
-e -Leer e!-protective-eystoe-channel (s-)-
-o Mispositioned-control-rod (s)-(or-rod-drope)
.o Inability-to-drive-eontrol-rods o Cond it ions - requ i ri ng-use -of-ene rgency- bo ra t ion -
o Fuel-cladding-failure-or-high-activity-in-reactor-coolant-
.o Malf unc tion-of-automa t ic-con t rol- sys tee ( s )-which-af f ec t reactivity-4 Loss-of-instrument-air-
.o Los s -of-elec t r ic a l- powe r-and /o r-deg r ad ed - powe r - s ou r c e s -
e Lee:-ef-eendeneer-veeuwe -
-o Leee of ee niee re:er e Lees e!--residesi heet rece fd.
c Lees of prieery ceeperest e^^ ling-systee-or- cooltag-to-an-
-individual-component o Leee ef ee =e1 fr:deeter-ee-neeuel-feedwette-syste- feiltree
-o-Maia-ste - h::' (4ee&de er eut:id nr.teineene)
Response to abnormal / emergency conditions should include use of alternate methods of accomplishing a given function, such as alternate methods of core cooling. Exercises involving multiple f ailures may be included. Utilization.of applicable plant procedures and Technical Specifications during the training exercises will be maximized.
Individual and team performance during the abnormal / emergency training exercises will be monitored and a post-exercise critique ceaducted with the licensees. The citiqu cr. uch abneraal/
.eaergency-condition-will b d:er reted-and pindd-in :h; %;nlifi cetice Trairie: reeerde.
In the event that an actual abnormal / emergency condition occurs at the plant and performance of the licensed personnel coping with the condition is satisfactory (as determined by their Unit Shift Supervisor), credit for completion of that evolution may be taken.
Completion of actual abnormal / emergency conditions that occur at the plant will be documented by the On-Shif t Training Coordinator and forwarded to the Training Center to be filed in the license ( . *
- training records.
55 4
13.2-12 53 w _ . _ . _ , , . . . , .
SB 1 & 2 Amendment 58 FSAR April 1986 i
In addition to actual control manipulations accomplished while on shift in the control room, on-the-job training includes o Design Change, Procedure Revision and Industry Experience Review ,
This portion of the program will ensure that completed changes and revisions to plant design, changes to procedures and Technical Specifications and industry experiences are reviewed by each licensee.
o Abnormal and Emergency Operating Procedure Review Each licensee will review the contents of all abnormal and emergency procedures annually.
o Simulator Exercises This portion of the program will ensure that required control manipulations that are not performed at the plant will be performed during the term of the operator's license. The simulator portion of the requalification program will emphasize s'uch areas as infrequently accomplished procedures, required responses to abnormal and emergency procedures, and significant operating events.
o In-Plant Training This portion of the program will ensure that training which is best suited to be conducted in-plant is performed on actual plant equipment. This includes review of major planc .modifi-cations, equipment which is provided with local controls, and simulation of selected procedures (e.g., remote safe shutdown).
- c. Design Change, Procedure Revision, and Industry Experience Review This element provides a system for on-shift review of selected operational experiences and changes to existing operating guidance or equipment. The operational review enables continuous updating of on-l shift personnel and establishes a means of disseminating new or changing information that has not been posted in the Standing Orders Book or the Night Orders Book.
This portion of requalification training will ensure that changes or revisions to the Technical Specifications, FSAR, significant changes to procedures and coupleted facility design changes, are reviewed.
L' hon determined by the On-Shif t Training Coordinator, an appropriate
, procedure revision or completed facility design change will be l included in the review process.
I ss I
t 13.2-13 s1 l ._._ - _ _ _ _ - . - --
4 SB 1 & 2 Amendment 58 FSAR April 1986 In addition, a continuing system will be established so that all licensees review the operating experience of Seahrook Station and aoolicable experiences of the nuclear industry. Selected coerational events and reportable occurrences at Seabrook Station will be analyzed and information pertinent to the event collected. Selected operational information from the nuclear industry will also be reviewed. The following sources of information will he considered, but not limited to:
o Licensee Event Reports o Audit, evaluation, and inspection reports o NRC IE Notices and Bulletins o publications and periodicals covering nuclear industry information o INP0 Significant Event Reports and Significant Operating Experience Reports This information will be-routed-to-411--11ceneces-with-a-eign-of f s hee t .--The-on-Shi f t-Training-Coordina t o r,-in- coope ra t ion-wi th- t he-Shif t-Superintendents-will-ensure-that-al1-on-shif t-licensed--
personnel-review-.the information-in-a-timelv-manner.-The-On-Shif t-Training-Coordinator will-maintain the documentation of this review.
-process.--
--A-copy-of-procedure-revisions r--along-with-a-sign-of f sheet 7 vill-be-
-olaced-in-the-Operational-Review-Noteboole.-During-a-training shif tr-ea ch -li cen s ee- wi l l- re vi ew - th e -co n t e n t s -o f- the -No t e bo ok-and ,- upo n ----
-c ompl e t i ng- the -a s s i gned - re ad i n g ,- wi ll - a i gn - t he - s i gn-o f f- sh e e t , .
s i gni f yi ng - th a t - he- has - re ad - and -und e rs t and s - th e - ch a nge -o r - revi s i on .
-The-STC-will-update-the-Notebook-and-remove concleted naterials to-
-the-t raining-reco rds .
In-ord e r-t o-ens u re-a-con t i eui n g -und e rs t and i n g- o f- t h e - ac t i on-and -
-response-necessary-during-wertenev-or-abnormal-situationsi-a --
comp le t e - rev i ew - o f-all--eme rge nc y-and-shno rmal--ope ra ting-procedur4 s will-be -conducted-by-each-licensee,-over-the-course-of -the annual -
cycle. - An-ackr.owledgement-sheet -will- be -signe.d -and - filed -at the
-Training-Center,---
- d. Simulator Traintne 55 The Seahrook specific simulator will be utilized, whenever practical, to fortify the on-going operator recualification program. Sinulator exercises and evolutions will he oreolanned and scheduled to frecuentiv interface with the Formal Lecture series. The sinulator Recualification Yraining Program will emphasize such areas as infrecuently accomplished procedures, recuired responses to abnormal and emergency procedures , and significant operating events.
13.2-14 M
, - m a e 75 WUltUdJttD6 W
. FSAR April 1986 Exercises w'ill include analy:ing the effects of potential equipment /
system malfunctions, possible causes and recommended operator responses. A program objective shall be involvement of Unit Shift Supervisors and Shif t Superintendents in the capacity of operations assessment and accident analysis during refresher exercise training. A-portionaf-each-week 4-eimulator-time r-not-to-exceed-
-twe n t y-pe r ce n ty-will-be-alloc a t ed-fo r -s peci f i e-applica t ion s-req u e s t ed -
-by-the-Unit Shift-Supervisors / Shift-Superintendents.--The-simulator-will-also bo-used-as-a-means-of-evaluating-and-indicating-areas-
- requir-ing-further-retraining upheede.
- e. Retraining Lectures for License Holders A formal cla'ssroom lecture series, including exams, will be conducted each year as part of the Requalification Program. The level of instruction for the retraining lectures will be consistent with the level of license held. The lecture series will be organized into separate training modules of instruction divided among the program topics and appropriately scheduled throughout the year. This lecture series will cover two general areas:
o Fundamentals and Systems Review o Procedures and Administrative Controls Fundamentals and Systems Review lectures will cover topics in which the standard source material is relatively constant; for example, reactor theory, plant design, radiation control, etc. These lectures will include instruction in heat transfer, fluid flow, the rmo-l dynamics, and mitigation of accidents involving a degraded core.
I Trocedures and Administrative Controls lectures will cover topics involving essential plant operational guidelines; for example, technical specifications, administrative procedures, major plant
- evolutions, etc.
1 All licensed individuals will be required to atrand each lecture included in the annual program. Attendance will be recorded and absence will be made up during the current annual cycle by rescheduling or by utilizing self-study and discussion with knowledgeable personnel. The absentee will be required to pass an exam covering the material presented during the missed lectures.
- f. Performance Evaluation and Review
-Requalification-training-program-ef f ec tiveness-shall-be- moni tored-es
-described-in-subsection-l h 2.-Irl .
At least once per year, each licensed operator will be observed and evaluated while responding to either real or simulated abnormal or emergency conditions. The evaluation will be performed by the individual's immediate-espewiser or a member of the Training Center Setff. w('* ** 7* Nj "
l i 13.2-15 l 5%
1
.. - .- ~ -.- - . . -.- - - .. ..
7
. i SB~1 & 2 Amsndmsnt 59 FSAR May 1986 An academic review board as described in 13.2.1.3 will be conducted !
when any of the following ' situations occurt sy '
o A licensed operator receives a modular exam score of less than !
70 percent during the annual cycle, or an annual overall grade '
average of less than 80 percent.
i A licensed operator receives a poor performance evaluation. t o
4 Prier-to-reeuming-et-seeuming-eetive-license-responsibilities-
-af ter-absenee-of-four-monthe-or-4cag*F-f roa-setively-performing.
-the-funestone-of-en-eperater er ;er.ier-operatorv--- !
51 l 3
The purpose of the review will be to determine a course of action ;
necessary to upgrade an individual's performance to a.n acceptable l 1evel. A supplemental training program will be established to up-
- grade areas where deficiencies are shown.
3 53 The review will be conducted as soon as practical af ter one of the ,
j above conditions occur. The action taken will be dependent on such i f actors u examination performance, watch standing performance, i observed operational performance and judged overall competence.
.- An -ac ademie- rev iew-w i41-be-e endve ted-to-de te rm i ne- t he-nec e s s a ry-se t ion s- l
.co be-performed by-a-liceasse r -prier te aesuming-responsibilities-at-- s9 t
. any-operat senal-ehif t-level f-ROr-SR0r-Uni-t-Shi-f t-Supervisory-Shif t-Superintendent.-Typically-this-review-would-address actions-to-be- l
. performed-by-an-inactive-licensee-prioe-to-being placed-in-en-operating- 59 j pos i t ior- req u i r ing-a-l ic ense r---The-re su l t s-o f--t h i s-re v iew-w i l l-be-u sed - 1 e to-c e r t uy-to-the-c ommi s s ion-tha t-the-lic e nsee ls-know led ge-a nd-unde r- !
j .s t and ing-o f- f ee ili t y-ope ra t ion-and-admin i s t ra t ion-a re-s a t i s f ac tory ra e- .
-sequired-by-lMFMG. . m .
4
- g. Requalification Training Program Records 1
Requalification training program records will be maintained for a !
minimum of two years from the date of the recorded event to document i che participation of each licensed operator and senior licensed
, operator in the program. The records will include copies of written examinations administered, the answers given by the licensee, results of evaluations, and documentation of any additional training in areas in which the licensee had exhibited deficiencies.
I JWS ER T G j 1L L 13 Replse::::t 0;eratee-License-Training-s i 4 ad iv idual-advaneamen t-to-ine reas i ng -le ve ls -o f- res pon s i bi l i t i e s - as -oppo r- N tuni t ies -deve lep -wi t h in - t he -o rg ani s a t ion -wi ll- be - e nc ou ra ged .-To r - en
- individual-to-edvance-to-e-sore-responsible positionrhe must-be-fully-l qualtfied cechnically7nd possess sufficient experience to meet the job-
- e*9 wee *m***** ,
) i i
13.2-16
SB 1 & 2 Amsndm3nt 59 FSAR Ksy 1986 An academic review board as described in 13.2.1.3 will be conducted when any of the following situations occurs sy o A licensed operator receives a modular exam score of less than 70 percent during the annual cycle, or an annual overall grade average of less than 80 percent.
o A licensed operator receives a poor performance evaluation.
o P r io r- to-re s umi ng-o r -as s u mi ng-ac t i ve-l i c e n s e - r e s pon s i b i li t i e s -
.-af ter-absence-of-four-months _or-longer f rom-actively-performing.
- t he-f u nc t ione-o f-an-ope r a t o r-o r-s e nio r-ope ra t o r .
M The purpose of the review will be to determine a course of action necessary to upgrade an individual's performance to an acceptable level. A supplemental training program will be establisted to up-grade areas where deficiencies are shown.
The review will be conducted as soon as practical af ter one of the above conditions occur. The action taken will be dependent on such factors as examination performance, vacch standing performance, obssrved operational performance and judged overall competence.
An-ac ademic- rev iew-w i41-be-conduc ted-to-d e te rmi ne- t he-nec e s s a ry-ac t ions- l to be-performed by-4-licensee r -prior-to-assuming-responsibilities-at- 59 ,
. any-opera tional-shi f t-level-t-ROr-S R0r-Unit-Shif t-Supervisarr-Shif t-Superintendent r--Typically-this-review-would-address actiong-to-be- l
. p e r f o rmed -by - a n-i nac t ive-l ic e n s e e-p r io r-to-be ing-p l a c ed -in-a n-op e ra ting- 59 p o s i t i on - requ i r ing-a-l ic e n s e r--The-re s u l t s-o f-t h i a- re v iew-w i l l-b e-u sed-
. t o -c e r t i fy-to-the-c omm i s s ion-th a t- the-l ic e n s eel s -knowled ge - and -und e r-
.s t and ing - o f-f ac ili ty-opera t ion-and- admin i s t ra t ion-are-sa t i s f ac to ry.-as-4equ ired-by-MGFR5 b 31 M .-
- g. Recualification Training Program Records Requalification training program records will be maintained for a minimum of two years from the date of the recorded event to document the participation of each licensed operator and senior licensed operator in the program. The records will include copies of written examinations administered, the answers given by the licensee, results of evaluatio As, and documentation of any additional training in areas in which the licensee had exhibited deficiencies.
invSn27 G 13-2-1 A Re pla ce menc -O pe ra t o r-L i c e n s e -T ra in in t
-Individ ual-advance me n t-t o-inc rea s i n g -levt is -o f -re s pon s i bili t i e s -as -oppo r-- SI
.tunities-develop-within-the-organization-will-be-encouraged. -For -an----
individual-to-advance-to-a-more-responsible position,-he mus t-be-fully-qualified cechnically and possess suffit:1ent experience to meer the job-eequirements.
13.2-16
s INSERT G i
13.2.1.5 Activation of Inactive License Program An inactive license is defined as a license held by an individual who has participated fully in the Seabrook Station Licensed Operator Requalification Program but has not actively performed the functions of a operator or senior operator for a minimum of seven eight-hour shifts or five twelve-hour shi' M per quarter.
An individual who holds an inactive license and is required to restore the license to active status will participate in the Activation of Inactive License Program. The program includes a minimum of forty hours of shift functions in the position to which the licensee will be assigned after the program. The licensee will stand watch on shift but will not be the watchstander of record.
The Operations Training Manager provides a checklist of activities / tasks that must be succersfully completed by the individual who is activating his or her license. Upon completion of these requirements, the licensee participates in two separate interviews, one with a Shift Superintendent and the other with !
either the Operations Manager or the Assistant Operations Manager. When the interviewers are satisfied that the licensee has rufficient knowledge of the .
, plant operations to stand watch as a crew member, they sign a Certification of l Completion of Training, activating the license. The Operations Training Manager also signs the certification form.
i t
l l
l l i i
SB 1 & 2 Amendmsnt 58 FSAR April 1986
\
\
- a. Replacement Operator License Training Program av Hampshire Yankee has recognized the need to have a Repla ment g Operator License Training Progrars which will continually en re the samdghigh quality of licensed personnel as the Initial Ope ator License Training Program. To this end, the replacement ogram for licensed operators will include the'same segments as th initial Operator \ License Training Program. Waiver of specificj rogram elements defined below may be granted based on a procydurally U administered review of each individual's education, formal training and experience. Prior to granting a waiver, a date ination will be made that the\ objectives of the waived element are met for the license level sought. Documentation of the form review and the conclusions reached will be maintained. Credit ill be taken for previous formal tisining and experience receiv in an individual's progression to the ' license level the person i seeking.
\
Thetrainingprogramwillincludeasaminim/ um the following 45 47 elements: \
- 1. Classroom Instruccio
\
Each license candidate will atte d a formal on-site school of sufficient duration, to complet prescheduled lectures in the following areas:
Nuclear Reactor Fundamentals 1 - see Subsection 13 2.1.1.b. l M
FormalOn-SiteSchool-se/ e Subsection 13.2.1.1.d.
N
- as The lecture program may be supplemented by the video tape program, as determinec) by the Training Center Staff. Periodic quizzes and exams will be administered to ensure student com- l prehension and rete ' tion. To further evaluate each student's M acquired knowledge level, a final exam wi,11 be given at the conclusion of th classroom phase. The final exam contents and degree of diffig lty will parallel that of an\ NRC operator
- license examination or senior operator license examination, as applicable. /
/
- 2. Control Room Experience Each licen/se candidate will receive on-the-job ext.erience by l particip'ation in discussions with on-shif t operators'\and by the M discuss /' ions will be directed to topics such as systems \ actual perfor '
intelface. control capabilities and instrumentation available in the control room. Particular emphasis will be placed on ' system l
operating characteristics and possible malfunctions. License candidates will participate on shift inthepositionofthe\
license being sought, under the direction of a licensed operator l for a period of three months. \ M l \
45 13.2-17 l
l
SB 1 & 2 hendment 58 FSAR April 1986
- 3. Simulator Trainin'g he Replacement Operator License Training Program will inclu tYsining on the Seabrook-specific simulator. This phase of the pro' gram will emphasize normal, transient, and emergency operkions. In the training, each license candidate pe orms controlsroom duties at the simulator as a member of a f ift crew. Each crew will be given the opportunity to wicdess and respond t'6gnumerous exercises involving system and omponent malfunctions The crews of icense candidates will receive t rough practice on the simulatorNin carrying out the followin plant operations:
a.
N Integrated Operations - Bringing the lant from 10% power to 100% power ac ording to normal o rating procedures;
- b. Plant Cooldowns an N H eacups - Pe orming a plant shutdown, cooldown, heacup, andgstartup ing normal plant operating procedures,interrupte(byocasionaluseofabnormal operating procedures fo r malfunctions;
- c. Reactor Startup - Implementing reactor startup using the applicable plant procedu'res;\and
- d. Transient and Acciden/ t Analysis \ esponding R to plant i malfunctions and epergencies throhqh use of the abnormal and emergency pladt operating proce'dures.
51 i
- 4. Pre-License Audit .
In addition to Jne final exam administered at completion of classroom training, an oral station walk-througliNwill be given to each candidate to further insure that the individual is properly pr,e' pared and is, in f act, capable of compe' rent and safe operationAf the station controls. This oral walk-through will be give /by a senior licensed member of the unit staffhoran indepe ent party, prior to the individual being permitted to takejche NRC licensing exam. The areas that are to be st'ressed %
l while conducting these walk-throughs are simulated malfunction and' emergency situation response, local instrumentation and '\'
control, and general plant hardware.
/
l
? -
i 13.2-18 l
l
A SB 1 & 2 Amendm:nc 59 FSAR Mcy 1986 6
13.2.1.5' Applicable NRC Documents e
The training program will be devdindadt.ee ope an' t=plemantad in accordance with the applicable requirements of the NRC Code of Federal Regulations and meet the intent of the recommendations provided by the applicable Regulatory Guides and applicable NRC reports listed below:
10CFR Part 50, "Jomestic Licensing of Production and Utilization Facilities" l xi 10CFR Part 55, "Operator's Licenses" 10CFR Part 19 "Notices , Instructions and Reports to W'orkers; Inspections" Regulatory Guide 1.8, "Personnel Selection and Training", Revision 1-R, September 1975 (re-issued May, 1977), with the exception that ANSI /ANS 3.1-1981 will be used as the standard in lieu of ANS 3.1/ ANSI 18.1-1971 l 53 Regulatory Guide 1.101, "Eme,rgency Planning for Nuclear Power Plants",
Rewision 2, October 1981 Regulatory Guide 1.149, "Nuclear Power Plant Simulators for Use in Operator Training", Revision 0, April 1981 4541 Regulatory Guide 8.2, "Guide for Administrative Practices in Radiation Monitoring", February 1973 Regulatory Guide 8.8, "Information Relevant to Insuring that Occupational Radiation exposures at Nuclear Power Stations will be as Low as Reasonably Achievable", Revision 3, June 1978 Regulatory Guide 8.10. "Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is R&asonably Achievable", Revision 1-R, September 1975 Regulatory Guide 8.13. "Instruction Concerning Prenatal Radiation Exposure",
Revision 1, November 1975 "Utility Staffing and Training for Nuclear Power", WASH-ll30 Revised June.
1973 L98 7 "Operator Licensing Examiner Sttndards", NUREG-1021, October &9&3- l
\ \
l "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommenda-l tions", NUREG-0578, July 1979 l
l 13.2-19 1
SB A & 2 Amendment 58 FSAR April 1986 ANSI /ANS 3.1-1981, "American National Standard for Se1ection and Training of l Nuclear Power Plant Personnel." #
ANSI /ANS 3.5-13f, Nuc1 ear rower riant Simuistors for use in operator T raining . "
"Nuclear Plant Fire Protection Functional Responsibilities, Adrainistrative O
Controls and Quality Assurance", issued by USNRC letter in August, 1977.
NUREG 0737, November 1980, "C1arification of TMI Action P1an Requirements".
. 45 13.2.2 Training for Technical and Management Staff
- a. General Discussion
^i A comprehensive training program is in place for technical and management personne1, complying with the provisions and intent of NRCl SI Regulatory Guide 1.8, Revision 1-R, with ANSI /ANS 3.1-1978 ut.ed as g the stand rd in lieu of ANS 18.1-1971.
M The program vill provide personnel involved wich' the startup and operation of Seabrook Station training in various disciplines necessary to ensure that each can safely and effectively perform his d assignments. The degree to which an employee is trained will be consistent with his experience, -intended- position, and regulatory 5T
- " " / / M requirements.
The overall objectives of the training program are To train a staff to operate and maintain the units safely, dependably, and eenomical1y.
To prepare technical service groups fo* 3eir functions necessary for the support and safety of plant operation.
- b. Responsibilities 1 -The following-Seabrook-personnel-ere-responsibie-for-this-trainingt- l 45 M
- 4. Station-Manager I
.T he-sea b rook-s ta t ion-Manage r-hae-t he-ove r a l l- re s pons i b i l i t y -f o r tha-qualification-of-personnel. He-vi ll-- r e v i ew- a nd -s pp rove-a l l-plant-training-programar l
% r es e.o ;, h ,' t ; t ,'er L ' *" P* #"t 'U * " O t " ' "1 f '*I "' '
,n s. L ,a ,a a v A.
~
l
- 13 2-20 l
l .- -- - --
.* In SB1&2 Amendment 58 FSAR April 1986 y
-2. A::(-seene-Geet10 ":::;;;r =
^'
The-Aeetetent-Stetic ";;: g : s-le-eeepene-ible-to-t he-S t at-len-Manager-f or-edninist eet ion-of-e l-1-t he-t eeining-eeurses-of-the-
! -T reining-Depeeteene r-Th A::istent -44etion-Nenesee-wi-H-review-all-ef-th::: ;;eeee-ennweHyc
, 51
- 4. Trainint-Manege-l Mi
-The-Teetat g " : ::r--r:p: rte to th; Aseistent-Stetten ".;;;;;e- I
-and-Le-responsible-for devele;;::t, =1aplementation-eatr ST
, -administrettee ef-General- and-spostelty-treising-taeludiag- l
-Gene ral-Employee-T roiaing ,-Fi re-Eri g ade-Training-end-Special i s ed. H I
Traininge
- 4v. --Training C
- :ter " ::;;;r
-The-Training C ter ":- ger is-eeepenethle-for d:v:10;;:ntT-
-implementation, : d administration-of-Auxi-11ary-Operator-t rainingv-
, 13.2.2 1 Program Description M
! Several basic categories of training help technical personnel to attain a high l 1evel of competence and professionalism. Specifically, these categories include the following:
, 4G i
- s. Initial Orientation All persons joining the Seabrook Station operational organization, regardless of job assignment, initially will receive orientation training. This phase of training consists of a brief informational M program explaining site organization, employee benefits, company l policies and procedures.
M
- b. General Employee Training j General Employee Training wi4} :: ;6+t of six programs covering site familiarization, security, radiation protection, industrial safety including fire safety, the radiological emergency plan, and quality l assurance. .TM : propriate-Station-pereennel-will d:::lep the l pregr= :: t::t --f t::tiet. The program assumes that the new employee has no f amiliarity with nuclear power plants. A rest a prea M l
- t. s 9 eke a kss.
( c. Supervisorv Training i Supervisory training is provided for working foreman, supervisors, l senior engineers, managers, and section leaders.
- A5 %
~js p <* .*oJ ni i =
- ll f ' ' * "" " l ' 1 * ' " "1 " " " ' * " #* "' N' inres. Its. w sts i 13.2-21 l
l l
531&8 Amendment 58
. FSAR April 1986 i
Supervisory indoctrination training includes but is not limited to (1) company organization, l2) purchasing procedures, (3) records '
familiarization, (4) r it ree;ence,-(4)-res*1et d ri weitenment M W 4
techniques (7) eefety, rof' (8) supervision technicalincluding hiring writing, N andonmMi.e.//;!,m Sekdr personnel appraisal,4 /.ed. n a ad O) . a 4. ,.,Lu.a.
In addition, all supervisors receive a program in problem analysis, decision analysis, and potential probles analysis. All supervisors , except in non-technical areas such as security and administrative services, participate in plant systems training. Meet- l
-supervAsere-will-soeplete-a-program-in-the-psychology-of-motivationy M
-4:Saatsstiemal-elisat* rend-ennegeriel-styles.
T.vS s12 T H
- 4. Departmental-T raining -
the-particulars-of-this-training-appear-in-Subsection-13.2.2.4.-
-Figure-13 2-2-showe-approximate-time-f rames-for-accomplishing this - M training.-The-training-schedule--is-intended-to-minimise-conflicts -in -
manpower-requirements-during-preoverational-testing.
- e. Fire Protection Training The fire protection traictag program for Seabrook Station follows the l guidance provided in the NRC document entitled "Nuclear Plant Tire %
Protection Functional Responsibilities, Administrative Controlu, and Quality Assurance." A doucription of that training program follows here.
- 1. Fire Brigade (a) Instruction Fire Brigade members receive instruction in the c6 pics l below, as well as in any othera deemed necessary by the M instructors.
(1) Fire hazards and associated types of fires that could l occur in the station, and the location of the hazards, M including areas where breathing apparatus is required, regardless of the size of the fire.
(2) The location of installed and portable fire fighting l equipment in each area, and familiarization with M layout of the station including access and egress routes to each area.
13.2-22
b 6
INSERT H
- d. Technical Staff Traininp.
The Technical Staff Training Program provides training for the engineers and supervisors employed by New Hampshire Yankee. The program is systematically developed to provide broad-based training for supervisors, engineers, and technical staff who support the day-to-day operation of the plant. The program is intended to supplement position-specific education and training in order to broaden the knowledge of the plant's technical staff, thus enhancing their abilities to perform assigned duties in a manner that promotes safe and reliable plant operations.
b l
SB 1 & 2 Amendment 58 I FSAR April 1986 (3) Use of available eqaipment, and a recommended method l of fighting different types of fires, The types of 51 fires covered will include electrical fires, fires in cables and cable tray, hydrogen fires, flammable liquids, waste / debris fires, record file fires, hazar-dous process chemical fires and fires resulting from construction or modification work. { l As si (4) Ind.octrination in the station fire fighting plan, with coverage of each individual's responsibilities, including changes thereto.
(5) Use of breathing equipment, communication, lighting l 65 and portable ventilation equipment.
(6) A detailed review of fire fighting strategius with l 51 particular emphasis on what equipment might be used in particular areas.
(7) A review of latest modifications, additions or changes to the facility, fire fighting equipment, fire fighting plan, or fire fighting. strategies.
(8) Fighting fires inside buildings, tunnels. and other 51 confined spaces.
(9) Fighting firea when a radiological hazard exists. l s1 (10) The toxic and corrosive characteristics of expected products of combustion.
45 Fire Brigade leaders will receive the above listed instruc-tions and special instruction in directing and coordinating l fire fighting activities. s1 (b) Practice In addition to the classroom instruction above, all fire brigade members will attend regularly scheduled (at least annual) practice sessions on the proper method of fighting various types of fires. These sessions will provide 45 brigade members with hands-on experience on extinguishing actual fires using the equipment available to them in the station. Practice sessions will also be held wt.tch require fire brigade members to don protective equipment, including emergency breathing apparatus. l 51 7
13.2-23
SB 1 & 2 Amendmsnt 58 FSAR April 1986 (c) Drills Brigade members will practice as a team in periodic drills. These drills will include the following:
ST (1) Simulated use of equipment for the various situations and types of fires which could reasonably occur in each safety-related aren.
(2) .Conformance, where possible, to the established ses- l tion fire fighting plans. 51
.(3) Operating fire fighting equipment, where practical.
This includes self-contained braathing apparatus, com-munication equipment and portable and/or installed ventilation equipment.
The drills will occur at regular intervals, but not to exceed quarterly for each fire brigade. The minimun number of fire brigade drills conducted within a quarter will equal the nuaber of operating shifts at the station. Each individual member of the fire brigade will participate in Si at least two drills per year. At least one drill per year for <h fire brigade will be unannounced. At least one dr2 jer year per brigade. will be on a backshif t.
As Pericdically (at least annually), a drill will involve off-site fire departments. Preplanning will establish the training objectives of the drills. A critique will deter-mine how well the training objectives have been met. At a minimum, the critique will assess 53 (1) Fire alarm effectiveness, response time, selection,
, placesent and use of equipment.
1 l
(2) The leader's direction of the effort and each member's response. ,
- 2. Other Station Emplovees All full-time employees will receive instruction on fire protec-tion safety, evacuation routes, the procedures for reporting a l fire, 2nd 2n-; ether eubject d :::d neeeeeecy.
45 l
l Security personnel will receive instruction on procadures for l
entry of off-site fire departments, crowd control, and l l procedures for reporting potential fire hazards observed when ST
! touring the facility.
l Temporary employees and construction personnel will receive the '
instruction in reporting fires, alarm _ response, and evacuation routes.' n (Jd d pner.d espig e ha,e.g .
13.2-24 1
.c . - , _ - - , - . ~ . - . . - , , , . . - . . , - , , . - . . - - - - . -
SB 1 & 2 Amsndmant 58 FSAR April 1986
- 3. Fire Protection Staff Training for the fire brigade and personnel responsible for issuing Ignition Source Fire Protection Permits will include courses in the design and operation of fire detection, suppression and extinguishing systems, and fire prevention techniques and procedures.
- 4. Off-Site Fire Department The training for the Town of Seabrook Fire Department will "I
include informatio.. on basic radiation principles and practices, and typical radiation hazards that may be encountered when fighting fires.
5 Refresher Training The fire pre:ection refresher training program for fire brigade members and for of f-site fire departments will be conducted on a 1 two year cycle. Ref resher instruction will be provided to all fire brigade members on a quarterly schedule and will include a l review of any changes in the fire protection program. Other 41 station employees receive annual raf resher training.
- f. Training for Mitigating the Consequences of Core Damage Special training for mitigating the consequences of cote damage is in L.chn.aQunem4 place for applicable 3 personnel. -fsee-Table-Br2-3r)- Instruction for A7 Jad n ev osua / this program reflects INPO guidelines for subject material.
As 51 13.2.2.2 Coordination with Pre-Operational Tests and Fuel Loading The training for technical and management employees is scheduled to minimize any conflicts in manpower requirements during the unit's preoperational testing and fuel loading. The positive training effects gained by actual 51 j
l participation in these phases of the startup will be incorporated in the l
training program.
l The-s cheduling-in te r f ace-be tween-the -gene ral-and -s pe cial t y-t ra ining-prog rem- l l and - the- s t a r t-up-is-11-lu s t r a t ed-in- F4gu re-13 r2-2. as l 51 13.2.2.3 Training Department Staff Elwl The training staff for this training consists of a, Training Manager and Tahoaal several technical instructors. The
- Training Manager has extensive experience l as a professional vocational educator, with a background in curriculum development, teacher training, supervision, and management.
He has had training in Seabrook Plant Systems. Er.ch training instructor has significant experience in one or more technical fields.
5%
! The staffing levels of the Training Department are based on a periodic eval-uation of station training requirements.
t AS 13.2-25 l
1
l SB 1 & 2 Amendment 58 FSAR April 1986 13.2.2.4 Departmental Training Programs [
In addition to the training described in 13.2.2.1, the programs described below will train the individuals who comprise the initial staffs of various station departments.
- a. General Technical Training 53 Instrument and control, chemistry, and health physics technicians, and maintenance mechanics and electricians receive an indoctrination program followed by nuclear power plant fundamentals, radiation M
, /,,uA/. 5 worker training, and site tagging instructionf Pretests may exempt an employee from portions of this training. Further training is M specific to the department as described below.
- 1. Health Physics personnel receive a program on health physics fundamentals and a program on health physics procedures. These programs are based on a site-specific task list. #
unau H&
- 2. Chemistry-techniciat,s-receive a course-in chemistry-fundamentals l followed-by-courses-in-analytical-chemistry-and-primary- 4 chemistry-related-to-plant-specific-procedures -and processes.
T hes e-cou rs es -are -followed-by-a- de tailed - chemis t ry-sys tems -
course-which-correlates laboratory-analyses-to-plact-system
. chemistry. , -. .
Certain-chemistry-techniciens-wi-1-1-receive-trainir.g-in-the use' ~
of-a-mult1-channel-analyzer-for-gamma-ray-an'. lysis. --
45 l Che mis t ry -t raining -con t en t -and-du ra t ion -are - ba s e d -on -a- s i t e - s pe-l cific-task-list.
- 3. Instrument and control technicians receive training in process l instrumentation and controls. Selected technicians, based on a e i site specific task list, are trained on selected plant protec-l tion and control systems including the solid state protection system, the 7300 process system, the nuclear instrumentation system, the rod control system and the rod position indication i system. Also, based on a site-specific capk list, selected 6 technicians are trained on additional plant systems including
! the radiation monitoring system, the main turbine electro-l hydraulic control system and selected plant fluid and electrical l systems.
l 51 i
I 1
13.2-26 l
i+1 .
INSERT HH Chemistry technician training course contents and duration are based on a site specific task list. The courses are divided into four fundamental areas:
- Basic Chemistry
- Instrumental / analytical chemistry
- Plant systems chemistry and chemical control
- Radiochemistry and radiochemical analyses.
Chemistry technicians are also trained on some specific analyses through OJT modules which are also based on job task lists. Finally, the technician's qualification to perform chemical analyses for plant systems is reviewed by chemistry department personnel, and signed off individually on the technician's Qualification Card.
1 i
1._
SB 1 & 2 -Amendmant 58 l
FSAR April 1986 I 4. Mechanics receive training in hand tools, basic mechanical main-tenance, and mechanical maintenance of site equipmentfwhtd4-Ls 3,
"' -'~~~ based on a si'te-spiicifiP task lis t. Certain-maintenance-
~
7"'
personnel-receive? Training in such areas as bolting, snubbers, advanced welding, vibration non-destructive and hydraulic wrenchesh examination, crane4-operation, m/W/e h-- a /" M -'*
reg w n>, sul t<<uay,
. 5. Electricians receive training in hand tools, basic electrical I maintenance, and applied electrical maintenance of site l equipment as determined by a site-specific task list. ,
L, ,t
- 6. Auxiliary operators receive up,t.btg te 3 weeks of initial training. The leogth of the training depends on the entry-level skills and knowledge of the trainees. The training consists of l classroom instruction on the primary and secondary plant systems
! and structured on-the-job trtining performed under the
( supervision of a qualified watchstander.
1 Activities included in the on-the-job training are systems walk-throughs, performance of shift duties, equipment and systems l
operations using plant operating procedures, and implementing surveillance inspections and checks on operating equipment.
l I
Following the initial training and assignment to regular shift duties, the auxiliary operators autLL return to training on a rotation plan to receive continuing instruction on plant equipment and systems.
13.2.2.5 Position Task Analyses ry.w 12 gg I n i t ia l-t ra i n i n g-u t i l i z e s -d e s c r i p t io n e -o f-j o bs-and-t a s k s-a s -p ro v id ed -by - e a c h --
department. The-Traiting-Department; with-the-help of the rechnteri d e pa r tmen es-is-usieg-t he-gene rie-te s k-a na ly s es-p rov id ed -by-INPO-end-is-mak i n g -
these-site-specific.--We-modify-training programs-based on the results of-t he s e-t ask-lis t s .-- g3 13.2.2.6 Program Evaluation ,
Testing accompanies most orientation and all skills training. Tests include proficiency exams and written exams. Annual reviews-of-training-provide feed-ba ck-f rom -dep a r tmen t-su pe rv i s o r s-on- t he-pe r fo rma nc e -o f-employee s -a nd - t h e - ne e d si for-retraining- or--additional-training-to-upgrade-skills.-- Annual- personnel --
appraisal- procedu re s- provid e- the - means - f or- supe rvision ~ to -indica t e -- -
-developmental-training needs-for-each-employee-during his next-appraisal.
-pertodo ~lili g pig.4, .yr,s..nh A, /Ja ,y /a, m La f.sa e! pig <.,as f. e/x,<
45 Liasop </Arfima.
4 13.2-27
a INSERT I Initial training utilizes descriptions of jobs and tasks as provided by each department. The Technical' Training Manager, with input from the station technical departments, developed site specific task lists based upon the INP0 generic task lists; new job activities will be identified in later revisions of these task lists. Training programs are modified based on these task lists.
i I
i l
t
' ^
SB 1 & 2 Am2ndmant 58 FSAR April 1986 13 2'.2.7 Retraining Technical personnel will receive retraining in the following subjects: l 54 Appropriate Administrative Procedures Radiation Protection Security Procedures Radiological Emergency Plan Fire Safety Safe Work Procedures Sk.hs%aaq~ as reguoM j This refresher training will be scheduled on a periodic basis / buo-noo-less-
-than-every-two-years, following receipt of an operating license. Also, periodic drills will reinforce procedures to be followed in the event of 51 radiological or fire emergencies.
13.2.2.8 Replacement Training Training to fill vacancies in the supervisory, technical, and maintenance staffs assures a sufficient reserve of qualified individuals. This training will be essentially equivalent to the program described in 13.2.2.1.
4E 13.2.2.9 Emergency Plan Training All persons assigned to the emergency response team will receive training to p perform the functions of their position. They will also participate in l periodic drills to ensure that they have maintained the ability to perform their tasks effectively.
53 1
1 l
l 13.2-28 l
l
SB 1 & 2 Amsndesnt 52 FSAR Decerbar 1983
./
,/
TABLE 13.2-1 . j/ .
(Sheet 1 of. 2)
Comparison of NUREG 0737
' APPENDIX C TO SEABROOK STATION OPERAIOR LICENSE PROGRAM
/
s CUMULATIVE CONTACT HOURS APP C SUGGESTED
/
PrerequisiteBeyondHighhchool Mathematics- 90 45 45 Chemistry 30 45 45 Physic s , 150 165 165
/
College Level Fundamentals Mathematics 90 120 Reactor Theory. 100 90 135 Reactor Chemistry 30 45 Nuclear Materials 40 90 Thermal Sciences 120 Thermodynamics 90 Fluids 45 Heat Transfer 45 60 45 Elec trical Sciences /
Nuclear Instrumentation & Control 40 45 45 Nuclear Radiation P[otection &
Health Physics j/ . 40 45 45-Applied Fundamentals' 460 \350 530 Plant Specibcs 120 Plant Syste'ms 200 Administra'tive controls 80 \
Operatipk Procedures 30 s Transient / Accident Analysis & '\
Emefgency Procedures 30
\
ManagerInt/ Supervisory 40 215'N Simul'ator Training 100 280 280*
/ kS63 em
SB 1 & 2 Amsndssnt 45 FSAR June 1982 N
TABLE 13.2-1 .
(Sheet 2 of 2)
- - Minimum of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> in the position fa supervisor directing activities.
RO -- Reactor Operator ,
SCR0 - Supervisory Control Roonr' Operator USS - Unit Shif t Supjer isor' '
SS - Shift Supe ntendent 45 1
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SB 1 & 2 Amendmsnt 49
. FSAR May 1983
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TABLE 13.2-3 PARTICIPATION IN TRAINING FOR MITIGATING CORE DAMAGE
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Note: These subj.e t areas g
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-s 49 Station Manager / \ /
X X X X X X Asst. Station Manager X NX X/
Technical Services Manager / 'j! X X X X X X Asst. Tech. Services Manager X ,
Chamistry Dept. Sup'v. X
/
j \ \
X X X X X X X X X X X X Maintenance Dept. ~ Sup'v. X j
I & C Dept. Sup'v.
,X' \ s X X X X X l X Reactor Engr. Dept. Sup'v. j X X yX X X X X X X Engr.ServicesDept.Sup'v./ X X Xg X X X X X X X Health Physics Dept. Sup'v. X X X Xs X X X l
Computer Dept. Sup'v.//
X \
l X X X 'y X X X X
ReactorEngineer[ X s
/ 'N Health Physicist / X X X X
Technici,ans /
/ X X X X Chemist /Tedhnicians
/
X X X X X Auxilia[yOperator X X X X
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X X X X X X Lie dsed Operator (SRO, RO) X X X y'
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ENCLOSURE 3 TO NYN-88048 Changes to FSAR Section 13.3 i
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13.3 EMERGENCY-PLANNING
- . . h25 been A comprehensive Radiological Emergency Plan for Seabrook Station i+ provided as a separate volume to this application.j The.Seabrook Station Radiological Emergercy Plan was developed in accordance with the requirements of Paragraph 50.34(b) and Appendix E to Title 10 of the Code of Federal Regulations Part 50, "Licensing of Production and Utilization Facilities."
The radiological analysis information required by Regulatory Guide 1.70 (Rev 3), but which is not part of the Seabrook Station Radiological Emergency Plan, is contained in Appendix 13E.
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0 ENCLOSURE 4 TO NYN-88048 Changes to FSAR Section 13.4 o
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4 SB 1 & 2 Amandmant 58 FSAR April 1986 13.4.2.2 NSARC Charter Bec Jed of e A NSARC Charter, approved by the NSARC members and the NRY Senter-Vice@s/Se o ff,/er -President3 delineates the mechanism for meeting Committee requirements. The Charter contains the following information: 93 Name Basis l 54 Function Composition l Oualifications 51 Meeting Frequency Quorum Review Audits Authority 51 Records NSARC Operations l Amendments 51 Attachments The NSARC composition and qualifications are provided in Technical 55 Specification 6.5.2.2. The NSARC shall collectively have expertise and l competence in the designated disciplines. Provisions are included in the 55 charter to assure that appropriate expertise is in attendance at NSARC meet-ings to review the operational phase activities being discussed. The Charter also provides that no more than a minority of the quorum have line resoonsi-bility for the operation of the Station. The NSARC members are generally selected from YAEC related organizations and NHY oersonnel; members may also be selected from outside consultants or organizations. The minimum.qualifi- 53 cations of all NSARC members meet or exceed those specified in ANS 3.1-1978. 54 Upon their selection, resumes of the regular NSAR Committee members and alternates will be maintained by the NSARC chairman. l s%
The NSARC is advisory in nature, making recommendations to Company management as deemed necessary. The NSARC has access to the Station and Station information at any time in carrying out its responsibilities. The Charter establishes the powers of the Chairman and the ese of subcommittees in performing its function. It also establishes the requirements for l- distribution of reports and/or meeting minutes and its authorization for l initiating work.
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SB 1 & 2 Amsndmtnt 58 FSAR April 1986 13 4.2.3 Reviews Technical Specification 6.5.2.7 defines the Committee review requirements. l These are conducted through a combination of document summary reviews , pre- 55 sentations at regularly scheduled meetings and special meetings held to review proposed changes to the Operating License or Technical Specifications. The NSAR Committee will be required to review and approve all Operating License /
Technical Specification changes prior to their submittal to the NRC. Parti-cular document review assignments may be made by the NSARC to either indivi-dual NSARC members or to subcommittees with the appropriate expertise. Their reperts or summary documents are reviewed by the full Committee at regularly scheduled meetings. Certain activities, such as In-Plant Audits, are per-formed under the cognizance of the NSARC. In such cases, written reports are issued to the Committee and the results discussed at regularly scheduled meetings.
13.4.2.4 Audit Program NSARC audits are considered management audits and are normally performed under the quality assurance audit program described in the Seabrook Operational Quality Assurance Program contained in Section 17.2. 54 13.4.3 Independent Safetv Engineering Group An Independent Safety Engineering Group (ISEG) will perform reviews of plant g 33 operations, independent of those reviews performed by the Station Operation Review Committee (SORC) and the Nuclear Safety Audit and Review Committee (NSARC).
Tne ISEG will be composed of five, full time, dedicated engineers located on site who rpport theirfind te the Senior Vice Presidentj7dEaffTilaYi'oIs{ggstotheEr.ecuti"ei.eeietant a orIkMiISEGmemberswillmeet or exceed the requirements in Section 4.4 of ANS 3.1, i.e., a Bachelor's degree in *%s angineering and two to four years experience in their field, including cne to 53 two years nuclear experience. The ISEG members will receive as a minimum the Training for Supervisors identified in Section 13.2.2. The ISEG will be activated approximately three months prior to fuel-loading. 53 s1 13.4.3.1 Duties and Responsibilities
- a. The general review functions of the ISEG include: ll 53 51
- 1. Examine plant operating characteristics, NRC issuances, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.
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J SB 1 & 2 Amend ant 61 FSAR Novgmbar 1986
- 2. Maintain surveillance of plant operations and maintenance l activities to provide independent verification that these 5%
activities are performed correctly and that human errors are reduced as far as practicable.
- 3. Perform independent review and evaluation of plant activities !
including maintenance, modifications, operational problems, and 5%
operational analysis, and aid in the establishment of programmatic requirements for plant activities.
- 4. Where useful improvements can be achieved, this group will develop and present detailed recommendations to corporate management for such things as revised procedures or equipment modifications.
- b. The ISEG is not responsible for sign-off functions such that it ll becomes involved ia the operating organization. 53 51 13.4.3.2 Reports The ISEG will prepare written summaries of reviews and evaluations performed ll as noted above. These summaries will include the results of, and recommenda- 53 5T tions resulting from, such reviews and evaluations. Ilonthly reports containing a summary of work completed and reconmendations made vill forwarded to the Exceuti c .beistentMo-the--Seniog#!,peqregident, with an information copy to the NH" Rais 'M[eIPresident".# Eie"N5NtN: .u sistent-to-the-Senior--Vice-President has been given appropriate and suf ficient 45"5M authority to ensure that results and recommendations of reports are gg, Pfakut ,/
addressed and acted upon by the operating organizstians. g,,g,9 ,t ga a f
.,oGul.tp 6-frs-s y 13.4.3.3 Charter The composition, qualifications, duties and respoasibilities, and reporting requirements stated above will be incorporated irto the ISEG Charter. l 51 ,
48 13.4-5