ML20138C113
| ML20138C113 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/27/1986 |
| From: | Derrickson W PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| SBN-975, NUDOCS 8604020229 | |
| Download: ML20138C113 (208) | |
Text
_ ______ - _ __ - _
William B. Derrickscn Serwor Vice Presdont Nuciecr Erog/
l March 27, 1986 SBN-975 OhdbM T.F. B7.1.3 New Harnpshire Yankee Division United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
Reference:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 Subj ect : FSAR Chapter 13 and Section 17.2 Update
Dear Sir:
Enclosed please find as Attachments A and B, revistens to excerpts of FSAR Chapter 13 and Section 17.2. These . revisions reflect functional title changes and redelegation of responsibilities in preparation for the operation of Seabrook. These changes to Chapter 13 and Section 17.2 will be incorporated into the FSAR via a future amendment.
l In accordance with 10CFR50.55(f), we have reviewed these FSAR changes and have concluded that the changes do not reduce the Quality Assurance Program commitments described in the Safety Analysis Report.
Very truly yours,
$ Y- 0W V l illiam B. Derrickson Enclosures i
i cc: Atomic Safety and Licensing Board Service List Dr. hmas E. Murley, Regional Administrator United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 pg*188R 8tfTg3 go o l
P.O. Box 300 Seabrook, NH 03874 Telephone (603) 474-9521
STATE OF NEW HAMPSilIRE Ro cki ngham , s s. March 25, 1986 Then personally appeared before me, the above-named William B.
Derrickson who, being duly sworn, did state that he is Senior Vice President of Public Service Company of New Hampshire, that he is duly authorized to execute and file the foregoing information in the name and on the behalf of Public Service Company of New Hampshire, and that the statements therein are true to the best of his knowledge and belief.
mb4 b LNeme- e Beverly S $ oway, Notary blic My Commission Expires: . rch 6, 1990
Diana Curr n Pster J. Mathews, Mayor Harmon & Weiss City Hall 20001 S. Street, W.W. Newburyport, MA 01950 Suite 430 Washington, D.C. 20009 Calvin A. Canney City Manager Sherwin E. Turk, Esq. City Hall Office of the Executive Legal Director 126 Daniel Street U.S. Nuclear Regulatory Comission Portsmouth, NH 03801 Washington, DC 20555 Stephen E. Merrill Robert A. Backus, Esquire Attorney General 116 Lowell Street Dana Bisbee, Esquire P.O. Box 516- Assistant Attorney General Manchester, NH 03105 Office of the Attorney General 25 Capitol Street Philip Ahrens Esquire Concord, NH 03301-6397 Assistant Attorney General Department of The Attorney General Mr. J. P. Nadeau Statehouse Station #6 Selectmen's Office Augusta, ME 04333 10 Central Road Rye, NH 03870 Mrs. Sandra Gavutis Designated Representative of Mr. Angie Machiros the Town of Kensington Chairman of the Board of Selectmen RFD 1 Town of Newbury East Kingston, NH 03827 Newbury, MA 01950 Jo Ann Shotwell, Esquire Mr. William S. Lord Assistant Attorney General Board of Eelectmen Environmental Protection Bureau Town Hall - Friend Street Department of the Attorney General Amesbury, MA 01913 One'Ashburton Place, 19th Floor Boston, MA 02108 Senator Gordon J. Humphrey 1 Pillsbury Street Senator Gordon J. Humphrey Concord, NH 03301 U.S. Senate (ATTN: Herb Boynton)
Washington, DC 20510 (ATTN: Tom Burack) H. Joseph Flynn office of General Counsel Diana P. Randall Federal Emergency Management Agency 70 Collins Street 500 C Street, SW Seabrook, NH 03874 Washington, DC 20472 Richard A. Hampe Esq. Matthew T. Brock, Esq.
Hampe and McNicholas Shaines, Madrigan & McEachern 35 Pleasant Street 25 Maplewood Avenue Concord, NH 03301 P.O. Box 360 Portsmouth, NH 03801 Donald E. Chick Town Manager Gary W. Holmes, Esq.
Town of Exeter Holmes & Ells 10 Front Street 47 Winnacunnet Road Exeter, NH 03833 Hampton, NH 03841 Brentwood Board of Selectmen Ed Thomas RFD Dalton Road FEMA Region I Brentwood, NH 03833 John W. McCormack PO & Courthouse Boston, MA 02109 i
r SBN-975 Attachment A Revisions to Excerpts FSAR Chapter 13 (Section 13.1, 13.2, 13.4; Table 13.5-2; Appendices A, B, C and D)
Seabrook Station
- r. .
. SB 1 & 2 Amendment FSAR March 1986 CHAPTER 13 CONDUCT OF OPERATIONS CONTENTS Page No.
LP 13.1 ORGANIZATIONALCSTRUCTURE 13.1-1 1
l
, 13.1.1 Management and Technical Support
! Organization 13.1-1 13.1.1.1 NHY Production Organization, Responsibilities and Authority 13.1-2 13.1.1.2 Seabrook Training Center Organization, Responsibilities and Authority 13.1-3 13.1.1.3 YNSD Operational Organization 13.1-4
! 13.1.2 Operating Organization 13.1-8 l 13.1.2.1 Station Organization 13.1-8 l 13.1.2.2 Station Personnel Responsibilities and
! Authorities 13.1-8 13.1.2.3 Operating Shift Crews - 13.1-15
,13.1.3 Qualification of Nuclear Plant Personnel 13.1-16 13.1.3.1 -Qualific'ations Requirements 13.1-16 13.1.3.2 Qualifications of Station Personnel 13.1-17 ar a
13.2 TRAINING 13.2-1 13.2.1 Operator License' Training Program 13.2-1 13.2.1.1 Program Description - Initial Operator License Training 13.2-3 l 13.2.1.2 Coordination with Pre-operational Tests and 4 Fuel Loading 13.2-3 l
13.2.1.3 Licensed Operator Requalification I
. Training Program 13.2-8
. 13.2.1.4 Raplacement Operator License Training 13.2-16 13.2.1.5 Applicable NRC Documents ', 13.2-19 l
13.2.2 Training for Technical and Management Staff 13.2-20 l m' l
13.0-1 -
1 L-
SB 1 & 2 Amendment FSAR March 1986 CONTENTS (Cont'd)
Page No.
13.2.2.1 Program Description 13.2-21 13.2.2.2 Coordination with Pre-Operational Tests and 7uel Loading 13.2-25 13.2.2.3 Training Department Staff 13.2-25 r 13.2.2.4 Departmental Training Programs 13.2-26 13.2.2.5 Position Task Analyses 13.2-27 13.2.2.6 Program Evaluation 13.2-27 13.2.2.7 Retraining 13.2-28 13.2.2.8 Replacement Training 13.2-28 13.2.2.9 Emergency Plan Training 13.2-28 1.*
13.3 EMERGENCY PLANNING 13.3-1 13.4 REVIEW AND AUDIT 13.4-1 13.4.1 On-Site Review .
13.4-1 13.4.1.1 SORC 13.4-1 13.4.1.2 SORC Charter 13.4-1 13.4.1.3 Operations Phase Reviews 13.4-2 13.4.1.4 Start-up Phase Reviews
- 13.4-2
~ .
,13.4.2 Independent Review 13.4-2 13.4.2.1 NSAR Committee 13 4-2 13.4.2.2 NSARC Charter 13.4-3 13.4.2.3 Reviews 13.4-4 13.4.2.4 Audit Program 13.4-4 13.4.3 Independent Safety Engineering Group 13.4-4 ll n
13.4.3.1 Duties and Responsibilities 13.4-4 .
13.4.3.2 Reports 13.4-5 l 13.4.3.3 Charter 13.4-5
- 13.5 PLANT PROCEDURES 13.5-1 13.5.1 Administrative Procedures - Ceneral 13.5-1 l
, as 13.5.1 1 Conformance with Regulatory .
i Guide 1.33 13.5-1
(
13.5.1.2 Preparation of Procedures 13.5-1 13.0-2
,, - . _. - .- . -. . - . ~ ... ._-. . . . _ . _ . .,
SB 1 & 2 Amendment' FSAR March 1986 CONTENTS (Cont'd)
Page No.
'13.5.1.3 Procedure Description 13.5-1
, 13.5.1.4 Administrative Procedures - Initial Test Program 13.5-29 13.5.2 Operating Procedures 13.5-29 l r
13.5.2.1 Conformance with Regulatory-Guide 1.33 13.5-29 l 13.5.2.2 Preparation of Procedures 13.5-29 13.5.2.3 Procedure Description 13.5-29
- l i 13.6 INDUSTRIAL SECURITY
- 13.6-1 l< a j ,
APPENDICES 13A Corporate Staff Resumes
.c 13B Training Center Staff Resumes '
13C (Deleted) j 13D Resumes of Key Seabrook Station Personnel 13E Radiological Analysis i
i e
i F
f 13.0-3 l
l
.iB 1 & 2 Amendment F5AR March 1986 CHAPTER 13 _
CONDUCT OF OPERATIONS TABLES f Table No. Title V
13.1-1 Yankee Atomic Electric Company Job Classification 13.2-1 ' Comparison' of NUREG 0737 Appendix C to Seabrook Station Operator License Program V
13.2-2 Operator Licensing Program Participation
. 13.2-3 Participation in Training for Mitigating Cote Damage 13 5-1.- Assignment of Responsibility for Station Procedures
. - 13 5-2 Titles of Control Room Operating Procedures e' l l
+ ;
i i
i
?
g 13.0-4
. - _ ~ - .. . - _. .. _- _ . _ - ..
? ;;
l- '
l F
l SB 1 & 2 Amendment ,
l FSAR March 1986' I
t CHAPTER 13 l CONDUCT OF OPERATIONS i
FIGURES 1 l
Figure No. Title P 13.1-1 New Hampshire Yankee Organization 4
13.1-2 Seabrook Organizational Interface 13.1-3 (deleted) *
, 13.1-4 Seabrook Station Training Center Organization i
13 1-5 Seabrook Station Organization l
.13.1-6 Seabrook Station Unit #1 - Key Operational Milestones ef
- . 13.2-1 Operator License Training Program Coordination with l Pre-Operational Test and Fuel Loading 13.2-2 Non-License Training Program Coordination with Pre-Operational Test and Fuel Loading 13.5-1 -
Control Building - Control Room Arrangement -
Plan at Elevation 75'-0" , $"
l l
G 9
e 0
e e
13.0-5
SB 1 & 2 Amendment FSAR March 1986 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORCANIZATIONAL STRUCTURE This section describes the organizations of the New Hampshire Yankee (NHY)
Division of Public Service Caepany of New Haepshire (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 af requested by NHY. The qualifications of both organizations are offered as supporting evidence that the operational responsibilities for Seabrook Station can and will be discharged in a competent and ef ficient 53 manner.
13.1.1 Management and Technical Support Organization The New Hampshire Yankee (NHY) Division of Public Se rvice Company of New Hampshire is responsible for the construction and operation of Seabrook Station. The overall responsibility for all activities associated with Seabrook Station resides in descending order with the PSNH Itesident and Chief Executive Of ficer, the NHY President and Chief Executive Of ficer, and the NHY Senior Vice President, who is designated as management of ficial in overall charge of the station.
An integrated project organization has been established, working under the direction of the NHY Senior Vice President, to ensure effective project management control. This integrated organization is comprised of the Vice President Nuclear Production, the Vice President and tirector of Chality Programs , th,e Director of, Engineering, the Director of Management Control, the Director of Corporate Services, and an Executive Assistant.
The Director of Management Control is responsible for preparation of budgets, cost control monitoring, purchasing and contract administration, material and
- equipment expediting, insurance, mediagraphics , employee relations , and information resources.
The Vice President - Nuclear Production is responsible f or station operations, maintenance, security, outage management, health physics , chemistry, plant stores and inventory, industrial safety, t raining, licensing, emergency planning, and system /coeponent testing. The Production organization is further described in Section 13.1.1.1 Th'e Vice President and Director of Quality Programs is responsible f or quality assurance and quality control. Operational quality assurance is described in
- Section 17.2. Construction QA activities are accomplished by the YAEC
- Construction QA Manager who reports directly to the YAEC Director of Chality Assurance, but interf aces with the NHY Vice President and Director of Quality Programs as shown in Figure 13.1-2.
The Director of Engineering is the f ocal point f or all engineering activities.
Middle level managers provide the direction needed for implementation of engineering programs, configuration management, reliability and performance engineering, special projects , field engineering and design, and safety i evaluations.
13.1-1
SB 1 & 2 Amendment FSAR March 1986 The Director of Corporate Services is responsible for construction management, special project management, project controls, development of cost forecasts and schedules, and maintenance of corporate facilities and equipment not controlled by the Seabrook Station Staff The Executive Assistant is accountable to administer special management projects, manage the Independent Safety Engineering Group, and perform other such activities as may be specified by the Senior Vice President. The resumes of appropriate corporate management personnel are contained in Appendix A. p 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 nnd YAEC. Amendments to this agreement must be signed by an officer 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 is responsible for the construction 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 escalation testing programs are further responsibilities of Westinghouse.
United Engineers and Constructors (UE&C) is responsible for construction phase engineering, design and certain construction activities of the station.
Included in their services is the furnishing of the balance of plant systems and components, structures and switchyards such that a complete and integrated f acility will result. General Electric is responsible for the design, fabrication and delivery of the turbine-generator unit.
13.1.1.1 NHY Production Organization, Responsibilities and Authority The Production organization is under the overall direction of the Vice President - Nuclear Production, who has full time responsibility for the operation and operational support for Seabrook Station. To assist him in the "
accomplishment of these responsibilities, the Vice President - Nuclear l Production has the Seabrook Station Manager, the Startup Manager, the Training "
Center Manager, and the Nuclear Services Manager reporting directly to him.
Also reporting to the Vice President - Nuclear Production are the Radiological Assessment Manager, who is responsible for emergency planning; and the Operational Projects Supervisor, who is responsible for the development and maintenance of administrative programs. The Vice President - Nuclear Production reports to the Senior Vice President and has the necessary qualifi-cations and job position to qualify as " Engineer in Charge" as defined in ANSI /ANS 3.1 - 1978.
,)*
13.1-2
SB 1 & 2 Amendment "
FSAR Harch 1986 l
l The responsibilities, training, organization and qualifications of the Station l Staff are discussed in Section 13.1.2. De responsibilities of the Seabrook Startup Test Department.are discussed in Section 14.2.2. The responsibilities
l of the Training Center Staff are discussed in Section 13.1.1.2. The Nuclear i Services organization is described below.
Nuclear Services is composed of a manager and a staff of at least two engineers. The Nuclear Services Manager will have a minimum of eight years power plant experience with two years of the experience associated with start-up or operational support. The staff engineers will have 3 to 5 years *'
l experience with at least one year of power plant experience. The group l functions in direct support of the station in the areas of licensing, health physics, training and operations. Nuclear Services personnel will receive the l Ceneral Employee Training and the Training for Supervisors described in '
Section 13.2. The Vice Presidant - Nuclear Production and the Nuclear Services Manager will also receive a plant operations orientation course which includes training for mitigating core damage.
t 13.1.1.2 Seabrook Training Center Organization, Responsibilities and Authority l NHY has recognized the importance of dperator training by establishing a g l
Training Center facility and organization which is independent of the station
- facilities and management, by providing a Seabrook site specific simulator, I
and by having the Training Center Manager report to the same level of manage- l ment as the Station Manager. The Training Center is located on the Seabrook C
5 site outside of the protected area.
The Trai,qfng,qenter facility contains classrooms, office space, a library,.
t study areas, an instructor material preparation room, a computer room, administrative areas, and a simulated Seabrook control room with a full size 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 l
built for the nuclear industry by 1. ink. 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 provide a realistic atmosphere for operator training. The Seabrook simulator meets the requirements of Regulatory Cuide 1.149, 1981 except as noted in FSAR Section 1.8.
, The Training Center Manager reports to the Vice President - Nuclear Production as shown by Figare 13.1-2. The Trafnirig Center organization is shown in Figure 13.1-4. The organization is divided along two functional areas. One l
i area is the maintenance of the simulator hardware and sof tware under a staf f "
l which includes a supervisor, a software specialist and a technician. These personnel undergo extensive training initially by 1. ink in'such areas as assembly language programming, simulator software and hardware, mathematical modeling, and preventative maintenance. The second functional area is l 13.1-3
SB 1 & 2 Amendment FSAR March 1986 operator instruction under the direction of the Training Supervisor whose staff includes four instructors. The Training Center Manager and Training Supervisor meet the ANSI /ANS 3.1 qualification requirements for Supervisors l Requiring NRC Licenses. j l
The primary responsibility of the Training Center Staf f is to provide the I License Training and Requalification Training Programs for the Seabrook oper- I ators. The staf f also must maintain the instruction material and the simulator up-to-date with the current Unit I design. The resumes of the Training Center Staff are contained in Appendix 13B.
The Training Program for the instructors is identical in scope to the Seabrook operator training required for a senior reactor operator license, except that f instructors are provided additional training on simulator control functions and to improve teaching skills. The training center staf f instructors will be i certified under facility procedures to conduct specific course of instruction.
Instructors will meet the qualification requirements of ANSI /ANS 3.1 - 1978 for licensed operators. Initially, the instructors will participate in the cold license program of the Operator License Training Program. Replacement instructors will participate in the hot license program. The Operator License Training Program is described in Section 13.2.
All courses of instruction in engineering topics such as heat transfer, fluid I flow and thermodynamics for the initial group of license candidates, including training center staff members, have been taught as fully accredited courses by faculty members of Memphis State University. Memphis State University is accredited by the Southern Association of Colleges and Schools.
l 13.1.1.3 YNSD Operational Organization NHY has contracted with the Yankee Nuclear Services Division (YNSD) of Yankee I Atomic Electric Company for certain operational support services and will depend on YNSD's qualifications and organizational expertise for certain station support services. NHY has delegated to YNSD the necessary authority and organizational freedom to accomplish these support services.
0 Yankee Atomic Electric Company, an electric utility company, was incorporated as a Massachusetts electric company in 1954 under provisions of the Massachu-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 Coupany 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 funccions of generating, buying, and selling electricity, it has broad related functions, including conducting research and assisting others engaged in the nuclear l
13.1-4 i
i l
l
SR 1&2 FSAR Amendnent March 1986 power business.
The twelve (now eleven) sponsoring utilities own the entire common capital stock of Yankee Atomic in the percentages indicated below.
_Soonsorine Company
_ Percent of Stock New England Electric System New England Power Company Northeast Utilities 30.0 The Connecticut Light & Power Co. e The Hartford Electric Light Co. 15.0 p
9.5*
Vestern Massachusetts Electric Co. 7.0 New England Cas & Electric Assoc.
New Bedford Gas & Electric Light Cambridge Electric Light Co. 2.5 Boston Edison Company 2.0 Central Maine Power Company 9.5 Public Service Co. of New Hampshire 9.5 7.0 Eastern Utilities Associates Montauo Electric Company n tral Vermont Public Service Corp.
Ce' 4.5
_ 3.5 100:
Includes 0.5% originally allocated to the Connecticut Power Co. which subsequently merged into The Hartford Electric Light Company.
In at the construction and operation of the Yankee Ato'nic Elect'ric Company plant l
Rowe, Massachusetts, a group of engineerinr, one' rating and support per-
' " asseE6Yed'.~fe'rsonnel were later assignedtofrom
' Yankee project.
this groupsonnel w the Connecticut Since completion of the Connecticut Yankee orotect, other ~
nuclear projects have been conoleted, including the jointly sponsored Maine Yankee and Vernont Yankee projects. Other protects have also been undertaken individually by several of the sponsoring utilities of Yankee Atomic. With this increase in the number of nuclear protects in New England, it becane apparent that a nnelear services organization was desirable to develop the reoutred support for the major New England utilities.
The purpose of YNSD is to provide a vehicle and a place for the assembly of a group of engineering, licensing, and operations supoort eersonnel that is 1) under the common control of New England sponsors of the various nuclear plants being built in the New England area and, 2) available to provide general
' advice on nuclear power matters to the sponsoring companies. This group of bersonnel is located at the corporate headquarters of the company in Hassachusetts.
O The expertise and experience gained by YNSO during~the design and construction phase of Seabrook Station, as well as their considerable operating experience on the three Yankee plants, will be utilized to its fullest in the operational support of Seabrook Station.
The organizational interface and responsthility l
. c 13.1-5
SB 1 & 2 Amendment
. FSAR March 1986 reporting lines between NHY and YNSD are shown on Figure 13 1-2. The l necessary administrative and technical authority for YNSD to carry out this U 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 respoa-sibility for the overall coordination and implementation of many of the operational support services outlined in the NHY-YAEC Interf ace Agreement. I These operational support services, as well as requests from NNY for other special services are controlled by the Project Manager in the followipg 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 the fundamental organizational element for the accomplishment of work within YNSD, is assigned by the appropriate line department / group manager / lead engineer to assume the responsibility of assuring that the task is completed "
on schedule. The Project Manager and appropriate department / group management are kept informed of the task progress and development by the cognizant engineer. Various forms of communications, including working level discussions, between the activeaTNSD and NHY participants for the assigned
, task occur directly and with whatever. frequency is deemed necessary.
Conflicts that cannot be resolved at the YNSD/NHY 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 NHY President and Chief Executive Officer and the YAEC President. dl The Yankee Nuclear Services Division is organized .to provide a complete spectrum of expertise for the operational support of Seabrook Station. The specific
- areas of potent 141' YNSIT slipport for Seabrook Station arer o Nuclear Engin'eering 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 Human Factors Engineering o Quality Assurance and NDE o In-Service Inspection o Accident Analyses o Transient Analyses
- o Seismic Analyses ,
, o Reload Analyses
- 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 Permit Acquisition and Renewal o Meteorology -
l SB 1 & 2 Amendment FSAR March 1986 l
l l
o Hydrology o Aquatic Ecology
, o Fuel Fabrication and Procurement i o Fire Protection o Equipment Qualification o Systems Interaction / Failure Modes and Effects Analysis o Vendor QA Audits / Surveys o Emergency Preparedness Support o . Performance and Reliability Analyses o Document Control and Records Retention c The experience and qualifications of YNSD engineering personnel that may be 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 Engineeer, 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.
-- n-3ANumee-ere several advantages that accrue to Seabrook as s result *of-the utilization of. Yankee, including:
i
, e o An awareness of problems and their resolutions at several operating
[ plants that could aid in preventing similar situations at Seabrook; i
L o An increased knowledge of the capabilities of, and the establishment of, good working relationships with a varJety of consultants and
- contractors who could also provide support services to Seabrook;
.. 4..... A broadening of the experience of YNSD's cadre of engineers; and o The maintenance of a greater staf f awareness of the various regula-tory requirements imposed upon operating power reactor facilities.
l It is also YNSD's operational philosophy to maintain suf ficient 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.
i 13.1-7
SB 1 & 2 Amendment FSAR March 1986 13.1.2 Operating organization l
13.1.2.1 Station Organization The Seabrook Station organi:ation chart is shown in Figure 13.1-5. This chart ,
, depicts the titles and the minimum number of employees assigned to each f' position. The station organization includes all the technically trained personnel necessary to support all aspects of Unit 1 operation. l The key supervisory positions for the station organization were filled in j 1979. Personnel to meet the operational requirements of Unit I have been, or ', l will be hired on a phased basis consistent with the training and licensing requirements of the individual positions. The schedule for this expansion is I shown in Figure 13.1-6, which also shows the fuel loading and other key mile- g I stones for Unit 1. ,
l l The Unit 1 on-duty operating shift crews will be composed as shown in _
t l Technical Specification Table 6.2-1, and will meet the requirements outlined 4
in Technical Specification Section 6.2.2 describing the plant organization.
Manpower necessary to staf f Hvedhif t crews will be provided. Each member of "
- e the station organization will meet, or, exceed, the minimum qualifications - - -
, recom:sended for comparable positions in Regulatory Guide 1.8, Revision 1-R, J except ANSI /ANS 3.1 - 1978 will be used as the standard rather than ANS 3.1 ANSI 18 1 - 1971.
i
, The employees assigned to the station organization will be trained as des-l cribed in Section 13 2. . l 13.1.2.2 Station Personnel Responsibilities and Authorities '
- s. Overall Station Management i The Station Manager of the Seabrook facility is responsible for overall management of Unit 1. In his absence, the Assistant Station j Manager assumes this responsibility. In the event of unexpected contingencies of a temporary nature, occurring during the absence of 1
these two managers, the Operations Manager will be responsible for j overall station operations. The Shif t Superintendent assumes the
! responsibility for overall management of Unit 1 when the above
- station management is not within the station. In addition, the l
}
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 1 Station Manager, or his assistant, are seven managers i
- 1. Operations Manager: Responsible for the operation of the station.
{
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! 13.1-8
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1 1
1 SR 1 & 2 Amendment FSAR March 1935
- 2. Chemistry and Health Physics Manager: Responsible to provide support for chemistry and health physics activities at the station.
- 3. Technical Services Manseer: Responsible to provide technical support for the operation and refueling of the station.
p 4. Maintenance Nanager: Responsible to provide support for maingenance and radwaste activities at the station.
l 5. Traintne Manager: Responsthle for the training of station personnel in activities not requiring an operator's license.
Training of Operations personnel is performed under the direct supervision of the Training Center Manager.
- 6. Adninistrative Services Manager: Responsthie for general administration activities of the station. ,
. . su. . s. . . . --- . 7. Cono11ance Manager: Responsible foo-monitoring the compliance l of station functions wit,h stated requirements. .-.
The Seabrook Station staff has assumed several responsibilities in support of the Initial Test Frogran in order to increase staff awareness of the Preoperational Test Program details, provide staff contribution to the progran implementation details and procedures, insure staff readiness to accept the completed systems and derive as
- much training benefit as possible from the Initial Test Progran
--- ------r . effort. These support ef forts include-the loan-of staf f personnel to the Start-Up Test Dopartment, the assumption of assigned preoperational testing responsibilities, the verification of design and installation, chemistry suoport, procedure review, evaluation of test data and operational as well as maintenance support of plant systems prior to final acceptance turnover of the systems.
The functions, responsibilities and authorities for station positions under the direct cognizance of these managers are defined helow.
- b. Ooerations The Ooerations Manager is responsible for the operation of the station. He reports to the Station Manager, and maintains close
, comnunications with the other managers with regard to all activities at the station.
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 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 pubite. The Operations Manager will hold a Senior Reactor Operator's License. He l also supervises the Assistant Operations Manager and the Fire Fighter Supervisor.
p
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I SB 1 & 2 Amendment l
- FSAR March 1986 The Assistant Operations Manager directs the activities of the Shif t l
Superintenden.s.e He reports to the Operations Manager and will assume the responsibilities of the Operations Manager in his ll 82 absence. He is responsible for the safety and operation of the l
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 p 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-l tendent and Unit Shift Supervisor will possess a Senior Reactor Operator's License; Supervisory Control Room Operator and the ,
Control Room Operator will possess a Reactor Operator's
---Lacense.- The minimum shif t crew composition for various modes * '- ~+
of unit operation is shown in Technical Specification Table '
6.2-1.
(a) Shift Superintendent L Each Shift Superintendent reports to the Assistant Oper-l ations Manager. He is responsible for the safety and operation of the station's equipment, in accordance with written and approved station procedures. Each Shift ^'
. Superintendent has the authority to order the shutdown of ' ' ' ' *
'l l the reactor when in his judgement such action is required ] r i to protect the safety of the unit or health and safety of :
l 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 Shift Technical Advisor will be assigned to his shift. The Shift Superintendent will function as the Shift l
Technical Advisor and provide requisite technical expertise to the Unit Shift Supervisor in the event of any abnormal operational occurrences.
(b) Unit Shift Supervisor The Unit Shif t Supervisor is responsible for all unit operations being conducted in accordance with appropriate r station orders, procedures and technical specifications.
He is responsible for maintaining a record of all shif t activities and establishing unit electrical load, as directed by the Shift Superintendent or as emergency conditions dictate. He has the authority to order the shutdown of the unit reactor, when in his judgement such l
t l
13.1-10 .
SB 1 & 2 Amendment
. FSAR Harch 1986 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 Operator 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 l Room Operator will hold a Reactor Operator's License.
. . p.~.,. . . ..
(d) Control Room Operator
( The Control Roos Operator monitors the unit's status and l makes adjustments, as needed, to maintain control of the various plant processes. 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 l Room Operator will" hold"a' Reactor Operator's License.
(e) .tuxiliary Operator l The Auxiliary Operator performs routine inspections and surveillance activities in other areas of the unit. He maintains various' logs and records as required by station procedures. In the absence of a Health Physics Technician, he makes radiation and contamination surveys within the controlled areas. During periods when the unit is shut down, he makes routine tests and clears and returns equipment to service as directed by the Supervisory Control j Room Operator. The Auxiliary Operator is unlicensed.
! . c. Chemistry and Health Physics The Chemistry and Health Physics Manager reports directly to the Station Hanager and is responsible for the coordination and direction j of the Chemistry and Health Physics Departments.
l l
13 1-11
1 .
. SR 1 & 2 Amendment FSAR March 1986 i
- 1. Chemistry Departnent Sunervisor l l 1 ,, .
! The Chemistry Department Supervisor is charged with the direct responsthility for ensuring that the nuclear and steam portions of the station operate within the appropriate water cuality specifications. He is responsible for water treatment and ,
conditioning for specific station needs. Me is responsthin for perifying that all liquid, resin and gaseous wastes are properly analyzed and processed for station reuse or disposal.
- 2. Health Physics Department Supervisor l l a
The Health Physics Department Supervisor is the Station Radia-tion Protection Manager and as such has the responsibility and authority to report to the Station Manager (as shown on Figure 13.1-5) on any asoect of the Radiation Protection Program or its implementation as he deems necessary. Ne normally reports ,
directly to the Chemistry and Health Physics Manager and is
...- .. responsible for monitor (ng station activities foc. comp 11anca.. .
. with Mealth Physics related_ regulations and programs. The entire station staff, fr'on the Station Manager on down, recot-nizes and honors this responsibility, thereby ensuring that the Realth Physics Department Supervisor, in concert with the members of his approoriately trained and experienced staff, will fully implenent the station radiation protection program. He is responsible for monitoring devices u, sed by personnel at the l
- station and the maintenance of required radiation exposure records for station and visiting personnel. He ensures-that appropriate monitoring devices and protective clothing are available. He is responsible for verifying that solid radioac-tive materials, other than radioactive waste meet packaging and shipping requirements of the station and federal regulations.
During an extended absence of the Nealth Physics Deoartment Supervisor, a Health Physics Supervisor is designated to tempo-rarily assume those responsibilities as discussed in Section 12.5.1.
- d. Technical Services i The Technical Services Manager reports to the Assistant Station
. Manager and is responsthle for technical support functions for the station. He monitors the activities of and provides overall direction for the Technical Services Group Departments which provide technical and engineering activities at the station.
- 9
- 1. Reactor Engineering Department Supervisor The Reactor Engineering Department Supervisor is responsihte for the analysis of core performance to ensure operation of the station within the facility liegnse limitations. He will calculate reactivity requirements, evaluate the thermal-11.1-12
SB 1 & 2 Amendment FSAR March 1986 hydraulic performance of the reactor cores, specify control rod patterns, prepare fuel movement sequences, and be responsible 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.
- 2. Technical Support Department Supervisor e
The Technical Support Department Supervisur is responsible for the general engineering and quality engineering support services performed on-site. He supervises a multi-disciplined staff of graduate engineers who perform a wide spectrum of activities including: initiation and preparation of design change requests, preparation and review of safety-related procedures, test performance and inspection, and carrying out assigned engineering programs.
- e. Maintenance
. . . The Maintenance Manager reports to the Ctation Manager and is responsible for the coordination and direction of the Maintenance Services, Radioactive Waste and Utilities, Instrumentation and Control, and Maintenance Departments.
I 1. Maintenan'e' c Services' Manager .
The Maintenance Services Manager is responsible for the technical and administrative support of the Maintenance Group by
--- developing and maintaining formal' programs for preventive maintenance, corrective maintenance and surveillance testing.
He participates in the maintenance process by providing mechanical, electrical, relaying, radwaste, and instrumentation and control engineering for station corrective and preventive maintenance activities ~.
- 2. Instrumentation and control Department Supervisor The Instrumentation and Control Department Supervisor is responsible for the maintenance of all instrument and control equipment associated with the reactors, their auxiliary systems and the conventional steam portions of the station. He
- 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 teactor, turbine and auxiliary systems. 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.
13.1-13
f SB 1.& 2 Amendment FSAR March 1986 ,
t
- 3. Maintenance Department' Suceevisor .
, 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.
i f
l 4. Radioactive Waste and Utilities Department Supervisor l
The Radioactive Waste and Utilities Department Supervisor is j responsible for the operation of the radioactive waste proce'ssing system and the collection, processing, packaging and i i loading of radioactive waste. He is also responsible for the l 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. .
, . . . , . . . -.c
- f. Fire Protection Program Management
- 1. Fire Fighter Supervisor The Fire Fighter Supervisor reports.to the Operations Manager.
d' He is responsible for implementation. of the fire protection program on-site. He will develop the procedures for testing and surveillance of all fire protection equipeent and ' systems, and
-**-o** is responsible for all fire prevention and protection activities on-site. ,
- 2. Fire Brigade Leader l The Fire Brigade Leader is responsible for directing the fire l brigade during a fire emergency on-site. This duty will be performed by a systems trained individual who shall be qualified l
to fire fighting standards and who is responsible to the Fire ;
Fighter Supervisor.
p l '
- 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.
( .
13.1-14 1
,- ..- - - _ . - . ~ . - . . - - ._ _ - - .- - - - - . - - _- -
i l
l :
1 ;
i SB 1 & 2 Amendment.3 i
FSAR March 1986 ;
i
- g. Other Station Manaigers' l
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 i various station functions. !
I
- 1. Training Manager s'
The Training Manager reports to the Assistant Station Manager [
and is responsible for all training and retraining activities t I with the exception of operator training. I
- 2. Administrative Services Manager The Administrative Services Manager reports to the Station '
Manager, and is responsible for administrative support of the l station, including computer systems, security services, stores, !
records, office support and station nurse. !
P l
- 3. _ Compliance Manager , . - ;
The Compliance Manager reports to the Station Manager and is ,
responsible to assess station activities toportant to nuclear safety to assure that applicable procedures, specifications, ;
3 licenses and regulations are satisfied.
13 1 2.3* Operating Shift Crews
..........-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 normal [
! operating shift will consist of five Auxiliary Operators, a Control Roos '
! Operator, a Supervisory Control Room Operator, a Unit Shift Supervisor, and a !
l Shift Superintendent for the station'.
I !
l During unic refueling operations, when the reactor core configuration is being j altered, an individual having a Senior Reactor Operator's license will i directly supervise the refueling activities in the reactor containment. i Auxiliary Operators are trained in applicable station radiation protection procedures to perform routine or special radiation surveys commensurate with ,
l .the duties of their job. They receive radiation worker training which l l includes the use of protective barriers and signs, protective clothing and l breathing apparatus and limits of personnel exposure. The Shift l
Superintendent is responsible for implementing the radiation protection '1 t program in the absence of the Health Physics Department Supervisor or his I designated alternate. When fuel is in the unit reactor, a qualified health :
physics technician is assigned to the onsite shift to provide additional !
l support to the Shift Superintendent. .
i
{
l i
l 13.1-15 i
I SB 1 & 2 Amendment l . FSAR March 1986 i
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 afditional support to the Shift Superintendent.
13.1.3 Qualification of Nuclear Plant Personnel 13 1.3.1 Qualifications Requirements l The recommendations of Regulatory Guide 1.8, " Personnel Selection and c-l Training", Revision 1-R, have been used as the bg.sts 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 vill 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
. . e .e o,..as signment. Where desirable, off-site f acilities. may be.used. for specialized traJning. Records of the scope, gener,41 content and level of accompitshment
. for each person attending off-site training are retained at the station.
t 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 l .~.... 4..... Station Manager . Plant Manager"- - - -*
l l b. Assistant Station Manager Plant Manager
- c. Operations Manager Operations Manager
- d. Assistant Operations Manager Operations Manager
- e. Technical Services Manager Technical Manager l f. Maintenance Manager Maintenance Mansger l l 67 i
- - g. Maintenance Services Manager Maintenance Manager t
l h. Chemistry and Health Physics Supervisor without NRC Manager License, l 1. Compliance Manager Supervisor without NRC l License
, J. Shift Superintendent . Supervisor with NRC License ;
n i I
13.1-16
SB 1 & 2 Anendment FSAR March 1986
- k. Unit Shift Supervisor Supervisor with NRC License l?
- 1. Supervisory control Roon Operator Supervisor with NRC License
- m. Chemistry Department Supervisor Professional-Technical
- n. Maintenance Department Supervisor Supervisor without NRC License 9 o. Technical Support Department Professional-Technical Supervisor e
- p. Reactor Engineering Department Professional-Technical Supervisor
- o. Instrunentation and Control Professional-Technical Department Supervisor
- r. Health Physics Department Professional-Technical Supervisor
- s. -* Radioactive Waste Supervisor. Supervisor without NRC License
- t. Computer Engineering Department Supervisor without NRC Supervisor License
- u. , Training Manager Supervisor without NRC License y
Administrative Services Manager Supervisor without NRC"* ~~
License sy 13.1.3.2 Oualifications of Station Personnel The key managenent, 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 senior personnel at the time of startup will generally be in the range of 8 I to 20 years. These personnel include the Station Manager, Assistant Station Manager, Operations Manager, Technical Services Manager, Training Center
- Manager, Shift Superintendents, Technical Support Department Supervisor, !
- Instrumentation and Control Department Supervisor, Chemistry Department Supervisor and Health Physics Department Supervisor. Many of the key personnel will have had Senior Ooerator Licenses or Operator's Licenses at other operating plants or have had extensive nuclear submarine operational responsthilities. Most of the Unit Shif t Supervisors and Control Room Oper-ators and at least one individual in each of the major technical disciplines (nuclear engineering, chemistry, health physics, 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 130.
nstJt-s
SB 1 & 2 Amendment -
FSAR March 1986
, TABLE 13.1-1 l (Sheet 1 of 2)
YANKEE ATOMIC ELECTRIC COMPANY JOB CLASSIFICATION CLASSIFICATION - Graduate Engineer c 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) Satisfaction of educational requirements of a Graduate
! Training and Engineer (i.e., completion of Bachelor's Degree
-. ~ . ~ ~-Experience requirements in an approprists -dircipline and
. . . . . graduation from an accredited college or university) -
or educational and experience reqairements of an Engineering Associate (i.e., completion of Bachelor's l Degree requirements in a math or science field and j graduation from an accredited college or university, or sufficient experience to attain equivalent knowledge and skills); .
(2) Satisfactory completfon'of at least one year of l
employment at a professional level in the field for which employed or completion of an advanced degree; and (3) Attainment of Engineer-In-Training qualification is desirable as'a first step in obtaining certification as a Registered Professional Engineer.
si l CLASSIFICATION - Engineer !
Education, - (1) Satisfaction of educational and experience Training and requirements for an Associate Engineer;
- Experience
. (2) Satisfactory completion of at least three years of employment at a professional level in field for which employed which demonstrates a progression of competence in field of expertise (Note: advanced education may be substituted for work experience); and l (3) Attainment of Professional Engineer's License is desirable. -
L
SB 1 & 2 Amendment
,. FSAR March 1986 TABLF. 13.1-1 (Sheet 2 of 2)
CLASSIFICATION - Titled Engineer Education, -
(1) Satisfaction of educational and experience reautre- !
Training and ments for an Engineer; and r Experience (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 experience).
CLASSIFICATION - Senior Engineer Education, - (1) Satisfaction of educational and experience reautre-
^ ^ * ' ' ' ~ ^ ' ' * "
Training'end ~"~~ ments for Titled- Engineer; Experience ---
. (2) Satisfactory completion of at least seven years of employment at a professional level in field of expertise which demonstrates a progressive development of competence; and (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 require-Training and ments for Senior. Engineer; Experience (2) Satisfactory completion of at least nine years of employment in field of expertise which demonstrates a progressive development of competence.
(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 le'ast twelve years of Training and enployment at a professional level in field of Experience expertise which has demonstrated a progression in competence to a level of marked prominence.
(2) Completion of at least one advanced degree in field or suf ficient experience' to be deemed equivalent.
(3) Membership in professional societies in field of expertise as well as professional licenses are desirable.
g Amendment
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SB'l & 2 Amendment FSAR March 1986 r
(Figure Deleted) -
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UNIT SHIFT SUPERVISOR (6) $-
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March 1986 '.
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_ , q,l :
4
SS 1 & 2 Amendnent FSAR March 1986 13.2 TRAININC 13.2.1 Operator License Training Program
- a. General Discussion The program will provide personnel associated with the operation of Seabrook Station training in various disciplines necessary to ensure that each individual can safely and effectively perform various .F assignments. The degree to which an employee is trained will be consistent with the individual's experience, intended position and regulatory requirements. Eligibility of individuals to license or ,
renew a license pursuant to the requirements of 10CFR55 will be d' certified by the Vice President - Nuclear Production.
, The Seabrook specific simulator will be made available to NRC personnel to conduct Seabrook Operator License examinations.
Qualified staff members will be available for assistance if requested. - . . . .
19 -
The overall objectives of the Operator License Training Program are:
o To train a staff to operate and maintain the units safely, dependably and economically.
o To prepare shift superintendents, unit shif t supervisors, control room operators and selected station managers for the NRC licensing examination for Reactor Operator (RO) and Senior Reactor Operator (SRO). -- - - - - * -
v>
~
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 personnel with a high' degree of competence and profession-alism. Specifically, these categories of training are as follows: ,
e
- 1. Operator License Training All personnel requiring NRC operating licenses, as spect-fied in ANSI /ANS 3.1-1981, will have to undergo intensive training which will meet or exceed the minimum requirements l
, of 10CFR55. Prior to the initial criticality, operator c'.p
=
license training comes under the Initial Operator License Training Program. Operator license training completed af ter the first criticality is given by the Replacement Operator L! cense Training Program.
9 13.2-1
.. . _- . . . - . ~. .. . . .
SB 1 & 2 Amendment FSAR March 1986
- 2. Shif t Technical Advisor Training New Hampshire Yankee has upgraded the training program for the Shift Superintendents or Unit Shift Supervisors to meet 43 '
the long term plan.of satisfying the need for a Shift Technical Advisor on shift. The Shif t- Technical Advisor Training is designed to meet or exceed the recommended guidelines referenced by NUREG-0737.
~
c *( I
- 3. Licensed Operator Requalification Training Program l,'
e-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
- 4. Replacement Operator License Training Program '
- ~'- - * ' ' Operators joining the Seabrook' urg'aniration af ter the start of power operation will be given appropriate training to satisfy their job classifications. The extent and duration
.of the training period depends upon their previous experience and job aptitude. All applicants for a senior operator or control operator license will have three. months on shif t under instruction in the License position they _are
, seeking. Senior operator applicants will, in addition,
~
have held an operator's license for one year. If an NRC-
' '~ ^ " ~
Operator's License is require'd 'foY 'a sp'ecific -job category, et suitable classroom and practical training is-provided.
i if
- 5. Program Accreditation and Instructor Certification New Hampshire Tankee is committed to the INPO developed l accreditation program. To meet this commitment, the- i3 company instituted a procedurally administered accreditation process. .The process is carried out by an aceradication 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, integrated response, transients, and simulator courses will t' maintain a current facility SRO license through participa-tion in the requalification training program. Staff ,
I
- instructors who have not obtained a facility SRO license may be certified for specific subjects in which they have demonstrated SRO license level comprehension and skill.
The determination of this certification is the responsi-
,. bility of the Training Cedter Manager.
ns J
13.2 2 _ _ , . _ _ _ _ , _ --._ _ _ _ - , _ __
.-_ _ - . _ - . . . _ . . _ . _ . _ _ _ _ _ _ __..__ _ , ~
us.
SB l & 2 Amendment FSAR March 1986 Cuest lecturers considered to be experts by nature of their work responsibilities will be used on a limited basis to
' supplement the training cen'ter staf f instructors. These i
guest lecturers are exempt from the senior operator
. criteria, s
Prior to the initial licensing of instructors and operators e for Seabrook Unit I, previously senior licensed, senior license certified or Training Centre Manager certified instructors will teach systems, integrated response, transients, and simulator courses.
et
- b. Responsibilities The following Seabrook personnel are responsible for various areas of Seabrook's Operator License Training Program.
- 1. Station Manager j -
.The Seabrook Station Manager has the overall responsibility for qualification and proficiency of its personnel. As such, the Station Manager will review and approve all plant training j Programs.
l
- 2. Assistant Station Manager .
The Assistant Station Manager is responsible to the Station Manager for administration of all the general and specialty training courses given by the Training Department. _The Assistant Station Manager will review those training courses annually.
i 3. Training Center Manager The Training Center Manager is responsible for development, implementation, and administration of licensed operator training and auxiliary operator training. This will include initial,
. replacement, and requalification training.
n:
13.2.1.1 Program Description - Initial Operator License Training
~
j
.This program will provide an individual with the knowledge and experience . ,
level necessary to obtain an NRC Senior Operator's License or Operator's License. The program has been developed and scheduled in a modular fashion to be implemented in segments. In most cases, each licensing candidate will participate in each segment. However, whether an individual participates in all segments will depend upon previous nuclear experience and previous license qualification. Program participation has been categorized on Table 13.2-2.
l 13.2-3
1 SB 1 & 2 Amendment FSAR March 1986 The license training program schedule will insure that a suf ficient 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 performed by: 1) l
. Training Center management periodic assessment of classroom pqssentation .and simulator instruction; 2) independenteparty oral and demonstrative audits conducted on at least a yearly basis; 3) student generated evaluations. 4 ll Revisions are made to the license training program to strengthen weak areas
_ identified through the evaluation process.
4 >*
The following paragraphs provide a general description of the various training segments:
- a. Introductory Training o , a _ _ . m_ . . In addition to the initial o.rientation and. general employee training described in Section 13.2.2,.those individuals specifically designed to become license holders will attend an introductory program on PWR systems.- The first portion of the program is a generic course 9f covering the Nuclear Steam Supply System (NSSS). License candidates will also be given an introductory course covering the balance of Seabrook's systems. .
- b.
- Nuclear Fundamentals Training Program
_ l
. ni Fundamentals I - -- .
This is an eighteen to twenty week program presented by the l 1 Training Center Staff or an outside vendor. The program pro- **
vides the reactor operator license candidates with a thorough ,
i understanding of the basic principles, characteristics and 9 unique features of a nuclear system. The major areas to be covered are mathematics and classical physics, basic nuclear physics, reactor operations,' core performance, radiation pro-tection, plant chemistry, instrumentation and control, fluid flow, thermodynamics, heat transfer, and plant performance. An integral part of the Fundamentals I training program is reactor start-up experience. This is a one week program presented at a research or training facility by an outside vendor. Experi-ments, discussions and demonstrations are conducted to compli-ment the principles and theory taught in,the fundamentals program. Specific training objectives are selected which place additional emphasis on concepts which are difficult to visualize in the classroom environment.
4' 13.2-4
SB 1 & 2 Amendment FSAR March 1986 Fundamentals II This is a forty to fif ty week program- presented by the Training Center Staff or an outside vendor. The program is designed to psuvide the Shift Superintendent and UnIL Shift Supervisor with an added depth of knowledge of engineering principles found in nuclear reactor fundamental applications. Selected courses are based upon an analysis of the Shift Technical Advisor's
.qualif) cations and responsibilities outlined in NUREC-0578. The courses include the following: '
Differential Calculus Integral Calculus Advanced Reactor Physics Material Study Course Fracture Mechanics Corrosion Processes Computer Technology
-s' Electric Generation and Transmission - - - * * -
Thermodynamics .
Heat Transfer Fluid Mechanics
- To supplement Fundamental II courses, workshops will be held to reinforce theoretical concepts learned in the courses with practical Seabrook applications. The workshops will generally
~
consist of a classroom phase and use of the simulator where appropriate.
An additional ten to twelve weeks of specialized training is provided to supervisory level license holders. These courses include motivation of personnel, problem and decision analysis, interpersonal communication, technical writing, stress and human behavior. er
- c. Operating Plant Observation o~
This segment consists of four to six weeks of plant observation at 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, quality control /
assurance, fuel handling, and waste disposal / management.
13.2-5
SB 1 & 2 Amendment FSAR March 1986
- d. Formal On-Sit'e School-This segment of approximately 14 to 18 weeks duration will encompass ,
the on-site formal classroom lecture series. The instructors for this lecture series will be permanent and temporary members of the *(
Seabrook Station Training Center. staff, Seabrook Station Supervisory staff and Yankee Atomic staff. Other censult=nt and vender
- representatives will be invited-to discuss topics of special j interest.
? . V i
' p The subjects to be taught and/or reviewed in the formal on-site school are listed below: '
Math and Physics
- j. Reactor Operations
- Plant Chemistry (Primary and Secondary) ;
Health Physics Heat Transfer l Fluid Flow Materials Science
- Thermodynamics ; . r- ...
2 Specific Systems & Compon,ents
- 4 Instrumentation & Controls I Mitigating Cora Damage (per Table 13.2-3) 5f 6 Technical Specifications Administrative Controls !
[_ Special Topics ,
p '
l- ' Lectures applicable to Mitigating Core Danage (per Table 13.2.3) will s i-- _ total in excess of forty-(40) contact hours. Credit will be taken, l
- , where applicable, for contact hours presented in other subjects as listed above. !
[
- e. L Included in the classroom training segment will be periodic simulator j exercises and demonstrations. In addition, directed in-station tours o will be conducted to review system and component lay'out and inter-fa:e. .
- e. Simulator Training -
l Seabrook has the distinct advantage of including a site specific simulator as part of the operator training program. The simulator 1 -
was modeled and built to duplicate the Seabrook main control board as well as real time system response. The simulator meets the el l .
requirements of Regulatory Guide 1.149, 1981, except as noted in FSAR,
- i. Section 1.8, Conformance to NRC Regulatory Guides.
- i .
41 l
i 4 "
I s .
l k
13.2-6 l
SB 1 & 2 Amendment FSAR March 198G A fully qualified simulator staff, with previously SRO licensed or certified instructors, will implement and conduct this sagment of the operator training program. All license candidates will spend time participating in the simulator training program as needed to prepare for NRC licensing exams. .This progra3 will enmhina hand =-on practical experiences with formal classroom instruction. The training objectives and performance evaluations for the simulator training program are tailored to the license level sought by the e p prospective license candidate. Two levels of knowledge are acco=modated in those portions of the program where a distinction #'
exists between the skills required of a reactor operator candidate and those required of a senior operator candidate.
Those senior operator license candidates who will function as Unit Shift Supervisors or Shift Superintendents will have had at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> in either the Unit Shift Supervisor or Shift Superintendent position during the simulator training program. Major program emphasis will be placed or. obtaining complete familiarity with the er - plant's operating, emergency.and surveillance procedures. ---
. This familiarity will be obtained and reinforced through actual perfo rmance.
Successful completion of this program, combined with operating plant observation, will satisfy requirements of 10 CFR 55.25(b) and will provide the basis to establish a candidate's eligibility for cold
- licensing.
_f. On-the-Job Training m'
Participation in the pre-operational testing phase of the unit start-up will provide on-the-job training to license candidates.
Operating personnel are given departmental work assignments in addition to participating in system turnover and acceptance testing. Throughout this period, assignments will include preparation at.3/or review of the various operating, emergency, maintenance, surveillance, and test procedures necessary for the start-up and operation of the unit. ,
On-the-job training also includes structured training on plant
, systems. This training requires tracing each major system in plant walk-throughs and answering questions associated with equipment / component function, operating proce,dures, and related industry events.
13.2-7
4 SB 1 & 2 Anendment FSAR March 1986
- g. Progran Review and Pre-License Evaluation At the culmination of the training program, each license candidate "#
will participate in review session followed hy pre-license evalu-ation.
The review session will consist of formal classroon' instruction, c simulator exercises and individualized study. The review session will emphasize areas where earlier program information may have been shallow or unknown.
A final pre-license evaluation of each license candidate will be administered by an independent party. This evaluation will be conducted in two parts: the first will be a written exam to determine the candidate's comprehension and retention. The exam
, contents and degree of dif ficulty will parallel that of a current NRC Operator examination or Senior Operator examination, as applicable.
The second portion of the evaluation will be an oral walk-through and simulator. demonstration >to-further- evaluate practical knowledge and
-.u- - -
experience. This evaluation.will insure each candidate is properiv prepared for the NRC exan, and is capable of competent and safe operation of the plant controls.
13.2.1.2 Coordination with Pre-Operational Tests and Fuel Loading The Station Staff Training program has been developed and will be scheduled to minimize any conflicts in manpower requirements during the unit's pre-operatio~nal testing and fuel lording.-- The positive training effects gained by actual participation in the start-up will be incorporated in the training Program.
The scheduling interface between the Operator License Training Program and the start-up is illustrated in Figure 13.2-1.
13.2.1.3 Licensed Operator Recualification Training Program A comprehensive requalification training program will be conducted for all licensed operators and will be implemented within three (3) months after the initial cold licensing of operators. This requalification training progran has been developed and will be implemented to maintain a high level of
- knowledge and skill in licensed reactor operators and senior reactor operators. The basis for this program is to enhance safety,. productivity, and efficiency in operating the plant during normal and abnormal situations.
9 13.2-8
SB 1 & 2 Amendment FSAR March 1986 The Seabrook Station Requalification 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 Training Center's
_ Curriculum Development Committee (CDC). The CDC consists of, but is not li=ited to, the Training Center Manager, the Training Supervisor, a representative from Operations management, and a representative from Media Support.
c.
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 an operator or senior operator license will be accompanied by a statement, signed if
, 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. -- n - -- -
.. The requalification training program consists of four. interrelated elements:
o Requalification 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
--- failure or unsatisfactory performance will require that the deficient licensee meet with the appropriate academic 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. Staff 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: -
- s. 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 designed to meet the requirements of the requalification modules' di MLJbo
SB 1 & 2 Amendment
. FSAR ' March 1986 objectives. At the completion of each annual cycle, a sufficient number of exams' vill 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 Design o General and Specific Plant Operating Characteristics o Plant Instrumentation and Control System o Plant Protection Systems o Engineered Safety Systems ,
o Radiation Control and Safety ,
- o Applicable Portions of Title 10, Code of Federal Regulations--- . -
. -- ... o Fuel Bandling and Core Parameters - - -- -
o . Technical Specifications o Administrative Procedures, Conditions and Limitations o Nuclear Industry Operating Experience The person (s) responsible for the preparation of the examination and answer key and the person (s) who reviewed the examination will not be required to take the examination.
- 2. Demonstrative Examination A demonstrative examination will be scheduled for each module.
These examinations can be either-simulator evaluations, oral 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.
13.2-10
SB 1 & 2 Amendment FSAR March 1986 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 receiving a module grade of less than 70% more than once vill meet with the Performance Review Board. The.lican*** must schieve an overall grade average of 80% or greater at the completion of each annual cycle.
r-
- b. On-the-Job Training e In order to maintain 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:
o Required reactivity 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 that
- pirticipation on the simulator is unsatisf actory, the licensee will
-- .
- meet with the Alert Status Review Board and carry out the recommendations handed down by the Board.
Each licensee will annually participate in the following list of plant evolutions and abnormal / emergency conditions in either the plant control room or at the plant simulator:
o Plant or reactor startup and power escalation to a range where reactivity feedback from nuclear heat addition is noticeable and heatup rate is established o Manual control of steam generator water level or feedwater flow during plant startup or shutdown o Reactor power changes of 10% or greater where rod control is in manual o Loss of coolant including:
l a) Steam generator tube leaks b) Pressurizer leaks -
c) .Large and small leaks located inside and outside of primary ;
containment (including leak rate determination for small l
leaks inside containment) I d) Saturated Reactor Coolant. System response l o Loss of coolant flow / natural circulation o Loss of all feedwater (normal and emergency) sf as n-as i
SB 1 & 2 Amendment FSAR March 1986 i On a two-year cycle basis, each licensee will participate in the following normal plant evolutions and abnormal / emergency conditions in either the plant control room or at the plant simulator:
o Plant shutdown o Boration and dilution during power operation o
Reactor power changes of 10% or greater where load' change is performed ia --- '
o Reactor trip o Turbine or generator trip 9 o Remote safe shutdown p o Nuclear instrumentation failure (s) o Loss of protective system channel (s) o Mispositioned control rod (s) (or rod drops) o Inability to drive control rods o Conditions requiring use of emergency boration o Fuel cladding failure or'high activity in reactor coolant o Malfunction of automatic control system (s) which affect reactivity o Loss of instrument air o Loss of electrical power and/or degraded power sources o Loss of condenser vacuum , "
o Loss of service water o Loss of residual heat removal o Loss of primary component cooling system or cooling to an individual component o Loss of normal feedwater or normal feedwater system failure h o Main steam line break (inside or out'sJde containment)
Response to abnormal / emergency conditions should include use of
- alternate.nethods of accomplishing a given function, such as - ' ' ' - - ~
alternate methods of core cooling. Exercises involving multiple failures 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 conducted with the licensees. The critique on each abnormal /
emergency condition will be documented and placed in the Requalifi-l cation Training records.
l 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 Shif t' 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 licensees' i training records.
i
. t o" 13.2-12 l
I SB 1 & 2 Amendment FSAR March 1986 ,
In addition to actual control manipulations accomplished while on shif t in the control room, on-the-job training includes: f o
Design Change, Procedure Revision and Industry Experience Review L '
This portion of the program will ensure that completed cisanges l
and revisions to plant design, changes to procedures and Tech 71 cal Specifications and industry experiences ~are reviewed by each licensee. c c !
- o Abnormal and Emergency Operating Procedure Review -
Each licensee will review the contents of all abaormal and emergency procedures annually.
o Simulator E.xercises This portion of the program will ensure that required control manipulations that are not performed at the plant will be i
performed.during the teca of the operator's license. The -
l simulator portion of the requalification program will emphasize such areas as infrequently accomplished procedures, required responses to abnormal and emergency procedures, and significant operating events.
o In-Plant Training ..
i This portion of the program will ensure that training which is
.best - suited to be conducted in-plant is performed on actual- ~ -- - *'
- l plant equipment. This includes review of major plant modifi-cations, equipment which is provided with local controls, and i
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-shif t review of selected operational experiences and changes to existing operating guidance or i
equipment. The operational review enables continuous updating of on-shi(t personnel and establishes a means of disseminating new or l changing information that has not been posted in the Standing Orders Book or the Night Orders Book.
L This portion of requalification training will ensure that changes or revisions to the Technical Specifications, FSAR, significant changes to procedures and completed facility design chac2es, are reviewed.
When determined by the On-Shif t Training Coordinator, an appropriate procedure revision or completed facility design change will be included in the review process.
<f ,
13.2-13 l
SR 1 & 2 Amendnent FSAR March 1986 In addition, a continuing system will be established so that all licensees review the operating experience of Seahrook Station and applicable experiences of the nuclear industry. Selected operational events and reportable occurrences at Seahrook Station will be analyzed and information pertinent to the event collected. Selected operacional information f rom the nuclear industry will also be reviewed. The following sources of information will be considered, but not limited to:
e 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 INPO Significant Event Reports and Significant Operating Experience Reports This information will be routed to all licensees with a sign-off sheet. The on-Shift Training Coordinator, in cooperation with the
~
.~ Shif t Superintendents will e'nsure that ill 'dn-shif t licensed personnel review the information in a timely manner. The On-Shift Training Coordinator will maintain the documentation of this review process.
A copy of procedure revisions, along with a sign-off sheet, will be placed in the Operational Review Notebook. During a training shift,
. each licensee will review the contents of the Notebook and, upon
~
. completing the assigned reading, will sign the sign-off sheet, '
signifying that he' his "r'ea3' and understands the change or revision.
The STC will update the Notebook and remove completed materials to the training records.
In order to ensure a continuing understanding of the action and response necessary during emergency or abnormal situations, a complete review of all emergency and abnormal operatine procedures will be conducted by each licensee,~over the course of the annual cycle. An acknowledgement sheet will be signed and filed at the Training Center.
- d. Simulator Training
. r The Seahrook specific simulator will be utilized, whenever practical, to fortify the on-going operator requalification program. Simulator exercises and evolutions will be preplanned and scheduled to f requently interface with the Fornal Lecture series. The simulator Requalification Training Program will emphasize such areas as infrequently accomplished procedures, reautred responses to abnormal and emergency procedures, and significant operating events.
13.2-14
551&2 Amendssnt FSAR Harch 1986 Exercises will include analyzing the effects of potential equipment /
system malfunctions, possible causes and recommended operator responses. A program objective shall be involvement of Unit Shif t Supervisors and Shif t Superintendents in the capacity of operations assessment and accident analysis during refresher exercise training. A portion of each week's simulator time, not to exceed twenty percent, will be allocated for specific applications requested by the Unit Shif t Supervisors / Shift Superintendents. The simulator, will also be used as a means of evaluating and indicating areas requiring further retraining emphasis.
- e. fetraining Lectures for License Holders A formal classroom 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 he'.d. 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:
e 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, thermo-dynamics, and mitigation of accidents involving a degraded core.
~
. Procedures and Administrative Controls lectures will cover topics -,
involving essential plant operational guidelines; for example, technical specifications, administrative procedures, major plant evolutions, etc.
All licensed individuals will be required to attend 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 effectiveness shall be monitored as ,
described in Subsection 13.2.1 1.
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 supervisor or a member of the Training Center Staff.
- 13.2-15
SB 1 & 2 Amendment FSAR March 1986 A performance review will be conducted when any of the following situations occur:
o A licensed operator receives a moduist exam score of less than 70 percent more than once during the annual cycle, or an annual overall grade average of less than 80 percent.
o A licensed operater receives a poor performance evaluation.
c r o Prior to resuming or assuming active license responsibilities af ter absence of four months or longer f rom actively performing the functions of an operator or senior operator.
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 established to up-grade areas where deficiencies are shown.
The review will be conducted as soon as practical after one of the
.&.:. . - above conditions occur. The.. action taken.will be dependent on such f actors as examination performance, watch standing performance, observed operational performance and judged overall competence.
A performance review will be conducted to determine the necessary actions to be perfor=ed by a licensee, prior to assuming responsi-bilities at any operational shif t level; RO, SRO, Unit Shif t Supervisor, Shift Superintendent. Typically this performance review
'would address actions to be performed by an inactive licensee prior
- --: to being placed in an operating' position requiring a license. The results of this review will be used to certify to the commission that the licensee's knowledge and understanding of facility operation and administration are satisfactory, as required by 10CFR55.31(e).
- g. Requalification 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 evaluations, and documentation of any additional training in areas in which the licensee had exhibited deficiencies.
P '
13.2.1.4 Replacement Operator License Training ,
s Individual advancement to increasing levels of responsibilities as oppor-tunities develop within the organization will be encouraged. For an individual to advance to a more responsible position, he must be fully qualified technically and possess sufficient experience to meet the job requirements. ..
13.2-16
SB 1 & 2 Amendment FSAR March 1986
- a. Replacement Operator License Training Program New Hampshire Yankee has recognized the need to have a Replacement g Operator License Training Program which will continually ensure the same high quality of licensed personnel as the Initial Operator License Training Program. To this end, the replacement program for licensed operators will include the same segments as the Initial Operator License Training Program. Waiver of specific program elements defined below may be granted based on a procedurally administered review of each individual's education, formal training and experience. Prior to granting a waiver, a determination will be made that the objectives of the waived element are met for the license level sought. Documentation of the formal review and the conclusions reached will be maintained. Credit will be taken for previous formal training and experience received in an individual's
, progression to the license level the person is seeking.
4 e The training program will include as a minimum the following elements:
- ~
- 1. Classroom Instruction Each license candidate will attend a formal on-site school of sufficient duration, to complete prescheduled lectures in the following areas:
Nuclear Reactor Fundamentals I - se Subsection 13.2.1.1.b. l
~~~
~~
?----- -
Formal On-Site School - see Subsection 13.2.1.1".d'. ' '
at The lecture program may be supplemented by the video tape program, as determined by the Training Center Staff. Periodic quizzes and exams will be administered to ensure student com- l prehension and retention. To further evaluate each student's acquired knowledge level, a final exam will be given at the conclusion of the classroom phase. The final exam contents and degree of difficulty will parallel that of an NRC operator license examination or senior operator license examination, as applicable.
- 2. Control Room Experience Each license candidate will receive on-the-job experience by l participation-in discussions with on-shift operators and by the actual performance of routine control room functions. The discussions will be directed to topics such as systems interface, control capabilities and instrumentation available in the control room. Particular emphasis will be placed on system operating characteristics and possible malfunctions. License candidates will participate on shift in the position of the license being sought, under the direction of a licensed operator l for a period of three months.
ec 13.2-17
,, ..w SB 1 & 2 Amendment FSAR March 1986
- 3. Simulator Training The Replacement Operator License' Training Program will include training on the Seabrook-specific simulator. This phase of the program will emphasize normal, transient, and emergency operations. In the training, each license candidate performs control room duties at the simulator as a member of a shif t crew. Eagh crew will be given the opportunity to witness and respond to numerous exercises involving system and component malfunctions.
The crews of license candidates will receive thorough practice on the simulator in carrying out the following plant operations:
- a. Integrated Operations - Bringing the plant from 10% power to 100% power according to. normal operating procedures;
- b. Plant Cooldowns and Heatups - Performing a plant shutdown, cooldown, heatup, and startup using normal plant operating
. .. procedures, interrdpted by occasional use of abnormal operating procedures for minor malfunctions;
- c. Reactor Startup - Implementing reactor startup using the applicable plant procedures; and
- d. Transient and Accident Analysii - Responding to plant
. malfunctions and emergencies through use of the abnormal
,and emergency. plant operating procedures.
- 4. Pre-License Audit In addition to the final exam administered at completion of classroom training, an oral station walk-through will be given to each candidate to further insure that the individual is properly prepared and is, in fact, capable of competent and safe operation of the station controls. This oral walk-through will be given by a senior licensed member of the unit staff, or an independent party, prior to the individual being permitted to l take the NRC licensing exam. The areas that are to be stressed while conducting these walk-throughs are simulated malfunction
, and emergency situation response, local instrumentation and control, and general plant hardware.
t e
13.2-18
SB 1 & 2 Amendment FSAR March 1986 13.2.1 5 Applicable NRC Documents The training program will be developed and implemented 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, " Domestic Licensing of Production and Utilization Facilities" 4 l1 10CFR Part SS, " Operator's Licenses" 10CFR Part 19, " Notices, Instructions and Reports to Workers; Inspections" Regulatory Guide 1.8, " Personnel Selection and Training", Revision 1-R,
, September 1975 (re-issued May, 1977), with the exception that ANSI /ANS 3.1-1978 vill be used as the standard in lieu of ANS 3.1/ ANSI 18.1-1971
. Regulatory Guide 1.101, " Emergency Planning for Nuclear Power Plants",
Revision 2, October 1981 Regulatory Guide 1.149, " Nuclear Power Plant Simulators for Use in Operator Training", Revision 0, April 1981
- a. w1 Regulatory Guide 8.2, " Guide for Administrative Practices in Radiation Monitoring" February 1973 ,
Regulatary Guids 8.8, "Information Relevant to Insuring that Occupational
_. __ ___Radia. tion exposures at Nuclear Power Stations will be as Low. as Reasonably Achievable", Revision 3, June 1978 u -
Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably 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-1130, Revised June, 1973 "NRC Operator Licensing Guide", NUREG-0094, July 1976 "TMI-2 Lesso.ns Learned Task Force Status Report and Short-Tern Recommenda-tions", NUREG-0578, July 1979 ,
13.2-19
SB 1 & 2 Amendment FSAR March 1986 ANSI /ANS 3.1-1981, "American National. Standard for Selection and Training of l Nuclear Power Plant Personnel." 4 ANSI /ANS 3.5-1981, " Nuclear Power Plant Simulators for Use in Operator Training."
" Nuclear Plant Fire Protection Functional Responsibilities, Administrative
Controls and Quality Assurance", issued by USNRC letter in August, 1977.
c NUREG 0737, November 1980, " Clarification of TMI Action Plan Requirements".-
l
.c 13.2.2 Training for Technical and Management Staff
- a. General Discussion A comprehensive training program is in place for technical and management-personnel, complying with the provisions and intent of NRC Regulatory Guide 1.8, Revision 1-R, with ANSI /ANS 3.1-1978 used as l v
the standard in lieu of ANS 18 1-1971.
, Ni The program will provide personnel involved with the startup and operation of Seabrook Station training in various disciplines necessary to ensure that each can safely and effectively perform his assignmentr. The degree to which an employee is trained will be *"
consistent with his experience, intended position, and regulatory requirements. .
~
~The overall objectives of the training program are
.~.... -.
To train a staff to operate and maintain the units safely, ;
dependably, and economically.
l l
To prepare technical service groups for their functions necessary for the support and safety of plant operation.
- b. Responsibilities -
The following Sea!. rook personnel are responsible for this training: l gi
- 1. Station Manager The Seabrook Station Manager has the overall responsibility for
, j the qualification of personnel. He will review and approve all plant training programs. ,
l E
13.2-20
, - . - - - - - - _. ~ . _ . --, . _ . - ;. -
SB 1 &-2 Amendment FSAR March 1986
- 2. Assistant Station Manager The Assistant Station Manager is' responsible to the Station
' . Manager for administration of'all the training courses of the Training Department. The Assistant Station Manager will review all of those courses annually.
i-
- 3. Training Manager The Training Manager reports to the Assistant Station Manager I and is responsible- for development, ~implemen(ation and administration of general and specialty training including ~l Ceneral Employee Training, Fire Brigade Training -and Specialized Training.
- 4. ' Training Center Manager
[ The Training' Center Manager is responsible for development, i
implementation, and administration of Auxiliary Operator 4
training.
13 2.2.1 Program Description .,
4 Several ~ basic categories of training help technical personnel to attain' a high level of competence and professionalism. Specifically, these categories include the following:
- s. Initial Orientation i
111 persons joining the Seabrook Station operational organization, N--~-~
regardless of job assignment, initially will" receive orientation t
training. This phase of training consists of a brief informational program explaining' site organization, employee benefits, company policies.and procedures.
- b. General Emoloyee Training Ceneral Employee Training will consist of six programs covering site familiarization, security, radiation protection, industrial safety including fire safety, the radiological emergency plan, and ' quality assurance. The appropriate Station personnel will develop the program content and testing. - The program assumes that the new employee has no familiarity with nuclear power plants.
- c. -Supervisory Training Supervisory training is provided for working foreman, supervisors, senior engineers, managers, and section leaders.
rr .
13.2-21
SB 1 & 2 . Amendment FSAR March 1986 Supervisory indoctrination training includes but is not limited to (1.). company organization, (2) purchasing procedures, (3) records familiarization, (4) audit response, (5) regulatory environment, (6) techniques of supervision including hiring and personnel appraisal, (7)~ safety, and (3) technical writing.*
In addition, all supervisors receive a program in problem analysis, decision analysis, and potential problem analysis. All supervisors, except in non-technical areas such as s.ecurity and administrative services, participate in plant systems training. Most supervisors will complete a program in the psychology of motivation, organizational climate, and managerfal styles.
- d. Departmental'Trainink The particulars of this training appear in Subsection 13.2.2.4. g Figure 13.2-2 shows approximate time frames for accomplishing this.
training. The training schedule is intended to minimize conflicts in manpower requirements during preoperational testing.
- e. Fire Protection Train'ing The fire protection training ptogram for Seabrook Station follows the l guidance provided in the NRC document entitled " Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance." A description of that training program follows here.
~
- 1. Fire ' 'B rigade *
(a) Instruction ,
Fire Brigade members receive instruction in the topics !
below, as well as in any others deemed necessary _by the instructors.
(1) Fire hazards ~and associated types of fires that could occur in the station, and the location of the hazards, 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
- layout of the station including access and egress
, routes to each area.
^
13.2-22 ~
SB 1 & 2 Amendment FSAR March 1986 (3) Use of available' equipment, and a recommended method l
of fighting different types of. fires. The types of fires covered will include electrical fires, fires in cables and cable tray, hydrogen fires, flammable liquids, vaste/ debris fires, record file fires, hazar-dous process chemical fires and fires resulting from i construction or modification work. l .
I =f (4) Indqgtrination in the station fire fighting plan, with coverage of each individual's responsibilities, including changes thereto.
(5) - Use of breathing equipment, communication, lighting !
and portable ventilation equipment.
(6) A detailed review of fire fighting stratagies with l particular emphasis on what equipment might be used in particular areas.
(7) A review of Idtest 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 confined spaces. ,
(9) Fighting fires when a radiological hazard exists.
~
(10) The toxic and corrosive characteristics of expected products of combustion.
4 Fire Brigade leaders will receive the above listed instruc-tions and special instruction in directing and coordinating l fire fighting activities.
(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 9f brigade members with hands-on experience on extinguishing
' actual fires using the equipment available to them in the station. Practice sessions will al_so be held which. require fire brigade members to don protective equipment, including emergency breathing apparatus.
t O
j 13.2-23
l SB 1 & 2 Amendment FSAR March 1986-(c) Drills
-Brigade members will practice as a team in periodic drills. These drills will include the following:
(1) Simulated use of equipment' for the various situations and types of fires which could reasonably occur in each safety-related area.
r -
(2) Conformance, where possible, to the established sta- !
tion fire fighting plans.
(3) Operating fire fighting equipment, where practical.
This includes self-contained braathing apparatus,'com-
. aunication 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 minimum number i., of fire brigade der.11s conducted within a quarter will equal the number of operating shif ts at the station. Each individual member of the fire brigade will participate in l' at least.two drills per year. At least one drill per year for each fire brigade will be unannounced. At least one drill per year per brigade will be on a backshif t.
.,c
. Periodically (at least annually), a drill will involve off-
. _ _ _ _ . . , , _ . site fire departments. Preplanning will establish.the. --
H-. .. training objectives-of-the drills. A critique will deter--
i mine how well the training objectives have been met. At a minimum, the critique will assess I
(1) Fire alarm effectiveness, response time, selection, placement and use of equipment.
(
(2) The leader's directio'n of the effort and each member's response. .
- 2. Other Station Employees
, All full-time employees will receive instruction on fire protec-tion safety, evacuation routes, the procedures for reporting a fire, and any other subjects deemed necessary.
we Security personnel will receive instruction on procedures for entry of off-site fire departments, crowd control, and procedures for reporting potential fire hazards observed when l touring the facility.
Temporary employees and construction personnel will receive the instruction-in reporting fires, alarm response, and evacuation l routes.
i-13.2-24
)
SB 1 & 2 Amendment FSAR March 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 c The training for the Town of Seabrook Fire Department will include information on basic radiation principles and practices, and typical radiation hazards that may be encountered when '
fighting fires.
- 5. Refresher Training The fire protection refresher training program for fire brigade members and for ef f-site fire departments will be conducted on a two year cycle. Refresher 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
- station employees receive annual refresher training.
- f. Training for Mitigating the Consequences of Core Damage Special training for mitigating the consequences of core damage.is in place for applicable personnel. (See Table 13.2-3.) Instruction for ',
this program reflects INP0 ' guidelines for subject material.
" ---- : t 13.2.2.2 Coordination with Pre-operational Tes'ts sh3" Fuel Loading oc 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 participation in these phases of the startup will be incorporated in the training program. ,
The scheduling interface between the general and specialty training program l, and the start-up is illustrated in Figure 13.2-2. *
~13.2.2.3 Training Department Staff The training staff for this training consists of a Training Manager and several technical instructors. - The Training Manager has extensive experience as a professional vocational educator, with a background in curriculum ~
development, teacher training, supervision, and management. He has had training in Seabrook Plant Systems. Each training instructor has significant experience in one or more technical fields.
The staffing levels of the Training Department.are based on a periodic eval-uation of station training requirements. -
a 13.2-25
r SB 1&2 Amendment FSAR March 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 Instrument and control, chemistry, and health physics technicians, and spintenance mechanics and electricians receive an indoctrination j program followed by nuclear power plant fundamentals, radiation worker training, and site tagging instruction. Pretests may exempt an employee f rom portions of this training. Further training is 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. #
- 2. Chemistry technicians receive a course in chemistry fundamentals
. _ _ . _ . _ followed by courses in analytical chemistry-and pcimary f.
chemistry related to plant specific procedures and processes.
These courses are followed by a detailed chemistry-systems course which correlates laboratory analyses to plant system chemistry.
Certain chemistry technicians will r.eceive training in the use of a multi-channel analyzer for gamma-ray analysis.
- r
, Chemistry training content and duration are based on- a site spe-
~ ' " " ' - ~ ' '
cific task list.
- 3. Instrument and control technicians receive training in process l instrumentation and controls. Selected technicians, based on a *~
site specific task list, are trained on selected plant protec-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 system. Also, based on a site-specific task list, selected er technicians are trained on additional plant systems including the radiation monitoring system, the main turbine electro-hydraulic control system and selected plant fluid and electrical
. systems.
13.2-26
SB 1 & 2 Amendment FSAR March 1986 i
- 4. Mechanics receive training in hand tools, basic mechanical main-tenance, and mechanical maintenanceo 'f site equipment which is et based on a site-specific task list. Certain maintenance personnel receive training in such areas as bolting, snubbers, velding, non-destructive examination, crane operation, advanced vibration and hydraulic wrenches.
- 5. Electricians receive training in hand tools, basic eigstrical maintenance, and applied electrical maintenance of site equipment as determined by a site-specific task list. %
- 6. Auxiliary operators receive up to 36 weeks of initial training. The length of the training depends on the entry-level skills and knowledge of the trainees. The training consists of ,
classroom instruction on the primary and secondary plant systems and structured on-the-job training performed under the supervision of a qualified watchstander.
Activities included in the on-the-job training are systems walk-
. - . u.,- oc. .. throughs, performance of. shif t duties, equipment and systems operations using plant operating procedures, and implementing l
.. surveillance inspections and checks on operating equipment.
I I
Following the initial training and assignment to regular shift duties, the auxiliary operators will return to training on a rotation plan to receive continuing instruction on plant equipment and systems. .
~13.2.2 5 Position Task Analyses - ~ ' '
av Initial training utilizes descriptions of jobs and tasks as provided by each department. The Training Department, with the help of the' technical departments is using the generic _ task analyses provided by INPO and is making these site specific. We modify training programs based on the results of l these task lists. ,
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-back from department supervisors on the performance of employees and the need
.for retraining or additional training to upgrade skills. Annual personnel i appraisal procedures provide the means for supervision to indicate developmental training needs for each employee during his next appraisal period.
af 13.2-27
SB 1 & 2 Amendment FSAR March 1986 13.2.2.7 Retraining Technical personnel will receive retraining in' the following subjects: l Appropriate Administrative Procedures Radiation Protection Security Procedures Radiological Emergency Plan Fire Safety
- Safe Work Procedures This refresher training will be scheduled on a periodic basis, but not less than every two years, following receipt of an operating license. Also, periodic drills will reinforce procedures to be followed in the event of 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.
nr 13.2.2 9 Emergency Plan Training All persons assigned to the emergency response team will receive training to perform the functions of their position. They will also participate in periodic drills to ensure that they have maintained the ability to perform their tasks effectively.
e 13.2-28
Amendment March 1986
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SB 1 & 2 Amendment FSAR Harch 1986 13.4 Review and Audit Operating phase activitics that affect nuclear safety are reviewed and audited through a comprehensive program. The reriev and audit program will assure proper review and evaluation of proposed changes, tests, experiments, and unplanned events. Regulatory Guide 1.33 and ANSI N18.7-1976/ANS 3.2 require-ments for reviews and audits will form the basis for the program.
r 13.4 1 On-Site Review 13.4.1.1 SORC A Station Operation Review Committee (SORC) will perform the on-site opera-tional review responsibilities. The purpose of the SORC is to advise the Station management on all matters related to nuclear safety. The function, composition, meeting frequency, responsibilities and authority of the SORC are contained in Technical Specification 6.5.1.
13.4.1.2 SORC Charter .
A SORC Charter, approved by the Station Manager and Vice President-Nuclear Produ'ction delineates the rules and procedures by which the SORC functions.
The Charter contains the following information: C Name .
Basis .
Purpose
. -. Auth~ority Composition Meeting Frequency Ouorum Committee Responsibilities Recordt Amendmer.ts The SORC composition and qualifications are provided in Technical Specifi-cation 6.5.1.
The qualification levels of Station staff personnel and their alternates assigned to SORC membership meet or exceed those required by Section 4 of ANSI /ANS 3.1-1978.
In performing its duties the SORC will establish its own rules of practice that include: -
- a. When less than full membership is present, the quorum will ensure that matters to be considered are limited to those that are within the technical competence of the members present.
vs*
l 13.4-1
SB 1 & 2 Amendment FSAR March 1986
- b. Committee members will ensure an appropriate interdisciplinary review of activities under discussion.
- c. Sub-committees may be used at the discretion of the Chairman. When used, due consideration shall be given to the interdisciplinary composition of the subcommittee membership,
- d. The Chairman may authorize the use of experience from sources outside the SORC or outside the station staff where the particular matters under consideration cannot otherwise be reasonably resolved.
- e. The minutes of each SORC meeting are official plant records and shall be retained as provided in the station record retention procedures.
- f. In addition to distribution of SORC meeting minutes as provided in the Technical Specification 6.5.1, copies will be submitted to other appropriate management.
, 13.4.1.3 Operations Phase Reviews .
~
The scope of SORC review matters include those noted 1n Section 4.4 of ANSI 18.7-1976/ANS 3 2 as endorsed by Reg. Guide 1.33. The scope of SORC operational phase review is specified in Technical Specification 6.5.1.
13.4.1.4 Start-up Phase Reviews .
The SORC will be activated a minimum of six months prior to fuel load in order to condutt the following activities:
- a. Review test results of the integrated system pre-operational tests l performed prior to fuel load of each unit. /J
- b. Review and approve the test procedures and test results of initial start-up tests.
13.4.2 Independent Review 13.4.2.1 NSAR Committee A Nuclear Safety Audit and Review Committee (NSARC) will be operational six nionths prior to Unit 1 fuel loading. The function, composition, qualifica-tion, meeting frequency, responsibilities and authority of the NSARC are contained in Technical Specification 6.5.2. The goal of the NSARC is to provide management with an independent evaluation of station operations required to ensure safety. The NSARC performs its function through indepen-dent reviews and audits of all aspects of station safety.
4f 13.4-2
SB 1 & 2 Amendment FSAR March 1986 13.4.2.2 NSARC Charter A NSARC Charter, approved by the NSARC members' and the NHY Senior Vice President, delineates the mechanism for meeting Committee requirements. The Charter contains the following information: D Name Basis Function
- Composition Oualifications Meeting Frequency Quorum Review Audits Authority Records NSARC Operations Amendments , ,
Attachments .
" The NSARC composition and qualifications are provided in Technical Specification 6.5.2.2. The NSARC shall collectively have expertise and competence in the designated disciplines. Provisions are included in the charter to assure that appropriate expertise is ip 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 responsi-bility far the operation of the Station. The NSARC members are generally
--. selected from YAEC related organizations and NHY personnel; members may also be selected from outside consultancs or organizations. The minimum qualifi- s>
cations of all NSARC members meet or exceed those specified in ANS 3.1-1978.
Upon their selection, resumes of the regular NSAR Committee members and alternates will be maintained by the NSARC chairman.
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 use of subcommittees in performing its function. It also establishes the requirements for distribution of reports and/or meeting minutes and its authorization for
. initiating work.
~
91 t
13.4-3
SB 1 & 2 Amendment FSAR March 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-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 P reports 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 issaed 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
, p, , . - the quality assurance audit program described in the Seabrook Operational Quality Assurance Program contained in Section 17.2.
13.4.3 Independent Safety Engineering Group An Independent Safety Engineering Group (ISEG) will perform reviews of plant ,.3 operations, independent of those reviews performed. by the Station Operation Review Committee (SORC) and the Nuclear Safety Audit and Review Committee (NSARC).*
The ISEG will be composed of five, full time, dedicated enginee's'r loca't'ed on site who report their findings to the Executive Assistant to the Senior Vice President. Qualifications of the ISEG members will meet or exceed the requirements'in Section 4.4 of ANS 3.1, i.e., a Bachelor's degree in "*
engineering and two to four years experience in their field, including one to two years nuclear experience. The ISEC 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.
13.4.3.1 Duties and Responsibilities
- a. The general review functions of the ISEG include l A
- 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.
r ei e
13.4-4 l-
SB 1 & 2 Amendment FSAR March 1986
, 2. Maintain surveillance of plant operations and maintenance !
activities to provide independent verification that these 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 operational analysis, and aid in the establishment of programmatic requirements for plant activities. p r
- 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 l
becomes involved in the operating organization. 0l
~
13.4.3.2 Report's The ISEC will' pre p~ are dritten summaries of reviews and evaluations performed
' g ll as noted above. These summaries will include the results of, and recommenda-tions resulting from, such reviews and evaluations. Monthly reports containing a summary of work completed and recommendations made will be forwarded to the Executive Assistant to the Senior Vice President, with an information copy to the NHY Senior Vice President.,
13.4.3.3 . ch'arter
- The compp J.t_ign., qualifications, duties and responsibilities, and reporting -
requirements stated above will be incorporated into the ISEG Charter.
l e
13.4-5
SB 1 & 2 Amendment FSAR March 1986
~
Table 13.5-2 (Sheet 1 of 17)
Titles of Control Room Operating Procedures c
Listed below are the titles of Operating procedures which are used by licensed operators in the control room to perform various activities and plant evolu-tions. These titles are listed by various categories that are discussed in FSAR Section 13.5.2.3 1. They are lists of procedures that cover the signi-ficant operations within each category. Other procedures pertaining to these categories will be developed as indicated by future circumstances.
- 1. System Operating Procedures
- a. Reactor Coolant System ut REACTOR C00LAST SYSTEM EVACUA' TION FILL AND VE?G -
DRAINING TIE REACTOR COOLANT SYSTEM, REACIOR COOLANT DRAIN TANK OPERATION REACIOR C00LAST PUMP OPERATION PRESSURIZER BUBBLE FORMATION PRESSURIZER RELIEF TANK OPERATION ,
REACTOR MAKEUP WATER FILL AND VEhT -
,REACIOR MAKEUP WATER SYSTEM OPERATION
~
- b. Control Rod Drive System - -
' * * ~ '
ROD DRIVE M.C. SET OPERATION ACTIOMATIC AND MANUAL ROD CO.VIROL MAIhTAINING AXIAL FLUX DIFFERENCE
- c. Shutdown Cooling System ,
RESIDUAL HEAT REMOVAL TRAIN "A" STARTUP AND OPERATION RESIDUAL HEAT REMOVAL TRAIN "B" STARTUP AND OPERATION RESIDUAL HEAT REMOVAL TRAIN "A" SHUTDOWN RESIDUAL lEAT REMOVAL TRAIN "B" SHlTIDOWN
- d. Safety Injection and Containment Building Spray Systems t
INITIAL FILL AND VENT OF TIE SI SYSTEM FILLING AND VE!TIING THE SI ACCUMULATOR FILL AND VEVI 0F TEE CBS AND RHR SYSTEM TRAIN A AND TIE COMMON HOT LEG INJECTION LINES FILL AND VETTI 0F THE CBS AND RHR SYSTEM TRAIN B SPRAY ADDITIVE TANK MAKEUP AND !! EATING OPERATION OF TIE CONTAINMEfTI SPRAY SYSTEM
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 2 of 17)
- e. Component Cooling Water System e
PRIMARY COMPONE!G COOLING WATER FILL & VE?G P PCCW LOOP "A" STARTUP AND OPERATION PCCW LOOP "B" STARTUP AND OPERATION PRIMARY COMPONENT COOLING WATER LOOP "A" SHUTDOWN PRIMARY COM?ONEhT COOLING WATER I40P "B" SHUIDOWN PRIMARY COMPONE?E COOLING WATER LOOP HAXEUP AND CHEMICAL ADDITION SCCW SYSTEM FILL & VENT SECONDARY COMP. COOLING WATER SYSTEM OPERATION THERMAL BARRIER COOLING SYSTEM FILL AND VENT THERMAL BARRIER COOLING WATER STARTUP AND SHUIDOWN
~
- f. Containment ,i -
CONTAINMENT VE!GILATION OPERATIONS C0hTAINMEhT ENCLOSURE VENTILATION OPERATIONS C0!EAINMENT AIR PURCE OPERATIONS C0tGAINMENT ON-LINE PURCF. SYSTEM OPERATION H RECOMBINER OPERATION
,2 *
~ ~ ~ ~ - - -
- g. Steam Generator and Steam Generator Blowdown System PREPARING A STEAM CENERATOR FOR OPE 2ATION STEAM CENERATOR WET LAYUP AND RECIRCULATION STEAM CENERATOR DRAINING AND DRY LAYUP STEAM CENERATOR BLOWDOWN SYSTEM OPERATION STEAM CENERATOR BLOWDOWN DEMINERALIZER OPERATION SCBD EVAPORATORS OPERATION STEAM CENERATOR BLOWDOWN RECOVERY SUBSYSTEM OPERATION
- h. Fuel Storage Pool Purification and Cooling System SPE!E FUEL POOL CLEANUP & COOLING SYSTEM FILL AND VENT
', SPE!E FUEL POOL COOLING AND PURIFICATION SYSTEM STARTUP AND OPERATION
, i. Main and Auxiliary Steam Systems HAIN STEAM OPERATION HAIN STEAM TO AUX. STEAM REDUCING STATION OPS HOISTURE SEPARATOR / REHEATER OPERATION EXTRACTION STEAM SYSTEM OPERATION TURBINE STEAM SEAL SYSTEM OPERATION .
l L SB 1 & 2 Amendment FSAR March 1986 i
Table 13.5-2 j (Sheet 3 of 17)
L
- j. Auxiliary Boiler System l
AUXILIARY BOILER A STARTUP r l AUXILIARY BOILER R STARTUP l AUXILIARY BOILER DRY LAYUP l AUXILIARY BOILER WET LAYUP I
RECEIVING AUXILIARY BOILER FUEL OIL AUXILIARY STEAM AND CONDENSATE RETURNS AUXILIARY BOILER A SHW DOWN l AUXILIARY BOILER B SHWDOWN SHIFTING ATOMIZERS DURING AUX BOILER A OPERATION SHIFTING ATOMIZERS DURING AUX BOILER B OPERATION
- AUXILIARY BOILER 1A BLOWDOWN .
AUXILIARY BOILER IB BLOWDOWN .
AUXILIARY BOILER AND DEAERATOR FILL AND VEE
- k. Feedwater and Condensate System
[ CONDENSATE AND FEEDWATER SYSTEM FILL AND VEE STARTUP FEED PUMP OPERATION -
HAIN FEED PUMP STANDBY AND STARTUP OPERATION AAIN FEED PUMP RETURN TO STANDBY AND SHW DOWN l WARMING AN IDLE FEED PUMP -
FEEDWATER HEATER SYSTEM VENI OPERATION FEEDWATER HEATER ISOLATION AND RETURN TO SERVICE NITROCEN LAYUP 0F FEEDWATER HEATERS OPERATION OF THE HEATER DRAIN PUMPS HOTWELL FILL CONDENSATE SYSTEM OPERATION CONDENSATE WATER STORACE TANK MAKEUP OPERATION OF CONDENSATE STORACE TANK HEATING SYSTEM CONDENSATE HOTWELL DRAINING CONDENSATE CLEANUP SYSTEM OPERATION l'
- 1. Emergency Feedwater System ALIGNING THE EFW SYSTEM FOR AWOMATIC INITIAT10h
- RESTORATION OF EFW SYSTEM TO STANDBY AFIER AtJIO INITIATION i
E
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 4 of 17)
- m. Service Water and Circulation Water Systems e
SERVICE WATER SYSTEM FILL AND VE!R 9 TRAIN A SERVICE WATER OPERATION TRAIN B SERVICE WATER OPERATION SERVICE WATER COOLING TOWER OPERATION IDLE COOLING TOWER DEICING SERVICE WATER SCREEN WASH SYSTEM OPERATION CIRCULATING WATER SCREEN WASH SYSTEM CIRCULATING WATER SYSTEM STARTUP CIRCULATING WATER SYSTEM SHUTDOWN l CIRCULATING WATER HEAT TREATME!E
..s. .
CIRCULATING WATER SYSTEM TWO PUMP OPERATION CIRCULATING WATER SYSTEM FILL AND VENT CIRCULATING WATER CHLORINATION SYSTEM OPERATION DRAINING CONDENSER WATER BOXES CIRCULATING WATER SYSTEM ONE PUMP OPERATION FOR TESTING OR CHLORINATION
- n. Chemical and Volume Control System -
6PERATION OF LETDOWN, CHARGING AND SEAL INJECTION OPERATION OF EXCESS IITDOWN 3YSTEM OPERATION OF LETDOWN DECASSIFIER OPERATION OF MIXED BED DEMINERALIZERS ESTABLISHING A NITROGEN ATMOSPIERE IN TIE VOLUME C0!RROL TANK ESTABLISHING A HYDROGEN ATMOSPHERE IN THE VOLUNE CONTROL TANK OPERATION OF CVCS DEMINERALIZER PREFILTER CS-F-1 OPERATION OF THE REACTOR COOLA!E FILTER CS-F-2 OPERATION OF SEAL WATER INJECTION FILTERS CS-F-4A AND 4B OPERATION OF SEAL WATER RETURN FILTER CS-F-3 FILLING AND VE! RING TIE CHARGING, LETDOWN, SEAL INJECTION AND EXCESS LETDOWN PORTIONS OF TIE CVCS PRESSURIZER LEVEL C0!RROL SYSTEM OPERATION RESIN FILL OF MIXED BED DEMINERALIZER 2A RESIN FILL OF MIXED BED DEMI!ERALIZER 28 CATION DEMINERALIZER OPERATIONS AND FILL CHEMICAL AND VOLU?E CO?RROL SYSTEM MAKEUP OPERATION BORIC ACID PREPARATION AND TRANSFER TO THE STORACE TANXS BORIC ACID TANKS RECIRULATION AND SAMPLING l
BTRS CllILLER UNIT FILL AND VE?R BTRS CilILLER UNIT PRE-STARTUP BTRS OPERATION .
! BTRS RESIN FILL
- PRIMARY CHEMISTRY ADDITION
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 5 of 17)
- o. Heating and Ventilation Systems ADMINISTRATION BUILDING HEATING SYSTEM OPERATION ADMINISTRATION BUILDING VENTILATION SYSTEM OPERATION ADMINISTRATION BUILDING CHILL WATER SYSTEM OPERATION TURBINE BUILDING HEATING SYSTEM OPERATION TURBINE BUILDING VENTILATION SYSTEM OPERATION TURBINE BUILDING AIR CONDITIONING SYSTEM OPERATION CIRCULATING WATER PUMPHOUSE HEATING SYSTEM OPERATION CIRCULATING WATER PUMPHCUSE VENTILATION SYSTEM OPERATION SERVICE WATER PUMPHOUSE HEATING SYSTEM OPERATION SERVICE WATER PUMPHOUSE VENTILATION SYSTEM OPERATION SERVICE WATER COOLING TOWER HEATING SYSTEM OPERATION SERVICE WATER COOLING TOVER VEf(IILATION SYSTEM OPERATION CohTROL ROOM HEATING SYSTEM OPERATION C0hTROL ROOM VE!(IILATION SYSTEM OPERATION CONIROL ROOM AIR CONDITIONING SYSTEM DIESEL GENERATOR BUILDING EATING SYSTEM OPERATION DIESEL GENERATOR BUILDING VENIILATION SYSTEM OPERATION PRIMARY AUXILIARY BUILDING EATING SYSTEM OPERATION PRIMARY AUXILIARY BUILDING VEhTILATION SYSTEM OPERATION
,pABEE SPREADING AREA, EMER SWGR AREA AND ELELTRICAL TUNNEL AREA
, VENIILATION SYSTEM OPERATION - -- -
- NON-ESSEffrIAL SWITCHGEAR ROOM VEffrILATION SYSTEM OPERATION NON-ESSENTIAL SWITCHCEAR ROOM HEATING SYSTEM OPERATION WASTE PROCESSING BUILDING HEATING SYSTEM OPERATION WASTE PROCESSING BUILDING VENTILATION SYSTEM OPERATION FUEL STORAGE BUILDING HEATING SYSTEM OPERATION FUEL STORAGE BUILDING VEVIILATION SYSTEM OPERATION EMERGENCY FEEDWATER BUILDING HEATING SYSTEM OPERATION EMERGENCY FEEDWATER BUILDING VEP(TILATION SYSTEM OPERATION WPB COMBINATION AIR CONDITIONING / ELECTRIC HEAT OPERATION
- p. Instrument Air System OPERATION OF THE COMPRESSED AIR SYSTEM OPERATION OF C0!(TAINME!(I COMPRESSED AIR SYSTEM OPERATION OF CE?frRIFUCAL AIR COMPRESSOR ,
6 O
SB 1 & 2 Amendment FSAR March.19o6 Table 13.5-2 (Sheet 6 of 17)
- q. Electrical System c
MAIN GS'ERATOR TRANSFORMER AUXILIARIES OPERATION UNIT AUXILIARY TRANSFORMER AUXILIARIES OPERTAION RESERVE AUXILIARY TRANSFORMER AUXILIARIES OPERATION 245 KV OPERATION 13.8 KV OPERATION 4.16 KV OPERATION VITAL 480 VOLT OPERATION NON-VITAL 480V OPERATION LIGHTING SYSTEM OPERATION OPERATION OF MAIN GENERATOR BREAXER MANUAL OPERATION OF MOTOR OPEl(ATED DISCONNECTS VITAL INVERTER OPERATION . - - --
TRANSFERRING POWER SUPPLIES TO 120V VITAL INSTRUMENT BUSES NON-VITAL INVERTER OPERATION TRANSFERRING POWER SUPPLIES TO 120V AC NON-VITAL INSTRUMENT BUSES 125V DC VITAL SYSTEM OPERATION 125V DC BATTERY CHARGERS 1A, 15, 1C AND 10 OPE 2ATION 125V DC NON-VITAL OPERATION .
OPERATION OF BATTERY CHARGERS 2A AND 2B PORTABLE BATTERY CHARGER OPERATION
- - ~ * " " **
- SWITCHYARD EATTERY CHARCER OPERATION OPERATION OF D/G 1A CPERATING THE D/G 1A LUBE OIL SYSTEM STARTUP AND SHUTDOWN OF D/G 1A JACKET COOLING WATER SYSTEM OPERATING THE D/G 1A STARTING AIR SYSTEM OPERATING THE D/G 1A FUEL OIL SYSTEM OPERATING THE D/G 1A AIR INTAKE, EXHAUST AND YACUUM SYSTEM ALIGNING D/G 1A CONTROLS FOR AtTIO START D/G 1A MAINTENANCE STARTING OPERATION OF THE D/C IB OPERATING THE D/G 1B LUBE OIL SYSTEM STARTUP AND SHUTDOWN OF D/G 1B JACKET COOLING WATER SYSTEM OPERATING THE D/G 15 STARTING AIR SYSTEM ,
OPERATING THE D/G 18 FUEL OIL SYSTEM OPERATING THE D/G 1B AIR INTAKE, EXHAUST AND VACUUM SYSTEM
{
ALIGNING D/G 15 CONTROLS FOR AtTr0 START D/G 18 MAINTENANCE STARTING
+
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 7 of 17)
- r. Nuclear Instrument System e
NIS SWITCH ALIGNME!G NI SYSTEM VISUAL / AUDIO COUNI RATE SYS OPERATION
- s. Reactor Control and Protection System RPS PRECRITICAL CHECKS & SWITCH ALIGN >ENTS
- t. Fire Protection Systems FIRE WATER PIPING DRAIN, FILLING AND VE!GING DIESEL FIRE PUMP OPERATIONS .
MOTOR DRIVEN FIRE PUMP FP-P-21. OPERATION FIRE PROTECTION TANK HEATING RECEIPT OF DIESEL FIRE PUMP FUEL OIL FIRE PUMP HOUSE SYSTEM STEAM AND BUILDING HEATING FIRE PUMP HOUSE PACKAGE BOILER OPERATION DIESEL FIRE PUMP ROUTINE TEST .
ELECTRIC FIRE PUMP ROITIINE TEST .
FIRE PROTECTION SYSTEM MONTHLY VALVE ALIGNMENT C1ECK ANNUAL FIRE PROTECTION SYSTEM FLUSH ANNUAL FIRE PROTECTION SYSTEM VALVE CYCLE TEST 18 M0!GH FIRE SYSTEM FUNCTIONAL TEST ANNUAL FIRE HYDRANT FLOW CHECK 3 YEAR HOSE STATION VALVE CYCLE AND FLOW TEST 3 YEAR FIRE SYSTEM WATER FLOW TEST DRY PIPE SPRAY AND SPRINKLER HEADER INSPECTION (18 MONTH)
N0ZZIZ SPRAY AREA INSPECTION (18 M0?EH)
OPEN LEAD SPRAY N0ZZLE AND LEADER AIR FLOW TEST (3 YEAR)
- u. Water Treatment and Domineralized Water System FILL, VENT AND BACKWASH WATER TREATME!E SYSTEM COMPONE!GS TRA7N A FILL, VE!E AND BACKWASH WATER TREATMENT SYSTEM COMPONE?GS TRAIN B OPERATION OF THE CARBON FILTERS PLACING TIE WATER TREATMENT SYSTEM IN SERVICE - Attr0HATIC OPERATION SEMI-AtJIONATIC RECENERATION OF TIE CATION-ANION TRAIN A SEMI-AITIOMATIC REGENERATION OF THE CATION-ANION TRAIN B SEMI-AUTOMATIC RECENERATION OF MIXED BED A SEMI-Attr0MATIC RECENERATION OF MIXED BED B OPERATION OF TIE NEllrRALIZATION SYSTEM FILLING THE ACID STORACE TANK .
SB I & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 8 of 17)
- u. Water Treatment and Demineralized Water System (Continued)
FILLING TE CAUSTIC -STORAGE TANK PLACING THE WATER TREATMENT IN SERVICE - MANUAL OPERATION OPERATION OF DEMINERALIZED WATER TANK HEAT EXHANGER FILL AND VEE OF DEMINERALIZED WATER SYSTEM OPERATION OF THE DEMINERALIZED WATER SYSTEM
- v. Main Turbine and Turbine Support Systems PLACING TE TURBINE CENERATOR ON TURNING CEAR FROM COLD STANDSTILL CONDITION STARTING AND P)tASING TE TURB{NE CENERATOR TURBINE CENERATOR SHUTDOWN .
REMOVING TE TURBINE CENERATOR FROM TURNING CEAR OPERATION STARTUP AND SHWDOWN OF ELECTRO-!!YDRAULIC CONTROL SYSTEM MAIN TURBINE STANDBY CONTROL SYSTEM OPERATION OPERATION OF MECHANICAL VACUUM PUMPS ENERGIZING AND DE-ENERGIZING TE CORE MONITOR STARTUP AND SHWDOW OF TE STATOR COOLING. WATER SYSTEM PURGING CO FROM THE TURBINE CENERATOR VITH AIR STARTUP M SHUTDOWN OF SHAFT SEAL OIL SYSTEM FILLING TE T'JRBINE GENERATOR WITH HYDROCEN -
PURGING AIR FRC't TE TURBINE CENERATOR PURGING H FROM TE CENERATOR WITH C0 STARTUP AbD SHITIDOWN OF TE ISOPHASE kUS DUCT COOLING SYSTEM FILLING TE MFP TURBINE (P32A-P32B) LUBE OIL RESERVOIR CLEANING TE LUBE OIL CONDITIONERS CONDITIONING THE MAIN TURBINE LUBE OIL RESERVOIR CONDITIONING TE FEED PUMP LUBE OIL RESERVOIRS BATCH CONDITIONING THE TURBINE LUBE OIL STORAGE TANK, TK-48 TURBINE LUBE OIL SYSTEM OPERATION FILLING THE TURBINE LUBE OIL STORACE TANK, TK-48 FILLING THE MAIN TURBINE LUBE OIL RESERVOIR
- w. Boron Recovery and Waste Systems PRIMARh DRAIN TANK DECASSIFIER STARTUP AND OPERATION PRIMARY DRAIN TANK DEGASSIFIER SHUIDOWN AND PURGE BORON RECOVERY EVAPORATOR 3A STARTUP AND OPERATION BORON RECOVERY EVAPORATOR 3B STARTUP AND OPERATION BORON RECOVERY EVAPORATOR 3A SHUTDOWN AND FLUSit BORON RECOVERY EVAPORATOR 3B SHUIDOWN.AND FLUSH BORON RECOVERY TEST TANK SYSTEM OPERATION BORON RECOVERY STORAGE SYSTEM OPERATION
r SB 1 & 2 Amendment FSAR March 1986 l
Table 13.5-2 f
(Sheet 9 of 17)
- w. Boron Recovery and Waste Systems (Continued) c FLOOR DRAIN TANK (WL-TK-59A) RECIRCULATION r FLOOR DRAIN TANK (WL-TK-595) RECIRCULATION WASTE EVAPORATOR EV-4 STARTUP AND OPERATION l FLOOR DRAIN TANK WL-TK-59A TRANSFER TO EVAPORATOR EV-4 FLOOR DRAIN TANK WL-TK-595 TRANSFER TO EVAPORATOR EV-4 WASTE EVAPORATOR EV-4 BOTTOMS TRANSFER, SHUT DOWN AND FLUSH RECIRC VASTE TEST TANK (SAMPLINC)
WASTE TEST TANK 63A DISCHARGE TO TRANSITION STRUCTURE WASTE TEST TANK 635 DISCHARGE TO TRANSITION STRUCIURE WASTE TEST TANK 63A TRANSFER TO FLOOR DRAIN TANKS
..:.zw.-.
. . WASTE TEST TANK 635 TRANSFER TO FLOOR DRAIN TANKS-PURIFICATION OF WASTE TEST TANK RESIN FILL OF TE LIQUID WASTE DEMINERALIZER WL-DM-15 RESIN SLUICE OF TE WP5 DEMINERALIZERS TO SRST RESIN SLUICE UNIT 1 CATION AND MIXED BED DEMINERALIZERS RESIN SLUICE OF THE BTRS DEMINERALIZERS RESIN SLUICE OF TE UNIT 1 SPE}ff FUEL POOL.DEMINERALIZER OPERATION OF TE SPE!TT RESIN SLUICE SYSTEM.
R'ADICACTIVE WASTE CAS SYSTEM OPERATION
~~ - ~ ~~ "" ~
EQUIPMENT VENT SYSTEM OPERATION FLOOR AND EQUIPME!(I DRAIN SYSTEM OPERATION -
l CHEMICAL DRAIN TREATHE!ff SYSTEM OPERATION
- x. Miscellaneous Systeus I STARTUP AND SHtTIDOWN OF NITROCEN CAS SYSTEM l
BULK HYDROCEN OPERATION .
l PGTABLE WATER SYSTEM OPERATION l WATER HEATER OPERATION REMOVINC MAJOR SECTIONS OF THE PW SYSTEM FROM SCVICE SOUND POWERED PHONE SWITCHINC PANEL OPERATTCa
- 2. Station Operating Procedures
- a. Main Plant Evolutions ,
~
HEATUP FROH COLD SHITfDOWN TO HOT STANDBY PLAlfr STARTUP FROM HOT STANDBY TO MINIMUM LOAD PLANT SHUTDOWN FROM MINIMUM LOAD TO hut STANDBY PLAfff C00LDOWN FROM HOT STAND 8Y TO COLD SHttfDOWN POWER INCREASE .
POWER DECREASE .
APPROACH TO CRITICALITY POST TRIP REVIEW l
h SB 1 & 2 Amendment l FSAR March 1986 Table 13.5-2 (Sheet 10 of 17)
- b. Refueling Procedures e
REFUELING OPERATIONS r FILLING THE REACTOR REFUELING CAVITY AND FUEL TRANSFER CANAL REACTOR REFUELING CAVITY PURIFICATION l REFUELING MACHINE OPERATION FUEL TRANSFER SYSTEM AND UPENDER OPERATION NEW FUEL HANDLING TOOL OPERATION SPENT FUEL PIT BRIDCE OPERATION RCCA CHANGE MACHINE OPERATION IN CONTAINMENT l REFUELING CANAL AND CAVITY DRAINING IRRADIATION SAMPLE HANDLING TOOL CPERATION l RCCA CHANGE TOOL OPERATION . -
i,. . . . .
BURNABLE POISON ROD ASSEMBLY HANDLING TOOL OPERATION
- THIMBLE PLUG HANDLING TOOL OPERATION SPENT FUEL HANDLING TOOL OPERATION NEW FUEL ELEVATOR OPERATION UNLATCHING AND LATCHING RCCA EXTENSION SHAFTS
- 3. Abnormal and Emergency Operating Procedures .
- a. System Abnormal Procedures -
RESPONSE TO FIRE OR FIRE ALARM ACTUATION SAFE SHUIDOWN AND C00LDOWN FROM THE MAIN CONTROL ROOM SAFE SHUTDOWN AND COOLDOWN FROM THE REMOTE SAJE SillfrDOWN FACILITIES ABNORMAL REACTOR COOLAYr PUMP OPERATION AND $11UIDOWN UNISOLATABLE REACIOR COOLANT SYSTEM LEAKACE TO COVIAINMEYr RCS VALVE STEM LEAKAGE LOSS OF REACTOR VESSEL FLANGE SEAL LOSS OF LETDOWN LOSS OF C11ARGING RAPID BORATION REACIOR COOLANT SYSTEM HIGH ACTIVITY REACIOR COOLANT SYSTEM - CHEMISTRY OUT OF SPECIFICATION
, FAILURE OF CONTROL ROD BANK TO MOVE COVIINUOUS C0!GROL ROD INSERTION CONTINUOUS CORTROL ROD WITilDRAWAL "
DROPPED ROD . .
MISALIGNED ROD (S)
RPI MALFUNCTION I PCCW SYSTEM MALFUNCTION LOSS OF RllR DURING S!!!TfDOWN COOLING .
t
SB 1 & 2 Amendment FSAR March 1986
_ Table 13.5-2 (Sheet 11 of 17)
- a. Systen Abnornal Procedures (Continued)
SERVICE WATER SYSTEM MALFUNCTION COOLING TOWER MALFUNCTION P RECOVERY FROM STEAM CENERATOR BLOWDOWN SYSTEM ISOLATION STEAM CENERATOR TUBE LEAK HIGH VIBRATION TURBINE CENERATOR TURBINE TRIP BELOW P-9 TURBINE RUNBACK / SETBACK PARTIAL LOSS OF VACUUM CONDENSER TUBE OR TUBE SHEET LEAK PARTIAL LOSS OF SECONDARY FEED FLOW LOSS OF STATOR COOLING SYSTEM STATOR COOLING WATER HICH CONDUCTIVITY LOSS OF ISOPHASE BUS DUCI COOLING LOSS OF INSTRUMENT AIR LOSS OF CONTAINME.Vr INSTRUMENT AIR FIRE MAIN BREAK OIL SPILL LOSS OF CONTROL ROOM MAKEUP AIR -
L,0SS OF TIE PLANT COMPITTER *
^'
- b. E$ergency Operating Procedu~r'es' "
- 1. Optimal Recovery Guidelines REACIOR TRIP OR SAFETY INJECTION REDIACNOSIS REACIOR TRIP RESPONSE NATURAL CIRCULATION C00LDOWN NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
- LOSS OF REACIOR OR SECONDARY COOLANT SI TERMINATION POST-LOCA COOLDOWN AND DEPRESSURIZATION TRANSFER TO COLD LEC RECIRCULATION TRANSFER TO HOT LEC RECIRCULATION .
FAULTED STEAM CENERATOR ISOLATION STEAM CENERATOR TUBE RUPTURE POST-SCTR C00LDOWN USING BACKFILL POST-SCTR C00LDOWN USING BLOWDOWN POST-SCIR COOLDOWN USL/C STEAM DUMP
SB 1 & 2 Amendment FSAR March 1986 l
Table 13.5-2 (Sheet 12 of 17) l 2. Emergency Contingency Actions e
LOSS OF ALL Ac POWER c
LOSS OF ALL AC POWER RECOVERY WITH0tTT SI REQUIRED LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED LOSS OF EMERGENCY C00LANI RECIRCULATION LOCA OtJTSIDE CONTAINMENT l UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS SCIR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY SCTR WITH0tfr PRESSURIZER PRESSURE C0hTROL 3 Critical Eafety Functions, ,
SUBCRITICALITY (CRITICAL SAFETY FUNCTION STATUS TREE)
,, CORE COOLING (CRITICAL SAFETY FUNCTION STATUS TREE)
HEAT SINK (CRITICAL SAFETY FUNCTION STATUS TREE)
INTEGRITY (CRITICAL SAFETY FUNCTION STATUS TREE) l CONTAINMENT (CRITICAL SAFETY FUNCTION. STATUS TREE)
. INVENIORY (CRITICAL SAFETY FUNCTION STATUS TREE)
- 4. Function Restoration Guidelines -
RESPONSE TO NUCLEAR POWER GENERATION /ATWS RESPONSE TO LOSS OF CORE SHITIDOWN RESPONSE TO INADEQUATE CORE COOLING RESPONSE TO DECRADED CORE COOLING RESPONSE TO SATURATED CORE COOLING CONDITIONS RESPONSE TO LOSS OF SECONDARY HEAT SINK RESPONSE TO STEAM GENERATOR OVERPRESSURE RESPONSE TO SIEAM GENERATOR HICH LEVEL RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES RESPONSE TO STEAM CENERATOR LOW LEVEL l RESPONSE TO IMMINENT PRESSURED THERMAL SHOCK CONDITIONS i -
RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION l
- RESPONSE TO HICH CONTAINMENT PRESSURE RESPONSE TO CONTAINMENT FLOODING RESPONSE TO HICH CONTAINMENT RADIATION LEVEL l RESPONSE TO HICH PRESSURIZER LEVEL l RESPONSE TO LOW PRESSURIZER LEVEL l RESPONSE TO VOIDS IN REACTOR VESSEL i
l
, SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2
+
(Sheet 13 of 17)
- 4. System Surveillance Procedures i
i c
- a. Rey tor Coolant System POST REFUELING LEAK TEST RCS STEADY STATE LEAK RATE CALCULATION PORV BLOCK VALVE OPERABILITY TEST RCP SEAL INJECTION CONIROLLED LEAKAGE SURVEILLANCE i 18 MONIH PORV TEST, l
- b. Emergency Core Cooling Systems MONTHLY ACCUMULATOR VALVE, BREAKER AND BORON CHECKS 18 M0hTH ACCUMULATOR VALVE ACTUATION TEST
- MONTHLY SAFETY INJECTION PUMP FLOW TEST C0hTAINMEhT SPRAY SYSTEM VALVE VERIFICATION CONTAINMENT SPRAY PUMP TEST 18 M0hTH CONTAINMENT SPRAY AUIO VALVE ACTUATION VERIFICATION 18 MohTH C0hTAINMENT SPRAY PCMP AITIO ACTUATION TEST 5 YEAR COhTAINMEhT SPRAY SYSTEM AIR FLOW TEST SEMIANNUAL SAT VOLUME AND CONCENTRATION VERIFICATION 3 YEAR SPRAY $ ADDITIVE- SYSTEM SOLUTION FLOW TEST
. EMERGENCY BO'AATION FLOW TEST BORON INJECTION FLOW PATH MONTHLY VALVE ALIGNMEhT chi.CK MONTHLY CHARGIhG PUMP FLOW TEST MONTHLY ECCS VALVE VERIFICATION
( 18 MONIH ECCS AITTO VALVE ACTUATION VERIFICATION 18 MONIH ECCS PUMP AUTO ACTUATION TEST t
18 MONTH ECCS THROTTLE VALVE VERIFICATION ECCS SYSTEM FLOW BALANCE
, MONTHLY RHR PUMP FLOW TEST j RHR SYSTEM INTERLOCK CHECKS CONTAINMENT RECIRCULATIOP SUMP INSPECTION
- c. Component Cooling Water System PCCW PUMP A OPERABILITY TEST ,
3 PCCW PUMP B 0FERABILITY TEST ,
PCCW PUMP C OPERABILITY TEST PCCW PUMP D OPERABILITY TEST PCCW LOOP A LINEUP VERIFICATION TEST PCCW LOOP B LINEUP VERIFICATION TEST e
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 14 of 17)
- d. Control Rod Drive System p ROD OPERABILITY CHECK
- e. Containment CONTAINMENT 24 HOUR AVERAGE AIR TEMP SURVEILLANCE
- CONTAINMENT PRE-ENTRY AND REFUELING PURGE SYSTEM SURVEILLANCE H22ECOMBINER 6 MONTH FUNCTIONAL TEST H2 RECOMBINER 18 MONTH FUNCTIONAL TEST H2MIXING SYSTEM 92 DAY SURVEILLANCE H 2 MIXING SYSTEM 18 MONTH SURVEILLANCE
. .. a _ . . . . . . . CONTAINMENT ENCLOSURE EMERGENQY EXHAUST .EILTER. SYSTEM 31 DAY SURVEILLANCE .
CONTAINMENT ENCLOSURE EMERGENCY EXHAUST FILTER SYSTEM REFUELING SURVEILLANCE CONTAINMENT ENCLOSURE COOLING SYSTEM 31 DAY SURVEILLANCE
. CONTAINMENT ENCLOSURE COOLING SYSTEM 10 MONTH SURVEILLANCE CONIROL ROOM MAKEUP AIR SYSTEM 31 DAY SURVEILLANCE CONTROL ROOM MAKEUP AIR SYSTEM 18 MONTH SURVEILLANCE CONTAIN!!ENT PURCE AND EXHAUST ISOLATION SURVEILLANCE
. f. Fuel Storage and Refueling '"'
SPENT FUEL POOL CRANE LOAD TEST REFUELING MACHINE CHECK OUT PROCEDURE
- g. Service Water System .
MONIHLY SERVICE WATER VALVE VERIFICATION 18 MONTH COOLING TOWER AUTO ACTUATION TEST MONTHLY COOLING TOWER FAN OPERABILITY TEST
- h. Chemical and Volume Control System WEEKLY BORATED WATER SOURCE EVALUATION
.i. Ventilation System FUEL STORACE BUILDING CLEANUP SYSTEM 31 DAY SURVEILLANCE FUEL STORACE BUILDING EMERGENCY AIR CLEANING SYSTEM 18 MONTH SURVEILLANCE
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 15 of 17)
- j. Main and Auxiliary Steam Systems e
MSIV CLOSURE TEST WEEKLY TEST OF THE EXTRACTION STEAM NON-RETURN CHECK VALVES
- k. Electrical Systems D/G 1A OPERABILITY SURVEIi.t JCE D/G 1A 18 MONTH OPERABILITY SURVEILLANCE EMERGENCY POWER SEQUENCER OPERABILITY D/C 1A 24 HOUR LOAD TEST D/G IB OPERABILITY SURVEILLANCE D/G 1B 18 MOSTH OPERABILITY SUJtVEILLANCE - ---- -
D/G 1B 24 MONTH LOAD TEST .
AC POWER SOURCE OPERABLE BUSES E5 AND E6 0FFSITE POWER SUPPLY TRANSFER OPERABILITY TEST AC ELECTRICAL DISTRIBUTION SYSTEM OPERABILITY (OPERATING)
AC ELECIRICAL DISTRIBUTION SYSTEM OPERABILITY (SHUI DOWN)
INVERTER ED-I-2A TRIP CIRCUIT TEST .
DC ELECTRICAL DISTRIBUIION SYSTEM OPERABILITY BATTERY CHARGER SEMI ANNUAL BREAKER CHECK
- 1. Air System - - ---- ' " ' ' ' ' ' -~
SERVICE AIR LOW HEADER PRESSURE ISOLATION COMPRESSED AIR EMERGENCY COOLING VERIFICATION
- m. Feedwater System .
~
THRUST BEARING WEAR DETECIOR TEST FEED PUMP TURBINE . ALTERNATE MOP AND EOP OPERABILITY TEST OVERSPEED TRIP AND LOCK 0UI SUPPRESSED SPEED TEST FEED PUMP TURBINE OVERSPEED TRIP MECHANISM TEST MAIN FEED PUMP TURBINE STOP VALVES TEST EMERGENCY FEEDWATER MONTHLY VALVE VERIFICATION TURBINE DRIVEN EMERGENCY FEEDWATER PUMP MONTHLY OPERABILITY TEST ELECIRIC DRIVEN EMERGENCY FEEDWATER PUMP MONIHLY OPERABILITY TEST FW ISOLATION VALVE ACIUATION TEST
- O O
w -, -e-r %,, -- --,, ,-- ---- - = , - , . _ . - -- - -,
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 16 of 17)
- n. Fire Protection System c
MONTHLY VISUAL INSPECTION OF ACCESSIELE FIRE HOSE FrATIONS INACCESSIBLE HOSE STATION INSPECTION AND INVENIORY HOSE AND CASKET INSPECTION FIRE HOSE HYDROSTATIC TEST MONTHLY YARD HYDRANI AND HYDRANT HOSE STATION INSPECTION AND INVE.YTORY SEMI-ANNUAL YARD HYDRANT BARREL INSPECTION ANNUAL YARD HYDRANI HOSE STATION HYDROSTATIC TEST AND CASKET INSPECTION PORTABLE FIRE EXTINGUISHER INSPECTION (MONTHLY)
ANNUAL PORTABLE FIRE EXTINGUISHER INSPECTION /MAIhTENANCE
~
PORTABLE FIRE EXTINGUISHER MAINTENANCE _. . _ _.
PORTABLE FIRE EXTINGUISHER HYDP'0 STATIC TEST (5 YEAR)
PORTABLE FIRE EXTINGUISHER HYDROSTATIC TEST (12 YEAR)
. FIRE BRIGADE TOOL & EQUIPMENT INVENTORY (QUARTERLY)
M0hTHLY INSPECTION PROCEDURE FOR HALON 1301 SYSTEMS SEMI-ANNUAL HALON 1301 QUA.YrITY AND PRESSURE VERIFICATION ANNUAL HALON 1301 INSPECTION AND TEST RATED FIRE DOOR INSPECTION (VARIABLE FREQUENCY)
VISUAL INSPECTION OF AMBULANCE (DAILY) g,.. INSPECTION AND INVENTORY OF AMBULANCE (M0hTHLY)
- o. Main Turbine and Auxiliaries BACKUP SPEED CONTROL AMPLIFIER SURVEILLANCE TEST TURBINE STOP VALVES TEST CONTROL VALVE TEST -
CIV TEST EMERGENCY BEARING OIL PUMP MONTHLY TEST WEEKLY MECHANICAL TRIP PISTON TEST MAIN TURBINE WEEKLY ELECTRICAL TRIP TEST MAIN TURBINE OVERSPEED TEST ACTUAL 105% BACKUP OVERSPEED TURBINE TRIP TEST EMERGENCY BEARING OIL PUMP YEARLY TEST
- CENERATOR AND HYDROCEN SUPPLY SYSTEM LEAK DETECTION TURBINE, LIFT PUMP TEST I
MAIN TURBINE LUBE OIL PUMP WEEKLY TEST ' 1 THRUST BEARING WEAR DETECTOR TEST I WEEKLY T/C BACKUP OVERSPEED TRIP CIRCUIT TEST WEEKLY MECHANICAL OVERSPEED TRIP TEST TURBINE LUBE OIL LEVEL SWITCH WEEKLY TEST EHC HYDRAULIC POWER UNIT WEEKLY TEST ,
EHC HYDRAULIC POWER UNIT ACCUMULATORS QUARTERLi TEST J
)
SB 1 & 2 Amendment FSAR March 1986 Table 13.5-2 (Sheet 17 of 17)
- o. Main Turbine and Auxiliaries (Continued)
POWER / LOAD UNBALANCE WEEKLY TEST r EARLY VALVE ACTUATION TEST WEEKLY TEST OF THE EXTRACTION STEAM NON RETURN CHECK VALVES OPERATIONAL TEST OF STATOR COOLANT LOW FLOW TURBIhI RUNBACK CENERATOR CORE MONITOR QUARTERLY TEST GENERATOR CORE MONITOR MONTHLY TEST EMERGENCY SEAL OIL PUMP TEST STATOR COOLING WATER PUMP WEEKLY TEST
- p. Miscellaneous System 7- - - WEEKLY TEST OF THE STATION GA TRONICS ALARMS RADIATION MONITORING OPERABILITY TEST I
O e
me oe 9
O t
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e
l SB 1 & 2 Amendment FSAR March 1986 DR. GERALD M. KWASNIK CORPORATE HEALTH PHYSICIST Dr. Kwasnik received his Bachelor of Science Degree in Biological Science >
in 1972, and his Master of Science Degree in Biological and Environmental p Science in 1975 - both from the University of Detroit. In 1977, Dr. Kwasnik
- received his Doctorate Degree from Purdue University in Radiation Health 9 Physics.
Upon graduation from Purdue University, he was employed by Exxon Nuclear, Inc. as a Senior Health Physicist at the Idaho Nuclear Fuels Reprocessing '
Facility. While at the nuclear fuel reprocessing facility he performed a wide range of health physics and radioactive vaste management duties and responsibilities. . In October of 1978, Dr. Kwasnik was part of the initial plant recovery and assessment team following the uncontrolled criticality incident that occurred there.
< . . - In 1980 he joined American Nuclear Insurers (ANI) as a Staff Health Physicist. His primary responsibilities and duties were nuclear power and fabrication plant inspections, development of inspection standards and criteria for ANI. inspections and providing technical support for radiation claim litigation including the Three Mile Island class action suit.
In 1982 Dr. Kwasnik joined Public ' Service of New Hampshire as the Principal Health Physicist for the corporate support staff. His duties and responsi6111 ties include station health physics support, managing interface for the radioactive waste management program, serving as the New Hampshire - -
_ Yankee (NHY) liaison with all regulatory agencies in the areas of radiation protection and radioactive vaste management and corporate liaison for on-site emergency planning.
t e
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O 13A-6 i
SB 1 & 2 Amendment FSAR March 1986 JAMES A. MacDONALD RADIOLOGICAL ASSESSMENT MANAGER Mr. MacDonald received his Associate in Nuclear Engineering from Wentworth Institute in 1965, his Bachelor of Science in Nuclear Engineering from Lowell Technological Institute in 1968, and his. Master of Science in Radiological Health from Harvard University in 1970. IW the summer of 1969 he completed i the Health Physics Training Program sponsored by Brookhaven National Laboratory and the USAEC.
'While completing the last three years of his undergraduate studies, Mr.
- / -
MacDonald worked for Sanders Nuclear Corporation in Neshua, New Hamsphire as an Engineering Assistant. His time was devoted to performing analytical design of various systems employing radioisotopes as heat sources. This work included the feasibility evaluation of the application of radioisotopes for these systems and devices by analytically designing and optimizing fuel capsules,' energy conversion systems, and shielding.
a.,n.m. .m In addition, Mr. MacDonald worked on establishing and implementing a facility radiation safety program. This included work on the design and licensing of a remote-handling hot cell and a radiochemistry laboratory.
Mr.. MacDonald joined Yankee-Westboro in May of 1970 as -an engineer within p the Radiation Protection.Section. In this capacity, Mr. MacDonald assisted in obtaining plant operating licenses in the areas-of radioactivity source
~ term analysis.and dose evaluations, environmental radiological monitoring emergenef planning and in-plant radiation protection programs. '
In September of 1972, Mr. MacDonald transferred to the Safety Analysis Section where he worked in the source term and dose evaluation areas. These evaluations were performed for radioactivity releases associated with normal plant operation and for releases associated with accident conditions.
In October.of 1973, Mr. MacDonald was appointed to the position of Manager of.the Radiation Protection Group. In this capacity, Mr. MacDonald directed the activities of the group which include b'oth licensing assistance in the radiation protection area for plants under design and construction and oper-ational health physics assistance for operating -plants.
i.
Mr. MacDonald joined Public Service Company of New Hampshire in August of
- 1983 as Radiological' Assessment Manager with the responsibility for j i
implementation of the Seabrook Station Radiological Emergency Plan. '
Mr. MacDonald is a national and New England chapter member of the Health
-Physics Society and is certified in the field of health physics by the American Board of Health Physics.
1
, 30 13A-7
4 SB 1 & 2 ' Amendment !
FSAR March 1986 JEFFREY J. WARNOCK NUCLEAR OUALITY MANAGER-EXPERIENCE i
-Public Service Company of New Hampshire 1 Nuclear Quality Manager (10/84 to present)
Manage activities verifying that the operation, maintenance and operational
~
support activities of Seabrook Station are performed in accordance with applicable quality standards. Serve as Chairman for the corporate safety ;
t review committee.
t Operational Quality Assurance Department : Supervisor (3/83 to .10/84)
. Develop the on-site operational Quality Assurance program. Responsible for the implementation and evaluationLof inspections, surveillances, audits, examinations and tests in response to regulatory and Quality Assurance requirements.
' American Electric Power Service Corporation (9/78 to 3/83)
Manager, Radiological Support .
._su.-u., Managed matters pertaining to emergency planning, radiological environmental matters, off-site dose assessment methods, ALARA program, meteorology,
)
~
radiochemistry, decommissioning, radiation monitoring, generic radiation protection and health physics in support of the D.C. Cook Nuclear. Plant.
Senior Engineer, Nuclear Materials and Fuel Management' Prepared and administered contracts pertaining to the procurement and
. fabrication of uranium ore, conversion, enrichment and fabrication of fuel assemblies. Prepared. nuclear fuel reload specifications.and negotiated fuel
. contracts. .
Public Service Electric and Cas 'Co., NJ (1/73 to 9/78)
Senior Performance Supvervisor Exercise management control and direction of all work associated with the operation and maintenance of power plant instrumentation and control systems, feedwater and waste treatment systems, equipment performance 1 tests, performance monitoring reports and calculations.
Commissioned Officer, U. S. Navy (9/68 to 10/72)
General Dynamics Corporation (7/65 to 7/68)
Nuclear Project Engineer j;
Prepared and developed. electrical and mechanical systems for reactor plant equipment.. Performed study projects for prototype and. new construction concepts. . Reviewed vendor and contractor plans and specifications.
p EDUCATION Master of Business Administration, Rutgers University, 1976.
o
. Bachelor of Science in Electrical Engineering, Manhatten College, 1965.
Craduate courses in Radiation Science, Rutgers University.
Craduate courses in Electrical Engineering, Northeastern University.
4 13A-8
.1 w - ,,w. , _ , , , , , - ...m. .,___.m . ,.~..,__.m. . - , . , - - , _ . . - . . _ - , _,_.__,,..m_ , , . ,, -.
SB 1 & 2 Amendment FSAR March 1986 WALTER R. STURGEON, JR.
NUCLEAR SERVICES MANAGER Mr. Sturgeon received his Bachelor of Engineering Degree fron Yale
. University in 1963, and his Master of Business Adninistration Degree from the University of Rhode Island in 1971. Fe holds a Professicnal Engineer License in Nuclear Engineering from the State of California and a Senior Reactor Operator License for Seabrook Station Unit 1.
In 1963 he .ioined General Dynanics/ Electric Moat Division as a Senior Test Engineer. He was appointed Refueling Director in 1965, with resoonsi-bility for directing all reactor disassembly, fuel exchange and reactor reassenhly. Mr. Sturgeon subsequently served as Foreign Advisor to Rolls Royce and Associates, coordinating CD/ER activities to supply procedures, equipment and advise on refueling a PWR.
e In 1966 he was appointed Chief Refueling Engineer, and in 1971 Chief
- e. Contract Change Negotiator with responsibility for negotiation and ad.judication of all new construction and design contract changes. He became -
Nuclear Ship Manager in 1972.
Mr. Sturgeon joined Public Service Company of New Hampshire as la Nuclear Engineer in 1975 and was pronoted to Station Manager in 1977. In this capacity"h'e was responsible for planning, recruiting a'nd s'taffing Se'abrook
~
Station; development of a training program; and development of an overall management plan for the station.
In 1982 he was appointed Nuclear Services Manager with responsibility for direct support of Seabrook Station in the areas of licensing, health physics, and operations. -
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0 13A-9
l SB 1 & 2 Amendment FSAR March 1986 WARREN J. HALL OPERATIONAL SERVICES SUPERVISOR
~
Mr. Hall received his Associate Degree in Electronic Engineering Technology from Caston Technical Institute in 1966 and his Bachelor of Science Degree in Electrical Engineering from the University of Virginia .in 1972.
Upon graduation from the University of Virginia, he was employed by Bechtel Power Corporation in Gaithersburg, Maryland as a Control Systems Engineer. In this capacity she vas involved with the engineering and design of instrumen-tation and control systems for both pressurized and boiling water reactors.
In 1973 he was appointed Senior Control Systems Engineer and made Assistant Group LSupervisor on ~ a 900 megawatt pressurized water reactor project.
In- July of .1974, Mr. Hall joined Carolina Power and Light Company as n Senior Electri, cal . Engineer. He was responsible for the review of electrical and instrumentation and control designs for a Ceneral Electric boiling water !
reactor and a Westinghouse pressurized water reactor. He also participated in t the startup/ testing of arboiling-water reactor. -
In January of 1977, Mr. Hall joined Consumers Power Company as a Senior Engineering Supervisor with responsibility for complete plant modifications, both safety related and non-safety related, at Palisades and Big Rock Point Nuclear Power Plants.
In June of 1980 he was appointed Senior Safety and Licensing Engineer,
~
assigned"co the Midland Nuclear. Plant. In this capacity he had project management responsibility for' development of licensing criteria for Emergency
. Operating Procedures, Emergency Operations Facilities, Safety Par'amet'er Display System, Appendix R, Operating Experience Review, and other NUREG-0737 items.
Mr. Hall was a member of the Babcock and Wilcox Owners Group Operator Support Subcommittee and served 'as Chairman 'of - the Subcommittee in 1981 - 1982. He was a founding member of an industry owners group that was set up and worked with INFO and developed the Verification and. Validation Guidelines and Writers e Guide Guidelines for Emergency Operating Procedures.
In March of 1983 Mr. Hall joined Public Service Company of New Hampshire as a Senior Operations Engineer. He was primarily responsible for development of
- plant technical specifications for Seabrook Station and other licensing and regulatory issues..
In October of 1984 he was appointed to his present position of Operational !
Services Supervisor. In this capacity he is responsible for coordinating the nuclear licensing activities for Seabrook Station between the Station Staff and Yankee Nuclear Services Division during the operating license review, development of licensing and administrative procedures to provide operations
. and licensing support for the commercial operation of Seabrook Station and for development and coordination of industry interface with Corporate and Station i Staffs.
SB 1 & 2 Amendment ,
FSAR March 1986 [
RESUME: John P. Cady, Jr.
SUMMARY
OF QUALIFICATIONS:
Registered Professional Engineer, nuclear engineering, and active in conventional, diesel and nuclear power plant construction, testing, operation, maintenance, repair and refueling since 1951. Experience includes both liquid sodium and pressurized water nuclear plants. Assignments covered all aspects from equipment operator, through supervisor of operating crews and m Intenance personnel, to chief engineer responsible for whole nuclear and conventional power plants, and as Com=anding c Officer of two nuclear powered submarines. As Project Manager for an Architect-Engineering firm, was responsible for design and engineering of a PWR nuclear plant.
EXPERIENCE:
1980 PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE to Present Independent Safety Engineering Group (ISEG) Supervisor (since February, 1984):
Provides engineering review and assessment of nuclear safety related
~ .,-r ,- 4-< < --- - operations from a position independent'of' station staff.
p ~ Compliance Manager (April, 1980 to January, 1984):
-. Perfor=ed verification and evaluation of Station activities related to nuclear safety.
. 1974 BURNS AND ROE, INC. (ARCHITECT-ENGINEERING FIRM) to -
1978 ~ Project Manager (1975 to 1978):
Responsible for the direction and coordination of' engineering and design
~
~ ~ ~ ' ' -
--for a 960-MW pressurized water nuclear reactor plant project.
Manager, Logistic Support (1974 to 1975):
Established, organized and put into operation, for the first time in this company,'the Logistic Support Group and developed a Scandard Logistic Support Program.
1973 CONSOLIDATED EDISON COMPANY to 1974 Planning Engineer:
Provided long range and budget year. planning and scheduling to support fiscal requests and expenditures for two commercial nuclear power plants.
1950 UNITED STATES NAVY. ;
to .
1972 Career assignments that included extensive nuclear power, engineering and management experience.
EDUCATION:
1950 B.S. (Electrical) Engineering, U.S. Naval Academy.
1963 Post graduate studies in Nuclear Reactor Safeguards, AEC.
1967 Post graduate studies in Industrial Management, ICAF.
I
_ _ - . - - -. _ . _ _ 13 A_-I1.. __ - - _ - - - - - - _
-)
SB 1 & 2 Amendment FSAR March 1986 TRAINING CENTER MANAGER Resume Peter'M. Rich ~ardson Summary of Qualifications Mr. Richardson has twenty years of nuclear power plant experience. Prior to his present position as Training Center Manager of the Seabrook Training Center, Mr. Richardson was employed by Northeast Nuclear Energy Company working in the areas of Operations, Startup and Training at Millstone Poipt. Mr. Richardson presently holds a senior operator's license for Seabrook Station and previously held a senior operator's license for the Millstone Point facility.
Excerience 1978 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Training Center Manager
.: : : r- rf e . Responsible for all training facility, operator training
., m, . . . programs and simulator support activities at the Seabrook Training Center.
Assistant Training Center Manager / Training Supervisor Develops, revises and supervises the Training programs provided by the Training Center. - Supervisory responsi-
~
bilities for all instructor department activities. In addition, performs special projects as assigned by the Training Center Manager. Previous position held as Senior
.. _ Instructor.
1971 to Millstone Point Company 1978 Training Coordinator Conducted license operator replacement and requalification program for Millstone Unit 2.
~
Supervisory Control Room 0perator In training with collateral responsibility as a liaison between Bechtel startup and Millstone organization to transfer, test and accept system jurisdiction. Participated in writing operating, emergency and surveillance procedures.
Also performed duties as Se ior Control Room Operator during hot functionals, fuel loading, power ascension testing and commercial operation. Previous positions as Control Room Operator and Plant Equipment Operator.
Education / Bachelor of Professional Studies (BPS) - Training Military Management - Memphis State University, 1983 Experience -
U. S. Navy - Served as First Class Machinist Mate on SSN.
Total Service Time: 7 years (1964-1971) 13B-1
SB 1 & 2 Amendment FSAR March 1986 TRAINING SUPERVISOR
- Resume Robert J. Hanley Summary of Qualifications Mr. Hanley has a combination of twelve years experience in the nuclear field in Operations positions and as a simulator instructor. Prior to his present position as Training Supervisor of the Seabrook Training Center, Mr. Hanley was p employed by Combustion Engineering as a Simulator Instructor and by Maine Yankee Atomic Power Company in the area of-Operations. 'Mr. Hanley held a senior operator's license for the Maine Yankee facility. <
Experience 3/83 to 'New Hampshire Yankee - Division of Public Service of New Present Hampshire Training Supervisor
.. ? e. . .
. . . . - - - Responsible for all facets of operator training including Shift Technical Advisor, Auxiliary Operator, Licensed
. Operator Requalification, and Hot License Program develop-ment. Supervisory responsibilities for all instructor department activities.
Senior Simulator Instructor .
Responsible for developing and teaching classes for the initial license class at Seabrook Station. ~
6/81 to Combustion Engineering Inc.
2/83 Simulator Instructor Instructed cold license, hot license, and requalification candidates on simulator and in classroom.
5/73 to Maine Yankee Atomic Power Company 6/81 Shift Operating Supervisor Supervised the shif t crew as well as writing tagging orders, signing work requests, and authorizing radiation work ,
permits. Previous positions as Supervisory Control Room i Operator, Control Room Operator, and Auxiliary Operator.
Held an SRO license and previous RO license (R0 in 1976; SRO in 1981).
Education B. S. in Marine Engineering, Maine Maritime Academy, 1973 138-2
SB 1 & 2 Amendment FSAR March 1986 SENIOR SIMULATOR INSTRUCTOR Resume Laurits S. Carlsen Summary of Qualifications Mr. Carlsen has a combination of fourteen years experience in the nuclear field in Operations positions and as a simulator instructor. Prior to his present position as a Senior c Simulator Instructor of the Seabrook Training Center, g Mr. Carlsen was employed as a Simulator Instructor at Combustion Engineering. Mr. Carlsen previously held an SRO license in Sweden which is the equivalent to the SRO license issued by the NRC.
Experience 8/82 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Senior Simulator Instructor Responsible for developing and' teaching classes for the
~
initial license class at Seabrook Station.
10/80 to Combustion Engineering 7/82 Simulator Instructor -
~
Instructed cold license, hot license, and requalification candidates on simulator and-in~ classroom. SRO certified at
. Combustion Engineering.
8/71 to Swedish State Power Board, Vasteras and SSPS Ringhals 9/80 Senior Operator / Supervisory Control Room Operator' Qualified watch operator on boiler, turbine and feedwater station. Performed functions as supervisory control room
~
operator. Previous position as Auxiliary Operator. Held a l Swedish SRO equivalent license. l Education Zimmermanska Gymnasiet, Vasteras, Sweden - Obtained equivalent of an associates degree.
School for Lifelong Learning - University of New Hampshire New Hampshire College and University of Hartford - Additional .
credit hours. .
e 13B-3 u
. - - - _ .. _ . _. . ~ . - ..
SB 1 & 2 Anendment FSAR March 1986 !
SIMULATOR INSTRUCTOR Resume Steven W. Kessinger Summary of Mr. Kessinger has worked at the Seabrook Training Center Qualifications for two years. Prior to his present position as Simulator Instructor, Mr. Kessinger was employed by Westinghouse Nuclear Training Center as a Senior Instructor / Assistant Senior Instructor, and Training Engineer. Mr. Kessinger was certified at Westinghouse as an SRO Simulator Instructor.
Experience 8/83.to New Hampshire Yankee - Division of Public Service of New Present Hampshire Simulator Instructor Responsible for developing and teaching classes for the initial license class at Seabrook Station.
4 1/81 to Westinghouse Nuclear Training Center 7/83 Senior Instructor / Assistant Senior Instructor i
Conducted and/or directly supervised licensed operator
~
requalification programs.for Connecticut Yankee, D. C. Cook, and Trojan Nuclear Power Stations.
Training Engineer Conducted cold license simulator training for candidates from Wolf Creek Nuclear Generating Station (KG&E).and Byron '
Station (CWE).
4 .
Education / Bachelor of Science in Occupational Educatio'n with one year -
Military of advanced Math and Physics - South Illinois University Experience ,
. U. S. Navy - Served as First Class Machinist Mate. Total Service Time: 8 years (1972-1980) i' I 4
)
W 13B-4
SB 1 & 2 Amendment FSAR March 1986 SIMULATOR INSTRUCTOR Resume Tim M. Jenkins Summary of Qualifications- Mr. Jenkins has worked at the Seabrook Training Center for one and a half years. Prior to his present position as Simulator Instructor, Mr. Jenkins was employed by Westinghouse Nuclear Training Center as a Project Engineer, Senior Phase II Instructor, and Training Engineer.
Mr. Jenkins was certified at Westinghouse as an SRO Simulator Instructor.
Experience 2/84 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Simulator Instructor Responsible for developing and teaching classes for the
' initial license class at Seabrook Station.
5/80 to Westinghouse Nuclear Training Center 2/84 y Project Engineer .
Coordinated the redevelopment of Fundamentals materials for A.C.E. accreditation. This included editing and coordination of graphic arts, authors, technical editors and clerical staff.
o Senior Phase II Instructor Conducted and/or supervised classroom lessons on system design and operations for a number of utilities. Other duties included scheduling instructors and preparing a schedule of lessons.
Training Engineer Conducted cold license systems and simulator training for Callaway Nuclear Generating Station (UE) and Byron Nuclear Generating Station.
Education / Southern Illinois University - Enrolled in Bachelor of Military Science Degree Program majoring in Occupational Education Experience (117 credit hours - one remaining course to obtain BS)
U. S. Navy - Served as First-Class Machinist Mate on SSBN.
Total Service Time: 6 years -(1972-1978) 13B-5
SB 1 & 2 Amendment FSAR March 1986 SIMULATOR INSTRUCTOR Resume Douglas R. Tilton Summary of Qualifications Mr. Tilton recently joined the Training Center as a Simulator Instructor. Prior to his present position, Mr. Tilton was employed by Public Service Electric and Gas Company as a Licensed teactor Operator at the Salem Nuclear Power Plant Units I and II.
Experience 6/85 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Simulator Instructor Responsible for developing and teaching classes for the initial license class at Seabrook Station.
10/81 to Public Service Electric and Gas Company 6/85 Licensed Reactor Operator Manipulated all controls at the Salem Nuclear Power-Plant Units I & II. Conducted plant startups, shutdowns, and
~
testing. Responsible to oversee the safe operation of each unit while at power, during casualties, and ~while shutdown.
Directed fifteen non-licensed personnel in their duties as equipment operators. Involved in rewriting and testing Salem's emergency operating procedures on an in-house simulator. Participated in four refueling outages, including two electric generator replacements.
Education / Bachelor of Science Degree in Nuclear Industry Operations Military Thomas A. Edison State College - June 1985 Experience U. S. Navy - Served as Machinist Mate Fir'st Class on USS Texas. Total Service Time: 6 years (1975-1981) t
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138-6
I SB 1 & 2 Amendment FSAR March 1986 i >
SENIOR PROGRAM INSTRUCIOR 4
Resume Thomas F. Crew Summary of Qualifications Mr. Crew has worke.d at the Seabrook Training Center for over four years. Prior to his present position as Senior Program Instructor, Mr. Grew was employed by Manchester High School Central as a Physics and Physical Science Teacher. .He held a e Secondary Education Certificate with New Hampshire andc
! Massachusetts. Mr. Crew presently holds a senior operator's
. license for Seabrook Station.
Experience 6/81 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Senior Program Instructor / Program Instructor
~
- s. ~ .. Designs, develops, presents, documents and revises assigned License Training modules and procedures in accordance with Training Center objectives and regulatory requirements.
Responsibilities included developing and teaching portions of our Nuclear Reactors Fundamentals (NRF), Shift Technical 4 Advisor (SIA), and Detailed Systems programs.
1971 to - Manchester High School Central 6/81 -
Physics and Physical Science Teacher -
New Hampshire Vocational-Technical College Assistant Professor, Department of Math & Science 4
(1979 - 6/81 Part-time Assistant Professor)
Education /
Certification Master of Science Degree (Physics) - Northeastern University -
, 1979 i
Bachelor of Science Degree (Physics) - Lowell Technological
. Institute /Lowell University - 1971 5 Secondary Education Certificate - N.'H. - 1974 (Physics)
Secondary Education Certificate - Mass. - 1971 (Math and 1 Physics) i i
, l l l 13B-7
. t SB 1 & 2 Amendment
- FSAR March'1986 'I PROGRAM INSTRUCTOR <
i i-i Resume . William H. Smith i Summary of Qualifications Mr. Smith has three years experience in the position of Program Instructor at the Seabrook Training Center. ;
a Mr. Smith has had previous experience as an Environmental Scientist -and as a Plant l Operator for a vastewater treatment
- facility. Mr. Smith has previously hgid a Secondary Education Certification in Massachusetts for Science in 1975.
- ' Experience o
9/82 to New Hampshire Yankee - Division of Public Service of New Present Hampshire-Program Instructor i
I- --e a-o re- --- Designs, develops, presents, documents and revises assigned j -,3,3;., , . .a . .. - License Training modules acd procedures in accordance with
-..- Training Center objectives and regulatory requirements.
4/82 to - Lowell Wastewater Treatment Plant
, 8/82 .
Wastewater Treatment Plant Operator
~
1 Haintain the daily operation of the City of Lowell's wastewater treatment plant. ,
1977 to Environmental Research and' Technology, Inc.
4/82
- Environmental Scientist .
5 Task manager or principal investigator for environmental assessments representing utilities, mining, highways, railroads, industry, and u,rban and rural mixed use develop-ments.
, 1975 to Previous positions held as Installation Security Supervisor 1977 for Burns International Security Services, Inc. and as a Teacher-Earth Sciences for Tewksbury Public School System.
Education M. S. Degree in Resource Management and Administration,
{ Antioch University - 1984 ,
B. S. Degree in Environmental Science - University of Lowell - l 1975 i
I
. 1 j
138-8
- ,__ J
l SB 1 & 2 Amendment FSAR March.1986 PROGRAM INSTRUCTOR Resume Bruce F. Aquizap Summary of Qualifications Mr. Aquizap has worked at Seabrook Station for two years as an Auxiliary Operator and presently at the Training Center as a Program Instructor. Prior to his present position, Mr.
Aquizap retired as a Staff Operations Officer after twenty-four years of service with the U. S. Navy. Seven years of military service was' nuclear related. Mr. Aquizap also has over eight years of teaching experience. Presently holds a New Hampshire Occupational Education Teacher Certification.
Experience 10/83 to New~ Hampshire Yankee - Division of Public Service of New Present Hampshire Program Instructor
. Designs, develops, presents, documents and revises assigned License: Training modules and procedures in accordance with *-
.. f s . r. ~ . . . - Training Center objectives and regulatory requirements.
Auxiliary Operator Operates, maintains, inspects and tests equipnent as directed by Supervisory Control Room operators.
1976 to
- Pinkerton Academy .
10/83 Work Extarience Coordinator / Power Mechanics Instructor
- - - - - - - - - - - - . Implemented a three year sequential Power Mechanics program to provide entry level skills upon graduation. Also imple-mented a program of individualized career counseling for approximately one hundred students placed annually in cooperative work stations. Participated in the planning and building' process fo'r a $2.2 million Vocational Center, uti-lizing objectives provided by local skill craf t committees.
1975 to University of New Hampshir'e 1976 Graduate Project Assistant / Occupational Education Intern Implemented in-service vocational teacher / administrator workshops on placement of special needs students in vocational programs. Coordinated State-wide Youth Leadership Conference. Consultant and panelist to Lifelong Learning Center on " Student Evaluation of Instructors and Promotion of Adult Education". Instructor of Micro Teaching course.
Education Master of Occupational Education - University of New Hampshire Bachelor of General Studies (Management) - University of New Hampshire 13B-9
March 1986 PROGRAM INSTRUCTOR Resume Timothy C. Cassidy Summary of Qualifications Mr. Cassidy recently -joined the Training Center as a Program Instructor. Prior to his present position, Mr. Cassidy.has completed seven years of service with the U. S. Navy. His last position with the Navy was Mobility Department Bran + i Head where he was manager over a staff of instructors.
Experience r 8/85 to New Hampshire Yankee - Division of Public Service of New Present Hampshire Program Instructor Designs, develops, presents, documents and revises assigned License Training modules and procedures in accordance with Training Center objectives and regulatory requirements.
4/.'8 to -
U. S. Navy . -._
4/05 Mobility Department Branch Head Responsible for the management cf six Engie. sering Department instructors including four lead instructors.
~
Engineering Instructor / Lead Instructor Developed, updated, and implemented training ' objectives and '
curriculum content including a complete re-write of all i lessons in the unit area. Instructed classes in the ship's propulsion, auxiliary systems, and management and operations areas. Also conducted state-of-the-art Leadership / Management seminars for graduating junior officers to prepare them for their initial Division Officer assignments.
Held previous positions as' Main Propulsion Assistant and Boilers Division Officer.
' Education / Bachelor of Science in Marine Engineering - Maine Maritime
- Licenses Academy-1978 Master of Marine Affairs (6 credit hours) - University of Rhode Island i
Third Assistant Engineer of steam and motor vessels of l unlimited horsepower license - April 1978
. l l
13B-10 i
SB 1& 2 Amendment FSAR March 1986 e
- Contents Deleted e
SB 1 & 2 Amendment FSAR March 1986 DONALD E. MOODY STATION MANAGER - NEW RAMPSRIRE YANKEE DIVISION OF PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE Mr. Moody attended the University of Maine in Orono, Maine where he received a Bachelor of Science degree in Mechanical Engineering in 1959. Mr.
Moody has twenty-six years experience in Utilities Engineering and Operations, I nineteen years specifically in Nuclear Plant Operations and Engineering.
In 1959, Mr. Moody joined Central Maine Power Company where he entered the Management Development Program. Through the period of 1959 - 1966 he held various technical and administrative positions. Responsible for special reports and studies covering all aspects of the distribution systems of an electric utility.
In 1966 Mr. Moody was reassigned to assist in the preoperational testing
, and: check out of systems, initial core loading and startup testing of the Connecticut Yankee facility. During this time he participated in initial training programs and performed various system checkouts in Operations and Instrumentation and Control, pseticipated in initial preoperational testing and physics testing. Also, during this time period he performed preliminary reviews on Maine Yankee systems.
In 1967 Mr. Moody joined Yankee Atomic Electrte Company as an Engineer.
During this period of time he obtained a Senior Reactor Operator's license at Connecticut Yankee in the fall of 1968.- He also completed the design and' field installation,-including installation of two 2850 kW diesel generators ~~ ~
for the Connecticut Yankee plant. Responsible for design, construction and installation of new diesels LPSI - HPSI systems at Yankee Rowe. Review responsibilities for system designs at Maine Yankee.
In 1971, Mr. Moody joined the Maine Yankee staff, where he held several positions. Responsible for all operator and general plant training, coor-dination of NRC inspections and preparation of correspondence with the NRC and special/ technical studies. Mr. Moody received a Senior Reactor Operator's license for the Maine Yankee facility in 1972. He was appointed Plant Superintendent in 1974. Responsible for operation, maintenance and engineering at the Maine Yankee facility.
~
In 1977 he joined Yankee Atomic Electric Company as Manager of Operations.
Responsible for all facets of nuclear operations and maintenance at Yankee Nuclear Plant facility located in Rowe, Massachusetts. Also responsible for providing operational support to Vermont Yankee and Maine Yankee facilities.
In 1982 Mr. Moody joined Public Service Company of New Hampshire and was appointed to the position of Station Manager. Responsible for all operational aspects of the Seabrook Station facility. .
)
f SB 1 & 2 Amendment FSAR March 1986 WILLIAM A. DIPROFIO ASSISTA.Vr STATION MANAGER - NEW HAMPSHIRE YANKEE DIVISION OF PUBLIC SERVICE COMPANY OF NEW RAMPSHIRE Mr. DiProfio attended the University of Massachusetts for one year, -trans-ferred to the U.S. Naval Academy in Annapolis, Maryland and received a Bachelor of Science Degree in Engineering in 1965. He completed Ghis MBA at the University of New Hampshire in 1976.
From 1965 to 1971 Mr. DiProfio was an officer in the U.S. Navy. uAs a participant in the Navy's nuclear power program, he had various assignments involving supervision of the operation and maintenance of submarine nuclear plants both at sea and in the shipyard. Mr. DiProfio served as a lead instructor at one of the Navy's land based prototypes before being discharged from the Navy with the rank of lieutenant.
From 1971 to 1978 Mr. DiProfio worked as an engineer and manager in the
- PSNH fossil production division. He performed design and supervised the installation of several projects before being assigned as Assistant Station Manager at PSNH's 400 MW oil fired generating. station. In that position he hired and trained the staff, performed the startup and initial operation of the station and managed several outages.
In 1978 Mr. DiProfio was assigned as Assistant- Station Manager at Seabrook. He worked at Maine Yankee during the 1979 refueling outage and subsequent startup and in-the-Westboro, Massachusetts offices of Yankee
Nuclear Services Division for 18 months under the direction of the Manager of Operations. During this time he was responsible for development of the initial staffing and training plans for the station and their implementation.
He supervised the initial development phases of station programs for maintenance, operations and procurement. He presently is responsible for the station budget, non-licensed training program and planning and scheduling for the station. .
Mr. DiProfio holds a Senior Reactor Operator's License for Seabrook.
t I
13D-2 )
)
SB 1 & 2 Amendment FSAR March 1986 RESUME: James T. Tuberty
SUMMARY
OF c OUALIF1 CATIONS: Thirty-five years of management and staf f experience.
Experience in planning, organizidg, budgeting, training, and managing all services to support major military organizations. Three years experience as the Adminis-
, trative Services Manager for a large nuclear power station
.." .} under construction. Qualified by responsible positions in the fields of personnel and financial management, administration and training.
EXPERIENCE :
Mar 1978 '.
to present Administrative Services Manager for the Public Service Company of New Hampshire's Seabrook Nuclear Power Station.
Responsible to the Station Superintendent for the security, fire protection and safety, stores, documents control, station services, and general station administration.
. Coordinates the personnel, payroll, and hiring practices
( vith the corporate organization.
' ~
Apr 1975'to - --
Mar 1978 Senior Management Analyst for the Governor's Commission on Crime and Delinquency in the State of New Hampshire.
Performed responsible professional duties of an adminis-trative, analytical nature which entailed the formulation, refinement, and implementation of management and related systems. Performed analyses of management methods and procedures, data collection, formating, organization, costs and equipment to insure effective operations.
May 1974 to Jul 1975 Commander of a 1,200 personnel base operations organization consisting of four major directorates, Facilities.
Engineers, Personnel and Community Affairs, Industrial Operations, and Resource Management. Simultaneously, functioned as the Assistant Division Commander of an Armored Division with the responsibility for organizing and directing the training and maintenance for over 15,000 personnel and 5,000 pieces of heavy equipment. Also functioned as the District Commissioner of the largest Boy Scout district in Europe. -
SB 1 & 2 Amendment FSAR Harch 1986 Page 2 Oct 1973 to May 1974. Developed the detailed plans and managed the implementation phase of the complete reorganization of eight large mili-tary communities. The combined population was 180,000 and the capital budgets involved totaled over $170 million.
Concurrently, administrator of one of the communities in-volved that covered 21,000 square miles and contained in excess of 25,000 people. Responsible for the development and control of an annual budget of $25 million. Planned, operated and budgeted the complete activities of the com-munity to includdPaaintenance and engineering services, family housing, police and fire protection, educational facilities, medical and dental services, the recreational services and the retail. food and clothing outlets.
Feb 1972 to Sep 1973 Commanded an armored brigade of over 4,000 personnel engaged in performing maintenance, transportation, housing food service and training functions. As the manager and administrator, extensive community relations and negotia-tions were' conducted directly with high officials of foreign governmentr on sensitive subjects with interna-tional implication.1. -
Feb 1970 to Jan 1972 Department Director at the U.S. Army's Senior Tactical College. Responsible for graduate level instruction
- presented to a multi-national study body of 1,200. Manager
, of a highly professional staff of eighteen, with the
-- concurrent responsibility of teaching graduate cours,e,s.
Jan 1969 to Jan 1970 Senior Advisor to a foreign organization of 15,000 personnel. Controlled the development of specific opera-tional, administrative, and logistical plans fo'r implemen-tation within the foreign society. Responsible for the entire resource allocation and utilization of U.S. Covern-ment property and forces within a large geographical region.
Jul 1967 to Dec 1968 Administrative Assistant to the Director of Doctrine and
, Systems on the Department of the Army Staff. Developed U.S. Army positions relative to joint Atmy, Navy and Air Force doctrine. Extensive personal contact with Department of Defense officials and civilian defense contractors.
Also, principal advisor to the Army Chief of Staff on intratheater transportation matters.
EDUCATION: BGE in Military Science and Education, University of Omaha',
1961. . U.S. Army War College, International Relations ,
1967. U.S. Army Command and General Staff College, 1960.
Computer Science and Applications course, 1971. Financial Management at Executive Level course,1973.
130-4 l
7 l
SB 1 & 2 Amendment FSAR March 1986 c.
_ RESUME: Raymond E. Cyr POSITION: Maintenance Manager SUXHARY OF QUALIFICATIONS: Twenty two years experience in the nuclear field. Experience includes construction, pre-operational testing, start-up and maintenance of two nuclear plants.
r EXPERIENCE:
December 1978 Public Service Company of New Haepshire, Seabrook Station to Job
Title:
Maintenance Manager, 1982 to present.
Present Responsibilities: responsible for all activities of the electrical and mechanical Maintenance Department, I&C Department, Logistics Group, and the Radioactive Waste and Utilities Group.- .
Job
Title:
Maintenance Department Supervisor,1979 to 1982.
Responsibilities: responsible for the initial staffing of the Maintenance Department, developing of surveillance re procedures, preventive and corrective programs and procedures for all mechanical / electrical systems and equipment, identification of spare parts for all mechsnical and electrical equipment, and assisting the Training Manager in
- developing a training program for all Maintenance personnel.
December 1969 Maine Yankee Atomic Company, Wiseasset, Maine to Job
Title:
Senior Maintenance Supervisor, January 1975 to December 1978 December 1978 -
1 Responsibilities: supervisory responsibilities for all preventive and correctiv~e maintenance activities for all mechanical and electrical equipment and systems. Coordinated all outside mechanical and electrical contractors.
Developed, planned, implemented and supervised the preventive !
maintenance program, maintenance procedures, and spare parts program. Developed a training program for mechanical and electrical craftsmen. ,
Job
Title:
Maintenance Foreman, December 1970 to December 19)3.
t Responsibilities: planned, scheduled and supervised a daily work assignment program for all maintenance personnel.
l SB 1 & 2 Amendment FSAR March 1986 Raymond E. Cyr !
Page 2 EXPERIENCE (CON'T):
Maine Yankee Atomic Company, Wiscasset, Maine During plant construction, supervised mechanical and c electrical maintenance personnel in performing daily quality c assurance inspections during initial installation and testing of plant mechanical and electrical equipment and systems.
Welding Supervisor performing initial' procedure and welder performance qualifications. Developed and implemented maintenance surveillance and equipment calibration program.
Provided administrative and specialized assistance to the Maintenance Department Head in the development of departmental programs. Supervised the preparation of reports, logs and historical data. Evaluated the performance of mechanical and electrical maintenance personnel and 2-----
provided recommendations relative to hiring, firing, promotion and other actions affecting personnel.
Yankee Atomic Electric Company, Westboro, Massachusetts Job
Title:
Quality Assurance Representative, 1969 to 1970.
1 -
Temporary assignment during eahly Maine Yankee construction.
~
Responsibilities: reviewed and commented on' vendor and Maine Yankee architectural engineers non-destructive test procedures, engineering specifications and drawings.
Traveled to vendor facilities and Maine Yankee Plant site to appraise and review manufacturing and construction processes for both mechanical and electrical equipment and systems to assure contractual adherence to applicable procedures, specifications and codes. Performed necessary audits.
l l
Accompanied.NRC inspectors during plant site inspections.
August 1965 Combustion Engineering, Inc., Windsor, Connecticut
! to Job
Title:
Vendor Quality Control Representative l - November 1969 Responsibilities: reviewed and commented on vendor non- ,
l destructive test procedures, engineering specifications and drawings for both mechanical and electrical equipment.
- Assisting Engineering in establishing acceptance criteria and quality level requirements for vendors. Provided technical assistance regarding quality problems and coordinated with vendor personnel to assure the establishment and proliferation of good vendor relationship. Had a thorough knowledge of ANSI,- ASME, ASTM, and Power Piping Codes. Had a working knowledge of -IEEE and NEMA Standards.
Accompanied NRC inspector during audits of C.E. vendors.
SB 1 & 2 Amendment i~
Raymond E.S Cyr /
Page 3 EXPERIENCE (CON'T):
Combustion Engineering, Inc. , Windsor, Connecticut Required to travel to vendors' facilities to appraise and review manufacturing processes. Witnessed dimensional, non-destructive, operational and functional tests and inspections of both mechanical and electrical equipment to assure i
contractual adherence to applicable proceducts, r specifications and codes. Performed vendor surveillance and audits. Generated and prepared executive reports on results of inspections and audits.
Job
Title:
Erection Superintendent
. Responsibilities: traveled to customers' facilities for the repair of power plant boilers.. Conferred with customer and union representatives to discuss the job, manpower require-ments, safety and medical arrangements and other special requirements.- Hired. personnel, established a payroll, and obtained necessary tools and equipment. Qualified welders to ASME code and performed necessary non-destructive test of weldments. Established and maintained progress reports.
3 Job
Title:
Leadman Welder - Naval Reactors Division
- Responsibilities: responsible for the general function and supervision of the veld shop plus any velding performed on the submarine prototype. Qualified welders (Navy) to MIL-STD-250-1500-1. Maintained qualifications as an "A" welder.
November 1964 Fratt and Whitney Aircra'f t, East Hartford, Connecticut to Job
Title:
Welder - Experimental Department August 1965 .
Responsibilities: Performed heliare and electric are welding of jet engines'in test stands.
November 1960 Combustion Engineering, Inc. - Naval Reactors Division, tu Windsor, Connecticut
-November 1964 Job
Title:
Welder "A"
. t Responsibilities: performed general silver soldering, electric arc, heliarc, and braze welding of various metals to conform to rigid military specification pertinent to nuclear reactors. All weldments were subject to magnetic particle and/or liquid penetrant test and radiographic inspections.
Qualified on automatic seal welding machine and a multitude of machine shop equipment. -
13D-7 8
SB 1 & 2 Amendment FSAR March 1986 Raymond E. Cyr Page 4 EXPERIENCE (CON'T):
February 1960 Pratt and Whitney Aircraft, East Hartford, Connecticut to Job
Title:
Production Line Welder November 1960 Responsibilities: performed production line heliare and electric arc welding on jet engine parts. Also used the dry box method of heliarc welding of titanium.
1959 Wooster Express, Hartford, Connecticut to Job
Title:
Truck Driver 1960 Responsibilities: local shipments in the Hartford-Springfield area.
1955 to 1959 United States Navy - '
EDUCATION:
Associates Degree in General Studies Presently enrolled in BS degree program with the University of NH Advanced ~ Technical Training:
- 1. Three (3) months TIG & MMA Welding School, USN - Portsmouth, Va. 1956
- 2. One (1) month TIG Welding School, Experimental Test Dept., P&W Aircraft, E. Hartford, Conn. (1959)
- 3. Three (3) months advanced welding school (TIG, MMA, Auto-Weld) to NAV-SHIP-250-1500-1 at Combustion Engineering, Windsor, Conn. (1960)
- 5. One (1) week Ultra-Sonic Test School at Automation Industries, Danbury, Conn. (1969) ,
- 6. One (1) week Diesel Engine School, Electromotive Division, General Motors Corp., Chicago, Ill. (1973)
- 7. Forty (40) hour course on Air Conditioning and Refrigeration, Central Maine Vocational Technical Institute, Auburn, Maine (1974) 13D-8
SH 1 & 2 Amendnent FSAR March 1986 J
Raymond E. Cyr - Resume Page 5 1
A. Forty _(40).bour course on Electrical Equipment Testing and Maintenance at j George Washington University, Washington, D.C. (October lo79)'
- 9. One (1) week course on Turbine overhaul at Wheaton College, Chester, Pa.
(Feb. 1975)
- 10. One (1) week Mayagenent and Labor Relations training at Rutgers University, Brunswick,' N.J. (May, 1978) e
- 11. Two (2) day training on Grievances and Arbitration at Cornell University, New York City (Oct. 1979)
- 12. TVo (2)- day course on IRD Mechanaysis ' Vibration Analysis -Eauipment at the University of Maine, Portland, ME.(September 1978)
- 13. Forty-five (45) hour course in Advanced First Aid and Emergency- Care (March 1976) -
.14..Ninety-{90) hour course and qualified as an Emergency Medical Technician (Licensed Ambulance Attendant), (May 1976)
'15. Tuency (20) hour refresher course to maintain Emergency Medical Technicians Oualifications (November 1978)
- 16. Thirty-two (32) hours training in Technical Writing by Eugene Ehrlich of Columbia University sponsored by PSNH (June 1979)
.12.. Forty (40) hours training in Motivation, organizational Climate and -
Managerial Styles by David Burnham (ITC) sponsored by PSNH (1979)
~ 18. Forty (40) hour Kepner-Tregoe course in Decision Making and Problem 4
Analysis, sponsored by PSNH (January 1980)
- 19. Two (2) day seninar on Mechanical Seals by. Chesterton Co'ro. at the Holiday Inn, Wohurn, Mass. (October 1980)
- 20. One (1) day workshop on Interviewing Techniques at the University of New Hampshire, Durhan NH (October 1980)
- 21. Two (2) day training on Visual Inspection in accordance with SNT-TC-1A by
- . YAEC at Seabrook Station (July 1980)
- 22. Sixteen '(16) hours ' Introductory to Electrohydraulic , Controls - by CE at Seabrook Station, December 8 and 9, 1981.
[
e l 11n-9 1
-, .- . , . . . . - - - -~
SB 1 & 2 FSAR RESQlE OF QUALIFICATIONS LAURE!!CE A. MAI.SH (
, , . _ _ . . . . . . . . . ~ .
r Have worked in the nuclear field since early 1961. Previous job hgld covered the full range of operations. With t.c commercial and one Navy nev construction plants behind me, Seabrook construction is no stranger. Will complete training necessary to hold any management position in a Nuclear Co= plex.
POSITION Operations Manager EDUCATION .
St. Thomas Grs==ar Graduated 1.955 Sacred Heart High School Graduated 1959 Navy Schools:
Basic Electronics and Electricity School Intercom =unication Technicians School Submarine School Nuclear Power Training School
(
~
Oxygen Generator Operations & Maintenance "
-"' P
- H2 ' Analyzer Operations & Maintenance
.. ... Vibration Analysis . .
Motion Projection Operation & Maintenance Connecticut Yankee Startup Training Course Central Maine Vocational Institute Instructor Training Maine Yankee Startup Training Course Central Maine Vocational Institute Technical Uriting American Management Association Com=unications Course Psychology 401 University of lev Hampshire Four credit hours Mathematics 1211 Memphis State University Three credit hours Physics 2511 Memphis State University Four credit hours Physics 25L2 Memphis State University Four credit hours Nuclear Physics Memphis State University Phys. 4110 Three credit hours
- Re'accor Physics Memphis State University Phys. 4220 Three credit hours Ins trumentation Memphis State University Tech. 7411 Three credit hours Chenistry Memphis Scace University Chem. 1010 Three c'redit hours Radiation Protection Memphis State University Biol. 4080 Three credit hours Calculus I Memphis State University Math 1321 Four credit hours Calculus II Memphis State University Math 2321 Four credit hours
~
Additionally, Memphis State University has been contracted for an add t-tional 51 credit hours of Shif t Technical Adviso'r courses. k Management training - PS 4H 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />
. SB 1 & 2 FSAR L. A. VALSM - RESCME
. - Page Two j
EXPERIENCE _
Worked in shipping, receiving, display and advertising for 1956 to 1958 (Grive, Eisset'& Holland, Waterbury, local department store.
Marked in an eyelet manuf acturing shEp as a machine (Weoperator s tbury 1953 to 1959 and started an apprentice' program for tool making.
Mfg. Co. , Waterbury, Connecticut)
Af ter completion of service schools associated with ny rate, 1959 to 1961 served aboard USS Sea Owl (SS408) for approxim months. d tenance of all communications systems, electronic compasses an ,
ships batteries. '
Af ter completing nuclear power training school, " qualified as a Windsor, 1961 to'1962 reactor operator at the SIC tr'aining prototype at (Conbustion Engineering PUR)
Served as a member of the nuclear engineering crew aboard the 1962 to 1964 USS Lafayette (SSBN616) through initial construction, seaAmong oth
}- trials, commissioning and operati,ons. d also
\ -
~ vas also a qualified reactor operator on the 55u plant an filled the duties of the spare parts petty of ficer. - ~-
Was e= ployed by Connecticut Light and Power Company at the 1964 to 1966 While avaiting startup crew assignment at Co Atomic, served as operating assistant.
1966 to 1970 ' a member of the staf f during construction a h local union and
-station. ..Vas elected business agent of t e 81 .
received AEC reactor operating licenses OP-2438 and OP-243 Transferred to Maine Yankee Atonic Power Assisted Company with instruc- to as 1970 to 1978 d initia!
plant acceptance from the NSSS and AE.
tion of prospective licenses holders and formulate
' ?romoted to Assistant
- procedures for plant operations.
Department Head for Plant Operations and: also represented pany as Project Engineer for a backfitted systen While at Maine Yankee, to compleme I
the cooling water outlet dif fuser.
held an NRC Senior Operating License i SOP 1693, SOP 16 SOP 1693-2, the latter being current until August 1978.
Have 1978 Transf erred to Public Service- Company of Ne Have staged the effort for proce-(, , to Present Unit 1 Licensed operators.
~
dure development and am nidway through plant systems design W
SB 1 & 2 Amendment FSAR March 1986 RESUME: Joseph M. Crillo
SUMMARY
OF QUALIFICATIONS: Promoted to Assistant Operations Manager _in April, 1982, after three years as Shift Superintendent for PSNH. This was-preceded by nearly 14 years of nuclear power experience, five as Control Room Operator and three as Auxiliary Operator at Yankee Rowe and six years navy service culminating in duty' as Engihe Room Supervisor of a nuclear submarine power plant.
Responsibilities and duties in addition to normal requirements included active participation in six refuelings as Health Physics Technician, Auxiliary Operator, Control Room Operator and Nuclear Puel Handling Operator.
EXPERIENCE:
April 1982 to Seabrook Station .PSNH Present Assistant Operations Manager Responsible for the' selection, coordination and hiring of Auxiliary Operators, Satisfactorily completed Memphis State University's " Shift Technical Advisors" program. Member of the Joint Test Group which approves procedures and policies used in the Startup Test Program.
June 1979 to Seabrook Station, PSNH -
April 19,82 Shift Superintendent- -
~
Responsible lor the preparation of assigned' operating and Visual Alarm procedures. Participated in establishing the.
Policies and practices of the Operations Department.
Participated in the Acceptance Test of Seabrook's Site-Specific Simulator, which involved an extensive operational exercise and detailed analysis of plant system responses.
April 1974 to -
June 1979 Yankee Atomic Electric Company, Rowe, MA Control Room Operator Controlled all operations relative to the primary and secondary systems of a Pressurized Water Reactor, Nuclear Power Plant. Responsibilities included reactor and steam plant startups and shutdowns, normal and emergency.
operations, electrical switching and tagging.
O 13D-12
SB 1 & 2 Amendment FSAR March 1986 Joseph M. Grillo
- - Page-2 September 1970 Yankee Atomic Electric Company, Rowe, MA to April 1974 Auxiliary Operator Responsible for normal and abnormal operations of the Steam Plant, Radioactive Waste Plant, Water Treatment Plant, with e assignments to the Health Physics Department-requiring radiation and contamination monitoring with decontamination as necessary.
Refuelings: Actively participated in six reactor refuelings at Yankee as: Health Physics Technician, Auxiliary Operator, Control Room Operator and Nuclear Fuel Handling Operator.
Member of Joint Safety Committee for two years. (1972 and 1973)
Vice President-of Independent Nuclear Utility Workers Local
- 1 for one year. (-1974)
September 1964 US Navy to September 1970 Engine Room Supervisor Responsible for the operation and maintenance of the nuclear
. activity, steam propulsion, and electrical generating systems aboard a nuclear submarine. Attained the rank of Machinist Mate First Class (E-6). Qualified as Ships Welder and Ships
. Diver. ,,
EDUCATION AND TRAINING: Presently enrolled in a program with Memphis State University's University College studying for a Bachelor of a
Professional Studies'in Nuclear Industrial Oper'tions.
Associate Degree, Industrial Engineering, Greenfield Community College, 1982.
17 Nuclear Power Basics and Training, Machinist Mate, Nuclear Grade Arc Welding, Scuba 1964 Graduate of Lawrence High School, Lawrence, MA LICENSES: USNRC Senior Reactor Operator Massachusetts Nuclear Power Plant Operating Engineer 13D-13
SB 1.& 2 Amendment-FSAR March 1986-RESUME: Cary J. Kline EXPERIE'NCE :
-1978-Present =Seabrook Station Technical Services Manager Responsible.for technical. support functions for the c ation.
Provides overall direction for the Technical Services Group p Departments which provide technical and engineering activities at the station..
Reactor Engineering Department Supervisor Responsible for the formation and development of the Reactor Engineering Department and all associated functions. Successfully
- ' completed Shif t Technical Advisor Training. Obtained Senior Reactor Operators License on Seabrook Unit 1, March 1985.
.- 1976-1978 Millstone Nuclear ' Power S'tation, Unit'2 Reactor Engineer .
Respons'ibleforalkReactorEngineeringfunctionsonUnit2.
Directed core loading and startup physics testing for first refueling. -Member of Plant Operation Review Committee.
1974-1976 Assistant Reactor Engineer Assisted Reactor Engineer in preparation for initial startup, including fuel receipt and inspection, development of computer programs, and preparation of startup and operational procedures.
Shift coordinator during initial fuel loading and startup physics testing.
1973-1974 Maine Yankee Atomic Power ' Company Member of Reactor and Computer Engineering Department.
Participated in all phases of Reactor Engineering including physics testing, primary and secondary plant performance, computer programming, refueling schedules, and fuel receipt and inspection.
. EDUCATION: B.S. in Nuclear Engineering, Lowell Technological Institute, June 1972. i 4
Senior Reactor Operators License on Nd11s' tone Unit 2, May 1977.
13D-14 a
,j SB'1 & 2 Amendment FSAR March 1986 RESUME: Richard M. Cooney
SUMMARY
OF QUALIFICATIONS: Qualified by 21 years of responsible positions in Nuclear Power Plant Instrumentation and Control.
EXPERIENCE:
9 September 1985 New Hampshire Yankee Maintenance Services Manager to Present Seabrook Station - directing the overall Maintenance Engineering for Mechanical, Electrical, Instrumentation and Control.and Radioactive Waste Disciplines including programmatic controls.
March 1979 to September 1985 Public Service Company of New Hampshire Instrumentation and Control Department Supervisor - Seabrook Station - directing
~--
the establishment of the preventive maintenance, ' calibration and surveillance testing programs ' including initial staffing
~
and outfitting of the Instrumentation and Control Department.
November 1974 to March 1979 . Yankee Atomic Electric Company Technical Assistant f Instrumentation and Control Department - Yankee Rowe.- Acting I&C Supervisor - 1 year. Instructor for I&C portion of the
~
Senior / Reactor Operators course. Member of the Public Speakers Bureau. .-....- . ...
October 1971 to September 1974 USS Daniel Boone, Chief Electronics Technician, qualified as Engineering Officer of the Watch, Engineering Watch Supervisor, Leading Reactor Operator, Engineering Department Training Petty Officer,' Chairman Human Relations Council.
August 1968 to ,
October 1971 Nuclear Power Training Unit, Windsor, CT. Engineering Officer of the Watch Instructor, Leading- Reactor Operation Instructor, Phase Coordinator, Formal Classroom Instructor (Officer and Enlisted), Crew Assistant for Officer Training. Qualified as Engineering Officer of the Watch, Engineering Watch Supervisor, and Reactor Operator.
February 1966 to .
August 1968 USS Sam Rayburn, Leading Reactor Operator. Qualified as Reactor Operator.
October 1964 to February 1966 Nuclear Power Training Unit, West Milton, NY. Reactor Operator Instructor. Qualified as Reactor Operator, Reactor
. Technician.
SB 1 & 2 Amendment FSAR March 1986 Richard M. Cooney Page 2 EDUCATION: 1. B. S. in Computer Science - Franklin Pierce College. 3.81 GPA.
- 2. Various Management Training Courses as offered by Public P Service Company of New Hampshire.
- 3. Westinghouse Pressurized Water Reactor Information !
Course - 3 weeks
- 4. Balance of Plant Information Course - 3 weeks l S. Electronics Technician School, 38 weeks inst,ruction in I electrical and electronic theory and applice, tion on various electronic equipment. Graduated 7./38
- 6. Nuclear Power School, 26 weeks instruction in Math, !
Physics, Nuclear Physics, ' Radiology and Chemical Theory, Metallurgy, Thermodynamics and specialized training in reactor centrol systems. Graduated 2/256
- 7. Nuclear Reactor Prototype training, 26 weeks instruction (12 hrs / day) in practical training related
. to course covered at Nuclear Power School. Trained at
, General Electric pressurized water reactor S3G at .
West Milton, NY. Graduated,2/32 .
- 8. Basic Submarine School 8 weeks instruction in !
hydraulics, compressed gas, air conditioning equipment, diesel generators and other submarine related systems. Graduated 73/180 ,
- 9. Electronic Test Equipment School, 2 weeks instruction in l the operating of various test equipment, digital counters, oscilloscopes,'etc. Graduated 1/10 O
k e
SB 1 & 2 Amendment FSAR March 1986 Richard M. Cooney
- Page 3
- 10. Advanced Test Equipment School, 2 weeks instruction in , I the repair and calibration of above mentioned test equipment. Graduated 1/10
- 11. Basic Digital Fundamentals, 2 weeks instruction in I thefundamentals of Digital Circuitry.c
- 12. Engineering Of ficer of the Watch School, 8 weeks !
instruction in the detailed operation and characteristics of the SIC Pressurized water reactor, Combustion Engineering Windsor, Cr. Graduated 1/30.
Qualified as Engineering Officer of the Watch.
ORGANIZATIONS: 1. MENSA.
- 2. Instrument Society of America.
. . ... . . . . a. Past Chairman, Nuclear Power Plant Instrument Engineers Committee..
- b. Past Member Executive Council Power Industry l Division.
- c. General Review Board Nuclear Power Plant Standards Committee. .
G k
13D-17 .
SB 1 & 2 Amendment FSAR March 1986 RESUNE : Neal A. Wiggin
SUMMARY
OF QUALIFICATIONS: Over 20 years experience as teacher, administrator and educa-tional consultant. Extensive experience in teacher training, including consultant work in New Hampshire State Department of Education and staff training workshops from Ft. Kent, Maine, to Miami, Florida. Principal of both an academic high school and an area vocational center.
EXPERIENCE :
May 1979 Training Manager, Public Service Company of New Hampshire to Hired and trained instructors for non-licensed training,
- Present . -
coordinated management training. Supervised development of training programs.
June 1976 General Agent, American Bankers Life, Miami, Florida to May 1979 -
~
July 1973 Principal, Hopkinton High School, Contoccook, New Hampshire co '
Responsible for curriculum, budget, staff selection, super June 1976 vision and evaluation, guided school successfully through its 10 year evaluation by NEASC. Introduced Citizens' Advisory Committe, Student Advisory Committee, a K-12 career education project, and tutorial program, peer instruction, revision of ninth and tenth grade social s'tudies. English Department revised their entire curriculum. Math added several needed courses. Upgraded fine arts and increased staffing for those areas. Home economics revamped its whole curriculum. Introducted French and German in junior high.
Sept. 1972 consultant, Career Education, New Hampshire State to Department of Education
- June 1973 Provided consultant service to public schools in initiating
. career education programs. Supervised the selection and
- funding of several projects to test the "New Hampshire Guidelines for Career Education". Conducted many staff training programs in values clarification and decision-making. Also served on the Department's Staff Development Team and was Interim Director of EPDA.
13D-18 l
SB 1 & 2 Amendment FSAR March 1986 Sept. 1971 Director, Northern New England Occupational Exploration to June 1972 Project. Took over this position in the 3rd and final year of the project. It was one of the first career education projects in the U.S. Published a newsletter for partici-pants, conducted staff training workshops and managed the final evaluation. Wrote a booklet describing the project.
Booklet edited and printed by the sponsoring organization, New England School Development rouncil.
July 1969 Principal, Contoocook Valley Reg?onal High School, to Peterborough, New Hampshire June 1971 Responsible for administrative details associated with the 9 opening of a new high school, including:a broad vocational program. Coordinated curriculum development, organized and implemented a staff development program. Planned and carried out a successful program of audio-visual instruction, including preparing bid specifications for production equipment for an instructional television system.
Responsible for budget preparation, staff selection, super-vision and evaluation.
July 1966 ~
Assistant Principal for Curriculum, Timberlane Regional to High School, Plaistow, New Hampshire June 1969 Shared equally, with the principal, the screening of more than 1200 applicants for 51 positions. Interviewed from 12-14 hours a day.
, Helped organize a full two months of training for lower management, bringing together specialists from all over the U.S.
Directly responsible, during building construction, for approval of the installation of fixed and movable equipment. I supervised the preparation for bids of all the instructional supplies and equipment, as prepared by department heads. I personally prepared the specifications and bid proposals for a $95,000 dial access information retrieval system, including audio and' video functions. I was totally in charge of program development, holding weekly meetings with department heads for this purpose.
Feb. 1965 Chairman, English Department, Greenwich High School, to Greenwich, Connecticut
- June 1966 Sept. 1959 House Coordinator, English Department, Chairman, to Winnacunnet High School, Hampton, New Hampshire Jan. 1965 Sept. 1956 English Teacher, Exeter High School, Exeter, New Hampshire to -
June 1959 -
130-19
SB 1 & 2 FSAR Amendment March 1986 Sept. 1954 to English Teacher, Spaulding High School, Barre, Vermont June 1956 Sept. 1952 to English
_New Teacher, Hampshire Woodstock High School, No. Woodstock June 1954 ,
_ EDUCATION:
f!. Ed. , Uhiversity of New Hampshire, 1965 P c
Additional Mass. graduate courses at U.N.H., Keene State and U .
_B.
Ed. , Plymouth Teacher's College, 1952 Major: English, Social Studies
_ John Hay Fellow, Harvard University, Academic year 1961-1962
_Kennett High School, Conway, New Hampshire, 1947 Completed 4 years work in 3 years.
Honor Society. Member of Kennett Keys e
4 e
SB 1 & 2 Amendment FSAk March 1986 RESUME: Geoffrey Kingston
SUMMARY
OF-
_ QUALIFICATIONS:
Five years nuclear navy experience plus fourteen years experience in responsible commercial nuclear power positions. Previously licensed as senior reactor operator of a 560 MW commercial PWR station; registered professional engineer. 9
-EXPERIENCE: PUBLIC SERVICE OF NEW HAMPSHIRE, SEABROOK STATION Dec 1982 Compliance Manager /Special Projects Supervisor to Present Responsible for coordination of Station involve =ent and commitment tracking in the areas of NRC, INPO, ANI, Operational Quality Assurance, OES and NSARC audits, inspections and reviews.~ Coordinates SORC activities and performs various special projects for the Station Manager.
Nov 1978 Engineering Services Department Supervisor to Dec 1982 Responsible for hiring a staff of thirty engineers and technicians; supervising the development of program and
, procedure preparation for key engineering and technicial
, programs for the operating phase.
Nov 1975 _ Senior Engineer, Yankee Atomic Electic Company to Nov 1978 Responsible for engineering support of three operating Yankee Nuclear Power Stations. Projects included response to licensing issues, design changes and modifications, and a major upgrade of one plant's spent fuel pool. Also participated as a member of one plant's Nuclear Safety Audit and Review Committee.
Oct 1970 WISCONSIN PUBLIC SERVICE CORPORATION, KEWAUNEE POWER PLANT to Nov 1975 General Engineer, Startup Engineer, Shif t Supervisor, Training Engineer and Corporate Staff Engineer Responsible initially for FS R review and a wide range of operationally-orientated tasks preparatory to plant testing, startup and operation. Trained for and obtained an SRO license and functioned as Shif t Supervisor during the testing period including hot functional testing, initial core loading, physics testing, power ascension testing, and over one year of commercial operation. As Training Engineer, established the Operator Requalification 13D-21 1
SB 1 & 2 Amendment FSAR March 1986 Geoffrey Kingston Page 2 Program required by 10 CFR 55, Appendix A. As Corporate Staff Engineer, performed varicus engineering and quality assursnce support functions.
June 1965 Lieu t enan t', U.S. Navy. Attended over two years of formal to Sep 1970 training in muelear power and navigation. Qualified for the position equivalent to Shift Supervisor on two naval nuclear propulsion plants. Served three years on nuclear power, polaris submarine, holding increasingly responsible officer positions. Qualified in submarines.
EDUCATION AND TRAINING: Completed three courses toward a Masters Degree Program in Engineering Science and Management.
Bachelor of Mechanical Engineering, Marquette University, 1965. .
U.S. Naval Nuclear Power School, Bainbridge, MD, 1965. West Milton, NY, 1966.
, U.S. Naval Guided N1ssile's School, Inertial Navigation, Das Neck, VA, 1967.
Graduated High~5chool, Concord, MA, 1961.
e O
SB 1 & 2 Amendment FSAR Harch 1986 RESUME: Charles W.. Roberts
SUMMARY
OF QUALIFICATIONS : Twenty-one years experience'in both allitary and ir.dustrial security, planning, operations, and supervision. Seven years experience in the management of large scale computer systems, acquisitions and development.
EXPERIENCE: P P
Aug 1984 Public Service Company of New Hampshire to Present Security and Computer Systems Manager Responsible for three departments executing the station security program and the development, acquisition, and maintenance of process computer systems.
July 1980 to Aug 1984 Security Department Supervisor
. Directly responsible for the development of the station physical security program and for directing the activities of those personnel assigned to the department. Perform liaison with engineering, construction, and the NRC to ensure compliance with regulatory guidance.
t .
July 1956 .
to July ~1980 US Army
- - . For seven years, on three accasions, responsible for large I scale computer systems design and development including budgeting for the necessary personnel and equipment.
Managed and supervised personnel to. accomplish the requirements.
Responsible for the administrative and logistical support of ,
a division on the demilitarized zone in Korea, and the ,
internal security of the headquarters and one major i4 subordinate element. Responsible for the computer center that provides data processing support to the division.
Subsequently responsible for the same support for a division stationed in the United States.
Other command and leadership responsibilities commensurate with rank for twenty-four years. ,
e 13D-23
l l
SB 1 & 2 Amendment FSAR March 1986 i-Charles W. Roberts Page 2 '
EDUCATION United States Army War College, 1977 - Management.
AND TRAINING:
Master of Arts in Mathematics, 1971 University of Missouri, Columbia, Missouri. '
4 r United States Army and General Staff College, 1970 Leadership.
i i
United States Army Nuclear Engineering and Radiological Safety Course. - 1959.
Bachelor of Science in Mathematics, 1956 Southwest Missouri i State University, Springfield, Missouri.
9 ee en -
~1=..
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e e l--- .
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e e O e
e 9
, SR 1 & 2 Amendnent
$ FSAR March 1986 REStrME Winthrone R. Leland OffALIFICATIONS: Sixteen years of experience in Chemistry and Health Physica disciplines. Experience ranged from six years at the SIC Naval Reactors Prototype, 1 year at Argonne National. !
Laboratory and 4 years at Connecticut Yankee Atomic Power
, Company.
p i l
EXPERIENCE:
Nov.1979 '
to present Public Service Company of New Hampshire. Seabrook Station Job
Title:
Chemistry and Health Physics Manager - February 1986 to present Responsible for the coordination and direction of the
!. Chemistry and Health Physics Departments. Advise Station Manager of plant radiological conditions 'and radiation
- protection program s'tatus.
i t
Joh
Title:
Chemistry Department Supervisor - May 1981 to February 1986 Responsibilities: Manage the Ch'emistry Department in planning, developing, and implem'enting programs of ohemistry
. . . , _ and radiochemistry which result in the safe and efficient
, , ,,_, , , , ,, operation of th'e nuclear generating station.
Job
Title:
Chemist - November 1977 to May 1981 Responsibilities: Supply te-hnical and supervisory support to the Chemistry Supervisor. Implement current technioues,.
concepts and analytical methods necessary to support the and
,' efficient operation of the ' uclear n generating supervise chemistry and radiochemistry functions of the station.
Nov 1975 to
- Nov 1979 Connecticut Yankee Atomic Power Company, Naddam, CT 4
, Job
Title:
Chemistry and Realth Physics Technician Responsibilities: Perform Chemical and Radiochemistry functions reouired for all phases of op'eration of a pressurized water nuclear plant. Provide Health Physics support during maintenance and operation of the plant.
-,m, - - . - . - , , . _ ..,-,,,m_ _ . , . .___m__ , ,__,._,-,-___w. ,
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-,._,.,.,_.e, -
SB 1 & ,2 Amendment FSAR March 1986 Winthrope B. Leland Page 2 Oct 1974 to Oct 1975 Argonne National Laboratory, INEL, Idaho Falls, Idaho Job
Title:
Senior Health Physics Technician Responsibilities: Write procedures for Laboratory Health Physics Manual, administer radiation worker training course,
-introduce and train radiation worker in concepts of total containment devices, perform safety audits, provide radiation protection for EBR-II reactor maintenance, operate multi channel analyzer for detection of reactor fission breaks.
Jan 1971 to Oct 1974 Ceneral Electric Company, Knolls Atomic power Laboratory.
SIC Prototype, Windsor Site, Windsor, CT Job
Title:
Radiological Controls _and Chemistry Technician Responsibilities: ~ Maintain-Qualification as Radiological Controls and Engineering Laboratory Technician (ELT) as specified by Naval Reactors. Performed and encountered technical aspects of: monitoring radiation exposure. shield planning, liquid and solid waste disposal, thermoluminescent dosimetry, environmental monitoring, perform plant chemical and radiochemical analysis, operate and calibrate instrumen-
- tation, radiation and contamination surveys, first aid, audit radiological operations of Navy personnel and submit written reports of audits.
Jan 1969 to
'Jan 1971 Combustion Engineering - Naval Reactors Division, Windsor, CT (SIC Prototype, same facility'as above)
Job
Title:
Radiological Controls Technician Responsibilities: Same as above under General Electric EDUCATION Bachelor of Science in Chemistry from the University of Hartford - August 1980 MISCLLLANEOUS: Held "L" clearance with the Energy Research and Development Administration. Member of the Health Physics Society.
e 9
SB 1 & 2 Amendment FSAR March 1986 RESUME: Donald J. Abely
SUMMARY
OF OUALIFICATIONS: Over twenty three years experience in power plant related construction and maintenance. Experience includes pre-operational testing and start-up of one fossil and two nuclear generating plants, p _ EXPERIENCE:
June 1979 to Present Public Service Company of New Hampshire, Seabrook Nuclear Power Station.
Job
Title:
Maintenance Department Supervisor, December 1982 to present.
Responsibilities: Establishment of surveillance, preventive r...,...s_-
and corrective maintenance programs for station mechanical ar.d electrical systems and components. Procurement of mechanical and electrical spare parts. Recruiting and s.
ntaf fing Maintenance Department personnel. Function as a member on the Station Operating Review Committee (SORC).
Job
Title:
Electrical Maintenance Supervisor, June 1979 to November 1982. .
Responsibilities: Act as the Maintenance Department
~
Supervisor in his absence. Recruit and staff working foremen, mechanics, electricians and relay technicians.
Develop electrical preventive and corrective maintenance programs. Procurement of electrical spare parts. Supervise electrical working foremen and electricians.
July 1971 to June 1979 Vermont Yankee Nuclear Power Corp. , Vernon, VT.
Job
Title:
Maintenance Department Technical Assistant, 1978-1979.
Responsibilities: Provide administrative and specialized technical assistance to the Maintenance Department Supervisor.
Cor. duct technical studies and evaluations as required for the generation and implementation of plant design changes and additions. Procurement of spare parts.
Function as an alternate member on the Plant Operating Review Committee.
E 130-27
SB 1 & 2 Amendment FSAR March 1986 Donald J. Abely Page 2 EXPERIENCE:
(continued)
Job
Title:
Lead Plant Mechanic, 1975 - 1977.
Responsibilities: Assist the Electrical Foreman in planning and scheduling the daily activities of the Maintenance Department. Supervise electrical maintenance personnel in the performance of electricaJ inspections, surveillance and preventive and corrective maintenance.
p Job
Title:
Plant Mechanic / Electrical, 1971 - 1974.
Responsibilities: Construction verification, preoperational testing, procedure development, preventive and corrective maintenance and surveillance of safety-related systems and conponents.
Nov 1962 to July 1971 New England Power Service Company, Worcester, MA.
Job
Title:
Switchbo'ard Foreman, 1971.
Responsibilities: Relay and metering installation and testing in New England Electric's distribution substations.
Job
Title:
Switchboard Wireman',,1968 - 1970.
. Responsibilities: (1970) Instrumentation and Control-
, . , , , , , Supervisor for the coal to oil conversion of New England -
Power's Salem Harbor Cenerating Plant, Salem, MA. (1968 -
1969) Construction, preoperational testing and startup of New England Power's Brayton Point, Unit #3 Cenerating Plant.
Job
Title:
Construction. Electrician, 1962 - 1967.
Responsibilities: (1967) Construction verification, preoperational testing and start-up of the Connecticut Yankee Nuclear Plant in Haddam, CT. (1962 - 1966) New England Electric System substation construction. Refueling support at the Yankee Rowe Nuclear Plant in Rowe, MA.
EDUCATION: Associate's Degree, Industrial Engineering, Greenfield Community College, Greenfield, MA. - 1980.
Certificate, National Electrical Code, Coyne Electrical Inst., Boston, MA. - 1969.
MISCELLANEOUS : School Director, Town of Vernon, VT. , 1975 - 1979.
l SR 1 & 2 FSAR i
Amendment .
March 1986 RESUMR:
H. Michael Anderson SWfMARY OF OUALIFICATION1. :
i Over 17 years experience in the Nuclea are directly related to the handling r Industry, 10 of which and shipment of Radioactive Waste Material, s.
packaging, processing experience in compliance with federal Extensive radioactive waste materials,and n regulations sposal of governin EXPERIENCE:
cask / container modifications and'new designsincluding shipping Sant 1983 to Present h _Seahrook, New HamnshirePublic Service of New Hampsh tation I
a c..q i
. . ... _ Radioactive site radioactive waste operations.
Waste Utilities handling and packagiSuoervisor - Responsi I ng systen installation, and startuo activitiesSupport. initial system desig t
Utilities Group which is responsible f Supervise the groundskeeping, April 1982 treatment systems, and site janitorialbuilding , sewage and facilities to Aug 1983 and decon activities.
NUS Process Services Corporation.
_ columbia, South Carolina o,-.~.._ - _.
Manager of Waste Management Service;s - R supervision and- canagement of service proje tesponsible for the eobile decontaminstion, liquid waste c s including and solidification. , water, and oil removal ,
Manager of Transoortation Services - Res Cask Service department. organization and operation of the Tr
. ation and Shielded Development Workshop. of Radioactive Waste Packagi four utility sites: Presented this workshop and training cong and Transpor urse at and nuane Arnold. San Onofre, Calvert Cliffs, Oyster Creek D2e 1973 to March 1982 . columbia, MarylandHittma.n Nuclear & Development Corporatio n
Regional Manager of coerations - In loading and movement of 26 shielded e distelhution, traOperatio the transportation of radioactive wast nsport casks used in e materials.
SB 1 & 2 FSAR Amendment March 1986 H. Michael Anderson Page 2 Dispatch and control the Eastern Division of Ri ttman Transport Services, a wholly-owned subsidiary Nuclear & Development Corporation. ttman of Hi P
design /9 fabrication projects. Project Manager ons and new for all ship Regulatory Commission Cask Packages. ance nCertificate Nuclear of Provide marketing support.
Manager of Field Services - Responsible fore the fi ld operations group.
operations to major nuclear utilities bothn and Midwestern United States.
in the Easte Supervised on-site radioactive liquid, resin and/o r sludge transfer and solidification projects at Nine Mile Point the Maine Yankee, C. Cook Millstone, Robert E. Cinna, James A. Fitzpa Arkansas,NuclearOne,andZion}uclearPowerPlant s.
~ . _
various plants including _ decontamination r at special pr waste handling and packaging, Health Physics suppo,rt packaging and transportation consulting. ,
Served Creek. as on-site project manager for Hittman s er at Oy t the handling, packaging, and transportation ofWhile waste materials, radioactive including' building decontamination contaminated equipment ,
cubic feet of backlogged and stored materials. removal, and the rem
_ Start up Engineer - Performed system start up activities on nuclear utilities.several liquid waste solidification systems supplied to 13D-30 J
SB 1 & 2 Amendment FSAR March 1986 H. Michael Anderson Page 3 Jan 1968 United States Navy to Dec 1973 USS George Bancroft SSBN643 U.S. Nuclear Navy Program - Served as Leading Engineering Laboratory Technician performing pr Chemistry Control and Radiation Pro,(mary andactivities.
tection secondary V
Ship's representative during defuel-refuel operations at Portsmouth Naval Shipyard, Portsmouth, New Hampshire.
EDUCATION: Moorhead State College Moorhead, Minnesota U.S. Navy Nuclear Power Schools Bainbridge,. Maryland /
West Milton, New York PROFESSIONAL AFFILIATIONS:
MemberAmericanNuc}EarSoc,iety O
>+ -
- D t
e 13D-31
I i
SB 1 & 2 Amendment l FSAR March 1986 RESUME : Timothy F. Hurphy EXPERIENCE:
September 1985 - Present: Instrument and Control Department Supervisor, Seabrook Station, Public Service of New Hampshire, Seabrook, N.H.
Responsible for directing the establishment of the e preventive maintenance, calibration and surveillance testing programs, including staffing and outfitting of the Instrument and Control Department.
July 1979 - September 1985: Instrument and Control Supervisor, Seabrook Station, Public Service of New Hampshire, Seabrook, N.H.
Exercised the authority of the Instrument and Control D partment Supervisor.
Supervisory responsibilities for all p'reventive and corrective maintenance activities for all instrumentation and control. Assisted in developing, implementing and supervising the preventive maintenanefe program, instrumentation and
, control procedures, and spare parts program.
,. Evaluated the performance of instrument and control personnel. Provided recommendations relative to hiring, firing, promotion and other actions affecting personnel.
October 1978 - July 1979: Instrument and Control Supervisor, Catawba Nuclear Station, Duke Power Co. , Rock Hill, S.C.
Responsible for ESS, RPS, Turbine, Test Equipment and Ice Condensers. Also responsible for initial department staffing and supervision of personnel for the activities of the Instrumentation and Control Department.
August 1977 - October 1978: Instrument and Control Supervisor, Oconee Nuclear Station, Duke Power Company, Seneca, S.C.
Responsible for the E.S. System, Ratiation Monitoring System, H.P. Equipment, Chemical Equipment.
SB 1 & 2 Amendment FSAR March 1986 Timothy F. Murphy Page 2 EXPERIEN_C(:
(Continued)
August 1972 - July 1977: Instrument and Control Technician, Oconee Nuclear-P Station, Duke Power Company, Seneca, S.C.
Maintained the engineering safeguard systems that protected the reactor core and the building.
Calibrated and tested the Radiation Monitoring System and the Integrated Control System. Assisted with station modifications. Submitted problem reports dealing with Nuclear Regulatory Commission
- regulations and technical specifications.
June 1965 - December 1966: X-Ray Technician, Quality Control Department, Avco Research *and Development Company, Lowell, Massachusetts.
- Responsible for detection of welding flaws and heat-shield voids in the construction of the Apollo Space Command module. Familiar with magnaflux, fluoroscope, and ultrasonic testing devices.
EDUCATION: Partial list of completed training:
Pb'R Information Balance of Plant Meteorology Licensing and Regulatory Requireuents Westinghouse Statistical Setpoint Method UNH Hiddle Management 7300 Process System Rod Control System Nuclear Instrumentation System Mitigating Core Damage Motivational Management Techniques
" Vocational Tri-County Technical College
' School: Pendleton, South Carolina Craduated: August 1976 -
Degree: Associate's Degree Studied: Engineering Technology 130-33
t SB 1 & 2 -Amendment FSAR. March 1986
- Timothy F. Murphy Page 3 i
EDUCATION:
(Continued)
New Hampshire Vocational Technical College Berlin, New Hampshire P l - Graduated: June 1972 Degree: Associate's Degree Studied: Industrial Electronics High Berlin High School l - School: Berlin, New Hampshire Graduated: 1965 l
! - MILITARY:
i L
1967 - 1969 1st Lieutenant, U.S. Army, Served as Assistant Executive Officer in Vietnam in charge of Fire Direction Control. Advisor to Army of Republic of Vietnam. Training Officer at Fort Jackson and Company Commander at Fort Dix, New Jersey.
} 1970 - 1972: Captain in New Hampshire National Guard.
l . Intelligence Officer.-
l I
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l l -
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l 13D-34
.. .,,--....,-m... .e ., --,, - - ,_ _ . _ _ . - . . , . , . , , ,-
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SB 1 & 2 Amendment FSAR March 1986 RESUME: Joseph J. Rafalowski POSITION: Health Physics Department Supervisor
SUMMARY
OF ~
_ QUALIFICATIONS: Over nineteen years total nuclear power experience in the field of radiation protection, health physics, primary' and secondary chemistry, and nuclear plant mechanical equipment cperation, maintenance and repair. Twelve of these years have been in commercial nuclear power plants and over fourteen years have involved various levels of supervisory c ,
experience. Certified by the National Regist.ry of Radiation Protection Technologists (NRRPT).
PROFESSIONAL EXPERIENCE:
December 1978 to Present SEABROOK STATION, Public Service Company of New Hampshire.
Position: Health Physics Department Supervisor Brief Summary: Over six years service on the Seabrook l
. Station staff as Health Physics Department Supervisor (Radiation Protection Manager) during which time the Health Physics personnel have been assembled, the' organization established and the station Radiation Protection Program Manual and its implementing policies and detailed procedures have been prepared under his direct supervision.
l 1
Some Specifics: Development, implementation, and maintenance of the Station Radiological Protection Program in compliance with Federal and State Regulations, national standards, and other applicable requirements.
Planning, scheduling, and directing all radiological safety activities which ensure detection and control of radiation and radioactivity in the station and its systems to maintain personnel exposures As L'ow As Reasonably Achievable (ALARA). This includes the specific and detailed review of plant systems and radiation shielding installation.
Recruiting, staffing, and supervising a complement of forty-four (44) health physics personnel including Health Physics
, Supervisors, Health Physicists, Health Physics Working.
Foremen, and Health Physics Technicians. Review and approval of technical training of all personnel and direct supervision of their professional growth.
Administrative Responsibilities: Preparation of all required records and reports; evaluation of personnel, preparation of department budget, purchase requisitions, and equipment specifications.
41 13D-35
l SB 1 & 2 FSAR Amendment March 1986 Joseph J. Rafalowski Page 2 July 1971 to Dec. 1978 Maine Yankee Atomic Power Company Position:
Technician Health Physics ' ream Leader' and Chemistry Briff Summary:
Yankee nuclear power station (PWR) as a Health Phys cs " fTeam Leader" (supervisor) and Technician during initial uel load, normal operations, maintenance and four major refueling outages during was conducted on the which . extensive primary systems. modification and repair work Directed and health physics technicians, and of the numerous additional contracted health physics personnel
, in the performance the surrounding environment. of their assignments in plant and also out through j Some Specifics:
_ Program development.
initial fuel load and start of plant Inoperations: preparation for Reviewed and recommended necessary technical essional and prof revisions in the development and draf ting of the Maine ankee Y
, Radiation Protection Program Manual and implementing procedures.
Established the initial including equipment Health Physics Control Point layout. ,
Designated monitoring points throughout the plant .
detection instrumentation. Performed initial , setup and calibration Established survey techniques and counting methods .
- Defined and assembled contents of emergency kits .
. Performed source inventory and leak tests.
Developed survey maps and analysis .
uel. record formsPer Reviewed and analyzed installation of plant syste ms and L
radiation exposure. recommended to upper management changes needed to Health Physics Technician and direct assistantAs addi as Senior to the RPM Rowe Nuclear Power Station.during a refueling ankee and major mainte 91
--_-_ ___WY -
March 1936 Joseph J. Rafalovski Page 3 JProgram implementation. Upon start during plant testing and operation: of initial fuel load, and Performed or supervised and assisted assigned per the continuous monitoring of all radiological sonnel in within the plant and its systems, environment activities ALARA at to ensure all cimes. maximum safety and radiation osGre expincl During first performed all phases of radiologicalcontrol. monitoring an During the three subsequent maintenance workloads, as Lead (Supervisory) H Prefueling ou assigned, supervised and coordinated the . . Technician, health ysics ph activities of other station Health Physics Technici 20 contracted Health Physics personnel. ans an 10-
_ Chemistry Laboratorv Technician.
water chemistry operation of a PWR.and radiochemistry tasks requit a or d fPerformed all p to corrosion, radioactive radiological hazards. waste disposal and potentialEns July 1969 to July 197~1 .
United Aircraf t Research Laboratory Position:
Senior Instrument Technician jRadioisotope Laboratory:
Performed radioactive gaseous diffusion research I ment centered on physical heating of aircraft engiand develop-and mapping of the radioactive content of this ne hardware hardw determine material defects. are to Responsible for radiological monitoring of work to ensure maximum safety at all times .
environment
_ Chemical Science Laboratory:
Mass energy conversion systems. Responsible earch Bio for operat May 1962 to June 1969 U.S. Navy, First Class Petty Officer (Machinist ate)
M Position: {
Technician Leading (Supervisory) Engineering Laboratory
}
di 13D-37
1 SB 1 & 2 Amendment
, FSAR Harch 1986 Joseph J. Rafalowski Page 4 Brief Summary: Seven years service in naval nuclear power program which culminated in three and one half ' years duty as a supervisor of radiation protection, health physics and ehemistry (analysis .and control in both primary and secondary systems) of a PWR. This service included normal nuclear power plant operation, maintenance and repair and also a complete refueling cycle.
i V .
I
- Some Specifics
- Performed, supervised and assigned personnel t
to perform continuous monitoring of both radioactivity and radiation levels of vessel's environment and surrounding 3
atmosphere and environment to ensure maximum safety at all times.
Trained and. supervised a crew of five (5) Engineering laboratory technicians in Radiation Protection,' Radiological
- Methods and Procedures and Water Chemistry Control in j accordance with bureaurof ships guidance and shipboard 4
directives. --- -
2 Responsible for all phases of radiological, health physics --
and chesistry control and for management of radioactive wastes, including discharges from the vessel. Analyzed and documented all discharges (amount released, curie content, y'
etc.). Solid radioactive waste- management included
', generation, packaging, handling, storage and disposal.
Supervised mechanical, radiological, health physics and water chemistry personnel during refueling of'the S2C reactor.
Performed radiological and chemistry training of other engineering depar,tment personnel including pros'pective Engineering watch officers.
Prepared and documented ,all required records and reports; ,
lesson plans and training programs; requisition and inventory -
l of all laboratory spare parts requirements.
As a Hechanical Technician / Operator (since 1963), was con-currently responsible for maintenance, repairs and operation of all primary and secondary systems and components.
EDUCATION: . l i.
t Continuing education at Northern Essex Community College.
Courses completed include college algebra, trigonometry, statistics and Computers with Basic Programming.
~
c Management and Supervision courses (PSNH) (32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />), 1985 130-38
. . , ., , , - . . - . ~ . - . . . . . - _ _ . - . _ . - ,-.._ - . - - - - - . - _ . -
. - =
SB 1 & 2 Amendment FSAR March 1986 Joseph J. Rafalowski Page 5 Biological Ef fects of Iontaing Radiation, Harvard School of Public Health (26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />), 1983.
PSNH Middle Management Development Program (5 day resident course at UNH, 1982.)
C p
Radiological Health Physics, University of Lowell (2 weeks),
, 1982.
PSNH Middle Management Program (5 day resident course at UNH), 1982.
Air Pollution Meteorology, Northrup Services, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />),
1981.
Applied Health Physics, Oak Ridge Associated Universities (5 weeks), 1981.
Planning for Nuclear Emergencies, Harvard School of Public Health, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />), 1980.
-Internal Radiation Dosimetry, University of Lowell, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />), 1980.
- Assessment of Environmental' Releases of Radioactivity,
. University of Washington, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />), 1980.
'EPRI-DOE Facility Decontamination' Workshop, Hershey, PA, (16
- hours), 1979.
Westinghouse PWR Information Course, (60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />), 1979.
Balance of plant course (PSNH), (60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />),:1979.
Management and supervision courses, (PSNH), (145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />),
1979.
Basic Radiological Health Course, University of Lowell, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) 1976.
Basic Electronics, (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />), 1969.
U.S. Navy Engineering Laboratory Technician School,1965.
U.S. Navy Nuclear Power School, 1963-1964.
Other U. S. Navy service schools; Machinist Mate (A), 1962; Steam Component, 1968; Hydraulic,-1968; CO2 scrubber and H2 Burner School, 1967. -
Graduate: South Vocational High School, Pittsburgh, PA, 13D-39
- - - g3 -
SB 1 & 2 Amendment FSAR March 1986 RESUME: Gregg F. Sessler
SUMMARY
OF OUALIFICATIONS: Twelve years experience in the nuclear power field; engineering, operations, and quality assurance. (Six years specifically in the naval nuclear propulsion program.)
EXPERIENCE:
C Dec 1982 PUBLIC SERVICE COMPANY OF NEW RAMPSHIRE to Present Technical Support Department Supervisor (Feb 1986 present)
Engineering Services Department Supervisor (Dec 1982 - Feb 1986)
Directs the engineering support activities at Seabrook Station. Responsibilities: Configuration management through drawing and design control. Inservice inspection and testing activity support. Program and procedure support for unit startup and operation.
Jan 1982 PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE to Dec 1982 Senior Engineer (Mechanical) "*"~~
. Assisted the Engineering Services Department Supervisor at Seabrook Station in the coordination of mechanical engineering and technical projects. Participated in the development of station programs and procedures to support unit startup and operations. -
1980 - 1932 SCHNEIDER POWER CORPORATION Chief Site Engin~er e '
Managed an engineering department of over 90 personnel including project engineers, piping designers, and draftsmen at Beaver Valley Power Station Unit 2, Shippingport PA. Worked in an integrated site engineering organization which required close coordination with the architect engineering firm and Duquesne Light Company engineering personnel.
Responsibilities: Small bore piping design layout. Piping system design verification and isometric drawing preparation. ASME III/IX, ANSI B3.1.1 and AWS welding
- programs. Technical construction procedure preparation.
Quality assurance records. Document control.
O 13D-40
l SB.1 & 2 Amendment FSAR March 1986 Cregg-F. Sessler Page 2
- 1977 - 1980
- SCHNEIDER POWER CORPORATION
! Site Quality Assurance Manager I
t Managed a quality assurance / quality control group at Beaver Valley e Power Station Unit 2, Shippingport PA, consisting of ANSI level II and III personnel and functioned as a member of Duquesne Light Company site quality control organization staff.
l Responsibilities: Supervision of mechanical / welding inspectors ~ and non-destructive examination personnel. Performance of audits.
Maintenance of'the site Quality Assurance Manual and the NPT/NA stamps. Coordination of inspections or reviews by
[ jurisdictional / enforcement authority personnel (ANI/NRC).
1972 - 1977 UNITED STATES NAVY Served _on tw) nuclear powered ships in assignments ~that provided extensive experience in nuclear propulsion' plant operations ~ and shipyard overhaul' activities. Completed seven years active duty and detached in the grade of Lieutenant.
1975 - 1977 USS BAINBRIDGE (CGN-25)
~ Ship's Test Officer and Dasage Control ssistant during a 27-month nuclear refueling and conversion / overhaul ~ Duties and
' " responsibilities involved: Engineering Duty Officer / Engineering t
Officer of the Watch. Damage control readiness. Shipyard testing.
t 1974 - 1975 STAFF, SUBMARINE SQUADRON 10 Staff Weapons Officer for unit of seven nuclear attack submarines.
Duties and responsibilities involved: Engineering assistance and weapons department audits on squadron submarines.
1972 - 1974 USS WHALE (SSN-638)
O e
6 i
13D-41 -
r t
t ., -,
SB 1 6 2 Amendment FSAR March 1986 RESUME :
Harold O. Whitney
SUMMARY
OF OUALIFICATIONS:
Eleven years experience including startup of large scale nuclear unit, background. other utility and teaching experience, math college
_ EXPERIENCE:
Aug 1979 to Present Public Service Company,of New Hampshire - Seabrook Station Computer Engineering Department Supervisor Responsible for formation of computer department and integration of that department with plant staff and with nuclear projects computer group.
system atResponsible for staffing and for implementing process computer Seabrook Station.
Dec 1969 to Aug 1979 Maine Yankee Atomic Power Company - Wiscasset, Maine ~
Have been responsible for the, process computer system at Maine t
. . . Yankee. . These responsibiliti,es included involve =ent in initial system development and continual upgrades of plant process computer r.ystem to meet changing plant requirements.
During this time period, the plant computer the plant has grown from an " aid to Operations" to an essential part of operatingspecifications.
to plant technical equipment and several of its functions are related During plant refuelings, I have been assigned duties as Reactor Engineering Refueling Coordinator responsible for fuel movement.
Aug 1967 to Dec 1969 Analyst / Programmer for Tenny Group of utilities.
Did work involving conversion to new computer system for corporate office for six utilities in New York and New England.
Sep.1965 to Jun 1967 Hinckley School, Hinckley, Maine During a smallthis timeschool.
private I was a mathematics teacher, coach and dorm parent at last year there. I was chairman of math department during the
- Sep 1964 to Jun 1965
, Franklin High School, Franklin, NH Taught math and science. '
EDUCATION AND TRAINING: ~
Attended Acadia University, Wolfville, Nova Scotia. Majored in Math (50 credit hours.)
related to process computer systems..Have attended numerous courses and seminars 13D-42
SB 1 & 2 Amendment FSAR March 1986 RESUME: Joseph M. Malone
SUMMARY
OF QUALIFICATIONS: Over eighteen years experience in the nuclear field consisting of ten years in the U.S. Navy Nuclear Power Program, three and one-half years as an instrumentation and control design engineer and over five years as a member of the operations department at Seabrook Station.
EXPERIENCE : 9 May 1983 to- Operations Administrative Supervisor - Public Service present Company of New Hampshire Functioning as the representative of plant management in all matters relating to administrative activities of the operations department for Seabrook Station Units 1 and 2.
January 1980 Unit Shift Supervisor - Public Service Company of New to May 1983 Hampshire - -
Responsible for supervising shift operating personnel in the testing of systems during the start-up testing program of Seabrook Station, Unit 1. During the construction ef fort, directed shift operating personnel in the development of station procedures. Participated in the Human Factors review
, of the Unit 1 main control board.
April 1979 to Control Room Operator --Public Service Company of New January 1980 Hampshire ,
Responsible for writing operating procedures for the station and reviewing technical documentation.
December 1975 Design Engineer, ' Instrumentation and Control Engineer-to April 1979 _ing Department, Combustion Engineering Inc.
Directly involved with the design of CE's Nuplex 80 Control Complex for the TVA Yellow Creek and CPU Forked River proj ects. Areas of responsibility:
Developed control room arrangement based on Human Factors design criteria and operator oriented design objectives.
Established criteria and wrote procedure for the layout of control room indications and controls. This effort included research of operating procedures and philosophies and application of human engineering techniques.
SB 1 & 2 Amendment FSAR March 1986 Joseph M. Malone Page 2 Created alarm point selection criteria and designed a plant annunciator system which greatly reduced the nunber of annunciator windows in the control room.
Organized and supervised a control room operibility analysis P which involved the customer.'s engineers and operating representatives. This aaslysis utilized a of the control center and consisted of walk {pil scale mock-up throughs of plant procedures and casualty operations to evaluate effectiveness of the control center design.
Coordinated the development of a catnode ray tube display information system to ensure consistency of the entire control center design.
July 1972 to Stationed at U.S. Navy Nuclear Power Training Unit, November 1975 Windsor, CT Engineering Officer *of the Watch - Served as E00W during refueling operations and post-refueling' core physics acceptance testing and power range testing and directed the operation evolutions.
of the power plant for all prototype training Engineering Officer of the Watch Training Coordinator -
Scheduled, supervised and instructed eight to fourteen officer students in propulsion plant theort and operation and all aspects of the duties of. a nuclear propulsion plant watch officer.
Electrical Division Leading Petty Officer - Supervised and participated in the overhaul and modernization of electrical equipment associated with nuclear power propulsion plant during a major refueling / overhaul period.
Classroom Instructor and Phase Coordinator - Instructed thirty to forty students in propulsion plant theory and-operation during classroom phase and supervised introduction-to operational phase.
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o 13D-44
SB 1 & 2 Amendment FSAR March 1986 Joseph M. Malone Page 3 July 1967 to Served aboard the USS John Marshall (SSBN 611)
July 1972 This period included participation in a major shipyard refueling / overhaul and eight Polaris deterrent patrols.
Major responsibilities:
c Supervised maintenance and? repair of all ships . auxiliary power systems while serving as auxiliary power petty officer.
Actively participated in the administration of the ship's submarine qualification program and was also responsible for teaching and administering examinations on the ship's propulsion plant and electrical. systems to new crew members.
EDUCATION AND TRAINING: Bachelor of Science, University of the State of New York, September 1982.- .-
Completed Memphis State University, Shif t Technical Advisor training program in October 1982.
Graduated Coyne Electrical and Technical School, Boston MA, 1965. .
~
Graduated Central Catholic High School, Lawrence, MA, . 1963.
. Military Schools U.S. Navy Electrician's Mate 'A' School 10/65-02/66 U.S. Navy Nuclear Power School 03/66-09/66 U.S. Navy Nuclear Power Training Unit 10/66-04/67 U.S. Navy Submarine School - 04/67-06/67 Engineering Officer of the Watch Training 03/74-08/74 Also attended various sp'ecialized schools dealing with the technical aspects of a nuclear propulsion plant.
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0 13D-45
SB 1 & 2 Amendment FSAR March 1986 RESUME: Michael R. David
SUMMARY
OF QUALIFICATIONS: Experience in pressurized water reactor operations or operations related positions since 1969. Positions held have been in the commercial nuclear industry since 1974, including supervisory positions requiring a senior reactor operating license from 1976.
EXPERIENCE: c Public Service Company of New Hampshire 1983 to shift superintendent, Seabrook Station. Responsible present for the preparation and approval of plant operating and
- emergency procedures; coordination of shift participation in
'tation startup activities; and functioning as the on-shift regresentative of station management to ensure all station operations are performed in a safe and efficient manner.
.uac.s:: 1979 to 1983 Lead simulator instructor, Seabrook2 Station Training Center. Responsible for the supervision of licensed training instructors; the _ development of training materials; and the implementation of programs to support licensed operator training.
Maine Yankee Atomic Power Company 1974 to - Training gr'oup supervisor. Responsible for the n ~- ------ 197 9
- supervision of two nuclear trainers'and one administrative assistant. Supervised and conducted reactor operator training, senior reactor operator training, operator requalification programs and general employee training.
Senior licensed reactor operator. Responsible for the supervision and manipulation of all controls utilized in the production of electric power at thir facility. ,
United States Navy, USS Plunger (SSN-595) 1969 to 1974 Engineering watch supervisor. Supervised twenty-four nuclear operators in the operation and maintenance of naval nuclear power plant electronic, electrical and mechanical rea.ctor systems.
O 13D-46
SB 1 & 2 Amendment FSAR March 1986 Michael R. David Page 2 Reactor operator. Four yea's r experience in the operation, maintenance and overhaul of the reactor and supporting systems.
( ' EDUCATION p AND TRAINING:
p Completed shift technical advisor training at Seabrook Station conducted by.Hemphis State University.
Bachelor of Science Degree, University of the State of N.Y.,
1983.
Attended University of Lowell, New Hampshire College, University of New Hampshire and accredited naval schools.
l Nuclear Power Training Unit, Windsor Locks, Connecticut, l November 1968 to April 1969.
?
Nuclear Power School, Mare Island, California, Ju.es 1968 to October 1968.
Electronics Class A Schhol, creat Lakes, Illinois,~ July' 1966 to April 1967. .
Western Kentucky State College, Bowling Creen, Kentucky, September 1964 to June 1965.
Lakeview High School, Winti e Carden, Florida, September 1969 -
to June 1964, academic cou.ses.
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SB 1 & 2 Amendment FSAR March 1986 RESUME: Lance H. Fritz SUE!ARY OF OUALIFICATIONS: Sixteen years of active involvement in the day to day operation of nuclear power plants. At these facilities, I participated in numerous startups, shutdowns and refueling outages. In support of these functions, it was necessary, in addition to my normal operational' duties, that I perform various types of . radiological suryeys and chemical analysis p functions.
EXPERIENCE :
Public Service Company of New Hampshire 1982 to Shift superintendent. Responsible for the on-shift present representation of plant management and for supervising all station operations required for safe, efficient and dependable service.
_.. 1979 to Unit shift supervisor. Directly responsible for the 1983 overall safety and efficiency of the unit to which assigned and for directing the activities of personnel assigned to that unit.
Yankee Atomic Electric Company 1973 to Control room operator. Responsible for the control of 1979 -
all operations relative to the primary and secondary systems of a pressurized water-reactor. Responsibilities also 3 .- -
included reactor and steam plant startup and shutdown,' normal and abnormal operations, and switching and tagging.
Alternate control room operator. Relieved above for retraining with all attendant responsibilities.
Auxiliary operator. Responsible for normal and abnormal -
operations of the steam plant, radioactive waste disposal, water treatment plant, and health physics coverage as required.
United States Navy 1965 to Leading first class (machinery division). Responsible 1973 for the overall direction of twenty-five men.in the' repair and operation of the USS Nautilus re' actor support systems, main propulsion and electrical generating equipment.
13-48
l SB 1 & 2 Amendment FSAR March 1986' Lance H. Fritz Page 2 Leading engineering laboratory technician. Responsible for the ship's chemistry and radiological controls. This included the equipping and training of laboratory personnel, radiation and monitoring, dosimetry and radioactive waste disposal.
EDUCATION AND TRAINING: ~
University of the State of New York, Bachelor of Science Degree, 1983.
Memphis State University, Completed shift technical advisor training, 1982.
' Nuclear Power Basics and Training, machinist mate A and engineering laboratory technician school.
Pioneer Valley Regional (High) School, Northfield,-
Massachusetts, graduated 1965. -
LICENSES:
Reactor operator, USNRC Assistant nuclear power plant operator (State of
~
Second class fireman (State of Massachusetts)
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SB 1 & 2 Amendment
- FSAR March 1986 RESUME: Eugene V. Madej
SUMMARY
OF QUALIFICATIONS: Promoted to shift superintendent December 1, 1982, after nine months as a senior instructor at PSNH Seabrook Training Centet. This was preceded by more than fif teen years of nuclear power experience and nine years of fossil and related steam plant experience.
c EXPERIENCE :
9 December 1982 Seabrook Station, PSNH to Present Shift Superintendent Responsible for startup systems and the preparation of emergency, abnormal operating and V.A.S. procedures as assigned.
March 1982 to Seabrook Station Training Center, PSNH Dece=ber 1982 Senior Training Instructor
~
Responsible for implementing observation training for operators at Millstone Unit #2. Participated in teaching startup engineer training program. Participated in acceptance testing of Seabrook's site specific simulator.
April 1975 to Maine Yankee Atomic Power Co. -
March 1982, Plant Shift Superintendent
-~~ -
In charge of a seven man operating shift; acting plant manager on backshifts, holidays and weekends. In charge of all phases of operation including secut-ity. Participated in seven refuelings as a refueling shift supervisor responsible for conducting refueling activities safely and expeditiously. As'sisted operations department head in planning shutdowns and other activities. Responsible for on the job training of control room operators and auxiliary operators. Responsible for procedural updates as assigned.
November 1970 Maine Yankee Atomic Power Co.
to April 1975 Shift Operating Supervisor Participated in initial procedure development and writing, core loading, plant startup, and reactor physics testing.
Responsible for conducting several preoperational system tests. Directed and participated in all. plant power changes from the control room. Acting plant shift superintendent during shut downs and refuelings.
e 130-50
SB 1 & 2 Amendment FSAR March 1986 Eugene V. Madej Page 2 March 1969 to Connecticut Yankee Atomic Power Co.
November 1970 Control Room Operator In addition to normal control room operator responsibilities, operated refueling equipment, performed surveillance testing, directed auxiliary operators during normal plant load changes and' emergency conditions. c
, January 1967 to Connecticut Yankee Atomic Power Co.
March 1969 Auxiliarv Operator Participated in initial core loading and initial plant testing and startup. Operated all auxiliary equipment under the direction of the control room operator.
January 1958 to Western Mass Electric Co. and Mt. Holyoke
. . January 1967 College Fossil Fuel Steam Plant .,=-v.-
Auxiliary Operator .
. Auxiliary operator in a pulverized coal burning plant and oil-fired plant. Participated in fuel handling and maintenance work on heating systems and other related equipment.
MILITARY 1955-1957 Army (Engineer Supply Specialist)
SERVICE:*
~
1957-1959 Active Reserve (Supply Sergeant) 1959-1961 Inactive Reserve -- --"
Honorably Discharged .
~
EDUCATION 1983 (PSNH) management development seminar UNH AND TRA.I?ING: 1978 (MYAPCo) supervisory management development seminar - Rutgers University-1971 Maine Yankee Atomic Power Co. initial cold license training program culminating with N.R.C. S.R.O. license.
1968 Connecticut Yankee license training
, program resulting in an N.R.C. operating license 1957-1962 B.S. program in Mechanical Engineering, Western New England College, Springfield, Mass.
1953-1955 B.S. program in civil engineering,
, University of Massachusetts 1953 A.S. Degree in. Engineering, Holyoke Jr.
College, Holyoke, Mass.
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I 13D-51
SB 1 & 2 Amendment FSAR March 1986
- Eugene V. Madej Page 3 LICENSES: Senior Reactor Operator (1701-4)
Massachusetts Third Class Engineer (010711) c e
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SB 1 & 2 Amendment FSAR March 1986 RESUME: Jerry L. Peterson SU!OtARY OF QUALIFICATIONS: Sixteen years experience in the operation of a nuclear power plant, both commercial and military.
Experience includes: procedure writing, initial startup, full power operations,. refueling and minor maintenance and testing of various nuclear power plant systems, c
EXPERIENCE: p April 1982 to Present Shift Superintendent, Public Service Company of New Hampshire Functions as the on shift representative of plant management and supervises all station operations required for safe, efficient and dependab'le service. STA qualified. l July 1979 to .
April 1982 Unit Shift Supervisor, Public Service Company of New llampshire .
Directly responsible for the overall safety and efficiency of the unit tc which assigned and for directing the activities of personnel assigned to that unit.
January 1973 to July 1979 Power Authority of the State of New York Indian Point Unit No. 3 - Reactor Operator Responsible for shift operations, and supervisor of support groups, of a 1000 megawatt electric nuclear station. Also responsible ~for acceptance testing associated with nuclear equipment, instrumentation and systems. Obtained Unit No. 3 operators license January 1977, Docket No. 55-4974.
Indian Point Unit No. 3 - Nuclear Plant Operator Responsible for the safe and competent operations of the nuclear and conventional systems for the Unit No. 3 facility. Was involved during the construction phase with flushes, hydrostatic tests, equipment and system operational tests, fuel assembly inspection and acceptance.
41 13D-53
~
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SB 1 & 2 Amendment
'FSAR March 1986 Jerry L. Peterson Page 2 Consolidated Edison of New York,'Inc.
New York, New York Indian Point Unit No.2 - Reactor Operator l
Completed the formal reactor training program at the Con c Edison Indian Point Facility. During this time became intimately familiar with all components of the primary and secondary systems, including: the design, purpose,
> limitations and normal / emergency procedures. Also had ,
extensive training on the Indian Point Simulator including full power operations and emergency casualty training.
Obt,ained Unit No. 2 license January 1975.
Indian Point Unit ~No. 2 - Nuclear Plant Operator
- - - a e. - -
Responsible for the safe and competent operations'of the nuclear and conventional systems of the Unit No. 2 start-up
. . program, up to and including the initial core loading.
I United States Navy 1966 to 1972 Assigned to the-USS John C. Calhoun, (SSBN630) as an Electronic Technician. Qualified as a Reactor Operator and-as an Engineer Watch Supervisor. Was involved with a
- ~
complete overhaul and refuel'ing of the nuclear power plant on the Calhoun.
EDUCATION AND TRAINING:
April 1985 B.S. Degree, N.Y. Regents October 1984 SRO License, Seabrook Station, Unit 1 January-1983 to September 1984 Seabrook License Training Program October 1982 STA Qualified 1973 to 1977 Con Edison Training for Nuclear Plant Operator and Reactor Operator.
1966 to 1968 Electronic Technician School, U.S. Naval Nuclear Power School 1964 to 1966 Edinboro State College -
en 13D-54
SB 1 & 2 Amendment FSAR March 1986 RESUME: Ronald G. Strickland SU!CtARY OF QUALIFICATIONS: Sixteen years experience in the nuclear field. Positions held include shift superintendent, unit shift super. visor, control room operator, equipment operator and engine room supervisor. Held an NRC reactor operator's license for four years. Have Bachelor of Science degree.
p EXPERIENCE:
May 1982 Shift Superintendent, Seabrook Nuclear Station.
to Present Responsible for . approving Seabrook Station procedures (emergency, operating, abnormal, and alarm responses). In charge of general administration of a shift. Involved in giving input and making decisions on Station policy; hiring; FSAR RAI's; technical specification development; system design changes; start-up. test procedures;. scheduling; and coordinating operational support activities.
May 1979 to Unit Shift Supervisor, Seabrook Nuclear Station.
~
May 1982 Responsible for' running a shift. Assisted in the development and writing of station procedures; participated in the control board labelling process; involved in the interview .
process and recommendation of auxiliary operator candidates.
May 1974 to Employed by Jersey Central Power and Light at Oyster May-1979* Creek Nuclear. Generating Station. General Electric BWR.
. Qualified as an equipment operator A and B. Held a New Jersey _ State Black Seal Fireman's License, and Blue Seal Engineer's License. Was a control room operator and utilized an NRC operator's license for' 3/2 years. Very active during four refueling periods, and participated in many plant start-ups, low power physics testing, system hydro's, power escalation, surveillance testing, and Rx trip recoveries.
Also had input on plant design changes and. system operating procedures development.
February 1968 to Attended US Navy Nuclear Program. Stationed aboard February 1974 the USS James K. Polk and the USS Stonewall Jackson.
Qualified all mechanical watch stations including engine room supervisor. Made a total of five deterrent patrols, was placed in charge of quality control. .
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SB 1 & 2 Amendment FSAR Harch 1986 Ronald G. Strickland
~
Page 2 EDUCATION AND Received a Bachelor of_ Science degree from the TRAINING: University of the State of New York on September 23, 1983. Earned 172 semester hours with an overall average of 3.80. Attended Memphis State University, University of Lowell (Mass.), New Hampshire College and Ocean County Collpge (N.J.), as well as accredited naval schools.
Completed the shift technical advisor training at Seabrook Station administered by Memphis State University.
Attended University of Lowell for start-up experience on a test reactor.
Completed nuclear reactor fundamentals course at Seabrook' offered by Memphis State University.
. e .a . . Completed hot licensed training anderequalification training
. . at Oyster Creek Nuclear Station.
Attended naval nuclear power school at Bainbridge,- Maryland and submarine prototype.at Windsor Locks, Connecticut.
Completed nuclear component welding course in San Diego, California (USN). .
Completed basic propulsion and engineering school and machinist's mate 'A school in Great Lakes, Michigan.
Graduated from Warren High School, Warren, Rhode Island, in 1967 with college preparatory courses.
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9 13D-56
SB 1 & 2 Amendment FSAR March 1986 RESUME: Roger B. Thompson
SUMMARY
OF QUALIFICATIONS: Completed seven years in the US Navy Nuclear Power Program along with eleven years at a commercial nuclear power l facility in the Operations Department.
EXPERIENCE:
r April 1979 to Present Public Service Company of New Hampshire, Seabrook, New Hampshire Hold the position of Shift Superintendent. Responsible for the generation of operating procedures and general administration of a shift during the operator training program.
April 1974 to April 1979 ' Toledo Edison' Company, Toledo, Ohio Held the position of Reactor Operator at Davis Besse Unite One. Experience at Davis-Besse included.the following:
- 1. Involved in initial construction phase of the plant, system follow-up and review.
- 2. Assisted in writing the operating procedures for the unit and personally coordinated the interfacing of all radioactive waste procedure's.
- 3. Participated in the initial plant system flushes, hot.
functional testing, plant startup, low power physics testing, and power escalation.
July 1970' to April 1974 Atlas Crankshaft Corporation, Fostoria, Ohio Held the positions of Metalurgical Laboratory Technician and Shift Foreman on the camshaft production line.
June 1963
- to July 1970 US Navy nuclear submarines. Qualified Engineering Watch Supervisor and attained the rank of Machinist Mate First Class. -
SB 1 & 2 Amendment FSAR Harch 1986 Roger B. Thompson l
page 2-EDUCATION AND 4' TRAINING: Bachelor of Science, University of the State of New York, 1983.
Completed the Nuclear Reactor Fundamentals Training for license candidates at Seabrook Nuclear Power Station.
Completed Memphis State University courses culminating in qualification as Shift Technical Advisor for Seabrook Nuclear Power Station.
Attended one year at Terra Technical College, Fremont, Ohio, majoring in Business Management.
Completed Hot License Training at Davis Besse Nuclear Power Station. .
Attended US Navy Nuclear Power Training at Bainbridge,
. Maryland, and Saratoga, New York.
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13D-58 l
SBN 975 Attachment B Revision to FSAR Section 17.2 Seabrook Station
Dr o SB 1 & 2 Amendment FSAR March 1936 17.2 OUALITY ASSURANCE DURING THE OPERATIONS PHASE It is the policy of New Ha=pshire Yankee (NHY).that all activities associated with Seabrook Station, which may affect the safety of the general public, shall be perfor=ed in a manner that provides a level of quality co==ensurate with the ac:ivi:y. To i=plement ' this policy during the operation of Seabrook Station, a series of management controls has been instituted which control the quality of work perfor=ed on, and materials used in, safety related s:ructures , sys te=s , and co=ponents. The NHY Operational Quality Assurance Progrs= (0QAP), described below, and its associated managemenf controls for materials and activities meet the applicable regulatory require =ents of 10 CFR 50, Appendix B and is the progrs= established to meet this policy. 51 I
Individuals responsible for the perfor=ance of activities af fecting s: uc- 30 tures, syste=s, and co=ponents at Seabrook Sta: ion are responsible to be faciliar with and to i=ple=ent the applicable require =ents as defined in the OQA?. -
t?3 17.2.1 Orzanization . ...
a
~ ~ '
17.2.1.1 Program Rescensibili:v - ~ ~ ~
The ul:i=a:e responsibili:y for operation, including maintenance, mcdifica:lon and refueling, of Seabrook S:stion rests with New Hampshire Yankee. The Senior Vi.ce President has been designated as the responsible corporate l officer., As such, he has the au:hority and responsibility to develop and 53 i=ple=en,: the Operational Quality Assurance Progrz=, hereinaf:er referred to as the P,rogra or OQAP.
"'~
The Progrs=, which is presented in this and the following see:lons, is expressed as an outline of the assig==ents, actions and procedures tha:, taken together, will result in pro v ar manage =ent and operation of activities at Seabrook S:a: ion. .
Through the established organi:stion, verification of confor=ance to established quality require =ents is i=plemented by individuals or groups not '
having direct responsibilities for the work being verified. Those individuals perfor=ing the verifications and other quality related functions have direct access to canagement levels in the organi:ation which assures the ability to:
o Identify quality problems o Initiate, reco==end, or provide solutions through designated channels ;r3 o Verify i=ple=entation of s'olutions 17.2-1
t_ e.. -
SB 1 & 2 Amendment FSAR March 1986 The Vice President and Director of Quality Programs will mediate disputes !
arising within the OQAP. Where disagree =ent persists, the matter may be appealed to the Senior Vice President for final resolution.
ll 17.2.1.2 Delegation of Authority and Assign =ent of Responsibility
- a. The Senior Vice President, whileretainingfullresponsibilityand!!
the ove6all authority, has delegated the necessary authority and 53 has assigned responsibility for the Progra to the Vice President and Director of Quality Progra=s.# He has assigned the Nuclear !
Quality Manager the responsibility to manage the progrs==stic aspects of the OQAP.
- b. Various operational support services have been delegated to the Nuclear Services Divisica of the Yankee Atomic Electric Co=pany (YAEC). The Quality Assurance Depart =ent of YAEC establishes the progra=s and practices necessary to ensure that such services meet appropriate qualityrstandards. In addition, NHY reviews YAEC
-n=c .doecumentation, audies YAEC perfor=ance, perfor=s an annual u :
'-'-- -' canagement assess =ent of YAEC QA activities, and coordinates the
~
work to assure.a quality work product for' the Seabrook project.
63 % .
17.2.1.3 Organi:stional Structure -
. NEY Or;anization
~
. The NEY organisational ' structure disc ssedi below is shown on
. Figure 17.2-1. gf
^
. . . .. . .. .... ..- ,- 83
- a. ~Vice' President and Director of Ouality Progra s The Vice President ar.d Director of Quality Programs is responsible for the construction and operational QA progra=s. He has been delegated the responsibliity to develop and i=ple=e.: the Operational Quality Assurance Progra: (0QA?). - In order to accocplish this he is assisted by the Nuclear Quality Group whose 53 functions are described below.
Nucles: Ouality Group (NCC)
Il 1.
The Nuclear Quality Manager has overall responsibility for assuring that the Operational Quality Assurance Progra is effectively imple=ented by all organi:ations perfor=ing work on systems and equip ='ent within the scope of the OQAP.
33 W
17.2-2 l
s- e S3 1 & 2 Amendment FSAR Harch 1986 The Nuclear Quality Group has the freedon and authority to perform in?.ependent reviews of OQAP related work and request work stoppages or- remedial actions if conditions adverse to quality are encountered. Functions to be perfor:ed by the Nuclear Quality Group are matched with available manpower resources on a short and long ters basis. For each functional G' category, specific quality assurance activities are identified and man hours required to accocplish the tasks are I esti=ated. Based on these estimates, the number and types of personnel? required to support the activities are detersined.
The program audits are scheduled up to a year in advance. For l short term inspection planning, specific work packages are developed. Due to the ti=e required to recruit and train I personnel and other variables in the work load, certain tasks may be assigned to YNSD and consultants as needed. At present, the QA/QC staff planned is approximately 27 i recogni:ing that this number will vary. dependent on work 53 5=*
- " activities, schedules, and ability to contrac:
- * " - - - - -7 assign =ents outsidc7uThe-NQC's authority extends QA/QCwork"-"~~'k^^
over the NEY Corpora:e Staff, the Seabrook Station Staff,'YNSD and any 6' other organisation performing OQAP related work for Seabrook 33 Station. The Nuclear Quality Manager has a line of co==unication with the directors and managers of the staf fs to assure a timely resolution of 00AP related proble:s, audi:
findings, and corrective ac: ions. The com=unication interface 51
. is shown in Figure 17.2-1. The qualifications and experience
'~
. of the Nuclear Quality Manager are as defined in ANS1/ANS 3.1-
~
80
. 1978 for Professional" Technical. The Nuclear Quality Manager '
direc s and supervises quality activ,1(1,es, such that he:
o Approves the Progra= and all changes to the Progras.
o Maintains co==unications with NEY Directors and Managers, l YNSD Director of QA and other appropriate personnel, as required, to maintain cogni:ance of matters relating to imple=entation of the program.
o Has authority to assign quality assurance functions to YAEC Quality Assurance in accordance with existing-agreements. \
o Directs the Nuclear: Quality Group in the implementation of
, the OQAP. 6./ ,
o Develops a training progran for NQC personnel and provides for their certification, as required.
Sb 17.2-3 . _ _ _ _
? e S3 1 & 2 Amendment FSAR March 1986 o Identifies quality problems and evaluates their extent and safety i=plications.
o Reco== ends, provides or initiates solutions to identified quality proble=s.
e o Verifies -i=ple=entation of approved solutions to such proble=s.
r F
o Ad=inisters the audi:, surveillance and . inspection programs of the NHY organi:stion. l-sa o Evaluates and repor:s on the effectiveness of the Prograr, and identifies trends in quality perfor=ance.
o Refers to the Vice President and Director of Quality Progra=s for mediation, cases where he is unable to
-~ U establish mutual agree =ent with, oEbetween, other
""<3. -
organi:stions involved in the implements:ich# of'the " ~
Progrs=.
o Is Chairman of the Nuclear Safety Audit and Review Co==ittee (NSARC). g4 The Nuclear Quality Group also provides the on-site verifica-
_ . . . _ . . . _ . . tion and assess =ent of the Program i=ple=ents: ion.
57
. The Nuclear Quality Manager receives prior notification of I SC'RC meetings and a representative participates on a l regular # Ik basis. The Nuclear Quality Group is on distribution for }
, pertinen: meeting notices, correspondence and information and 6/
a representative attends any mee:ing which appears appropriate. Nuclear Quali:y Group personnel routinely attend and participate -in work schedule and status meetings to assure ,
that they are kept abreast of day-to-day work assignments ,6Y throughout the plant and that there is adequate QA/QC coverage l relative to procedural and inspection controls, acceptance criteria, and QA/QC staffing and qualification of personnel to carry out QA/QC assign =ents.
The Nuclear Quality Group consiste <f the Quality Control, the I
l ,
Quality Assurance and the Audir 4t.1 Evaluation Sections. The l
Quality Assurance Sect' ion cent f3, expertise in the areas of quality engineering. ,T he At t (- Evaluation Section contains expertise in.qualtij 4.t 4 ance auditing. The Quality l, Control Section contains expertise in the areas of electrical, 30 mechanical, and instrumentation and control. The sections
{
report direc:1y to the Nuclear Quality Manager. j l .
M B7.2-4 ;
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SB 1 & 2 Anendment FSAR March 1986 The Nuclear Quality ' Manager and his staf f embody the necessary technical and professional qualifications and expertise, and 3Y are responsible to: .
(a) Assist the Training Manager in providing basic and advanced QA Training for Station personnel.
(b) Train, retrain, an[ qualify personnel ip the specific OA and QC skills and techniques required do perform audits, F surveillances and inspections cf OQAP related work.
associated with NHY operations, maintenance and other l activities.
84 (c) Monitor and review the condue: of quality control activi:ies and the perfor ance of inspections.
(d) Perfors QC inspectica functions not delegated to 'other groups /organi:st, ions.
$h
('e) Perford audits and surveillances of Sta: ion progra=s and '
I ac:ivicies vi:hin' the scope of the OQA?.
1 (f) Review and audit to assure tha: contractors or service agencies performing on-site werk, within the scope of the i CQAP, e= ploy adequate QA programs and imple=enting I
- procedures.
. .. 80 (g) Exercise s:op-work authority.
~*
- b. Vile President - Nuclear Production The Vice Presiden: - Nuclear P:cduction is responsible for the operation and operational support of Seabrook Station. ' To assist his in the accomplish =ent of these responsibilities, he has the Seabrook Station Manager, the Star:up Manager,- the Nuclear ,
Services Manager and the Training Center Manager reporting directly to him.
- 1. The Startup. Test Department is headed by the Startup Manager and is responsible for ,the scheduling, administration, technical direction, and performance of the initial test program. -
e
__ _ _ % 2-2 _
- 2. ,
SB 1 & 2 Amendnent FSAR Natch 1986
- 2. . The Nuclear Services Group functions in direct support of the Station in the. areas of ' licensing, health physics, and i operations. I Sist
- 3. Seabrook Training Center (TC) is headed by the Training Center p Manager sd:o is responsible to his for the activities of the TC as described in FSAR Chapter 13. !
- 4. Seabrook Station is headed by the Station ~ Manager who is responsible for the operation and administration of Seabrook Station. To carry out this assignment the Station Nanager has the staff and organisation described in FSAR Chapter 13. The various parts of this organizatica implement their assigned aspects of the Progras as follows:
(a) Station Manager
- 1. Overall responsibility for imple=entation aspects of
--a - - the Program on Seabrook Station s:tuctures,'syste=s t'
and cecponents. - -
. 2. Is Chairsan of the Station Operation Review Co==ittee .
(SORC).
(b) As sis tant Station Mana2er
~
The Assistant Station Manager repor:s directly to the Station Manager and is responsible to:
~ ~
1.' Supervise the Seabrook Station Technical Services Manager and the Training Manager. _
G
- 2. Is a member of the Station Operation Review Coesi::ee (SORC).
- 3. Assu=es the responsibilities of the Station Manager' in his absence.
(c) Cocaliance Manager The Compliance Manager reports directly to the Station Manager and is responsible to him to: 3-6 i
o e
v e S31&2 Amendment FSAR March 1986
- 1. Maintain communications with the Nuclear Quality Manager on matters related to the implementation of the Program within the s'ation. S'Y
- 2. Represent the Station Ma uger in matters relating to regulatory compliance a
- quality assurance actitrities within the deation.
r (d) The Administrative Services Manager reports directly to the Station Manager and is responsible to:
- 1. haintain a staff of administrative, computer development, security, and safety personnel who are trained and qualified to perform their duties.
$6
- 2. Administer and monitor performance of Station security services.
- 3. Coordinate all Station drills related to security, '
fira' protection and safety.
. 4. Supervise the procurement, receipt inspection, handling, storage, issue of and records associated with material ar.d services that are encompassed by 156
. the Program.
(e) The Seabrook Station Training Manager reports directly to
~
- ~
, the Assistant Station Manager and is responsible to:
- 1. Develop and maintain, for nonlicensed. personnel, the progra= needed to train individuals in their assigned tasks and functions.
- 2. Conduct non-licensed /non-operator training for each designated person. .
- 3. Coordinate the celection and timing of personnel to' i be assigned to initial training and retraining 66 courses.
- 4. Provide quality assurance and quality control training under the technical direction of the Nuclear Quality Manager.
i* '
e 17.2-7
SB 1 & 2 Ame ndmer.t FSAR March 1986' (f) The Technical Services Manager reports to the Assistant Station Manager and is responsible for:
~
- 1. Perfor, ming the technical and engineering suppor:
functions for the station staff.
p
- 2. Reactor engineering activities.
e (g) The Chemist v and Health Physics Manager reports directly to the Station Manager and is responsible for:
- 1. The nuclear and steam portions of the operations of the station to ensure that the quality of stess and water is within' specifications.-
- 2. Health physics and radiation protection programs a:
. the station.
. :. .., . ..--,.m (h) '.The Maintenance Manager reports direc:ly to the Station Manager and is responsible to:
- 1. Perform the support func: ions that include the corrective and preventive maintenance progra=s;
. station modification and repair actions; and radwaste facility operations.
~
. . 2. Prepare the required procedures for" performance of the above functions. Schedule the perfor=ance of work and control the material,~ personnel and
- processes involved.
6b (1) The Ooerations Manager reports directly to the Station !
Manager and is responsible to: -
- 1. Operate equipcent at the Station in compliance with.
Technical Specifications and other license require =ents.
- 2. Assist in the', training of opera: ions personnel to assure'an adequate number of qualified e=ployees for each task.
'O O
O 17.2-8
< v s SB 1 & 2 , Amendment
.FSAR March 1986
't a
I
- 4. ,
- 3. Prepare, review, approve and implement the operating r procedures to be used for Station operations.
- 4. ' Direct actions, within the realm of the Operations Group, to perform the balance of the surveillance testing program required by the Station license.
- 5. Maintain a 'staf f of fire protection . personnel.
' 53
- c. Director of Engineering The Director of Engineering reports. to the Senior Vice President and interfaces with the Vice President and Director of Quality Programs. He is responsible for NHY engineering programs, configuration management engineering studies, safety evaluations licensing services and environ = ental programs. *
, ,1- .
- d. Director of~ Corporate Services
-The Director'of Corporate Services reports to the Senior Vice
-President and interfaces with the Vice President and Director of --- x c use Quality Programs. He is responsible for construction and special i projects management, and facilities.
- e. Director of Management Control
. The Director of Management Control reports to the Senior Vice
.. President and interfaces 'with the Vice President and Director of Quality Programs. He is responsible for purchasing and contracts, information resources, employee relations and budgets. - -
i The NHY Purchasing Department reports to the Director of
~ Management Controls and provides the purchasing activities as described below. ,,
- 4. -
I
- 1. NKY Purchasing Department ,
"L .
NHY Purchasing is minimally involved in the implementation of h the Program, since quality aspects concerned with procurement SY 60 i of materials and services that are within the scope of the 7 Program are perfor=ed by others. Specific functions and l responsibilities of the Purchasing Department are:
- dy Ob (a) Issue Purchase Orders in response to Material Purchase Requests that are generated and approved. l
]
~
l (b) Maintain current the commurcial status of Purchase
- Orders, a
I l
l 17.2-9
__ ~ . . _ . _ _ _ . _ - _ _ - _
SB 1 & 2 Amendment
~
FSAR March 1986
- f. Yankee Atomic ~ Electric Company - Nuclear Services Division (YNSD)
- 1. Organization The YNSD organizational interface with NHY for quality l assurance activities is shown in Figure 17.2-1. 3;3Slb The YNSD organization consists of a variety of disciplines.
'# The two that provide the direct interface with NHY are the !
Quality Assurdnce Department and the Projects Department. The53 Projects Department draws upon the other YNSD technical disciplines to furnish the specific support services as they are needed.
- 2. Responsibilities YNSD responsibilities in support of Seabrook Station are:
~
(a) Quality Assurance Department
- F~"~~ (1) Assure that TNSD' activitiestconply with requirements of the OQAP.
(2) Provide evaluation, inspection and/or surveillance of vendor services for Seabrook Station. This includes evaluation of QA programs
. and procedures, the examination of vendors selected to fabricate or furnish material,
~ ~ ^ equipment and services and maintenance of an updated list lof such approved . vendors.
(3) Provide the TNSD interface with the NHY Vice ( b President and Director of Quality Programs and 53 l
carry out functions in accordance with procedures ! 6b and agree =ents between YNSD and NHY.
- . }[$
(b) Projects Department Draw upon the varied technical expertise within YNSD, and coordinate activities in support of Seabrook Station.
(c) Technical Discipline Departments Provide the technical expertise required by the Projects Department in the areas of Plant Engineering, Licensing, Environmental Engineering, Fuel Cycle and Nuclear Engineering.
17.2-10
i _. _
SB 1 & 2 Amendsent .
FSAR March 1986
- g. Nuclear Safety Audit and Review Committee (NSARC)
NSARC is an executive body that is responsible for conducting a critical examination of Station activities, including Station operation, evaluation of procedures, investigations of abnormal
~
conditions, and functioning of the OQAP. Technical Specifications define the responsibilities and authority of NSARC. A written p charter, approved by the Senior Vice President, designates the l E membership, authority and rules for conduct of activities. 53 r
- h. Station Ooeration Review Committee (SORC)
SORC is an advisory group, composed of Station manage =ent and supervisory personnel, constituted for the purpose of reviewing current activities and determining the eff ect on operational safety. SORC reco= mends to the Station Manager approval or disapproval of proposals considered by the Coccittee. Technical Specifications define the responsibilities and authority of ,
SORC'. _ A written charter, approved by the Station Manager, '
~ ~ ~ ~
designates me=bership, authority and rules for conduct of activities.
17.2.1.4~ Authority to Stoo Work
- a. -
NHT
, The Nuclear Quality Manager and designated Nuclear Quality personnel have the responsibility and written authority to stop gy ~
work or other activities that are not in compliance with the
~ ~ '
Program.
- b. YNSD The -YNSD Director of QA and, through him, personnel of the YNSD-QAD have the responsibility and authority to stop work, if ,
required, on activities delegated to YNSD. ,
17.2.1.5 Resoonsibility to Reoort Included in the corporate policy, and an, essential part of this Program, is the responsibility of all'NHY, Seabrook, Station, and YNSD personnel working l within the scope of this Program,.to report to their supervisor any equipcent, work or other activity that is not in ' compliance with this Program. Should
? the circumstances warrant such action, particularly when a substantial safety hazard or when the public health and safety is involved, the situation is to be further reported to the Compliance Manager or to the Nuclear Quality Manager, or to other increasingly higher levels of NHY and Station management l until appropriate action is observed to be undertaken.
e 17.2-11
z_. . . _ .
S3 1 & 2 Amendment FSAR Harch 1986 17.2.2 Quality Assurance Progras 17.2.2.1 Outline The. commitments outlined in each section fors the basis for preparation of procedures, instructions and other administrative controls. This ensures that activities affecting the testing, repair, and design of the applicable structures, systems, or components are controlled and documented in a quality 9 manner. To ensure the effectiveness of the OQAP, the commitments of each section and their implementing controls are audited as described 'in Subsection 17.2.18.
The Progras is implemented on structures', systems, or components at least 90 days prior to fuel load or at the time of conditional acceptance by the l l Station staff.
gyS b l
The OQAP focuses on NHY activities, however, where a major portion of an 56 activity is performed by a group other than NHY, the group or organization is
- identified and discussed.
17.2.2.2 Scope
. Structures, Syste=s, and Components The OQAP applies to structures, systems or components which are required to assure: ,
' - -- --- " 17.'" The integrity of the reactor coolant pressure boundary;..
-2. - The capability to shut down the reactor and maintain it in a safe shutdown condition or; ,
- 3. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures
~
comparable to the guideline exposures in 10CFR100.
These structures, systems and components have been designated as Safety Class' 1, 2, 3; Class 1E or seismic category 1, and are listed in Tables 3.2-1 and 3.2-2. They are also identified as safety-related instrumentation and l controls in FSAR, Sections 7.1 through 7.6.
fo A procedure establishes the mechanism to determine the appropriate safety classification of specific structures, systems and components where infor=ation on the appropriate safety classification is not available. ,
.s e
e 17.2-12
s s .
.' SB 1 & 2 Amendment FSAR March 1986
. In addition, certain other structures, syste s, E components, and activities determined to be within the scope of the OQAP are listed -below:
- a. Fuel Assemblies
- b. Control Rods e c. Steam Generator Steam Flow R2strictors
-r
- d. Missile Barriers
- e. Computer Programs Computer prograss which form a basis, for design, modification or operation of the structures, systems, and components identified above require administrative controls which are subject to the OQAP. Procedu,res specify the development, approval, certifica-tion, . control and use of these programs to assure that assusp-
- '- --+*w:tions, processing and application of results are consistant.with . -
Station design cocsitsents.
- f. Expendable and Consumable Items Expendabla.and consu=able items, when used in safety-related activities, are considered to. be within the scope of the OQAP, and
,ill w be subject to the pertinent requirements of the OQAP. The .
, requirements will be evaluated on a case-by-case basis.
- g. Fire Protection Program . . - . .
Appropriate. portions of the Operational Quality Assurance Program apply to the Seabrook Station Fire Protection Program described in FSAR Section 9.5.1.2. The scope of the QA, program extends to the fire rated assemblies (i.e., valls, floors, ceilings) enclosing a
~
fire area containing safety-related equipment ge , separating portions of redundant systems within a fire area that are required
- for safe shutdown as defined in 10CFR30, Apppendix R, and to fire .
protection equipment whose failure would render the fire protection system (or portion of it) unable to provide fire detection and/or suppression to fire areas containing safety related equipment.
- h. Spent Fuel Pool Liner :
Backfits, repairs or modifications to the spent fuel pool liner will be conducted under the scope of the OQAP.
6b 17.2-13
e .
SB 1 & 2 Amendment FSAR March 1986
- 1. Flood Prevention Design Features Modifications of the site and roof- drainage systems, the seawall, retaining walls, and other revetments surrounding the plant will be evaluated to determine if their implementation will increase the flood vulnerability of safety-related items. Those modifi-cations determined to affect safety-related items will be covered by the OQAP. P 17.2.2.3 Program implementation It is recognized that the degree of Program applicability varies with different systems and activities. 53 The degree to which the requirements of this Program and its implementing procedures are applied are. based upon the following:
o The importance of malfunction or. failure of the item to plant safety; 53 $'h o - The potential degradation of a safety related function as.a result of performing an activity. 53 o The complexity or uniqueness of the item.
o .The need for special controls and surveillance or monitoring of
.-processes, equipment and operational activities.
o The degree to which functional compliance can be demonstrated by inspection or test.
o The quality history and degree of standardization of the item or activity.. ,,
A three-level approach is defined' to assure program implementation to the degree necessary. .
- a. Level 1 - This level includes independent inspections and/or tests performed during routine and non-routine activities by appropriately trained personnel.
- b. Level 2 - This level includes surveillance and monitoring activities that ;are performed by the Nuclear Quality Group. Such activities may include observation of tests, inspections and significant activities; review
- of records and procedures, and verification of test reports. 8b Records of surveillance and monitoring activities are ma inta ined .
17.2-14
SB 1 & 2 Amendment FSAR March 1986
- c. Level 3 - This level includes a comprehensive audit and evaluation program initiated by the Nuclear Quality Manager to assure proper functioning of Levels 1 and ,
- 2. This level includes measures performed tc verify 61f that activities required by the OQAP are established, implemented and satisfy regulatory requirements.
17.2.2.4 Program' Standards c
NHY maintains a working knowledge of applicable industry codes, standards, federal. regulations and guides. The OQAP, complies with the following references and the regulatory position of the Regulatory Guides, except as noted in Appendix 17A.
- a. 10 CFR' Part 50, Appendix A - General Design ~ Criteria For Nuclear Power Plants. ,,
- b. 10 CFR', Part 5'0, Appendix B - Quality
- Assurance Criteria For Nuclear -Power Plants 'and Fuel Reprocessing Plants. ' _,,,,. '
- c. 10 CFR' Part 50.55a - Codas ard Standards.
- d. 10 CFR, Part 50.59 - Changes' Tests and Experiments.
- e. 10 CFR', Part 71, Subpart H - Quality Assurar.ce Criteria For Shipcing Packages For ' Radioactive Material. ,
~
- f. 10 CFR, Part 50.34 (b.6.ii) Final Safety Analysis ~ Recort. - <~-
- g. Regulato ry Guide 1.8, May,1977', Personnel Selection'and' Training (endorses ANSI-N18.1-1971, however, ANS3.1-1918 will be the standard used).
- h. Regulatory Guide 1.26', Rev. 3, February,'1976, Quality Croup _
Classification'l *and Standards ~ Yor Water, Steam, 'and Radioactive Waste Containing Components 'of Nuclear Power Plants.
- i. Regulatory Guide 1.29; Rev. 3 September 1978', seismic Design Classification.
J. Regulatory Guide 1.30, August, 1972, Quality Assurance Requirements 'for the - Installation," Inspection 'and Testing o f Instrumentation and Electrical Equipment, (endorses ANSI-N.4 5.2.4-1972).
- k. Reguletory Guide 1.33, February 1978, Quality Assurance Program Requirements (Oceration), (endorses ANSI-N18.7-1976/ANS-3.2) .
17.2-15
9 SB 1 & 2 Amendment FSAR March 1986
- 1. Regulatory Guide 1.37, March 1973, Quality Assurance Requirements for Cleanine of Fluid Syste=s and Associated Components of Water-Cooled Nuclear Power Plants, (endorses ANSI-N45.2.1-1973).
- m. Regulatory Guide 1.38) May 1977, Quality Assurance Requirements for Packaging'," Shipping,' Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants, (endorses ANSI N45.2.2-I 1972).
r
- n. Regulatory Guide 1.39, September 1977, Housekeeping Requirements for Water-Cooled Nuclear ~ Power Plants, (endorses ANSI-N45.2.3-1973). ,
~
- o. Regulatory Guide 1.58, . September 1980, Qualification of Nuclear Power' Plant Inspection', ' Examination 'and Testing Personnel, (endorsea ANSI-N45.2.6-1978).
- p. Regulatory Guide 1.64, June 1976', Quality Assurance Requirements for 'the ' Design of ' Nuclear"." Power' Plants. (endorses ANSI-N45.2.11- - :, ~o u-:--
1974). .
- q. Regulatory Guide 1.74' February 1974, Quality Assurance Terms and Definitions , (endorses ANSI-N4 5.2.10-1973).
- r. Regulatory Guide 1.88' October 1976, Collection, Storage and
. Maintenance of Nuclear Power Plant Ouality Assurance Records,
, (endorses ANSI-N45.2.9-1974).
- s. Regulatory Guide.l.94, April.1976, Quality Assurance Requirements for Installation,-" Inspection?'and Testing of Structural Concrete and Structural ' Steel During 'the Construction Phase of Nuclear Power Plants , (endorses ANSI-N45.2.5-1974) .
- t. Regulatory Guide,1.116, May 1977, Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems, (endorses ANSI-N45.2.8-1975).
- u. Regulatory Guide 1.123, July 1977, Quality ' Assurance Requirements for Control of Procurement 'of Items and Services for Nuclear Power Plants (endorses ANSI-N45.2.13-19 76).
- v. Regulatory Guide 1.144, Septe=ber 1980, Auditing of Quality
~
Assurance Progra=ned for Nuclear Power Plants, (endorses ANSI N45.2.12-1977).
- v. Regulatory Culde 1.146, August 1980, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants, (endorses ANSI N45.2.23-1978).
- x. Branch Technical Position (BTP) APCSB 9.5-1, Appendix A.
17.2-16
SB 1 & 2 Amendment FSAR March 1986 The Technical Specifications shall be the governing document in case of conflict between the Technical Specifications and the above references.
Exceptions, alternatives and clarifications to the referenced standards are noted in Appendix 17A. t l
17.2.2.5 Program Revision c
The Nuclear Quality Manager is responsible to maintain the OQAP current. All proposed changes, whether reflecting editorial co=ments or major program j policy revisions, are forwarded to the Nuclear Quality Manager for approval and control.
Procedural controls are required to ensure that prior to making any ch.tnge to the OQAP, a written, evaluation shall be prepared to identify the change, the reason it is needed, and the basis for concluding that the change results in an OQAP that continues to, meet the criteria of Appendix B of 10 CFR 50.
Changes to the OQAP, as described in this section, are submitted to the NRC in accordance with 10 CFR 50.54. - - -- . , y, g 17.2.2.6 Procedures
- a. NHY To imple=ent the quality assurance policies identified in the
,0QAP, and to assure compliance with the 10 CFR 50 Appendix B criteria, procedures are prepared, reviewed, and approved in
~
accordance with OQAP requirements. Qualified individuals in the
~ ~ ~'-~ -" Nuclear Quality Group will be responsible, for performing reviews of documents affecting quality and safety, including changes dIY thereto. The QA/QC review is to assure that the necessary QA/QC
. requirements are properly and correctly stated and that the procedures meet the FSAR require =ents. A matrix in Appendix 17B i
i reflects the individual 10 CFR 50 Appendix B criteria met by program documents. l 56
- b. YNSD .
The Nuclear Quality Group annually performs a management assessment of YN -QA as described in 17.2.1.2.b.(3).
$b
- c. On-Site' Contractor.
The Nuclear Quality. Group approves the QA programs of contractors l and service agencies which are engaged in on-site OQAP related 5y work activities. 36 17.2-17
SB 1 & 2 Amendment FSAR March 1986 17.2.2.7 Management Evaluation
- a. In addition to any major quality problems which are immediately brought to the attention of upper management, the Nuclear Quality Manager conducts quarterly meetings which gives the Vice President and Director of Quality Programs ongoing cogni:ance of the FY i=plementation and adequagy of the OQAP. The meetings address go areas of audit, surveillance, and inspection results; qual [ty l trends; significant problema and interactions with the regulatory 50 agencies. #
- b. NSARC performs a bi-annual audit of the CQAP and sub=1:s a report to the Senior Vice President. This report provides NHY management !
with an independent assess =ent of the OQAP. The NSARC identifies and tracks corrective action.
g4 17.2.1.8 Indoctrination and Traininz - .
The Quali:y Assurance portion of the non-licensed training program consists of introductoryandspecializedtraining'} .
The introductory training segment instructs new or transferred employees, who .
may perform quality related activi:les, in .the purpose, scope and method of i=ple=entation of quality-related manuals, instructions and procedures. This segment also describes the company organi:stion, interface with regulatory
- bodies and other topies per:inent to the employees job description. --
Specialt:ed training in areas of inspection, test,' and auditing leads to , ----
certification or qualification of individuals. This training is initiated as L early as practical to meet OQAP objectives'. ,For the formal training p'rograss,
~
documentation includes the objectives, content of the Progras, attendees, and l da:es of attendance. 65 The scope, technical content, and frequency of training is determined by the Nuclear Quality Manager. Tests are given as necessary to those NQC personnel performing and verifying activities affecting quality. Acceptance criteria . 60 are developed to determine if individuals are properly trained and ,
qualified. E=ployee proficiency is maintained by ' retraining, reexamining, or recertifying.
The licensed training program, assures'that a sufficient number of appro - l priately trained and licensed individua,l's are available to operate Seabrook
, Station.
17.2.3 Design control 17.2.3.1 Scope The designs of structures, systems and components described in Section l' 17.2.2.2 are controlled. Design control is applied to activities such as field engineering; core physics, seismic, stress, thermal, hydraulic, and ceccident analyses; and associated computer programs. Design controls consider l
compatibility of materials; accessibility for inservice inspection, mainte-
! nance and repair; and the acceptance criteria for tests and inspections. jl- .
I 17.2.3.2 Design Document Preparation, Review and Aporoval I
The preparation, review and approval of design documents such as design criteria, design drawings, computer programs, specifications, and procedures require the interface of NHY, YNSD, and vendors / contractors. Procedures are I established which include requirements for a documented check to verify the d2 t
completeness and adequacy of design docu=ents. The organizational elements l
- involved with the design document preparation, . reviewThe andNuclear approval are the NHY l66 Quality
_ Engineering, Nuclear Quality Group and YNSD engineering. 53 review is to ensure that the necessary QA/QC requirements are adequate and -
that the technical requirements are consistent with the FSAR and applicable s procedures'.- The interface between organizations is procedurally defined to
- assure proper control and to maintain design activity awareness of those activities of reviews, approval, release and distribution of the documents.
Criteria ~and methods used by vendors / contractors which may affect the design
'- of Seabrook are evaluated and approved -prior to use.
- - ~ - -
17.2.3.3 Design Verification The assigned lead design group or organization (i.e.,' NHY, YNSD, supplier, architect engineer) ensures that the designs and materials are suitable and that they comply with the design criteria, quality standards and regulatory 53 requirements. Des,ign verification is performed'by individuals other than those who performed the original design. The extent of design verification is determined by the complexity of the system, the safety function to be ,
performed and the applicable regulatory requirements, codes, standards, FSAR cocmitments and QA requirements. Procedures provide criteria for identifying l
which organization or group performs the design verification including the method of verification (i.e., design review, alternate calculation or test). S3 i
If testing is chosen, the most advers.e' design basis conditions are stipulated 6 ,
and demonstrated. Procedures identify the criteria for determining the i
verification by testing. Prototype, component, or feature testing vill be 60
- performed as early as practicable prior to installation, but will always be i
performed before the structure, system, or component is relied upon to perform l 3 05
! its safety function.
l I 17.2-19
1 SB 1 & 2 Amendment FSAR March 1986 Procedures which control the design verification activities specify internal and external- interfaces. The methods used by the verifier are documented.
Computer programs are certified prior to use and their application is specified. Procedures require that design verification must be complete prior i to relying upon the-structure, system, or component to perform its function.
- Procedures control design verification and specify which documents receive formal design verification by interdisciplinary or multiorgani:stional teams 5 37 anf those which can be reviewed by a single individual. Design documents subject to procedural' control include, but are not limited to, specifications, calculations, computer programs, the FSAR when used as a design document, and drawings including piping and instrument diagrams, control logic diagrams, and electrical single line diagrams. Specialired reviews will be used when uniqueness or special design considerations warrant. Procedures specify the responsibilities of the verifier, the areas and features to be verified, the .
pertinent considerations to.be verified, and the extent of required documentation. ,
-17.2.3.4 Design Changes . <- .
Changes to the design of Seabrook Station require the same design control g-measures that were applicable to the original design. NHT Engineering ,
I normally reviews changes to the design, unless, review responsibility is specifically delegated to another organization. SORC will review safety related changes to the design of Seabrook Station to ensure that no unreviewed )
DN l
safety questions exist. Procedures which may be affected by safety related i
- design changes will be reviewed to enaure their continued effectiveness.
Administrative procedures ensure tha c the responsible -Station personnel are
- aware of the changes which may affect their duties. Station design changes . .-- .
and related changes to station procedures are controlled and incorporated in the licensed training program. .
17.2.3.5 Deviations .. .
Procedures exist to document and control deviations from approved design documents, including design standards that could adversely af fect structures, systens and components. Also included, is the control of deviations from .
specified quality standards. In the case of errors or. deficiencies, action is i taken to determine the cause and to initiate appropriate changes based on the significance or recurrence of the error / deficiency. Errors / deficiencies may l
be revealed by; verification measures, use of the document, audit, tests,
~
actual failure, or other means.
17.2.4 Procurement Document Control' 17.2.4.1 Procurement Planning e
The Seabrook Staf f is the organizational element responsible for procurement activities. In this effort, they identify tasks and assign responsibilities i to execute an integrated procurement plan.
l 17.2-20
s SB 1 & 2 Amendment l ,. March 1986 FSAR 17 . '? . 4 .2 Procurement Document Preparation and Review
! New *bmpshire Yankee has the pri=ary responsibility for preparation and review of procurement initiating documents. The content and routing within L N'dY are procedurally defined. The document content includes, as appropriate:
I a. Scope of Procurement l b. Technical Requirement 3 s' i
- c. Quality Assurance R2quirements
- d. Documentation Requirements l
I
- e. Rights of Access Provisions
- f. Nonconformance Reporting Provisions
- g. Administrative and reporting' requirements l h. Required drawings
- 1. Required specifications J. Required codes and industrial standards
- k. - Test and inspection requirements-
.._...'J... -1. Special process instructions , , , , ,, ,
(,
The routing of the procurement initiating documents within the NHY organization consis;s of a technical and a quality review. The technical review, based on written guidelines, ensures that appropriate technical, The regulatory and special requirements are included and properly identified.
quality review is based on the Program and is performed by . Nuclear Quality Group personnel ti assure the quality requirements are properly specified. 63 The quality reviews are based on written guidelines and include:
l . Sb
- a. Quality requirements - correctly stated and verifiable by inspection, test or document review. 53 50 j
- b. Acceptance and/or rejection criteria.
Review and approval of the procurement document to assure that it
(.
c.
meets the OQAP requirements.
~
17.2-21 i
- SB 1 & 2 Amendment FSAR March 1986 For concercial "off-the-shelf" items where specific quality assurance controls appropriate for nuclear applications cannot be imposed in a practicable manner, special quality verification requirements will be established to provide the necessary assurance of an acceptable-item. This may include but not limited to receipt inspection, tests and/or document review.
' 5 ",
l l
',Upon completion of the above reviews, the h"dY Purchasing Department $b transcribes the procurement infor=stion on a purchase order (P.O.) . The NHY g Purchasing Department cannot waive or change any technical and quality ip require =ents of a procurement document without proper authori:stion from the 53 Seabrook Staff and NQG. Copies of the appropriate procurement initiating g document and executed P.O. are maintained at Seabrook Station as quality records and for subsequent receipt inspection functions.
During the procure =ent document preparation and review cycle, technical or quality changes or revisions to the procurement documents are subject to the g, same review and approval requirements as the original documents. Procurement of spare and replace =ent parts will be subject to the controls of the OQAP.
-- The procurement of spare and replacement parts which affect-design' bases, safety evaluation,. regulatory conformance, functional design, structural . . g v ,. _
integrity and testing requirements require technical and quality review and documented approval. .53 17.2.4.3 Selection of Procurement Sources TNSD-QA has the assigned responsibility to generate and maintain an Approved Vendors List (A7L) which identifies those vendors able to meet NHY l require =ents for a given scope of supply. 63
~~'
- a. I A documented evaluation of the vendor provides objective evidence of the approval based on one or more of the following:
(1) Historical data representative of cu'rrent capability.
(2) Status of the vendor's current quality program - review of the procedures, QA manual, audits, and associa'ted activities.
(3) Review of objective evidence which de=onstrates adequacy of vendor's QA program.
- b. The vendor holds a valid ASME Nuclear Certificate of Authorization. The vendor:may be considered an Approved Vendor for the ites/ service covered by the certificate.
- c. The vendor holds an NRC-LCVIP letter confirming QA Program
- implementation. The letter shall be identified in the AVL entry.
- d. The vendor is approved by a utility with which YAEC or NHY has a reciprocal agreement or other recognized activity. [
$3 ^
17.2-22
- s .
." SB 1 & 2 Amendment FSAR March 1986 Evaluations are documented and provide objective evidence of the approval basis.
'. Appropriate NHY departments maintain a current copy of the AVL for procurement 84*
source infor=ation. Seabrook Staff personnel may delete or request addition of vendors as experience dictates. The Nuclear Quality Manager maintains cognizance of the YNSD activities and is ultimately responsible for. the evaluation and selection of procurement sources.c Additionally, the NQG may perform evaluations off selected vendors as required. 53 56 17.2.4.4 Bid Evaluation and Award Bid evaluations .cre performed by the requisitioning organisation to assure that the bids received conform to the procurement document requirements.
Personnel, appropriately trained in the technical and quality disciplines are used as needed, to complet,e the evaluation, consisting of, as applicable: S3
'a. Technical considerations. - ~ ,-
- %s- . t .s, #' s . . . -
- b. Quality Assurance requirements.
- c. Supplier capability and perfor=ance record.
- d. Alternatives / exceptions to the procurement ' document requirements.
Any una.cceptable conditions resulting from the bid evaluation are resolved or an appropriate co=mitment is obtained from the vendor prior to contract award.
17.2'.4.5 Surveillance, Inspection and -Audit During the technical and quality reviews [ the scope of vendor verification activities is determined. This determination is based on the complexity, safety significance, quantity of the item and supplier historical quality 5(>
performance. This determination results in an assignment of activities for which source and site surveillance, inspection or audit is deemed necessary.
The source surveillance, inspection and audit functions may be delegated to .
YNSD-QA upon written notification from the Nuclear Quality Manager. Receipt inspection activities are delegated to the Station Staff as described in 53 Section 17.2.7.3. 66 G
17.2-23
. l
~., '
SB 1 & 2 Amendment FSAR March 1986 17.2.4.6 Acceptance Methods used to accept items are dependent on the scope of purchase and includ2 one or more of the following:
- a. Source verification
- b. Receipt Inspection
- c. Supplier Certificate of Conformance g.
- d. Post Installation Test 17.2.5 Procedures,* Instructions and Drawings 5 k
- 17.2.5.1 NHY l .s-
! NHY controls and performs. all activities, such as design, procurement and O operation, through a series of procedures, instructions, drawings and other
'docu~ ment 3NiicW define the methods for complying with the eighteen criteria -of l 10CFR50 Appendix B and -Regulatory Guide 1.33. -
s .-
The appropriate director is responsible for the preparation of procedures which define organizational relationships in a manner that assures compliance to the quality requirements delineated in the OQAP. Designated managers are responsible for preparing procedures consistent with NHY quality philosophy, j the OQAP, ,and their assigned work activities. 56 5.3
~
The Se'abrook Station departments prepare and maintain procedures for .
administ'rstive" control and technical support and the safe and efficient- e. ;.;-
l.. . operation of the Station. These procedures establish the system for off-site j interfaces, conduct of operations and operating status. . The procedures 53 provide instrugtions for performing agtivities in areas of Station administration, operations, refueling, maintenance," and other specialized
, technical support functions.
~
The Training Center Manager prepares and maintains procedur es necessary to -
provide instructions to administer and document the licensed training program and keep abreast of design changes which impact the use of the simulator.
The NHY Management Control provides procedures for accomplishing routine !
activities within the department which define the interfaces with other NHY N l departments that initiate procurement or contract documents. 53 Procedures, instructions and drawings contain applicable quantitative and [
qualitative acceptance criteria, as warranted, to enable determination of l satisfactory accomplishment of technical and quality requirements. 53 17.2-24 L
i SB 1 & 2 Am endment FSAR March 1986 !
l l
The quality review o f p rocedures include's: 1) a determination of the need for
, inspection, 2) identification o f inspection personne l, 3) identification o f the inspection requirements, methods, and acceptance criteria, and 4') docunen-tation of inspection results. I 30 Procedures require the timely preparation of as-built drawings and related l documentation which will accurately reflect the actual plant design. A s-4 builts are made available to s taff who need the information. The timeliness of the as-builts will be dependent upon the type of documents as established i
in accordance with approved p rocedures. If a s-b uilt drawjngs are not 63 available, eithe r interim o r final design gonfiguration docu=ents will be 4
available to St ation s taf f and Nuclear Qu ality s taf f prior to relying on the
' effected item to perfors its safety function.
33 17.2.5.2 YNSD YNSD nor:sily perfor=s various support services for NHY such as auditing, !
vendor evaluation, and certain licensing and engineering tasks as delegated by 53 55 N EY. Such activities.are p rescribed by doccuents appropriate to the _. -. c . c - ,
circu= stances and are internally reviewed .co assure ,the inclusion of g j qualitative and quantitative require =ents. The Nuclear Qu ality Gr oup I maintains cogni:ance o f the YNSD procedural-imple=entation through audit 53 J, activity described in 17.2.1.2.b.
- J' 17.2.5.3 Contractors 5#
Prior to per(orming work or inspection on safety related structures, systems or components, contractors (excep t those which work as an integral part of l NRY) are required to develop and sub=1t f or approval procedures which define "53 the scope and imple=entation o f the task. ' The pro'cedures reference applicable drawings, specifications, codes and s tandards, and include appropriate ecceptance criteria. The contractors are required 'to perform all work in accordance with the approved documents which also form a basis for monitoring and control of the activities assigne d.
17.2.6 Do cument co ntrol .
17.2.6.1 Sco o e -
(
The NHY doce ent control progra= applies to the issuance and control of i
documents which affect the quality of structures, systems and cocponents. lh e controlled documents include, but are not limited to the following:
! a. Operational (balit y Assuranc e , Pro'gra m.
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i
- b. Pr ocurement documents.
- c. Erswing s . -
3%
- 1 17.2 -25
h SB 1 & 2 Amendment FSAR March 1986
- d. Specifica tions.
- e. Administrative and operating procedures.
- f. Nonconformance reports.
- g. FSAR and Technical Specifications.
p .$b 17.2.6.2 Issuance c The review, approval and subsequent issue of documents is prescribed in procedures. The review and approval cycle includes a review to assure technical adequacy and inclusion of appropriate quality requirements prior to implementation.
S Similar review and approval controls are implemented by or' anizations which l perform work using documen,ts that pertain to Seabrook Station. 31*
17.2.6.3 control - , .-
The Seabrock Station Document Control Center (DCC) maintains a' system to identify and control the current revision of instructions, procedures, specifications, drawings and procurement docu=ents. As new or revised
_ _ documents are approved, DCC enters these into the system. The controlled distribution of new and revised documents is limited to those which are required for standard activities. Other documents are_ issued,on a request
,i basis. Thi,s system assures that the most current revision of a, document is available 'for'use at'the required locations. Where appropriate, procedures --
. . .;ihclude~ requirements to verify the revision status of documents. -- -- - --- .
17.2.6.4 Changes -
Procedures exist to ensure that changes to documents ar's reviewed and approved l by the same organizations that performed the initial review and approval or by 53 other qualified responsible organizations designated by NHY. , In either case, l the reviewing organizations have access to pertinent background information 53 upon which to base their review, and have an adequate understanding of the .
requirements and intent of the originsi document. This includes design and procurement document changes identified in other sections of the OQAP.
Documents that are made obsolate or are superseded as a result of changes are removed from the controlled distribution when replaced by the new revision. -
For those documents which are not on controlled distribution, the required verification of revision status prior to each use -results in purging outdated documents f rom the work areas. Audits of document control assure the proper implementation and control.
- Station procedures are reviewed by an individual knowledgeable in the proce-dure every two years to determine if changes are necessary or desirable.
Reviews are documented and are at least as rigorous as the initial procedure
~ review.
17.2-26
. _ , . , . _ __ _ - . _ ~ ~ _ _ . ___ _ - - - - _ , , - _ . ___ _. __ _ - -
SB 1 & 2 Amendment FSAR March 1986 17.2.7 Control of Purchased Material, Equipment and Services 17.2.7.1 Planning NHY has the responsibility to implement appropriate measures to ensure that ,
purchased material, equipment and services conform to procurement documents. l Appropriate measures are described in 17.2.4 and may include source evaluation 53 and selection, source inspection, surveillance or, audit, or receipt inspec- e tion. During the review of procurement docucents, personnel, following written procedures and guidelines, identify those characteristics and/or Il' processes important to the quality of the item or service and specifies inspection, audit or surveillance activities commensurate with the procurement scope.
17.2.7.2 Source Activities Inspection, surveillance aN audit activities at the source are identified in accordance with the plan developed for procurement. - These activities are ---
normally performed by YNSD--QAD personnel. Qualified personnel perform the activities using written procedures / checklists and formally report to the Station Staff on their quality findings, including problem areas of the procurement. Personnel assigned these activities have the delegated authority .
to stop work if necessary. The Nuclear Quality Group maintains cogni:ance of l the activities of YNSD to assure proper implementation of source activities. I3
$b 17.2.7.3 . Receipt Inspection l
- $b Receipt inspection is performed by qualified Seabrook Staff members using pre- l planned written procedures / checklists which define those characteristics to be 60 -
inspected. Personnel performing receipt inspection vill be certified by the l Nuclear Quality Manager to Regulatory Guide 1.58 (ANSI N45.2.6). These 53 g
personnel verify that the items are undamaged, that they conform to procure-ment requirements when not verified by source surveillance, inspection or audit, and that the required docu=ertation is availablu Where sampling .
inspection is specified, the plan is based on nationally recognized standards or equivalent. NQG personnel perform random surveillance and audi's of lI receipt inspection activities.
- 50 17.2.7.4 Documentation Documented evidence that the items meet procurement requirements, nuch as receipt inspection reports, physical and : chemical test reports, and appro-priate documentation or certification, cust be available at the Station prior fI0 to piscing the af fected item into service which relies on it for a safety function. Written guidelines are used by the receipt inspection personnel to evaluate and accept the submitted documentation. Heasures exist to periodi-cally evaluate Certificates of Conformance to assure validity. l, 56 17.2-27
l
)
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S31&2 Amendment FSAR March 1986 17.2.7.5 Status The status of procurement action is maintained through reports and inspections at the source and upon receipt. The documentation submitted by Y3SD-QAD or the supplier, or that which was internally generated during the course of procurement and receipt, identifies the requirements that have and have not been met. For those items delivered which deviate from procurement requir,ements, a report describing the nonconforming item is prepared forTaggin track'ing and disposition.
is used to identify the inspection status of individual 1: ems or orders prior to assignment to controlled storage facilities or use in the Station.
17.2.8 Identification and Control of Materials, Pirts and Components 17.2.8.1 Identification v-Procurement documents cont.ain appropriate require:ents for identification of materials, parts and components. Compliance to the specific procurement '
requirements is the responsibility of the supplier. Seabrook Station . . ,m ., . g
~ ~ Ws'oMeTe~nsure, p if not already verified and documented during-source- 63 verification activities, that identification of items meets the procurement require =ents upon receipt. Station procedures covering the identification of items are prepared by the Station Staf f ard approved as noted in subsection .
17.2.6.2. Identification by physical means is maintained where possib1; and 53 through documentation when not physically practical. Jbterials, parts and
- components.are traceable to appropriata documentation, such as procurement or inspection documents.
17.'2.8.2' control ,
_. . J..T -- - ~ ~ --
l Subsequent to the receipt functiens at the Station, identification and control dIb of items is maintained in accordance with technical and administrative procedures. At storeroom issu:, an item is verified by the user for correct identification and acceptabilley. During the,various phaseslof fabrication, installation, repair or modification of items, in process surveillance may be -
performed by Station and ceatractor personnel to verify the continuity of identification. When an item is subdivided, traceability of the item, when .
required, is controlled by transcribing information to the subdivided pieces.
The identification markings are placed on the item or on records traceable to the item. If required identification is missing, obliterated or hidden, the item is considered ne aconforming and is tagged and, where practical, placed in a segregated ares pending resolution.
17.2.9 Contrel of Special Processes 17.2.9.1 Pro :ess Qualification Special proce;ses such as welding, heat treatment, nondestructive testing, chemical cle 2ning, plating, where the required level of quality cannot be, or is disadvan:ageous to be, measured by direct visual inspection, require gf.
17.2-28
' ' - SB 1 & 2 Amendment FSAR March 1986 qualification. The Seabrook Staf f has the responsibility to qualify special processes, equipment, and personnel, as appropriate, in accordance with approved procedures to assure subsequent accomplishment under controlled conditions in accordance with applicable codes, standards and specifica-tio ns . Process, equipment, and personnel qualification records are maintained and updated as required. For special processes not covered by existing codes or standards, the qualification criteria is defined and documented. The Nuclear Quality. Group perforSs reviews and surveillances of special processes. E r
Qualification includes allowable control parameters of the process variables, specified equipment and personnel proficiency which are documented in special process procedures and approved as noted in Subsection 17.2.6.2 and reviewed by the Nuclear Quality Group. Special process procedures contain the neces-sary prerequisites, personnel and equipment requirements, qualification data, limitations, acceptance criteria, results interpretation and records, as applicable. When special processes are to be performed by vendors / subcontractors on(site, prior approval of their procedures by the Station Staf f and review by the Nuclear Quality Grcup is required to assure I conformance to applicable' specifications codes and standards. Provision for SS . , , .,
approval is defined in the procurecent documents. .. ,. .
17.2.9.2 Personnel Qualification .,
l N'dY, YNSD and contractor personnel responsibic for the performance of special ,53 processes are qualified in s.ccordance with applicable codes, standards and specifica tions . Training and examinations are administered to determine the ,
capability, of each individual. Qualification records of on-site personnel -~
associated with special processes are established, filed and kept current. ---
The period of validity and criteria ~ for, requalification are in accordance with the applicable codes, specification and standards.
17.2.9.3 Process Performance ,
Special processes are accomplished using written pr'o' cess sheets, procedures, checklists, travelers or equivalent. These documents provide for recording of ,,
evidence to indicate acceptance in accordance with the process requirements. -
Acceptance of the results is performed by personnel qualified for acceptance of the special process. Records which verify that the required activities were accomplished in accordance with qualified procedures and by qualified 6
personnel are maintained and filed.
17.2.10 Inspection :
17.2.10.1 Ceneral Inspections associated with normal operations of the plant, such as Nl maintenance, surveillance, and tests, are performed by the Nuclear Quality Group unless delegated to another organization. Inspectors are trained and 53 17.2-29 l
)
o SB 1 & 2 Amendment FSAR March 1986 certified to meet the requirements of ANSI N45.2.6 by the Nuclear Quality Manager prior to performing inspections. Personnel performing nondestructive j examination are certified to SNT-TC-1A. The responsibility of inspectors is 63 defined in appropriate procedures.
17.2.10.2 Technica1 ' Specification Surveillance Tests 56 The Station Manager directs the preparation of Technical Specification . p Surveillance tests. The program requires that surveillance be performed to 53 assure that the station equipment operates in accordance with documented procedures, Technical Specifications, FSAR and OQAP requirements. The original- and subsequent revisions of the Technical Specification surveillance procedures require review by SORC and approval of the Station Man 33er. The Nuclear Quality Group performs surveillances of technical specification tests.
17.2.10.3 Maintenanceand Modification Inspection Maintenance, modification [ repair or replacement activities are inspected in accordance with the original ~ inspection-requirements or engineering approved ., m , m
" ** r"Mternatives. Documents which provide instructions .fon performing the activities specify the inspection requirements and are reviewed by the Nuclear .
N Quality Group. Inspection hold points are designated in the procedures or other documents when deemed necessary to inspect the quality of the ites.
53 6 17.2.10.4 kaceipt Insreetion 6b The scope of this inspection activity is described in Subsection 17.2.7.3.
~17.2.10.5
- ~
Inservice Inspection ,
Base line data from Preservice Inspection (PSI) is collected during Station '
construction. This data is used as comparative standards during periodic Inservice Inspections (ISI) as required by Technical Specifications, ASME Section XI " Rules for Inservice Inspection of Nuclear Power Plant Components" and Station procedures. The development of the overall program for inspection is assigned to YNSD, while implementation rests with the Seabrook Staff. N Records of PSI /ISI activities are maintained and. used for comparison with the ,
results of subsequent inspections. h 17.2.10.6 Contractor and Vendor Inspections The Seabrook Staff assures that inspection requirements are included as necessary in procurement documents which. apply to contractors on-site and to vendors at their facilities [ including s'ervice agencies such as nondestructive examination (NDE) specialists].
17.2-30 1
5 .
- SB 1 & 2 Anendment FSAR March 1986 17.2.10.7 Qualification of Personnel gg, The organization responsible for work at Seabrook Station normally performs the verification to assure their own quality. The personnel performing verification have the necessary qualifications and are independent of the supervisor directly responsible for performing the work being verified. ff Personnel requiring special training are trained and qualified in accordance with the applicable documents covering the function. The training is accomplished and documented in accordance with station procedures or approved suppliers procedures. Reevaluation of personnel is performed at periodic intervals.
The Nuclear Quality Manager is responsible for the review and acceptance of inspection procedures and for personnel qualification criteria for NQG personnel. p 17.2.10.8 InspectionDo[uments Inspection procedures', instructions 4and checklists used by personnel su performing inspection : functions include the f ollowing, as necessary: -- scav.h.ur --
- a. Identification of characteristics to be inspected.
- b. Description of the method of inspection.
- c. . Identification of individuals or groups responsible for performing
, the inspection.
,,d. Acceptance and rejection criteria.
- e. ' Identification of inspection hold points. .
- f. Requirements for indirect control by monito' ring process methods, equipment and personnel, if direct insp'ection is .not possible.
Both inspection and process monitoring shall be provided when inadequate without both. .
- g. Identification of the inspector or data recorder and the results of the inspection operation.
- h. Specifying necessary measuring and test equipment, including accuracy requirements. .
- 1. Identification of required procedures, drawings and specifications, including revision status.
Sampling techniques, if used[ are based on recognized standards, and justifi-cation is provided for sample size and selection process.
17.2-31
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- SB 1 & 2 Amendment FSAR March 1986 17.2.10.9 Results/ Records Inspection results are documented and traceable to the item inspected. The responsible individual, or a group qualified in the inspection technique, evaluates the acceptability of the results. Inspection records are annotated with any deviations encountered and, if necessary, subsequent corrective cetion.
c 17.2.11 Test Control p 17.2.11.1 Types of Tests The Station Manager is responsible for the conduct of testing pertinent to the operation of Seabrook, such as:
Start-up Tests: 3 Precriticality' tests, criticality tests, low power tests and power ascension tests performed < af ter-initial fuel loading and af ter
' ' - ' ' - each refueling. ~ . ..m - .,..s.v..--
NOTE: During the , preoperational . phase", the Joint Test Group (JTC) supervises, reviews and approves procedures and practices of the preoperational testing activities. A member of the Seabrook Staff serves as a permanent member of the JTG. An alternate is appointed for each permanent member. The JTG exists until the completion and approval of all preopera-
~
tional testing.
~ ^ ~
$b Technical Specification Surveillance Tests: ,
Periodic tests performed on Station systems. and components to verify system and/or equipment operabil,1ty requirements.
63 Modification Tests: .
Tests performed on structures, systems and components by the .
Seabrook Staff or contractors after modification to assure compliance to operating requirements, codes and standards prior to returning the ~ system to service.
17.2.11.2 Test Procedures ,
Start-up, Technical Specification surveiflance' and modifications test procedures are reviewed by SORC and approved by the Station Manager (see Note 63 in Subsection 17.2.11.1). In the case of contractor involvement, test procedures are submitted for approval as required by procurement documents.
Any proposed test or experiment which involves an unreviewed safety question, as defined in 10CFR50.59, is reviewed by SORC and NSARC.
17.2-32
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' SB 1 & 2 Amendment FSAR Natch 1986 l
l Test procedures contain or provide the following, as required:
- a. Prerequisites such as environmental conditions, and test instrumentation requirements and accuracy.
- b. Provision for assuring that test prerequisites have been set.
- c. Instructions for performing the test. c
- d. Incorporation or reference to appropriate requirements and acceptance limits contained in the applicable design and procurement documents.
- e. Acceptance or rejection criteria. 3 (,
- f. Inspection hold points, where applicable. g
- g. Methods of do$umenting or recording test data and results.
17.2.11.3 conduct of Tests /Results .,_ s -. , ..
Tests are performed by suitably trained", qualified or licensed personnel according to the written procedures. Test abnor=alities discovered during testing are resolved before structures, systems or components are required to 63 perform an intended safety function. Results of testing are documented and evaluated f,or acceptability by qualified personnel to assure that test requirements have been satisfactorily completed. Documented test results are retained fer record. .
17.2.12 control of Measuring and Test
- Equipment .
17.2.12.1 ~ Measuring *and Test Equipment Lists ,
Lists of measuring and test equipment required for Station testing, 11 operations, maintenance, and modification are prepared by the Seabrook Staff. ;fr
.'u $$
Each list identifies the type of measuring and test equipment, corresponding .'
identification numbers, and other information pertinent to control and calibration activities. No rmal commercial items such as rulers, tapes and levels are excluded from the lists. The list approval, revision, addition or deletion requirements are procedurally controlled. The procedures are reviewed by the Nuclear Quality Group and regular surveillance and audits of the calibration pr'ogram are conducted to, assure the effectiveness of the program. 3(g 17.2-33
i .SB 1 & 2 Amendment FSAR March 1986 17.2.12.2 Identification Each item on the measuring and test equipment lists is assigned a unique designation to assure positive control. The designation is permanently af fixed to the item in a manner to af ford proper identification without interfering with the item's function. Tags, labels and records traceable to the ites, or other identifying means, document the calibration status of each item. A schedule is maintained which provides positive recall when recalibration is required and indicates che current status of all items.
17.2.12.3 Calibration Calibration is based on the manufacturer's recommended interval, however, the required accuracy, purpose, degree of usage, stability characteristics and other conditions affecting measurement may modify the frequency. Calib ration activities are also initiated when the accuracy of an item is suspect.
Procedures, identify the recommended calibration interval, calibration
~#~~ techniques, required tools and standards, methods to' document and evaluate the
~
results and required record maintenance. ., Primary standards have an accuracy of at least four times the required accuracy of the end use equipment being calib ra ted. Less accurate standards may be acceptable when the use of such .
standards and the basis of calibration acceptance is authorized and gj!
documented.
17.2.12.4 , S ta nda rd s
~
Standards used for calibration purposes within the program are traceable to
_ _. nationally recognized standards such as the National Bureau of Standards .
(NBS). Where national standards do not exist, the standard used for calibration is justified and documented. Primary calibrating standards have greater accuracy than the secondary standards being calibrated, unless 63 authorized and documented for specific use. ,
17.2.12.5 ' Control . ,
Neasuring and test equipment, including instruments", tools', gages, fixtures, .
reference and secondary standards and non-destructive test equipment, that is used in the measurement, inspection, testing and monitoring of structures, ,
systems and components is traceable to that activity. To control and document df3 the use of measuring and test equipment, the issue records or inspection / test documents contain appropriate informatio.n to identify the unique measuring and test equipment, calibration status, dates used, and specify the activity for which the ites was used.
Through this technique, the validity of inspection or tests that utilized defective measuring and test equipment can be determined and documented. l Reinspection or retest may be performed depending upon disposition of the 63 j
defective item. All records of calibration and control activities are 53 maintained as required.
17.2-34
1 1 -
SB 1 & 2 Amendment
- FSAR March 1986 a
17.2.13 Handling, Storage and Shipping 17.2.13.1 Procurement Provisions Requirements. for special handling and storage, including cleaning, preservation, packaging and shipment of. materials, spare parts and equipment cre conditions of procurement documents, as applicable. Shipping requirements concerning ths shipment method, container cleanliness, pressurization, dessication, labelling and others, are specified and reviewed during the procurement process. When requested, the supplier prepares written procedures which specify handling, shipping and storage processes, and subnits them to the Seabrook Staff and the Nuclear Quality Group for revieu and approval.
S3 Source inspection by YNSD-QAD or NHY-NQG, personnel may be employed to assure l proper implementation of supplier activities. jf6 17.2.13.2 Receipt and Storage
- 1"'#"'Upon delivery of items to the Station, receiving + activities commence. -The receiving actions are documented by procedure, and require receipt inspection _
of. the special provisions incorporated by suppliers to control cleanliness, labelling, marking, shipping characteristics, or other appropriate charac-teristics identified in the procure =ent process. The receipt inspection is k docu=ented and the item is assigned a storage location. Locations are 66 established with regard to environmental conditions and limitations, clean-liness, physical restrictions, handling requirements, manufacturers recommenda,tions, and other pertinent data applicable to the item.
.. .. Items'*whichisq6 ire preventive maintenance, special protective environments, special coverings or other particular activities to maintain and preserve the item in storage, are controlled and inspected through documented procedures.
Procedures for the storage and control of consumable materials, such as chemicals, reagents, lubricants and film, are provided to assure proper identification and use with regard for special environmental conditions 'and .
-shelf-life considerations. .
The Nuclear Quality Group conducts audits and surveillances of receipt .
inspection and storage activities. g3 56 17.2.13.3 Handling Detailed handling procedures and instructions are prepared for items that require special handling due to factors ;such as weight, size, susceptibility to shock and other conditions which warrant special controls. Station procedures require the use of special handling procedures and instructions when required. . Special handling equipment and tools are maintained, inspected and documented, at intervals consistent with their application to assure their availability for use.
17.2-35
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' SB 1 & 2 Amendment
- FSAR March 1986 17.2.13.4 Packaging and Shipping Packaging and shipping activities originating on-site are controlled by administrative procedures. Packaging requirements are divided into classification levels dependent upon the sensitivity of the item, transportation mode, ites destination and other factors which may affect the integrity and function of,the item. Items returned to a supplier are returned in the original container, when possible, or repackaged to equivalent stfndard s. Shipping requirements which are consistent with the required mode of protection are specified. For special nuclear material and sources, shipping is performed in accordance with the NRC and DOT regulations.
5.3 17.2.13.5 Personnel Personnel responsible for any phase of receiving, storage, handling, packaging I or shipment of items are suitably trained to assure proper implementation of db the specified activities and controls.
~* " "' "" 17 . 2 .14 Inspectioni Test and Ocerating 'Statuswet-a-
~..- w. n..
17.2.14.1 Status Indicators Theoperatingstatusofstructures[systemsandcomponentsduringstation operation, maintenance, testing and modification is indicated by devices such
.as tags, stamps or markings. These devices .are identified, described and controlled through administrative procedures. Inoperative or malfunctioning *
, ,,_,,,; items are also documented and highlighted through the use of various devices to prevent inadvertent use. The responsibility for application and removal of
- ^ ~ tags, stamps and other status indicators ~is defined to assure positive control and to preclude inadvertant operation. -
'The test and inspection status of items is indicated by, devices such as ,
documentation, tags, stamps, or markings. .
Nonconforming items are also ' documented and highligh'ted throush the use of various devices to prevent inadvertent use.
17.2.14.2 Sequence of Operations, Tests, inspections and operations are controlled by documented procedures.
Any alteration of the intent of a planned sequence is subject to the same review and approval controls as applied t,o the original. The authority and responsibility of personnel .and methods .to re-sequence actions are f'.3 procedurally stated. Tests, inspections or other operations which are bypassed are properly documented and the ef fect of bypassing is evaluated and approved by the organization responsible for s:ecifying the test, inspection, or operation.
l I
17.2-36
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- SB1&2 Amendment
- FSAR March 1986 17.2.15 Nonconforning Materials, Parts or Components 17.2.15.1 Identification and Control Materials, parts or components, which are deficient'in characteristic, documentation or procedure which render the quality unacceptable or indeterminate are identified as nonconformances. The Superviso- of a technical area or activity that is within the scope of the OQAP is responsible for documenting the nonconformance in accordance with establish.:d procedures, and assuring proper control to prevent inadvertent use or installation.
Controls may include marking, tagging or physical segregation. Affected organizations are notified of the nonconfor=ance and subsequent actions taken through distribution of a report describing the nonconforming item.
53 17.2.15.2 Disposition and Resolution The Station Manager is reshbnsible for assignment of technically qualified personnel to evaluate the extent and impact of the nonconformance to determine
'*"s~ disposition fo r the ites; (i.e., repair, rework,- scrap or use-as-is) and to
^" **take *a~pp'ropria te action, when nee 2 ssary, to prevent recurrence. --For-nonconformances involving repair or use-as-is dispositions, procedures specify
.the organi:stion responsible for the performance of an engineering review function. All dispositions are documented and signed by responsible parties.
53 Acceptability of rework or repair of material parts and components is verified
' by qualified personnel reinspecting or retesting the item as originally
.specified or by alternate means approved for the application.
~~~ teeS't'a' tion Manager is responsible to administer the nonconfor=ance reporting system. The Nuclear Quality Group reviews and concurs in each report of a nonconforming ites to verify that the deficiency was properly and. correctly ,
stated, that the disposition and corrective action are acceptable, and to assess the effectiveness of the steps to prevent recurrence. .
JI3 17.2.15.3_ Trend Analysis , ,
The Nuclear Quality Manager maintains a system to recognize" evaluate,
.I document, and assess quality trends. The systes provides for periodic ff3 analysis of reports on nonconforming items, inspection, surveillance and audit '
reports, and the submittal of significant results to the Vice President and db Director of Quality Programs for review and appropriate action. 63 17.2.16 Corrective' Action :
17.2.16.1 Initiation Corrective action is that action taken to identify, correct and preclude recurrence of conditions adverse to the quality of activities or equipment.
NHY programs identify those conditions for which corrective action may be l warranted including:
17.2-37 w -
-o e .
a r * .
- a. Failure of a structure, system or component that is within the scope of the OQAP. g3
- b. Defect of an item or service that could, if uncorrected, lead to failure or malfunction.
- c. Operation outside of specified limits.
9
- d. Repetitive minor problems which may be symptomatic of' a larger problem.
- e. Reportable occurrences as defined by the Technical Specification.
Loss or apparent loss of special nuclear material (SNM).
~
f.
- g. Significant conditions identified by the NRC, SORC, NSARC or audit l .
program. ,
6(,
~ ~~~*"NC6rre'c'tive action is nor= ally documented through appropriaterprocedures. In the case of significant condition's' adverse to safety, the corrective action -
a .uu includes an evaluation of the cause of the condition, the recommended action to prevent or reduce the probability of recarrence, and verification of ..
completion of corrective action. A special report may be prepared Vhen a significant condition adverse to safety is identified. This' report identifies root causes and documents action taken to preclude recurrence.
~
17.2.16.2 , Assessment Procedures require that c'orrective action associated with nonconformance 60 reports, and other special corrective action reports are reviewed for adequacy '
i and timeliness. The Nuclear Quality Manager periodically reports to the Vice President and Director Quality Programs on the effectiveness of the corrective action process and status of incomplete items. Corrective "
action reporting is dN
' included in the trend analysis program. ,
17.2.17 Quality Assurance Records .
17.2.17.1 , Identification The Nuclear Quality Manager and other cognizant managers have the joint responsibility for determining and identifying quality assurance records that 53 are to be retained and their retention period. Examples of the types of records ' retained include procurement documents, procedures, NDE results; inspection, audit and test results; material analyses; equipoent, process and personnel qualifications; calibration records, nonconformances and corrective action results and station operating records. Inspection and test records, where applicable, identify the inspector or data recorder, type of observa- 5.l0 -
tion, results', acceptability of the results, date, and action taken in l, Sb 17.2-38
e
- e ., .
S*.
(" SB 1 & 2 Amendnent .
e- FSAR March.1986 e.
connection with any deficiencies noted. The compilation of records generated
. is forwarded to the Document Control Center for inclusion into the Station records management system. The system is compatible with the design and construction phase records system. 63 17.2.17.2 Receipt, Storage and Retrieval Station procedures identify the respon!!ilbility of personnel and actions required.to control thefreceipt, storage and retrieval of quality assurance records. ' A suitable storage facility,. designed to prevent loss or deterioration of quality assurance records, is permanently located on-site.
Records, whether original or copies, are indexed, filed and maintained to aid in the retrieval process.
17.2.17.3 Supplier Records Principal. suppliers, their sub-tier suppliers and other suppliers are required to -identify quality assurance records generated throughout the life of the
~~ "#cWi&Yet~in accordance with the appropriate provisions -of 2theeMIT procurement l
- * ~MWotid:: rent's . The suppliers are required to maintain a-record-Jiystem and, upon 63 completion of the contract, either continue maintaining the records or forward
'- them to NRY for incorporation into the hTl records management system. l Internal procedures identify the receipt, inspection and transmittal 63
. activities and responsibilities associated with supplier records.
17.2.18 . Audits
, 17.2.18.1- Planning The Nuclear Quality Manager is responsible for development and management of an audit program pertaining to activities associated with operation and . 33 operational support at Seabrook Station. Formal reports are distributed by ,
the Nuclear Quality Manager to other management positions as required by _. ,
established procedures. A plan, which identifies the' audits to be performed ,
and their frequency, is appro~ed by the Nuclear Quality Manager. The audit, .
plan is based on the status and safety significance of activities being jd
. performed and ensures that an audit of all functions is completed within a two-year period. Audits of certain activities such as staff training and ..
qualification, and conformance to technical specifications have specific minimum frequencies. These are identified and included in the plan which is updated semiannually. Additional audits may be scheduled v'nen conditions warrant, i.e., extensive reorganization, guality becomes suspect, or supplier implementation of the QA program is suspect.
17.2.18.2 Performance Audits, based on the pre-established schedule, are performed by trained and qualified personnel using appropriate procedures, instructions and checklists. The procedures, instructions and checklists provide a basis for 17.2-39
o * . .
4 Y. ** s
. SB 1 & 2 Amendment FSAR March 1986
~{
. performance of audits including pre-audit and post-audit conferences and the -
mechanics of the audit process. The mechanics of the process include an objective evaluation of practices, procedures, instructions; activities and items; and review of documents and records to determine the extent that the quality assurance program is effective and is properly implemented. Auditors do not have direct responsibility in the area being audited. Their qualifications, as a minimum, are based on prior pertinent experience, specialized training and education in accordance with applicable procedures. ,
The audits conducted onsite are performed under the direction of the NQ Audit I ar.d Evaluation Supervisor. In addition the NSARC may request audits, which L may be performed by the Nuclear Quality Group or YAEC, or contracted to 6k outside professionals.
54 1
The NQG will perform independent' audits under the direction of the NSARC. The l audits will be conducted in accordance with the technical specifications and
. may involve contracting o,utside professionals.
$h 17.2.18.3 Reporting ahd Follow-Up An'~dddit report is. genera,ted a.t_the completion of each aOSit'and'subnitted to ,
the audited manager of the'lunctional area, the Nuclear Quality Manager and to i other appropriate management personnel. NSARC also receives a copy or summary 56 i
report for their review and assessment of the audit program. Follow-up is required by.both the audited and auditing organizations when deficiencies are identified. The audited organization is responsible to review and investigate the nature and cause of the deficiency and to provide appropriate corrective action. The Nuclear Quality Manager is responsible for evaluation of proposed ,
- ~ ~-or-completed corrective action and confirmation of satisfactory,..... 54 accomplishment. -. ,
~17.2.18.4 Au'dit Program Review . ,
An independent audit of the QA program effectiveness'and appropriateness is .
initiated biennial by NSARC in accordance with Technical Specifications.
, 6l-
- ew . ' .
9 9
17.2-40
. ~...-
a o- u 4
'( Amendment SB 1 & 2 FSAR March 1986 i
- set forth in the Operational Quality Assurance Program; and, (4) will be complied with, as stated, by individual technicians as part of the maintenance / modification process.
- b. With regard to Section 4 of ANSI N45.2.4 - 1972 titled Installation: Will be implemented by inclusion, as necessary, in the appropriate maintenance or modification procedure, where such procedures are used. Standard NHY maintenance practices require that care be exercised in the six areas listed whether a procedure 33 is required or not.
- c. With regard to Section 6.2.1 of ANSI N45.2.4 - 1972 titled Equipment Tests: . The last paragraph of this Section deals with tagging and labeling. NHY will co= ply with an alternate last paragraph which reads: "Each safety-related item of process instrumentation is identified with a unique number. This number is utili ed in 53 instrument maintenance records so that current calibration status, including data .such as the date of the calibration and the person
' "' " performing the calibration, can be readily determined. Such information may also be contained on tags or labels which 'may be -
attached to installed instrumentation." - -
Regulatory Guide 1.33 Quality Assurance Program Requirements (Rev. 2, 2/78) (Ocerations).
Endorses ANSI N18.7 - 1976/ANS 3.2 During the Operational phase, the Operational Quality Assurance Program
includes and complies with this guide with the following clarificition:
- a. Paragraph C.S.a of Regulatory Guide 1.33 (and Section 4.4 of ANSI N18.7 which it references) will be i=plemented with the '
clarification that " periodically" (as used in the second paragraph, first sentence) shall not require a set frequency, and " documented"
_ (as used in the second paragraph, second sentence). shall not require typed minutes, but may mean hand written notes or. memoranda.
- b. Paragraph C.S.d of Regulatory Guide 1.33 (and Section 5.2.7.1 of ANSI Nid.7 which it references) will be implemented by adding the
' clarifying phrase "Where practicable" in front of the fourth sentence of the fifth paragraph. The Regulatory Guide's changing of the two uses of the word "should" in this sentence to "shall" unnecessarily restricts NHY's: options on repair or replacement parts. It is not always prac'ticable to test parts prior to use. 33 17A-3
(
'. rO .
N'" c I SB 1 & 2 Amendment 9' FSAR March 1986
-- clarificaticas taken to other Sections which are referenced therein, if shipmenta are f rom NMY to another nuclear facility.
Alternatively, since N1Y will not normally be a " shipper", NRY might be subje:t to the requirements of this Section for shipments f rom
.Seabrock to another nuclear facility. Seabrook, when involved in such shipments, will comply with the requirements imposed by the receiving plant in their procurement document covering the shipment.
- h. With regard to Section 5C2.1 of ANSI N45.2.2 - 1972 titled Shipoing E2 mage Inspection: Warehouse personnel will normally visually
' scrutinize incoming shipments for damage of the types listed in this I Section; this activity may not be perfor=ed prior to unloading. The person performing an inspection function as defined under Regulatory Guide 1.74; therefore, while he will be trained to perform this function, he may not be certified (N45.2.6) as an Inspector.
- 1. With regard to Section 5.2.2 - Ices Inspection: In lieu of the requirement that "Ihe inspections shall be perfor=ed in an area equivalent to the level of storage requirements for the item", NRY
-than--ourform receipt inspections in a manner and in an environment '-
. which.does -not endanger the requisite quality of the item. Receipt- ina - - - -
inspection area environmental controls, however, may be less 56 stringent than storage environ = ental controls for that item. -This deter =ination shall be docu=ented and approved by an engineering {
g roup . Quality Assurance will review procedures to assure proper I controls are incorporated. When inspections are performed in receipt inspection areas with environmental controls less stringent than storage area environ = ental controls, a time limit shall be .l6 5
established on a case basis for retention of items in the receipt inspection area. Ratention time shall be'such that deterioratio'n is ~i prevented and applicable manufacturer recommendations are addressed. .-56 This approach is justified since receipt inspection activities are .:
for a much shorter duration and therefore should not be subjected to - . ~
the same stringent requirements as required for storage. -
.t. '
- j. With regard to Section 5.2.3 - Special Inspection: NHY takes ,
exception to the requirement that "Special Inspection" procedures .
shall be attached to the ites. The "Special Inspection" procedure shall be readily available to inspection personnel and may be attached to the item or containers. The procedure being used will be traceable to the item or lot. -
.k._ With regard to Section 6.1.2 (;l) of ANSI N45.2.2 - 1972:
Temperature and humidity controls. required for the storage of Level A i,tems are not considered applicable for nuclear fuel assemblies unless recommended otherwise by the nuclear fuel manufacturer. NHY will abide by the manufacturer's recommendation. See remarks under Section 3.2.1 'above.
. ty, 53 .
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