ML18038A190

Forwards Changes to FSAR Re Dual Role of Assistant Station Shift Supervisor & Shift Technical Advisor,Organizational Changes & Changes to Training Procedures.Changes Will Be Included in Subsequent FSAR Amend

ML18038A190
Person / Time
Site:	Nine Mile Point
Issue date:	07/24/1986
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	Adensam E Office of Nuclear Reactor Regulation
References
(NMP2L-0795), (NMP2L-795), NUDOCS 8608010196
Download: ML18038A190 (290)

Text

REQUL'Y INFORi'lATION DIBTRIBUT BYBTEN (RIDB)

,~ACCESSION NBR: 860801019'6 DOC. DATE: 86/07/24 NOTARIZED: YEB DOCKET I FACIL: 50-410 Nine Nile Point'uclear Station> Unit 2> Niagara Noha 05000410 AUTH. NAl'iE AUTHOR AFFXLIAT ION NANQAN> C. V. Niagara Mohawk Power Corp.

RECIP. NANE RECIPIENT AFFILIATION ADENSAN> E. l . BNR Pro J ect Directorate 3 g~c~

Fortoards changes to FSAR re dual role oi'- assistant station 5'UBJECT:

shift supervisor shift technical advisor> organizational changes to training procedures. Changes gi ll be 8<

changes Zc included in subsequent FSAR amend.

DISTRIBUTION CODE: B001D COPXES RECEIVED: LTR ENCL SIZE:

TXTLE: Licensing Submittal: PSAR/FSAR Amdts Zc Related Correspondence

't NOTES:

RECIP lENT I COP EB REC IP I ENT COP IEB ID CODE/NAl'lE LTTR ENCL ID CODE/NAilE LTTR ENCL BNR EB 1 1 BWR EICSB 2 2 BNR FQB 1 BNR PD3 LA BNR PD3 PD 1 1 HAUQHEY>l'l 01 2 2 BNR PBB 1 BAR RBB i.

INTERNAL: ACRS 41 6 6 *D}'I/LFNB 0 ELD/HDS3 0 IE FILE XE/DEPER/EPB 36 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 0 NRR PWR-B ADTS 0 FIL L 1 NRR/DHFT/NTB t

1 1 i REC 04 RQNi R l']I/NXB 1 0 EXTERNAL: BNL<Al'lDTB ONLY) 1 1 DNB/DSS (ANDTB) 1 1 LPDR 03 1 NRC PDR 02 1 1 NSIC 05 1 PNL GRUEL> R 1 TOTAL NUMBER OF COPIES REGUIRED: LTTR 36 ENCL 31

fl It> r!I '!',

l l 0 1 I I'

'l ">

~1 i ff" 'If N I iI Qf~

~f, tf" 2 E A, ff r1 f 1 I 'I ~ ~ l 1 I

I

'I

'Q.I Ifr f ge, I

f.l r .- ~ ~ 1'

l. I,l g

I 1"l ~ - l l t

~ I P

) '"" Q'f.>j fl[ j!I-. -, ~

'f > g ft >

) l I, f'l t l, ~

l III, 'I off,;(, .

1 tf

>,>f f'r~ I f'I I l.fi> >l f 1 I I'I ll I,

"1 l 4 "1 Pfg'/ f> l tt'

"$ / ' I

.f fi J t

NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 July 24, 1986 (NMP2L 0795)

Ms. Elinor G. Adensam, Director BWR Project Directorate No. 3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Washington, DC 20555

Dear Ms. Adensam:

Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are changes to the Final Safety A'nalysis Report. Attachment 1 includes changes concerning the dual role of the Assistant Station Shift Supervisor and Shift Technical Advisor. Attachment 2 includes changes resulting from Niagara Mohawk's reorganization and reflects the organization that will be in place after fuel load. Attachment 3 consists of changes resulting from new Nuclear Training Procedures.

Although changes in Attachments 2 and 3 cover a number of pages, they are not significant and do not involve a change in basic policy. The changes reflect a greater role of Niagara Mohawk management and the phasing out of the Management Analysis Company personnel.

These changes will be included in a subsequent Final Safety Analysis Report amendment.

Very truly yours, C. V. Manga Senior Vice President WB: ja 1867G Enclosures xc: W. A. Cook, NRC Resident Inspector Project File (2) 86080iQi96 860724 PDR *DOCK 050004i0 A PDR

~ ~

a I K 4

ii V

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In e Matter of Niagara Mohawk Power Corporation ) Docket No. 50-410 (Nine Mile Point Unit 2) )

AFF I DAVIT C. V. Man an , being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.

Subscribed and sworn to before me, a Notary+ublic in an for the State of New York and County of , this 2Y=:-" day of 1986.

Notary Public in and for County, New York My Conlmi s ~TigfQjgpp:

Hotaw PubUc in the State of Nae York QualPied In Onondaga Co. NL 47878g thy Commission Expues Match 30, laaZ

pl V.tTRA 3Qre'.HO PeY vali 1o ~~A cO ni o"dN qdvN TNT *H.N qcbno>0 td bs~tJ."u0

~.9f,OK thigh wvgx3 0:knur v0 y<i'I

ATTACHMENT 1 8608010196

Bine Rile Point Unit 2 tSAB TABLE 13 1-2 REACTOR OPERATZWG BODES (Wuaber of Personnel Required)

Operation WRPC Without Position Licensee Woraal Process EBRSil'BKIQi5 QRQRlhfKL %5I~ ~BR%1 $ 8iC~T QHP<<RX

• SSS SRO 1 1 ASSSCSA SROC+i 1C ~ >

Ireactor icea sad BO 1 2 operators (CSO/WAOE)

Anailiart 2/3 operators tire 5C el 5>>u) 5>> ~ ) 5Cu) 5c el brigade Badiatioa protection techniciaa Cheaistrt aad radiocheaistry technician Shift techaical 1>> ~ A 1 adaisor>> +A

<<1An SRO aho has no other concurrent responsibilities sill superTise all core alternations.

CaiTTo auxiliary operators are reguired np to 8 hr aithout the process coaputer; three auriliary operators are required after 8 hr aithout the process coaputer CTThat be other qualified staff position CiiSee Table 13 1-3 for further discussion of the ASSS and STl duties

>>I~Can include three aeabers froa the Unit 1 fire brigade, aaling the site fire brigade a total of seTen aeabers.

>> ~ iDuring a hot shutdoun condition, a dual ASSS/STA or an ASSS and STl are required. During a cold shutdoun condition, neither an ASSS or an STl is required.

1 of 1

0 Nine Mile Point Unit 2 FSAR TABLE 13.1-3 (Cont)

Su erintendent 0 erations Nuclear This Superintendent directs the functional conduct of shift operations and when required performs the duties. of the Station Shift Supervisor. He shall hold an NRC senior reactor operator's license for his station. In the absence of th'e Station Superintendent he is designated to act as Station Superintendent.

Assistant Su erintendent 0 erations Nuclear This Superintendent assists the Superintendent Operations Nuclear in the functional conduct of shift operations. He shall hold an NRC Senior Reactor Operators License. In the absence of the Superintendent Operations Nuclear he is designated to act in his behalf.

Station Shift Su ervisor SSS The Shift Supervisor is in charge of all operations on his assigned shift. Under the general direction of the Superintendent Operations Nuclear his function includes direction of shift activities, authorization of equipment releases for maintenance, ensuring that the plant is operated safely and within the license and technical specifications and ensuring that plant operations are conducted in accordance with approved procedures. As overall supervisor of operations for his shift, the Station Shift Supervisor should avoid becoming personally involved in the manipulative tasks or details of operation of any one portion of the plant so that he may retain a comprehensive perspective of general station conditions at all times. In an emergency situation, however, should the Shift Supervisor choose to perform manipulative functions to ensure that the plant is in a safe condition he shall coordinate his actions with the Chief Shift Operator. Whenever he determines that the safety of the reactor is in immediate jeopardy or when operating parameters exceed any of the reactor protection circuit set points and automatic shutdown should but does to not occur, he has the responsibility and the authority the order shutdown of the reactor, or to personally effect shutdown.

The Shift Supervisor shall hold a NRC senior reactor operator license. He shall be continuously present at the plant for the duration of his assigned shift until properly relieved by the oncoming Shift Supervisor. It is his 4 of 7

Nine Mile Point Unit 2 FSAR TABLE 13.1-3 (Cont)

Shift Technical Advisor The Shift Technical Advisor position normally will be combined with that of the Assistant Station Shift Supervisor. There may be some instances where a separate, dedicated Shift Technical Advisor will be utilized instead of a combined ASSS/STA. During off-normal events, the Shift Technical Advisor provides the Station Shift Supervisor with an assessment of station conditions and advises actions to terminate or mitigate the consequences of off-normal conditions.

Other erators The other operators at the station provide operational attendance to the station equipment on shift. Their duties shall include checking the rotating equipment, checking the operation of the screen-house, and handling the duties of the solid and liquid waste systems. They shall perform all operations with the concurrence of or at the direction of the Chief Shift Operator.

7 of 7

Nine Mile Point Unit 2 FSAR TABLE 13.1-4 (Cont)

Section of ANSI/ANS 3.1-1978 No. Site Containing Title Personnel alifications Respiratory Protection 4. 7.2 Coordinator Radiological Engineer 4.7.2 Assistant Station 16 4 3 1(1)

Shift Supervisor Nuclear Station Shift 16 4.3. 1 Supervisor Nuclear Shift Technical Advisor As needed (2)

(dedicated)

Chief Shift Operator 12 4.3.1 Nuclear Axuiliary 4.5.1 Operator E Superintendent Technical 4.2.4 Services Nuclear Supervisor Computer 4.7.2 Operations and Maintenance Nuclear Assistant Supervisor 4.7.2 Computer Operations and Maintenance Nuclear Supervisor Reactor 4.4.1 Analysis Unit Supervisor 4.4.1 Reactor Analysis Supervisor Instrument 4.4.2 and Control Nuclear Unit Supervisor 4.4.2 Instrument and Control Nuclear Supervisor Technical 4.7.1 Support Nuclear 3of5

Nine Mile Point Unit 2 FSAR TABLE 13.1-4 (Cont)

Section of ANSI/ANS 3.1-1978 No. Site Containing Title Personnel ualifications Planning Coordinator NA Nuclear Supervisor Office- Nuclear NA

• When one of these individuals temporarily fills the pos-ition of Superintendent Chemistry and Radiation Manage-ment, the individual will meet the qualifications of ANSI 3.1-1979 (draft), Section 4.4.4.

,'~'When the ASSS is functioning as STA, he also will meet the requirements for the STA.

'~'A bachelor's degree in a physical science or engin-eering, or a PE license issued by examination is

'equired.

5of5

ATTACHMENT 2

Nine Mile Point Unit 2 FSAR CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT The following sections describe the organizational structure of Niagara Mohawk Power Corporation (NMPC) and delineate the line of responsibility for the operation of Unit 2 in accordance with established administrative and quality standards. The organizational structure associated with the quality assurance program for plant operation is described in Section 17.2.

13.1.1 Management and Technical Support Organization 13.1.1.1 Design and Operating Responsibilities Design and construction activities:

Principal site-related work, such as meteorology, seismology, hydrology, demography, and environ-mental effects, has been completed and is descr'bed in Chapter 2. Postoperational environmental evaluations are described in the ER-OLS.

2. The design of the Unit 2 plant and auxiliary systems is described in Chapters 3 and 9.

3. The review and approval of plant des.'gn features were completed as an integral part of the design ,I review process.

4, Site layout with respect to environmental effects is described in Chapter 2. Section 13.6 discusses the security plan with respect to site layout.

5. Most of the FSAR was prepared through the combined efforts 'of NMPC, General Electric Company (GE), and Stone Ec Webster Engineering Corporation (SWEC).

Some portions were prepared by Dames and Moore, Lawler, Matusky, and Skelly, and Meteorological Evaluation Services.

13.1-1

Nine Mile Point Unit 2 FSAR

6. Management control and review of construction activities are currently and have 'been exercised routinely during construction of the plant.

13.1.1.2 Organizational Arrangement NHPC is a privately owned utility with over 20 yr experience in the operation, design, and construction of nuclear power plants. Figure 13.1-1 shows the corporate upper management and the functions of the senior vice presidents. The upper management organization is depicted on Figures 13.l-la and which show the corporation organizations responsible '3.1-2, for the nuclear generation program at NMPC. The Senior Vice President (Nuclear Generation, Engineering, and licensing) reports to the President and is responsible for nuclear operations, design, construction, project management, and other nuclear-related work. The Vice President, Quality Assurance reports to the President and is responsible for the quality assurance program. The Vice President functioned'he Nuclear Generation has responsibility for plant operations, maintenance, testing, and other operations Manager Nuclear,.Engineering and ficeneing hae responsibility for performing engi'neering analysis, design, licensing, and fuel design, services. Unit 2 is constructed close enough to Nine Mile Point Unit 1 to be connected by an enclosed passage. Therefore, the operation of Unit 2 will be under

) the same site management as Unit 1.

Nuclear Generation The Vice President Nuclear Generation has overall responsibility for the safe and reliable operation of Unite 1 and 2. The organization responsible for these activities is under the direct responsibility of the General Superintendent Nuclear Generation (Sections 13.1.2 and 13.1.3, and Figure 13.1-3). See Figure 14.2-6 for the 13.1-2

Nine Mile Point Unit 2 FSAR staffing levels of personnel assigned during preoperational testing and startup testing. See Figure 13.1-5b for the staffing levels of site personnel for Units 1 and 2.

Amendment 9 13.1-2a March 1984

Nine Mile Point Unit 2 FSAR Nuclear En ineerin and Licensin The Manager Nuclear Engineering and Licensing has overall responsibility for engineering services after commercial operation. The corporate engineering staff currently performs or controls the performance of design activities relating to modifications to Nine Mile Point Unit 1, and will support. Unit 2 in the same manner. Established Engineering Department procedures will be utilized for such activities. The Engineering and Licensing Department organization chart is provided on Figure 13.1-4.

The Manager Nuclear Engineering or his designee is the engineering contact for plant-to-engineering interfaces.

A number of engineers from ithis organization have actively engaged in technical aspects of the Unit 2 design. This organization presently consists of over 125 engineers and technical personnel with a variety of disciplines and backgrounds in power plant technology. The organization is expected to expand and add about 150 engineers and technical personnel. Support in plant chemistry, health physics, fueling and refueling operations, and maintenance support as required in nuclear, mechanical, structural, electrical, thermal-hydraulic, and instrument and control engineering are provided. During commercial operation, construction support will also be provided by this . organization.

Approximately 25 technical personnel will be used for this purpose. Specific headquarters support group descriptions are provided in Table 13.1-1. Qualifications of engineering support personnel are described in job descriptions.

Most design-related requests (after commercial operation) are relayed from the Station Superintendent through the Manager Nuclear Engineering, who assigns appropriate engineering support groups the design responsibility and/or hires a vendor or contractor to perform the work.

Conceptual designs are formulated and sent to the site for approval after engineering approval. Conceptual site approval is made by the Station Superintendent after review by the appropriate site discipline. Final design is provided by Engineering for review by the appropriate site discipline, the Station Superintendent, and Site Operations Review Committee (SORC), and is approved by the General Superintendent Nuclear Generation. Written safety evaluation reports are prepared in accordance with 10CFR50.59 and reviewed by the SORC, approved by the General Superintendent Nuclear Generation, and reviewed by the Safety Review and Audit Board (SRAB).

13 ~ 1 3

Nine Mile Point Unit 2 FSAR Nuclear Construction The Senior Vice President has the overall reponsibility for project management of Unit 2. The project management efforts include management of construction, design, support for preoperational and startup testing, and turnover of plant equipment and systems to Nuclear Generation for operation. These activities are governed by the Project Manual and procedures for Unit 2.

The technical staff will be used in the initial test program to the extent practical. Participants in the test program (i.e., Test Engineers) will receive training in plant specifics, systems, and indoctrination in administrative controls of the test program.

The Test Engineers will participate in preliminary and preoperational test phases. In the preliminary test phase they will write the preliminary test and help to direct the testing. In the preoperational test phase they will help to write the preoperational test and participate in the actual testing.

After commercial operation, the construction organization will be assimilated into other areas of the corporation, such as Quality Assurance, Nuclear and Non-Nuclear Engineering, and Operations. The Construction Engineers will provide coordination support for Contractors engaged in the installation and checkout of plant to Contractors will include the provision of modifications'upport equipment, such as welding machines, trailers, and special tools that may be required by the Contractor personnel during the performance of the contracted services.

13.1.1.3 Qualifications General responsibilities and activities of the above support groups are described in appropriate corporate documents including Administrative Procedures, the Project Manual, and Engineering Procedures. Contract support for Unit 2 is utilized in 'the same general manner as contract support at Unit l. After commercial operation, ultimate responsibility for contractor performance onsite rests with the General Superintendent Nuclear Generation.

The support group department heads are generally employees with 8 to 2S yr experience who have operations-related experience from the more than 20 yr of NMPC's nuclear power generation, construction, and design.

13.1-4

Nine Mile Point Unit 2 FSAR TABlE 13. 1>>1 HEADQUARTERS SUPPORT Position Summar Descri tion Manager Nuclear Manages the effort to verify all NRC com-Compliance and mitments and design activities to certify Veri fication accurate and as-built documentation is provided to regulatory agencies.

Manager Nuclear Manages the nuclear design engineering Engineering and analysis programs. Functions as the prime engineering contact with the site for engineering work.

I Manager Nuclear Manages the efforts for administrative Staff Services control of nuclear projects including those aspects associated with sched-ule and cost.

Manager Nuclear Manages consulting, scheduling, licens-Technology ing, fuels, plant productivity, and health physics.

Nine Mile Point Unit 2 PSAR TABLE 13.1-3 (Cont)

Su ervisor Radwaste erations The Supervisor Radwaste Operations, under the general direction of the Superintendent Operations, is responsible for coordinating the safe and efficient conduct of'aste operations. He schedules and coordinates waste shipments and supervises the packing of radioactive waste as necessary. He directs and supervises the work of operators assigned to duties in the waste facility. Assistant Supervisors Radwaste Operations are assigned, as required.

Radiolo ical En ineer Under the general direction of the Supervisor Radiological Support, this supervisor is responsible for providing highly specialized technical advice and assistance in the area of radiological engineering. There could be more than one Radiological Engineer.

Emer enc Coordinator This supervisor has responsibility for maintaining and modifying the Emergency Plan and Procedures as required, for maintaining the Emergency Plan Monitoring equipment and for the scheduling, operation and analysis of drills and other exercises of the Emergency Plan and Procedures. An assistant emergency coordinator is assigned to assist this supervisor.

Environmental Protection Coordinator This supervisor is responsible for coordination of the environmental programs associated with the Nine Mile Point Site and operated by contractors; and also for environmental monitoring conducted by site personnel.

3 of 7

Nine Nile Point Unit 2 FSAR TABLE 13.1-S SCHEDUZE FOR FIZZ ING OPERATING SHIFT CREW POSITIONS THIS TABLE HAS BEEN DELETED.

CHAIRHAN OF THE BOARD AND CHIEF EXECUTIVE OFFICER I

PRESIDENT SENIOR VICE PRESIDENT VICE PRESIDENT SENIOR VICE PRESIDENT SENIOR VICE PRESIDENT QUALITY ASSURANCE Fossil Generation Nuclear and Non-Nuclear Public Affairs & Corporate Nuclear Generation Hanagement Systems & Quality Assurance Comnunications Nuclear Engineering Services Safety and Licensing Engineering (Non-Nuclear) Administrative Services Nuclear Construction Po~er Contracts Training & Development Power Control Transportation Employee Relations SENIOR VICE PRESIDENT SENIOR VICE PRESIDENT, SENIOR VICE PRESIDENT SENIOR VICE PRESIDENT GENERAL COUNSEL &"

SECRETARY Treasury Legal Secretary's Office Controller's Office Gas Risk Hanagement Corporate Planning Electric Operations Purchasing Rates (System)

Security Regulatory Proceedings Consumer Services Haterials Hanagement Economic Development Customer Accounting Contract Administration Environmental Affairs Regional Operations Research & Development HANAGER INTERNAL AUDIT FIGURE 13.1-1 Internal Financial Auditing NMPC CORPORATE UPPER MANAGEMENT ORGANIZATIONAND FUNCTION.

Note the departments listed under each Senior Vice President. Vice President, or Hanager are representative and may not be inclusive. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

PRESIDENT OTHER SENIOR VICE PRESIDENT VICE PRESIDENTS SENIOR SENIOR DUALITYASSURANCE FOR NON NUCLEAR VICE PRESIDENT VICE PRESIDENT ACTIVITIES MANAGER MANAGER VICE PRESIDENT MANAGERS/SUPERVISORS SYSTEM NUCLEAR ENGINEERING NUCLEAR GENERATION OUAUTY ASSURANCE SECURITY ANO LICENSING FIGURE 13.1-1a NMPC UPPER MANAGEMENT NUCLEAR ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

SCNION St¹01 VCE PACSIDCNT VICE FNCQDENT IIANAOKN VICC SACSIOCNT NANAOIII STSTCII NVCLKM SNOINtlAINOANO SCCV¹TT OCNEIIATION LICKNSINO ASSISTANT TO TNt ASSISTANT TO VCC DAKSIDENl THE NANAOtA NUCLCM NUCLCAA CNOINtKSINO OCNtMTION AND UCKNSWO SUFC AVISON OCNKAAL IIANAOtN IIANAOKN IIANAOCN IIANAOtN IIANAOCN SUFCNWTCNDCNT SVDOtt S CDNFUAHCC ANO WICLCM NVCLCAN STAFF NVCLtAN VK¹FICATION TCCHNOLOOT ENOWCCIIWO SCNVICCS SKCU¹'IV NVC LEAN OC NCMTION COST CONTROLS FIGURE 13.1-2

'MPC NUCLEAR AND SECURITY ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

VICE PRESIDENT NUCLEAR GENERATION GENERAL SUPERINTENDENT NUCLEAR GENERATION ADMINISTRATIVEASSISTANT NUCLEAR ADMINISTRATION AND PLANNING SITE TECHNICAL MANAGER SUPERINTENDENT STATION SUP ERINTEHDENT STATION SUPERINTENDENT SUPERINTENDENT SITE CHEMISTRY AND SUPERINTENDENT TRAINING SUPERINTENDENT MAINTEHAHCE NUCLEAR RADIATION UNIT Z SERVICES NUCLEAR UNIT 1 NUCLEAR MANAGEMENT NOTES:

1. ALL OF THE ABOVE ORGANIZATIONIS ASSIGHEO TO THE SITE EXCEPT THE VICE PRESIDENT NUCLEAR GENERATION FIGURE 13.1-3 NUCLEAR GENERATION ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY'NALYSIS REPORT

IIANACtN WCL SAN t NCINLLNNNL ANOLICLNSNIC NQIACTN QANACIN QAINCTN QANACL1 WCLTM CONAQANCS WtltAN WtltMLNCNIttNIAC NVCLSM 5IAIf St NNCT 5 AND TTAIfICATION flCNNOL OCT TtaNNQANS LNCINttlls NANACLN NANACLN NANA4tN NANACLN NANACTN VANACTA IIANACTN LTAO SCNL OWN4 WCLTAN NtllTN st AO tNCAItts fVtLS AND NANACTN WCLSM COS'I QIOCt 'I5 ANO At COADS AOINNI5IAATNt

~ LANT CONSVLTWC NANACtNtNT SLANTS LICLNQNC ~ NTQasf fNOTLCT DTQCNLN OLQCN ASSVAANCS CO5f CONT AOL MOOVCTICN t NCQtt Ns SNQNttss OALNATIONS SNQNttss AtCOCOS ItCfeea MS ANALTSTS Sft aALTST t

5 aNNQANS DTQCNLNS 5 taNNQMS STSTLNS ANALTST TTCINNQAN5 FIGURE 13.1-4 NUCLEAR ENGINEERING AND LICENSING ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

STATION SUPERINTENDENT SUPERINTENDENT OPERATIONS NUCLEAR ASSISTANT TO THE

'SUPERINTENDENT-'PERATIONS NUCLEAR ASSISTANT SUPERVISOR SUPERINTENDENT RAOWASTE OPERATIONS OPERATIONS NUCLEAR ASSISTANT STATION SHIFT SUPERVISOR SUPEAVISOR AAOWASTE NUCLEAR OPERATIONS ASSISTANT AUXILIAAY CHIEF STATION SHIFT OPERATORS SHIFT SUPERVISOR 0 OPERATOR NUCLEAR NUCLEAR AUXILIARY AUXILIARY OP ERATOA OPERATOR E C NUCLEAR AUXILIARY AUXILIARY OPERATOR OPERATOR C S FIGURE 13 1-5 AUXILIARY OPERATOR 8 UNIT 2 SITE ORGANIZATION CHART-PRODUCTION NIAGARA MOHAWK POWER CORPORATION NINE MlLE PolNT-UNlT 2 FINAL SAFETY ANALYSIS REPORT

5ett Ass ItNOT Nl CHCUSSI11 AND AkOlk INNI ULNLOCSltNI sett AHSDA svtc 1rs501 CHt INS I1 I tNUAONUCNIAL MDTtcnoN ALDIOLOOCAL 1LDU TNNI COOAOelk 101 SVPPDAT PAONCTMN A55S5'I ANT ALDskNON tNSMONUINIks CNCINSTAT M0 I CC INW Naeaakas ~ AOICCTION l

'I CHMClkNs CINMDWAIOA TfCHMCUNS AS AC OUACD VMI~ I VMIII Sett ANION Veal M VMT sl I A SPMA TDA1 aklkcsoasckL SVtt AVS501 WittATI501 ALAAA DOSSUC 1st taoltcnoN lUIAOtNCT Iswesttw ALOLTSDN Sett 1VISCM WSI1VUIlll AAWATION NltfAH501 COOADWATOA COOADWAI01 Coolloel k 'NM ClsllUSTAT SVttollr CHCINSIAT COOADelk NM Ol PAOICCIION MON CTION IccleaCkL ItCINACAL ksssslANI kWNILSST klSI.CNCAO.

It CINACAL ItCwaCAL TCOANCAL Nclaeckt TtCHMCAL StlakLISI SPC CULSSI D05IUCI11 AIIPMkroar COOAOWAIOAS SttCILLIST SttakLUT StCClkLUI Stf OkLUT SPC CULIS I UMI ~ I VMIII COIMOWANNI C Ooalesk Nw IN akoMor CHCI¹SIAT NCHMCILNS Ako. PAOT.

ItCMNCUNS CHC Ussrar IfCwaakNs ItCHNCUNS I fCHMCUNS I t CINNCILNS 'It CHNICUNS Tf CHMCILNS II CHNSCUNS 11CMNCILNS ks A<4 O A$ 1fo'0. AS ACO D. ASACOO. A5 ACO'D. ksatoo ks AC 0 D ASACOD ks AC 0 D. ks Alon.

IMTIA Mwsta W tkansrsNIN ACPAINWS HUMWW1 Ot POUIIONA

~ Ncwaaeso eat u ksosowo or ross owcansoa aelasras UM akoUnoe PAONcnoa ks at ossa la.

FIGURE 13.1-9 CHEMISTRY AND RADIATION PROTECTION ORGANIZATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT s

Nine Mile Point Unit 2 FSAR Superintendent Nuclear Generation is included as a board member providing liaison and direct information to board members and ensuring that board recommendations are implemented.

The SRAB is charged with the responsibility for reviewing change requests originating in the SORC and recommending action where appropriate. When a license change is required, the SRAB reviews necessary documents for submission to the NRC. The SRAB also reviews all abnormal situations that may arise in plant operation. Periodic audits of operation are made by board members knowledgeable in the operating process, but without responsibility for daily plant operation. Functions served by these committees are the same as those performed by the Nine Mile Point Unit 1 committees shown in Tables 13.4-1 and 13.4-2.

Education and experience qualifications required for members of the SRAB are as follows:

I Staff En ineer Mana er or Vice President - Chairman Education: Four-year college graduate or equivalent.

Experience: Ten years of electric utility experience, with 5 years of experience in a responsible engineering management.

position which includes 4 years of nuclear plant engineering, design, construction, or operation.

General Su erintendent Nuclear Generation The General Superintendent Nuclear Generation qualifications are described in Section 13.1.3.1.1.

Staff En ineer - Nuclear Education: Four-year college graduate in engineering or operations, of nuclear facilities with at least 3 years of experience in nuclear engineering.

13.4<<2b

Nine Mile Point Unit 2 FSAR TABLE 13.4-2 (Cont)

8. Any area of facility operation considered appropriate by the SRAB, Vice President Nuclear Generation, or Manager Nuclear Engineering and Licensing.

9. The radiological environmental monitoring program and the results thereof at least once per 12 mo.

10. The Of fsite Dose Calculation Manual and implementing procedures at least once per 24 mo.

11. The Process Control Program and implementing procedures for processing and packaging of radioactive wastes at

=

least once per 24 mo.

Authorit The SRAB shall report to and advise the Vice President Nuclear Generation and Manager Nuclear Engineering and (

Licensing on those areas of responsibility specified. The SRAB shall report to the Manager, System Security, regarding security audits.

Records Records of SRAB activities shall be prepared, approved, and distributed as indicated below:

1. Minutes of each SRAB meeting shall be prepared, approved, and forwarded to the Vice President Nuclear Generation and Manager Nuclear Engineering and Licensing.

within 30 days following each meeting.

I

2. Audit reports encompassed by the above shall be forwarded to the Vice President Nuclear Generation and Manager Nuclear Engineering and Licensing and to management positions responsible for the areas audited within 90 days after completion of the audit. However, audit reports, made in connection with Nuclear Security, are submitted to the Manager, System Security, only.

3. Reports of reviews encompassed by foregoing items 5, 6, 7, and 8 shall be prepared, approved, and forwarded to the Vice President Nuclear Generation and Manager Nuclear Engineering and Licensing within 14 days following completion of the review.

3 of 3

SENIOR VICE PAESIOENT MANAGER NUCLEAR VICE PAESIOENT ENGINEERING ANO NUCLEAR GEHEAATION UCEHSING SITE OPERATIONS REVIEW COMMITTEE General Svperlntendent - Nuclear Generation Chrn.

SAFETY REVIEW 8 AUDIT BOARD Station Svperlntendent - Nuclear STAFF TECHNICAL Generation ASSISTANCE STAFF ENGINEER. MANAGER Technical Svperlntendent-OA VICE PAESIOEHT-CHAM Huclear Generation Superintendent Technical Servlces-GENERAL SUPEAINTENOENT Hvclear HUCLEAR GENERATION Site Superintendent Ha Intenance-IIuclear STAFF ENGINEER NUCLEAR Supervisor Instrvnent and Controf-Nuclear Superintendent Chcnlstry and STAFF ENGINEER MECH OA ELECTAICAL Radlatlon Hanagenent Supervisor Reactor Analysis STAFF ENGINEER EHVIROHMEHTAL Supervisor Iechnlcal Support Engineer CONSULTANTS OPERATIONS ASSESSMENT COMMITTEE SUPERIHTENOENT OPERATIONS NUCLEAR OPERATIONS ASSESSMEHT COOROIHA'TOA'UPEAVISOA COMPUTER OPERATIONS ANO MAINTENANCE NUCLEAR SUPERVISOR OC OPERA'IIONS FIGURE 13.4-1 SAFETY REVIEW AND AUDIT OF OPERATIONS ORGANIZATION

'THE OPERATIONS ASSESSMENT COORDINATOR IS A STAFF MEMBER OF THE TECHNICAL SERVICES DEPARTMENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

~

~

~ ~ ~

g I ~

I ~ ~ ~ ~

g

I j

~ I

~

~ ~

~

g g

~

~

HRf%%%%%RAWRAAAHAAA%%%%%%A

&%A WWAAHAAAAAA& AAA&%%%AHA

~ ~

g

~

WWWWWWWWWWWWW&W&&WWWWWWWW WWW&W&&&WWWWmmmWmermmmmwmm

~ ~

I ~ ~, I 0 ~

I ~

mmmmmmmmmWAAAH&A EHWAi%W%WEHiRWERAAKFRk%WA&A%&E%  %$ %WAHAA&f%

WmmmmmWmAEaRREa WWW&WAWX8%E%%%%

Wi%&WW I ~ ~

~

~

t

~

g I

~

WWWWIHl&WW&f%&&%lWQIQIWWERRl W&W&&WWWWlRRliRWWIAl&&lQl&&%&WSIIQ

~ ~

W%&W&&W&f%lHlRllHIWWSQWWIHlW&ffH&WLRI97 WA&Al8IAA

~

g

~

WH&AW&WWWlHJWW&&F%& WWIRHWWW&HERAHIR WRlWWWWWQllQl it rammrmmmmwww&WW&WWKHHWHHWHXINIIHl I I ~

fRWA&AAAAA&A&&W&mmmmmmmm W%W&W&WW&WWWWWWWWW WWWWW Rl~.'

~ ~

g

~ ~ ~

~

mmmmmm&m&Www&&8QRI&W W&WW&EQ

&HWW&&&&&WWW&&&W&[8l&%%&&%%l WH&W&&WW&WWW&WWW&R! WWWW&WFS

Nine Mile Point Unit 2 FSAR 17.1 QUALITY ASSURANCE PROGRAM DURING OPERATION Appendix D to the Unit 2 PSAR, as updated in accordance with 10CFR50 submitted under separate cover, defines the NMPC, QA program used for the design and construction phase of Unit 2. This section describes the QA program to be used during the preliminary and preoperational testing. phase of Unit 2 including those preoperational/acceptance tests and retests performed in the period starting with fuel load and ending with the 100-hr warranty run. Startup testing and operational activities subsequent to preoperational testing will be governed by the NMPC Quality Assurance Program Topical Report Nine Mile Point Nuclear Station Units 1 and 2 Operations Phase, NMPC-QATR-1, Revision 1. Figures 17.1-1 and 17.1-2 depict the organizational structure and lines of responsibility for the three program phases. Figure 17.1-2 also shows that during the interval between fuel load and full-power commercial operation, all three programs will be employed to handle any components or systems requiring reworking or retesting by the construction and preoperational test groups at Unit 2. Following the 100-hr warranty run at full power, the PSAR Appendix B and FSAR Chapter 17 programs will be replaced by the NMPC-QATR-l, Revision 1, Topical QA program.

17.1.1 Organization 17.1.1.1 General Organizational Structure The QA Department is a corporate department under the direc-tion of a Vice President of Quality Assurance (see Figure 17.1-1) who reports on quality matters to the President. Further definition of the administrative and functional organizations is included in the procedures developed to implement specific parts of this program.

Table 17.1-1 contains tabular cross-references from 10CFR50 Appendix B to the applicable NMPC procedures.

. The QA Department regularly reviews the status and adequacy of the QA program, including a quality compliance review of all contractors and a self-appraisal.

The organization of the Safety Review and Audit Board (SRAB) and the Site Operations Review Committee (SORC) is discussed in Section 13.4.

QA-related activities are performed by other individuals and groups in accordance with the requirements of the NMPC QA program manuals and Appendix B to 10CFR50. . The NMPC organizations that perform these activities for Unit 2 include:

17. 1-1

Nine Mile Point Unit 2 FSAR

10. Station Superintendent and Staff.

ll. Manager System Materials Management and Staff.

17.1.1.2 Program Responsibility

- Total'esponsibility for the QA program is retained by NMPC.

The QA Department is responsible to the President for execution and implementation of the QA program. This program includes control measures, such as audit, surveillance, and review and/or approval, to assure QA compliance for the design, procurement., fabrication, storage, construction, test, operation, and maintenance of the facility or any modifications.

Within this program, those individuals and organizations assigned specific QA functions, as described herein, have the responsibility for assuring the establishment of specific criteria for measurement and verification of the correctness of work performed against these criteria.

Additionally, the size of the QA Department will be determined by the scope of the design, construction, and operations activities and their importance to safety.

The management of Niagara Mohawk Power Corporation (NMPC) at the presidential or chief executive officer level assesses the scope, status, adequacy, and compliance of the Quality Assurance program for the nuclear stations at a predetermined regularity. Management at this level employs the following means:

~ The Vice President Quality Assurance normally attends Chief Executive Officer's staff meeting attended by appropriate members of executive management (C.E.O. and/or President and/or Administrative Assistant) as well as by the senior vice presidential, level. The Vice President Quality Assurance is expected to provide oral presentations or furnish an assessment of quality assurance matters.

~ The Vice President Quality Assurance is listed on the agenda of the corporate monthly operating review meetings and normally presents an oral capsule assessment of QA matters to the executive management level and to other attendees.

Certain actions of the safety review and audit board and of the site operations review committee result in audits and/or reports by which members of these offsite and onsite review committees are made aware, on a regular basis, of 'the J,

17.1-2

Nine Mile Point Unit 2 FSAR effectiveness of the QA program. The action of these committees and their reporting on a regular basis to the Vice President Quality Assurance and other specified vice presidential levels is described in Section 13.4.2.

Management above the QA organization utilizes, on at least an annual basis, the services of a combined utility assessment team and/or the contracted services of qualified QA assessors. The combined utility assessment team is composed of appropriately qualified auditors from a consortium of nuclear utilities.

17.1.1.2.1 Vice President Quality Assurance t The Vice President Quality Assurance reports directly to the President and is responsible for the overall control and implementation of the Quality Assurance program. The Vice President Quality Assurance is organizationally independent from the various functional groups and has the freedom to deal independently with matters concerning quality activities performed by those groups. To ensure that the Vice President Quality Assurance may deal with quality problems effectively, the Vice President Quality Assurance has the authority to take direct action concerning matters affecting quality. Direct action includes the initiation of an order to "stop work" or consultation with NMPC corporate management concerning unresolvable quality problems.

The Vice President Quality Assurance effects overall Quality Assurance policy through approval of the content of this document and through approval of the Quality Assurance Department Procedures, as delegated.

In addition, the requirements exist for the Vice President Quality Assurance or his designee to review top level procedures of other departments and to indicate, in writing, acceptance of (concurrence with) these procedures which cover quality-related activities.. This must be accomplished prior to implementation and applies equally to changes to these procedures. This requirement makes the Vice President Quality Assurance it possible for to achieve an acceptable level of control over all activities which relate to quality.

The Vice President Quality Assurance exercises the control and direction of NMPC's Quality Assurance program from:

17.1-2a

0 Nine Mile Point Unit 2 FSAR This being the highest NMPC corporate position totally and exclusively concerned with quality activities.

2. This position reporting to the President.

.3. This position exercising total functional control over the QA organization.

4, This position having the responsibility and authority to formulate and establish QA policy for NMPC.

5. This position having the responsibility to approve QA Department procedures.

6. This position having the responsibility to indicate acceptance prior to implementation of other procedures that contain quality provisions. Such procedures are those that deal with operation, design, repair, maintenance, modification, and procurement.

7. This position directing the audit/followup program of the QA organization.

8. This position having the authority to indicate or delegate initiation of "stop work" action and main-tain control to completion of acceptable corrective action.

17.1.1.2.2 Quality Assurance Supervisors/Managers Quality Assurance Supervisors/Managers have the respon-supervision of the members of their staffs as-sibility forevaluate signed to and coordinate necessary QA functions.

More specifically, some of their activities include:

Supervising, directing, and coordinating the staff personnel and consultants within the framework of established policies and QA Department procedures.

2. Bringing unresolved quality-'related problems to the attention of the Vice President Quality Assurance.

3. Coordinating and evaluating necessary audit functions.

Implementing Q4 Department procedures and instruc-tions regarding safety-related modification and refueling operations.

17 ~ 1 3

Nine Mile Point Unit 2 FSAR

5. Implementing all required quality control ac-tivities in accordance with applicable QA procedures and instructions.

6. Regularly reporting to the Vice President Quality Assurance the status of quality activities being performed.

7. Initiating "stop work" action at the site, when appropriate. This is further described in Section 17.1.10.2.1.

The QA Supervisors/Managers maintain the necessary indepen-dence to perform QA activities by reporting directly to the Vice President Quality Assurance. Organizational indepen-dence from those performing actual work will be maintained.

Personnel performing verification of conformance to estab-lished requirements are members of the Quality Assurance Department or their designee. This department is headed by the Vice President Quality Assurance; who reports directly to the President of NMPC.

Personnel performing the work being verified (nuclear engineering, nuclear generation, Purchasing, Materials Management, etc) report to other vice presidents.

The Manager Nuclear Quality Assurance Operations exercises control and direction of NMPC's Operations Nuclear Quality Assurance program by:

1. Being the highest position within the QA Department devoted exclusively to operations nuclear quality assurance activities.

2. Having the responsibility to ensure implementation of the NMPC nuclear policy and procedures esta-blished by the Vice President Quality Assurance.

3. Having the responsibility to advise the Vice President Quality Assurance of serious quality as-surance concerns regarding identified nuclear problems.

The Manager Corporate Quality Assurance provides support for the Nuclear Quality Assurance Operations unit by having the responsibility to:

1. Conduct corporate QA audits and provide a trend analysis program.

17. 1-4

Nine Mile Point Unit 2 FSAR

2. Recommend corporate QA Department procedures and policy to the Vice President Quality Assurance for I his approval.

3 ~ -Coordinate QA Department training.

4. Advise the Vice President Quality Assurance and the Manager Nuclear Quality Assurance Operations of serious quality assurance concerns regarding identified nuclear problems.

The Manager Quality and Reliability Engineering provides technical support to the Nuclear QA Operations section.

Responsibilities include:

Reviewing plant modification design documents for inspectability, developing quality planning to support installation of plant changes, and coordinating the technical aspects of QA modi fication package implementation during plant shutdowns.

2. Providing for control of purchased equipment through the contractor qualification program, source surveillance, and the preparation for receiving inspection planning (for implementation by Nuclear QA Operations personnel).

3. Providing materials engineering support in the areas of material selection, welding, corrosion prevention, nondestructive examination, and fuels

.quality assurance.

Advising the Vice President Quality Assurance and the Manager Nuclear QA Operations of nuclear quality activities.

5. Providing reliability engineering support for the equipment qualification program, establishment of system and equipment availability goals, followup with suppliers on achievements of equipment reliability requirements, and performance of studies on extending equipment life.

6. Reviewing and concurring with various documents and other department procedures, where applicable, which implement this Quality Assurance Program.

17. 1-4a

Nine Mile Point Unit 2 FSAR

7. Recommending to appropriate management, courses of corrective action, when required, including initiation of stop work orders. This stop work authority is delineated in writing.

17.1.1.2.3 Quality Assurance Staff The QA staff for Unit 2 consists of those members of the QA Department who are assigned by the QA Supervisors/Managers.

Some of the duties of the staff include:

Conducting audits of the various NMPC departments, architect-engineers, contractors and subcontractors, including QA groups within these organizations.

2. Preparing and updating policy manuals, certain procedures, and instructions necessary to implement the QA program.

3 ~ Reviewing the procedures, programs, and results of the various organizations performing the quality activities within or for NMPC, including the

'incorporation of hold or "witness" points therein.

4 Trending of quality-related problems.

5.a. Reviewing and approving quality programs of contractors involved in modification and refueling.

b. Reviewing and approving QA programs and manuals of contractors supplying services for maintenance, repair, and tests conducted at thb site.

e. Appraising the quality-related capabilities of contractors and vendors.

7 a~ Reviewing and accepting procurement documents, specifications, documentation of design cal-culations and related documents and drawings 17.1-4b

Nine Mile Point Unit 2 FSAR J

generated by the Nuclear Division relating to modification and refueling.

b. Reviewing and accepting procurement documents, specifications, and drawings relating to maintenance, repair, inspections, and tests conducted at the site.'.a.

Surveillance/auditing of NMPC and vendor activities relating to modification and refueling.

b. Surveillance of site activities regarding modifications, maintenance, repair, fuel handling operations, inspections, and tests.

9. Preparing reports for the Vice President Quality Assurance, as assigned.

10. Performing other duties delineated in subsequent sections of this document and in the appropriate QA Department procedures.

11. Performing or assuring performance of the independent inspections associated with corrective maintenance, receipt inspections, and modi-fications.

QA staff personnel h'ave expertise in various disciplines such, as mechanical, nuclear, electrical, structural, NDE, and metallurgical.

The responsibility for the inservice inspection resides with the Nuclear Generation staff. The QA Department provides surveillance and inspection of this function as part of the audit program.

The QA staff has the responsibility and authority to audit any organization, both within and outside NMPC performing quality-related activities. This allows the QA Department to evaluate/investigate the performance of applicable QA groups and to provide additional assurance of proper accomplishment of activities affecting quality.

Additionally, the QA staff is responsible to assist the QA Department Supervisors through regular audits, reviews, surveillances, and other assigned functions.

17. 1-5

Nine Mile Point Unit 2 FSAR 17.1. 1.2. 4 Nuclear Engineering and Licensing

'he Manager Nuclear Engineering and Licensing has overall responsibility fox engineering services after commercial operation. The corporate engineering staff cur-rently performs, or controls the performance of, design activities relating to modifications to Unit 1 and will support Unit 2 in the same manner. Established Engineering Department procedures will be utilized for such activities.

The Engineering Department organization chart is provided on Figure 13.1-4. The Manager Nuclear Engineering or his designee is the engineering contact for plant-to-engineering interfaces.

A number of engineers from this organization have actively engaged in technical aspects of the Unit 2 design. This organization presently consists of over 100 engineers with a

17. 1-Sa

~ %~% ~ ~ 'I ~ ~ ~

Nine Mile Point Unit 2 FSAR variety of disciplines and backgrounds in power plant technology. Support in plant chemistry, health physics, fueling and refueling operations, and maintenance support, as required in nuclear, mechanical, structural, electrical, thermal-hydraulic, and instrument and control engineering are provided. Specific headquarters support group descriptions are discussed in Chapter 13.

Most design-related requests (after commercial operation) are relayed from the Station Superintendent through the Manage'r Nuclear Engineering, who assigns appropriate engineering support groups the design responsibility and/or hires a vendor or contractor to perform the work.

Conceptual designs are formulated and sent to the site for approval after engineering approval. Conceptual site approval is made by the Station Superintendent after review by the appropriate site discipline. Final design is provided by Engineering for review by the appropriate site discipline, the Station Superintendent, and the SORC, and is approved by the General Superintendent Nuclear Generation and reviewed by the SRAB.

Any design-related activities not performed as described above are performed onsite or controlled onsite. Such activities are controlled in a similar manner except that technical review and approval and procurement are maintained by site personnel, with Engineering acting as a consultant if requested by the Station Superintendent.

17.1.1.2.5 Nuclear Construction The Senior Vice President has the overall responsibility for project management of Unit'. The project organization is shown on Figure 13.1-2. The project management efforts include management of construction, design, and support for turnover of plant equipment and systems to Nuclear Generation for preliminary, preoperational, and startup testing (fuel 1.oad). These activities are governed by the Pro) ect Manual and procedures for Unit 2.

17. 1. 1.2. 6 Purchasing The Vice President Purchasing reports directly to a Senior Vice President and is responsible for formulating, establishing, and enforcing compliance with procurement requirements. The Vice President Purchasing and his staff are responsible to ensure that all applicable procurement documents and changes are reviewed and accepted by the QA Department.

17.1-6

Nine Mile Point Unit 2 FSAR 17.1.1.2.7 Safety Review and Audit Board (SRAB)

The SRAB is responsible to the Manager Nuclear Engineering and Licensing and the Vice President Nuclear Generation. In addition to other specified duties, this board reports its observations regarding Unit 2 QA functions to the previously mentioned Manager and Vice President and the Vice President of Quality Assurance. The organization and functiohs of the SRAB are discussed in Chapter 13.

17.1.1.2.8 Site Operations Review Committee (SORC)

The SORC is responsible to the General Superintendent Nuclear Generation and transmits reports to the SRAB. In addition to other specified duties, the SORC reviews all initial and revised pxocedures utilized at, the site by the Nuclear Generation Department. The organization and functions of the SORC are discussed in Chapter 13.

17.1.1.2.9 General Superintendent Nuclear Generation The General Superintendent Nuclear Generation reports directly to the Vice President Nuclear Generation. The General Superintendent is responsible for implementing NMPC QA policies as applicable to operation, maintenance, modification, and repair conducted at the site. He is responsible for formulating, establi shing, and enforcing compliance with all Nuclear Generation Department procedures implemented at'he site.

The General Superintendent is authorized to approve all site Nuclear Generation Department procedures, to continually analyze site operations to detect potential safety problems, and to implement "stop work" action at his discretion 'and when requested by the QA Department in accordance with applicable procedures.

17.1.1.2.10 Maintenance Superintendent Nucleax and Staff The Site Maintenance Superintendent Nuclear and his staff repoxt to the General Superintendent Nuclear Generation.

This superintendent is primarily concerned with:

Originating procurement documents for maintenance, modification, and repair.

2. Welding.

3. Equipment testing fox maintenance (electrical, structural, mechanical), repair, and modification.

17.1-7

Nine Mile Point Unit 2 FSAR Supervision of maintenance, repair, and site-controlled modifications.

5. Control of Maintenance Department measuring and test equipment.

17.1.1.2.11 Technical Superintendent Nuclear Generation The Technical Superintendent Nuclear and his staff report to the General Superintendent Nuclear Generation. The Superin-tendent Technical Services Nuclear and his staff report to the Technical Superintendent Nuclear and are concerned with:

Control of Instrument and Control and Operations Department measuring and test equipment, and main-tenance and testing of process, instrumentation, and control equipment.

2. Reactor core management receipt, storage, inspection, utilization, and disposal of nuclear fuel.

3. Operations maintenance of computer-related services.

Technical support services.

5. Inservice inspection.

6. Fire protection.

7. Administrative services (Chapter 13).

17.1.1.2.12 Superintendent Chemistry and Radiation Management The Superintendent Chemistry and Radiation management and his staff report to the General Superintendent - Nuclear Generation. They are responsible protec-for chemistry, radiochemistry, radiation protection, environmental test equip-tion and emergency planning including control of measuring and ment for these activities (Chapter 13).

17.1.1.2.13 Superintendent Training The Superintendent Training and his staff report to the General Superintendent Nuclear Generation. They are responsible for. the training of personnel (Chapter 13).

17.1-8

Nine Mile Point Unit 2 FSAR NNPC and by those supplying materials, equipment, and services to NMPC. In making this evaluation, QA personnel audit or conduct surveillance of quality activities in all of the above-mentioned areas. QA personnel are responsible to assure the identification of quality problems, to initiate or recommend'solutions to these problems, to verify corrective actions relative to these problems, and to verify that quality instructions are implemented. The Vice

! President Quality Assurance regularly informs the President and the appropriate Senior Vice President as to findings.

17.1.1'.3.3 "Stop Work" To ensure that the Vice President Quality Assurance may deal with quality problems effectively, he has authority to take direct action concerning matters affecting quality. Direct action includes the initiation of an ordex to stop work or consultation with NMPC senior executives concexning unresolved quality problems. Sections 17. 1. 1.2. 9 and 17.1.10.2,1 identify other personnel who have the authority to initiate "stop woxk" action.

17.1.1.4 Quality Assurance Interfaces The QA communications interfaces established are described below:

1. The interfacing gxoups are knowledgeable about the scope of each others'ctivities affecting quality by exchanging controlled documents as required.

2. For the life of certain modification projects, interfaces, including QA interfaces, are identified in appropriate documents furnished to major project participants including contractoxs.

Examples of QA communications interfaces include the following:

QA/QC nuclear operations organization pexsonnel will attend informal planning sessions with the maintenance department. These are generally held daily.

During normal operation, QA/QC may attend plant operation meetings. These are generally held weekly.

QA/QC may attend site operational review committee meetings as a nonvoting member. These are generally held weekly.

QA/QC will review all Class I work requests-prior to the initiation of work and all modification requests.

Nine Mile Point Unit 2 FSAR 17.1.2.8 Program Development Copies of NMPC and contractors'A procedures, instructions, or manuals are available for reference in the NMPC QA organization offices or at the contractors'ffices. The procedures require provision for controlled conditions when carrying out activities affecting quality. These procedures require the use of appropriate equipment in suitable environments and verification that quality prerequisites have been achieved.

17.1.2.9 Program Assessment The Vice President of Quality Assurance periodically assesses the impl ementati on and effectiveness o f the QA program

17. 1-13a

Nine Mile Point Unit 2 FSAR through review of reports concerning audits and surveil-lances conducted by the QA organization. The QA Department regularly performs audits and surveillances ofQA-related the ac-tivities of the various organizations performing activities (Section 17.1.18). Copies of the reports of audits/surveillances are sent to the Vice President who in turn reports significant findings/problems Quality'ssurance, to the President. The audits of the SRAB are conducted and reports distributed as indicated in Section 17.1.18.

The QA programs and the QA manuals for contractors and ven-dors involved in repair, maintenance, inservice testing, and modifications to, and the refueling of, Unit 2 are reviewed and accepted by QA personnel under the direction of a Quality Assurance Manager/Supervisor. Documentation of the review and acceptance action is audited by the QA group.

17.1.2.10 QA Interfaces During Initial Testing The QA interfaces are described in Section 17.1.1.4. This will include interfaces between architect>>engineers, NSSS, and other NMPC groups to assure successful transition and implementation of the QA program.

17.1.2.11 Review and Approval of Program Manuals/Procedures The frequency of audits and surveillance is commensurate with the safety significance of the activities performed.

The audit frequency is suf ficient (Section 17. 1. 18) to provide QA Department management, and in turn, NMPC cor-porate management, with means to continually evaluate the QA program.

All QA Department policies and procedures that are used by the QA Department require the approval of the Vice President Quality Assurance or his designee. QA Department procedures are originated by QA Department staff personnel, reviewed by the QA Department Supervisors, and approved by the Director of Quality Assurance or his designee.

The QA program description will be kept current by annual review and update of the FSAR as required by 10CFRSO. Sub-stantive changes to the accepted QA program will be submit-ted to the NRC for review and concurrence before implementation. Additionally, the NRC will be notified of organization changes within 30 days of announcement.

Sine Hile Point Unit 2 ?ShB 17.1.5 Instructions, Procedures, and Drawings 17.1 5 1 General k

The intent of this section is to assure that quality-related activities are prescribed by docuaented instructions, procedures, and drawings and are accoaplished in accordance with these instructions, procedures, and drawings 17.1.5.2 Quality activities The NHPC Ql Department or their designated representative

<<ill verify that appropriate Ql aeasures ernest and are ia-pleaented in all quality-related activities Quality

'measures include, but are not liaited . to, instructions, procedures, and drawings.

The NHPC design office, operations group, or designated representative, as applicable, is responsible for establish-ing appropriate quantitative and/or qualitative acceptance criteria for determining that quality-related activities are satisfactorily accoaplished'n the case of equi.paent and coaponents, these criteria are aade a part of the design docuaents, for procureaent and/or installation of each piece of equipaent, coaponent, or order of aateri.al. In the case of operations, these criteria are set forth in the applic-alle operations and aaintenance procedures.

The description of coapliance to the requireaents of 10CFB50. 55(a) is described in various FShR sections (such as conforaance to ASIDE Section II, described in FSllB Section 6) . Procedures will be developed to address the ia-pleaentation of plant aodifi,cat9.ons to ensure continuing conformance to 10CFR50.55(a) and gh procedures to assure

~

conforaance The description of coapliance to regulatory guides is described in Section 1 8 Procedures will be developed to

. address the iapleaentation of the'egulatory guides listed in Table 17 0-1 and {}1 procedures to ensure conforaance Qk departaent procedures for the preparation, review, and control of procedures requires that reviews he perforaed on a scheduled basis. ill changes or revisions are reviewed, approved, and controlled in the saae manner as the original procedure. The reviews are perforaed by the Corporate Qk Section with input'rovided by the affected {}AD sections Qk Department procedures are approved by the Vice President Quality Assurance and aay be concurred with by other SHPC organizations whose responsibilities are affected by the Qh procedure 17 1-22

Nine Mile Point Unit 2 FSAR Assurance that similar procedures are established and im-plemented in other departments is obtained by audit and sur-veillance by the QA department.

The Quality Assurance department reviews all engineering and site administrative procedures for QA-related aspects. before Con-currence by the QA Manager is required implementation. Concurrence is indicated by signature and date on the title page of the procedure.

17.1.5.2.1 Document Procedures Procedures for directing quality-related activities will be prepared to comply with each of the 18 criteria within 10CFR50, Appendix B.

17.1.5.2.2 Preparation of Procedures, Instructions, and Drawings All quality-related activities shall be performed in accord-ance with properly approved instructions, procedures, and drawings. The preparation of necessary written procedures and instructions is the responsibility of the department or group performing the activity. Required procedures, instructions, and drawings are prepared in accordance with controlling procedures that include requirements for review, approval, and issuance of the documents involved.

All NMPC QA Department procedures are reviewed and approved by the Vice President Quality Assurance or his designated representative. Certain other procedures including NMPC En-gineering procedures, the Nine Mile Point site adminis-17.1-22a

Nine Mile Point Unit 2 FSAR trative procedures, and certain controlling procedures of the Nuclear Construction Department, Materials Management, and Purchasing Departments require the concurrence prior to issuance of the Vice President Quality Assurance or his designated representative for quality-related content.

1'7. 1. 5. 2. 3 Requi rements NMPC imposes on their architect-engineers, vendors, and contractors, the requirement for appropriately utilizing approved written procedures and instructions, as The architect-engineers, vendors, and contractors are obligated to impose applicable requirements on their suppliers and subsuppliers.

17.1.6 Document Control 17.1.6.1 Document Issuance Maintenance and Control The purpose of this section is to assure the implementation of programs for establishing and maintaining control over documents that affect the quality and safe operation of Unit 2. This policy is implemented through written procedures. It is imposed upon contractors, suppliers, and subsuppliers, when appropriate, through contractual arrangements.

The measures that control the issuance and revision of these documents require:

Review of controlled documents for accuracy.

2. Approval of controlled documents by authorized personnel prior to release.

3. Distribution of controlled documents to the points of use.

4. Use of controlled documents where the prescribed activity is carried out.

S. 'Changes and alterations to documents affecting quality are made by subjecting the revised document to the same controls (review, approval for release',

distribution, and use) as the document that replaces, changes, or alters. The changes are it reviewed and approved by the same organizations that performed the original review and approval.

Document control provides that changes are included in a timely manner, when applicable. Unit 2 will maintain marked-up copies of all drawings to 17.1-23

Nine Nile Point Unit 2 FSAR inspected by methods that are the same as the original inspection methods. Modified or repaired items are inspected by methods ,that are equivalent to the original inspection methods.

In the event that direct inspection of processed material is not feasible, measures are established to employ indirect control as a means of determining product quality. This may take the form of monitoring of processing, equipment, and personnel. Indirect control methods supplement direct inspection whenever required to verify product quality.

17.1.10.1.1 Implementation Inspections are conducted, but are not limited to:

1. The contractor's manufacturing facility.

2. Receipt inspection at the site.

3. Installation inspection.

4. Inservice inspections.

5. Operations inspections.

6. Corrective maintenance.

7. Preventive maintenance.

At the Unit 2 site, Quality Control is responsible to perform receipt inspection. Normally, inspection j will be performed by Quality Control personnel, although qualified and appropriately certified independent personnel from other departments or outside contractors may be used.

Instructions for inspection are documented and are furnished to inspectors prior to an inspection activity. Equipment used in an inspection operation is controlled in accordance with Section 17.1.12. The Engineering or QA Department evaluates and determines the accuracy requirements.

Completion of inspection and/or certification that all inspection operations have been performed shall be provided consistent with the requirements of the inspection.

Responsibility for verification of inspection shall be accomplished by the QA Department prior to placing the equipment into service.

17.1-35

Nine Mile Point Unit 2 FSAR identify those mandatory inspection hold points beyond which work may not proceed until inspected by a designated inspector.

17.1.10.2.1 "Stop Work" Policy The Vice President Quality Assurance or his designated rep-resentative has the authority to initiate "stop work" action. Where normal station operation or maintenance work is involved, the General Superintendent Nuclear Generation is also authorized to issue "stop work" action. He may designate that certain of his personnel have the authority to issue "stop work" actions. For ma)or repairs or modifications delegated to it, the Design Office is also authorized to issue "stop work" action.

When a process on a safety-related system fails to meet established criteria due to noncompliance with specifications, procedures, or drawings, unsatisfactory workmanship, or deviation from operational standards, authorized personnel may deem it necessary to issue "stop work" instructions. When safety-related station changes or modifications are involved, either the NMPC Design Office or the General Superintendent Nuclear Generation (as previously described) shall issue "stop work" instructions to:

Forbid the use of materials, ecpxipment, or workmanship that do not conform to specifications, or that would cause improper installation relative to specifications.

17.1-36a

Nine Mile Point Unit 2 FSAR Measures are established within test programs to ensure that test performance and test results are documented and evaluated and that test requirements have been satisfied by predetermined qualified personnel.

Prototype and preinstallation tests are specified in the specifications and reviewed by NMPC's responsible engineer and the appropriate QA Department staff member in accordance with Sections 17.1.3 and 17.1.4. Specified prototype and preinstallation tests conducted in vendors'hops are witnessed, .inspected, or audited by NMPC and/or their agent.

NMPC may also participate in "notification Point" or "hold point" tests. Specified prototype and preinstallation tests performed in the field are witnessed, inspected, or audited by NMPC and/or their agent.

17.1.11.1.1 Preliminary, Preoperational, Startup and Operational Tests Station Operations personnel perform necessary preliminary, preoperational, startup, and operational tests in accordance with guidelines established in both the Startup and Site administrative procedures. Test procedures are prepared and reviewed by Station Operations personnel in accordance with these procedures.

Preliminary testing is that phase in the test program which is performed prior to preoperational testing to veri.fy that individual components or subsystems and setpoints function correctly. These tests serve as a prerequisite to preoperational test.

testing is initially verify that a structure,thatsystem, Preoperational testing necessary to or component, or modification thereto, meets certain design and performance requirements prior to placing that structure, system, or component into commercial operation. Preoperational testing may include some tests that must be run while the unit is operating. Therefore, preoperational test procedures must define the basis for completion of the test, thus establishing the point at which the structure, system, or component is in commercial operation. Preoperational test procedures are reviewed for QA adequacy by the QA Department and approved by the Joint Test Gr oup Chairman or other responsi-ble approved authority.

Operational testing is testing conducted to establish that a structure, system, or component placed into commercial operation continues to meet specified requirements, including those contained in the technical specification.

These procedures are reviewed and approved by the SORC prior to implementation.

Nine Mile Point Unit 2 FSAR

2. The cause of the condition is determined and prompt corrective action is implemented.

3. Determination of corrective action is made by cognizant and responsible personnel.

Follow-up action is taken to provide implementation, verification, arid closure- of the documentation by the appropriate QA Department supervisory personnel.

It is the responsibility of the particular QA Department Supervisor to control the deficiency and corrective action reporting system in his area of responsibility. He shall determine which of those reported conditions are significant conditions adverse to quality, and shall ensure that they are immediately reported to appropriate management levels including the Vice President Quality Assurance. Corrective action for significant deficiency reports is handled in a manner consistent with their importance to safety.

Corrective action includes preventive measures to preclude recurrence of the condition.

The appropriate manager/supervisor of the organization upon which a deficiency citation has been prepared is responsible for determining the corrective action to be applied, preparing any procedures required, and ensuring that the corrective action is implemented.

Contractors involved in station modification, repair, or services are required to have procedures that require that nonconformance and corrective action documentation and reporting be implemented. The QA Department is responsible for ensuring that such requirements are stated in procurement documents by review, and for ensuring implementation by surveillance and/or audit,.

The Vice President Quality Assurance maintains overall responsibility for, and control of, the deficiency and corrective action reporting system. He has the approval authority for all procedures and changes thereto involved in the Nonconformance Reports system. He maintains control by means of audits, surveillance, and reviews of Nonconformance Reports by personnel of the QA staff. Procedures require that a copy of any report indicating a significant condition PresidentQuality adverse to quality be transmitted to the Vice Assurance or his designee.

Nine Mile Point Unit 2 FSAR 17.1.16.3 Analysis Reports indicating quality problems are reviewed by the QA Department for trend analysis. The QA Department staff is also required by procedures to document and report adverse trends, QA program breakdowns, or other significant deficiencies to the Vice President Quali'ty Assurance or his designee. He has the authority, through reporting to corporate management, to ensure that proper corrective and preventive measures are undertaken to satisfy the requirements of the applicable safety criteria.

17.1.16.4 NRC Notification of Problem Areas Procedures are established regarding the reporting of failures to comply or defects to the NRC, as required by 10CFR21. Procedures provide for internal reporting and analysis of deviations and require the imposition of the requirements of 10CFR21 on suppliers as part of procurement documents.

17.1.16.5 Records The QA Department shall maintain a file of records generated relating to this section as delineated in Section 17.1.17.

17.1.17 Quality Assurance Records 17.1.17.1 General It is the policy of NMPC to maintain a record retention system which contains an easily retrievable quality history for each safety-related item. All records must be consistent with applicable codes, standards, specifications, and contracts. This policy requires that station operating and maintenance records be maintained. Design offices, vendors, and contractors are required to generate and provide to NMPC records covering the period of design, manufacture, and installation. The purpose of this system is to permit reconstruction of the significant events that cause any given part to be located where it is, in regard to physical position and operating status, at any particular point in time. These records can be used for such purpose as analysis of failures, maintenance programs, and replacement frequency.

The following are examples of records to be maintained:

procurement documents, calibration procedures and results, nonconformance reports, operating logs, refueling records,

A Nine Mile Point Unit 2 FSAR 17.1.18.8 Audits/Surveillances by the Quality Assurance Department Staff Independent audits as well as surveillances shall be conducted by the QA Department staff. These include, but are not limited to:

Operation, maintenance, receipt inspection, testing, modification, installation, - repair, technical services, training, and chemical and radiation management.

2. Engineering, Pro) ect Management, Purchasing, and Materials Management.

3. Audits of records of SORC and SRAB.

4. Contractors'ctivities, design offices, shops, and field erection.

5. Corrective action and nonconformance content.

6. FSAR commitments.

7. Compliance with regulatory requirements.

8. Calibration facilities.

9. Activities associated with computer programs.

Audits and surveillances are scheduled at appropriate intervals to ensure that all safety-related activities, procedures, and programs are in compliance with their intended functions and regulatory requirements. Checklists shall be prepared in advance when appropriate.

Audit and surveillance reports are distributed, as applicable, to:

Vice President Quality Assurance.

QA Department Managers and Supervisors.

General Superintendent Nuclear Generation or SRAB chairman.

Station Superintendent.

5. QA Department files.

6. Organizations involved in audit/surveillance.

17.1-52 I ~ P ~

Nine Mile Point Unit 2 FSAR All audits include an objective evaluation of quality-related practices, procedures, instructions; ac-tivities and items; and review of documents and records im- to ensure that the QA program is effective and properly plemented in accordance with procedures.

17.1.18.9 Audits by the Safety Review and Audit Board NMPC corporate management utilizes the services of the SRAB to audit QA-related activities at the site, as well as within applicable portions of the QA and Nuclear Departments.

The SRAB conducts audits in the areas and at the frequency specified in the Technical Specifications using checklists prepared in advance. SRAB audits of QA-related activities are conducted under the immediate direction of a board mem-ber or consultant who has no direct responsibilities in the areas being audited. He may invite the participation of a member of the QA Department and/or other concerned groups as observers. The scope of audits conducted by, the SRAB is of such nature as to appraise the QA program policies, activities, and procedures. These policies, activities, and procedures are evaluated against the criteria of Appendix B to 10CFR50. Deficiencies observed in the QA program policies, activities, and procedures are described in the audit report. Snsuing corrective ac(ion is verified on sub-sequent audits by the SRAB.

An annual summary of SRAB audits performed is reported. The distribution of this report is, as a minimum, to the Vice President Nuclear Generation, the Manager Nuclear En-gineering and Licensing, the Chairman of the SRAB, and the Vice President Quality Assurance.

17 ' ~ 18 '0 Records Audit reports are maintained as delineated in Section 17.1.17.

17.1.19 Fire Protection Quality Assurance Program NMPC commits to the general requirements provided in the Fire Protection Quality Assurance Program for Unit 2 (see Section 9A..3.4).

444. UUClTAO IIOO. 44etoMT c fc41. ovwfT 4 4C UcctffTY

41. OtC MT IOUC OU CliffACWMUOC CVOel c c ew4 WtfeYICOO CVtfCYICOO WtCAYIOOO WtfeY401 Ccfe04 cUtcenc04 CVtC1YIC01 Wtc AY401 WtceYIO01 Wtfecl$04 OUATTTYCIIOIVCCWIO OUAUTY c Ieeec cewo OUACITY ACAVAAUCC MOCIIACIacef UAT CAIACS OVACTTY

~

OUAUTYCOV feOL otcff, ccefY. OA AUOUC OA ccenccc

~

Inlt ~ Inat ceOelcfeelo c conf f oleo

~

C OVAUTY ~

~ ootlceoe eon alotlllntee

~ oaon aatecc

~ eal at toctee aeoee

~ Ineeae ac tsnatacc

~ Ml c~n aee Iwlaeon ~ cooaoatalll oa laaaaan ~ a\tee eooeeaeoe

~ ceaeoocaeeen CCUAUUTY ceolecceelo

~ et neat ~ ecaaatee ecaeeo eeteec t lallocl

~ ~ ~ o neo acean ~ I ae acta leo ~

~ noletco~ nctaacaa eeaoec ~ naaaeo necf Itee aeo ~ ntaaln naooa otaaoetlen ~ ael

~

~ tel otcaaenw ate

~

~ Iottaeec oeaaoeo IM ~ ~oa naalae net etan aaaecc

~

~ Otalln tlaaene

~ eooeaco lee eotcet FIGURE 17.1-1 QA NUCLEAR ORGANIZATION DURING

'ONSTRUCTION, PRELIMINARYTEST,:

, PREOPERATIONAL TESTING, STARTUP TESTING. OP E RATIONS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

0 ATTACHMENT 3

Nine Mile Point Unit 2 FSAR CHAPTER 13 CONDUCT OF OPERATIONS TABLE OF CONTENTS Section Title Pacae

13. 1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1-1

13. l. 1 Management and Technical Support

'rganization 13.1-1 13.1.1.1 Design and Operating Responsibilities 13.1-1 13.1.1.2 Organizational Arrangement 13.1-2 13.1.1.3 Qualifications 13.1-4 13.1.2 Operating Organization 13.1-5 13.1.2.1 Site Organization 13.1-5 13.1.2.2 Lines of Communication 13.1-5 13.1.2.3 Operating Shift Crews 13.1-6 13.1.3 Qualifications of Personnel 13. 1-6 13.1.3.1 Supervisory Personnel 13. 1-6 13.2 TRAINING 13.2-1 13.2.1 Unit 2 Station Staff Training Program 13.2-1 13.2.1'.1 Program Description 13.2-1 13.2.1.2 Administration of Training Programs 13 ~ 2 2 13.2.2 Training of Unlicensed Operators (NTP-12) Up to 24 Months 13.2-2a 13.2.2.1 Program 13 ~ 2 3 13.2.2.1.1 Technical Training 13 ~ 2 3 13.2.2.1.2 Systems Training 13.2-4 13.2.2.1.3 Individual Reading Assignments as Necessary 13.2-4 13.2.2.1.4 Offsite Facilities Training 13.2-4 13.2.2.1.5 On-the-Job Training 13.2-4 13.2.3 Training of Licensed Operator Candidates (NTP-10) Approximately 520 Hours 13.2-5 13.2.3.1 Technical Training 13.2-5 13.2.3.2 On-Shift Training 13.2-6 13.2.3.3 On/Offsite Simulator Training 13.2-7 13.2.3.4 Tests and Audits 13.2-7 13.2.4 Licensed NRC Operator Retraining (NTP-11) 24 Months 13 ~ 28 I 13.2.4. 1 Technical Training 13.2-8 13.2.4.1.1 Lectures 13.2-8 13.2.4.1.2 Training A'ids 13.2-9 13.2.4.1.3 Individual Study 13.2-9 13.2.4.2 On-the-Job Training 13.2-10 13.2.4.2.1 Control Manipulations 13.2-10

Nine Mile Point Unit 2 FSAR CHAPTER 13 TABIE OF CONTENTS (Cont)

Section Title Pacae 13.2.4.2.2 Licensed Operator Manipulations 13. 2-12 13.2.4.2.3 Licensed Senior Operator Manipulations 13.2-12 13.2.4.2.4 Simulator Training 13.2-12 13.2.4.2.5 Licensed Staff Members 13.2-12 13.2.4.2.6 Iog of Control Operation and Simulation 13.2-13 13.2.4. 3 Evaluation 13.2-13 13.2.4.3.1 Written Examinations 13.2-13 13.2.4.3.2 Oral Examinations and Evaluation 13.2-15 13.2.5 Radwaste Operator Training (NTP-13) 13.2-16 13.2.5.1 Programs 13.2>>16 13.2.5.1.1 Level B (Auxiliary Operator B) 13.2-16 13.2.5.1.2 Level C (Auxiliary Operator C) 13.2-17 13.2.5.1.3 On-the-Job Training 13.2-17 13.2.5.2 Retraining 13.2-18 13.2.6 General Employee Training (NTP-6) 13.2-18 13.2.6.1 General, Program 13.2-18 13.2.6.1.1 General Administrative Plans and Procedures Training 13.2-18 13.2.6.1.2 Nuclear Security Orientation 13.2-19 13.2.6.1.3 Quality Assurance Training 13.2-13 13.2.6.1.4 Site Emergency Plan and Procedures Training 13.2-19 13.2.6.1.5 Industrial Safety Training 13.2-19 13.2.6.1.6 Fire Protection Training 13.2-20 13.2.6.2 Radiation Protection Training Programs 13.2"20 13.2.6.2.1 Radiation Protection Orientation 13.2-20 13.2.6.2.2 Respiratory Protection Orientation 13.2-20 13.2.6.2.3 Radiation Protection Qualification And Requalification 13.2-20 13.2. 6.2. 4 Respiratory Protection Qualification And Requalification 13.2-20 13.2.6.2.5 Self-Contained Breathing Apparatus Qualification and Requalification 13.2-21 13.2. 6.2. 6 Self-Monitoring Qualification and Requalification 13.2-21 13.2. 7 Emergency Preparedness Training (NTP-4) 13.2-21 13.2.7.1 Functional Groups of Site Personnel 13.2-21 13.2.7.1.1 Site Personnel Granted Unescorted Access to Protected Area 13.2-21

Nine Mile Point Unit 2 FSAR CHAPTER 13 TABLE OF CONTENTS (Cont)

Section Title pa<ac 13.2.7.1.2 Emergency Director 13 '"22 I 13.2.7.1.3 Radiological Assessment and Survey/

Sample Team Coordinators 13.2-22 13.2.7:1.4 Operators 13.2-22 13.2.7.1.5 Radiological Monitoring Teams 13.2-22 13.2.7.1.6 Post-Accident, Sampling Technicians 13.2-22 13.2.7.1.7 Operational Support Center Staff 13.2-23 13.2.7.1.8 Technical Support Center Staff and Control Room Advisors 13.2-23 13.2.7.1.9 Damage Control Teams 13.2-23 13.2.7.1.10 Fire, Search and Rescue, and First>>Aid Brigade 13.2-23 13.2.7.2 Functional Groups of Nonsite Personnel 13.2-24 13.2.7.2.1 Nonsite Personnel Granted Unescorted Access to the Protected Area 13.2-24 13.2.7.2.2 Nonsite Personnel Working at the Nine Mile Point Station Site Outside the, Protected Area 13.2-24 13.2.7.2.3 Communications Chief and Staff 13.2-24 13.2.7.2.4 EOF Managers 13.2-24 13.2.7.2.5 Corporate Headcpxarters Support 13.2-24 13.2.7.2.6 Energy Information Center Staff 13.2-25 13.2.7.2.7 Nine Mile Point Security 13.2-25 13.2.7.2.8 Emergency/Disaster Service Organizations 13.2-25 13.2.7.2.9 Local Fire/Ambulance Companies and Local Medical Support 13.2-26 13.2.7.2.10 Public News Organizations 13 ~ 2 27 13.2.7.2.11 Joint News Center Director and Staff 13 e2 27 13.2.8 Instrument and Control Technician-Nuclear Training Program 13.2-28 13.2.8.1 Technical Training 13.2-28 13.2.8.1.1 Initial Training 13.2-28 13.2.8.1.2 Advanced Training 13.2-29 13.2.8.2 On-the-Job Training 13.2-31 13.2.8.3 Examination and Quizzes 13.2-32 13.2.8.4 Certification 13 2 32

~

13.2.8.5 Continued Training Program 13.2-33

Nine Mile Point Unit 2 FSAR CHAPTER 13 TABLE OF CONTENTS (Cont)

Section Title Pa<ac 13.2.8.6 Records 13 2-34 I 13.2.9 Training and Continued Training of Chemistry and Radiochemistry Technicians (NTP-1) 13.2>>36 t

13.2.9.1 Chemistry and Radiochemistry Technician Training Program 13.2-36 13.2.9.1.1 Scope 13.2-36 13.2.9.1.2 Annual Training 13.2-36 13.2.9.1.3 Technical Training 13.2-36 13.2.9.1.4 Station On-the-Job Training and Task Qualification 13.2-37a 13.2.9. 1.4. 1 Qualification Manual 13e2-37a 13.2.9.1.5 Examinations and Quizzes 13.2-38 13.2.9.1.6 Exemptions 13.2-39 13.2.9.2 Chemistry and Radiochemistry Tech-nician Continued Training Program 13.2-39 13.2.9.3 Documentation 13.2-41 13.2.9.3.1 Technician Training File 13.2-41 13.2.9.4 Chemistry and Radiochemistry Technician Advancement 13.2-41 13.2.9A Training and Continued Training Protection Technicians of'adiation (NTP-14) 13.2-42 13.2.9A.l Radiation Protection Technician Training Program 13.2-42a 13.2.9A.l.l Scope 13.2-42a 13.2.9A.1.2 Annual Training 13.2-42a 13.2.9A.1.3 Technical Training 13.2-42a 13.2.9A.1.4 Station On-the-Job Training and Task Qualification 13.2-42b 13.2.9A.1.4.1 Qualification Manual 13.2-42b 13.2.9A.1.5 Examinations and Quizzes 13.2-42c 13.2.9A.1.6 Exemptions 13.2-42c 13.2.9A.2 Radiation Protection Technician Continued Training Program 13.2-42d 13.2.9A.3 Documentation 13.2-42e 13.2.9A.3.1 Technician Training File 13.2-42e 13.2.9A.4 Radiation Protection Technician Advancement 13.2-42f 13.2.10 Training of Maintenance Mechanics (NTP-9) 13.2-42g 13.2.10.1 Mechanical Maintenance Training 13.2-42g 13.2.10.1.1 Initial Program Training 13.2-42g.1

0 Nine Mile Point Unit 2 FSAR CHAPTER 13 TABLE OF CONTENTS (Cont)

Section Title , Pacae 13.2.12.4 Records 13.2-49c 13.2.12.5 Other Station Employees 13.2-49c 13.2.12.6 Fire Protection Staff 13.2-49d 13.2.13 Reserve Fire Brigade Training and Retraining (NTP-5.1) 13.2-53

13. 2. 13. 1 Training Program 13.2-53 13.2. 14 Training of Unlicensed Personnel (NTP-8) 13.2-54

13. 2. 14. 1 Professional Personnel 13'.2-54

13. 2. 14. 2 Quality Control Personnel 13.2<<55 13.2. 14. 3 Quality Control Duties of Station Personnel 13.2-55 13.2. 15 Training Program Records 13.2-55 13.2.15.1 Records 13.2-55 13.2.16 Shift Technical Advisor Training 13.2"56 13.2.17 Applicable NRC Documentation 13.2-56 13.3 EMERGENCY PLAN 13.3-1

13. 4 OPERATION REVIEW AND AUDIT 13.4-1 13.4. 1 Administrative Controls 13.4-1 13.4.2 Safety Review and Audit of Operations 13.4-1 13.4.2. 1 Site Operations Review Committee 13. 4-1 13.4.2.2 Safety Review and Audit Board 13. 4-2 13.4.3 Audit Program 13.4-3

13. 5 PLANT PROCEDURES 13.5"1 13.5. 1 Administrative Procedures 13.5"1 13.5.1.1 Conformance with Regulatory Guide 1.33 13.5-1 13.5.1.2 Preparation of Procedures 13.5-1 13.5.1.3 Administrative Procedures 13.5-2

13. 5. 1. 3. 1 Standing Operating Orders 13.5-2 13.5.1.3.2 Special Operating Orders 13.5-3 13.5.1.3.3. Equipment Control Procedures 13.5-3 13.5.1.3.4 Control of Maintenance and Modification 13.5-3 13-. 5. 1. 3. 4. 1 Modification Procedure Objectives 13.5-3 13.5.1.3.5 Master Surveillance Testing Schedule 13.5-3a 13.5.1.3.6 Procedures for Logbook 13.5-3a 13.5.1.3.7 Temporary Procedures 13.5-4 13.5.2 Operating and Maintenance Procedures 13.5"4 13.5.2.1 Control Room Operating Procedures 13.5-4 13.5.2.1. 1 General Plant and System Operating Procedures 13. 5-4

Nine Mile Point Unit 2 FSAR CHAPTER 13 TABLE OF CONTENTS (Cont)

Section Title Pacae 13.2.10.1.2 General Training 13.2-44 13.2.10.1.3 Practical Training 13.2-45 13.2.10.2 Maintenance Mechanic Evaluations 13.2-45 13.2.11 Training of Maintenance Electricians (NTP-3) 13246 I 13.2. 11.1 Training 13.2-46 13.2. 11.1.1 Technical Training 13.2-46 13.2. 11.1.2 General Training 13.2-47 13.2. 11.1.3 Practical Training 13.2-48 13.2. 11.2 Maintenance Electrician Evaluations 13.2-48 13.2.12 Nuclear Firefighter and Nuclear Fire Chief Training (NTP>>S.O) 13.2-49 13.2.12.1 Initial Training Program 13.2-49 13.2.12.2 Practice 13.2-49a 13.2.12.3 Drills 13.2-49a 13-iva

Nine Mile Point Unit 2.FSAR CHAPTER 13 LIST OF TABLES Table Number Title 13.1-1 HEADQUARTERS SUPPORT 13.1>>2 REACTOR OPERATING MODES 13.1-3

SUMMARY

OF AP-l.l, AP-1.2, AND AP-1.3 RESPON-SIBILITIES OF CERTAIN SITE PERSONNEL 13.1-4 NUMBER AND QUALIFICATIONS OF SITE PERSONNEL 13.1-5 DELETED 13.2-1 1986 FUEL IOAD 13.2-2 TRAINING FOR MITIGATING CORE DAMAGE 13.2-3 SRO PROGRAM COMPARISON TO NUREG-0737, APPENDIX C 13.4-1 SITE OPERATIONS REVIEW COMMITTEE (SORC) 13.4-2 SAFETY REVIEW AND AUDIT BOARD (SRAB) 13.4-3 TECHNICAL REVIEW AND CONTROL

13. 5-1 RESPONSIBILITY FOR PREPARATION OF PROCEDURES 13.5-la SCHEDULE FOR DEVELOPMENT OF PLANT PROCEDURES 13.5-2 REVIEW AND APPROVAL CYCLE FOR PROCEDURES 13.5-3 ADMINISTRATIVE PROCEDURES - CROSS REFERENCE 13.5-4 APPROVAL FOR OPERATING PROCEDURES 13.5-5 ANNUNCIATOR RESPONSE INSTRUCTIONS GENERAL FORMAT 13.5-6 OPERATING PROCEDURES 13.5-7 APPLICABIE EVENTS FROM REGULATORY GUIDE 1.33

0 Nine Mile Point Unit 2 FSAR 13 . 2 TRAINING 13.2.1 Unit 2 Station Staff Training Program The objectives of this program are to:

1. Train sufficient personnel to operate and maintain the plant in a safe and reliable manner.

2. Prepare the Technical Services Group for their functions necessary for the support and safety of plant operation.

3. Prepare 'hift supervisory personnel, main control room personnel, and other licensed personnel for NRC licensing examinations.

4. Provide training for replacement of personnel due to vacancies.

5. Provide requalification training, as required by NRC regulations, to maintain a high level of proficiency throughout the plant staff.

The initial plant staff training schedule is presented on Table 13.2-1. This schedule is established to meet the scheduled fuel load date.

The overall training program for the plant staff is the responsibility of the General Superintendent Nuclear Generation. The details of the training program and its ad-.

ministration are the responsibility of the Training Superin-tendent Nuclear, who in turn is responsible to the General Superintendent Nuclear Generation.

The Training Superintendent Nuclear designates, as necessary, qualified individuals to prepare lesson plans, give lectures, tests and examinations, provide performance evaluations, and document various aspects of the training programs.

The duration of the listed courses is typical, but may vary depending on the needs of the students and the intensity of the course instruction.

13.2.1.1 Program Description The training program for Unit 2 is designed to provide the initial plant staff training, requalification training, and 13.2-1

Nine Mile Point Unit 2 FSAR replacement training at all levels of the plant organization.

The training programs incorporate the guidelines set forth in Regulatory Guide 1.8. They are designed to allow placement of personnel into specific programs based on the employee's previous experience and intended position.

Pursuant. to ANSI-3. 1, differences in the training programs based on the extent of an individual's previous nuclear power plant experience may be used to establish eligibility for cold license examinations as follows:

Individuals who have had nuclear experience at.

facilities not subject to licensing (e.g., U.S.

Navy) are evaluated on a case-by-case basis to determine training required.

Individuals certified to have completed an NRC-approved training program utilizing a nuclear power plant simulator or having completed an NRC-adminstered written examination and operating test at a comparable licensed reactor facility with or without issuance of an RO or SRO license will attend the Unit 2 Licensed Operator Candidate Course (NTP-10) as a minimum. Additional training is specified on a case basis. commensurate with the individual's needs.

3. Individuals with no previous nuclear experience will attend the Unlicensed Operator Training Course (NTP-12) prior to attending the licensed operator candidate course (NTP-10).

Other personnel attend lectures in courses on systems related to their disciplines which satisfy NRC requirements.

In the following sections each course is described to include 1) a general course description, 2) the approximate course length, 3) the organization responsible for teaching the course or supervising the instruction, and 4) a listing of personnel who will be scheduled to attend.

13.2.1.2 Administration of Training Programs All instructors teaching the licensed training and retraining programs concerning systems, integrated responses, transients, and simulator courses shall demonstrate senior reactor operator qualifications and participate in appropriate requalification programs. Other 13.2-,2

Nine Mile Point Unit 2 FSAR members of the permanent or nonpermanent training staff who are responsible for teaching technical subjects such as reactor theory, heat transfer, fluid mechanics, thermodynamics, health physics, chemistry, and instrumentation are exempt from the senior reactor operator criterion. Guest lecturers who are considered subject matter experts and are used on a limited basis are also exempt from the senior reactor operator criterion; however, they shall be monitored by a qualified instructor.

13.2.2 Training of Unlicensed Operators (NTP-12) Up to 24 Months This course is structured to teach fundamental nuclear reactor plant technology including a review of fundamental mathematics and science. The subject matter provides the student with the prerequisite knowledge for understanding

13. 2-2a

Nine Mile Point Unit 2 FSAR the material taught in the training of Licensed Operator Candidates Course (NTP-10). I The course is taught by members of the Nine Mile Point nu-clear training staff or by qualified vendors under the supervision of the Supervisor of Training Nuclear. The schedule for operator training programs is shown on Figure 13.2-1.

13.2.2.1 Program 13.2.2.1.1 Technical Training Operating personnel who are not licensed candidates shall be scheduled for training sessions on topics including:

Nuclear power plant fundamentals, 1-wk course (design familiarization) .

2. Mathematics, 2-wk course including but not limited to:

a. Algebraic functions.

b. Trigonometric functions.

c ~ Exponential functions.

d. Graphic and vector analysis.

e. Graphic application of differentiation and integration.

3. The physical sciences, 2-wk course including but not limited to:

a. Mechanics.

b. Heat and heat transfer.

c ~ Electrical fundamentals.

(1) Resistive circuits.

(2) Motors and generators.

13.2-3

0 Nine Mile Point Unit 2 FSAR (2) Quantum energies.

e. Structure and properties of materials.

f. Nuclear physics:

(1) Nucleons, binding energy.

h (2) Radioactive decay, activation.

(3) Fission, fusion.

13.2. 2. 1. 2 Systems Training The following courses are 1 to 4 weeks in duration:

1. Nuclear steam supply system.

2. Neutron monitoring system.

3. Containment and emergency systems.

4. Turbine, generator, and electrical systems.

5. Balance-of-plant and auxiliary systems.

13.2.2.1.'3 Individual Reading Assignments as Necessary 13.2.2.1.4 Offsite Facilities Training Visits to offsite training facilities may be used to tech- sub-stitute for or supplement the on-the-job training and nical training specified in Sections 13.2.2.1.1, 13.2.2.1.2, and 13.2.2.1.5.

13.2.2.1.5 On-the-Job Training On-the-job training is variable in duration until such time as they meet the experience eligibility requirements of 10CFR55 to become licensed operator candidates.

Operators shall participate in shift operations, including manipulation of equipment control when practical.

2. Training manuals similar to those provided for licensed candidates and for licensed operators shall be maintained by all operating personnel as-signed to a shift. These manuals shall contain check-lists of plant evolutions, individual reading 13.2-4

4 Nine Mile Point Unit 2 FSAR Personnel . attending this course are, but may not be limited' to, those persons designated unlicensed operators.

13.2.3 Training of Licensed Operator Candidates (NTP-10)

Approximately 520 Hours This course is structured to teach those persons designated NRC Licensed Operator candida'tes the knowledge and skills necessary to obtain an NRC Senior Reactor or Reactor Operator License.

This program is taught by members of the Nine Mile Point Nu-clear training staffs or by qualified vendors under the supervision of the Training Supervisor Nuclear.

Personnel attending this course will include, but may not be limited to:

Superintendent Operations - Nuclear.

2. Assistant Superintendent of Operations - Nuclear.

'3. Assistant to the Superintendent of Operations - Nuclear.

Station Shift Supervisor.

5. Assistant Station Shift Supervisor.

6. Chief Shift Operator.

7. Nuclear Auxiliary Operator E.

8. Superintendent, Training.

9. Assistant Superintendent of Training.

10. Training Supervisor Nuclear.

11. Generation Specialist Nuclear.

13.2-5

Nine Mile Point Unit 2 FSAR 13.2.3.1 Technical Training Technical training for candidates for the NRC Operator license shall consist of scheduled classroom sessions to cover the following subjects:

1. Theory and principles of reactor operation.

2. General and specific plant operating character-istics.

3. Plant instrumentation and control systems.

4. Plant protective systems.

S. Engineered safety systems.

6. Normal, abnormal, and emergency operating proce-dures.

7. Administrative procedures, conditions, and limitations.

8. Radiation protection and Site Emergency Plan and procedures.

9. Fuel handling and core parameters.

10. Technical specifications.

ll. Applicable portions of Title 10 of Code of Federal Regulations.

12. Heat transfer, fluid flow, and thermodynamics.

13. Use of installed plant systems to control or mitigate an accident in which the core is severely damaged (see Table 13.2-2).

14. Reactor and plant transients and accidents.

15. Procedures and equipment available for handling and disposal of radioactive material and effluents.

Nine Mile Point Unit. 2 FSAR The Training Supervisor or his designee shall review each individual's training manual quarterly.

He shall arrange with the Superintendent Operations-Nuclear to schedule manipulations or simulations so that the candidate may complete prescribed evolutions on a timely basis.

13.2.3.3 On/Offsite Simulator Training Visits to offsite reactors and training facilities including a simulator may be used to substitute for or supplement the technical and on-shift training specified in Sections 13.2,.3.1 and 13.2.3.2. Detailed records of this on/offsite training shall be placed in the individual's training file. When a simulator is used the candidate shall actually perform all logged operations by manipulation of controls of the simulator.

Operator and Senior Operator license applicants will attend simulator training as outlined in Enclosure 1 of H. R.

Denton's March 28, 1980 letter (NUREG-0737).

All Operator and Senior Operator license applicants will be administered a simulator examination in addition to the written and plant oral tests when the Unit 2 plant reference simulator is available. Until such time, examinations shall be administered pursuant to SECY 82-232.

The Unit 2 plant reference simulator is designed and con-structed to meet the requirements of Regulatory Guide 1.149 and ANSI/ANS 3.5-1981, Nuclear Power Plant Simulators for Use in Operator Training.

13.2.3.4 Tests and Audits Progress tests similar to the requalification writ-ten examinations (NTP-11) shall be used to evaluate the effectiveness of the lecture series. Assign-ments to additional individual study or attendance at repeat lectures shall be made on the basis of test results.

2. The Station Superintendent or his appointed re-presentative shall conduct oral examinations and evaluations of demonstrated or simulated perform-ance for each candidate prior to formal presen-tation to the licensing examiner. These evaluations shall be placed in the individual's training file.

13.2-7

Nine Mile Point Unit 2 FSAR

3. Certifi;cations completed, pursuant to Section 55.10

{a)(6) of 10CFR55 shall be signed by the Vice President Nuclear Generation-.

13.2-7a

Nine Mile Point Unit 2 FSAR 13.2.4 Licensed NRC Operator Retraining (NTP-ll) 24 Months This course establishes the procedures, programs, responsibilities, and requirements for requalification of NRC licensed Reactor Operators and Senior Operators at Unit 2.

This program is taught by members of the Nine Mile Point Nuclear Training staff or by qualified vendors under the supervision of the Training Supervisor Nuclear.

This program shall be structured and administered in accordance with 10CFR55. The program will be ongoing for the duration of the 2-year license period with written examinations to check the training needs of the licensed operators.

13.2.4.1 Technical Training 13.2.4.1.1 Lectures The requalification program shall include preplanned lectures to be given throughout the 2-yr period. Lectures will normally be scheduled. to average 4 hr/month/man to accommodate all licensed operating personnel. Emphasis shall be placed on those areas where annual operator and senior operator written examinations indicate that an increase in scope and depth of coverage is needed in the following general subjects:

I. Theory and principles of operation.

2. General and 'specific plant operating character<<

istics, including operational limitations, pre-cautions, and set points.

3. Plant'instrumentation and control systems.

13.2-8

Nine Bile Point Unit 2 PSAR 13 2 4,.2..6 Log of Control Operation and Simulation eben an operator or senior operator participates in a plant manipulation or performs a valk-through he shall log the date of the exercise in his ivdividual training manual and note vhether he actually performs the manipulation or a simulation it or performed under his direction. Each entry vas shall be initialed by the Station Shift Supervisor or another licensed senior operator present.

13243 Evaluation 13.2.4 3.1 Rritten Examinations Qritten examinations shall he gi,ven as prescribed by 10CPR55 The examination shall closely parallel the N RC vritten examinations outlined in 10CPR55. 21 and 10CPR55.22 20 All written examinations shall he graded and filed in the individual's training file for audit hy the HRC 30 The written examination results shall he used to determine the areas in which retraining is needed to upgrade licensed operator and senior operator knovledge Examination results will also he used to determine the scope and content of subsequent requalification cycles An operator scoring 80 percent or above in all sec-tions of the annual reqaalification examination shall 'not be required to attend further requalification lectures until the next annual requalification examination. Other operators may he excused from'ectures in subjects for'hich they scored 80 percent or above hut shall be required to attend lectures on all other topics.

5 An accelerated reqaalification program consisting of additional lectures and/or walk through shall be scheduled for all individuals vhose average score for all sections of the annual reqaalification examination is below 80 percent, or vhose in-dividual category score is below 70 percent. In-dividual programs consisting of any or all of the following shall he tailored to place emphasis where required:

a. Individual reading assignments

h. Additional on-shift evolutions 13 2-13

Nine Mile Point Unit 2 FSAR

c. Individual review with members of the operating staff.

d. Attendance at formal lectures.

The exact details of the accelerated program, in-cluding its scope and duration, will be made by a review team consisting of the - Station Superintendent, Superintendent Operations Nuclear, and Training Supervisor. Any individual who is required to participate in this program will be removed from normal shift operation for the duration of his/her program and will be given no additional responsibilities other than training.

Any operator or senior operator assigned to the ac-celerated program shall be required to successfully complete a second written and/or oral requalification examination or category at the com-pletion of his/her accelerated review program. All written reexaminations shall be graded and placed in the in4ividual's training file along with the results of any oral examination given.

Written quizzes shall be administered following each required attendance requalification lecture or series of lectures on a given topic. In addition, written quizzes may periodically be administered to determine the operator ' knowledge of material covered in specific reading assignments or walk-through exercises. These quizzes shall be graded and their results placed in the individual's training file. An operator or senior operator who fails a quiz shall require remediation.

13.2-14

Nine Mile Point Unit 2 FSAR 13.2.4.3.2 Oral Examinations and Evaluation Continuous Evaluation Systematic observation and evaluation of the performance and competency of licensed operators and senior operators shall be made by the Station Superintendent and his designated representatives. The following procedure will be used:

1. The Superintendent of Operations Nuclear and/or the Training Supervisor shall review each in-dividual training manual quarterly.

2. He shall arrange with the Station Superintendent to schedule reactivity control manipulations,'f possible, so that each individual may complete the prescribed manipulations on a timely basis.

Su erintendent's Audit On an annual basis, each operator and senior operator shall participate in an oral examination with the Station Superin-tendent or his appointed designee. This examination and evaluation shall, as a minimum, contain the following:

A discussion of required actions to be taken during abnormal and emergency conditions and the reasons for these actions.

2. A simulation of abnormal and emergency conditions while in the control room showing each action and each controlling device to be operated.

3. Should the performance of the operator or senior operator be deemed unsatisfactory, the operator or senior operator shall participate in an accelerated review program as described in Section 13.2.4.3. 1.

13.2-15

Nine Bile Point Unit 2 PSAR 4.. Upon completion of the accelerated review program but no later than one month following the initial interview he shall be subject to reexamination.

5. plant-specific simulator may be used in meeting A

the requirements of the Superintendent's Audit if operating the simulator reproduces the general characteristics of the plant involved, and the arrangement of instrumentation and controls's similar to the plant involved.

A . written record of the results of these oral examinations and evaluations shall be placed in each individual's training file.

Personnel required to attend this course are all personnel holding an NRC Reactor Operators License or Senior Operator License at Unit 2.

13.2.5 Badwaste Operator Training (NTP-13}

Training - 2 weeks

~ ~

Retraining - 2 weeks annually This program is structured to provide basic knowledge in radvaste systems and procedures for waste handling.

Included in this program is a practical section to enhance operator skills and development This program will be taught by members of. the Nine Nile Point training staff, or by a qualified vendor under the supervision of the Training Supervisor Nuclear..

13.2.5.1 Programs Technical training for Badwaste Operators shall consist of scheduled classroom sessions and jor laboratory time, offsite training, vendor training, and assigned reading to cover the following subjects.

13.2.5.1.1 Level B {Auxiliary Operator B)

Persons employed as Badwaste Operators at the entry level shall receive classroom training in the following areas:

1. General theory of liquid and solid radwaste han-dling systems

2. General sources of radioactivity and contamination.

Nine Nile Point Unit 2 FSAR certification sheets must be signed by the Radvaste Supervisor, and entered in the individualis training file.

4. Upon completion of the Practical Factors for a given level of qualification, a final exaaination vill he conducted hy the Radvaste Supervisor.

examination aay he vritten or This oral, . or a combination vritten and oral exaa. Successful completion vill be at tested to hy the Radvaste Supervisor's signature on a certification sheet for each leve1.

13. 2. 5. 2 Retraining Retraining vill he conducted as needed to keep Radvaste Operators abreast of changes to procedures, regulations, equipment modifications, and significant LZR's.

Personnel attending this program are, hut aay not he liaited to, personnel assigned to or designated as Radvaste Operators.

13.2.6 General Employee Training (HTP-6)

(

Training Days Retraining Annually These courses are structured to provide a basic knowledge of radiation protection and general eaployee training topics required for vork at the Nine Nile Point Station.

The prograa vill be taught hy aeahers of the Nine 5ile Point training staff, or by a qualified vendor under the supervision of the Training Supervisor Nuclear 13.2.6.1 General Prograa 13 2 6 1 1 General Adainistrative Plans and Procedures Training Annually, all site personnel shall attend a training class in administrative plans and procedures that shall include such portions of the adainistrative controls and procedures that should generally be known hy all site personnel. This shall include ,the composition and responsibilities of the site and station organization security access control and correct use of the photo ID system.

Nine Mile Point Unit 2 FSAR 13.2.6,.1.2 Nuclear Security Orientation Annually, all site personnel and nonsite personnel granted unescorted access to the Security Protected Area shall attend a nuclear security orientation that shall review the portions of the security plan and procedures with which they must be familiar.

13.2.6.1.3 Quality Assurance Training Annually, all site personnel shall attend a quality assurance training class which shall review the objectives of the quality assurance program, the duties of individuals and groups in connection with the program, and the importance of cooperation in the performance of work. l

2. Personnel not licensed in accordance with 10CFR55, who perform quality-related inspections, examinations, and tests shall be qualified and certified in accordance with NQA-1 and AP 1.3.1.

Certification of these personnel shall be retained in the individual's training file maintained hy the Training Superintendent.

3. Personnel who are licensed according to 10CFR55 may abc considered certified for the surveillance tests and inspections assigned to operators without further documentation in accordance with NQA-1 and AP 1.3.1.

13.2.6.1.4 Site Emergency Plan and Procedures Training Annually, all site personnel and nonsite personnel granted unescorted access to the security protected area shall receive site Emergency Plan and procedures training to review the actions they should take in an emergency. This includes personnel actions as detailed in the Emergency Plan implementing procedures, response to station alarms, evacuation routes and assembly areas, and evacuation to an assembly area offsite.

13.2.6.1.5 Industrial Safety Training Annually, all site personnel and nonsite personnel granted unescorted access to the security protected area shall attend an industrial safety training class based upon the NMPC Manual of Accident Prevention Rules.

Nine Mile Point Unit 2 FSAR 13.2.6.2.5 Self-Contained Breathing Apparatus Qualification and Requalification Initially, and annually thereafter, to be qualified to wear self-contained breathing apparatus, or to directly supervise such individuals, an individual must attend a self-contained breathing apparatus qualification course or requalification course.

13.2.6.2.6 Self-Monitoring Qualification and Requalification Initially, and annually thereafter, measure to be qualified to use radiation and radiation detection instruments to contamination levels and to use the extended radiation work permits, an individual must attend a self-monitoring qualification training course or requalification course.

Requalification of Radiation Protection Technicians shall be as described in NTP-14.

13.2.7 Emergency Preparedness Training (NTP-4)

This program is structured to describe the training requirements for site personnel and nonsite personnel who have response and functional group duties in accordance with the Nine Mile Point site Emergency Plan and Corporate Emergency Response/Recovery Plan.

This program is taught by members of the Nine Nile Point training staff, or by a qualified vendor under the supervision of the Training Supervisor Nuclear.

13.2.7.1 Functional Groups of Site Personnel 13.2.7.1.1 Site Personnel Granted Unescorted Access to Protected Area Annually, all site personnel granted unescorted access to the security protected area shall receive site Emergency Plan and procedures training to review the actions they should take in an emergency. This includes personnel actions as detailed in the Emergency Plan Implementing Procedures, response to station alarms, evacuation routes and assembly areas, and evacuation to an assembly area offsite.

13.2-21

Nine Mile Point Unit 2 FSAR 13.2.7.1.2 Emexgency Director The General Superintendent, Station Superintendents, Superintendent of Operations, Station Shift Supervisors, As-sistant Station Shift Supervisors, and other staff personnel licensed as Senior Reactor Operators compose the functional group known as emexgency directors. Annually, they shall be trained in applicable emergency procedures.

13.2.7.1.3 Radiological Assessment and Survey/Sample Team Cooxdinators The Chemistry and Radiation Management Superintendent, Chemistry and Radiation Protection Supervisor, Environmental Protection Cooxdinator, Emergency Planning Coordinator and other Chemistry and Radiation Management Department Super-visors compose the functional gxoup known as Radiological Assessment and Survey/Sample Team Coordinators.

Annually, they shall be trained in applicable emergency procedures. Annually, they shall be trained in the post-accident sampling and analysis procedures for stack gas, reactor water, drywell atmosphere, and floor and equipment drains.

13.2.7.1.4 Operators Reactor Operator licensed and non-licensed shift operating personnel compose the group known as operators. For the purpose of this paragraph, "operators" does not include the Station Shift Supervisor or the Assistant Station Shift Supervisor.

Annually, operators shall be trained in applicable emergency procedures.

13.2.7.1.5 Radiological Monitoring Teams Radiation Protection technicians "C" and above compose the functional group known as Radiological Monitoring Teams.

Annually, they shall be trained in the technician actions required for applicable emergency procedures.

13.2.7.1.6 Post-Accident Sampling Technicians Chemistry Technicians, as assigned by the Supervisor Chemis-try and Radiation Protection, shall be trained in post-accident sampling and analysis procedures for stack gas, reactor water, drywell atmosphere, and floor and equip-ment drains.

13.2-22

Nine Mile Point Unit 2 FSAR In addition, scheduled Chemistry Technicians will receive radiological assessment training.

13 2 22a

~

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK 13.2-22b

Nine Mile Point Unit 2 FSAR 13.2.7.1.7 Operational Support Center Staff This functional group consists of individuals as listed below. Annually, they shall be trained in their actions required by applicable emergency procedures.

1. Maintenance - Supervisors, Assistant Supervisors, Chief Mechanics, and Chief Electricians.

2. Instrumentation and Control - Chief Technicians IEcC.

3. Chemistry and Radiation Management - Chief Chemis-try and Radiochemistry Technicians and Chief Radiation Protection Technicians.

4. Fire Protection - Supervisor Fire Protection and Assistant Supervisors - Fire Protection.

5. Materials Management - Supervisor Storeroom, As-sistant Supervisor Storeroom, and Storekeeper.

13.2.7.1.8 Technical Support Center Staff and Control Room Advisors The Technical Superintendent and staff, Maintenance Superin-tendent and Maintenance Supervisors, Site Instrumentation and Control (IEC) Supervisor and IEC Supervisors, Reactor Analyst Supervisor, Security Supervisor, and their alter-nates compose the functional group known as the Technical Support Center (TSC) Staff.

Annually, the above groups shall be trained in the actions required of them by applicable emergency procedures.

13.2. 7. 1 9 Damage Control Teams a

Maintenance Supervisors, Assistant Maintenance Supervisors, Chief Mechanics and electricians, mechanics and electricians "C", Chief INC Technicians, and INC Technicians compose the functional group known as the Damage Control'eams.

Annually, they shall be trained in their actions and the in-formation given in emergency procedures.

13.2.7. 1.10 Fire, Search and Rescue, and First-Aid Brigade The fire, search and rescue, and first-aid brigades are com-posed of members of the Nine Mile Point Fire Department.

Annually, they shall be trained in their actions required by the emergency procedures.

13. 2-23

Nine Mile Point Unit 2 FSAR 13.2.7.2 Functional Groups of Nonsite Personnel 13.2.7.2.1 Nonsite Personnel Granted Unescoxted Access to the Protected Area Annually, all nonsite personnel granted unescorted access to the security protected area shall receive site Emergency Plan and procedures training to review the actions they should take in an emergency. This includes personnel ac-tions as detailed in the Emergency Plan Implementing Procedures, response to station alarms, evacuation routes and assembly areas, and evacuation to an assembly area offsite.

13.2.7.2.2 Nonsite Personnel Norking at the Nine Mile Point Station Site Outside the Protected Area Nonsite personnel working at the site but outside the protected area are informed of their emergency response in accordance with emergency procedures. The Manager Construc-tion Services, or his onsite representative is responsible for ensuring that appropriate personnel receive this training.

13.2.7.2.3 Communications Chief and Staff The Supexvisox Quality Assurance Operations, and his staff (as assigned by the Supervisor Quality Assurance Operations) compose che functional group known as the Communications Chief and staff. Annually, they shall be trained in their actions required by the emergency procedures.

13.2.7.2.4 EOF Managers The Corporate Emergency Response/Recovery Plan and Im-plementing Procedure CPP-4, Emergency Operations Facility (EOF), lists individuals assigned duties in the EOF, and their alternates. These individuals compose the functional group known as the EOF Managers. Initially, they shall be given an orientation in the basic principles of radiological safety. Initially, and annually thereafter, they shall be trained in their actions required by emergency procedures.

Initially, and annually thereafter, they shall be trained in their actions required by the Corporate Emergency Response/Recovery Plan and Implementing Procedures.

13.2.7.2.5 Corporate Headquarters Support Engineers listed in CPP-7 with expertise in Electrical Engineering, Mechanical Engineering, Structural Engineering,

Nine Mile Point Unit 2 FSAR Fuel Management and Operations Assessment Engineering, Licensing, and Health Physics comprise the group known as the Engineering Technical Support Center Coordinator and staff.

13.2-24a

Nine Mile Point Unit. 2 FSAR THIS PAGE INTENTIONALLX BLANK 13.2-24b

7 Nine Mile Point Unit 2 FSAR Annually, they shall be trained in their actions required by emergency pxocedures, and their callout procedures.

13.2.7.2.6 Energy Information Center Staff Full time, NMPC employees of the Energy Information Center (EIC) compose the functional group known as the EIC staff.

Annually, they shall be trained in their actions, and those of visitors, in an emergency, as required by procedure'.

13.2.7.2.7 Nine Mile Point Security Guards of the Nine Mile Point Security Force compose the functional group known as Security. Annually, they shall be trained in their actions requixed by the emergency procedures. The Training Instructors, Nuclear Security are responsible for the training.

13.2.7.2.8 Emergency/Disaster Service Organizations The New York State Department of Health, the New York State Office of Disaster Preparedness, and the Oswego County Of-fice of Emergency Preparedness compose the Emergency/

Disaster Service Organizations. Annually, key personnel from these organizations will be invited to attend emergency preparedness training. The training may include a review of the Nine Mile Point Emergency Plan and appropriate Emergency Plan implementing procedures, the Corporate Engineering Response/Recovery Plan and appropriate procedures, clas-sification of emergencies, reporting requirements, assessment, protective and corrective actions, and com-munications networks as appropriate to meet the specific training needs/requests of these organizations.

13.2-25

Nine Mile Point Unit 2 FSAR 13.2.7.2.9

~ ~ ~ ~ Local Fire/Ambulance Companies, and Local Medical Support NMPC will provide emergency preparedness training to local fire/ambulance companies and local medical support personnel as specified in .respective letters of agreement, or as required to ensure a high state of emergency preparedness and response capability between these organizations and the Nine Mile Point emergency organization. These local or-ganizations and personnel who may provide onsite emergency assistance will be encouraged to become familiar with the Nine Mile Point Station (including the physical plant layout) and key station personnel. The local fire/ambulance companies will be invited to attend annual training programs that may include:

l. Nine Mile Point facility layout.

2. Basic health physics training.

3. Onsite fire protection equipment.

4. Differences between onsite fire protection equip-ment and fire company supplied equipment.

5. Communications system.

6. Appropriate sections of the Nine Mile Point Emergency Plan.

7. Emergency Plan implementing procedures.

8. Interface with Nine Mile Point Security during an emergency.

9. Interface with the Nine Mile Point Emergency or-ganizations especially the Nine Mile Point Fire Department.

The Supervisor Fire Protection will coordinate the scheduling of training for all offsite fire support personnel.

The local medical support organizations will be invited to attend annual training that may include:

1. A review of the appropriate sections of the radiation emergency plan and procedures of the Oswego Hospital and the State University of New York at Upstate Medical Center.

13.2-26

Nine Mile Point Unit 2 FSAR

2. The Nine Mile Point emergency oiganization in-cluding interface between Nine Mile Point radiation protection personnel, local medical support personnel, and radiation medicine consultants.

3. Radiological aspects of emergency medical treatment.

4. Nine Mile Point Emergency Plan procedures fo' decontamination.

5. Communications system.

13.2.7.2.10 Public News Organizations Annually, major public news organizations serving the Nine Mile Point emergency planning zone (EPZ), such as radio and TV stations, newspapers, local wire service offices, and local correspondents to national news media will be invited to send representatives to attend emergency preparedness training. The training may include:

Orientation to the content and implementation of the Nine Mile Point Emergency Plan.

2. Emergency classification scheme.

3. Public notification system.

4. News release/public information procedures and points of contact for release of public information in an emergency.

A basic overview of nuclear power electrical (

generation and radiation concerns.

Familiarization with the physical plant layout. I The Director Nuclear Information Services will coordinate the scheduling of this program and, in conjunction with station personnel and/or contractor personnel, administer the program.

13.2.7.2.11 Joint News Center Director and Staff I

\

The position of Joint News Center Director will be filled by the Manager Public Affairs and Corporate Communications, or designee, and members of his staff.

13.2-27

0 Nine Mile Point Unit 2 FSAR Annually, they shall be trained in their actions required by procedure.

13.2.8 Instrument and Control Technician - Nuclear Training Progx am 13.2.8.1 Technical Training Training for Technicians - Instrument and Control - Nuclear shall consist of the following classroom training and/or laboratory sessions, and in addition, will include, as appropriate, the following:

1. Technical Specifications and Administrative Pxoce-dures

2. Instrument and Control Procedures

3. On-the-job training (OJT) orientation.

(

13.2.8.1.1 Initial Training General technical training provides the technician with ge-neric technical knowledge as follows:

• 1. Math

• 2. Physics 3 ~, Electricity and electronics a ~ Dc electronics

b. Ac electronics c ~ Semiconductor devices

d. Electronic circuits/troubleshooting

e. Operational amplifiers

f. Digital electronics/troubleshooting g, Introduction to computers 4 Tools and test equipment

a. Gauges, indicators

b. Calibrators (voltage and current)

C~ Power supplies d 0 Meters and recorders e~ Bridges

f. Generators, counters, and analyzers

• Required prerequisite by job specification; may be required by supervisor.

13. 2-28

0 Nine Mile Point Unit 2 FSAR g Oscilloscopes and probes

h. Soldering techniques

i. Tubing bending and fittings 3 ~ Logic probes

5. BWR technology

a. Reactor theory

b. Plant systems

c. Mitigation of core damage

6. Print reading

a. Symbols

b. Index identification, types, and classifica-tions

7. Instrumentation - measurement concepts a ~ Pressure

b. Level and flow c ~ Temperature d Conductivity measurement

e. Radiation detection

f. Vibration and seismic

8. Instrumentation - contxol methods a ~ Pressure control loop

b. Level control loop c ~ Flow control loop

d. Temperature control loop

e. Final control elements

f. Valve manifolds and valving methods

9. Instrumentation automatic - control theory

a. Modes of control

b. Control system action c ~ Proportional contxol

d. Proportional and reset control

e. Proportional and reset and rate control 13.2.8.1.2 Advanced Training Signal Processing/Conditioning (Module Operation)

a. Transmitters

b. Square Root Convexters

c. Controllers 13.2-29

0 Nine Mile Point Unit 2 FSAR

d. Electronic to Pneumatic Devices, Summers-

'function generators

e. Positioners

f. Linear Variable Differential Transmitters g, Servos

h. Chart recorders Microprocessors and computer interface a~ Microprocessor

b. Digital interface c ~ Analog Digital, Digital/Analog conversion units

d. Computer techniques

e. Display devices

f. Data loggers g, Multiplexers

h. Data links

i. Control systems Reactor plant system training Each technician will be trained in a minimum of five major systems, as assigned:

a. Reactor protection system

b. Nuclear instrumentation (SRM, IRM, LPRM, APRM, tip machines) c ~ Rod control and rod position indication

d. Rod block monitoring

e. Radiation monitoring (area and process)

f. Electric hydraulic control (EPR, EMC) g Turbine supervisory instrumentation

h. Reactor recirculation flow contxol Feedwatex control/HPCS/RCIC Containment and 'essel isolation system (PCRVICS)

k. Reactor core isolation coolant system

l. I iquid radwaste Radiation monitoring system m.

n. Video system 0 ~ Meteorological po Fire protection system

13. 2-30

Nine Mile Point Unit 2 FSAR 13.2.8.2 On-the-Job Training The On-the-Job Training (OJT) Program consists of three manuals:

1. Qualified Evaluators Manual

2. Technician Qualification Record Manual

3. Reference Manual.

The OJT Qualified Evaluators Manual provides a listing of modules/tasks and qualified evaluators approved by the Department Supervisor or his designee.

The OJT Technician Qualification Record Manual provides a listing of modules and associated tasks. Each technician will receive his own manual. An action code is used to determine whether the task was performed, simulated, observed, or discussed (P, S, 0, D). Performed is the preferred action,'ith acceptable alternatives listed in decreasing order of preference. When a task is successfully completed as witnessed by a Qualified Evaluator; the technician shall be deemed qualified to perform the task again unsupervised. This is verified by the signature and date of the Qualified Evaluator.

The OJT Reference Manual provides a complete guideline to all modules and associated tasks for the technician and the evaluator. The reference manual is provided to each Qualified Evaluator. The information provided consists of:

1. Index - module/task

2. Purpose/Scope

3. 'Instruction - Technician/Evaluator

4. Start/End a Task

5. Module

a. Cover Sheet

b. Task Reference Number Sheet C ~ Task Sheet.

Technicians participating in the on-the-job qualification program may also be administered written, practical, and/or 13.2"31

Nine Mile Point Unit 2 FSAR oral examinations. Instrument and Control Technicians - Nuclear in qualification may perform responsible work if:

1. The work is performed under the direct supervision of a qualified Instrument and Control Technician who is responsible for and signs for the work accompli shed, or

2. The individual has satisfactorily performed work and has been verified as proficient in' specific qualification element pertaining to that work. The work will be reviewed and countersigned by a Supervisor Instrument and Control or his designee, if required by procedure.

The Training Supervisor Instrument and Control or his designee shall review each individual's Qualification Manual quarterly. All manuals will be centrally located { IEC Shop).

13.2-3la

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK 13.2-31b

Nine Mile Point Unit 2 FSAR 13.2.8.3 Examination and Quizzes Examinations and quizzes shall be used to evaluate the effectiveness of the instrument and control technician training program.

2. Additional reading assignments and/or attendance at repeat classroom lectures shall be made o'n the basis of the test results.

'3. Demonstration of competency of an individual shall be accomplished by satisfactory completion of the Instrument and Control Technician Training Program with a minimum grade of 80 percent in each subject.

13.2.8.4 Exemptions Exemptions from attending specific presentations will be ap-proved by the Supervisor Instrument and Control dividual demonstrates expertise in that area if the in-by academic performance or on-the-job performance.

The Supervisor Instrument and Control shall approve all technical training lesson plans and the station practical training program.

13.2-32

E~

Nine Mile Point Unit 2 FSAR 13.2.8.5 Continued Training Program The Instrument and Control Technician Continued Training Program shall include regularly scheduled lectures, laboratory exercises, and on-the-job training.

Lectures The continued training program shall include preplanned lectures for Instrument and Control Technicians. Lectures will cover selected topics outlined in Sections 13.2.8.1.1 and 13.'2.8. 1.2 and, in addition, infrequent performed tasks, changes to procedures, station modifications, and other pertinent information. Examinations may be administered following laboratory exercises or lectures. A minimum grade of 80 percent will be required on all examinations.

Additional reading assignments and/or attendance at repeat lectures shall be made on the basis of test results.

13.2-33

Nine Mile Point Unit 2 FSAR 13.2.8.6 Records An individual Training Records Book will be maintained for each Instrument and Control Technician.

Recordings will be maintained in accordance with NTIs 2.1 (Individual Training Files) and 2.2 (Nuclear Training Department Files), and Station Records Management Procedures AP-10 and Administration of Training AP-9.0.

13.2-34

Nine Mile Point Unit 2 FSAR THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

13.2-35

Nine Mile Point Unit 2 FSAR 13.2.9 Training and Continued Training Chemistry and Radiochemistry Technicians (NTP-1)

This program is structured to provide a comprehensive tech-nical and practical program for chemistry and radiochemistry training and continued training. This program wi 11 be taught by members of the Nine Mile Point training staff, or by a qualified vendor under the 'supervision of the Training Superintendent-Nuclear.

13.2.9;1 Chemistry and Radiochemistry Technician Training Program 13.2.9.1.1 Scope This training program will consist of annual training, tech-nical training, station on-the-gob training and task qualification, and assigned reading.

13.2.9.1.2 Annual Training Annually,, k 3 months, chemistry and radiochemistry tech-nicians will attend the following training, as detailed in the appropriate administrative procedures:

1. General Employee Training and Radiation Protection Training (NTP-6).

2. Site Emexgency Plan Procedures Training.

13.2.9.1.3 Technical Training Technical training for chemistry and radiochemistry tech-nicians will consist of the following classroom training and/or laboratory sessions, and in addition will include as appropriate, the following:

1. Technical Specifications and Administrative Pxocedures.

2. Chemistry and Radiation Management Procedures.

13.2-36

Nine Mile Point Unit 2 FSAR Com an School - A

• l. Mathematics

• 2. Physics

3. Mechanical Fundamentals 4 ~ Electrical Fundamentals

• 5 Nuclear Physics

6. Health Physics Fundamentals

• 7 Chemistry Fundamentals Analytical Chemistry and Corrosion

9. Analytical Laboratory

10. Radiochemistry

11. Counting Room Laboratory

12. BWR Technology

a. Reactor Theory

b. BWR Systems (Unit Specific)

c. Mitigation of Core Damage Com an School - B Advanced training for chemistry and radiochemistry technicians will consist of four of the following classroom training and/or laboratory sessions, as assigned: I I. Atomic Absorption Spectrosopy

2. Gas Chromatography

3. Gamma Ray Spectroscopy for Chemistry and Radio-chemistry Technicians 4.. Radioactive Waste Sampling, Analysis, and Classi-5.

fStack ication Determination Effluent Monitoring Systems Sampling, Analysis, and Recordkeeping

6. Nine Mile Point Station Lesssons Learned

7. Liquid Scintillation Counting

8. Demineralizer Management

9. Post-Acident Sampling and Analysis

10. Fuel Oil Analysis

11. Ion Chromatography

12. Total Organic Carbon/Purgible Organic Carbon Analysis

13. Surveillance Testing

• Required prerequisite by )ob specifications; may be required by the supervisor.

13. 2-37

Nine Mile Point Unit 2 FSAR 13.2.9.1.4 Station On-the Job Training and Task Qualification Station on-the-job training and task qualification for chemistry and radiochemistry technicians will consist of a systematic on-the-job training and task qualification module program.

13.2.9.1.4.1 Qualification Manual Each chemistry and radiochemistry technician will be forwarded an individual Chemistry Technical Task Qualification Module Manual. The 13.2-37a

0 Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK 13.2-37b

Nine Mile Point Unit 2 PSAR Qualification Manual shall contain training modules for on-the-job training and qualification.

(

Technicians will be given assignments by the Supervisor, Chemistry and Radiation Protection or his designee, providing for regular participation in chemistry and radiochemistry technician tasks to complete required alification modules.

I Technici'ans participating in the on-the-job qualification program may also be administered written examinations and/or oral examinations.

in qualification Chemistry and radiochemistry may perform responsible work if:technicians

1. The work is performed under the direct supervision of a qualified chemistry and radiochemistry technician, who is responsible for and signs for the work accomplished, or

2. The individual has satisfactorily performed work and has been verified as proficient in a specific qualification element pertaining to that work. The work will be reviewed and countersigned by the Supervisor, Chemistry and Radiation Protection or his designee, if required by procedure.

The Training Supervisor, Chemistry and Radiation Protection or his designee will review each individual's Qualification Manual quarterly and arrange with the Supervisor, Chemistry and Radiation Protection to schedule job assignments so that the technician may complete qualification modules on a timely basis.

13.2.9.1.5 Examinations and Quizzes Examinations and quizzes will be used to evaluate the effec-tiveness of the chemistry and radiochemistry technician training program.

13.2-38

Nine Mile Point Unit 2 FSAR Information on this page has been deleted.

17.1-38a

I I

0

Nine Mile Point. Unit 2 FSAR Additional reading assignments and/or attendance at repeat, classroom lectures will be made on the basis of the test results.

13.2.9.1.6 Exemptions Exemptions from attending specific presentations will be ap-proved by the Supervisor, Chemistry and Radiation Protection if the individual demonstrates expertise in that area by academic performance or on-the-job performance..

The Supervisor, Chemistry and Radiation Protection will ap-prove all technical training lesson plans and the station on-the-job training and task qualification program.

13.2.9.2 Chemistry and Radiochemistry Technician Continued Training Program The chemistry and radiochemistry technician continued training program will be conducted on a 2-yr cycle. The program will include regularly scheduled lectures and self-study. Lectures will cover selected subjects outlined in Section 13.2.9.1.3 and also changes to procedures, station modifications, and other pertinent information.

Written examinations or quizzes may be administered fol-lowing the lectures.

13.2-39

t Nine Mile Point Unit 2 FSAR Additionally, Chemistry and Radiochemistry Instruction No. 1 describes the mechanism for keeping technicians apprised of changes to procedures, station modifications, and other per-tinent information.

13.2-40

Nine Mile Point Unit 2 FSAR 13.2.9.3 Documentation 13.2.9.3.1 Technician Training File An individual training file will be maintained for each chemistry and radiochemistry technician. Training files will contain the following information:

l. A list of the subjects of the formal training lec-tures with a record of the name of the instructor, the length of the lecture, and the date of attendance.

2. A list, by subject, of all examinations and quizzes taken. The list shall also indicate the date taken and results of all examinations and quizzes.

3. A list of reading assignments completed.

4. A record of the successful completion of the modules as contained in the Task Qualification Module Training Manual.

13.2.9.4 Chemistry and Radiochemistry Technician Advancement Technician A Chemistr and Radiochemistr to Technician B Chemistr and Radiochemistr Upon satisfactory completion of 18 months as a Technician A, Chemistry and Radiochemistry, satisfactory completion of company school, and demonstration of the satisfactory per-formance of each of the routine procedures, measurements, and calibrations basic to chemistry and radiochemistry, the employee will be promoted to Technician B, Chemistry and Radiochemistry.

13.2-41

0 Nine Mile Point Unit 2 FSAR Technician B Chemistr and Radiochemistr to Technician C Chemistr and Radiochemistr Upon satisfactory completion of 2 yr as a Technician B, Chemistry and Radiochemistry, satisfactory completion of company school, and certification by qualified supervisors of satisfactory performance of each of the routine procedures, measurements, and calibrations basic tb chemis-try and radiochemistry, the employee will be pxomoted to Technician C, Chemistry and Radiochemistry. Assignment as Technician C, Chemistry and Radiochemistry may be subject to certification and recertification with periodic reviews required by NRC or industry standards.

if Chief Technician Chemistr and Radiochemistr This position must have completed 2 yr as a Technician C, Chemistry and Radiochemistry and demonstrated satisfactory completion of company requalification training and task as-signments required for the Technician C, Chemistry and Radiochemistry.

Chief Technician, Chemistry and Radiochemistry must have knowledge of reactor and power plant operation sufficient to analyze problems, make necessary calculations, prepare com-prehensive reports, draw conclusions, and prepare recommendations. Assignment as Chief Technician, Chemistry and Radiochemistry may be subject to certification and (if

~

recertification, with pexiodic reviews required) by NRC or. industry standards. He must be able to assign and direct the work of others and be physically capable of performing assigned duties.

Pexsonnel may be provisionally advanced to a higher grade without meeting the company school requirement sating qualification for assigned duties can be identified if compen-by the Supervisor, Chemistry and Radiation Protection.

13.2.9A Training and Continued Training of Radiation Protection Technicians (NTP-14)

This program is structured to provide a comprehensive tech-nical and practical program for radiation protection tech-nician training and continued training. This program will be taught by members of the Nine Mile Point training staff, or by a qualified vendor under the supervision of the General Training Superintendent Nucleax.

13. 2-42

Nine Mile Point Unit 2 FSAR 13.2.9A.1 Radiation Protection Technician Training Program 13.2..9A.1.1 Scope This training program will consist of annual training, tech-nical training, station on-the-job training, task qualification, and assigned reading.

13.2.9A.1.2 Annual Training Annually, 2 3 months, radiation protection technicians will attend the following training as detailed in the appropriate administrative procedures:

1. General Employee Training and Radiation Protection Training.

2. Site Emergency Plan Procedures Training. I 13.2. 9A. 1. 3 Technical Training Technical training for radiation protection technicians will consist of the following classroom training and/or laboratory sessions and also will include, as appropriate, the following:

1. Technical Specifications and Administrative Procedures.

2. Chemistry and Radiation Management Procedures.

Com an School - A

• 1. Mathematics

• 2. Physics

3. Mechanical Fundamentals

4. Electrical Fundamentals

+5. Chemistry Fundamentals

• 6. Nuclear Physics

7. Health Physics Fundamentals

8. Radiochemistry

9. Counting Room Laboratory

10. Radiation Protection

11. Radiation Protection Laboratory

+Required prerequisite by job specifications; may be required by supervisor.

13.2-42a

Nine Mile Point Unit 2 FSAR

12. BWR Technology

'a. Reactor Theory

b. Systems (Unit Specific)

c. Mitigation of Core Damage Com an School - B Advanced training for radiation protection technicians will consist of four of the following classroom training and/or laboratory sessions, as assigned:

l. Gamma Ray Spectroscopy for Radiation Protection Technicians

2. Operation of the Panasonic TLD System

3. Respiratory Protection Program and Engineering Controls

4. Preparation, Packaging and Shipment, Accounta-bility, and Receipt of Licensed Radioactive Material

5. Nine Mile Point Station Lessons Learned

6. Surveillance Testing

7. Radiological Evaluations

8. Senior Radiation Protection Technician Procedure Training Program

9. Dosimetry Assignment, Beta and Neutron Monitoring 13.2.9A.1.4 Station On-the-Job Training and Task Qualification Station on-the-)ob training and task qualification for Radiation Protection Technicians will consist of a sys-tematic on-the-gob training and task Qualification Module Program.

13.2.9A.1.4.1 Qualification Manual Each Radiation Protection Technician will be forwarded an individual Radiation Protection Technician Task Qualification Module Manual. The Qualification Manual shall contain training modules for on-the-gob training and qualification.

Technicians will be given assignments by the Supervisor, Chemistry and Radiation Protection or his designee, providing for regular participation in radiation protection technician tasks to complete required qualification modules.

13 . 2-42b

Nine Mile Point Unit 2 FSAR Technicians participating in 'the on-the-job Qualification Program may also be administered written examinations and/or oral examinations.

Radiation Protection Technicians in qualification may per-form responsible work if:

1. The work is performed under the direct supervision of a qualified Radiation Protection Technician, who is responsible for and signs for the work accomplished, or

2. The individual has satisfactorily performed work and has been verified as proficient in a specific qualification element pertaining to that work. The work will be reviewed and countersigned by the Supervisor, Chemistry and Radiation Protection or his designee, if required by procedure.

The Training Supervisor, Chemistry and Radiation Protection or his designee will review each individual's Qualification Manual quarterly and will arrange with the Supervisor, Chemistry and Radiation Protection to schedule job assign-ments so that the technician may complete qualification modules on a timely basis.

13.2.9A.1.5 Examinations and Quizzes Examinations and quizzes will be used to evaluate the effec-tiveness of the radiation protection technician training program. Additional reading assignments and/or attendance at repeat lectures will be made on the basis of the test results.

13.2. 9A. I. 6 Exemptions Exemptions from attending specific presentations will be ap-proved by the Supervisor, Chemistry and Radiation Protection if the individual demonstrates expertise in that area by academic performance or on-the-job performance.

The Supervisor, Chemistry and Radiation Protection will ap-prove all technical training lesson plans and the station on-the-job training and task qualification program. I

13. 2-42c

Nine Mile Point Unit 2 FSAR 13.2.9A.2 Radiation Protection Technician Continued Training Program The radiation protection technician continued training pro-gram will be conducted on a 2-yr cycle. The program will in-

! clude regularly scheduled lectures and self-study. Lectures will cover selected subjects outlined in Section 13.2.9A.1.3 and also changes to procedures, station modifications, and other pertinent information. Written examinations or quizzes may be administered following the 'lectures.

Additionally, Radiation Protection Instruction No. of1 describes the mechanism for keeping technicians apprised changes to procedures, station modifications, and other pertinent information.

13.2-42d

Nine Mile Point Unit 2 FSAR 13.2.9A.3 Documentation 13.2.9A.3.1 Technician Training File An individual training file will be maintained for each radiation protection technician. Training files will con-tain the following information:

1. A list of the subjects of the formal training lectures, with a record of the name of the instructor, the length of the lecture, and the date of attendance.

2. A list, by subject, of all examinations and quizzes taken. The list shall also indicate the date taken and the results of all examinations and quizzes.

13. 2-42e

Nine Mile Point Unit 2 FSAR

3. A list of reading assignments completed.

4. A record of the successful completion of the modules as contained in the Task Qualification Module Training Manual.

13.2.9A.4 Radiation Protection Technician Advancement Technician A Radiation Protection to Technician B Radiation Protection Upon satisfactory completion of 18 months as a Technician A, Radiation Protection, satisfactory completion of company school and demonstration of the satisfactory performance of theroutine procedures, measurements, and calibrations basic to radiation protection, the employee will be promoted to Technician B, Radiation Protection.

Technician B Radiation Protection to Technician C Radiation Protection Upon satisfactory completion of 2 yr as a Technician B, Radiation Protection, satisfactory completion of company school and certification by qualified supervisors of satis-factory performance of the routine procedures, measurements and calibrations pertaining to radiation protection, the em-ployee will be promoted to Technician C, Radiation Protection. Assignment as Technician C, Radiation Protec-tion may be subject to certification and recertification with periodic reviews standards.

if required by NRC or industry Chief Technician Radiation Protection This position must have 'ompleted 2 yr as Technician C, Radiation Protection and demonstrated satisfactory com-pletion of company requalification training and task assign-ments required for Technician C, Radiation Protection. The Chief Technician, Radiation Protection must have sufficient knowledge of reactor and power plant operation to analyze problems, make necessary calculations, prepare comprehensive reports, draw conclusions, and prepare recommendations. As-signment as Chief Technician, Radiation Protection may be subject to certification and recertification with periodic reviews. 'e must be able to assign and direct the work of 13 .2.-42 f

Nine Mile Point, Unit 2 PSAR others and be physically capable of performing assigned duties.

Personnel may be provisionally advanced to a higher grade without meeting the company school requirements if compen-sating qualification for assigned duties can be identified by the Supervisor, Chemistry and Radiation Protection.

13.2.10 Training of Maintenance Mechanics (NTP-9)

This couxse is structured to provide a comprehensive tech-nical and practical program for mechanical maintenance training. This course will be taught by members of the Nine Mile Point Training Staff, or by a qualified vendor under the supervision of the Training Superintendent Nuclear.

13.2.10.1 Mechanical Maintenance Training Mechanical maintenance training is divided into three categories:

1. Initial training

a. Mechanic Helper School

b. Mechanic A School

c. Mechanic B School.

2. Continued training

a. Routine training

b. Nonroutine txaining.

3. On-the-gob training (OJT).

Any or all of these categories may involve the use of:

Classroom training

a. Lecture, and/or

b. Videotape, and/or C~ cwork booklets, and/or

d. Demonstrations, and/or Assigned reading 13.2-42g

Nine Mile Point Unit 2 FSAR

f. Computer-assisted training (CAT).

2 Shop/lab practicals

a. Hands-on pass/fail practicals, and/or

b. Checkoff sheets, and/or

c. Written examinations.

3. On-the-job training

a. In the plant

b. Training center mockups.

13.2.10.1.1 Initial Training Program Mechanic Helper School Successful completion of Mechanic Helper School with its associated shop practicals and on-the-job training, as described in the individual's training manuals, is required before progressing to Mechanical "A" School. Part 1 consists of generic subjects and must be successfully completed prior to entry into Part 2. Mechanic Helper School is conducted twice annually and consists of two parts.

13. 2-42g. 1

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLY BLANK 13.2-42g.2

Nine Mile Point Unit 2 FSAR Part 1, which may be attended jointly by electricians and mechanics, consists of: \

Procedures Familiarization Mathematics for Repairmen Physical Science Measuring Tools Basic Rigging (includes forklift)

General Shop Practices Reactor Familiarization Lubrication Communications Systems Technical Specifications Orientation Systems Training Part I Part 2, designed for a Mechanic Helper level, consists of:

Mechanical Print Reading Corrosion Chemistry Properties of Materials Care and Use of Hand Tools Care and Use of Power Tools Cutting, Welding, and Introduction'to Fabrication Lubrication and Turbine Oil Reservoir Filters, Strainers, and Pipe Obstructions, Condensers and Tubes Basic Pneumatics Basic Hydraulics Storeroom and Document Control Computers - Part I

2. Mechanic 'A'chool Successful completion of Mechanic 'A'chool, with its as-sociated shop practicals and on-the-job training, as described in the individual's training manual, is required before progressing to Mechanic 'B'chool. Mechanic is conducted annually and consists of: 'A'chool Math/Science Review Plant Systems Part II Helper School Review Advanced Metals Basic Bearings and Lubrication Basic Valves Basic Pumps Basic Fans, Blowers, and Air Compressors Filters, Traps, and Strainers Basic Packing Hangers and Restraints Precision Instruments 13.2-43

Nine Mile Point Unit 2 FSAR Thermal Insulation Machine Shop Familiarization Maintenance Work Practices - Part I Document Control Computers - Part II Storeroom Computers - Part II Bolting and Fastening Brazing and Braze Welding Overview Principles of TIG Plasma - Arc and Air Carbon Arc Overview Hazaxdous Substances

3. Mechanic 'B'chool Successful completion of Mechanic 'B'chool, with its as-sociated shop practicals and on-the-job training, as described in the individual' training manual, is required before a mechanic is considered a fully qualified journeyman level mechanic (Mechanic C). Mechanic 'B'chool is con-ducted twice each 3-yr cycle and consists of:

'A'chool Review Plant Systems Part Advanced Rigging III

~ Overhead Crane Certification

~ Lift-A-LoftCertification

~ Information only - Cherry Picker Quali fication, as appropriate Advanced Valves and Piping Advanced Pumps Alignments/Vibration Mechanical Seals Snubbers/Restxaints Basic. Diesel Generator Bearings - Roller/Sliding Heat Exchangers/Condensers Turbine Generators Heating and Air Conditioning Use of Organic Compounds Mechanical Modifications Technical Specifications - Mechanical OJT Orientation QA Requirements for Mechanics Emergency Training Maintenance Work Practices - Part II Surveillance Procedures Upon sati s factory completion of Mechanic chool, the candidate becomes a fully quali fied j ourneyman level mechanic, which allows him to work independently as a lead man on any mechanical job at Unit, 2.

13.2-44

Nine Mile Point Unit 2 FSAR Limited qualifications may be authorized by meeting specified xequirements and demonstration of abilities for any task in the program from the time an individual enters the program until he becomes fully qualified.

Mechanics who have not demonstrated a particular task, but have been evaluated by Maintenance Supexvision to possess the knowledge and basic skills necessary to do the-job, can perform the job, providing controls are in place to ensure the work has been completed satisfactorily (i.e., detailed work package, added work group hold points, or. sufficient testing to ensure the job has been completed in a manner consistent with its importance).

Any person, regardless of training status, may perform tasks or procedures requiring demonstrated skill under the direc-tion of a trained mechanic, factory representative, or Main-tenance Supervisor. Direction specifically means having one of these persons eithex physically present or in com-munication with the person performing the work to provide direction.

13.2.10.1.2 Continued Training The continued txaining program is established to ensure that essential job-related knowledge and skills are maintained and improved. The appropriate categories of continued training are entered into upon completion of Mechanic The Continued Training Program consists of two '8'chool.

categories: routine txaining and nonroutine training.

Routine trainiag is training normally required on a specified time basis. This training typically consists of:

1. General employee training

2. Radiation work training

3. Emergency Plan txaining

4. Self-contained breathing apparatus training

5. Hearing testing

6. Eye examinations.

Additionally, routine training shall incorporate:

1. Industry events

Nine Mile Point Unit 2 FSAR

2. License event reports (LERs)

3. Nine Mile Point occurrence reports

4. Plant modifications update

5. Station procedures changes.

Nonroutine training is training scheduled through normal training requests procedure. This training is provided to address observed or anticipated training needs identified by the Maintenance Department.

Persons selected by Mechanical Maintenance Supervision to attend nonroutine training are required to demonstrate mastery of the subjects.

Task difficulty, importance to plant safety, reliability, and ALARA are factors in determining traihing needs and depth of coverage.

This nonroutine training consists of, but is not limited to, the following:

Training for infrequently performed tasks such as:

a. Rolling vessel stub tubes

b. Major overhaul of recirculation pump internals

c. Under vessel and refuel-related work.

2. Training to improve degraded job performance recog-nized in either individual workers or work groups, such as:

a. Excessive reworks

b. Less than normal quality.

3. Training on complex systems, systems modifications, or equipment changes, such as:

a. Development of a new process dealing with recirculation seal cartridges

b. Control rod drive overhaul c ~ Heavy Loads criteria.

13.2-45a

Nine Mile Point Unit 2 FSAR Methods of implementing the Continued Training Program con-sist of any combination of the following:

Classroom- Lectures, self study, demonstra-tions, written examinations, oral examinations, or computer-assisted training.

2. Shop Practice - Hands-on pass/fail practicals, written examinations, or checkoff sheet procedural testing.

In-plant task performance graded by an evaluator to predetermined criteria.

Continued training may be accomplished by attending initial training, on-the-5ob training, or specially developed training.

13.2.10.1.3 On-the-Job Training (OJT)

On-the-job training is conducted in conjunction with Mechanic Helper School, 'A'chool, and 'B'chool, as appropriate.

Additionally, OJT is utilized when conducting continued training.

The Training Department, in cooperation with plant main-tenance management, assumes the responsibility of analyzing the recognized tasks and incorporating those tasks, as appropriate, along with the appropriate references, into the training manual.

The Maintenance Department designates the evaluators, and the Training Department trains the evaluators.

The Maintenance Department has the overall responsibility for implementing the OJT program with a Generation Specialist from the Training Department, assuming the responsibility of documenting the completed OJT tasks on a quarterly basis, and supplying updates and modifications to the training manuals, as required.

The training manuals are maintained in an accessible desig-nated area with a current list of task evaluators and, in-structions for evaluations.

Training manuals consist of the following:

13.2-45b

Nine Mile Point Unit 2 FSAR

1. Training courses and/or evaluations required in each level of training with appropriate signoffs.

2.- Any milestones that might be established by Main-tenance Supervision.

3. On-the-job training assignments and signoffs.

13.2.10.2 Mechanical Evaluations When appropriate, examinations are given to evaluate trainee mastery. Examinations may include written and/or practical segments. A mechanic must demonstrate mastery by achieving a score of at least 80 percent on any examination or com-bination of examinations related to any course.

All examinations, both written and practical, become file.

a mat-ter of record in the individual's training An accelerated retraining program consisting of additional lectures, additional studies, and/or practical training is scheduled for any mechanic whose average score is below 80 percent.

13.2-45c

Nine Mile Point Unit 2 PSAR THIS PAGE INTENTIONALLY BLANK 13..2-456

Nine Mile Point Unit 2 FSAR 13.2.11 Training of Maintenance Electricians (NTP-3)

This course is structured to provide a comprehensive tech-nical- and practical program for electrical maintenance training. This program will be taught by members of the Nine Mile Point Training Staff, or by a qualified vendor.un-der the supervision of the Training Superintendent Nuclear.

13.2.11.1 Electrical Maintenance Training Electrical maintenance training is divided into three categories:

1. Initial training

a. Electrician Helper School

b. Electrician 'A'chool

c. Electrician 'B'chool

2. Continued training

a. Routine training

b. Nonroutine training

3. On-the-job training (OJT)

Any or all of these categories may involve use of the following:

Classroom training

a. Lecture, and/or

b. Videotape, and/or

c. Work booklets, and/or

d. Demonstrations, and/or e Assigned reading

f. Computer-assisted training (CAT).

2. Shop/lab practicals

a. Hands-on pass/fail practicals, and/or 13.2-46

Nine Mile Point Unit 2 FSAR

b. Checkoff sheets, and/or

c. Written examinations.

3. On-the-job training

a. In the plant

b. Training center mockups.

13.2.11.1.1 Initial Training Program

1. Electrician Hel er School Successful completion of Electrician Helper School is required before progressing to Electrician 'A'chool.

Part 1 consists of generic subjects and must be successfully completed prior to entry into Part 2. Electrician Helper School is conducted twice annually and consists of two parts.

Part 1, which may be attended jointly by mechanics and electricians, consists of:

Procedures Familiarization Mathematics for Repairmen Physical Science Measuring Tools Basic Rigging (includes forkxift)

General Shop Practices Reactor Familiarization Lubrication Communications Systems Technical Specifications Orientation Systems Training Mech.

Part 2, designed exclusively for the Electrician Helper level, consists of:

Basic Electricity Maintenance of Electrical Equipment,,

Battery Safety,.

Grounding Fuses Conduits Electrical Test Equipment and Tools Lighting Storeroom and Document Control Computers Bearings Use of Calibrated Tools 13.2-47

Nine Nile Point Unit 2 PSAR Trigonometry Print Reading - Part I

2. Electrician 'A'chool Successful completion of Electrician 'A'chool, with its associated shop practicals and on-the-job training, as described in the individual's training manual, is .required before progressing to Electrician 'B'chool.

Electrician 'A'chool is conducted annually and consists of-Electric Theory Control Circuit Theory Motor Controllers Relays and Control Circuits Use of Test Equipment - Part II Maintenance of Electrical Equipment. - Par't II Electric Heaters Disconnect Switches Cable Terminations Electric Motors (less 25 hp)

Transformers Batteries Heat Trace Soldering Bucket Truck Safety Maintenance Work Practices Part I Print Reading - Part II Electrical Separation Criteria Storeroom Computer - Part II Document Control Computer - Part II Solenoids Cable Trays and Conduits Emergency Lighting Welding Machines Equipment Qualification - Part I Elevator Overview Washer and Dryer Naintenance Voltage Regulators Solid State Theory Systems Training - Part II

3. Electrician 'B'chool Successful completion of Electrician 'B'chool, with its associated shop practicals and on-the- job training, as described in the individual's training manual, is required 13.2-48

Nine Nile Point Unit 2 FSAR before an electrician is considered a fully qualified jour-neyman level electrician (Electrician C). Electrician is conducted twice every 3-yr cycle and consists of:

'B'chool-Maintenance of Electrical Equipment - Part III Valve Operators Fire Protection Maintenance Air-Conditioning Equipment Medium Volta'ge Circuit, Breakers Low Voltage Circuit Breakers Medium Voltage Cable Terminations Cable Motors (over 25 hp)

Use of Test Equipment - Part Mechanical Couplings III Generator and Exciter Transformers and Buses Batteries and Chargers Communication Systems Use of Organic Compounds Maintenance Work Practices - Part II Print Reading - Part Electrical III Modifications Surveillance Procedures Technical Specifications - Electrical OJT Orientation Vibration Multipin Connectors Equipment Qualification - Part II Emergency Training Advanced Rigging

~ Overhead Crane

~ Life-A-Loft Certification

~ Heavy Loads Criteria UPS System Control Circuitry Systems Training - Electrical QA Requirements for Electrician Upon satisfactory completion of Electrician 'B'chool, the candidate becomes a fully qualified journeyman level electrician, which allows him to work independently as a lead man on any electrical job at Unit 2.

Limited qualifications may be authorized by meeting specified requirements and demonstration of abilities for any task in the program from the time an individual enters the program until he becomes fully qualified.

13.2-48a

Nine Mile Point Unit 2 FSAR Electricians who have not demonstrated a particular task, but have been evaluated by Maintenance Supervision to pos-sess the knowledge and basic skills necessary to do the job, can perform the gob, providing controls are in place to en-sure the work has been completed satisfactorily (i.e.,

detailed work package, added work group hold points, or suf-ficient testing to ensure the gob has been completed in a manner consistent with its importance).

Any person, regardless of training status, may perform tasks or procedures requiring demonstrated skill under the direc-tion of a trained electrician, factory representative, or Maintenance Supervisor. Direction specifically means having one of these persons either physically present or in com-munication with the person performing the work to provide direction.

13.2.11.1.2 Continued Training The Continued Training Program is established to ensure that essential gob-related knowledge and skills are maintained and improved. The appropriate categories of continued training are entered into upon completion of Electrician The Continuing Training Program consists of two 'B'chool.

categories: routine training and nonroutine training.

Routine training is training normally required on a specified time basis. This training typically consists of:

General employee training

2. Radiation work training

3. Emergency Plan training Self-contained breathing apparatus training Hearing testing Eye examinations.

Additionally, routine training shall incorporate:

Industry events

2. License event reports (LERs)

3. Nine Mile Point occurrence reports 4, Plant modifications update 13.2-48b

Nine Mile Point Unit 2 FSAR

5. Station procedures changes.

Nonroutine training is training scheduled through 'normal training requests procedure. This training is provided to addre'ss observed or anticipated training needs identified by the Maintenance Department.

Persons selected by Electrical Maintenance Supervision to attend routine training are required to demonstrate mastery of the subjects.

Task difficulty, importance to plant safety, reliability, and ALARA are factors in determining training needs and depth of coverage.

This nonroutine training consists of, but is not limited to, the following:

Training for infrequently performed tasks, such as:

a. Test Equipment - Part IV

b. Oil Circuit Breakers

c. Air Circuit Breakers

d. Motor-Operated Disconnects

e. Print Reading << Part IV

f. Containment Penetrations

g. Generator and Exciter - Part II

h. Transformers and Buses - Part II

i. Voltage Regulators.- Part II.

2. Training to improve degraded job performance recog-nized in either individual workers or work groups, such as:

a. Excessive reworks

b. Below normal quality.

13.2-48c

Nine Mile Point Unit 2 FSAR

3. Training on complex systems, systems modifications, or equipment. changes.

Methods of implementing the'Continued Training Program con-sist of any combination of the following:

Classroom- Lectures, self-study, demonstra-tions, written examinations, oral examinations, or computer-assisted training.

2. Shop Practice - Hands-on pass/fail practicals, written examinations, or checkoff sheet procedural testing.

3. OJT- In-plant task performance grades by an evaluator to predetermined criteria.

Continued training may be accomplished by attending initial training, on-the-job training, or specially developed training.

13.2.11.1.3 On-the-Job-Training (OJT)

On-the-job training is conducted in conjunction with Elec-trician Helper School, 'A'chool, and 'B'chool, as appropriate.

Additionally, OJT is utilized when conducting continued training.

The Training Department, in cooperation with plant, main-tenance management, assumes the responsibility of analyzing the recognized tasks and incorporating those tasks, as appropriate, along with the appropriate references, into the training manual.

The Maintenance Department designates the evaluators, and the Training Department trains the evaluators.

The Maintenance Department has the overall responsibility for implementing the OJT program with a Generation Specialist from the Training Department, assuming the responsibility of,reviewing the electricians'ompleted OJT tasks on a quarterly basis, and supplying updates and modifications to the training manuals, as required.

Periodically, and at least after completion of a level, the manual will be photocopied and filmed for plant records by Training. ll 13.2-48d

Nine Mile Point Unit 2 FSAR The training manuals are maintained in the Electrical Shop with a current list of task evaluators and instructions for evaluations.

Training manuals consist of the following:

1. Training courses, laboratories, and/or evaluations required in each level of training, with appro-priate signoffs.

2. Any milestones that might be established by Main-tenance Supervision

3. On-the-job training assignments and signoffs.

13.2.11.2 Electrical Evaluations When appropriate, examinations are given to evaluate trainee mastery. Examinations may include written and/or practical segments. An electrician must demonstrate mastery by achieving a score of at least 80 percent on any examination or combination of examinations related to any course.

Any examinations, both written and practical, become a mat-ter of record in the individual's training file.

An accelerated retraining program consisting of additional lectures, additional studies, and/or practical training is scheduled for any electrician whose average score is. below BO percent.

13.2-48e

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLYBLANK 13.2-48f

Nine Mile Point Unit 2 FSAR 13.2.12 Nuclear Firefighter and Nuclear Fire Chief Training (NTP-5.0)

This program is structured to provide comprehensive training in firefighting techniques, including fundamentals in power plant systems and safety systems with a practical program for development of skills. This program will be taught by members of the Nine Mile Point Training Staff, or by a qualified vendor under the supervision of the Training Superintendent Nuclear.

13.2.12.1 Initial Training Program The initial classroom instruction shall include:

Indoctrination of the plant fire-fighting plan with identification of each brigade. member' responsibilities.

2. Identification of the type and location of fire hazards and associated types of fires that could occur in the plant.

3. The toxic and corrosive characteristics of expected p "oducts of combustion.

Identification of the location of fire-fighting equipment for each fire area and familiarization with the layout of the plant, including access and egress routes to each area.

5. The proper use of available fire-fighting equipment and the correct method of fighting each type of fire. The types of fires covered willfires include in fires in energized electrical equipment, fires cables and cable trays, hydrogen. fires, involving flammable and combustible liquids or hazardous process chemicals, fires resulting from construction or modifications (welding), and record file fires.

6. The proper use of communication, ventilation, and emergency breathing equipment.

7. The proper method for fighting fires inside buildings and confined spaces.

8. The direction and coordination of the fire-fighting activities (fire brigade leaders only).

13.2-49

Nine Mile Point Unit 2 FSAR

9. Review of fire-fighting strategies and procedures.

10; Review of plant modifications and corresponding changes which affect fire-fighting plans.

ll. The instruction will be provided by qualified individuals who are knowledgeable, experienced, and trained in fighting fires that could occur in the plant and using equipment available in the nuclear power plant.

12. Instruction will be provided to fire brigade members and fire brigade leaders.

13. Regular planned meetings will be held, at a minimum, every 3 months for brigade members to review changes in the fire protection program and other subjects as necessary.

14. Periodic training sessions will be held to repeat the classroom instruction program for brigade members over a 2-yr period. These sessions may be concurrent with the regular planned meetings.

13.2.12.2 Practice Practice sessions will be held for each shift fire brigade on the prop r method of fighting fires that could occur in a nuclear power plant. These sessions will provide brigade members with experience in actual fire extinguishment and the use of emergency breathing apparatus under conditions encountered in fire fighting. These practice sessions will be provided once each year for each fire brigade member.

13.2. 12. 3 Drills

1. Most fire brigade drills will be performed in the plant so that the fire brigade can practice as a team. Other drills will occur in the site area (transformer yard, etc.).

2. Drills will be performed at regular intervals not to exceed 3 months for each shi ft fire brigade.

Fire brigade members may participate in each drill, but must participate in at, least two drills per year.

A. sufficient number of these drills, but not less than one for each shift, fire brigade per year, will be unannounced to determine the fire-fighting 13.2-49a

Nine Mile Point Unit 2 FSAR readiness of the plant fire brigade, brigade leader, and fire protection systems and equipment.

Persons planning and authorizing an unannounced drill will ensure that the responding shift fire brigade members are not aware that a drill has been planned until it will not be normally has begun.

scheduled Unannounced drills closer than.4 weeks.

At least one drill per year should be performed on a "back shift" for each shift fire brigade.

The drills will be preplanned to establish the training objectives of the drill and will be critiqued to determine how well the training objectives have been met.

Unannounced drills will be planned and critiqued by members of the management staff responsible for plant safety and fire protection. Performance deficiencies of a fire brigade or of individual fire brigade members will be remedied byor scheduling additional training for the brigade members.

Unsatisfactory drill performance will be followed by a repeat drill within 30 days.

At 3-yr intervals, a randomly selected unannounced drill will be critiqued by qualified individuals independent of NMPC's staff. A copy of the written critique shall be available for NRC review.

Drills will, as a minimum, include the following:

Assessment of fire alarm effectiveness, time required to notify and assemble the fire brigade, and selection, placement, and use of equipment and fire-fighting strategies.

Assessment of each brigade member' knowledge of his or her role in the fire-fighting strategy for the area assumed to contain the fire. Assessment of the fire brigade member ' conformance usewith of established fire-fighting procedures and fire-fighting equipment, including self-contained communication emergency breathing apparatus, equipment, and ventilation equipment, to the extent practicable.

The simulated use .of fire-fighting equipment required to cope with the situation and type of fire selected for the drill. The area and type of 13.2-49b

F I'I,

Nine Mile Point Unit 2 FSAR

13. 2. 13 Reserve Fire Brigade Training and Retraining (NTP-5.1)

Training - 1 day Retraining - annual meeting This program is structured to provide a functional knowledge in firefighting fundamentals. This program will be taught by members of the Nine Mile Point Training Staff, or by a qualified vendor under the supervision of the Training Superintendent Nuclear.

13.2.13.1 Training Program Training will include, but not be limited to, the following:

1. Initial training: Fire school - 1 day .session 2 Retraining: Annual meetings shall be held for all Reserve Fire Brigade members to review changes in

~

the fire protection program and other subjects as necessary.

I 13.2-53

I' Nine Mile Point Unit 2 FSAR 13.2.14 Training of'nlicensed Managerial Personnel (NTP-8)

This program describes the responsibilities for training of professional personnel assigned to Unit 2. Specific programs will be taught by members of the Nine Mile Point Training Staff or by subject matter experts as designated by the General Superintendent Nuclear or 'Station Superintendent.

13.2.14.1 Professional Personnel It shall be the responsibilty of each individual management or professional person assigned to the plant/station or site to maintain an up- to-date resume of his professional training and experience.

2. The General Superintendent Nuclear Generation or Station Superintendent, with the assistance of the Training Superintendent, shall from time to time arrange for training activities for management and professional personnel as .they may consider required. These may include:

a. Assignments at other operating reactors or simulators.

b. Participation in construction or startup activities.

C ~ Attendance at lectures, seminars, or retraining sessions.

d. Formal academic training.

3. A training file shall be maintained for each individual assigned as professional personnel.

This file shall contain a record of formal training sessions attended and a resume of the individual's technical competence. A checklist shall be included of the major job assignments for which the individual is qualified.

4, A record of attendance at general employee training shall be included in each individual's training file.

13.2-54

Nine Mile Point Unit 2 FSAR TABLE 13.2-1 1986 PUEF IOAD Start Completion Section Title Date Date 13.2.2 Training of Un- 1/1/84 Continuous licensed Oper-ations NTP-12 13.2.3 Training of Li-censed Operator Candidates APN-10A:

• 1st Start Cold Iicense 1/85 6/85

• 2nd Start Cold License 6/85 12/85

• 3rd Start Cold Iicense 2/86 7/86 1st Hot License Course 3/87 12/87 13.2.4 license Oper>> Implemented Continuous ator Retraining 1/86 NTP-11 13.2.5 Radwaste Oper- Implemented Continuous ator Training 1/84 NTP-13 13.2.6 Other Unli- This training is presently through censed Personnel in place for Unit 1; 13.2.14 these training programs are generic to both units and are presently being conducted.

• Personnel attending these classes will hold current NRC RO and SRO licenses on Unit 1 or meet all of the requirements set forth in lOCPR55 and NUREG 737.

NOTE: This schedule is subject to fuel load in 1986.

Nine Mile Point Unit 2 FSAR TABLE 13.2-2 (Cont)

H.R. Denton INPO Letter Rev. 1 3 28 80 III15 81 B. Administrative Procedures AP>>l.l, 1.2, 1.3

• This program has been developed to ensure that appropriate personnel are trained in the use of installed plant systems to recognize, control, and/or mitigate an accident in which the core is severely damaged.

The columns adjacent to the course material reference the paragraph of H.R. Denton's letter of March 28, 1980, to all Power Reactor Applicants and Licensees, Enclosure 3, and/or INPO's Guidelines for Training to Recognize and Mitigate the Consequences of Core Damage, Rev. 1, January 15, 1981.

In addition to the personnel listed in Section 13.2.3, the following will attend training for mitigating core damage:

1. Technical and maintenance superintendents

2. Reactor analysts,'upervisors, and technicians

3. Station superintendent IEC technicians

5. Radiation protection technicians 7 of 7

Nine Mile Point Unit 2 FSAR TABLE 13.2-3 SRO PROGRAM COMPARISON TO NUREG-0737* APPENDIX C Duration NUREG-0737 A endix C ~hr 6.2 Applied Fundamentals (120 hr) Reactor Theory 80 Plant, Specific Rx Technology Simulator Week 8 Chemistry & Corrosion Control Plant Systems Train-I&C ing 40 Plant Materials Plant Systems Train-Plant Thermal Cycle ing 4 Thermodynamics 40

[ 172-192 [

6.3 Management/Supervisory Skills Admin Procedures, (40 hr) Controls & Limita-Leadership tions 24 Interpersonal Communication (Leadership Training)

Motivation of Personnel (Procedural Training) 16 Problem & Decisional Analysis [40-60]

Stress Human Behavior Command Responsibilities &

Limits 6.4 Plant Systems (200 hr) Plant Systems Training [200-300[

6.5 Administrative Controls Simulator Training 25 (80 hr) Admin Procedures, Controls &

Limitations 40

[65-70]

6.6 General Operating Procedures Simulator Training [30-70]

(30 hr) 6.7 Transient/Accident Analysis Simulator Training [30-70]

(30 hr) 6.8 Simulator Training Simulator Training [120-280]

• This table is typical of each training class; however, the actual hours may vary based upon the qualifications and experience of the training class.

1 of 1

0 NINE MILE POINT UNIT 2 FSAR TABLE 13.5-4 APPROVAL FOR OPERATING PROCEDURES Review and/or approvals required.

Procedure element should always be considered if applicable.

May be issued by either Superintendent or Operations Supervisor.

Approval required if procedure is in Supervisor's or Superintendent's department area.

Unit 1 and Unit 2 for site procedures; otherwise appli.cable unit only.

2of2

0-THlS FIGURE HAS BEEN DELETED FIGURE 13.2-1 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

0