ML20105D056

Rev 16 to Operational QA Plan

ML20105D056
Person / Time
Site:	Monticello, Prairie Island
Issue date:	05/18/1992
From:	Blair C, Mendele D NORTHERN STATES POWER CO.
To:
Shared Package
ML20105C993	List: ML20105C990 ML20105D056
References
NUDOCS 9209240248
Download: ML20105D056 (103)

Text

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O HORTHER!1 STATES POWER COMPANY f

414 Nicollet Hall Minneapolla, MN- 55401 i

t OPERATIONAL OUALITY ASSURANCE PLAN REV 16 O

Revicwed By: A uf MMd Date: !/N!9k David J fy'ndele Director Tower Supply Quality Assurance Approved By: , /I - 4 Date: I C. J/./(draig) Blair Exe%tive Vice President Power Supply O

9209240240 920630-

~PDR -.ADOCK 05000282 g -PDR'

oparcticnol Quality Accurenco Plcn novision 16 IAh192,..QL.SODICALQ L' age 1.0 Policy Statomont 1 2.0 Introduction 6 3.0 organization 7 4.0 Operationni Quality Annurance Program 23 5.0 Modification Control 29 6.0 Procurement Document Control 30 7.0 Inntructiona, Proceduren and Drawingo 32 8.0 Docu.9nt Control 34 9.0 Control of Purchased Material, Equipment and Servicon 37 10.0 Identification and Control of Materiala, Partu and 39 Componenta 11.0 Control of Special Procennes 41 12.0 Innpoetion 43 13.0 Tont Control 47 14.0 Control of Measuring and Tent Equipment 49 1 5 . 0 lla n d i t. a g , Storago and Shipping 50 16.0 Inapoction, Test and Operating Statun 52 17.0 lionconforming Materiala, Partn or Componenta 55 10.0 Corrective Action 57 19.0 Quality Annuranco Recorda 58 20.0 Audits 61 Appendix A - Monticello Structuren, Systemn, and Components Subject to Appendix B of 10CFR50 63 Appendix B - Prairie Inland Structuren, Syntemn, and Componento Subject to Appondix B of 10CFR50 69 Appendix C - IJuclear Plant Fire Protection Program 77 Appendix D - Rovinion 16 Chango Summary 93

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Cp0rotienol Quolity Accuranac Plcn Revision 16

-~ 1.0 Eolicy Statement l.1 Northern States Power Company (NSP) has established and is implementing an Operational Quality Assurance Program. This quality assurance program is applicable  ;

to NSP nuclear plants that are regulated under provisions of an NRC Operating License.

, 1.2 The quality assurance program, as applied to activities affecting safety related functions, shall comply with and be responsive to applicable regulatory requirements -

and applicable industry codes and standards including:

1. 10CFR50, Appendix B.

2. NRC Operating Licenses.

3. The ASME Boiler and Pressure Vessel Code,Section XI, " Inservice Inspection".

4. 10CFR21 " Reporting of Defects and Noncompliance".

5. 10CFR71, Subpart H, " Quality Assurance".

6. Nuclear Plant Fire Protection Program, Operational Quality Assurance Plan, Appendix C. '

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7. NSP Plant Security Plans.

8. NSP Radiation Environmental Monitoring Program.

9. ANSI N45.2.6-1978, Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants, as modified by Regulatory Guide 1.58, Revision 1.

10. ANSI N45.2.12-1977, Requirements for Auditing of Quality Assurance Programs for Nuclear _ Power Plants.

11. ANSI N45.2.23-1978, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Pl' ants, as modified by Regulatory Guide 1.146, August, 1980.

1.3 The Operational Quality Assurance Program shall incorporate: (1) the requirements of-ANSI-N16.7-1976, ac modified by Te.ble 1-1 and (2) the requirements of the followir.g standards to the extent specified by ANSI N18.7-1976, as modified by the regulatory position of the Regulatory or Safety Guides referenced below.

1. ANSI N18.1-1971, Selection and Training of Nuclear s .. Power Plant Personnel (Regulatory Guide ~1.8, Rev. 1).

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Cp raticnol Quality AccurCnCO P1Cn Revision 16

2. ANSI N45.2-1971, Quality Assurance Program Requirements for Nuclear Power Plants

3. ANSI N45.2.1-1973, Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuc1 car Power Plants (Regulatory Guide 1.37, 3-16-73).

4. ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants (During the Construction Phase)

(Regulatory Guide 1.38, Rev. 2).

5. ANSI H45.2.3-1973, Nousekeeping During the Construction Phase of Nuclear Power Plants (Regulatory Guide 1.39, Rev. 1).

6. ANSI H45.2.4-1972, Installation, Inspection, and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations (Safety Guide 30, August 11, 1972).

7. ANSI N45.2.5-1974, Supplementary Quality Assurance Requirements for Installation, Inspection and Testi~1g of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Regulatory Guide 1.94, Rev. 1).

8. ANSI N45.2.8-1975, Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants

9. ANSI H45.2.9-1974, Requirements for Collection, Storage and Maintenance of Quality Ausurance Records for Nuclear Power Plants (Regulatory Guide 1.88, Rev. 2),

10. ANSI N45.2.10-1973, Quality Assurance Terms and Definitions (Regulatory Guide 1.74, February, 1974).

11. ANSI N45.2.11-1974, Quality Assurance Requirements for the Design of Nuclear Power Plants (Regulatory Guide 1.64, Rev. 2).

12. ANSI N45.2.13-1976, Quality Assurance Requirements for the Control of Procurement of Items and Services for Nuclear Power Plants

13. ANSI N101.4-1972, Quality Assurance for Protective Coatings Applied to Nuclear Facilities W

(Regulatory Guide 1.54, June, 1973).

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optraticnni Quality A surtnao Pltn Revision 16

,\ 1.4- Management directivos and departmental instructions and (N' ) procedures shall provido for compliance with appropriato regulatory, statutory, licenso and industry requirements. Specific quality assuranco requiremonta and organizar.lonal responsibilitico for implomontation of thoco requirements shall be specified in k implomonting directivos and instructiono.

1.5 Compliance with this policy and the provisionn of the Operational Quality Assuranco Program 10 mandatory for NSP personnel with respect to nuclear plant operational activition or activities which support nuclear plant operation. Personnel shall thoroforo, be familiar with the requiremonto and responsibili. ties of the program that are applicable to their individual activitica and interfacon.

1.6 The Executivo Vice President Power Supply, through an indopondent organization, shall periodically have the operational Quality Assuranco Program reviewed to casuro its adequacy.

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oporctional Quality AccurCnco Plcn '

Revision 16 Table 1-1 Exception to ANSI N18.7-1976 O

1. Documentation required by ANSI N18.7-1976 may be deferred for emergency work. Emergency work is defined as that work that must be completed immediately and which, if dolayed, may result in an unsafe condition or significantly interfero with reliable plant operation.

2. Exceptions to Hegulatory Guidos and ANSI Standards are acceptable for those principal contractors, retained by NSP, such as USSS contractors and A/E Firms, which exceptions have been approved by the NRC.

3. Section 5.1; doloto this section. The provisions associated with identification of the Operational Quality Assurance Program scope are explicitly identified in Section 4 of the 2 Operational Quality Assurance Plan.

4. Section 5.2.2; replace the third sentence with the following "Proceduro changes shall be reviewed and approved as required by the Technical Specifications". Deloto the fourth sentence.

5. Section 5.2.5; replace the second and third contonces with

" Temporary procedures shall be reviewed and approved as required by the Technical Specifications".

6. Section 5.2.9; dolote the reference to ANSI N10.17. The Plant Security Plans contain required security provisions.

7. Section 5.2.11, first sentence; change " abnormal occurrences" to " reportable events".

8. Section 5.2.13.2, fourth paragraph; change the first sentonce to read "... Installation or use of such items that serve a safety function". Last paragraph; change " quality" to " quantity". This change corrects an error in the standard,

9. Section 5.2.15 of ANSI N18.7-1976 shall govern review, approval, and control of required procedures except that for procedures required by the Plant Technical Specifications, the review and approval requirements stipulated in the Technical Specifications shall be utill:cd rather than those contained in Section 5.2.15.

10. Section 5.3; change the last acntence to read " Procedures shall be prepared and approved prior to implementation as required by 5.2.15".

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oporctional Quality Accurenco Plcn Revision 16

11. Sections 5.3.9 and 5.3.9.1; doloto those sections.

Emergency operating Procedures shall be consistent with

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Supplomcnt 1 to NUREG - 0737 - Hoquirements for Emorgency Responso capability (Genoric Letter 82-33) .

12. Section 0; doloto this section. The referenced documents are explicitly referenced in the operational Quality Assuranco Plan. HSP will evaluato now or revised ANSI Standarda if appropriato for inclusion in the operational Quality Assuranco Plan.

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l Operational Quality Anouranco Plan Revision 16 2.O Intr.QAVgilgn llorthern Staton Power Company (11SP) in involved in the construction and operation of nuclear, foss11-fuo3ed and hydro cower planto. Construction of nuclear planto is conducted under a quality anot*Ance program on a project basis. IISP's nuclear plant operational activition are conducted under tho operational Quality Ansurance Program.

The Conatruction Quality Anouranco Program in utructured to govern nuclear plant design, fabrication, construction, testing and annociated procurement as required by the applicablo NRC Construction Permit and portinent regulations. Tho Operational Quality Annuranco Program in formulated on a company-wido basis, to govern nuclear plant operational activities and ascociated support activition as required by linc Operating Licenso provisionn and associated regulations. Tho operational Quality Annuranco Program is implemented, to the extent compatible with construction rouponsibilities, at 1 cast 90 dayn prior to initial fuel loading and in fully implemented upon satisfactory completion of the prooperational and startup tout program.

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CpOrcticC31 Qu311ty ACCurtnSo PICn .

R;viciC3 16' i 1.0 QLqanization I

\ 3.1 gener31 Renvirements ,

1. NSP shall be responsible for the establishment and execution of the operational Quality Assuranco Program, NSP may delegate to other organizations the work of establishing and exocuting the operational Quality Assuranco Program, or any part thoroof, but she.11 retain responsibility therefor.

2. The authority and dution of persono and organizations performing quality assurance functions shall be clearly established and dolineated in writing. Such persono and organientions shall have sufficient authority and organizational freedom to identify quality problems; to'initiato, recommrnd, or provide solutions; and to verify implementation of solutions.

3. Assurance of quality requires management measures which provide that the individual or group nooigned the responsibility for chocking, auditing, inspecting, or otherwise verifying that an activity has been correctly performed is independent of the individual or group directly responsible for performing the specific activity.

(al 3.2 Ouality Oraanization Gummary

1. The Power Supply Quality Assurance Department is rerponsible for the overall administration of the-operational Quality Assuranco Program, specific responsibilities are ctated in Section 3.3.2.1 and its subsections.

2. The' Quality Servicco Section for each nuclear site is responsible for the' administration of the site quality assuranco program and quality control of site activities. Specific responsibilities are stated in Section 3.3.2.2.1.2.

3. The Materials & Special Processes Section of the Production Plant Maintenance Department is <

responsible for providing technical support for the quality control .of special processes at the nuclear plants. Specific .esponsibilities are stated in Section 3.3.2.3.2.1.

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Cparaticn21 Quality Accurcnco Plcn Revision 16 3.3 gornorate Oraanization With operational cuality MRRTauce Procram Responsibilities 3.3.1 President & Chief Operating officer This position is responsible for all NSP activities associated with operating nuclear plants. This responsibility is implemented by assigning responsibility to the corporate officers of the company (See Figure 1, Corporate Organization With operational QA Responsibilities, Pago 21).

3.3.2 Executive Vice President Power Supply This position is designated by the President &

Chiof Operating Officer as responsible for the establishment and implomontation of an operational Quality Assurance Program. Responsibilitics include:

1. Engineering, construction and operation of all generating facilities.

2. Establishment of an Operatienal Quality Assurance Plan that governs activities associated with Federal Regulation (10CTR50, Appendix B).

3. Establishment of Corporate Nuclear Administrative Contr'ol Directives that identify quality assurance requirements and positions responsible for implemoi ting those requirements.

4. Providing status reports to management.

Positions reporting to the Lxecutive Vice President Power Supply include: Director Power Supply 3 Quality Assurance, Vice President Nuclear Generation, Vice President Combustion & Hydro operations, Vice President Transmission & Inter-Utility Services, Director Power Supply Finance & 4 Performance, and Director Power Supply support 5 Services.

3.3.2.1 Director Power Supply Quality Assurance.

This position is responsible for the establishment, maintenance and evaluation of the Operational Quality Asr,urance Program. Responsibilities include:

1. Controlliag revisions to the Operational  !

Quality Assurance Plan.

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Op0rctiCn31 QuOlity Accurtnco Pltn R;vicicn 16

2. Stop work authority for nonconforming

(^N activities until the adverse conditions have

() been corrected.

3. Assisting other company organizations in implerenting quality assurance program requirements.

4. Providing Power Supply Quality Assurance status reports to approprieto levels of management.

Positions reporting to this Director include:

l6 Superintendent supplier Quality Assurance, Manager Nuclear Operations Quality Assurance snd Superintendent Site Quality Assurance (Monticello a;.d Prajrie Island). 7 3.3.2.1.1 Superintendent Supplier Quality Assurance This position is responsible for control of the supplier qualification program.

Responsibilities include

1. Inspections of nuclear fuel suppliers.

2. Qaality assurance audits / source surveillances and qualification of D

[d suppliers of materials, equipment and services.

3. Quality assurance reviews of nuclear procurement madt by general office organizations.

4. Preparation / review of internal quality assurance programs and procedures.

3.3.2.1.2 Manager Nuclear Operations Quality Assurance This position is responsibic for quality assurance activities associated with general office organizations and internal auditing.

Responsibilities include:

1. Internal audits of all levels of the Operational Quality Assurance Program.

2. Review of Corporate Nuclear Admir.istrative Control Directivos and Corporate Nuclear Administrative Work Instructions.

3. Maintenance of Corporate Nuclear Administrative Control Directives and (g7-

) Corporate Nuclear Administrative Work ,

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Cporaticnol QuOlity Accurtn 0 Pltn R;vicicn 16 Instructions current with corporato commitmenta and policies.

4. Program implomontation monitoring and periodic trending.

3.3.2.1.3 Superintendent Sito Quality Annuranco (Monticello and Prairlo Island)

Theno positions are responsiblo for the l8 administration of Sito Power Supply Quality Assurance activitics. Responalbilition 17 includo:

1. Implomontation of nito curvoillance program.

2. Quality Aosuranco review of sito '

procuromont documents.

3. Quality Asocrance review of modificationn t.

projects. -

4. Maintaining and reporting the statur. of on-sito Quality Annurance Program implomontation.

I7 3.3.2.2 Vice Prooident Nuclear Generation This ponition is responsible for thra operation and physical control of the company's nuc) oar gonorating facilitics. Responsibilition includo:

1. Operation of nuclear facilition.

2. Maintenance of nuclear facilition.

3. Modification of nuclear facilitioc.

4. Nuclear facility fuel utilization.

5. Operational review of new nuclcar facility donign.

6. Indopondent review and audit of nuc11ar plant operations and operating liconno administration.

7. Training Support for all Power Supply pornonnel.

8. Providing overall direction and support to nuclear cito management it. matters of staffing and employco qualifications. h Page 10 of 101 1 _

Cp0rcticn:1 Quality AccurencD Pltn R0viciCn 16 1

9. Providing emergency preparedness management. 9 rw 0 k_,) Positions reporting to this Vice President include: Director Power Supply Training, General-Manager Nuclear Site (Monticello and Prairie Island), General Manager Nuclear Support Group, Manager Special Nuclear Programs, Executive Engineer and Safety Audit Committee Chairman (on matters relating to the Safety Audit committee).

3.3.2.2.1 General Manager Nuclear Site (Monticello and Prairie Island)-

These positions are responsible for the overall management of nuclear site activities, and for l11 ,

ensuring compliance with regulatory requirements. Responsibilities include:

1. Review of plant operating abnormalities, problems, performance, malfunctions, etc.,

and concurrence in corrective actions.

2. Review of quality assurance status, trend and audit reports, and follow-up of resolution to nonconformances.

3. Review of Safety Audit Committee reports and recommendations.

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4. Performance of further actions as required to ensure safety.

5. Nondestructive examinations not associated with inservice inspection.

6. Development and impicmentation of the following programs:

a. Material control including receipt inspection.

b. Site quality assurance and control.

c. Site physical security and guard force 12 staffing and supervision. 13

7. Technical manual control' program.

8. Eroviding nuclear project management, engineering and construction services.

9. Procurement of items and services for the 14

- nuclear site.

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opcraticnni Quality AccurOnOO PICn novision 16 Positions reporting to those General Managers respectively includo: Plant Managor, Managar Nuclear Projects, Superintendent Quality Services.

3.3.2.2.1.1 Monticello and Prairio Island ! nt Managers Those positions are responnible for ensuring that activition and operationa comply with applicable regulatory requirements.

Ronponsibilitica include:

1. Hosponnibilitics assigned by the operating liconao and the Corporato !!uclear Administrativo control Directivos.

2. Plant managerial control nyatom.

3. Plant operation and maintenance.

4. Plant staffing, including qualificationo, hiring, training, disciplino, and ndminintration of the labor contracto.

5. Development and implomontation of the following programs:

a. 5 oventivo maintenanco,

b. Su rvo111anco ,

c. operating, maintenance, and tonting procedural syntoms.

d. Fire protectio ,

c. Operating experienco assoucmont.

6. Coordination of activities performed by non-plant staf f personnel with plant operation.

7. Operation and maintenanco of the indopondent upont fuel storage installation 15 (Prairio Island only).

3.3.2.2.1.2 Superintendent Quality Services (Monticello and 16 Prairio Island)

Those positions are responsible for tho l8 adminintration of operational Quality Accuranco Program requirements at the nito level.

Responalbilition include:

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Cp rcticnol Quality AccurCn30 PICn ROvinien 16  ;

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1. Implementation of the site quality control

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inspection program (except ISI).

2. Review of inspection schedules (except ISI), procedures, and results (i.e., those associated with routine maintenance and modification activities, operational activities, technical services, radioactive material packages, emergency equipment, and +

fire protection).

3. Requesting audits of selected site level l18 activities when determined that the audit will improve site program implementation.

4. Review of site Adminictrative Control l 19 Directives and Instructions.

5. Site program implementation monitoring and periodic trending.

6. Stop work authority for nonconforming  ;

activition at the site until adverse i conditions have been corrected.

7. Providing site quality assurance status and trend reports to appropriato levels of management.

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8. Monitoring contractor quality control activities.

20 3.3.2.2.1.3 Manager Nuclear Projects (Monticello and '16 Prairie Island)

These positions are responsible for the execution of projects assigned to Nuclear Projects and for providing craft labor when requested. Responsibilitics include:

1. Design, manufacture, fabrication, l 14 -

construction, installation, and preoperational testing of modification projects.

2. Implementation of assigned on-going 21 projects at nuclear plants.

3. Providing technical support.

4. Performing assigned responsibilities for maintenance activities.

S. Praviding craft labor.

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operational Quality Ansuranco Plan Revision 16

6. Derforming engineering studios. h

7. Management of sito design documentation.

l23 3.3.2.2.2 Coneral Manager Nuclear Support Group This position's responsibilities includet

1. Support to nuclear plants in licensing, saf ety, coro analysis, and related technical arcao.

l10 positions reporting to this General Manager include: Manager Nuclear Support Servicon, Manager Nucient Analysis, and Manager Nuclear Radiological Gervices. l24 3.3.2.2.2.1 Manager Nuclear Support Servicon This position la responsible for providing cupport to the nuclear planto in the arcan of licensing adminictration, and safety audit and asscosmont. Rosponsibilition includo:

1. Independent review functionn for operating nuclear planto to verify complianco with operating licence requirements as required by NRC regulations.

2. Liconne administration for nuclear plants and liaison to the NRC Office of Nucionr Roector Regulation.

3. Engincoring and technical support to nuclear plants in nuclohr safety and liconning areas.

3.3.2.2.2.2 Manager Nuclear Analysin This position's responsibilitics includo:

1. Coro and nuclear safoty analyaic for ,5 nuclear plants.

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2. Licensable reload coro designs for nuclear 3 plants. Y y]

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3. Technical exportise, information and direction to the Nuclear Support Services Department to ensure licensability of reload coro designs, and to ensure adequacy of technical specifications.

4. Technical expertise, in*ormation and k direction to the Fuel Resources Department in the fornulation, coordinatiori and Page 14 of 101

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Cp;rctic 21 QuSlity A0curCOOO Pltn Revision 16 implementation of reload designs, vendor i

7-) evaluations and vendor contract

\- negotiations.

5. Technical expertise and direction to the Power Supply Quality Assurance Department to ensure that nuclear fuel meets company and regulatory age.tcy requirements.

6. Feedback and technical expertise to the Production Training Department to ensure that necessary expertise, information and computer physics models are available for training.

24 3.3.2.2.2.3 Manager Nuclear Radiological Services 26 This position As responsible for providing '

support to the nuclear plants in the area- of radiation protection, chemistry, emergenc-planning and radiation environmental monitoring. Responsibilities includet  ;

1. Providing a corporate radiation protection g support program.

2. Providing a corporate nuclear chemistry g 7

support program (BWR and PWR).

3. Administering NRC operating licenses and technical specifications for radiological environmental activities. l 28

4. Reviewing, coordinating and evaluating company emergency preparedness and radiological environmental activities l 28 required by the NRC.

5. Conducting a radiological environmental l 28 monitoring program to comply with NRC requirements.

6. Reviewing proposed and revised regulations related to radiation protection, chemistry, 27 emergency preparedness and radiolegical 28 environmental activities.

9 3.3.2.2.3 Manager Strategic Issues Group 29 This position's responsibilities include:

1. Coordinating and managing, as applicable,

('N the storage, shipment and disposal of spent

(_,/ fuel, low level waste, and high level waste for NSP.

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Cpcrcticn21 Quclity AccurCn00 Pltn Revision 16

2. Developing corporato positions on legislative and regulatory issues, other than NRC actions, which may impact nuclear llh operations.

3.3.2.2.4 Executivo Engineer This position is responsible for providing technical consultation on projects and issues which affect nuclear generation.

3.3.2.2.5 Safety Audit Committoo (SAC) Chairman This position is appointed by and responsible to the Vico President Nuclear Generation. This position is normally an NSP Managor.

Responsibilition include:

1. The overall administration of the SAC.

2. Appointing SAC members.

3.3.2.2.6 Director Power Supply Training This position is responsible for ovaluating the training needs of Power supply employees, developing programs to meet those needs, and providing the necessary instruction.

Positions reporting to this position include:

Manager Power Supply Training - Nuclear 3; ,

(Monticello and Prairio Island).

3.3.2.2.6.1 Manager Power Supply Training - Nuclear 33 (Monticello and Prairio Island)

These positions are responsible for the training of Power Supply employees at the sites. Responsibilitics includo:

1. Providing NRC Reactor Operator and Senior Reactor Operator license training programs.

2. Providing requested training for Power Supply personnel working at nuclear plants. 30

3. Providing required training to personnel temporarily working at nuclear plants.

4. Managing and operating simulator facilities.

5. Providing requested support for Power q Supply internal nuclear plant training.

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Cporatienol Quality AccurOO90 Pltn Revision 16

6. Maintaining required training records.

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7. Providing fire protection training. 30

8. Maintaining INPO accrsdited training programs.

9. Providing required training to security 12 personnel at nuclear plants.

3.3.2.3 Vice President Combustion & liydro Operations This position is responsible for the maintenance and physical control of the company's combustion and hydroelectric power plants, and support to the nuclear plants. Responsibilities include:

1. Support of nuclear plant maintenance program.

Positions reporting to this Vice President include:

General Manager Plant Engineering & Construction and Manager Production Plant Maintenance.

3.3.2.3.1 General Manager Plant Engineering &

Construction

(~g This position's responsibilities include U 1. Technical support and drafting services for '

nuclear plants.

Positions reporting to this General Manager include: Manager Plant Engineering.

3.3.2.3.1.1 Manager Plant Engineering This position's responsibilities include:

1. Drafting services for the nuclear sites. 32 3.3.2.3.2 Manager Production Plant Maintenance This position's responsibilities include:

1. Assisting in securing maintenance contracts.

2. Providing materials and special process controls.

3. Providing technical support and counsel in assigned areas.

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( Positions reporting to this Manager include:

Superintendent Materials & Special Processes.

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escrctionni Quality Accurenco Pltn Revision 16 3.3.2.3.2.1 Superintendent Materials & Special Proconaan gg This position la responsible for activities associated with special processen, innervico inspection and technical support in areas of quality control for special processes and  ;

material proporties. Rosponalbilition includo: '

l. Developing, preparing, and distributing .

Wolding, heat treating and nondcotructivo l oxamination procedures.

2. Cortifying personnel in wolding and nondestructivo examinntion and maintaining qualification recorda.

3. Developing, implomonting, and documenting an Inservico Inspection Examination Program in assigned areas for nuclear plants.

4. Providing technical support to planta in the aroan of metallurgy, ASME Dollor Codos, welding, hont treating and nondestructivo examination.

5. Providing technical instruction in wolding and other special proconson as required.

lh 3.3.2.4 Vico Prooident Transmission & Intor-Utility Servicon This position is responsible for the planning, design, construction, operation and maintenance of 33 the transmission nyatom.

Ponitions reporting to thia Vice Pronident includo:

General Manager System Operations and General Manager Substation / Transmission Services.

3.3.2.4.1 General Manager System Operations This position is responsiblo ' for operation of the company's electrical system.

Responsibilitics include:

1. Coordinating electrical transmission system operation with generating facility operation.

Positions reporting to this General Manager include: Manager System Control.

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I Cp rotiecol Quality AccurO300 Plch l Revision 16 '6 3.3.2.4.1.1 Manager System control j This position's responsibilities include:

1. Coordination and supervision of.the operation of NSP's generating and  ;

transmission system.  ;

2. Coordination of planned transmission line -

and generating unit outages. -

3.3.2.4.2 General Manager Substation / Transmission i Services 'l This position is responsible for the design, 34 engineering, construction and maintenance of the transmission uystem. Responsibilities -

include:

1. Performance of maintenance on. plant  :

electrical equipment and the electrical transmission system.

2. Electrical construction testing services for nuclear power plants.

- Positions reporting to this General Manager include Manager Electric Maintenance &

Protection.

3.3.2.4.2.1 Manager Electric Maintenance & Protection a This position's responsibilities include: ' l .35 -

l. Providing administration,-supervision,.and >

technical expertise to facilitate-maintenance and testing of Power.SupplyJ ~36' equipment including battery capacity. -

testing.  ;

2. Providing for the maintenance, proper I application and functioning of all" relay protection, control,-energy: management, system computer, communication and -

telemetering--equipment, including electrical construction-testing, at substations,=-power _ plants and control :l25: ,

centers.

3.3.2.5 Director Power Supply Support Services-- _ l 5: ,

This positions's responsibilities include:

O 1. Nuclear fuel procurement.

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op;raticnol QuOlity AccurCOoD Pitn Revision 16

2. Procurement and material management for Power Supply.

3. Provido management for NSP Corporate Security 10 Program.

4. Testing Laboratory services. l6 Positions reporting to this DirGetor includGI Manager Corporato Security, Manager Fuel Resourcos, 24 Manager Material Services & Testing and Manager 38 Procurement & Material Management.

l39 3.3.2.5.1 Manager Corporato Security 24 This position's responsibilities includor

1. Implementation of the company's security program, which includes providing trained security Dorsonnel at non-nuclear plants. 1;

2. Nuclea Access Authorization, general employee screening, investigations and other related security services.

3. Developmer i implementation of Nuclear Generation s fitness for Duty Program. { }

3.3.2.5.2 Manager Fuel Resources l42 This position is responsible for Power Supply procurement functions of fuel for the company's 40 generating plants.

41 3.3.2.5.1 Manager Material Services & Testing 38 This position's responsibilities include:

1. Developing and preparing NDE and Testing Laboratory procedures.

2. Certifying Testing Laboratory personnel and 7 maintaining qualification records.

3. Providing chemical, nondestructivo examination and physical testing and inspection services including air filter testing.

3.3.2.5.4 Manager Procurement & Material Management 39 i This position is responsibic for Power Supply j

procurement and material management functions for material, equipment and services. lh l

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i op0roticcol Quality AccurOnGO PICn Revision 16 i 3.3.2.6 Director -?ownr Supply Finance & Performanco l4  :

This position's responsibilitics includo -

1. Financial operations of Power Supply

2. Drawing Control 43

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v .,

' M4AAN OPERATIONAL QUALITY ASSURANCE PLAN _,

g r wE REVislON 16 I

PRES; DENT OPEFMTING 1

EXECUTNE VIC POWERS i

l I l .

VICE PRES 1 DENT VICE FRESIDENT COMBUST NUCLEAR GENERATION HYDRO OPERATIONS .-,

2.3 2.2 ...

~

GLNEFKUANAM.H GTRERAL MANAGER N R P 'O T C JP .-

T An s Tr _

2.2.2 2.3.1 22.1 }

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PLANT MANAGER SUPPORT SERVICES PLANT ENGINEERING 2.2.1.1 2.2.2.1 2.3.1.1 l

SUPERINTENDENT MANAGER

- QUALITY SERVICES NUCLEAR A'lALYSIS 2.2.1.2 2.2.2.2 MANAGER PRODUCTION MANAGER MANAGER NUCLEAR PLANT MAINTENANCE -

_ NUCLEAR PPOJECTS RADIOLOGICAL SERVICES "

2.21.3 2.2.2.3 2 ~2 -,

I _

SUPERINTENDENT M ATh.eALS

& SPECIAL PROCESSES 'T 232.1 - i MANFER STRATEGIC // fr I' -

ISSUES GROUP PF%IR!E ISLs.ND 22.3 t? : f M tcl T AA RfTT 2.2.1 EXECUTNE ENGINEER Pt. ANT MANAGER 2.2.4 L 2.1.1 SAC CHAIRMA N SUPERINTENDENT 2.25

-- Ol'ulTY SERVICES

^ - DIRECTOR POWER

~ - stiPPLY TRAINING

~ ~ ~ '

MANAdi- A 22.6 **

.- NUCLEAR PROJECTS 2.2.13 (~'

,1 MAPMGER POWE.R SUPPt.Y TRAINING - NUCLE AR 2.2.6.1 e

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l. - _ _ - - _ - - _ _ - - - ..

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kretn . --gg APERTURE cnEr FICER '

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DmLC70Fi POWER GUPPLY DIRi CTOR POWER SUPPLY DiftECTOR POWER SUPPLY VICE PRE SIDENT 1RANS

& lNTER-UfiUTY SE5WICES l-

_ FINANCE & PEDFORMANCE f:UPPORT SERVICE S -

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QUALITY ASSURANCE - -

2.4 28 26 2.1 i

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I GENERAL MANAGER MANAGER MANAGER NUCLEAR CORPortATE SECURITY - OPERATONS QA -

SYSTEM OPERATONS 25.1 2.1.2 2.41 M, . .GER MANAGER SUPERINTENDENT FUEL RE SOURCES ._ . SUPPLIER QA ,_

SYSTE M CONTFW 2.41.1 25? __

2.1.1 MANAGER MATERIAL SUPERINT ENDENT

~ EERVICES & 1ESTING -

SITE QA (EACH PLANT) -

21,3 2.5.3 ,

O N N MANAGE R P6DCUREMENT SUBSTATOF#TRANSMISSON' _ & MATERIAL MANAGEMENT _

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2.42 2 h. 4 I .,

MANAGER El.Er* ,..

I MAlk" NANCE & PHCit CTION 1

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FIGunE 1 l

CORPORATE ORGANIZATION WITH OPERATIONAL. OA RESPONSIBILITIES l

! NOTE:

NUMBERS IN TITLE BOXES INDICATE SUBSECTIONS OF SECTION 3.3 DESCRIBING RESPONSIBILITIES 1 i 9209240248 I/

Page 22 of 101 4

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J

' operations 1-QuclityiAccurcnooLvlen

. Revision 16 ,

<t -

7 ,g 4. 0- Og3I,ational Ouality Assurance Procren  ;

- 4.1 General Reauirements ,

-1. The Operational 1 Quality _AssuranceiProgram shall be:-

l a.- Documented by written Directivea, Instructions,--

or Procedures.

b.. Carried out-throughoutLplant operating-lifefin_ '

accordance with those Directives, Instructions,- J or Procedures.

2. The Program shall include-identification of:

a. The. structures, systems, and: components to-be-covered.

b. The major organizations participating 1in the-Program, together with the designated functions of these organizations.  ;

3. The Program shall provide control 1overEactivities affecting the: quality of the identified structures,- ,

systems,'and components to the extent consistent with their importance to safety.

() 4. Activities affecting quality.shall beLaccomplished under suitably controlled conditions. Controlled 45-conditions' include the use_of appropriate equipment; suitable environmental conditions for accomplishing the' activity, such_as' adequate cleanliness; and assurance that-all prerequisites for the given. activity have been satisfied.c

5. The Program shall take into account =the1need;for-special controls, processes, test-feguipmentJ-tools,.

and skills to attain the required quality,--- and the -

need for verification of - quality- by inspection 'and -

test.

6. Thi Program shall provide for' indoctrination and Ltraining of personnel: performing activities affecting quality as;necessary to-assure-that' _

suitable--proficiency is achieved and: maintained.

7. The adequacy and status of-the Program shall be regularly, reviewed.

8. Management of other organizations participating in the Program'shall regularly review the status and

-adequacy of that part of the Program which they~are-l, executing. '

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op;rctiencl-Quality AccurOn30 Plcn Revis1or 16 4.2 General Description

1. The operational Quality Assurance Program has bet 4 established to govern the operational activities and the activities necessary to support oporation of the company's nuclear plants operated under an NRC operating License. The Operational Quality Assurance Program is thus an overall integrated company-wide program which governs all safety related, fire protection related and 10CFR71 related activi. ties as they pertain to operating nuclear plants.

.. The Program has been initiated by the Presid3nt &

Chief operating officer of the Company issuing a single directive to the Executive Vice President Power Supply establishing him as being responsible for formulating and implementing an operationa)

Quality Assurance Program and identifying the program objectives.

3. The operational Quality Assurance Program shall utilize the following documer.ts to meet the program objectives:

a. Operational Quality Assurance Plan (Plan).

b. Administrative control Directives (Directives) at the Corporate and Site level. l 19

c. Admi.nistrative Work Instructions (Instructions) at the Corporate and Site level. l 19

d. Required Procedures (Procedures) at the Plant and Department level.

4. The Plan shall be considered an overall document which governs the implementing documents (i.e.,

Directives, Instructions, and Procedures).

S. For ease of administration, implementing documents shall be issued at'the following program levels:

a. Corporate: Approving Authority, Power Supply Vice Presidents and Director Power Supply Quality Assurance. 46

b. Sites (Prairie Island and Mont pt y ol: 32 Approving Authority, General 1 Onag f Nuclear Site, 7

c. Departments Proviclipo Nuclear Plart Suppgrl:

Approving Authority, Department Manager.

h Page 24 of 101

Oporctional Quality Accurtnco PlCn-Revision 16 7s 6. It should be noted that the Site Level Directives jl9

-(

are controlled by the Corporate level Directives

\2 (i.e., the Corporate level establishes the minimum requirements associated with the Site level) . l19

'4.3 Qp_grational Ouality Assurance Plan

1. The Operational Quclity Assurance Plan shall be a document which describes in general' terms how compliance with the quality requirements presented in 10CFR50, Appendix B and 10CFR71, Subpart H is accomplished with respect to company nuclear plants regulated by an NRC Operating License.

2. The Operational Quality Assurance Plan shall be issued under the authority of the Executive Vice President Power Supp2y and shell be reviewed periodically.

3. The Operational Quality Assurance Plan shall be-controlled to assure current copies are made available to each Approving Authority of the two Directive lavels of the program, to those personnel responsible for administration of the program, and to those individuals or organizations responsible for reviewing the program.

/7

(') 4. All changes to the Operational Quality Assurance Plan shall be approved by the Executive Vice President Power Supply or equivalent management position.

4.4 Administrative Control Directivqs

1. Administrative Control Directives (Directives) shall be documents which establish responsibility and requirements governing activities associated with plant operation. Directives shall be first tier implementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with the operational Quality Assurance Program objectives. Required Directives shall be controlled and reviewed periodically.

2. Administrative Control Directives shall be issued as necessary. It is mandatory that the Directives at the Corporate level cssure compliance with all appl.icable requirements of 10CFR50, Appendix B and 10CFn'1, Subpart H. The Directives issued at the site levels are not expected to satisfy all l 19 10CFR50, Appendix B and 10CFR71, Subpart H

(~T requirements but shall implement responsibilities

(_) assigned by the higher level Directives.

Page 25 of 101

Operational Quality Assurance Plan Revision 16 4.S Adminictrative Work Instructions -

1. Administrative Work Instructions _(Instructions) shall be documents which provide guidelines or instructions for the impler.entation of the requirements of Administrative Control Directives.

Instructions shall be second tier implementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with pertinent Directive requirements and assigned resprnsibilities.

2. Administrative Work Instructions may be issued at the Corporate and Site level. Instructions shall generally be utilized for department interfacing. l39 Required Instructions shall be controlled and reviewed periodically.

4.6 Erocedures

1. Procedures shall be documents which provide specific instructions for performing an activity.

Procedures shall be second or third tier documents utilized to perform safety related, fire protection, and 10CFR71 related activities as required by the applicable NRC Operating License Technical Specifications.

2. Procedures shall be provided where applicable, to assure that activities important to safety are performed in the required manner. Required procedures shall be reviewed and approved as required by the applicable Technical Specifications. Approval of procedures not required by the Technical Specifications shall be by a member of the responsible area management.

Review of procedures not required by Technical Specifications shall be by an independent knowledgeable person. Required procedures shall be controlled and reviewed periodically.

4.7 Procram Administration

1. Administration of the Corporate level of the operational Quality Assurance Program shall be performed by the Director Power Supply Quality 3 Assurance.

2. Administration of the site level of the Program shall be performed by the Superintendent Quality Services except in the areas of procurement and modification which shall be performed by the Director Power Supply Quality Assurance. ,

Page 26 of 101

P I

op0rotienci Quclity;Accurcnoo7Plcn> '

,ROvicien=16L 1

13 . - Disputes betweeniQuality Assuranceipersonnel and .

other organizations' relative to Program-O- requirements _shall be referred;to the Approving ~

Authority.(as_identifiediin Section-4.2 of.this Plan)eresponsible for establishing-the pertinent; E requirement'. -  ;

Program administration shall include the following

- 4 ', _ activities:-

a. Quality review of Directives.

b. Quality review of Instructions.-

c. Procurement review.

d. Performance of required' audits.

e. Reporting to management concerning:

1. Program status.

2. Program-discrepancies including quality trends.

4.8 Procram Boundary

1. The_ structure, systems, components,.and oth'er items O- -requiring quality assurance are listed in Appendices A andLB. The Program shall also include shipment of radioactive materials'ascrequired by 10CFR71 and systems and activities associated'with-fire protection-as identified in. Appendix;c. *

2. An index shall be establish'ed and maintained by the -

Director Power Supply 7 Quality-Assurancefwhich ]3-identifies the-Directives and Instructions thatiare-

-utilized to implementothe requirements of' ANSI . . i N18.7-1976 that are committed-to in~Section 1.0 of-this planzandLthe requirements identified in the-remaining-sections of this plan.- ,

4.9 Ouality-Assurance-Trainina Training programs shall be-established for those-personnel performing quality-affecting activities'such' that they are' knowledgeable in1the-quality assurance documents and'their requirements and proficient-in' >

- impleme nting._ ' the s e re quirement s . - These training-programs'shall assure that:

1.- Personnel responsible for performing quality-affecting activities are instructed as to the purpose, scope, and-implementation of the 3( )

Page 27 of 101 '

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Operational Quality Assurance Plan Revision 16 quality-related Directives, Instructions, and &

Procedures. W

2. Personnel performing quality-affecting activities are trained and qualified, as appropriate, in principles and techniques of the activity being performed.

3. The scope, the objective, and the method of-implementing the training programs are documented.

4. Proficiency of personnel performing quality-affecting activities is maintained by retraining, re-examination, and/or recertification as appropriate.

5. Methods are provided for documenting training sessions describing content, attendance, date of attendance, and the results of the training session, as appropriate.

6. Fire protection training is accomplished in accordancc with Appendix C.

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Op3ratien01 Quclity'Accurenca Pltn Revision 16

~

-5.0- Modification Control i

' 5.1 General Recuirements Modifications shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design unless the company designates 1another responsible organization.

5.2 Uniform Modification Process A uniform process for controlling modifications to nuclear plants shall be provided in the Operational Quality Assurance Program. Measures shall be established to assure that:

1. The requirements of ANSI N45.2.11-1974 are implemented.

2.- Reviews and approvals are performed.

3. Plant documentation is updated.

4. Appropriate installation procedures are prepared and-utilized.

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( ,/ 5. ' Tests and inspections are performed as necessary.

6. Site procedures are reviewed and revised as 39 appropriate.

7, 10CFR50.59 is complied with.

8. Fire protection reviews are performed as required by Appendix C.

O Page 29 of 101

Operational Quality Assurance Plan Revision 16 6.0 Procurement Document Control 6.1 General Reauireqgnta Measures shall be established to assure that applicable regulatory requirements, design bases, and other requirements which are necessary to assure adequate quality are suitably included or referenced in tne documents for procurement of material, equipment, and services, whether purchased by NSP or by its contracters or subcontractors. To the extent necessary, procurement documents shall require contractors or subcentractors to provide a quality assurance program consistent with the pertinent provisions of 10CFR50, Appendix B or 10CFR71, Subpart H.

6.2 Technical and Ouality Recuirements

1. The Operational Quality Assurance Program shall contain provisions for controlling procurement of material, equipment, components, and services that are safety related, fire protection related, or 10CFR71 related and utilized at or for an operating nuclear plant.

2. Procurement documents shall contain specific technical and quality requirements. Renewal, spare, and replacement parts shall be required to meet the original specification (or properly reviewed and approved revision) or construction code, quality assurance documentation requirements, and vendor quality assurance program requirements.

3. Quality assurance requirements that are required of the vendor shall be included. Quality assurance requirements shall be based on ANSI N45.2-1971 (or equivalent standard). Documentation requirements shall include, as applicable, chemical analysis reports, material certification, testing results, and testing reports. Time and frequency of submittals should be included.

4. Procurement documents shall contain provisions which establish the right of access to vendor facilities and records for source inspection and audits as appropriate.

5. Procurement documents for contracting packages for transport of radioactive materials shall require a copy of the package license, certificate, or other NRC approval authorizing use of the package. The procurement documents shall also require copies of all documents referred to in the license, certificates, or other NRC approval as applicable.

Page 30 of 101

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-' oporatienc1' QuclityfAccurcnoo'Pltn

-: Revision 16-6 .' 3 ~ Review ~and'ADDIoval

- Documents,iand; changes thereto3 initiating procurement .

~

of safety _.related,ifire protection._related,'J10CFR71- ,

.related material,; equipment, components;or services 1 f *

- - shall'be approved;by-appropriate management personnel -

-and'shall=:.be-subject to.a quality review to insure: -

applicable regulatory requirements,:-design basest

~

. quality _ assurance, and other requirements'are '

- adequately satisfied-prior __to release.

6.4 Fire Protection Procurgment Control- ,

The additional procurement-controls identified.in Appendix C shall'be: applied to-purchasing fire.

protection ~ systems and equipment.

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Operational Quality Assuranco Plan Revision 16 7.0 Instructicas, Procod4ros and Drawinos 7.1 General Recuirements

1. Directives, Instructions, Procedures, and drawings of a type appropriate to the circumstances shall be provided for the control and performance of activities which affect quality.

2. Directives, Instructions, Procedures, and drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accompliched.

7.2 Directives and Instructions Directives and Instructions shall be issued which establish procedural requirements for appropriate functional areas. Such procedural requirements shall include the following as appropriate:

1. Procedure review and approval requirements.

2. Procedure control requirements.

3. Procedure content requirements, h 7.3 Procedures

1. Procedures of a typo appropriate to the circumstances shall be provided for the performance of activities which affect the quality of safety related, fire protection related, or 10CFR71 re'.ated structures, systems, or components.

2. The following procedurec shall be provided:

a. Operating procedures.

b. Emergency procedures.

c. Surveillance test procedures.

d. Routine or preventive maintenance procedures.

e. Calibration procedures.

f. Plant chemistry and count room procedures,

g. Radiation protection procedures,

h. Emergency plan procedures,

i. Special process procedures.

Page 32 of 101 t _

, operational Quality Assuranco Plan i Revision 16

j. Preoperational and operational test procedures.

k. Audit precedures.

1. Fire fighting procedures.

m. Document control procedures.

n, Radioactive material shipment procedures.

o. Inspection procedures.

7.4 Drawinas and Technical Manuals Drawings and technical manuals of a type appropriate to the circumstances may be used as procedural documents for conducting activities that affect the quality of safety related, fire protection related, or 10CFR71 related structures, systems, or components.

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Operational Quality Assurance Plan Revision 16 8.0 Document Control 8.1 Genernl Reauirements

1. Measures shall be established to control the issuance of documents, such as Directives, Instructions, Procedures, and drawings, including changes thereto, which prescribe activities affecting quality.

2. These measures shall assure that documents, including changes, are:

a. Reviessd for adequacy and approved for release by authorized personnel, and

b. Are distributed to and used at the location where the prescribed activity is performed.

3. Changes to documents shall be reviewed and approved by the same. organization that performed the original review and approval or another designated responsible organization.

8.2 Directive Control

1. Directives issued to implement the Operational h Quality Assurance Program shall be controlled to assure that current copies and appropriate indexes are made available to personnel performing the prescribed activities. Directives shall be reviewed by quality assurance personnel to assure their compatibility with the Operational Quality Assurance Program objectives and shall be approved L by the designated management.

2. Changes to Directives shall be reviewed and approved in the same manner as the original.

8.3 Instruction Control

1. Instructions issued to implement provisions of Directives shall be controlled to assure that current copies and appropriate indexes are made I

available to personnel performing the prescribed activities. Instructions shall be reviewed by quality assurance personnel to assure that they are compatible with pertinent Directive provisions and l shall be approved by designated management.

l l 2. Changes to Instructions shall be reviewed and l approved in the same manner as the original.

l Page 34 of 101

c 9 oporationn11Quclity: AccurencaEPlcn

--Revision:16' ' - _

j

-i 6

8.4i=E;ocedure Control

1. -Required procedures shall be controlled to'asshre that current copies are_made'availableito personnels

~

performing the prescribcdsactivities. ; Required procedures shall-be reviewed by a-knowledgeable ~

individualJ and shall:be1 approved;by a_ management:

member of.the organization responsible for the-prescribed activity. Required ~ procedures 1shall be' reviewed and_ approved as required by the Technical ,

Specifications._ Appropriate = indexes of standing--

procedures shall be formulated and made available- ,

to personnel responsible for: performing _the-prescribed activities.

2. Significant changes to required' procedures shall bei reviewed and_ approved in the same manner as'the:

original'and shallocomply with the Technical-Specifications.

8.5 Dr.awina Control

1. Drawings which-represent the physical.and functional aspects of-the' operating nuclear plants-and which are critical:to safe. plant; operation or-safety.of personnel shall be maintained-in a current status. Appropriato indexesTshall'be-O.s formulated and=made available to. personnel--

responsible;for plant operation, maintenance, andc modification.

2. Measures shall be established for revising _ site ~ 32l ,

drawings and for distributing revised drawings.

Proposed revisions to drawings'shall be reviewed by a-knowledgeable' individual?to determine theEsafety significance'and appropriateness-of the change, g 8.6 Specifications Plant design-specifications lshallsbe. controlled to assure that current copies and appropriate indexes are made available to personnel responsible _for plant operation, maintenance, and modification.

8.7 Radioactive Shipment Packaoe Documents A111 documents related'to-a specific shipping package for radioactive material shall be controlled by appropriate' instructions; all significant changos to such documents shall-be similarly controlled.

8.8 Updated Safety Analysis Reports Updated Safety-Analysis Reports shall be updated in L

accordance with the applicable provisions-of 10CFR50.

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Op0rctionci Quclity Accurenco Plan Revision 16 ]

8.9 Tpqqhnical Manuth Technical manuals that are used as procedural documento shall be controlled.

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~

opbrctienol?Quclity1Accurense Pltn:-

Revision 16 lt;

?

,9.0: Gontrol of-Purchased MateriaA,.'Eaulement and'8Arvic$2;

?

-9.1! General'Reauirements'

' 1, Measures shall;betestablished to assure that

-purchased-material, equipment-and services' conform: 0 to the~ procurement documents. 1These1 measures-shall . - -  :

include -provisions, : as; appropriate, for vendor - _

evaluation 1and selection,1 objective. evidence of'. 'l quality, furnished ^by~the vendor,-inspection at:-the O vendor-source,1and examination of-products upon

- _ delivery . -

2. Documentary evidence thatDmaterial and equipment: ,

conform to the-procurement requirements shallibe available at the site prior to-installation lor use of such material and equipment. This documentary; evidence-shall:be retained ~at the-siteLand shall be' sufficient to indicate thatLthe-purchased material ..

and equipment meet the' specific-requirements of;the_ '

codes, standards, or specifications.-

3. The. effectiveness of'the control of quality bys vendors shall be assessed at intervals consistent

-with-the importance, complexity.and quantity of_.the;

-product or service.-

( 9.2 Ouality Review

[

1. Documents initiating procurement-of-safety related, fire protection related, and 10CFR71 related- ,

material, equipment and-_ services shallibe'subjecti to a quality review:to ensure appli' cable. regulatory. '

requirements, design. bases, quality assurance,'and-other requirements 1are adequately-satisfied.-

2. Quality assurance requirements 1shalliinclude identification of applicable elements'of-ANSI- . _

N45.2- 1971 (or equivalent) that are required:to be included in the vendor's-quality assurance = program.-

9.3 Vendor Evaluation and Veri *ication'

1. The adequacy of vendor's. quality assurance program specified-.in procurement documentation shall be-verified-prior to use of-the procured material, equipment,_or service. Vendor's! adherence to-their quality _ assurance program to the extent appropriate-for the procured material, equipment or service-shall-be verified.

2. Vendor evaluations shall include inspections,

- 1 audits, or-surveillances as appropriate. These- l 48 activities shall be planned and performed in Page 37 of 101

op0rotienal Qunlity AccurGnDO Pltn Revision 16 accordance with written procedures based upon-procurement document requirements. _

3. Material and equipment may be procured and used based on appropriate certificates of conformance, provided the validity of such certificates are periodically evaluated by audits, independent inspection cnr tests and that such certificates comply with applicable code provisions.

9.4 Receint Inspection

1. Material and equipment shall be inspected upon receipt at the site prior to use or storage to l 32 determine that procurement requirements are satisfied. This inspection shall include verification that required documentation is complete.

2. Nonconforming material and equipment shall be controlled to assure such material or equipment is not utilized to fulfill a safety related, fire protection related or 10CFR71 related function prior to an acceptable resolution of the discrepancies.

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g -

9

-i-Op0rctien'c1 Quclity A3CurCn30 Plcn! 3

-Revision 16-cfy- 10.0 Ilentification and Control of' Materials;-Parts'andL

~993p_qnents 10.1 General Recuirements ,

l .- Measures shall be established for the identification and control of materie'3, parts and components, including partially ~t4nricated assemblies. These measures _shall;sa, ithat- "

identification of'the item is maintal by'heati number, part. number, serial number or other-appropriate means, either on the item or on:

records traceable _to.the item,cas required-throughout fabrication, erection, installation- .;

and use of the item.

2. -These identification.and control measures shall~

be designed to prevent the use of incorrect or defective material, parts and components.

10.2 Spare Parts Control -

1. Spare parts held for future use on safety i related, fire' protection related, and 10CFR71 related components shall be controlled in such a manner that assures'they will perform their

-safety function when utilized.

2. Measures shall be taken which assures these items-are ir. an aprPopriate. condition for use or will be placed in such-a condition prior ~to use.

10.3 Material Contrpl Materia. held in storage for use on safety related, fire protect'on related, and_10CFR71 related systems, structures or squipment shall be controlled in'such a s manner as to prevent its. degradation and to assure ,,

the rejection of incorrect or defective material. 1 This material shall be identified-by' heat number.or l other appropriate means, either on the item'or.on records traceable to the item. The method utilized in identification shall not significantly affect the-

-fit, function, or quality of the item being identified, i 10.4 Epceipt Inspection I Material, parts and components that are to be i utilized to fulfill a safety related, fire protection related, and 10CFR71'related function or used for shipment of radioactive materials shall be inspected f upon receipt to assure that associated procurement

\ document provisions have been satisfied. Measures Page 39 of 101 i

j

Operational Quality Assurance Plan Revision 16 shall be established for identifying nonconforming material, parts and components.

10.5 Nuclear Fuel Control Measures shall be established to protect special nuclear material against theft or diversion in accordance with applicable NRC regulations.

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OpOrctienci Qunlity AccurOnco PlCn l Revision 16

/~~N 11.0 ggAt.rol of Boecial Proiesseu 11.1 General Recuirements Measares shall be established to assure that special processes, including welding, heat treating, and non-destructive examination are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria and other special requirements.

11.2 Weldina Procedures

1. Safety related welding and brazing shall be perforred in accordance with qualified procedures. Safety related welding and brazing procedures shall be qualified in accordance with applicable codes and standards and shall be reviewed to assure their technical adequacy and approved by management.

2. Measures shall be ectablished for controlling welding and brazing procedures that assure such procedures are qualified, reviewed and approved, as required, prior to use, c

( 11.3 Welder Oualification

1. Measures shall be established that assure safety related welding and brazing is performed by qualified personnel. Welders and brazers shall be qualified, and requalified, in accordance with applicable codes and standards.

2. Measures shal) be establisi.ed for controlling welder and brazer quall'.ication and requalification that at.sure qualified personnel are utilized to perien safety related welding and brazing.

11.4 lieat Treatina Procedures

1. Heat treating shall be performed in accordance with procedures formulated and approved in accordance with applicable codes and standards.

2. Measures shall be established for controlling heat treating procedures that assure such procedures are qualified, reviewed, and approved, as required, prior to use.

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Op;ratien21 Quality AOCuranco PICn R;vicicn 76 11.5 NDE Procedures

1. Safety related non-destructive examinations (NDE) shall be performed in accordance with procedures formulated in accordance 'vith applicable codes and standards and shall be reviewed to assure-their technical adequacy and approved by management.

2. Measures shall be established for controlling NDE procedures that assure such procedures are reviewed and approved, as required, prior to use.

11.6 UDE Personnel Ot1311fication

1. Measures shall be established that assure safety related non-destructive examinations (NDE) are performed by personnel qualified and requalified in accordance with applicable codes and standards.

2. Measures shall be catablished for controlling NDE personnel qualification and requalification that assure qualified personnel are utilized to perform safety related non-destructive examinations.

O Page 42 of 101

Op0raticn01 Quality AccurenDO Plan Revision 16-12.0 Inspection

\' General Recuirempnts 12.1

1. Measures shall be established for inspection of activities affecting quality to verify conformance with the documented instructions, procedures and drawings for accomplishing the activity.- such inspections shall be performed by individuals other than those who performed the activity being inspected or directly supervised the activity being inspected.

2. Examinations, measurements-or tests of material or products shall be performed for each work-operation where necessu / to assure quality. If inspection of processed material or products ic impossible or disadvantageous, indirect control by monitoring processing methods, equipment and personnel shall be provided.

3. Both inspection and process monitoring shall be provided when. control-is inadequate without both.

4. If mandatory inspection hold points, which requ've witnessing or inspection and beyond which r~T work whall not proceed without prior consent are

( required, the specific hold points shall be indicated in appropriate documents.

12.2 Plant Operation

1. Measures shall be established that assure periodic inspection of safety related and fire protection related systems, components, and structures. Such inspection of plant systems and equipment shall be performed to assure that such systems and equipment are in the required status and configuration. Routine general inspections of the accessible plant facilities to verify appropriate safety measures are maintained including fire protection shall also be performed.

2. In addition, an inspection of the core shall be performed prior to startup following initial fuel-loading or refueling to assure specified fuel and reactor internal configuration.

12.3 Ipservice Inspection Measures shall be estualished that assure inservice inspection examinations are performed in accordance

("N s_/ with applicable provisions of the ASME Boiler and Pressure Vessel Code,Section XI as required by Page 43 of 101

oparoticnnl' Quality ACCurtnso Pltn Revision 16 10CFR50.55 (see Section 13.2 relative to Inservice Inspection functional testing).

12.4 Insoection of Maintenance and Modifications Measures shall be established which assure thet activities associated with plant maintenance and modifications are inspected when determined appropriate by quality or other qualified personnel.

Such inspections shall include verification that:

1. Appropriate procedures are available,

2. Plant equipment control exists,

3. Applicable procedures are adhered to,

4. Qualified personnel are utilized,

5. Fire protection measures are established,

6. Radiation protection measures are established,

7. Appropriate materials and replacement parts are utilized,

8. Work is completed as required, j }

9. Plant equipment is returned to service as required,

10. Activities are appropriately documented, and

11. Red _.1 dant equipment is available.

12.5 Modifications and Non-Routine Maintenance

1. Measures shall be established which assure that ,

non-routine maintenance and modification receive i prior review by a qualified individual to identify applicable inspections. Such reviews shall include considering: (1) required mechanical inspections, electrical inspections, instrumentation and-control inspections, structural inspections, and inspection of non-NDE special processes, (2) appropriate inspection procedures, and (3) appropriate qualification of inspection personnel.

2. Measures shall also be established which assure that the results of identified inspections are evaluated by a qualified individual to verify their adequacy.

h Page 44 of 101

__ _ _. ._ _. _ . y . .

-] .

Loporctionn1_ Quality 1AccuranoQ Plcu.

= Revision: 16 q f~/-

12.6. -Technical' Services'

&}L ^

= Meamtrese shall= be ' established .which' assure that .

+

activities associated:with technicalLservicesS(sucht

• as: surveillance testing,-instrument calibration, _ _

' laboratory servicas,Letc.) are inspected by. qualified' personnel when da.armined appropriate'by1guality orJ -

other: qualified personnel.

12;7 Reccint Insnection g Measures-sha31 be established-which assure that" I received items are inspected'by qualitied personnel (see Section 9.4).

12.8 Vendor Insoection Measures shall be established which assure that '

inspections'and_ process monitoring'specified-in1 appropriate-procurement dacuments for materials, .

• components,:and equipment-are performed.by qualified

-personnel.

12.9 Fire Protection Insoections Measures-shall be established which assure'that fire O protection _ inspections required by applicable-Technical Specifications are performed-by qualified

. personnel.

12.10 Radioactive Material Packaces Measures shall be established which assureLthat packages utilized to ship licensed radioactivo.

material off-site _are inspected in accordance!with-

-the applicable provisions 1of 10CFR71.

12.11 Emeroency Eauinment Measures shall be established which assure that emergency equipment requiredito implement emergency plans is inspected when aetermined appropriate by; qualified-personnel'.

12.12 Handlina Eauiement Measures shall be established which_ assure that. plant handling equipment (such as cranes,' lift trucks, fuel handling tools)'is inspected by qualified personnel and when determined _ appropriate by quality or other-qualified personnel.

Page (5 of 101-i

-,,-~'t . ~ ..,.,_,....m_,. _,._ _ , . . ,_ , _ , , - , . . _ _ _ _ . ,

. , _ _ _ . , _ _ . , , ._,.m.. _,. _m., . . ,-_ ..~,,.m._ _,_ m .m..., , _ . , . , , ' ' ,.,

opercticnol_ Quality AccurenOO Plcn Revision 16 12.:' Inonection Procedures

1. Required inspections shall be performed in accordance with appropriate instructions, procedures, and checklists. Such instructions, procedures, and checklists shall contain a description of objectives; acceptance criteria and prerequisites for performing the inspections.

These procedures shall also specify any special equipment or calibrations required to conduct the inspection. Inspection results shall be documented and evaluated by responsible authority to assure that inspectior, requirements have been satisfied.

2. Where activities are + be inspected, the activity procedure shall identify hold points in the activity sequence to permit inspection. The activity procedure shall require appropriate approval for the wor; to continue beyond the designated hold point and identification of those performing the inspection. The inspection procedure or checklist shall require recording the date, identification of those performing the inspection, and as-found condition.

12.14 Personnel Oqnlificatiqn

1. Personnel performing required inspections shall be qualified in accordance with applicable codes, standards and training programs. Required inspections shall not be performed by individuals who performed the inspected activity or directly supervised the inspected activity.

2. Personnel perforning inspections required by Sections 12.2, 12.4, 12.6, 12.10, 12.11, and 12.12 shall be qualified bated upon experience and training applicable to area of inspected activity and upon training in inspection methods.

3. Personnel performing inspections required by Sections 12.3, 12.5, 12.7, and 12.8 shall be qualified in accordance with ANSI N45.2.6-1978 as modified by Regulatory Guide 1.58, Revision 1.

4. Personnel performing insportions required by Section 12.9 shall be qualified in accordance with Section 14.0 of Appendix C.

O Page 46 of 101

~\:

OpOrcticn31_Quclity A2t, uron 30-Pltn Revision 16 r] 13.0 Test Contrpl

(/ _ 13.1  : General Reauirements

1. Measures shall be established to. assure.that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable documents. Proof tests prior to installation, preoperational tests, and operational tests-during nuclear power plant operation, of structures, systems and components shall be included as appropriate.

2. Test procedures shall include provisions for assuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. Test results shril be documented and evaluated to assure that test requirements have been satisfied.

(~ 13.2 Surveillance Tests

(,

1. b surveillance test program shall be established to assure that testing required to demonstrate that safety related and fire protection related structures, systens, and components will perform satisfactorily in service. Surveillance tests shall be identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable documents. The surveillance test program shall include, as a minimum, those surveillance tests specified in appli .ble Technical Specifications and functional Inservice Inspection testing of pumps and valves.

Surveillance requirements for fire detection and protection systems in other areas of the plants shall be developed using appropriate NFPA for guidance.

2. Surveillance test results shall be documented and evaluated to assure that test requirements have been satisfied or deficient items satisfactorily resolved. Functional Inservice Inspection tests shall be performed by personnel qualified in accordance with applicable requirements.

('s\

U Page 47 of 101

N, oporchicnc1TQuality Accurenco Plcn Revision 16; 13.3: Precoerational-and ooerational Tests  :

iMeasures shall be establishedEto: assure that

~

appropriate preoperational*and-operational-ftestsJare ~

.performedion safetyLrelated;and fire protection l related structures,: systems >and components--that havei l been subject tofmodification or significant s -maintenance.-Such tests shallibe-performed:in. ,

accordance withithe original: design andJtesting requirements or acceptable alternatives.- Test; 's results shallibe~ documented'and. evaluated to. assure  ;

s that; test 1 requirements-have.been' satisfied or deficient ~ items-satisfactorily, resolved.

13.4 Proof Tests i

Measures shall-be established to assure-that.

appropriate proof. tests are specified in procurement--

documents'for safety ~related and= fire protection. _

related replacement material and equipment and'that o such tests are performed and documented priorito ,

installation.

13.5 'Special' Tests "

Measures'shall be established that assure: safety l ,

related tests are reviewed and approved as required- .

by 10CFR50.59 and applicable Technical .

Specifications. Such tests shall be performed-in 4 accordance with appropriate procedures. --Test;results j shall~be documented.and_ evaluated.to assureq;.est requirements have been-satisfied, i

)

Page'48 of'101

i opcrotional Qusaity Accurtn00 Plth itevision 16 r~'s 14.0 ggnitol of Measurinc and Test EaulpRant

(] 14.1 General Reauirement.g Meubures chall be established to assure that tools, gauges, instruments and other measuring and testing devices used in activitic, affecting quality are properly controlled, calibrated and adjusted at specified periods to maintain accuracy within nocessary liuits.

14.2 Inntalled Plant Instrumentation Measures shall be established to assure that installed safety related plant instrumentation is maintained and calibrated at specified periods to maintain accuracy within necessary limits.

Maintenance and calibration of safety related instrumentation shall be performed in accordance with appropriato procedures and shall be controlled and documented.

14.3 Measurina and Test InstrumentatioD Measures shall be established to assure that tools (micrometer, calipers, etc.), gauges, instruments and other inspection, measuring, test equipmont and Os devices used to verify conformance to established requirements are maintained and calibrated at specified periods to maintain accuracy within necessary limits. Calibration of such measuring and test equipment shall be controlled and shall be traceable to the National Institute of Standards and Technology or where national standards are not available, the basis of calibration shall be documented.

/~'s Page 49 of 101

l l

l OpOrctien01 Quality Accurcn30 Plcn Revision 16

15. 0 1[AILdiffig,__ D toragg Aad.jihipping 15.1 Ganoral Rg_quirements

1. Measures shall be established to control the handling, storage, shipping, cleaning and prese rvation of safety related material and equipment in accordance with work and inspection instructions to prevent damage or deterioration.

2. When necessary for particular products, special protective environments such as inert gas atmosphere, humidity levels, and temperature levels, shall be specified and identified.

15.2 Storage Facilitieg Storage' facilities shall be provided at each operating nuclear plant for storage of safety related and fire protection related operating and maintenance supplies, spare parts, replacement parts, replacement equipment, materiais and tools. Thece storage facilities shall assure physical protection and protection from cnvironmental conditions including temperature and moisture as appropriate. Storage facilities shall be arranged and equipped to facilitate control of the stored safety related items.

15.3 Nuclear Fuel Sigra_g_q Areas shall be provided for storage of nuclear fuel which assure physical protection, subcritical arrangement, adequate cooling, adequate radiation shielding an1 containment of radioactive material as appropriate for the condition of the stored fuel.

15.4 Rggioactive Material Stgrace

1. Areas shall be provided for storage of radioactive material which assure physical protection, as low as reasonably achievable p A

radiation exposure to personnel, control of the stored material, and containment of radioactive material as appropriate.

2. Handling, storarc, and shipment of radioactive material shall ao controlled based upon the following crit- ia:

a Established safety rectrictions concerning ~

the handling, s orage. and shipping of packages for radioactive material shall be followed.

Page 50 of 101 j

oporotien01 Quality Accurenso PICn Revision 16

b. Shipments shall not be made unless all tests, O' certifications, acceptances, and final inspections have been completed.

c. Work instructions shall be provided for handling, storage, and shipping operations.

15.5 Storace Contro,1 Stored material, parts and equipment shall be controlled in a manner that assures safe plant operation when and if the items are utilized. Stored safety related and fire protection related items shall be controlled to assure that the item will perform its safety function when utilized.

15.6 Material Handlinc Safety related material, supplies, equipment and parts shall be handled in accordance with procurement documentation and in accordance with appropriate material handling practices._ Material handling equipment shall be subject ts periodic testing and preventive maintenance which assures its operability.

Appropriate operating instructions and procedures shall be provided for handling equipment.

15.7 Shippina and Packacina

1. Shipping and packaging requirements shall be prepared for material, equipment, and components that are to be shipped off-site and returned for use at a nuclear plant to perform a safety related function. Such requirements shall assure that the item's safety related function is not significantly degraded while in transit.

2. Shipping and packaging documents for radioactive material shall be consistant with pertinent requirements of 10CFR71 O

V Page 51 of 101

OpOratiCnci QuS11ty Accuran00 PICn Revision 16 16.0 Inspectiop, Test and Operatine_ Status 16 1 General Reauirements

1. Measures shall be established to indicate, by the use of markings such as stamps, tags, labels, routing cards, or other suitable means, the status of inspections and testa performed upon individual items of the nue ar plant. These measures shall provide for .he identification of items which have satisfactorily passed required inspections and tests, where necessary to preclude inadvertent bypassing of such inspections and tests.

2. Measures shall also be established for indicating the operating status of structures, systems and compor.ents of the nuclear power plant, such as by tagging valves and switches to prevent inadvertent operation.

16.2 Maintenance CQDtI21

1. Measures shall be established for the control of maintenance to safety related and fire protection related structures, systems nd components that assure that:

a. Affected structures, systems and components

( are removed from service and secured in a 1

manner consistent with operability and isolation requirements of the Technical specifications-( b. Repair and moC'.tj7ation activities are l

performed in a manner consistent with its

! importance to safety.

c. Upon completion of repairs and modifications the affected structures, systems and components are inspected and tested to determine that the required work was performed satisfactorily and that they will perform their safety function in the required manner.

l 2. In addition, measures shall be established to l control maintenance activities that assu.a l resulting radiation exposure to personne' is I maintsined as low as reasonably achieva (ALJ'A and consistent with pertinent . . .

I regu.utions.

l 3. The above measures shall be implemented by utilizing appropriate work authorization Page 52 of 10'

op;raticnal Quality Accurenco Plcn Revision 16

a. Proposed bypannon to safety rela ed and fire protection related items are reviewed to determine that the plant will be placed in an acceptable statuo when the bypana is applied.

b. Applied bypauneu are independently verified.

c. Removal of bypaonos from nafaty reinted and fire protection related items are reviewed prior to removal.

d. Application of bypannon to safety related and fire protection related items in authorized by renponoible pornonnel.

2. The application of safety related and firo protection related bypannen shall be conaldered a temporary measure and chall be reviewed periodically.

3. All required activitien accociated with the application, review, approval and removal chall be documented.

16.7 EntiloA9J;1v_nlat'2IlilLControl Inupoetion, tent, and operating statua of equipment and components associated with shipment of radioactiva material chall be established based upon the following critoria:

1. Inupection, test, and operating status of packages for radioactivo material shall be indicated and controlled by octablished proceduren.

P. Statua chall be indicated by tag, label, marking or log entry.

3. Statun of non-conforming parto or packagcc shall be positively maintained by catablished

% proceduren.

16.8 Reactor Si n tupJinsi HectaIt__ContrQ1 Measures chall be octablished for controlling reactor startupa and rentarts. Such meanuron shall accure that safety related systems, components and structures have been placed in the required status and reviewn have been completed to assure that the cause of any reactor trip (scram) han boon invastigated and satisfactorily renolved.

O Page S4 of 101

Op0roticcol Quality Accurcnoo Plcn ROvioica 16 t 17 . 0 EqnganLerning_)[a t e r i a 1 m (_J g tin _o r CONppngnta (D

() 17.1 general Roauiremonte

1. Monsures shall be established to control materials, parts, or components which do not conform to requiromonts in ordor to prevent their inadvortant use or installation. There measures shall include, as appropriato, proceduros for identification, documentation, segregation, disposition and notification to affected organizations.

2.  !!onconformance items shall be reviewed and accepted, rejected, repaired, or reworked in accordanco with documented proceduros.

17.2 Rt.:, 1 '9321100 i, < c yeui ca cnall be established which assure that

.uroty rolated and fire protection related i material, supplion, equipment, and components aro inspected to dotormino that they conform to specified requirements of portinent procuromont documents upon roccipt at the site. The absenco l 32 of required documentation or discropant documentation shall constituto nonconformance.

2. Provisions shall be mado for identifying nonconforming ! toms and for segregation of nonconforming items. Ilonconforming items shall '

not be used to fulfill a safoty related and fire protection related function until the discropancy is satisfactorily resolved.

17.3 Maintenanco TntwngfdqD Equipment, components or parts found nonconforming in a manner that could significantly affect its ability to fulfill its safety related and firo protection related function shall be identified as a nonconforming item and shall bo segregated.

Nonconforming items shall not be used until the '

discropancy is satisfactorily resolved.

17.4 12ignpyitiqn of Nongonformina_. Items

1. Moncuros shall be established which assure that nonconforming items are disposed of-in a manner '

which prohibits their inadvortent use or installation. Provisions shall bo mado for reviewing the nonconformanco and correcting discrepancies by repair or rowork if appropriate.

O Page 55 of 101 4

oporcticnni Quality Accurcn00 PICn Revision 16

2. The acceptability of such reworx or repair of materials, parts, components, nystoma, and W

structuren chall be verified by reinspection and rotesting the item as originally i;.opocted and touted or by a method which in equivalent to tho original inspection and tooting method.

Inapection, tooting, rework, and repair proceduren shall be documented.

3. Normally, nonconforming safety related and fire protection related itema shall not bo installed prior to natisfactory resolution of outstanding dincrepancien. In exceptional canon .

nonconforming items may bo inatalled provided specific action is taken, which annuron the item is not utilized to fulfill a safoty function, prior to resolution of the discropancy.

17.5 l{qngc11[gmnqc_J2qcmjnpf1ta112D

1. Nonconformance reports ohn11 be initiated for significant deviations from opecified requiremonta. Such reporto chall identify the nonconforming item, doncribe the nonconformanco, the disposition of the nonconformance, and the inspection requirements. Nonconformancon shall be reviewed and approved by appropriato quality personnel. lll

2. Nonconformanco reports shall be periodically analyzed to show quality trends and the resultu of this review chall be reported to the appropriato lovel of management for review and ,

annonnment.

17.6 Rapprting Moacurea shall be antablished which accure that defects as defined in 10CFR21 and failures to comply with the Atomic Energy Act of 1954, an amended, or any applicable rule, regulation, order or 11conao of the NRC relating to a substantial safoty hazard aro reported in accordance with the applicable requirements of 10CFR21.

l k

l Pago 56 of 101

op0 ratio 201 QuSlity A00urtnoo PICn Revision 16 18.0 Corrective Action 18.1 General Reauirements

1. Measures shall be established to assure that conditions adverso to quality, such as failures, malfunctions, discropancies, deviations, ,

defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverne to quality, the measures shall assure 1 that the cause of the condition is determined and corrective action taken to preclude recurrence.

2. The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriato lovols of management. -

18.2 Onoratina_ occurrences and Events Measures shall be established which assure that operating occurrences and events that could have a significant safety offect are invectigated, reviewed, and reported as required by the Technical Specifications. Such measures shall assure that T appropriate corrective action is taken and that the

(/

s_ event or occurrence is reported to responsibic levels of management. Correctivo action includes provisions which preclude recurrence.

18.3 Adminiatyative Control Discrepancies Measures shall be established which assure that significant discrepancies identified during quality assurance program audits.are reported to those responsible for the activity and to appropriato levels of management. These measures shall includo corrective action designed to preclude recurrence of the discrepancies identified and verification of implomtntation.

O Page 57 of 101

Cp; rational Quality Accuranco PICn Revision 16 19.0 QMplity AgguratngelgggI.4g 19.1 General Tinguiremonta O

1. Sufficient records shall be maintained to furnish evidence of activities affecting quality. Those records shall include at least the followingt

a. Operating logs and the results of reviews, inspections, tests, audits, nonitoring of work performance and material analysis.

b. The records shall also includo closely ,

roleted data such as qualifications of personnel, proceduros, and equipment.

c. Inspection and test records shall, as a minimum, identify the inspector or data recordor, the type of observation, the results, the acceptability, and the action taken in connection with any deficienclos noted.

2. Records shall be identifiable and retrievable.

3. Requirements shall be established concerning record rotention, suca as duration, location, and assigned responsibility which are consistant with applicable regulatory requirements.

19.2 Operating Records Measures shall be established which assure that records as they apply to plant operation are generated and retained as required by the Technical Specifications or other regulatory requirements.

19.3 d Plant Modification Reggrd.n Measures shall be established which assure that adequate records are generated and retained to reconstruct plant modifications that are safety related or fire protection related.

1 19.4 Plant Maintenance Records

( Measures shall be established which assure that i

records portaining to maintenance of plant safety related and fire protection related structures.

equipment and components are generated and retained.

19.5 P_ersonncLQqplificationRecorda Measures shall be established which assure personnel qualification records are generated and retained.

Page 58 of 101

. ~ .. _ _.

Cporotienni Quality Accurtn30 Pltn Revision 16

(~} 19.6 Procurgment Records V

Measures shall be established which assure that safety related, fire protection related, or 10CFR71 related procurement documents and associated documents are generated and retaitied.

19.7 Surveillqnce Test Recorda Measures shall be est blished which assure that records associated with Surveillance Testing, including Innervice Inspections, are generated and retained.

19.8 Audit Reporto Measures shall be establis'ed which assure records pertaining to audits of quality activities are generated and retained.

19.9 EDdioactive Material Conttpl Measures shall be established which assure that records associated with radioactive material control are generated and maintained.

() 19.10 Drawincs Measures shall be established which assure that records of drawino changes made to plant safety related and fire protection related structures, equipment and components are generated and retained.

19.11 Records Manacement

1. Records management systems shall be established which assure that the required records are collected, stored, and maintained in accordance with ANSI N45.2.9-1974. Such records shall at least be stored in insulated filing devices (rated 350-1 hour by UL as to fire resistance only) located in areas having' combustible loading of less than 5 lb/sq ft, or duplicate records shall be maintained in romote locations.

Specific records shall be identified in implementing or source documents. Identification shall indicate records required by Technical Spe,fications, committed to standards, and other reg .atory documents.

Page 59 of 101 l

1 CporOticn21 Quality Accurcn 0 PICn Revision 16

2. Records management systems chall be established  !

which assure that those records used to demonstrate program implementation are collected, stored, and maintained in accordance with good records management practicos. Such systems shall assure that these records are made available to auditors and inspectors in a timely manner,

(

F O

i i

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l Page 60 of 101

op0rOtienni Quality AccurCnSO PICn Revision 16

-s 20.0 Audits

\' 20.1 General Recuirements A comprehensive system of planned and periodic audits shall be carried out to verify compliance-with all aspects of the operational Quality Assurance Program and to determine the effectiveness of the program.

The audits shall be performed in accordance with written procedures or checklists by appropriately trained personnel not having direct responsibility in the areas being audited. Audit results shall be documented and reviewed by management having responsibility in the area audited. Follow-up action, including re-audit of discrepant areas, shall be taken where indicated.

20.2 Reauired Audits Measures shall be establiched which assure that the provisions of the operational Quality Assurance Program are audited periodically. In addition, an overall audit shall be performed periodically which determines the adequacy of the program with respect to requirements contained in the operational Quality Assurance Plan. This overall audit shall be performed by an organization other than that responsible for

administration or implementation of the program.

20.3 611ditEheduleg

1. Required audits shall be performed each year except that this time period may be extended to not more.than two years provided such extensions are justified based upon past experience, special audits may be schrdaled on the initiative of quality assurance personnel based upon suspected or known discrepancies or as directed by management.

2. Appropriate audit schedules shall be prepared each year.

20.4 Audit Procedures Required audits shall be performed in accordance with appropriate audit procedures. Checklists may be used as audit procedures or in conjunction with audit procedures. Procedures shall include auditing requirements at various levels of the operational Quality Assurance Program.

/s 20.5 Audit Renorta Q. 1. Reports of the results of each audit shall be prepared. These reports shall include a l Page 61 of 101 l

Operational Quality Assurance Plan Revision 16 description of the area audited, identification of individuals responsible for implementation of the audited provisions and for performance of the audit, identification of discrepant areas, and recommended corrective action as appropriate.

2. Audit reports shall be distributed to the appropriate management level and to those individuals responsible for implementation of audited provisions.

3. Audit reports and associated nonconformance reports shall be periodically analyzed for quality trends and the results reported to the appropriate level of management for review and assessment.

20.6 Corrective Act1QD Measures shall be established which assure that discrepancies identified tw Sudits or other meann are resolved. These measures shell include notification of the manac r responsible for the discrepancy, recommended corrective act ion, and verification of satisfactory resolution. Discrepancies shall be lh resolved by the manager responsible for the discrepancy. Line management shall resolve disputed discrepancies.

O

i Cporatienol Quality A00uren30 Plcn ROY 16 App 02 dix A APPENDIX A  :

Monticello Structures _ .vstems, and Components Subiect to-ADoendix B of 10CFR50 i l

i

1. . STRUCTURES l i

Reactor Building i Plant Control and Cable Spreading Structure Off Gas Stack i Intake Structure-(Service Water pump area)  ;

Diesel Generator Building  ;

Diesel Fuel Oil Day Tank Rooms '

Turbine Building (parts which house, support and/or i protect safety related equipment)-. .t Off Gas Compressor and Storage Building (parts which-house, support and/or. protect safety related equipment) ,

Emergency Filtration Train (EFT)- Building

n

2. MECHANICAL SYSTEMS AND-COMPONENTS *

'l COMPONENTS Reactor Coolant System Reactor VesselL O

Reactor Vessel Support Skirt '

Reactor Vessel Stabilizer

-Rocirculation System Piping Recirculation System Pumps and Valves Main Steam Piping (to and-including outermost containment isolation valve)

Main. Steam-Safety Relief Valves Main Steam Safety Relief Valve Discharge Piping Feedwater Piping (to and. including outermost' containment isolation valve) 3 Control Rod Drive Housing Supports j Reactor Vessel Internais-l Fuel' Assemblies-Core Support Structure Jet Pumps Control-Rods Liquid Poison Pipe Core Spray Sparger Li Control Rod Drive System-Control Rod: Drives -

Control Rod Drives-Accumulators i Scram Discharge Volume O Scram Piping

.[

Page 63 of 101

_ . . _ . _ _ _ _ _ _ . _ . . _ _ . ~ . . _ _ _ _ _ _ . _ . _ _ . _ _ . _ . , _ _ _ . . . _..__ ., _ . , , - .

Operational Quality Assurance Plan Rev 16 Appendix A ColiPRERTE Etandby_ Liquid Control svatna SIE Tank SLC Pumpa SLC Explosive Valves SLC Piping PtimttrY_C_Qntninu nt Dryvell Torus Drywell Vent Piping / Vacuum Dreakora Torus Ring lloador and Downcomora Containment Ponotrations Containment Piping and Valves (to and including outermont isolation valvo)

DPc99AdurY_CQntainEDt RD Ventilation Isolation Damporo Standby Gan Treatment Filters and Fans llenidual llont tiemoval System RilR Piping, Pumps and Valven S-Rl!R lloat Exchangers (chell nido)

Cnre Snroy_.Hyntra Core Spray Piping, Pumps, and Valvon 11191Llno. nun _Csal.antJ nd n911sn_SXtitem IIPCI Steam Piping and Valves Inuido Containment (to and including outotrost isolation valvo) llPCI Steam Supply and Exhaust Piping and Valvon (outsido containment)

IIPCI Pump-Turbino llPCI Injection Piping and Valvon

!!PCI Suction Piping ,

Reaglgr Core Isol0 tion CQoling_Sy1Lem RCIC Stoan Piping and Valvos Inside Containment (to and includ*.g outermost isolation valvo)

RCIC Steam Supply and Exhaust Piping and Valves (outsido containntent)

RCIC Pump-Turbino RCIC Injection Piping and Valves RCIC Suction Piping l

l Pago 64 of 101 l

Op0rctien31 QuSlity Accurcuso PIC3 Rev 16 Appendix A Service Water Systea

'~'

~]-

Emergency Service Water Pumps '

Emergency Service Water Piping and Valves RHR Service Water Pumps RHR Heat Exchanger (tube side)

RHR Servico Water Piping and Valvos EFT Emergency Servico Water Pumps, Piping, and Valves Reactor Water Cleanun System RWCU Piping and Valves (to and including outermost isolation valvo)

Snent Fuel Storace Systema Spent Fuel Pool Diesel Generator-Supnort System Air Start System from Receivers to Air Start Solenoids Fuel Oil System from Day Tank to Injectors Diesel coolers and Associated Piping and Valves (water side)

Diesel Fuel Oil Heatina and Ventilatina Systen Emergency Filtration Train (EFT) for Control Room and EFT Building Combustible Gas Control System SECTION 2 NOTES:

1. Mechanical components included within each mechanical system include hangers (up to and including the first anchor supporting a safety related section of piping),

fittings, flanges, vessels, tanks, etc. as necessary to perform the system safety functions.

3. ELECTRICAL SYSTEMS AND CO'4PONENTS COMPONENTS 4160 Volt Bus 16 Breaker 152-602, 601, 609, 610, Feed Breaker 408 RHR Service Water Pump B Motor RHR Service Water Pump D Motor RHR Pump B Motor RHR Pump D Motor Core Spray Pump B Motor 480 Volt Load Center 104

() No. 12 CRD Pump Feed Breaker 152-606 Page 65 of 101

~ - -

Cparctic;21 Quality AccurOnGO Pica nov 16 App ndix A Alft9._YDit_DMD_1f2 Breaker 152-502, 501, 509, 511, Food Breaker 308 RilR Servico Water Pump h Motor RIIR Servico Water Pump C Motor Rl!R Pump A Motor RllR Pump C Motor Coro Spray Pump A Motor 400 Volt load Contor 103 No. 11 CRD Pump Food Breaker 152-506

.430 Volt SwitEI1'Ici1E_.Lgild_.CfDier 104 480 V MCC 142 (1) (Essential) 400 V MCC 143A (1) 480 V MCC 143D (1) 400 V MCC 144 (1)

ALO_Vglt SwitgligimI3go.d CentcI 103 400 V MCC 133A (1) 400 V MCC 133D (1) 480 V MCC 134 (1)

DicRELGRJ30IAtQE_lio .- 11 (1)

DirnRLQRJ1prator. No,_12 (1) 250 V DC (.D iv i s inn _1LQinkriblit Lon_lmncl_D11 (1) 22_Y_D.C__iDiV._lpion 21 Dintrijtution _ IMngl_D19.Q (1) 12D V DC__ _DiPriril2ution_P_031cl_D-11 (1) 125 V DC_J11n.tribRt_ip31_lMnnLD-21 (1) 12.9/ 24 0 Vo1 t 11C_lnutrJ1 ment {ttign_ Dinttilntt121L.fiuici (1)

SECTION 3 NOTES:

1. For those electrical systems or components designated with the Note (1) above, quality assurance electrical program requirements are applicable dnly to those portions of systems as defined in Section 2 as necessary to perform the system safety function.

2. Electrical components included wi' hin each electrical system include power sourco, breaker, control circuit cable, relaying and operating device (motor, solenoid, heater, relay, etc.) as necessary to perform the system safety function.

3. Cortain components are excluded from the quality assuranco program requirements if they meet the critoria described in Section 5.

pago 66 of 101

OpOraticC01 QuS11ty AccurOn30 Pltn Rev 16 Appendix A

4. INSTRUMENTATION SYSTEMS AND COMPONENTH Reactor Protection System Primary t'ontainment Isolation System High Pressure Coolant Injection System Initiation and ,

Isolation Reactor Core Isolation Cooling System Initiation and Isolation Core Spray System Initiation Low Pressure Coolant Injection System Initiation Automatic Blowdown System Neutron Monitoring System (IRM and APRM)

Standby Gas Treatment System Initiation SJAE off Gas Radiation Monitor EFT System Initiation and Operation Combustible Gas Control System SECTION 4 NOTES:

1. For th no instrumentation systems designated above, quality assurance instrumentation program requirements are applicable only to those portions of systems defined in Section 2 as necessary to perform the system safety function.

2. Instrumentation components included within each instrumentation system include power supply, sensors,

(]/

s_ relays, wiring and final operating device (solenoid, relay, etc.) as necessary to perform the system safety function.

3. Certain components are excluded from the quality assurance program requirements if they r'2t the critoria described in Section 5.

5. ELECTRICAL AND INSTRUMENTATION SYSTEM COMPONENT EXCLUSION CRITERIA

1. Any component of an electrical system in Section 3 or instrumentation system ir. Section 4 As excluded from the quality assurance program requirements if it meets the following criteria:

a. A failure of the component by electrical shorting, open circuiting, grounding or mechanical failure would not render the system incapable of performing its intended safety function.

b. A failure of the fluid pressure boundary of the component would not render the system incapable of l performing its intended safety function.

r~}

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Page 67 of 101

Cp0rctic201 Quality AccurcCCO Pica Rev 16 Appendix A

2. Small spare parts having no traceability, such as commercial off-the-shelf items, may be purchased as nonsafety-related and then qualified for use in equipment requiring quality assurance. Examples of such items are resistors, capacitors, switches, indicators, coils, wire, connectors, solid state devices and miscellaneous hardware.

O l

1 l

O Pago 68 of 101

oporctienti Qun2ity AccurccSO Plan Rev 16 Appendix B APPENDIX B

('

Prairie Island Structures. Systems, and Components Subiecl__to Appendix B of 10CFR50

1. REACTQR SYSTEM AND FUEL A. Reactor Vessel and coolant System Reactor vessel Reactor vessel support Reactor vessel internals Full length control rod drive mechanism housing Part length cor.;rol rod drive mechanism housing Steam generator (tube side and shell side)

Pressurizer, including instrumentation, piping, and components Reactor coolant hot and cold leg piping, fittings surge pipe, fittings Loop bypass line Temperature detector bypass manifold Reactor coolant thermowell Reactor coolant thermowell boss Safety valves Relief valves

(~') Reactor coolant system boundary valves (J Control rod drive mechanism head adapter plugs Reactor coolant pump Pump casing Main flanges Thermal barrier Seal housing Pressure retaining bolting Reactor coolant pump motor Shaft coupling Flywheel Reactor coolant pump internals RCC tbimble plug (rod control clusters)

Primary and secondary sources Electric modules with safety function cable with safety function B. Fuel Assemblies Fuel assemblics, sub-assemblies, components and materials, including fuel material Page 69 of 101

, ,__-._,..-e._._,-7 _.. -.- - -,_-.,--.,-_ .,

operational Quality Assurance Plan Rev 16 Appendix D

2. REACTIVITY CONTROL SYSTEMS h Drivo nochanisms including:

Control rod cluster drive shaft assembly, including latch assembly Reactor trip breakers Control rods and rod cluster assemblios Control rod guide tubo control rod drive housing Electric modulos with safety function Cable with safety function

3. CIIEMICAL AND VOLU_ME QONTROL SYSTEM Rogonorativo heat exchanger Lotdown heat exchanger Reactor coolant filter Volume control tank Positivo displacement charging pump and motor Seal water filter Lotdown orifices and lotdown valves Excess lotdown heat exchanger Seal water heat exchanger Boric acid tanks Doric acid transfer pump Boric acid filter Reactor coolant pump seal and bypass orifico Piping, inboard of isolation valves Electric modules with safoty function Cable with safety function Heat tracing

4. 1HQ.QHE INSTRUMENTATIQ1{

Thimble guide tubos Seal tablo S. DQRQH RECYCLE SYSTEM Recyclc holdup tanku, piping and valvos associated with gaseous rrdioactive waste .

6. EMEJLGENCY CORE _COOi,J.UG SYSTEM Accumulators High head safety injection pumps Piping, inboard of isolation valves i Motors, electric n sulos, with safety function Cable with safety function

7. C_Qll.TAINMENT SPRAY SYSTE1.

Refueling water storage tank Spray aoditive tank Page 70 of 101

Op3rctional Quality Accurtnoo Plcn Rev 16 Appendix B g spray pumps g'

Spray rings and nozzles Piping and valves Pump motora Electric modules with safety function Cable with safety function

8. BESIDUAL llEAT REMOVAL SYSTEM Pumps and motors Heat exchanger Piping and valves with safety function

?,lectric modules with safety function Cable with safety function

9. SPENT FUEL POOL. COOLING SYSTEM Piping and valves whose failure could result in significant release of pool water

10. CONTAINMENT FAN COOLER SYSTEM Ductwork Fans Dampers

~N, Fan coolers (Q

Electric modules with safety function Cable with safety function

11. WASTE PROCEESING SYSTEM Gaseous and liquid waste piping and valves forming part of containment boundary Systems handling gaseous rr.dioactive materials Electric modules with safaty function Cable with safety function ,

NOTE: The Waste Gas Disposal System shall be maintained in accordance with tl.a guidance establiched in Regulatory Guide 1.143, Revision 1, October, 1979.

12. EAMPLING SYSTEMS Valves and piping from the reactor coolant system up to the second isolation valve outside containr^~t Valves and piping to the first isolation valv, from other safety related-systems

13. STEAM GENERATOR BLOWDOWN Piping from steam generator to containment isolation valves Page 71 of 101

Oporcticoni QuSlity AccurCnGO PlC3 Rev 16 Appendix D

14. REACIQ1 PROTECTION SYSTEM Electrical modules cable

15. EEQ. PISS RADIATION MONITORS Radiation Monitors, including electric modules and cable with a safety function, associated with the Shield Building, Auxiliary Building, Spont Fuel Pool and Control Room Ventilation Systems

16. CONTAINME}LT HYDROGEN CONTROL SYSTEM Piping and valves with safety function Electric modules and cable

17. REACTOR VESSEL GdRVICE EOUIPMENT Containment polar crane Vessel head handling equipment Crane strt%'. ural supports Crane electrical, cable, controls and instrumentation with safety function

18. REFUELING EOUIPMENT Spent fuel cask Auxiliary Building crane Auxiliary Building crane structural supports Crane electrical, cable controls and instrumentation with safety function Fuel transfer tube -

Spent Fuel Bridge Crane Manipulator Crane

, 19. FUEL STORAGE New fuel racks Spent fuel racks Spent fuel pool structure and enclosure ,

Spent fuel storage casks Independent spent fuel storage installation concrete pads

20. .9_OlTFOL ROOM PANELE Electric modules, with safety function cable with safety function

21. IDCAL PANELS AND RACKS Electric modules with safety function Cable with safety function Page 72 of 101

'T CparctienS1 Quality ACCur0n00 PICn Rev 16 Appendix B

_ 22. MAIN STEAM SYSTEM

's J Main steam piping and valves from steam generators up to and including piping restraints downstream of the main steam isolation valves Main steam piping and

-valves from main steam lines to auxiliary feedwater pump turbine Steam line flow restrictor Safety and relief valves Piping to first isolation valves and safety and relief valve discharge Electric modules with safety function Cable with safety function

23. FEEDWATER_ SYSTEM Feedwater piping and valves inside containment structure up to and including first isolation valve outside containment structure Electric modules with safety function cable with safety function

24. AUXILIARY FEEDWATER SYSTEM Piping and valves supplying auxiliary feedwater from and including containment isolation valves to connections with feedwater lines 7s Auxiliary feedwater pumps (turbine and motor-driven)

( ) Piping and valves supplying auxiliary foodwater from the cooling water system Electric modules with safety function Cable with safety function

25. COOLING WATER SYSTEMS component cooling water systems (essential)

Piping (except to curbine building and non-essential equipment)

Heat exchangers, with safety function Pumps Pump motors Surge tank Valves, isolation Valves, other, with safety function Electric modules with safety function Cable with safety function Cooling water systems (essential)

Piping (except to turbine building and non-essential equipment)

Diesel engine pumps Strainers, with safety function Valves, isolation Valves, other, with safety function r- Screen wash systems, with safety function

'\ Traveling screens, with safety function Electric modules with safety function Page 73 of 101

Operational Quality Assurance Plan Rev 16 Appendix D  ;

Cable with safety function Diesel engine pump auxiliarios as follows:

Diesel oil storage tanks  !

Day tanks Fuel oil transfer pumps and motors i Fuel oil piping and valves with a safety function Starting air compressors Air receivers Starting air piping and valves with a safety function Cooling water piping and valves with a safety function Electric modules with safety function Cable with safety function Diosol engine, lubricating oil and jacket cooling systems Diosol fuel oil

26. INSTRUMCl!' LAIR SYSTEM Piping and valves associated with containment penetration

27. DIESEL GENERATQE Diesel oil stor.g' tanks

• Day tanks Pumps and motors, fuel oil transfer Diesel filter Valves, with safety function Piping except vent and fill piping downstream of last valve Cooling water system pipe and valves Diesel generator jacket cooling water system Diesel generator lubricating oil system Air intake Electric modules with safety function Cable with safety function Diesel fuel oil

28. DIESEL GENERATOR AIR _ STARTING SYSTIM Compressor.

Air receivers Piping and valves from receiver to diesel generator Piping between compressor and receiver

29. ELECTRICAm CLASS 1RJ3MMA Switchgear, transformers, motor control centers, load centera, batteries and chargers, and associated i equipment with safety function NOTE: Point of interface with onsite electric power i systems (i.e., at point of interface with Class 1E breakers which isolate main Class 1E onsite buses Page 74 of 101 l i

.)

-oporcticaol Qunlity AccurcOoo Pitu  !

'Rev 16 Appendix B 1

(~ from.the=offsite power system; and including. l components and circuitry interfaces that affect  ;

the proper performance of such interfacing i breaker).  !

4,160 - 480 V switchgear from engineered safety systems-  !

(EST), inc'uding ESF buses ,

4,160 - 480 V transformers (ESF load centers)' ,

480 - 120/208 V transformers (control room and ESF area emergency lighting)  ;

480 V-switchgear (ESF load centers)

-480 V-motor control and motor control centers  :

125 V station batteries and racks (control and vital  ;

instrumentation power supplies) q 125 V. dc panels and .switchgear- (vital de power i distribution) l 120:V ac instrument bus panels (vital instrumentation ac

- power distribution)

Containment penetration assemblies #

Main control board Radiation monitor panel Hot shutdow.i panel  !

Control room air conditioning control panel-Post LOCA Hydrogen control panel Emergency lighting i Emergency communications Diesel generator and accessories O. Diesel-generator control panels 3 Relay, boards and racks Wire and-cable raceway system "

Underground electrical duct bank' system Cable system (power, control and instrumentation)

Instrument racks Electrical supports '

Heat tracing / freeze protection

30. INSTRUMENTATION AND CONTROL SYSTEM COMPONENTS Reactor trip system , .

Engineered safety features (ESF) . actuation system Systems recruired for safe shutdown- 1 Safety rel:sted instruments, tubing and fittings

31. HEATING, VENTILATION AND AIR CONDITIONING SYSTEMS (HVAC)

Control and Relay Room RVAC System Air handling units Fans,,ductwork and dampers Filters chillers and chilled water pumps Auxiliary Building Special Ventilation System Faus, ductwork and dampers L() Filters Screenhouse Ventilation System h

Page 75'of 101 1

'e tWe t y y  ;--4.=

-9 yT.'-g4een -$ 3-'gg gi,'pyy4,3.g - ,7.p'W '

g F W ~a4 Yew-B'r 4,--51'"8?*-'*8- w ur- F-#+v V*PT *f"#"e t

l Operational Quality Assurance Plan Rev 16 Appendix B Fans and dampers associated with diesel engine h ventilation Shield Building Ventilation System Fans, ductwork and dampers Filters Battery Room Special Ventilation System Fans, ductwork and dampers Spent Fuel Pool Special Ventilation System Exhaust fans, ductwork, dampers Exhaust filters Diesel Generator Rooms Cooling System Fans, ductwork and dampers Auxiliary Building Normal Ventilation System Ductwork and dampers associated with steam exclusion Turbine Building Ventilation System Ductwork and dampers associated with steam exclusion Electric modulco with safety function Cable with safety function HVAC sensors and monitors having safety function

32. CIVIL STRUCTURES AND FOUNDATLQllE Containment and structures containment airlocks Containment isolation (valves, piping, canisters)

Containment penetratiens Shield building Auxiliary building Control room Diesel generator room Radwaste building Cooling water intake structure Electrical tunnels, with safety function Pipe tunnels, with safety function Shielding structures Turbine Building (housing emergency diesel generatot cooling water pipes, batteries, safeguards switchgear, auxiliary feedwater pumps)

• 33. OTHER A. Fire protection system piping associated with the safeguards ventilation exhaust filters and containment penetration D. Turbine building crane Crano structural support Crano electrical, cable, controls and instrumentation with safety function 9

Page 76 of 101 ,

5 operhtienci Quclity Accurenco PICn Rov 16 Appondix C APPENDIX C <

Nuclear Plant Fitq Protection ProctrjlLa 1.0 Policy Statement i

Northern States Power Company (NSP) has established a system of Administrative control Directives (ACDs) that implement the Operational Quality Assurance Plan. This system shall be used to implement the requirements of the operating .

nuclear power plant fire protection program. The basic requirements of the fire protection program are specified in this appendix to the operational Quality Assurance Plan.

2.0 organization 2.1 General Requirements

1. NSP shall be responsible for the establishment and implementation of the fire protection program NSP may delegate to other organizations the w .k of establishing and implementing the fire protection program, or any part thereof, but shall retain responsibility for the program.

- 2 The authority and duties of persons and organizations involved in the fire protection program shall be clearly established and delineated in writing.

3. To r.7sure adherence to the fire protection program, management measures shall be established which provide that the individual or group assigned the responsibility for checking, auditing, inspecting, or otherwise verifying that an activity has been correctly performed is indep:ndent of the individual or group directly responsib]e for performing the specific activity.

2.2 Fire Protection Organization Summary The NSP organization is summarized in Section 3.0 of the Operational Quality Assurance Plan. In addition to that summary, the following additional responsibilities shall pertain to the fire protection program.

1. Director Power Supply Quality Assurance l3

a. Scheduling and assuring completion of independent off-site fire protection inspections and audits.

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Operational Quality Assurance Plan Rev *.6 Appendix C

b. Reviewing non-site purchase requisitions related to fire protection.

2. General Manager Nuclear Site (Monticello and Prairia Island)

a. Procurement of equipment for the fire 49 brigades.

b. Establishing a policy for the security actions to be taken by the guard force during a fire.

3. Monticello and Prairic Island Plant Managers j 50

a. Routine inspection of the plant-for fire hazards.

b. Establishing plant fire brigades.

l49

c. Ensuring that fire brigade members receive required training and physical evaluations.

Coordinating fire drills and determining their effectiveness,

e. Establishing cooperation with the local fire.

department, includfoy joint drills and llh training sessionr "* ;amiliarize fire department personnel with plant access routes, layout, equipment, and special hazards.

f. Establishing storage requirements to insure no additional fire hazards are created.

g. Establishing a surveillance program for -ire protection systems and fire fighting equipment.

h. Establishing a system to control nonconforming items,

i. Reviewing required work processes for fire hazards and possible reduction of fire protection system effectiveness.

j. Reviewing modifications to determine if they would cause an unreviewed fire hazard or reduce the effectiveness of the fire protection systems,

k. Establishing a fire salvage program (when h required).

Page 78 of 101

.. m._ , , _ . _ _ . . . _ - ~ _ .. _. _ _ . . . _ , . , - , .

operctioncl:--Quclityf Accurcnoc z PIEn  ?

1Rev116' ! Appendix C-

'p 1, ' Reviewing purchase requisitionslinitiated by e

f( ). the plant and Nuclear Projects Department:

'that are related'to fire. protection.-

-m. DevelopingLinstructions1for fighting. fires <in $

specific. areas ri identifying effects'off f firdu-in speci'ic -e a s .-

-l49

n. Preparing news ce;aase information for NSP's

• Communications-Department.

4. Manager Power Supply Training - Nuclear (Monticello and' Prairie Island) 61 '

a. . Establishing- a training program 3 for the fire-brigades.

2.3 Fire Protecti'on Engineer

1. A fire protection engineer (or_ engineering-consultant).shall be used to provide _thelfollowing:

types of services:

a

a. Review of design for a significant modification to a fire protection, system.

b. _ Review of proposed plant modifications which-O-.

would; introduce major' hazards not: analyzed in the' Fire Hazards' Analysis.-

c

c. Triennial. independent-fire protection- ,

inspections (see Section:14.2).

~2. . The fire protection engineer (or engineering

' consultant) shall: meet the following qaalifications:

a. 'A graduate of:an engineeringJcurriculum-of accepted standing who has completed not_lesss than :six years of engineering attainment:

' indicative,of growth.in engineering:

competency and achievement,Ethree of which shall have been in responsible: charge of fire; protection. engineering work, 2I.

b.- 'A member in:the Society of Fire. Protection-Engineers.

3.0 -Nuclear Plant-Fire Brigades

- 3 .1 Monticello-

.' A fire brigade shall be establ-ished in accordange 1.

with the requirements of 10CFR50, Appendix R, Section-III.H, and the~requirenents listed below:

Page 79 of 101

,,_ . _ - . _ , . , _ . _ _ . . _ _ _ _ . _ . _ . . u. _ ....__,_.a__._. ___

Op3rctionni QuSlity AccurcnCO PICn RCv 16 App;ndix C

a. Fire'brigado composition may be less than the minimum requirements for'a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate the unexpected absence of-fire brigade:  !

members. Under this circumstance, immediate action shall be taken to restore the fire brigade to within the r,inimum requirements.

3.2 Prairie Island

1. A fire brigade of five persons shall be on-site at l all times in addition to the minimum shift crew complement needed to safely shut down the unit (s).

a. Fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to cccommodate the unexpected absence of fire brigade H members. Under this circumstance immediate action shall be taken to restore the fire brigade to within the minimum requirements.

2. Each fire brigado shall have an appointed leader.

This leader shall not be t... 7hift Supervisor (the Unit No. 1 Shift Supervisor at Prairio Island).

3. All new members of the fire brigades shall have an initial physical examination for strenuous physical activity as experienced in fire fighting.

Annual follow-up physical examinations shall include respiratory protection qualification testing which screens all respirator users (including fire brigade members) for-cardiopulmonary deficiencies. Physical examinations shall be. conducted by a physician. A program shall be established by NSP's corporate physician to ensure that all respirator users, when subject to even the most severe working conditions, are physically fit to wear a-

. respirator. The program shall include pulse, blood pressure, and spirometry testing, and a medical history review in which the possibility of past or present heart disease is determined. The program shall be administered by nursing personnel who will perform the necessary cardiopulmonary screening function.

4.0 Fire Protection Training 4.1 Monticello and Prairie Island

1. Level I fire protection training shall be general training given to operations and maintenance personnel assigned to nuclear power plants.

Following initial training, these topics shall be Page 80 of 101

Op0 ration 01 Quality Accuronso Pltn Rev 16 Appendix C c'~' reviewed at least annually with required

\,. personnel. Level I shall cover, as a minimum, the following areas:

a. Basic principles of fire chemistry and physics.

b. Fire hazards.

1) Common fire hazards.

2) Combustibles, general.

3) Flammable liquids.

4) Flammable gases,

c. Fire detection systems.

d. Types of extinguishing systems,

e. Special fire hazards associated with nuclear power plants,

f. Emergency Plan with emphasis on fire emergency.

~) 2. Basic instruction in fire protection shall be given to contractor personnel before granting them

. unescorted access to safety related areas of the plant.

4.2 Monticello

1. Fire brigade training shall be conducted in accordance with the requirements of 10CFR50, Appendix R, Section I.

4.3 Prairie Island

1. Level II fire protection training shall be given to all fire brigade members. An initial training program with annual retraining shall be conducted.

Retraining shall repeat all Level II subject material over a period of approximately two years.

Level II shall include a detailed treatment of the subject matter in Level I. In addition, the following items shall be covered:

a. The identification and location of fire hazards and associated types of fires that 7s could occur in the plant.

l

\2 b. The identification and location of fire fighting equipment in each fire area.

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oporotienci Quality Accurenco Plcn Rev 16 AppOndix C

{ c. Familiarization with layout of the plant I including access and egress routes in each area.

d. The proper use of fire fighting equipment.

e. Methods of fighting each type of fire.

f. Review of the plant fire fighting strategies with specific coverage of each individual's responsibilities.

g. Proper use of comuunication, lighting, ventilation and emergency breathing equipment.

h. Considerations of radiation and contamination in fire areas.

2. Level III training anall be presented to the fire brigade leaders. Initial training with annual retraining shall be provided. Included will be a detailed review of Level I and II training and the following additional material:

a. The direction and coordination of fire fighting activities,

b. The proper method of fighting fire inside buildings and confined areas.

c. Evaluation of fire hazards.

3. Training Documentation Classroom training sessions, practice sessions, and drills for the fire brigade shall be documented. The following should be included in the documentation for persons participating:

a. Name.

b. Date.

c. Summary of what was done.

d. Evaluation by observer.

O Page 82 of 101

oporatien01 QuOlity AOCurtnDO Pltn Rev 16 Appendix C 5.0 Drills and Practice

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d.1 Monticello

1. Fire protection drills and practices shall be conducted in accordance with the requirements of 10CFR50, Appendix R, Section I and the requirements listed below:

a. A meeting shall be held after each drill to discuss the drill and the need to repeat portions of the training program that are applicable to the_ type of drill performed.

b. Preplanned strategies, and the proficiency of brigade members and control room operators in their-use shall be tested during drills,

c. Each year, one drill, conducted with any fire brigade, shall involve the local on-duty fire department.

5.2 Prairie Island

1. Drills

/~T a. Drills shall be scheduled so that each fire

(,) brigade will participate in at least four drills per year. The following types of drills shall be scheduled:

1) Involve local on-duty-fire department.

This shall be done at least once a year, with any fire brigade.

2) At three year intervals, a randomly selected,' announced-drill shall be critiqued by qualified individuals independent of NSp's staff.

3) Back shift, conducted by the fire brigade leader on duty at the time.

This shall be scheduled at least once per year for each brigade.

b. Except as required above, drills may be announced and may involve only the shift fire brigade members (to preclude the disruption of essential plant activities).

c. All drills shall be preplanned and critiqNed.

A meeting shall be held after each drill to discuss the drill and the need to repeat

(~')%

(- portions of the training program that are applicable to the type of drill performed.

Page 83 of 101

operational Quality Assurance Plan Rev 16 Appendix C

d. To the extent practical, fire brigade members h shall use protective equipment, suppression systems, and other equipment used to fight an actual fire during all drills. Proplanned strategies shall be tested during drills as well as the proficiency of brigade members and Control Room operators in their use.

2. Practice

a. Practice sessions shall be held at least once every year. These sessions shall involve actually fighting fires which are similar to those which might be encountered in the plant. These sessions shall include:

1) Use of fire fighting equipment.

2) Use of breathing equipment under strenuous conditions.

3) Extinguichment of fire.

4) Best method by which to approach each type of fire, to the extent possible,

b. Brigade members missing a practice session shall be rescheduled to attend a later session with another brigaCo. If this is not possible, they shall be required to review the training material covered during the practice session.

6.0 Control of Combustibles and Ignition Sources 6.1 Monticello

1. Control of combustibles and ignition sources shall be in accordance with the requirements of 10CFR50, Appendix R, Sectibn K, and the requirements listed below:

a. All areas containing safety related equipment or cables shall be surveyed once each working day for fire hazards by a member of the plant staff.

b. Storage of combustible materials shall be permitted only in posted areas or in approved cabinets and containers.

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l Page 84 of 101 i-

(opOrotienol Quality AccuranDO-iPlcn _

lRev 16L Appendix C- 1 g-s Lc. Transient:combustiblesJinianyEsafety related-  ;

T -

area,.or.areaicontaining safefshutdown equipment, shall'be? limited toJthe; equivalent; '

of 2'. gallons of: combustible ~ liquid.

Use'of:-

-larger amounts of combustible >materialushall:: -i be governed by written. procedures.which-specify! augmented fire protection measures.- +

d. A person"designatedLas~~a. fire watchiand- -1 equipped to prevent ~ and -; combat; fire shall be' '

assigned toisafety related areas-where cutting,1 welding,7 grinding and open:flamel work is involved.-

e. The fire watch shallEremain'in~the assigned area.for 30 minutes after work involving;the1 cutting,1 welding, grinding,- or.open flame is completed.--

.1. When' excessive radiation' exposure'to the--

fire watch is a concern, alternate'firei ,

watch measures may be implemented;if these-alternate measures address how to

-detect,' prevent?and combat a-fire in the fire watch area..

1 f.- Where feasible, all movable combustible-material below or within:35 feet of cutting,.

welding,7 grinding, or open flame work shall;

-be removed, and-all immovable combustibles-below or within 35 feet shall be protected,

g. Smoking _shallfbe prohibited'in all safety.

related areas, except those specifically.

designated'by the plant management.

6.2 Prairie' Island 1.- Permanent and Temporary Storage

a. Measures.shall-be established 1to' minimize fire? hazards-in areas containing safety-related' equipment-or; equipment required to safely shut down thecreactor(s) which: .. ;

.1 ) - Govern the handling andclimitation'of:

the use of ordinary combustible

-materials,' combustible and flammable-

_ gases and'11guids, high ' efficiency particulate air and' charcoal filters,-

_ dry ion exchange resins,7or other: _

combustible-supplies in safety related-areas.

Page 85 of 101'

operational Quality Assurance Plan Rev 16 Appendix C Govern the removal from-tho aron of all 2) waste, debris, scrap, oil spills, or lhL other combustibles resulting from the work activity immediately following completion of the activity, or at the end of each work shift, whichever comes first.

3) Govern the handling of transient fire loads such as combustible and flammable materials during maintenanco,-

modification, or refueling operations.

4) Govern the use of specific combustibles-in safety related areas.

a) All wood used in safety related areas during maintenance, modification, or refueling operations (such as laydown blocks or scaffolding) chall be treated with a flamo retardant, b) All untreated wood in safety related areas (during operations other than maintenanco, modification or refueling) shall be limited to less than 2 cubic feet per area, c) Equipment or supplies (such as new fuel) shipped in untreated combustible packing containers may be unpacked in safety related areas if required for valid operating reasons. However, all combustiblo materials shall be removed from the l area immediately following the unpacking, i .

d) Large amounts of combustible material shall not be left l unattended during lunch breaks,-

shift changes, or other similar periods, e) Looso combustible packing material such as wood or paper and excelsior shall be placed in metal containers with tight- fitting self-closing metal covers.

O l Page 86 of 101

lOpOrctionni Quality kocurcnUO Plcn Rev 16" iAppendix-.C q_ .b. All' areas containing: safety related equipmentL

or cables shall-be surveyed-'once each working.

A 2 '

day for fire" hazards,byfa member ofithe plant--

staff. Storage _ofl combustible materials-shall_be' permitted onlyLin posted areas-orLin--

approved cabinets and' containers.

Unnecessary transient combustibles shallinot-

-be stored in areas containing safety related equipment or_-areas containing: safe' shutdown?

equipment or other essential' auxiliary _

equipment area.(e.g., HVAC equipment room).

c. Transient-combustibles 11n any; safety;related area or area containing, safe shutdown _ .

equipment shall be' limited to:the equivalent' of 2 gallons-of combustible liquid. 'Use of.

larger amounts of combustible material shall be governed by written procedures which specify augmented' fire protection measures.

2. Cutting, Welding, Grinding and Open Flame

a. Cutting,Lwelding, grinding and open flame work-in safety related areas shallibe' administratively-controlled. A' person designated as fire watch and. equipped 1to-

-y g prevent and combat' fire shall be. assigned to

_(_) safety related areas where cutting, welding, grinding _ and open flame : work is involved.

The fire. watch shall' remain in.these1 assigned areas for 30 minutes after the work involving

~

the cutting, grinding!or open flame is '

completed.

1. When excessive radiation exposure to the fire watch is a concern,' alternate fire-watch measures may be implemented if these alternate measures address how to detect, prevent and combat a fire in the fire watch. area,

b. Where' feasible, all movable combustible material below or within 35 feet of cutting, welding, grinding, or open flame work shall be removed.and all immovable combustibles '

below or'within 35' feet.shall'be protected'- . _

c. Smoking shall be prohibited _in'all safety.

related areas, except those specifically_

designated by the plant management.

-v

.d Page 87 of 101

Cparctional Quality Accurcnco Plcn

-RCv 16 App;ndix C

d. Fire barrier penetration leak testing shall be done with approved and reviewed procedures. Permission to do this leak testjng_shall be obtained from the Shift Supervisor.

7.0 Fire Fighting Procedures 7.1 Monticello Fire fighting procedures shall be established in accordance with the requirements of 10CFR50, Appendix R, Section K.

7.2 Prairie Island

1. Fire fighting procedures or instructions shall be developed to cover the following areas:

a. Discovery of fire including:

1) Notification.

2) Attempts to extinguish fire.

b. Action of Control Room operator including:

1) Announcement.

2) Sounding of fire alarm.

3) Who to notify.

c. Selection and delineation of responsibilities of fire brigade members.

d. Coordination of off-site fire department activities,

c. Actions of security guards during a fire emergency.

f. Delineation of responsibilities of other plant personnel.

g. Instructions and preplanned strategies for fighting fires in specific areas of the plant when the general instructions are not adequate. These instructions shall include;

1) Identification of combustibles in area.

O Page 88 of 101

~

oporctionaliQuclity ADCurtnoo Pleab o~ J

-Rev 16  : Appendix.C--

I .2)

~

Identification"of safe shutdown L('TL /L 1

equipment in arealand alternate- - '. . j equipment:available for' performing:that 1

function..

3) LFire suppression. equipment availablelin-

[

tthe area.  ;

4) Information -' showing : ventilation : control--

(power: sources) , access -hallways, stairs, and doors.

5) Identification of~ plant systemsLthat shnuld'be mcnaged to reduce the damage potential from:affiretin the area..

6) -Identification of-radiologicalL.and toxic:-

- bazards' in the' area. - -

7) Ventilation system')ineups to minimize.

spread of smoke and to remove smoke from.

• the~ area.

8)- Ident'ification of: actions whichcmust be-coordinated with, operations-personnel.

g 2. Instructions and-preplanned strategies:shalliber

^ tested during. drills.

8.0 Modification Control (Monticello and2 Prairie. Island).

8.1 ~ Review of modifications.forfpossible-impact?on plant;-

fire. protection-provisions shall be' performed if-determined required-by a-designated member of the-plant-

. technical staff.. The following-guidelines shall1be- ,

used in. making this . determination::

1. Could the modification [present a hazard not- -

considered-in the~ Fire Hazards Analysis?' Will

. additional analysis 1be required?-

2. Could the modification have' the potential' to .

interfere with installed fire' protection equipment' or does it modify existing-fire protection-equipment?-

3. CouldLthe fire protection system require modification because of the-change?_'

~

Page 89,of 101

, . . . . . =_u. . - ..

Operational Quality Ausurance Plan Rev-16 Appendix C 8.2 If a fire protection review is required, the individual assigned to perform the review shall use the following as a guide:

1. Does the modification reduce the fire protection provisions for safety related or " safe shutdown" equipment?

2. Will . it be necessary to do a fire hazards analysis?

3. Does the design present an obstruction to installed fire protection equipment?

4. Will the installation of the equipment temporarily remove a fire protection system from service?

5. Does the modification involve thermal stress relieving and, if so, have precautions been taken?

6. Will any fire barriers be affected by the modification?

8.3 A modification shall be allowed to proceed only after satisfactory resolution of these concerns.

9.0 Procurement Control (Monticello and Prairie Island) 9.1 Underwriters Laboratories (UL) and Factory Mutual (FM) directories shall be reviewed to determine if the item is listed as being UL or FM approved. If the item is listed, a manufacturer shall be identified-and the item procured in accordance with NSP's procurement process for nuclear plants.

The one exception for not buying an em that is UL or FM listed is if it is a replacement ; original equipment or NSP standard type, then it shall be identified as such and procured from the original supplier or manufacturer. As a minimum, the item of equipment shall, by appropriate testing, meet NFPA standards.

9.2 If the item is not listed by UL or FM, the following process shall be used:

1. An evaluation shall be made to determine the compatibility of the item to the existing system or component, or

2. If the item has been manufactured for a long period of time, and

a. The item is standardized, and Page 50 of 101

n, .. . . . . .. , , . -~ _ . ,

toperationni QuclityTAccurcuso;Plon. J!

-- Rev 16 ~ Appendix C_

'b. The1 1 tem hasfa satisfactory' performance Oi . history,fanic

__ c.: Appropriatefreceipt inspection is identified-in the' procurement documents,(then'an -- '

evaluati~onsis unnecessary. ._The~ fact =that thei ,

supplier and'itemimeets-these' requirements'  :

shall be-documented in-the: procurement-files.4 4

9.3 Parts lof components-and' equipment that have-UL or FM-approval as;a unit shall be procured as.follows:

1.- The-part shall be-manufactured by'the original:

manufacturer of the' component or. equipment - i

-whenever possible.

~2 . The model number of theLeomponent or. equipment- >

shallobe identified.

3. The specific part number shall be identified.=

4. Documentation from the. supplier shallobo-~requeste'd that indicates the-part delivered = meets the '

specification of the:part used-in the original-component or equipment. LIf the-part has been changed, the manufacturer'shall-bezasked to indicate any changes'in the operation-of the O component or equipment. Inflieu of-this--

documentation, the acceptance-of thelpart shall be based on inspection or testing.-  !

9.4- All purchase _ requisit: ions pertaining _ tof fire -protection systems and equipment shall be-reviewed. Site 52-requisitions shall be revi'ewed by.an= individual-designated-byfthe Plant-Manager.- Non-plant requisitions shallLbeLreviewed by an11ndividuali designated by the Director Power Supply _ Quality =

' ~

Assurance.

-10.0 Instructions, Procedures, and Drawings (Monticello and-Prairie Island) i

.10.1 The system of Administrative Control' Directives '(ACDs) '

'shall be used=to delineate responsibilities and

-requirements for the fire protection program.

-10.2 Departmental instructions and procedures shall-be revised or issued to implement-the_ fire protection-program, responsibilities and requirements-contained in the ACDs.

10.3 Fire? protection maintenance, modifications,-

inspections, tests,-administrative controls, drills, x and training shall'be prescribed by written instructions, procedures, and drawings.

Page 91 off101

.Op3raticnO1 Quclity AccurOnco Pltn rov 16 App;ndix C 11.0 Surveillance and Inspection (Monticello and Prairie Island) 11.1 The Technical Specifications specify the surveillance and inspection requirements for the fire protection system. Surveillance shall be scheduled, performed, and documented in accordance with standard directives governing the surveillance testing program.

11.2 Procedures shall be developed to assure adequate preventive maintenance of fire protection equipment, including fire suppression water system pumps and hydrants.

12.0 Conditions Adverse to Fire Protection (Monticello and Prairie Island) 12.1 Administrative Control Directives shall establish criteria for housekeeping.

12.2 Work control process procedures shall be used to correct equipment failure, malfunctions, deficiencies, and defective components of fire protection systems.

12.3 As part of the training process, site personnel shall l 32 be instructed on how to identify fire hazards and report them to their supervisor.

13.0 Itecords (Monticello and Prairic Island)

Site and Corporate directives establish nuclear plant 53 records, creation, and retention requirements. Fire protection records requirements shall be included in the scope of these directives.

14.0 Audits (Monticello and Prairie Island) 14.1 In addition to normal quality assurance audits (at least biennial), an independent fire protection and loss prevention inspection and audit shall be performed annually at each plant utilizing either qualified

• off-site NSP personnel or an outside fire protection engineer or engineering consultant (annual independent inspection).

14.2 An inspection and audit by an outsido qualified fire protection engineer or engineering consultant (see Section 2.3) shall be performed at each plant at least every three years (triennial independent inspection).

14.3 Inspection and audit results shall be reported to levels of management having fire protection program responsibilities in those areas audited or inspected.

l O

Page 92 of 101 l

oporationci Quality Accurenco Plcn Rev 16 Appendix D APPENDIX D Revision 16 Chance Summary This appendix summarizes the changes made in Revision 16 to the Operational Coality Assurance Plan. The intent of this appendix is to fulfill the requirements for identifying changes in accordance with 10CFR50. 54 (a ) ( 3 ) , Conditions of Licenses. This appendix is not a  :

part of the operational Quality Assurance Plan.

Chance Number identifies the change number next to the sideline on the affected pages, page identifies the page numbers containing the change.

Reason (R) identifies the reason for the change.

Basis (B) identifies the basis for concluding that the revised program incorporating the change continues to satisfy 10CFR50, Appendix B and the quality assurance program description commitments previously accepted by the NRC.

Change Reason Number Pace (s) Basis 1 i R1 Revision number updated to 16.

/'N Hi Not required; editorial item.

2 4 B1 Corrected typographical error of word

" explicitly".

Hi Not required; editorial item.

3 8,26,27,77 R1 Title change from Director Power Supply Quality Assurance & Testing Services due to corporate reorganization.

Responsibility for testing _ laboratory

, services assumed by the Director Power l Supply Support Services.

Di This is a responsibility description only. It does not reduce previous l commitments.

! 4 8,21 81 Title change from Director Finance &

Performance.

Di This is a title change only. It does not reduce _ previous commitments.

5 8,19 81 Title change from Director Support Services.

l Hi This is a title change only. It does l not reduce previous commitments, l

O Page 93 of 101

op;ratien21 Quality Accurenco Plcn Rev 16 Appendix D Change Reason

-Number Pace (s) Basis 6 9,20 El Responsibility for Testing Laboratory services reassigned to Director Power Supply support Service due to corporate reorganization.

Di This is a responsibility description only. It does not reduce previous coLmitments.

7 9,10,20 El The position of Manager Testing Laboratory was eliminated due to corporate reorganization. The responsibilities were reassigned to the-Manager Material Services & Testing.

Di This is a responsibility change only.

It does not reduce previous commitments.

8 10,12 El Corrected wording to "These positions are". Included phrase " Responsibilities include:" as part of the firs,t paragraph.

Di Not required; editorial item.

9 11,15 El The responsibility for the Emergency Preparedness Program reassigned to the Vice President Nuclear Generation due to reorganization of the Emergency Preparedness Program.

R1 This is a responsibility description only. It does not reduce previous commitments.

10 11,14,20 El Director Power Supply Support Services assumed responsibility for management of the NSP Corporate Security Program from the General Manager Nuclear Support Services.

Di This is a responsibility description only. .It does not reduce previous commitments.

11 11 El Clarified responsibility of General Manager Nuclear Site.

Di This is a responsibility description only. It d ws not reduce previous commitments.

O Page 94 of 101

r -

Op;rctional Qu211ty Accurtnso Pltn Rev 16 Appendix D

(^ Change Reason

( j]. Number Pace (s) Basis 12 11,17,20 Bi Responsibility for providing security personnel at nuclear plants assumed by the General Manager Nuclear Site.

Responsibility for the training of security personnel at Buclear plants assumed by the Manager Power Supply Training - Nuclear.

R1 This is a responsibility description only. It does not reduce previous commitments.

13 11 B1 Typographical error; period mispositioned.

Di Not required; editorial item.

14 11,13 R1 Responsibility for site procurement activities reassigned to the General Manager Nuclear Site with the establishment of the Materials ,

Engineering Department.

Al This is a responsibility description

(' only. It does not reduce previous

\ commitments.

15 12 B1 The position of Plant Manager (Prhirie Island only) assumes responsibilities for operation and maintenance of the independent spent fuel storage installation (collocated at the Prairie Island site).

El This is an improvement of the QA-Program description. It does not reduce previous commitments.

16 12,13 R1 Changed reference to "Monticello and Prairie Island)" from "(each plant)"

for format consistency.

Di Not required; editorial item.

17 10 B1 Included phrase " Responsibilities include:" as_part of first paragraph.

Di Not required; editorial item.

18 13 B1 changed wording from " Audit of selected site level activities..." This is a clarification of the responsibilities for the Superintendent Quality ~

I~')

'V Services. Internal audits of all levels of the operational Quality Assurance Program is the responsibility Fage 95 of 101

operational Quality Assurance Plan nov 16 Appendix D Change Reason Number Pqge(s) Basis, of the Manager Nuclear Operations Quality Assurance.

Di This is a responsibility description only. It does not reduce previous '

commitments.

l 19 13,24,25,26, El Changed terminology from " plant" to 29,92 " site" With respect t o administrative l control directives and instructions to reflect conversion of the administrative control directives and instructions from plant level to site level.

Hi This is descriptive change only. It does not reduce previous commitments.

20 13 R1 Removed separate listing of responsibility-(old item 8) for developing and implementing a quality control program for Nuclear Projects section projects since the site reorganization has Manager Nuclear Projects reporting to the General h Manager Nuclear Site, responsibility is already stated in responsibility item 1. Removed separate listing of responsibility (old item 9) for performing required inspections and tests as this is redundant to responsibility item 1.

Di This-is a responsibility description only. It does not reduce previous commitments.

21 13 R1 Clarified responsibility. With site reorganization, the Nuclear Projects

. Department is no longer limited to "long range" or "large projects".

Di This is a responsibility description only. It does not reduce previous commitments, t

22 14 81 Changed wording from ". . . Request for l Engineering Studies." A " Request for l Engineering Studies" is a form not a function.

Q1 Editorial item; not required.

1 Page 96 of 101 l

Operational Quality Assurance Plan ,

Rev 16~ - Appendix D; -

Ts :-3=

-5 Change - Reason' >

'~# Number Pace (s) Basis .',

+

23 14 R1 Eliminated responsibility.for assuring-procedure adherence by contract employees.

H1' .This.is a managerial non-QA' responsibility, notz an operational responsibility.'lIt does not reduce previous commitments.' ,

24 14,15,20 R1 . Manager Corporate Security now reports to the Director-_ Power Supply Support-Services._ This' reflects the-corporate reorganization. . .

Di This is a'respansibility description-only. -It does-not reduce previous. -

Jommitments.-

25 -14,19 R1 Deleted "all" as_ grammatical.ly--

redundant.

• Hi Not required; editorialiitem.

26 15 Ri-.old.section. 3.3.2.2.2.3 renumbered'as 3.3.2.2.2.4_due to Manager Corporate-

~

O- Security-no longer reporting to.Gener'al, '

Manager Nuclear Support Group.-

Hi Not required; editorialLitem.

27 15 B1 Clarified responsibilitiest of: Manager-Nuclear Radiological Services. _

Hi This is a responsibility _._decariptions only.- It does_-not. reduce _ previous commitments'.

28 15 R1 _ Clarified that Manager = Nuclear Radiological Services. responsibilities:

are relatedLto1 radiological environmental activities. '

El This is-a-responsibility description only. It'does notireduce previousz ^

commitments.

29 15 R1' Title change ~from Manager Special

-Nuclear Projects.

Di This is a title change only.- It does not reduce previous commitments.

s Page 97Jof-101 '

o

. . ~ . , ~ , .,- - - , -.- -

oporctionci Quclity Accurenco Plan Rev 16 Appendix D change Reason Nunber Pacets) Basis 30 16,17 R1 The responsibilities for site training assumed from Director Power Supply Training.

Hi This is a responsibility description only. It does not reduce previous commitments.

31 16 R1 The position of Manager Power Supply Training - Nuclear changed from a superintendent position and added as a position with QA responsibilities.

This position reports to the Director Power Supply Training.

Hi This is a title change only. It does not reduce previous commitmrnts.

32 17,;4,35,38, B1 Changed terminology from " plant" to 55,92 " site" to reflect site reorganization.

Di This is a descriptive change only. It does not reduce previous commitments.

33 18 R1 Clarified responsibility of the Vice President Transmission & Inter-Utility Services.

Di This is an improvement of the QA Program description. It does not reduce previous commitments.

34 19 B1 Clarified responsibility of the General Manager Substation / Transmission Services.

Si This is an improvement to the QA Program description. It does not reduce previous commitments.

35 19 Ri Corrected typographical error of the word " positions".

El Not required; editorial item.

36 19 R1 Reference to Electric Utility removed.

El The maintenance and testing of Electric Utility equipment is a non-QA respormibility, not an operational responsibility. It does not reduce previous commitments.

37 19,20 R1 Section reformatted to accommodate the additional responsibilities assumed by Director Power Supply Support Services.

Hi Not required; editorial item.

Page 98 of 101

OpOratiCn31 QuOlity AOcuren30-Pltn Rev 16- Appendix D

(h Change Reason

(_ / Number Pace (s) Basis 38 20 Bt The position _of Manager Material Services & Testing added as a position with QA respons!"ilities. This position assumed responsibilities from the Manager Testing laboratory.

Di This is a responsibility description only. It does not reduce previous commitments.

39 20 El Title cnange from Manager Power Supply Procurnment & Material Management.

Di This is a title change only. It does not reduce previous commitments.

Au 20 R1 Clarified responsibility of Manager Fuel Resources.

Hi This is a responsibility description only. It does not reduce previous commitments.

41 20 El The responsibilities for the Manager Ih Fuel Resources were removed because the k- service provided was that of a procurement agent rather than that of providing QA functions. While this position assisted with QA activities, when requested, the responsibility for the QA activities remained with the requesting department.

Di Procurement of nuclear and. diesel-fuel is a responsibility of General Manager Nuclear Site. This is a responsibility description only. It does not reduce previous commitments. The disposition of depleted nuclear fuel is a responsibility of Manager Strategic Issues Group.- This is a responsibility description only. _It does not reduce previous commitments. The coordination of safety related documents provided by the nuclear fuel vendor is an administrative non-QA responsibility, not an operational responsibility. It does not reduce previous commitments.

The negotiation and administration of nuclear fuel and service contracts is g3 an administrator of contracts non-QA

( i responsibility, not an operational responsibility. It does not reduce previous commitments.

Page 99 of 101

h Op0rction21 Qualitcf Ascurenco Plcn l Rev 16 Appendix D Changa . Reason Number Page(s) Basis 42 20 Ri Sections for Manager Fuel Resources and Manager Procurement & Material Management renumbered with the addition of Manager Corporate Security and Manager Material Services & Testing as positions reporting to Director Power Supply Support Services.

El Not required; editorial item.

43 21 R1 Eliminated responsibility for industrial safety support for Power Supply.

Di This is a corporate non-QA responsibility, not an operational responsibility. It does not reduce previous commitments.

44 21 El The position of Manager Performance Measures was eliminated due to corporate reorganization.

Responsibility for drawing control is retained by the Director Power Supply -

Finance & Performance.

Di This is a responsibility description only. It dces not reduce previous commitments.

45 23 El Corrected typographical error of word

" suitably".

B1 Not required; editorial item.

46 24 El Clarified that the referenced director is the Director Power Supply Quality Assurance.

El Not required; editorial item.

47 24 El General Manager Nuclear Site identified as the approving authority for site level administrative control directives and instructions.

B1 This is a responsibility description only. It does not reduce previous commitments.

O 1

l Page 100 of 101

op;rctional Quality 4A00uranco Plen:

Rev; 16! _AppendixLD?

f Change _

Number

-Paae(s)

Reason Basis f\.

48' ---

-37 El Changed wording from-" monitoring"Lto! ~

"surveillances" to_ accurately reflect ~

ANSI N45.2.13-1976 wording:forf verificationiactivitiesE .

31 This-is_an improvementLto the?-QA: .

Program description. It does not' reduce previous: commitments.

49 78,79 B1 . General ~ Manager Nuclear Site =added:as a:

position with responsibilities inithe:

fire protection program 'due to site-reorganization.: :This position-assumed:

responsibilities from-the1 Plant l1:anagers

, for procurement of equipment-_forithe:

-fire brigadefand establishment of policy for security actions during a1 fire. '

JOL This isla responsibility description only.- It does not reduce previous commitments. '

p i s./

50 '78 Bl. Added' reference to-Monticello and.

Prairie Island-for format consistency.:

[

Hi Not required; editorial-item.

51 79 B1 The responsibility-for trainingiof1 fire:

brigades assumed-from the1 Director ,

Power Supply Training;(formerly Manager Production Training).1 D1 'this is a responsibility description only. It does not reduce l previous' commitments.-

52 91 R1 Changed-terminology tof" site"-with-reorganization.of Plant"and Nuclear ~

Projects departments to report to'the- ,

General Manager Nuclear Site.-

Hi This is a-descriptive change--only. It-

.does not' reduce: previous commitments.

53 92 El changed reference from " General office" to " Corporate" for-; terminology; consistency.

Hi Not required; editorial item.

O

.Page 101-of 101 P

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