ML20127N915

Rev 2 to, Operational QA Plan

ML20127N915
Person / Time
Site:	Monticello
Issue date:	11/15/1977
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20127N909	List: ML20127N906 ML20127N915
References
NUDOCS 9212010450
Download: ML20127N915 (76)

Text

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9 NORIHERN STATES POWER CO)fANY I

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1 OPERATIONAL QUALITY ASSURANCE PLAN-REV: 2

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, ' Approved By: ) -

ExecutYve V Me esident Effective Date: .NOV 15 - TI, 9212010450 771122' PDR ADOCK 05000263-P. PDR m_

Operations 1 Quality Assurance Picn Rev: 2 4

Table of Contents

?"El 1.0 Policy Statement 1 2.0 Introduction 5 3.0 Organization 6 1

4.0 Operational Quality Assurance Program 17

5.0 Design Control 37 i

6.0 Procurement Document Control 39 7.0 Instructions, Precedures & Drawings 41 8.0 Document control 43 9.0 Control of Purchased Material, Equipment & Services 46 i

10.0 Identification and Control of Materials, Parts &

Components 48

, 11.0 Control of Special Processes 50 12.0 Inspection 52 13.0 Test control 55 i

14.0 Control of Measuring & Test Equipment 57-i 15.0 Handling, Storage and Shipping 59 16.0 Inspection, Test and Operating Status 61 i

17.0 Nonconforming Materials, Parts or Components 64 18.0 Corrective Action 66 19.0 Quality Assurance Records 68

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20.0 Audits 72

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Operational Quality Assur:nce Plan l Rev:,2 l

1.0 Policy Statement )

- Northern States Power Company (NSP) has established and is unplementing 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.

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. 10CFR$0, Appendix B " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Planta".

2. NRC Operating Licenses.

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

The Operational Quality Assurance Program shall incorporate: (1) the requirements of ANSI N18.7-1976 as modified by Table 1-1 and (2) the requirements of the following 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 (Regulatory Guide 1.8 Rev: 1).

2. ANSI N45.2-1971

3. ANSI N45.2.1-1973 (Regulatory Guide 1.37, 3-16-73).

4. ANSI N45.2.2-1972 (Regulatory Guide 1.38, Rev: 2).

5. ANSI N45.2.3-1973 (Regulatory Guide 1.39, Rev: 1).

6. ANSI N45.2.4-1972 (Safety Guide 30 August 11, 1972).

7. ANSI N45.2.5-1974 (Regulatory Guide 1.94, Rev:1).

8. ANSI N45.2.6-1973 (Regulatory Guide 1.58, Augus t, 1973).

9. ANSI N45.2.8-1975 l

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Op3 rational Quality Assurcnca Plcn Rev: 2

10. ANSI N45.2.9-1974 (Regulatory Guide 1.88, Rev: 2) except that radiographs shall not be retained due to their non-permanent nature; records which documont the acceptability (Radiograplic Review Forms) shall be retained as stipulated in the Standard.

11. ANSI N45.2.10-1973 (Regulatory Guide 1.74, February,1974).

12. ANSI N45.2.11-1974 (Regulatory Guide 1.64 Rev: 2).

13. ANSI N45.2.12 (Draf t 4, Revision 2, Jan 1,1976) as modified by ANSI N18.7-1976.

14. ANSI N45.2.13-1976

15. ANSI N101.4-1972 (Regulatory Guide 1.54, June, 1973).

Management directives and departmental instructions and procedures shall provide for compliance with appropriate regulatory, statutory, license and industry requirements. Specific quality assurance requirements and organizational responsibilities for hnplementation of these requirements shall be specified in bnplementing directives and instructions.

Compliance with this policy and the provisions of the Operational Quality Assurance Program is mandatory for NSP personnel with respect to nuclear plant operational activities or activities which support nuclear plant operation. Personnel shall therefore, be familiar with the requirements and responsibilities of the program th? are applicable to their indiv-idual activities and interfaces.

The Executive Vice President, through an independent organization, shall periodically have the Operational Quality Assurance Program reviewed to assure its adequacy.

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Op3 rational Quality Assurance Plan j Rev 2 i .

Table 1-1 s Exception to ANSI N 18.7 - 1976

1. Section 5.2.13.2 last paragraph; change " quality" to " quantity." This

change corrects an error in the standard.

2 Section 6; delete this section. The referenced documents are explicitly j referenced in the. Operational Quality Assurance Plan.

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3. Documentation required by ANSI 18.7-1976 may be deferred for emergency work.

i- Emergency work is defined as that work that must be completed immediately and which, if delayed, may result in an unsafe condition or significantly interfere with reliable plant operation.

l 4. Section 5.2.2; replace the 3rd sentence with the following -

" Procedure changes shall be reviewed.and approved as required by the j Technical Specification." Delete the 4th sentence.

5. Section 5.2.5; replace the 2nd and 3rd sentences with " Temporary i

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

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6. Section 5.2.9; delete this section. The Plant Security Plans contain '

appropriate security provisions.

7. Section 5.2.11,1st sentence; change " abnormal. occurrences" to " reportable occurrences."

! 8. Section 5.2.13.2, 4th paragraph; change the 1st sentence to read ".. . . .

l installation or use of such items that serve a safety function."

9. The provisions of 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-

2. requirements stipulated in such Technical Specifications shall be utilized j- rather. than those contained in Section 5.2.15.

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10. Section 5.3; 1 change- the last sentence to read " Procedures shall be prepared and approved prior to implementation as required by 5.2.15."

11. Exceptions to Regulatory Guides and ANSI Standards for those principal contractors, retained by NSP, such as NSSS contractors and A/E Firms, which exceptions have been approved by the NRC.

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I Operational Quality Assurance Plan l l .- Rev: 2 2.0 Introduction

! Northern States Power Company (NSP) is involved in the construction and operation of nuclear and fossil fueled power plants. Construction of nuclear plants is conducted under a Quality Assurance Program on a project

] basis. NSP's nuclear plant operational activities are conducted under the Operational Quality Assurance Program.

The Construction Quality Assurance Program is structured to govern nuclear plant design, fabrication, construction, testing and associated procure-ment as required by the applicable NRC Construction Permit and pertinent regulations. The Operational Quality Assurance Program is formulated on a Company wide basis, to govern nuclear plant operational activities and associated support activities as required by NRC Operating License

provisions and associated regulations. The Operational Quality Assurance

Program is implemented, to the extent compatible with construction res-

, ponsibilities, at least 90 days prior to initial fuel loading and is I

fully implemented at the time of commercial-operation of the plant.

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i Operational Quality Assurence Plan

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3.0 organization l 3.1 General Requirements-NSP shall be responsible for the establishment and execution of the

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Operational Quality Assurance Program. . NSP may delegate to other -

organisations the work of establishing and executing the Operational Quality Assurance Program, or any part thereof, but shall retain responsibility therefore.

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! The authority and duties of persons and organizations performing

!. quality assurance functions shall be clearly established and delin-

] eated in writing. Such persons and organizations shall have sufficient j authority and organizational freedom to. identify quality problems;

, to initiate, recommend, cr provide solutions; and to verify imple- ,

mentation of solutions.

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Assurance of quality requires management measures which provide that l the individual or group assigned the responsibility for checking, l auditing, inspecting, or otherwise verifying that an activity has been 4 correctly performed is independent of the individual.or group directly.

! responsible for performing the specific activity.-

3.2 Quality Assurance Organization Summary Quality Assurance activities pertaining to operating nuclear plants l- involve the following three organizations:

l 1. The Operational Quality Assurance Section of the Power Produc-

! tion-Department.

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! 2. The Quality Section of each Nuclear. Plant Operating Organization.

! 3. The Quality Assurance Section of the Plant Engineering and Construction Department, t ~

L The O' p erational Quality Assurance Section of Power Production is

' responsible for overall administration of the Operational Quality

, Assurance Program. 'This responcibility is implemented by performance of the following activities:

1. Controlling revisions to the Operational Quality Assurance Plan.

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2. Reviewing all General Office Administrative Control Directives.

3. Reviewing all General Office Administrative Work Instruction.-

l 4. Reviewing all safety related purchase requisitions issued by=

General Office personnel except those issued by the Plant

- Engineering and Construction Department.

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4 Operations 1 Quality Assurance Plan.

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4 l S. Performing periodic audits Waich verify bmplementation of

! . General Of fice Administrative Control Directive requirements.

4 6 Preparing General Office Quality Assurance Status Reports and

submitting such reports to appropriate levels of management.

i 7. Controlling General Office

! a. Administrative Control Directives.

i i b. Administrative Work Instructions, i

c. Management Memorandums associated with temporary changes to

!. Administrative Control Directives.

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8. Periodically reviewing General Office audit reports and non-

conformance reports to determine trends that could be detrimental i to quality.

9. Reviewing nuclear fuel suppliers' quality assurance programs.

l 10. Performing inspections of nuclear fuel suppliers' facilities to j verify implementation of their quality assurance program.

i 11. Assisting other General Office organizations 0mplement l Operational Quality Assurance Program requirements.

l The Quality Section of each Nuclear Plant Operating Organization is a responsible for the administration and control of the plant portion i of the Operational Quality Assurance Program. This. responsibility is i implemented by performance -of the following activities:

1. Reviewing all Plant Administrative Control Directives.

l 2. Reviewing all Plant Administrative Work Instructions.

l. 3. Reviewing all purchase requisitions issued by Plant Personnel.

l 4. Performing perisdic audits which verify implementation of Plant L

[ Administrative Control Directive requirements.

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• 5. Preparing Plant Quality Assurance Status . Reports and submitting such reports _ to appropriate levels of management including the j ,

General Superintendent Operational Quality Assurance.

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6. Quality review of Work Request Authorizations for safety related work.

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7. Periodically reviewing plant audit reports and non-conformance reports to determine trends that could be detrimental to quality.

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Operational Qun11ty Assurance Plan Rev: 2

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8. Assisting other plant sections Unplement Operational Quality Assurance Program requirements.

The Quality Assurance Group of the Plant Engineering and Construction .

Department is responsible for reviewing supplier's quality assurance programs and for performing supplier's facility inspections to verify bnplanentation of his quality assurance program except those associated with procurement of nuclear fuel. This group is also assigned the responsibility for reviewing procurement documents for work delegated to the Plant Engineering and Construction Department.

All of the above responsibilities and the associated requirements are explicitly defined in Administrative Control Directives issued by the appropriate level of management.

3.3 Quality Control Organization summary Quality Control activities pertaining to operating nuclear plants involve the following three organizations:

1. The Power Plant Maintenance Section of the Power Production Dept.

2. The Nuclear Plant Organization.

3. The Nuclear Plant Projects Section of the Plant Engineering &

Construction Dept.

The Quality Control Engineer of the Power Plant Maintenance Section of the Power Production Dept has principle responsibility for quality control activity with respect to operating nuclear plants. This responsibility includes:

1. Developing, preparing, and distributing Special Process procedures and qualification of such procedures if appropriate.

2. Qualifying personnel on Special Processes and maintaining records of such qualification.

3. Qualifying Special Process Inspectors and maintaining records of such qualification.

4. Developing and documenting In-service Inspection programs and implementing such programs except those portions associated with functional testing of pumps and valves and hydrostatic testing.

5. Providing councel to the nuclear plant staf fs relative to quality control activities.

The Nuclear Plant Organization is responsible for the quality control aspects of activities assigned to the plant organizations which include maintenance activities and modifications that are assigned to the plant organiza tions . Quality control consist of inspection associated with

, Special Processes, Nondistructive Examination, and In-service Inspe-tion pertaining to functional testing of pumps and valves and hydrostatie testing. The Supt Plant Engineering & Radiation Protection is assigned Quality control responsibility for activities assigned to the Plant

, Organization.

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Operational Quality Ascurance Plan Rev: 2 The Nuclear Plant Projects Section of the Plant Engineering & Construc-tion Dept is responsible for the quality control activities associated with assigned plant modification projects. Generally the Plant Engineering & Construction Dept implements this responsibility by identifying quality control requirements and incorporating appropriate provisions in engineering and construction contracts. The projects assigned to the Plant Engineering & Construction Dept generally involve major modifications.

3.4 Executive Vice President The Executive Vice President has been assigned the responsibility for the engineering, construction, and operation of all physical facilities. These responsibilitics are impicmented in part by acting through the Vice President Plant Engineering & Construction, the Vice President Transmission & Operations Services and the Vice President Power Production & System Operation. The Vice President Power Production & System Operation has responsibility for nuclear plant operation. In addition, the Executive Vice President has been designated by Presidential Directive as being responsibic for establishing an Operational Quality Assurance Program.

3.5 Vice President Plant Engineering & Construction The Vice President Plant Engineering & Construction is responsible for the design and construction of major generating plant facilities.

He is also responsible for major modifications to operating nucicar plants.

The Vice President Plant Engineering 6, Construction is also respon-sibic for performing required quality inspections of vendors.

3 These recponsibilities are implemented by acting through the Manager Nuclear Plant Projects via the General Manager Plant. Engineering &

Construction and through the Manager Quality Assurance.

3.5.1 General Manager Plant Engineering & Construction The General Manager Plant Engineering & Construction reports to the Vice President Plant Engineering & Construction and is responsibic for the design, fabrication, erection, construction, testing and inspection of new generating facilities. He is

, also responsible for implementing major modifications to operating nuclear plants assigned to the Plant Engineering &

Construction Department. These responsibilities, with respect to nuclear plants, are implemented by acting through the Manager Nuclear Plant Projects.

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i Operational Quality Assurance Plan Rev: 2 3.5.2 Manager Quality Assuranc,e j i

The Manager Quality Assurance reports to the Vice President -j Plant Engineering and Construction and is responsible for l bnplementation of the Construction Quality Assurance Program, i He is also responsible for the following quality-activities pertaining to the Operational Quality Assurance Program. 1 I

1. Establishing and maintaining an approved suppliers list. j

2. Reviewing supplier's quality assurance program, except those associated with procurement of nuclear fuel.

3. Performing periodic inspections of supplier's facilities to verify bnplementation of their quality asst;rance program, except those associtated with procurement with nuclear fuel.

4. Reviewing Plant Engineering and contruction safety related

purchase requisitions and/or specification to verify ,

inclusion of appropriate quality provisions.

3. 6 Vice President Transmission and Operations Services The Vice President Transmission and Operations Services reports to the Executive Vice President and is responsible for the design and con-struction of the Company's electrical transmission system and sub-stations. He is also responsible for providing certain testing,

, maintenance, security, purchasing and drafting services to other Company Departments.

u These responsibilities are bmpleuented in part by acting through the 1

General Manager Maintenance and Testing, The Manager Substation.

! Engineering and Construction und the Director Operating Services.

! 3. 6.1 Director Operating Services

! The Director Operating Services reports-to the Vice President

- Transmission and Operations Services and has Corporate responsibility for the following services:

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1. Procurement of material and services es specified by responsible organization.

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2. Corporate security.

. These responsibilities are implemented by acting through the Manager Purchasing and Traffic and the Manager Security.

. 3. 6. 2 General Manager Maintenance and Testing

, The General Manager Maintenance and Testing reports to the Vice l President Transmission and Operations Services and is l 10 of 74 i

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Operational Quality Assurance Plcnd Rev: 2 responsible .or providing the following services to other Company Departments:

1. Electrical device maintet.ance and testing.

2. Breaker maintenance and testing.

3. Chemical analysis.

4. Mechanical testing.

5. Metallurgical testing and examination.

6. Air filter testing.

3.6.3 Gensral Manager Substation Engineering & Construction i

The General Manager Substation Engineering & Construction reports to the Vice President Transmission & Operations Services and is responsible for the, engineering, design and construction of the Company's substation facilities. He is also responsible for providing required draf ting services to other Company Departments.

3. 7 Vice President Power Production & System Operation The Vice President Power Production & System Operation reports to the Evecutive Vice President and has Corporate responsibility for the operation and physical control of the Company's generating f acilities and for the operation of the Company's Electrical System. These areas of responsibility include the following:

1. Operation and maintenance of generating facilities and plant substations.

2. Electrical System operation. -

3. Minor modifications to generating facilities.

4. Generating f acility fuel procurement, utilization and disposition.

5. Independent review and audit of nuclear plant operations and operating license administration.

These responsibilities are implemented in part by acting through the Manager System Operation, the Manager Fuel Procurement, the Manager Nuclear Support Services and the General Manager Power Production.

3.8 Manager Svstem Operation The Manager System Operation reports to the Vice President Power Production & System Operation and is responsible for operation of the Company's Electrical System including the plant substations.

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3.9 Manager Fuel Procurement The Manager Fuel Procurement reports to the Vice President Power Production and System Operation and is responsible for procurement and disposition of fuel for the Company's generating facilities.

These areas of responsibility include the following:

1. Procuring nuclear and fossil fuels.

2. Delivery of nuclear and fossil fuels to generating facility sites.

Disposition of depleted nuclear fuel.

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3.10 ManaRer Nuclear Support Services

! The Manager Nuclear Support Services reports to the Vice President i Power Production and System Operation and is responsible for technical support, independent review and audit of nuclear plant operation, and

• I administration of NRC Operating Licenses including the associated Technical Specifications.

3.11 General Manager Power Production The General Manager Power Production reports to the Vice President Power Production and System Operation and is responsible for operation, maintenance, minor modification, testing, and overall management of all generating plants. These responsibilities include the following specific items:

1. Developing and maintaining a plant and General Office organization capable of safely, efficiently, and reliably operating, maintaining, modifying and testing generating facilities.

2. Provide overall direction and control of the department's activities.

3. Determine and allocate the resources of manpower and material for department functions.

4. Provide necessary interfacing with other NSP activities.

These responsibilities are hnplemented in part by acting through the General Superintendent Production Plant Projects, the General Superintendent Power Plant Maintenance, the General Superintendent Electric Plant, the General Superintendent Nuclear Plant Operation and the General Superintendent Operational Quality Assurance.

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1 Operational Qunlity Assur nce Plcn ,

Rev: 2 3.12 General Superintendent Power Plant Maintenance The General Superintendent Power Plant Maintenance reports to the General Manager Power Production and is responsible for the overall supervision of mechanical maintenance activities, planning, and scheduling of major maintenance, and for providing departmental operating and maintenance training services.

3.12.1 Quality Control Engineer The Quality Control Engineer reports to the General Super-intendent Power Plant Maintenance and is responsible for activities associated with Special Processes and In-service Inspection. These responsibilities include:

1. Deve'oping, preparing, and distributing Special Process procedures.

2. Qualifying personnel on Special Processes and for main-taining Qualification Records.

3. Qualifying Special Process Inspectors and maintaining records of such qualification.

4. Developing and documenting In-service Inspection programs and implementing such programs except those portions associated with functional testing of pumps and valves and hydrostatic testing.

f Qualification requirements for this position include:

1. An engineering degree or equivalent technical education.

2 Three years of special process experience.

3.13 General Superintendent Production Plant Projects The General Superintendent Production Plant liojects reports to the General Manager Power Production and is responsible for coordinating activities between the Power Division and the Plant Engineering 6

- Construction Department on new plant design, major plant modifica-tion projects, t

3.14 General Superintendent Electric Plant The General Superintendent Electric Plant reports to the General Manager Power Production and is responsible for the electrical aspects of fossil and nuclear fueled plant operation and maintenance and maintenance of plant substations.

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3.15 General Superintendent Operational Quality-Assurance )

The General Superintendent Operational Quality Assurance is responsible for establishing and maintaining an Operational Quality l Assurance Program relative to General Office activities associated ,

. with operating nuclear plants and for providing overall control of

this program. In implementing this responsibility he has direct access to the Executive Vice President, Vice President Power l Production and System Operation, and General Manager Power Production regarding matters associated with the Corporate Power Production and System Operation, and the Power Production Department Levels of the

! Operational Quality Assurance Program respectively. llis specific responsibilities include the following for each of the above levels

of the program.

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1. Review all General' Office Administrative Control Directives and changes thereto to verify conformance with the objectives of J

the program,e.g.section 1.0 of this plan. ,

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2. Review all General Office Administrative Work Instructions to l verify that they are consistent with the requirements of pertinent Administrative Control Directives.

3. Perfom audits to verify conformance with Administrative Control Directive requirements.

4. Report findings associated with above audits to appropriate

management,

5. Perfom audit follow up.

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! 6. Review audit reports and non-confomance reports to determine

! if trends detrimental to quality exist.

l 7. ' Maintain records associated with Administrative Control Directive revision, Administrative Work Instruction revision, l and audits.

1 The General Superintendent Operational Quality Assurance is - also

! responsible for controlling the Operational Quality Assurance Plan

' including changes thereto and for reviewing safety related pro-j curement documents initiated by Power Production and System Operations 4 personnel and Power Productiron Department personnel to verify that l appropriate quality assurancu provisions are included, lie is also responsible for Quality Assurance activities associated with procurement of nuclear fuel.

4 The General Superintendent Operational Quality Assurance has the authority to stop work in progress that is in nonconfomance with specified quality requirements and to maintain the stop work status l until the adverse conditions have been corrected.

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Operational Qunlity Assurance Plan Rev: 2 3.16 General Superintendent Nuclear Plant Operation The General Superintendent Nuclear Plant Operation reports to the General Manager Power Production and is responsible for the safe and reliable operation of the nuclear fueled gencrating facilities.

These responsibilities are implemented in part by acting through the Nuclear Plant Managers.

3.17 Nuclear Plant Managers The Plant Managers of the Nucicar Plants report to the General Super-intendent Nuclear Plant Operation aid are responsible for ,the safe and reliabic operation of their respective plant and for assuring that the activities of the planc staff comply with applicable regulatory requirements. These responsibilities are Unplemented in part by acting through the Superintendent Plant Engineering & Radiation Protection and the Superintendent Operation & Maintenance.

3.18 Superintendent Plant Engineering & Radiation Protection The Superintendent Plant Engineering & Radiation Protection reports to the Plant Manager and is responsible for 'the technical direction of the plant operations and for Quality Control activities associated vith tasks assigned to the plant organization. He directs and coordinates the activities of the Radiation Protection Engineer (Supervisor), the Plant Engineer Technical, and the Plant Engineer Operations; and super-vises the Quality Engineer.

3.18.1 Quality Engineer The Quality Engineer reports to the Superintendent Plant Engineering and Radiation Protection and is responsible for the administration, coordination, and audit of the plant level of the Operational Quality Assurance Program. The Quality Engineer has the authority to stop work in progress that is in nonconformance with specified quality require-ments and to maintain the stop work status until the adverse conditions have been corrected. He has direct access to the Plant Manager, General Superintendent Nuclear Plant Operation General Manager Power Production, and the General Superintendent Operational Quality Assurance.

3.19 Superintendent Operations and Maintenance The Superintendant Operations and Maintenance reports to the Plant Manager and is responsible for direction of plant operation and maintenance. He is responsible for operation, maintenance, safety of all plant equipment, and the safety and actions of all personnel involved in plant operations.

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Operational Quality Assurance Plan

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3.20 Re fe rences 1 Specific responsibilities are presented in each functional Admin-

! istrative control Directive. The following Administrative Control i Directives are devoted to organizational considerations:

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1. 1ACD 3.1 Organization (Corporate)

2. 2ACD 3.1 Organization (Power Production & System Operation)

3. 3ACD 3.1 Organization (Power Production Department)

4. 4ACD 3.1 Monticello Plant Organization t

1 j 5. SACD 3.1 Prairie Island Plant Organization 1

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i Opsrction:1 Qaality Assur nco Plen Rev: 2 Figure 3-1 1

Operational Organization PRESIDENT CHIEF OPERATING OFFICEF.

EXECUTIVE ._ _____._._ _ _ _ ,_ _ _ _ _ _ _ _

VICE PRESIDENT i c-- 1 I

VICE PRESIDENT l VICE PRESIDENT  ;

PLANT ENGR 6 CONST  ; TRANS & OP SERVICES l

I I I l l MANAGER GEN MANAGER j DIRECTOR i GEN MANAGER SUBSTATION I QUALITY ASSUSANCE PLANT ENGR & CONST ENGR 6 CONST I

'OPSERVICESl I

I GEN MANAGER l MAINTENANCE & TESTING j l

VICE PRESIDENT I POWER PRODUCTION ____.___,___________,1

& 1 SYSTEM OPERATION l l I 1 I MANAGER MANAGER I MANAGER SYSTEM OPERATION FUEL PROCUREMENT NSS I I

I GENERAL MANAGER  ;

POWER PRODUCTION I

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I I GEN SUPT GEN SUPT l GEN SUPT GEN' SUPT PWR PLANT MAINT PROD PLANT PROJECTS l ELECTRIC PLANTS OP QUALITY ASSURANCE i

t_ _ _ _

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_ QUALITY CONTROL ENGINEER GENERnL SUPERINTENDENT NUCLEAR PLANT OPERATION

._I_____________I l i

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F - - - - -- - - - - - -f PLANT MANAGER f I

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SUPERINTENDENT SUPERINTENDENT l PE & RP

O&M i i

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J, _ _ __ QUALITY ENGINEER _ __ _ __ ___ _ _ _ _ _ _ _, _ _ _ _ _ _ _ _ a il of 74

f Operational Quality Assurance PIAN

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4.0 Operational Quality Assurance Program 4.1 General Requirements

.An Operational Quality As2urance Program shall be established at the earliest practicable time, consistent with the schedule for accomplishing the activities which comply with the requirements of this plan, i

The prograr ;aall be:

l a. Documented by written policies, proceduren, or instructions,

b. Carried out throughout plant operating life in accordance with those policies, procedures, or instructions.

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The Program shall include identification of:

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

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

The Program shall provide control over activities affecting the quality of the identified structures, systems, and components to the

extent consistent with their importance with safety.

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Activities affecting quality shall be accomplished under suitable controlled conditions. Controlled conditions include the use of

' appropriate equipment; suitable environmental conditions for accoup-lishing the activity, such as adequate cleanliness; and' assurance that 1

all prerequisites for the given activity have been satisfied.

The Program shall take-into. account the need for special centrols, processes, test equipment, tools, and skills to attain the r quired j

quality, and the need- for verification of quality by inspection and test. The Program shall provide for-indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintained. The adequacy and status of the Program shall be regularly reviewed.

Management of other organizations participating in the Program shall regularly review the status and adequacy of tnat part of the Program 1

which they are executing.

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, Operational Quality Assurcnce Plan 2

Rev: 2 1 4.2 General Description The Operational Quality Assurance Program has been established o govern the operational activities and the activities necessere -

i support operation of the Company's nuclear plants operated u . an

! NRC Operating License. The Operational- Quality Assurance Pr.;.am is thus an overall integrated company - wide program which governs all safety related activities as they pertain to operating nuclear plants.

. The program has been initiated by the President of the Company issuing a single directive to the Executive Vice President establishing him

, as being responsible for formulating and implementing an Operational Quality Assurance Program and identifying the program objectives.

The Operational Quality Assurance Program shall utilize the following j documents to meet the program objectives:

1. Operational Quality Assurance Plan (Plan)

2. Administrative Control Directives (Directives).

3. Administrative Work Instruct _ons (Instructions).

. 4. Required Procedures (Procedures).

The Plan shall be considered an overall document which governs the implementing documents, i.e. Directives, Instructions, and Procedures.

I For ease of administration, the implementing documents shall be

issued at the following four (4) levels.

l 1. Corporate; Issuing Authority, Executive Vice President, t

2. Power Production and System Operation; Issuing Authority, Vice

, President Power Production and System Operation.  ;

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3. Power Production Department; Issuing Authority, General Manager Power Production.

4. Plants (Prairie Island and Monticello); Issuing Authority, Plant j Manager.

3 Figures 4-1 and 4-2 diagram the above program subdivisions.

It should be noted that each level of the program is controlled by the preceding level; i.e., the Corporate Level establishes the minimum requirements associated with the Power Production and System Operation Level which in turn establishes the minimum requirements i

associated with the Power Production Department Lesel which in turn establishes the minimum requirements associated with the Plant Level. ]

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_Oparational Qutlity Assurance Plan Rev

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4.3 operational Quality Assurance Plan

! The Operational Quality Assurance Plan shall be an overall document which describes in general terms how compliance with the quality

requirements presented in 10CFR50 Appendix B_is accomplished with respect to company nuclear plants regulated by an NRC Operating i License.

i The Operational Quality Assurance Plan shall be issued under the

, authority of the Executive Vice President and shall be reviewed

! periodically.

l The Operational Quality Assurance Plan shall be controlled to j assure current copies are made available to each Issuing Authority of 4

the various levels of the program, to those personnel responsible for administration of the program, and to those _ individuals or organizations responsible for reviewing the program.

All such-changes shall be approved by the Executive Vice President i or equivalent management position.

i 4.4 Administrative Control Directives Administrative Control Directives (Directives) shall be documents which establish responsibility and requirements governing activities 1 associated with plant operation. _ Directives shall be first tier j

Laplementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with the Operational Quality Assurance Program objectives.

Administrative Control Directives shall be issued at each: level of

! the program as necessary. It is mandatory that the Directives at the

Corporate Level assure compliance with all applicable requirements of l 10CFR50 Appendix B. The Directives issued at any of the lower levels i

i of the program are not expected to satisfy all 10CFR50 Appendix B requirements but shall implement responsibilities assigned by the higher level Directives.

4.5 Administrative Work Instructions

- Administrative Work IJ nstructions (Instructions)-- shall be documents

, which_ provide guidelines or instructions for the bmplementation of

- the requirements of Administrative Control Directives. _ Instructions

shall be- second tier haplementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with pertinent Directive requirements and assigned responsibilities.

4 Administrative Work-Instructions may be issued at each level of the j -program by responsible individuals.

be utilized - for department interfacing.

Instructions shall generally j

[ '

All Administrative Work Instructions shall be controlled and reviewed periodically, p 20 of 74.

4 4

Operational Quclity Assurance Plan i

Rev: 2 4.6 Procedures j

Procedures shall be documents which provide specific instructions for performing an activity. Procedures shall be third tier documents j utilized to perform safety-related activities as required by the applicable NRC Operating License Technical Specifications.

In addition, 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 4 required by the applicable Technical Specifications. Required pro-

]* cedures shall be controlled and reviewed periodically.

4.7 Program Administration i

i Administration of the General Office levels of the Operational Quality Assurance Program shall be performed by the Quality Assurance _

Section of the Power Production Department. Administration of the i Plant level of the program shall be performed by the Plant Quality Engineer.

7 Disputes between Quality Assurance personnel and other organizations i relative to program requirements shall be referred to the Issuing

Authority (as identified in section 4.2 of this Plan) responsible for establishing the pertinent requirement.

Program administration shall include the following activities:

1. Quality review of Directives, i

2. Quality review of Instructions.

l- 3. Control of Directives and Instructions.

, 4. Procurement review.

! 5. Performance of required audits.

6. Reporting to management concerning:

a. Program status.

b. Program deficiencies including quality trends.

4.8 Program Boundarv

- The structure, systems, components, and other-items; requiring quality assurance are listed in-Tables 4-1 and 4-2.

l 4.9 Quality Assurance Training Training programs'shall be established for those personnel performing j _ quality-af fecting activities such that they are knowledgeable in the 21 of 74 t-

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

- - . - - - - . ~ _ . - . =~.- - . . . - _ -.-.- .. . - .-. -..

N Operational Quality Assurance Plan 2

Rev: 2 i

i quality assurance Directives and their requirements and proficient 1

in implementing these requirements. These training programs shall assere that:

1

1. Personnel responsible for performing quality-sffecting activities

are instructed as to the purpose, scope, and implementation of the quality-related Directives, Instructions, and procedures.

9

2. Personnel performing quality-affecting activities are trained

. and q6alified, as appropriate, in principles and' techniques

of the activity being performed.

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

, 4. Proficiency of personnel performing quality-affecting activitia.s

) is maintained by retraining, 're-examination, and/or recertification -

j as appropriate.

4 l- 5. Methods are provided for documenting training sessions describing i content, attendance, date of attendance, and the results of the

, training session, as appropriate.

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[ 22 of 74 B

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1 Operational Quality Assurance Plan l Rev: 2

~

IABLE 4 List of Monticello Structures. Systems, and Components Subject to Appendix B to 10CFR Part 50 i

j 1. STRUCTURES

- Reactor Building j Control Room Building Of f Gas Stack

~

j intake Structure (Service Water pwmp. area) i Diesel Generatof Rooms 1 Diesel Fuel Oil Day Tank Rooms l 2. MECHANICAL SYSTEMS AND COMPONENTS g

i COMPONENTS

Reactor Coolant System

.i j Reactor Vessel j Reactor Vessel Support Skirt Reactor Vessel Stabilizer

]- Recirculation System Piping i Recirculation System Pumps and Valves

} Main Steam Piping (to and including outermost containment isolation valve) l Main steam Safety Relief Valves

Main Eteam Safety Relief Valve Discharge Piping l Feedwater Piping (to and including outermost

i containment isolation valve)

{ Control Rod Drive Housing Supports j Reactor Vessel Internals I- -Fuel Assemblier t Core Support Structure j Jet Pumps .

Control Rods Liquid Poison Pipe Core Spray Sparger

'~

1 Control Rod Drive Svatem -

i

). Control Rod Drives-Control Rod Drives Accumulators

, Scram Discharge Volume

- Scram Piping 23 of 74 4

. _ . , . -~. , . . . , _ . , . . . . , , , _ . - .:,,...,,,,... . , . . . . . _ . , , , , . . _ _ . . , . _ . _ , _m.___ . . _ _ _ , . . . _ _ , _ . . _ . . .-. .

1 Opzrction:1 Quality Ascurcnce Plcn j Rev: 2  ;

2. (Cont.) 1 COMPONENTS Standby Liquid Control System SLC Tank SLC Pumps SLC Explosive Valves SLC Piping Primary Containment Drywell

Torus Drywell Vent Piping / Vacuum Breakers Torus Ring Header and Downcomers Containment Penetrations containment Piping and Valves (to and including outermos t isolation valve)

Secondary Containment RB Ventilation Isolation Dampers Standby Gas Treatment Filters and Fans Residual Heat Removal System a

RHR Piping, Pumps and Valves RRR Heat Exchangers (shell side) i Core Spray System Core Spray Piping, Pumps, and Valves Inside Containment High Pressure Coolant Injection System HPCI Steam Piping and Valves Inside Containment (to and including outermost isolation valve) i HPCI Steam Supply and Exhaust Piping and Valves (outside containment)

HPCI Pump-Turbine HPCI Injection Piping and Valves HPCI Suction Piping Reactor Core Isolation Cooling System RCIC Steam Piping and Valves Inside Containment (to and including outermost isolation valve)

RCIC Steam Supply and Exhaust Piping and Valves (outside containment) 24 of 74

- Operational Quality Assurance Plen Rev: 2 1 .

, RCIC Pump-Turbine l- _RCIC Injection Piping and Valves j RCIC Suction Piping i

l Service Water System

?

Emergency Service Water Pumps

! Dmergency Service Water Piping and Valves

! RHR Service Water Pumps RHR Heat Exchanger. (tube side) l RHR Service Water Piping & Valves Reactor Water Cleanup System l

i

}

RWCU Piping and Valves Inside Containment (to and including outermost isolation valve) -

t l Spent Fuel Storage Systems i

i Spent Fuci Pool f .

$ Diesel Generator Support System l Air Start System from Receivers- to Air Start

' Solenoids

Fuel Oil System from Day Tank to Injectors

$ Diesel Coolers and Associated Piping and Valves i

(Water side)

! SECTION 2 NOTES:

I j 1. Mechanical components included within each mechanical system include hangers, fittings, flanges, vessels, tanks, etc.- as necessary to

! perform the system safety function.

i 3. ELECTRICAL SYSTEMS AND C0t4PONENTS 1-COMPONENTS 3-

$ 4160 Volt Bus 16 ,

l Breaker 152-602

} RHR Service Water Pump B EHR Service Water Pump D RHR Pump B RHR Pump D 4 Core Spray Pump B

, 480 Volt Load Center 104 -

1'

j. 25 of 74 3-

_ _..___..a - . . . , ~ , _ . . ~ . , . ~ . _ _ . - . _ . . _ , . _ - - . . _ _._,,_ ._. . ~ . . , . . . . . . _ _ . ,

. Opsrationni Quality Assurcnce Plcn Rev: 2 4160 Volt Bus 15 Breaker 152-502 NBR Service Water Pump A RHR Service Water Pump C

, RHR Pump A KBR Pump C Core SprSy Pump A 480 Volt Load Center 103 480 Volt Switchgear Load Center 104 480 V MCC 142* (Essential) 480 V MCC 143A*

480 V MCC 143B*

480 Volt Switchgear L'ad o Center 103 4

480 V MCC 133A* .

480 V MCC 133B*

Diesel Generator No.11*

Diesel Generator No. 12*

250 V DC Distribution Panel D31*

125 V DC Distribution Panel D-11*

125 V DC Distribution Panel D-21*

120/240 volt AC Ins trumentation Dis tribution Panel

• SECTION 3 NOT"S:

1. For those electrical systems or components designated with ar asterisk (*) above, Quality Assurance electrical program:

requirements are applicable only to those portions of systems

, as defined in Section 2 as necessary to perform the system saf ety function.

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

3. Certain components are excluded frem the QA program requirements if they meet the criteria described in Section 5.

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Operational Quality Assurance Plan 1:ev: 2

4. INSTRUMENTATION SYSTEMS AND COMPONENTS Reactor Protection System Primary Containment Isolation System liigh 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 Cas Treatment Systei; Initiation SJAE Off Cas Radiation Monitor SECTION 4 NOTES:

1. For those instrumentation systems designated above, Quality Assurance instrumentation program requirements are applicabic only to those portions of systems defined in Section 2 as necessary to perform the t.ystem safety function.

2. Instrumentation components included within each instrumentation system include power supply, sensors, relays, viring and final operating device (solenoid, relay, etc.) as necessary to perform the system safety function.

3. Certain components are excluded from the QA program requirements if they meet the criteria described in Section 5.

5. ELECTRICAL AND INSTR 1 MENTATION SYSTEM COMPONENT EXCLUSION CRITERIA

1. Any component of an electrf a1 system Section 3 or instrumentation system Section 4 is excluded from the QA Program requirements if it meets the following critersa:

e

a. A failure of the compnnent by 4 /actrical shorting, open circuiting, grounding r mechanical failure would not render the system incapable of performing its intended safety function.

b. A failure of the fluid pressure bose' ey of the component would not render the system incapai 31 performing its intended safety function.

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 miscellaneaous hardware.

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Op3raticnal QuS11ty Assurcnce Plcn Revt 2

IABLE 4-7 LIST OF PRAIRIE ISIR O STRlfCTURES. SYSTEMS Afm CmPONENTS St1UECT 10 APPENDIX B TO 10 CFR PART 50 1

1. RFACTOR SYSTIM Atm TUEL A. Reactor Vessel and Coolant System Reactor vessel Reactor vessel support Reactor vessel internals Full length control rod drive mechanism housing Part length control rod drive mechanism housing Steam generator (tube side & 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 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 thimble plug (rod control clusters)

Primary and secondary sources Electric modules with safety function Cabic with safety function B. Fuel Assemblics Fuel assemblics, sub-assemblies, components and materials, including fuel material 28 of 74

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Operational Quality Assurance Plan l Revt 2 l l

2. REACTIVITY CONTROL SYSTEMS Drive mechanisms including:

Control rod cluster drive shaft assembly, including latch assembly Reactor trip breakers Control rods and rod cluster assemblies Control rod guide tube Control red drive housing ,

Electri: modules with safety function Cable s ;th safety function

3. CHEMICAL A?fD V0ttME CONTROL SYSTD1 Regeneta.ive heat exchanger Letdown heat exchanger Reactor coolant filter Volume control tank Positive displacement charging pump and motor Seal water filter Letdown orifices and letdown valves '

Excess letdown heat exchanger Seal water heat exchanger Boric acid tanks Boric acid transfer pump Boric acid filter Reactor Coolant pump seal and bypass orifice Piping, inboard of isolation valves Electric modules with safety function Cabic with safety function Heat tracing 4 INCORE INSTRtHENTATION Thimble guidL tubes Seal table

$. BORON RECYCLE SYSTD1 l

Recycle holdup tanks, piping and valves associated with gaseous radio-active vaste j 6. EMERGENCY CORE COOLING SYSTEM

Accumulators High head safety-injection pumps L Piping, inboard of isolation valves

, Motors, electric modules, with safety function Cable with safety function j

29 of 74

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_. _..-.___ __ . ~ - _ _ . . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ .- . _

+ r I

a Operational Quality Assurance Plan ,

Rev: 2 i

)  !

?,

7. CONTAIfS!ENT SPPAY SYSTD1 I

k Refueling vater storage tank i Spray additive tank ,

i Spray pumps Spray rings and norzles l Piping and valves i Pamp motors

! Elcetric modules with safety function

. Cable with safety function i

j 8. RESIDUAL HEAT RDiOVAL SYSTEM Pumps and motors  ;

I Heat exchanger .

[ Piping and valves with safety function  !

Elcetric modules with safety function -

I Cable with safety function -

9. SPE!:T TUEL POOL COOLING SYSTEM 1

l Piping and valves whose failure could result in significant release  ;

i of pool water i  !

l 10. CONTAItetENT FAN COOLFR SYSTD1 4

l Ductwork Fans ,

j Dampers l Fan coolers l' Electric modules with safety function 3 Cabic with safety function 1

j 11. WASTE PFOCESSINa SYSTD! 7 i

{

Caseous and liquid waste ,

Piping and' valves forming part of containment boundary  !

Systems handling gaseous radioactive materials Electric modules with safety function

Cabic with safety function-1 l 12 SAMPLT'0 SYSTEMS 4

Valves and piping from the reactor coolant system up to the_second i isolation valves outside containment Yalves and piping to'the first isolation valve from other tafety i

related systems

$ 13. E Ex-1 GENERATOR ELowrtN Pipine f rom s teen generator to containment-isolation valves-l 30 of 74 e

i

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Operational Quality Assurance Plan Rev: 2

)

i

14. REACTOR PROTECTION SYSTEM E1cetrical modules

Cabic i

15. PROCESS RADIATION MONITORS 1 Radiation Monitors, including electric modules and cable with a safety

! function, associated with the Shield Building, Auxiliary Ruilding,

. Spent Fuel Fool and Control Room Ventilation Systems

16. CONTAINMENT HYDROGEN CONTROL SYSTDi I Piping and valves with safety function d Electric modules and cable l

17. REACTOR VESSEL SERVICE EQUIPMENT ,

) Containment polar crane '

! Vessel head handling equipment l Crane structural supports Crane electrical, cable, controls and instrumentation with safety furstion 4

18. REFUELING EQUIPMENT 2

Spent fuci cask Auxiliary Building crane f Auxiliary Building Crane structural supports

. Crane electrical, cable controls and instrumentation with safety function Fuel transfer tube 4

19. FUEL STORAGE New fuel racks

Spent fuel racks Spent fuci pool structure and enclosure

20. CONTROL ROOM PANELS Electric modules, with safety function Cable with safety function

21. LOCAL PANELS AND RACKS Electric modules with safety function Cable with safety function 31 of 74

• . - - - ..--.,,-__,-.-.-_w-.__w.--__.--- , ., , ye . _ - , _ y. m..m. .y~ , . . .... -.-..,., , ,, , .,y, y

operational Quality Assurance Plan Rev: 2

22. MAIN STEAM SYSTD1 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 flew 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 Peedwater piping and valves inside containment structure up to and including first isolation valve outsido containment structure-Elcetric modules with safety function Cabic with safety function .

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

Piping and valves supplying auxiliary feedwater 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 turbine building and non-essential equipment) lleat exchangers, with safety function Pumps Pump motors Surge tank l

Valves, isolation Valves, other, with safety function Electric modu-les with safety function l

Cabic with safety function Cooling water systems (essential)

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

Diesel engine pumps Strainers, with safety function valves, isolstion Valves, other, with safety function-Screen vash . systems, with safety function Traveling screens, with safety function Elcetric modules with safety function l

Cabic with safety function

!- Diesel engine pump auxiliaries as follows:

Diesel oil storage tanks

- Day tanks 32 of 74

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

4 i

j Operational Quality Assurance Plan Rev: 2

25. (CONT. )

Fuel oil transfer pumps and motors Fuel oil piping and valves with a safety function Starting air compressors Air receivers i 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 Diesel engine, lubricating oil and jacket cooling systems 4

26. DJSTRLMENT AIR SYSTD4

! Piping and valves associated with containment penetration 27 DIESEL CENERATOR Diesel oil storage 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

, Cabic with safety function f 28. DIESEL GENERATOR AIR STARTING SYSTEM 3

Compressor Air receivers Piping and valves from receiver to dicac1 generator Piping betscen compressor and receiver

29. ELECTRICAL CIASS 1E SYSTDiS Switchgear, transformers, motor control centers, load centers, batteries and chargers, and associated equipment with safety function.

NOTE: Point of interface with onsite electric power systems, i.e.,

at point of interface with Class 1E breakers which isolate main Class 1E onsite buses from the offsite power system; and including components and circuitry interfaces that affect the proper performance of such interiacing breaker.

, 4.160 - 480 V switchgear for engineered safety systems (EST), including ESF buses i

33 of 74

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Operational Quality Assurance plan Revt 2

29. (CONT.)

4,160 - 480 V transformers (ESF load centers) 480 - 120/209 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) 125 V de panels and switchgear (vital de power distribution) 120 V ac instrument bus panels (vital instrumentation ac power distribution)

Containment penetration assembiles Main control board Radiation monitor panci Hot shutdown panel Control room air conditioning control panel Post LOCA Hydrogen control panel Emergency lighting Emergency communications Diesel generator and accessories Diesel generator control panels Relay boards and racks Wire and cabic raceway system Underground electrical duct bank system Cable system (power, control and instrumentation)

Instrument racks Electrical supports lient tracing /frecre protection

30. INSTR 1 MENTATION AND CONTROL SYSTEM COMPONENTS Reactor trip system Engineered safety features (ESF)_ actuation system Systems required for safe shutdown Safety related instruments, tubing and fittings-

31. HEATING. VENTIIATION AND AIR CONDITIONING SYSTEMS (HVAC)

Control and Relay Room HVAC System Air handling units Fans, ductwork and dampers Filters Chillers and chilled water pumps Auxiliary Building-Special Ventilation System Fans, ductwork and dampers Filters Screenhouse Ventilation System Fans and dampers associated with diesel engine Ventilation 4

i 34 of 74

Operations 1 Quelity Assurcnce Plan Rev 2

31. (Cont.)

Shield Building Ventilation System Tans, ductwork and dampers Tilters Battery Room fpecial Ventilation System Fans, ductwork and dampers Spent Fuel Pool Special Ventilation System Exhaust fans, ductwork, dampers Exhaust'illters Diesel Generator Rooms Cooling System rans, ductwork and dampers Auxiliary Building 11ormal Ventilation System Ductwork and dampers associated with steam exclusion Turbine Building Ventilation System Ductwork and dampers associated with steam exclusion Electric modules with, safety function Cable with safety function ll/AC sensors and monitors having _ safety function

32. CIVIL STRUCTURES AND FOUNDATIO"S Containment and stru:tures Containment airlock Containment isolation (valves, piping, canisters)

Containment penetrations Shield building Auxiliary building Control room Diesel generator room Radwaste building Cooling water intake structure Elect-tcal tunnels, with safety function Pipe t .nels, with safety function Shielding structures Turbine Building (housing emergency diesel generator, cooling water pipes, batteries, safeguards switchgear, auxiliary feedwater pumps)

33. OTHER

1. Fire protection system piping associated with the safeguards ventilation exhaust-filters and containment penetration

2. Turbine building crane Crane structural support crane electrical, cabic, controls and instrumentation with safety function ;

35 of 74

• Op3rctional Qu:lity Assurcnco Plan Rev: 2 Figure 4-1 Operational Quality Assurance Program Subdivision COPJ0 RATE EXECUTIVE VICE PRESIDENT

• P%'ER PRODUCTIO!4 6

SYSTD1 OPERATION VICE PRESIDENT Pb'R PROD 6 SYS OP*

POL'ER PRODUCTION DEPARTMDiT CEN MANAGER PN'ER PRODUCTION *

"oNT! CELLO PLANT PRAIRIE ISLAND P'. ANT PIANT MANAGER

• TIANT MANAGER

• NOTES:

• Is suing Authority - see Section 4.2 X oi 74

e Oporctionci Quality Asturcnce Picn Rev: 2 Pigure 4 2

- Operational Organization - QA Program Level PRESIDDIT CHIEF OPERATING OFFICER

, ............................................... 4..................................................

Corporate Level EMTWE VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT PLANT ENGR & CONST TRANS 6 OP SERVICES I I I m GEN MANAGER DIRECTOR 3EN MANAGER SUBSTATION MANAGER PLANT ENGR & CONST OP SERVICES ENGR 6 CONST QUALITY ASSURANCE 4

GEN MANAGER MAINTENANCE 6 TESTING

................................................. ................................................ 4 Power Production & System VICE PRESIDENT seration Level POWER PRODUCTION 6

SYSTD4 OPEPATION

~"

I l l MANAGER MANAGER MANAGER-SYSTEM OPERATION FUEL PROCUREMENT NSS Power Production Department GENERAL MANAGER Level POWER PRODl'CTION GEN SLTT GEN SUPT GD4 SUPT GEN SUPT PWR PLANT MAINT PROD PLANT PROJECTS E'ECTRIC PIANTS OP QUALITY ASSURANCE QUALITY CONTROL GENERAL SUPERINTD1 DENT

_ _, 7 ENGINEER NUCLEAR PLANT OPERATION I

...........................t.....................q.................................................

I PLANT MANAGER Plant Level l I -

1 I i SUPERINTENDENT SUPERINTDiDENT PE 6 RP O6M F

= QUALITY ENGINEER i . . .

37 of 74

k Operational Quality Assurance Plan Rev: 2 i

j 5.0 Desien Control i

5.1 General Requirements i

Design changes, including field changes, shall be subject to design I control measures commensurate with those applied to the original

design and be approved by the organization that performed the original design unless the applicant designates another responsible organization.

5.2 Design' Change Control I

j A uniform system for controlling design changes to nucicar plants shall be provided in the Operational Quality Assurance Program, i Provisions of this system shall include the following provisions:

1. Assurance that the change is reviewed and approved as required by the Technical Specifications and 10CFR 50.59.

2. Plant Docuuentation is revised as appropriate and new documentation

! generated where needed.

3. Appropriate Safety Evaluations are performed.

I

4. Appropriate analyses are performed it.rluding those required by 10CPR 50 Appendix B.

S. Appropriate installation procedures are prepared and utilized.

6. Technical Specification changes are prepared, reviewed and approved if required.

7. Tests and in on are performed as necessary.

8. Plant procedures are reviewed and revised as appropriate.

9. Appropriate hold points are established.

Provisions shall be made for assigning responsibility for individual Design Changes to the Plant Engineering and Construction Department, l the Power Production Department, or the Plant Organization; assignment of such responsibility shall be explicitly identified and documented prior to design, procurement, or construction activities

, associated with that Design Change.

The guidance contained in the pertinent ANSI 45.2 series of Standards listed in section 1.0 shall be utilized for Design Changes that are comparabic in nature and extent to related activities occurring during initial plant design and construction.

38 of 74

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Operational Quality Assurance Plan Rev: 2 1

5.3 References The following Operational Quality Assurance Program documents are utilized for controlling design changes.

A. General Office Directives l

1. LACD 3.3 Design Change Control i 2. 3ACD 4.1 Design Change control

.i

3. 3ACD 4.2 Design Change Installation Procedure -

] 4. 3ACD 4.3 Design Change Preoperational/ Operational Testing

5. 3ACD 3.7 Work Authorization l B. Monticello Directives

1. 4ACD 3.6 Work Request Authorization C. Prairie Island Directive

1. SACD 3.2. Work Request and Work Request Authorization 1

J I

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l 4

i l .

I l

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. Operational Quality Assurance Plan Rev: 2 .

6.0 Procurement Document Control 6.1 General Requirements 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 the documents for procurement of material, equipment, and services, whether purchased by NSP or by its contractors or subcontractore. To the extent necessary, procurement documents shall require contractors or subcontractors to provide a quality assurance program consistent with the pertinent provisions of 10CFR50 Appendix B.

6.2 Technical & Quality Requirements The Operational Quality Assurance Program shall contain provisions for controlling procurement of material, equipment, components, and services that are safety related and utilized at an operating nuclear plant.

Procurement documents shall contain specific technical and quality requirements. Renewal, spare, and replacement parts shall be required to meet the original specification or Construction Code, Quality Assurance documentation requirements, and vendor quality assurance program requirements.

Quality Assurance requirements shall include identification of appliable elements of 10CTR50 Appendix B that are required to be included in the vendor's Quality Assurance program, including j identification of applicable documentation requirements such as l

chemical analysis reports, material certification, testing results, testing reports and time and frequency of submittals.

! Procurement documents shall contain provisions which establish l

the right of access to vendor facilities and records for source inspection and audits as appropriate.

l 6.3 Review and Approval i

l Documents, and changes thereto initiating procurement of safety l

related material, equipment, components or services shall bc l approved by appropriate responsible management personnel and shall be subject to a quality assurance review to insure applicable regulatory requirements, design bases, quality assurance, and other requirements are adequately satisfied prior to release.

[ 6.4 References l

The following Operational Quality Assurance Program documents are utilized to control procurement:

40 of 74 l

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Operational Quality Assurance Plan

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Revt 2 i-A. General Office Directives e

1. 1ACD 5.1 Procurement Control

! 2. 1ACD 5.2 Technical 6 Quality Requirements 9

3. 2ACD 3.3 Procurement Control i 4. 2ACD 5.1 Nuclear Fuel Quality Assurance 1

] 5. 3ACD 6.1 Procurement Control j B. Monticello Directives

1. 4ACD 8.1 Procurement Process

2. 4ACD 8.2 Procurement Requirements l

f C. Prairie Island Directive i

4 1. SACD 7.1 Procurement Process E

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Op; rational Quality Assurance Plan Revt 2 7.0 Instructions, Procedures & Drawings 7.1 General Lequirements Directives. Instructions, procedures and drawings of a type appropriate to the circumstances shall be provided for the contro) and performance of activities which affect the quality of safety related structures, systems or components.

Directives. Instructions, procedures and drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisf actorily accomplished.

7.2 Directives 6 Instructions Directives and/or 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.

7.3 Procedures Procedures of a type appropriate to the circumstances shall be provided for the performance of activities which affect the quality of safety related structures, systems or components.

The following procedures shall be provided:

1. Operating Procedures

2. Surveillance Test Procedures

3. Major Maintenance Procedures

4. Plant Chemistry & Count Room Procedures

5. Radiation Protection Procr~ures

6. Emergency Plan Procedures 42 of 74

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7. Special Process Procedures j 8. Prcoperational & Operational Test Procedures  !

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9. Audit Procedures  ;

! 10. Document Control Procedures l 4

1 l 7.4 Drawings & Instruction Manuals  !

i i I Drawings and instruction manuals of a type appropriate to the l circumstances may be utilized as procedural documents for conducting activities which affect the quality of safety related structures,

, systems or components.  ;

1

7.5 References i The following Operational Quality Assurance documents establish  ;

procedure requirements,

! 1. 11AD 3.2 Plant Operation

, 2. 2ACD 3.2. Plant Operation l j

i 3. 3ACD 3.2 Plant Operation 4 3ACD 3.3 Plant Maintenance l S. 3ACD 4.1 Design Change Control '

i l 6. 3ACD 4.2 Design Change Installation Procedure i

7. 3ACD 4.3 Design Change Preoperational & Operational Testing I

8. 3ACD 5.1 Drawing Control

! 9. 3ACD 5.3 Drawing Revision  !

i l 10. 3ACD 7.1 Welding Procedure-Control

11. 3ACD 7.4 NDE Procedures j 12. 3ACD 9.2 Surveillance Test Procedures

13. 3ACD 10.1 Chemical Analysis Procedures i 14 3ACD 10.2 Count Room Procedures 1

I i 43 of 74 i

Operational Quality Assurance Plan Rev: 2 i

8.0 Document control 8.1 General Requirements

i 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.

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

1. Reviewed for adequacy and approved for release by authorized personnel and;

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

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

Y 8.2 Directive Control Directives issued to implement the Operational Quality Assurance

'rogram 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 by the issuing authority.

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

8.3 Instruction Control Instructions issued to implement provisions of Directives shall be controlled to assure that current copies and appropriate indexes are made available to personnel performing the prescribed activities.

Instructions rhall be reviewed by quality assurance personnel to assure that they are compatible with pertinent Directive orovisions and shall be approved by the issuing authority.

Changes to Instructions shall be reviewed in the same manner as the original.

8.4 Procedure Cont rol Required procedures shall be controlled to assure that current copies are made available to personnel performing the prescribed activities. j Required procedures shall be reviewed by a knowledgeabic individual and shall be approved by a management member of the srganization responsible for the prescribed activity. Required procedures shall also be reviewed and approved as required by the Technical 44 of 74

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Operational Quality Assurance Plan 1

Rev 2 i Specifications. Appropriate indexes of standing procedures shall

' be formulated and made available to personnel responsible for i performing the prescribed activities.

Significant changes to required procedures shall be reviewed and approved in the same manner as the original and shall comply with 1

applicabic provisions of the Technical Specifications.

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i 8.5 Drawing Control I

i Drawings which represent the physical and functional aspects of the d

Operating Nuclear Plants and which are critical to safe plant operation ]

or safety of personnel shall be maintained in a current status.

Appropriate indexes shall be formulated and made available j to personnel responsible for plant operation, maintenance,  !

and modification.

Measures shall be established for revising plant drawings and for distributing revised drawings. Proposed revisions to drawings shall be reviewed by a knowledgeable individual to determine the safety significance _and appropriateness of the change.

8.6 Specifications Plant design specifications shall be controlled to assure that current copies and appropriate indexes are made available to personnel responsible for plant operation, maintenance, and modification.

t 6.7 References The fol' *ing Operational Quality Assurance Program documents are utilized to control documents:

1 A. General Office Directives i

1. 1ACD 1.1 Administrative Control Directives

2. 1ACD 1.2 Adminis' > ative Work Instructions

3. IACD 4.1 Document Control 4

4. 1ACD 4.2 Plant Turnover

5. 2ACD 1.1 Administrative Control ' 'rectives

6. 2ACD 1.2 Administrative Work Instructions

7. 3ACD 1.1 Administrative Control Directives

8. 3ACD 1.2 Administrative Work Instructions

9. -3ACD 3.9 Procedure Review and Approval 45 of 74

1 Operational Quality Assurance Plan i Rev 2 1

10. 3ACD 5.1 Drawing Control

11. 3ACD 5.2 Specification Control I i

?2. 3ACD 5.3 Drawing Revision 4

13, 1ACD 5.4 Specification Revision )

B. Monticello Directiven

1. 4ACD 1.1 Administrative Control Directives i 2. 4ACD 1.2 Administrative Work Instructione i 3. 4ACD 3.10 Document Control l 1 i

4. 4ACD 3.11 Procedure Review and Approval f f C. Prairie Island Directivea

1. SACD 1.1 Administrative Control Directives

2. SACD 1.2 Special Orders

3. SACD 1.4 Plant Operations Manual

4. SACD 4.2 Blank Forms

5. 5ACD 4.3 Drawing Revisions i

6. SACD 4.4 Drawing Control J

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1 Operational Quality Assurance Plan Revt 2 9.0 Control of Purchased Material. Equipment and Services 9.1 General Requirements I

Measures shall be established to assure that purchased material, equipment and services conform to the procurement documents. These u.easures shall include provisions, as appropriate, for vendor evaluation and selection, objective evidence of quality furnished by the vendor, inspection at the vendor source, and examination of products upon delivery.

Documentary evidence that material and equipment conform to the procurement requirements shall be available at the plant site prior 1 to installation or use of such material and equipment. This I documentary evidence shall be retained at the plant site and shall be sufficient to indicate that the purchased material and equipment meet the specific requirements of the codes, standards, or specifications.

The effectiveness of the control of quality by vendors shall be assessed at intervals consistent with the importance, complexity and quanity of the product or service.

9.2 Quality peview Documents initiating procurement of safety related material, equipment and services shall be subject to a quality review to ensure applicable regulatory requirements, design bases, quality assurance,and other requirements are adequately satisfied.

Quality Assurance requirements shall include identification of applicable elements of 10CFR50 Appendix B that are required to be included in the vendor's Quality Assurance program.

9.3 Vendor Inspection 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. Verification shall include inspection of the vendor's facility for adherence to their Quality

' Assurance Program to the extent appropriate for the procured material, equipment or service.

Vendor inspections shall be planned and performed in accordance with written procedures based upon procur.-ment document requirements.

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

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, operational Quality Assurance Plan Rev 2 3

1 9.4 Receipt Inspection l

) Material and equipment shall be inspected upon receipt at the plant j site and prior to use to determine that procurement requirements

, are satisfied. This inspection shall include verification that I required documentation is complete.

Non-conforming material and equipment shall be controlled to assure i such material or equipment is not utilized to fulfill a safety '

i related function prior to an acceptable resolution of the deficiencies.

4 9.5 References i The following Operational Quality-Assurance Program documents are j utilized to control purchased material, equipment and servicest A. General office Directives j 1. lACD 5.1 Procurement Control

! 2. lACD 5.2 Technical 6 Quality Requirements i

j 3. lAci . 3 Vendor inspection i

f 4. lACD 5.4 Material Storage

.I

5. 2ACD 4.1 Procurement Control i

{ 6. 2ACD 5.1 Nuclear Fuel Quality Assurance Program l 7. 3ACD 6.1 Procurement Control

, 8. 3ACD 6.2 Material Storage & Shipment l

h B. Monticello Directives

] ,

! 1. 4ACD 8.1 Procurement Process

2. 4ACD 8.2 Procurement Requirements

3. 4ACD 9.1 Receiving Process

. C. Prairie Island Directives i

l 1. SACD 7.1 Procurement Process

, 2. SACD 8.1 Receiving Process 48 of 74 l . ,

l l

l Operational Quality Assura..cc Plan Rev 2 10.0 Identification and Control of Materials, Parts and Com-onents 10.1 General Requirements Measures shall be established for the identification and control of materials, parts and components, including partially fabricated assemblies. These measures shall assure that identification of the item is maintained by heat number, part number, serial number or other appropriate means, either on the item or on records trace-able to the item, as required throughout fabrication, erection, installation and use of the item.

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 Spare parts held for future use on safety related components shall be controlled in such a manner that assures they will perform their safety function when utilized. These spare parts shall be identified with the associated procurement documentation.

Measures shall be taken which assures these items are in an appropriate condition for use or vill be placed in such a condition prior to use.

10.3 Material Control Material held in stori eo for use on safety re' lated systems, structures or equipment shall be controlled in such 'a manner as to prevent its degradation and to assure the rejection of incorrect or defective material. This material shall be identified by heat number or 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.

10.4 Receipt inspection Material, parts and components that are to be utilized to fulfill a safety related function shall be inspected upon receipt to assure that associated procurement document provisions have been satisfied.

Measures shall be established for identifying non-conforming 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.

49 of 74 j

- Operational Quality Assurence Plan Rev: 2 10.6 References The following operational Quality Assurance Program documents are utilized in identification and control of materials, parts and components:

A. General Office Directives

1. LACD 5.4 Material Storage

2. LACD 5.1 Procurement Control

3. 2ACD 3.3 Procurement Control

4. 2ACD 5.1 Nucicar Fuci Quality Assurance

5. 3ACD 6.2 Material Storage & Shipment

6. 3ACD 7.3 Weld Material Control B. Monticello Directives

1. 4ACD 9.1 Receiving Process

2. 4ACD 9.2 Inventory control C. Prairie Island Directives

1. SACD 8.1 Receiving Process

2. SACD 8.2 Inventory Control 1

50 of 74

Operational Quality Assurance Plan

, Rev: 2 11.0 control of Special Processes 11.1 General Requirements Measures 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 Welding Procedures

• Safety related welding shall be performed in accordance with'

+

qualified welding procedures. Safety related welding procedures shall be qualified in accordance with applicable codes and-standards and shall be reviewed and approved in accordance with applicable provisions of the associated-Technical Specifications.

Measures shall be established for controlling welding procedures that assure such_ procedures are qualified, reviewed and approved, as required, prior to use.

11.3 Weider Qualification Measures shall be established that assure safety related welding is performed by qualified personnel. Welders shall be qualified, and requalified, in accordance with applicabic codes and standards.

Measures shall be established for controlling welder qualification and-requalification that assure qualified personnel are utilized to perform safety related welding.

11.4 Heat Treating Procedures Heat treating shall be performed in accordance with procedures formulated-and approved in accordance with applicable codes-and standards.

11.5 NDE Procedures Safety related non-destructive examinations (NDE) shall be performed in accordance with procedures formulated in accordance with appli-

-cable codes and standards and.shall.be reviewed and approved in-accordance with applicable provisions of the associated Technical Specifications.

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

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Operational Quality Assurance Plan Rev: 2 '

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

Measures shall be established for controlling NDE personnel qualifi-cation and requalification that assure qualified personnel are utilized to perform safety related non-destructive examinations.

11.7 References The following Operational Quality Assurance Program documents are utilized to control the special processes.

A. General Office Directives

1. 1ACD 3.2 Plant operation

2. 1ACD 7.3 Material Testing Services

3. 2ACD 3.2 Plant Operation

4. 3ACD 3.3 Plant Maintenance

5. 3ACD 4.2 Design Change Installation Procedure

6. 3ACD 7.1 Welding Procedure Control

7. 3ACD 7.2 Welder Qualification

8. 3ACD 7.4 Non-destructive Examination i B. Monticello Directives

.1. 4ACD 5.2 Mechanical & Electrical Equipment Maintenance Procedur(

2. 4ACD 12.1 Plant Welding Practices

3. 4ACD 12.3 Non-destructive Examination Procedures

4. 4ACD 12.4 Plant Heat Treating Practices C. Prairie Island Directives

1. SACD 9.1 Qualification of Welders 52 of 74

. Operational Quality Assurance plan Rev: 2 12.0 Inspection 12.1 General Requirements Measures shall be established for inspection of activities affecting quality to verify conformance with the documented inst uctions, procedures and drawings for accomplishing the activity. Such inspections shall be performed by individuals other than those who performed the activity being inspected.

Examinations, measurements or tests of material or products shall be performed for each work operation where necessary to assure quality.

If inspection of processed material or products is impossible or disadvantageous, indirect control by monitoring processing methods, equipment and personnel shall be provided.

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

If mandatory inspection hold points, which require witnessing or inspection and beyond which work shall not proceed without prior consent.are required, the specific hold points shall be indicated in appropriate documents.

12.2 Plant Operatfor.

Measures shall be established that assure periodic inspection of safety related systems, components, and structures. Such inspections shall assure that these systems, components and structures can fulfill their safety function.

The following reactor operation hold points shall be established:

1. Refueling Inspection; 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.

2. Reactor Startup; a review shall'be performed to assure that safety related systems, components and structures have been placed in the required status.

3. Reactor Re-Start; the cause of reactor trips initiated by the reactor protection system shall be investigated and satisfactorily resolved prior to restart of the reactor.

53 of 74

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. Operational Quality Assurance Plan i Rev: 2

. 12.3 Inservice Inspection

l l Measures shall be established that assure inservice inspections are performed in accordance with applicable provisions of the ASME Boiler and Pressure Vessel Code,Section XI and applicable Technical Specifications.

12.4 Plant Modification & Maintenance Measures shall be established that assure nodification and maintenance l

are reviewed by qualified personnel knowledgeable in quality l assurance to determine the need for (a) inspection, (b) identification

of inspection personnel, and (c) documenting inspection. results.

j Hold points shall be established as appropriate.

i l 1 12.5 Vendor Inspections j Measures shall be established which assure that inspections and process monitoring requirements are specified in appropriate 1 procurement documents for safety related material, components and i equipment when required. Hold points shall be established which assure that required inspections and process monitoring are performed.

l 12.6 inspection Procedures & Personnel Required inspections shall be performed in accordance with appropriate instructions, procedures, and checklists. Such

, instructions, procedures,and checklists shall assure that the j

characteristics and activities that are to be inspected are I

identified, individuals or organizations responsible for inspections are identified, acceptance criteria are provided, the method of inspection is identified, evidence of completion of inspections, and recording of the results of the inspection as appropriate.

l 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.

12.7 References j The following Operational Quality Assurance Program documents are utilized to control inspection activities:

. A. General Office Directives

1. 1ACD 3.2 Plant Operation

2. 1ACD 3.3 Design Change Control

3. lACD 5.1 Procurement Control

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Operational Quality Assurance Plan Rev: 2

4. lACD 5.2 Technical & Quality Requirements

5. 1ACD 5.3 Vendor Inspection 6, 2ACD 3.2 Plant Operation

7. 2ACD 5.1 Nuclear Fuel Quality Assurance

8. 3ACD 3.2 Plant Operation

9. 3ACD 3.3 Plant Mainte uce

10. 3ACD 4.1 Design Change Control B. Monticello Directive <

l. 4ACD 4.2 Integrated Operating Procedures

2. 4ACD 5.1 Mechanical 6 Electrical Equipment Preventive Maintenance Program

3. 4ACD 6.1 Instrumentation & Controls Preventive Maintenance Program 4 4ACD 8.1 Procurement Process

5. 4ACD 8.2 Procurement Requirements

6. 'Ji?P 14.2 Refueling Outage Procedures C. Prairie Island Directives

1. SACD 1.4 Plant Operations Manual

2. SACD 7.1 Procurement Process -

4 55 of 74

Operational-Quality Assurance Plan Rev:'2 d

13.0 Test Cuntrol 13.1 General Requirements i'

Measures shall be established to assure that all testing required j to demonstrate that structures, systern and components will perform satisfactorily in service is identified and performed in a-cordance with written test procedures which incorporate the requiretaats 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.

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 a under suitable environmental conditions. Test results shall be

] documented and evaluated to assure that test requirements have been satisfied.

13.2 Surveillance Tests A surveillance test program shall be established to assure that testing required to demonstrate that safety related structures, systems,and components will perform satisfactorily in service.

Surveillance tests shall be identified and performed in accordance l with written test procedures which incorporate the requirements l and acceptance limits contained in applicable documents. The j surveillance test program shall include, as a minimum, those

surveillance tests specified in applicable Technical Specifications except those included in a seperate Inservice inspection Program.

~

2 Surveillance test results shall be documented and evaluated to assure that test requirements have been satisfied or deficient items satisfactorily resolved.

i 13.3 Preoperational & Operational Tests Measures shall be established to assure that appropriate preoperational and operational tests are performed on safety related structures, systems and components that have been subject to modification or significant maintenance. Such tests shall be i

performed in accordance with the original design and testing requirements or acceptable alternatives. Test results shall be documented and evaluated to assure that test requirements have been satisfied or deficient items satisfactorily resolved.

13.4 Proof Tests i

j Measures shall be establis'aed to assure that appropriate proof tests are specified ir procurement documents for safety related replacement material and equipment and that such tests are i

performed and documented prior to installation.

l 56 of 74 1

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, Operational Quality Assurance Plan Rev: 2 13.5 Special Tests Measures shall be established that assure safety related tests are reviewed and approved as required by 10CFR50.59 and applicable Technical Specifications. Such tests shall be performed in accordance with appropriate procedures. Test resulte shall be documented and evaluated to assure test requirements have been satisfied.

13.6 References The following Operational Quality Assurance Program documents are utilized to control safety related tests:

A. General Office Directives

1. 1ACD 3.3 Design Change Control

2. 1ACD 5.1 Procurement Control

3. 1ACD 3.2 Plant Operation

4. 2ACD 3.2 Plant Operation

5. 3ACD 4.1 Design Change Control

6. 1ACD 4.3 Design Change Preoperational/ Operational Testing

7. 3ACD 6.1 Procurement Cont rol

8. 3ACD 9.1 Surveillance Test Program

9. 3ACD 9.2 Surveillance Test Procedures B. Monticello Directives

1. 4ACD 8.1 Procurement Process

2. 4ACD 8.2 Procurement Requirements

3. 4ACD 13.1 Surveillance Program

4. 4ACD 13.2 Surveillance Procedures C. Prairie Island Directives

1. SACD 7.1 Procurement Process

2. SACD 1.4 Plant Operations Manual 57 of 74

l g Operational Quality Assurance Plan Rev: 2 14.0 Control of Measuring & Test Equipment 14.1 General Requirements Measures shall be established to assure that tools, gages, instruments and other measuring and testing devices used in activities af fecting quality are properly controlled, calibrated and adjusted at specified periods to maintain accuracy within necessary limits.

14.2 Installed Plant Instrumentation

, Measures shall be established to assure that installed safety related plant instrumentation is maintained and periodically ca'11brated to maintain accuracy within necessary limits. Maintenance and calibration of safety related instrumentation shall be perforned in accordance with appropriate procedures and shall be controlled and documented.

14. 3 Measuring & Test Instrumentation Measures shall be established to assure that tools (micrometer, calfpers, etc.), gages, instruments and other inspection, measuring,

, test equipment and devices used to verify conformance to established requirements are maintained and periodically calibrated to maintain accuracy within necessary limits. Calibration of such measuring and test equipment shall be controlled and shall be traceabic to the National Bureau of Standards or'where national standards are not available, the basis of calibration shall be documented.

14.4 References The following Operational Quality Assurance Program documents are utilized to control safety related measuring and test equipment:

A. Corporate Directives

1. 1ACD 3.2 Plant Operation

2. 1ACD 7. 5 Instrumentation Calibration Program B. Power Production & System Operation Directives

1. 2ACD 3.2 Plant Operation C. Power Production Department Directives

1. 3ACD 3.3 Plant Maintenance '

2. 3ACD 9.3 Instrument Calibration Program 58 of 74

Operational Quality Assurance Plan

,j Rev: 2 D. Monticello Directives

1. 4ACD 6.4 Control of Measuring & Test Equipment

2. 4ACD 6.1 Instrumentation & Controls Preventive Maintenance Frogram F

59 of 74

1 Opera,tional Quality Assurance Plan Rev: 2 15.0 Handling. Storage and Shipping 15.1 General Requirements Measures shall be established to control the handling, storage, shipping, cleaning and preservation of safety related material and equipment in accordance with work and inspection instructions to

, prevent damage or deterioration.

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 Facilities Storage facilities shall be provided at each operating nucicar plant for storage of safety related operating and maintenance supplies, spare parts, replacement parts, replacement equipment, materials and tools. These storage facilities shall assure physical protection and protection from environnental 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 Storage Areas shall be provided for storage of nuclear fuel which assure physical protection, suberitical arrangement, adequate cooling,

adequate radiation shielding and containment of radioactive material as appropriate for the condition of the stored fuel.

15.4 Radioactive Material Storage Areas shall be provided for storage of radioactive material which assure physical protection, as low as reasonably achievable radiation exposure to personnel, control of the stored material, and containment of ' radioactive material as appropriate.

15.5 Storace control 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 items shall be controlled to assure that the item will perform its safety fuaction when utilized.

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Operational Quality Assurance Plan i Rev: 2 15.6 Material Handling Safety related material, supplies, equipment and parts shall be handled in accordance with procurement documentation and in accordance I with appropriate material handling practices. Material handling equipment shall be subject to periodic testing and preventive maintenance which assures its operability. Appropriate operating instructions and procedures shall be provided for handling equipment.

15.7 Shipping & Packing 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.

15.8 References i

The following Operational Quality Assurance Program documents are utilized to control handling, storage and shipping:

A. General Office Directives

1. LACD 5.4 Material Storage

2. 3ACD 6.2 Material Storage & Shipment

3. 1ACD 7.3 Weld Material Control

4. 3ACD 11.2 Fuel Handling & Inspection

5. 3ACD 12.1 Radioactive Material Control B. Monticello Directives

1. 4ACD 9.5 Handling, Storage, Shipping and Preservation of Material C. Prairie Island Directives

1. SACD 8.1 Receiving Process

2. SACD 8.2 Inventory Control

3. SACD 8.3 Weld Material Control i

4. SACD 8.4 Control of Nonconforming Items 61 of 74

Operational Quality Assurance Plan y Rev: 2 16.0 Inspection. Test & Operating Status 16.1 General Requirements 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 tests performed upon individual items of the nuclear plant. These measures shall provide for the identification of items which have satisfactorily passed required l

inspections and tests, where necessary to preclude inadvertent bypassing of such inspections and tests.

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

16.2 Maintenance control 4

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

1. Affected structures, systems and components are removed from service and secured in a manner consistent with operability and isolation requirements of the Technical Specifications.

2. Repair and modification activities are performed in a manner consistent with its bmportance to safety.

3. 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.

In addition, measures shall be established to control maintenance activities that assure resulting radiation exposure to personnel is maintained as low as is reasonable achievable and consistent with pertinent NRC regulations.

, The above measures shall be Unplemented by utilizing appropriate work authorization processes, work procedures, safety tagging, bypass control, key control and area posting, as appropriate, for the involved activity.

16.3 Test Control Measures shall be established for the control of tests to safety related structures, systems and components that assures that:

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Operational Quality Assurance Plan Rev: 2 l

• l L 1. Proposed tests are reviewed and approved as required prior

to performance.

, 2. The plant is placed in an acceptable status prior to the test, maintained in an acceptable status during the test, and returned to its nornal status upon completion of the j, test.

4 i

3. Test results are reviewed and approved as appropriate.

1 j The above measures shall be implemented by utilizing appropriate work authorization processes, test procedures, safety tagging, j bypass control, and key control, as appropriate, for the in-volved test.

I

16.4 Safety Tanning i

i A safety tagging program _ shall. be developed and utilized for con-l trol of nuclear plant equipment.. This program shall contain pro-

! visions for uniquely identifying components whose operation is re-i stricted or prohibited based upon safety considerations. Pro-

} visions shall be made for review, application, removal, and

documentation of such tagging, i

i 16.5 Key control

Measures shall be established for controlling keys for safety related switches and for keys or key devices important to plant security. These measures shall include restricted distribution and periodic inventory of such keys or key devices.

16.6 Bypass Control j

" Measures shall be established for controlling the application of devices utilized : tc bypass component functions that are important l r.o safety.- Such measures shall assure that:

l 1. Proposed-bypasses to safety related items are reviewed to

. determine that the plant will be placed in an. acceptable l status when the bypass is applied.

2. Removal of bypasses from safety related items are reviewed prior to removal.

3. Application:of bypasses to safety related items is authorized-by responsible personnel.-

1 The application of safety related bypasses shall be considered a temporary-measure and shall be reviewed periodically.

l_ -All required activities associated with the application, review, approval and removal shall be documented. '

63 of 74 1,

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i l

, Operational Quality Assurance Plan Rev: 2 l 16.7 References '

I The following Operational Quality Assurance Program documents are '

utilized to directly control inspections, tests, and operating status:

A. General Office Directives 4

1, 3ACD 3.6 Equipment Control

2. 3ACD 3.7 Work Authorization B. Monticello Directives

1. 4ACD 3.6 Work Request Authorization

2. 4ACD 4.5 Equipment Control Procedures

, 3. 4ACD 4.8 Bypass Control

, 4. 4ACD 3.5 Plant Key Control C. Prairie Island Directives

1. 5ACD 3.2 Work Request and Work Request Authorization

2. 5ACD 3.9 Bypass control

3. 5ACD 3.10 Equipment Control Procedures t

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Operational Quality Assurance Plan Rev: 2 17.0 Nonconforming Materials, Parts or Components 17.1 General Requirements Measures shall be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation. These measures shall include, as appropriate, procedures for identification, documentation, segregation, disposition and notification to affected organizations.

Nonconformance items shall be reviewed and accepted, rejected, repaired,or reworked in accordance with documented procedures.

17.2 Receipt Inspection 4

Measures shall be established which assure that safety related material, supplies, equipment,and components are inspected to determine that they conform to specified requirements of pertinent procurement documents upon receipt at the plant site.

Provisions shall be mad'e for identifying nonconforming items

cnd for segregation of nonconforming items. The absence of required documentation or deficient documentation shall constitute non-conformance.

Nonconforming items shall not be used to fulfill a safety related function until the deficiency is satisfactorily resolved.

17.3 Maintenance Inspection Equipment, components or parts found nonconforming in a manner that could significantly affect its ability to fulfill its safety function shall be identified as a nonconforming item and shall be segregated.

Nonconforming items shall not be used until the deficiency is satisfactorily resolved.

17.4 Disposition of Nonconforming Items Measures shall be established which assure that nonconforming itens are disposed of in a manner which prohibits their inadvertent use or installation. Provisions shall be made for reviewing the nonconformance and correcting deficiencies by repair or rework if appropriate.

The acceptability of such rework or repair of materials, parts, components, systems, and structures shall be verified by l reinspection and retesting the item as originally inspected and tested or by a method which is equivalent to the original inspection and testing method. Inspaction, testing, rework, and repair pro-l cedures shall be documented.

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!. -Normally, nonconforming safety items shall not be installed prior-to i satisfactory resolution of. outstanding deficiencies. In exceptional

. cases nonconforming items may be installed provided specific action.

I is taken, which assures the. item is not utilized to fulfill a i

safety function, prior to installation of-the item.

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$ 17.5 Nonconformance Documentation a

j. Nonconformances reports shall be' initiated 'for- significant deviations from specified requirements. Such reports'shall identify e the nonconforming item; describe the nonconformance, the j disposition of the nonconformance, and the inspection requirements ,

j- Nonconformances shall-be reviewed and approved by appropriate quality j assurance personnel.

I Nonconformance shall be periodically analyzed to_show quality-trends and the results of this_ review shall.be. reported to the appropriate '

level of management for review and assessment.

f 17.6 References

The following Operational Quality Assurance Program documents are

utilized to control nonconforming materials, parts or components

a A. General Office Directives 4

I' j 1. 1ACD 5.4 Materia 1' Storage

[ 2. 3ACD 6.2 Material Storage'& Shipment l B. Monticello Directives l 1. 4ACD 9.1 Receiving Process l 2. 4ACD 9.3 Control of Nonconforming Items C. Prairie Island Directives f 1. SACD 8.1 Receiving Process i 2. 5ACD 8.4 Control of Nonconforming: Items-I i' .

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Operational Quality Assurance Plan Rev: 2 18.0 Corrective Action 18.1 General Requirements Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the

' condition is determined and corrective action taken to preclude repetition.

The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management, s 18.2 Operating Occurrences & Events

' Measures shall be established which assure that operating occurrences and events that could have a significant safety effect are investigated, reviewed,and reported as required by the Technical Specifications. Such measures shall assure that appropriate corrective action is taken and that the event or occurrence is reported to responsible levels of management. Corrective action includes provisions which preclude recurrence.

, 18.3 Administrative Control Deficiencies i

Measures shall be established which assure that significant deficiencies identified during audits of Administrative Control Directives are reported to those responsible for the activity and to appropriate 1evels of management. These measures shall include corrective action designed to preclude repetition of the deficiencies identified and verification of implementation.

18.4 References The following Operational Quality Assurance Program documents are 4

i utilized to control corrective action:

A. General Office Directives

1. 1ACD 2.2 Audits

2. 1ACD 2.3 Quality Assurance Status Report

3. IACD 3.2 Plant Operation

4. 2ACD 2.2 Audits

5. 2ACD 2.3 Quality Assurance Status Report

6. 2ACD 3.2 Plant Operation 67 of 74

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7. 2ACD 7.1 Plant Operation Review & Audit i

8. 3ACD 2.2 Audits I l

9. 3ACD 2.3 Quality Assurance Status Report

10. 3ACD 3.10 Operating Occurrences & Events B. Monticello Directives I

1. 4ACD 2.2 Reporting of Quality Assurance Status

2. 4ACD 3.9 Operating Occurrences and Events j l

i 3. 4ACD 3.12 Control of Nonconforming Activities l C. Prairie Island Directives

1. SACD 2.2 Internal Audits

2. SACD 2.3 Reporting of Quality Assurance Status

3. SACD 3.6 Operating Occurrences & Events i

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Oparational Quality Assurance Plan j Rev: 2 19.0 Quality Assurance Records 19.1 General Requirement _s Sufficient records shall be maintained to furnish evidence of activities affecting quality. These records shall include at least the following; Operating logs and the results of reviews, inspections, tests, audits, monitoring of work performance and material analysis.

The records shall also include closely related data such as qualifications of personnel, procedures,and equipment.

Inspection and test records shall, as a minimum, identify the

. inspector or data recorder, the type of observation, the results, the acceptability,and the action taken in connection with any deficiencies noted. Records shall be identifiable and retrievable.

Requirements shall be established concerning record retention, such as duration, location,and assigned responsibility which are consistent with applicable regulatory requirements.

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

1. Reactor power level history a

2. Nuclear fuel exposure history

3. Safety related operational tests

4. Safety related operating procedure his t o ry

5. Safety related periodic operational tests and inspections N

69 of 74

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Operational Quality Assurance Plan s Rev: .2 )

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! 6. Required operational reviews and approvals

7. Shif t supervisory and reactor logs i

8. Personnel radiation exposure records

9. Radioactive release records J

10. Required Transient or Operating Cycling Records

11. Reportable Occurrence records j 12. Radioactive shipment records

13. Plant radiation and contamination survey _ records 4

14. Review Cournittee records 19.3 Plant Modification Records l Measures shall be established which assure that records are generated and retained adequate to reconstruct plant modifications that are safety related. Such records shall include the following documents pertaining to the modification where appropriate:

j 1. Modification description

2. Safety evaluation

) 3. Required reviews and approvals

4. Procurement documentation l 5. Detailed design description

, 6. Required analysis and test reports i

7. Document and procedure revision I

8. Required installation procedures l -

9. Required personnel qualifications l

l 19.4 Plant Maintenance Records I

Measures shall be established which assure that records pertaining to maintenance of plant safety related structures, equipment and components are generated and retained. Such records shall include

the following

1 Preventive Maintenance Records 70 of 74

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• Rev: 2

!. 2. Corrective Maintenance Records

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3. Calibration Records 19.5 Personnel Qualification Records

$ Measures shall be established which assure personnel qualification

] records are generated and retained. Such records shall include the j following:

i e

1. Training and qualification of personnel as required by 10CFR55. .

j 2. Training and qualification of personnel who perform special

processes. -

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3. Radiation protection training and qualification..

l 4. Participation in required training programs.

i 19.6 Procurement Records

}

4 Measures shall be established which assure that safety related l

procurement documents and associated documents are generated, j retained,and retrievable.

j 19.7 Surveillance Test Records i

l Measures shall be established which assure that records associated

with Surveillance Testing including Inservice Inspections, are j gathered and retained. Such records shall include, as appropriate,

schedules, test or inspection procedures, personnel qualifications, required reviews and approvals and test or inspection results.

19.8 Audit Reports Measures shall be established which assure records pertaining to j audits of-quality activities shall be gathered and retained. These

! records shall include audit' schedules, audit procedures, audit reports, j and associated followup actions.

i 19.9 Record Retention

• Measures shall be established which assure that record retention requirements are identified for each required record. Such retention-requirements shall assure compliance with pertinent Technical-Specifications or other regulatory requirements.

~

19.10 References The following Operational Quality Assurance Program documents are utilized for controlling required records

l 71 of 74

Audit reports and associated nonconformance reports shall be i periodically analyzed-for quality trends and the results reported to

, the appropriate level of management for review and assessment.

l l' 20.6 Non-Conformance l- -

Measures shall be established which assure that deficiencies l identified by' audits or other means.are resolved. These measures.

i shall include notification of the individual responsible for the j deficiency, recommended corrective action, and verification.

of satisfactory resolution.

4:

i 20.7 References l . The following Operational Quality Assurance Program documents are J utilized to control' audits:

5 A. General Office Directives-i

{' 1. 1ACD 2.2 sudits 1

2. 2ACD 2.2 Audits f 3. 3ACD 2.2 Audits I'

j B. Monticello Directives i

! 1. 4ACD 3.7 Internal Audits

, 2. 4ACD 3.12 Control of Nonconforming' Activities i

! C. -Prairie-Island-Directives

! 1. =5ACD 2.2 Internal Audits r

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