ML20214W522

Rev 3 to Operational QA Program

ML20214W522
Person / Time
Site:	Maine Yankee
Issue date:	06/01/1986
From:	Frizzle C, Garrity J, Lawton R Maine Yankee
To:
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ML20214W512	List: ML20214W509 ML20214W522
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NUDOCS 8612100267
Download: ML20214W522 (78)

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MAINE YANKEE ATOMIC PONER COMPANY OPERATIONAL QUALITY ASSURANCE PROGRAM i

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TABLE OF CONTENTS Approval Sheet -

Policy Statement I. Organization II. QA Program III. Design Control IV. Procurement Document Control V. Instructions, Procedures &nd Drawings VI. Docum'ent Control VII. Control of Purchased Material, Equipment and Services .

VIII. Identifi-cation and Control of Material, Parts and Components IX. Control of Special Processes X. Inspectio.n XI. Test Contr,ol XII. Control of Measuring and Test Equipment XIII. Handling, Storage and Shipping XIV. Inspection, Test and Operating Status XV. Nonconforming Materials, Parts and Components XVI. Corrective Action '

XVII. Quality Assurance Records XVIII. Audits Appendix A Qualification Requirements Appendix B Maine Yankee Responsibilities Appendix C Maine Yankee Classifications 0329A-RRL

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Rev. No.: 3 6/1/86 Date:

MAINE YANKEE ATOMIC POWER COMPANY OPERATIONAL QUALITY ~ ASSURANCE PROGRAM PREPARED BY: IIY  % '2 .

R. R. Lawton Jr., Manafer, Quality Assurance Maine Yankee Atomic Power Company REVIEHED BY: 'LL /

J.H.'(Garrity,PlantManager Maine Ya'nkee Atomic Power Company RE,!IEHED BY: 2

. C. D. Frizzle, Vice' P'resid'ent, Manager of Operations Maine Yankee Atomic Power Company pjy R VIEHED BY: 6 L -

P. S. Lydon, Vice President, Finance & Administration

' Maine Yankee Atomic Power Company APPROVED BY: d-T J. B. Ranpza, Executive 4We President, Chief Operating Officer Maine Yankee Atomic Power Company i-

, APPROVED BY: . / /

f C.j E. Monty, President

[ Maine Yankee Atomic Power Company i

POLICY STATEMENT Ooerational Ouality Assurance Procram The Maine Yankee Atomic Power Company Operational Quality Assurance Program shall comply with the requirements of the Code of Federal Regulations, Title 10, Part 50, Appendix 8, with respect to the operation, maintenance of, and changes to, the nuclear generating facility.

The Company policy of a firm commitment to quality is best reflected in a memorandum to all employees from its Chief Executive Officer and incorporated into this program as Attachment 1.

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l MAIRE EDISON ME HARHEE ATCMICPOWERCOMPARUe AUGUSTA, MAINE 04M6 g

U7 (207) 623-3521 ;

O ATTACHMENT 1 TO: All Personnel FROM: Charles E. Monty, President and Chief Executive Officer John B. Randazza, Executive Vice President, Chief Operating Officer MAINE YANKEE'S COMMITMENT TO QUALITY From its beginning, Maine Yankee has been committed to quality.

This commitment is reflected in the engineering conservatism, extra safety features , and quality construction bui.it into the station. It is also reflected in its long and excellent operating record: fourteen years of consistently high power production with no measurable environmental impact, never a threat to public safety, and no permanently disabling empl oyee injury.

At Maine Yankee, quality is everyone's responsibility--from the manager who should consistently exercise sound judgement to the production worker who should perform all assigned tasks with skill and professionalism. A conmitment to quality work must also be shared by the suppliers of equipment, material, and services to the Company and by contractors and tradesmen who work at the plant.

Over the last few years, we have continued to take measures to advance the quality of our operation. Plant modifications have been made to improve operational reliability and safety; special performance tests have been conducted to verify the reliability of safety related systems ; and our quality assurance and training programs have been substantially expanded. Most important of all, Maine Yankee people have made a greater personal commitment to improving quality in everything they do.

The formal Maine Yankee Quality Assurance Program identifies all the regulatory quality requirements to which the Company must adhere, and the Quality Assurance Department monitors operational activities to assure those requirements are met. However, no quality program and no amount of monitoring can assure a high level of quality. This can only be achieved with the personal dedication and commitment of every employee to doing every job carefully, skillfully, and professionally.

Maine Yankee's commitment to quality improvement must continue to be vigorously pursued if our Company is to gain and hold public confidence and acceptance necessary to its survival.

The Institute of Nuclear Power Operations (INPO) has as its overall goal: THE PURSUIT OF EXCELLENCE. That too must be Maine Yankee's overall goal.

The cooperation and support of all personnel is necessary if we are to achieve'the desired objectives of ever better performance, safer operation, and greater public confidence.

Ab President and

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Mecutive Vice President, COO

Title:

Section I. Oraanization Page: 1 of 2

_Rev. No.: 3 Date: 6/1/86 I. ORGANIZATION A. SCOPE This section describes the functions and relationship of personnel

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responsible for establishing and implementing the Operational Quality Assurance Program.

B. RESPONSIBILITY Maine Yankee Atomic Power Company is responsible for the safe operation of its nuclear power plant.

This Operational Quality Assurance Program is adopted to ensure that -

Company activities related to safety are in full compliance with regulatory requirements, meet all applicable industry standards, and are consistent with good engineering and management practices.

The Quality Assurance Department assures that the program is implemented effectively.

The Executive Vice President, Chief Operating Officer has corporate officer general responsibility for all aspects of operational quality. Specific areas of responsibility are delegated to other-personnel and organizations as indicated throughout the program and in Appendig B. The responsibility for the overall program is retained and excercised by Maine Yankee.

C. ORGANIZATIONAL RELATIONSHIPS -

Maine Yankee Atomic Power Company lines of authority of personnel involved in the implementation of the Operational Quality Assurance Program are indicated in Section 5 of the Technical Specifications.

The Nuclear Services Division of Yankee (YNSD) has a continuing contractual obligation to provide services to the Maine Yankee Atomic Power Company. The two companies interlock at the executive level to provide additional assurance that YNSD provides the services assigned. A corporate officer of the Yankee Atomic Electric Company is also a Vice President of the Maine Yankee Atomic Power Company. This Maine Yankee Vice President is referred to hereafter -

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as the Vice President, YNSD.

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Title:

Section I. Oraanization Page: 2 of 2 Rev. No.: 3 Date: 6/1/86 D. REVIEW AND AUDIT COMMITTEES As required by the Technical Specifications, two committees have been established to insure that the plant is operated in accordance with regulatory requirements and the standards established by this Program.

1. Plant Ooerations Review Committee This Committee is composed of experienced and qualified plant personnel having direct line responsibility for plant operation. See Section 5.5, " Review and Audit" of Technical Specifications.

2. Nuclear Safety Audit and Review Committee This Committee is composed of experienced and qualified personnel not having line responsibility for plant operation.

See Section 5.5, " Review and Audit" of Technical Specifications.

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Section II. 0A Proaram Page: 1 of 14 Rev. No.: 3 Date: 6/1/86 II. OPERATIONAL OUALITY ASSURANCE PROGRAM A. SCOPE The Operational Quality Assurance Program applies to activities affecting the quality of the identified structures, systems and components that prevent or mitigate the consequences of postulated accidents that could cause undue risk'to the health and safety of I the public which are listed in Appendix C of this Program. The program takes into account the need for special controls, processes, environmental conditions, equipment, tools and skills to attain the required quality and the need for verification of quality by inspections, evaluations or tests.

B. RESPONSIBILITIES Compliance with the requirements of the Operational Quality Assurance Program is the responsibility of all personnel involved with activities affecting operational safety. Individuals responsible for establishing and executing the Operational Quality Assurance Program are delineated in Section I, " Organization", and Appendix 8 of this program. The Quality Assurance Department shall regularly review the status and adequacy of the operational quality assurance program.

C. IMPLEMENTATION The Operational Quality Assurance Program is established as required by, and to assure conformance with, Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants.

Establishment of an effective Operational Quality Assurance Program is assured through conformance with ANSI Standards and the regulatory position of regulatory gu' ides as specified in Paragraph F of this section of the QA Program. Implementation of this program is assured through Quality Assurance procedures derived from those standards and guides.

NOTES: 1) The plant Technical Specifications shall be the governing document when determining requirements to be imposed in all areas which are addressed in both technical specifications and the specified standards and guides.

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Title:

Section II. 0A Proaram Page: 2 of 14 Rev. No.: 3 Date: 6/1/86

2) Revisions to the specified standards and guides will be considered for applicability to the Maine Yankee Operational Quality Assurance Program upon written direction thereof by the Nuclear Regulatory Commission -

Regional Office.

3) ANSI Standard N18.7-1976 is the endorsing document for all other specified ANSI Standards. All such endorsed ANSI Standards will be implemented to the degree of applicability indicated in ANSI N18.7-1976.

4) Changes to the Operational Quality Assurance Program shall be handled as follows:

a) This program shall be applicable to those activities requiring quality assurance which occur commencing 90 days after acceptance of the program by the , ,

Nuclear Regulatory Commission.

b) The NRC shall be notified of changes, that reduce commitments in the accepted description of the QA Program, for their review and acceptance prior to implementation. Acceptance will be assumed 60 days after submittal unless notified otherwise.

c) Changes that do not reduce QA Program commitments shall be submitted to the NRC at least annually.

d) Editorial changes or personnel reassignments of a minor nature do not require NRC nctification.

D. MANAGEMENT EVALUATION The Vice President, YNSD, directs a thorough evaluation of the established Operational Quality Assurance Program by assigning the Nuclear Safety Audit and Review Committee the task of reviewing for compliance with and evaluating the effectiveness of the quality assurance program.

E. TRAINING

1. 'The indoctrination and training programs shall provide the following quality assurance related activities:

a. Instruction as to the purpose, scope, and implementation of quality assurance manuals, instructions, and procedures.

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Section II. 0A Procram Page: 3 of 14

_Rev. No.: 3 Date: 6/1/86

b. Training and qualification in the principles and techniques of the activity being performed.

c. Maintenance of proficiency by retraining, reexamining,-

and/cr recertifying personnel.

d. Documentation of the training sessions including content, attendance, dates and results where applicable.

F. ANSI STANDARDS AND REGULATORY GUIDES The Operational Quality Assurance Program is written to conform to the ANSI standards and regulatory guides listed below, as modified '

herein. -

l. ANSI N18.1 - 1971, Selection and Trainina of Nuclear Power Plant Personnel, as modified by Regulatory Guide 1.8, Revision 1.

2. ANSI N18.7 - 1976, Administrative Controls and Ouality Assurance for the Ooerational Phase of Nuclear Power Plants, as modified by Regulatory Guide 1.33, Re. vision 2, and the following exceptions,

a. EXCEPTION:

The following exception is taken by Maine Yankee.

ANSI standards not referenced in ANSI N18.7-1976, but which are referenced in an ANSI standard endorsed by N18.7-1976 shall not be considered as applicable to the Maine Yankee Operational Quality Assurance Program.

ALTERNATIVE:

Maine Yankee may use the noted standards as gu' ides, as necessary.

b. EXCEPTION:

Maine Yankee takes exception to the application of paragraph 5.2.16, as applied to control of measuring and test equipment for radiological controls equipment. Paragraph 5.2.16 requires that an evaluation be made and documented concerning the validity of previous tests from the time of the last calibration when the device is found out of calibration.

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Section II. 0A Proaram Page: 4 of 14 Rev. No.: 3 Date: 6/1/86 ,

ALTERNATIVE:

It is impractical to log everywhere that a survey instrument is used. Personnel carry a pocket dosimeter and TLD for monitoring radiation levels.

c. EXCEPTION:

Maine Yankee takes exception to the provision of paragraph 5.2.2, which requires that one of the two individuals providing approval of temporary (procedure) changes "...

shall be the supervisor in charge of the shift.".

ALTERNATIVE: ,

Maine Yankee will adhere to Section 5.8.3 of the Plant Technical Specifications.

d. EXCEPTION:

Maine Yankee takes exception to application of paragraph 5.3.9.1, Emergency Procedure Format and Content.

ALTERNATIVE:

NRC Order dated July 10, 1981 confirmed Maine Yankee's commitment concerning NUREG 0737, supplement ICl for THI related items. Maine Yankee's Emergency Operating Procedures (EOP) will be written to the requirements of the E0P Hriter's Guide, based on NUREG 0899, submitted to the NRC for review on March 18, 1986.

e. EXCEPTION:

Maine Yankee takes exception to Section 4.3 " Independent Review Program" and Section 4.4 " Review Activities of the Onsite Operating Organization".

ALTERNATIVE:

Section 4.3 refers to requirements for the Nuclear Safety and Audit Review Committee (NSARC). Technical Specification 5.5.8 establishes appropriate requirements for independent review for NSARC.

Section 4.4 refers to requirements for the Plant Operations Review Committee (PORC). Technical Specification 5.5.A i establishes appropriate requirements for review activities of the onsite operating organization.

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Section II. OA Proaram Page: 5 of 14

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3. ANSI N18.17 - 1973, Industrial Security for Nuclear Power Plants.

a. EXCEPTION:

Maine Yankee takes exception to the application of ANSI N18.17 for Security.

ALTERNATIVE:

10CFR73 requires that. Security Plans be established and approved by the NRC. This provides adequate assurance that an acceptable Security Plan is established and implemented that meets or exceeds ANSI N18.17 requirements.

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4. ANSI N45.2 - 1977, Ouality Assurance Proaram Reauirements for Nuclear Facilities, as modified by Regulatory Guide 1.28, Revision 2.

5. ANSI N45.2.1 - 1973, Cleanina of Fluid Systems and Associated Comoonents Durina Construction Phase of Nuclear Power Plants, as modified by Regulatory Guide 1.37, March 16,1973.

6. ANSI N45.2.2 - 1972,'Packaaina. Shionina. Receivina. Storace &

Randlina of Items for Nuclear Power Plants (During the Ccnstruction Phase), as modified by Regulatory Guide 1.38, Revision 2, and the following exceptions.

a. EXCEPTION:

Subsection 3.7.1 & A3.7.1 - Containers Maine Yankee takes exception to the specific requirements for containers.

ALTERNATIVE:

Containers shall be of suitable construction to assure material.is received undamaged.

JUSTIFICATION: -

l Containers shipped by closed carrier, stored inside and not I subjected to a wet environment do not require weather l resistant fiberboard, therefore, this is an unnecessary )

expense. Additienally, numerous vendors utilize shipping containers : hat do not comply with the specific requirements of this section, i.e., flaps overlap. The acceptance criteria for a shipping container should be established 1 based on the capability of the container to maintain the l component / material in a safe condition. Technology has i advanced beyond the standard. .

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Section II. 0A Proaram Page: 6 of 14

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b. EXCEPTION:

Subsection 3.7.2 - Crates and Skids Maine Yankee takes exception to the requirement that skids and runners shall be used on boxes with a gross weight of 100 pounds or more.

ALTERNATIVE:

Skids or runners shall be used on boxes with a gross weight of 100 pounds or more if practical.

JUSTIFICATION: ,

Storage methods and container design frequently are such that runners or skids are not feasible.

c. EXCEPTION:

Subsection 5.2.1 - Shinoino Damaae Insoection Maine. Yankee takes exception to the requirement that a preliminary visual inspection or examination be performed prior to unloading.

ALTERNATIVE:

Maine Yankee shall perform those required inspections after unloading. In special instances, pre-unloading inspections shall be performed.

JUSTIFICATION:

Post unloading inspection is adequate to determine any damage that may have been incurred during shipping and handling.

d. EXCEPTION:

Subsection 5.2.2 - Item Insoection Maine Yankee takes exception to the requirement, that "The inspections shall be performed in an area equivalent to the level of storage requirements for the item".

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Section II. 0A Proaram Page: 7 of 14

_Rev. No.: 3 Date: 6/1/86 ALTERNATIVE:

Maine Yankee shall perform receiving inspection in a manner and in an environment which does not endanger the requisite quality of the item; however, receiving area environmental controls may be less stringent than storage environmental controls for that item. When inspections are performed in receiving areas with environmental controls less stringent than storage area environmental controls, a time limit shall be established on a case basis for retention of items in the receiving area. Retention. time shall be such that deterioration is prevented and applicable manufacturer -

recommendations are addressed.

JUSTIFICATION: -

Receipt inspection activities are for a much shorter duration and therefore should not be subjected to the same stringent requirements as required for storage,

e. EXCEPTION:

Subsection 5.2.3 - Soecial Insoection Maine Yankee takes exception to attaching special inspection procedures to the item or container.

ALTERNATIVE: \

Special inspection procedures shall be readily available to personnel performing inspections.

JUSTIFICATION:

Procedures are subject to less abuse and more stringent controls when maintained on file and not attached to the item. Inspection status is maintained by tagging and procedure control. i

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f. EXCEPTION \

Subsection 6.1.2 - Levels of Storace Maine Yankee takes exception to two specific requirements associated with fuel storage (classified level A).

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Section II. 0A Proaram Page: 8 of 14

- Rev. No.: 3 Date: 6/1/86 ALTERNATIVE:

Maine Yankee shall meet the requirements of level A storage f.or new fuel with the exception of special air filtering; and temperature and humidity controls.

JUSTIFICATION:

The existing storage conditions at the Maine Yankee plant is

- consistent with the protection provided to the fuel while in storage at the manufacturer (vendor) and/or while in transit to the plant site and are judged to provide adequate protection to the fuel assembly structure which is of highly corrosion resistant materials. He believe that the above ,

listed requirements are intended for application at the manufacturing facility (vendor) where the uranium pellets may be exposed to the atmosphere and not in its fully encapsulated, and therefore, fully protected form in a completed fuel assembly.

g. . EXCEPTION:

Anoendix A-3 Subsection A3.5.l(1) - Caos & Pluas Maine Yankee takes exception to the requirement that non-metallic plugs and caps shall be brightly colored.

AL'TERNATIVE:

Non-metallic plugs and caps shall be of a contrasting color.

JUSTIFICATIONS:

The purpose of utilizing brightly colored plugs and caps is to assist in assuring obstructions are not inadvertently

- placed in operating components or systems. By using plugs and caps of a contrasting color this objective can be achieved.

h. EXCEPTION:

Accendix A-3 Subsection A3.9(1) - Second Groun. Markinas 1 Maine Yankee takes exception to the requirement that container markings shall appear on a minimum of two sides. 1 0329A-RRL 4

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Section II. 0A Procram Page: 9 of 14

.Rev. No.: 3 Date: 6/1/86 ALTERNATIVE:

Containers shall be adequately marked to provide identification and retrievability.

JUSTIFICATION:

Containers are tagged to provide identification and inspection status. L?.gloyment of two tags on small containers adds bulk and confusion and does not provide for better identification or traceability.

i. EXCEPTION:

Accendix A-3. Subsection A.3.9(4) - Second Grouo. Markina -

Maine Yankee takes exception to the requirement. that container markings shall be no less than 3/4" high container permitting.

ALTERNATIVE:

l Container markings shall be of a size which permits easy recognition.

JUSTIFICATION:

Markings were intended to provide identification and instructions. The criteria should be that the markings i clearly provide the same.

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j. EXCEPTION:

Accendix A-3 Subsection A.3.9(6) - Second Groun. Markina i Maine Yankee takes exception to the information required for container marking.

ALTERNATIVE:

Marking'shall be adequate in each case to provide identification, traceability and instructions for special i handling, as applicable. i i

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Section II. OA Proaram Page: 10 of 14

_ Rev. No.: 3 Date: 6/1/86 JUSTIFICATION:

! The information r'equired is excessive. Cluttering a

container with excessive markings only reduces the main objectives, maintaining identification and establishing special controls. .

7. ANSI N45.2.3 - 1973, Housekeeoina Durina the Construction Phase of Nuclear Power Plants, as modified by Regulatory Guide 1.39, Revision 2, and the following exceptions.

a. EXCEPTION:

Subsection 2.1 - Plannina ,

Maine Yankee takes exception to the five-zone requirements specified in the subject standard.

I ALTERNATIVE:

i Maine Yankee shall establish as a minimum a three-zcne program as follows:

Zone III Zone III criteria shall be applied to major portions of t>P s

reactor coolant system which are opened for inspection,

\ maintenance or repair.

j 1) Access control over personnel shall be required.

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2) Cleanliness shall be maintained, commensurate with the

, work being performed, so as to preclude the entry of

' I foreign material to the Reactor Coolant System.

3) A documented cleanliness inspection shall be performed immediately prior to closure.

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\ HQIE: The Zone III requirements may be expanded for certain. maintenance / repair activities if deemed j appropriate by plant management. In such instances applicable sections of Zones I & II j shall be specified.

} Zone IV I

Zone IV criteria shall be applied to the radiation control areas of the plant.

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1) Standard janitorial and work practices shall be utilized to maintain a level of cleanliness commensurate with company policy in the areas of Housekeeping, Plant and l Personnel Safety and Fire Protection.

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2) Additional housekeeping requirements shall be implemented as required for the control of radioactive contamination.

3) Smoking and eating shall be controlled consistent with

. good health physics practices and to maintain 4

cleanliness.

. Zone V -

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F Zone V criteria shall be applied to the remainder of the plant.

l 1) Standard janitorial and work practices shall be utilized

{ to maintain a level of cleanliness commensurate with company policy in the areas of Housekeeping, Plant and Personnel Safety and Fire Protection.

b. EXCEPTION:

Subsection 3.2 - Control of Facilities Maine Yankee takes exception to the control of tools, equipment, materials and supplies used in Zone III.

ALTERNATIVE

i i Maine Yankee shall verify control for Zone III as indicated j in the previous exception.

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) 8. ANSI N45.2.4 - 1972, Installation. Insnaction. and Testina Reauirements for Instrumentation and Electric Eauinment Durina the Construction of Nuclear Power Generatina. Stations, as modified by Safety Guide 30, August 11, 1972.

9. ANSI N45.2.5 - 1974, Sunnlementarv Ouality Assurance Reauirements for Installation. Insnection. and Testina of Structural Concrete and Structural Steel Durina the Construction i Phase of Nuclear Power Plants, as modified by Regulatory Guide 1.94, Revision 1.

• 10. ANSI N45.2.6 - 1978, Oualifications of Insnection. Examination.

and Testina Personnel for Nuclear Power Plants, as modified by Regulatory Guide 1.58, Revision 1, and the following exception.

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a. EXCEPTION:

Maine Yankee takes exception to the application of the Standard to all Maine Yankee personnel performing inspection, examination and testing.

ALTERNATIVE:

Maine Yankee personnel identified in ANSI N18.1-1971 who perform inspection, examination and testing will be qualified to ANSI N18.1-1971.

Maine Yankee personnel not identified in ANSI N18.1-1971 who perform inspection, examination and testing will be ,

qualified to ANSI N45.2.6.-1978.

Contractor personnel who perform inspection, examination and testing at Maine Yankee will be qualified to ANSI N45.2.6-1978.

11. ANSI N45.2.8 - 1975, Sucolementarv Ouality Assurance Reauirements for Installation. Insoection and Testino of Mechanical Eauioment and Systems for Construction Phase of Nuclear Power Plants, as modified by Regulatory Guide 1.116 Revision OR.

12. ANSI N45.2.9 - 1974, Reauirements for Collection. Storace and Maintenance of Ouality Assurance Records for Nuclear Power Plants, as modified by Regulatory Guide 1.88, Revision 2.

13. ANSI N45.2.10 '1973, Ouality Assurance Terms and Definitions, as modified by Regulatory Guide 1.74, February 1974, and

• the following exception.

a. EXCEPTION:

Subsection 2 - Terms and Definitions Maine Yankee takes exception to the definitions of

" Certificate of Conformance" and " Certificate of Compliance".

ALTERNATIVE:

Maine Yankee shall reverse the definitions of the above terms so our Program will be in compliance with the implied definitions in the ASME B&PV Code and Maine Yankee i

specifications.

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14. ANSI N45.2.ll - 1974, Ouality Assurance Reauirements for the Desian of Nuclear Power Plants, as modified by Regulatory Guide 1.64, Revision 2.

15. ANSI N45.2.12 - 1977, Reauirements for Auditina of Ouality Assurance Proarams for Nuclear Power Plants, as modified by Regulatory Guide 1.144, January 1979, and the following exceptions.

a. EXCEPTION:

Subsection 4.2.2 Team Selection Maine Yankee takes exception to the requirement that a " Lead .

Auditor" be appointed as team leader.

ALTERNATIVE:

a Team Selection i Audits will be performed under the cognizance of a lead auditor.

b. EXCEPTION:

Subsection 3.5.3.3 Maine Yankee takes exception to the requirement for supplemental audits.

ALTERNATIVE:

Maine Yankee Internal Audits are performed on a calendar year frequency and preclude the need for supplemental audits. Supplemental Audits will be initiated by the Manager, Quality Assurance as deemed necessary for significant changes in the QA Program or procedures.

c. EXCEPTION:

Subsection 4.5.1 Maine Yankee takes exception to the thirty day requirement for corrective action.

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Section II. OA Proaram Page: 14 of 14

-Rev. No.: 3 Date: 6/1/86 ALTERNATIVE:

I Maine Yankee will specify corrective actions and provide

management approval within thirty working days. Corrective action completion dates will be as specified in the audit documentation approved by management.

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16. ANSI N45.2.13 - 1976, Ouality Assurance Reautrements for the 3 Control of Procurement of Items and Services for Nuclear Power Plants, as modified by Regulatory Guide 1.123, Revision 1.

17. NSI N45.2.23 - 1978, Oualification of Ouality Assurance Proaram Audit Personnel for Nuclear Power Plants, as modified by Regulatory Guide 1.146, August 1980. ,

18. ANSI N101.4 - 1972, Ouality Assurance for Protective Coatinas Anolied to Nuclear Facilities, as modified by Regulatory Guide 1.54, June 1973.

19. ANSI N323 - 1978, Radiation Protection Instrumentation Test and

! Calibration.

20. Regulatory Guide 1.26, Revision 3, Ouality Groun Classifications and Standards for Water. Steam and Radioactive - Haste -

Containina Components of Nuclear Power Plants,

a. EXCEPTION:

4 Maine Yankee takes exception to the Guide in its entirety.

ALTERNATIVE:

Maihe Yankee shall continue to classify structures, components and systems in accordance with ANSI Standard N18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Hater Reactor Plants" as in the past.

. 21. Regulatory Guide 1.29, Revision 3, Seismic Desian Classification.

a. EXCEPTION:

4 Maine Yankee takes exception to the application of Reg.

Guide 1.29, Rev. 3, (9/78).

ALTERNATIVE:

4 Maine Yankee shall apply Reg. Guide 1.29, Rev. 3 (9/78) to those structures, systems and components as defined in the 4

Maine Yankee FSAR Section 2.5.

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Section III. Desian Control Page: 1 of 3 Rev. No.: 3 Date: 6/1/86 '

III. DESIGN CONTROL A. SCOPE This section establishes measures to assure that the design of and changes to structures, systems, and components covered by the Operational Quality Assurance Program are controlled.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for:

a. Evaluation and/or audit of the design control system. ,

b. Review of design sketches and specifications to assure that the documents are prepared, checked and reviewed in

! accordance with procedures and that the documents contain I the necessary quality assurance requirements such as inspection and test requirements, acceptance requirements, i and the extent of documenting inspection and test results.

I 2. The Plant Engineering Department shall be responsible for:

a. The design of and control of activities for changes to structures, systems, or components.

b. Preparation, review and approval of design documents including the correct translation of applicable regulatory requirements and design bases into specifications, drawings i and written documents.

i I

c. Application of suitable design controls to such activities J as: field design engineering; physics; seismic, stress, j thermal, hydraulic, radiation, and accident analyses; compatiblity of materials; accessibility for inservice j inspection, maintenance and repair; and quality standards.

d. Identification, documentation, and control of deviations from specified design requirements and/or quality standards.

e. Delineation of acceptance criteria for inspections and tests.

, f. Design reviews to assure that design characteristics can be i controlled, inspected and tested.

I 0329A-RRL 1

Title:

Section III. Desian Control Page: 2 of 3 Rev. No.: 3 Date: 6/1/86

g. Proper selection and performance of design verification process such as design reviews, alternate calculations, qualification testing or test programs. If the verification method is only by test, procedures shall provide: criteria that specify when verification should be by test; that prototype, component or feature testing is performed as early as possible prior to installation of plant equipment, or prior to the point when installation would become irreversible; and verification by test is performed under conditions that simulate the most adverse design conditions.

h. Subjection of design and specification changes to ihe'same design controls and approvals that were applicable to thE original design unless designated in writing to anothey ' ,

responsible organization. ef ,

1. Evaluation of commercial "off-the-shelf" items for ~

suitability for use in safety classified systems, components or structures. prior to use.

j. Selection of suitable materials, parts, equipment, and processes for safety classified structures, systems, and components.

k. Control of Fire Protection in accordance with YNSD YA-GEN-9.

1. Notification to responsible personnel that a design change may affect performance of their duties.

m. Maintenance of records which correctly identify the as-built condition of the facility for the life of the item while installed.

n. Establishing design control program procedures which prescribe:

1) Implementation of the provisions delineated above.

2) Organizational responsibilities for preparing, reviewing, verifying and approving design documents such as system descriptions, design input and criteria, design drawings / sketches, design analyses, specifications, and procedures / instructions.

3) Identification of internal and external design interface~

controls including lines of communication among participating design organizations and across technical disciplines for the review, approval, release, distribution and revision of design documents.

0329A-RRL

\d ,,,,

Title:

Section III. Desian Control Page: 3 of 3 Rev. No.: 3

. Date: 6/1/86

4) Provisions to satisfy Regulatory Guide 1.64, Rev. 2 (ANSI Standard N45.2.ll - 1974).

3. The Fire Protection Coordinator YNSD shall be responsible for review of proposed design changes of fire protection systems in accordance with the. Yankee Nuclear Services Division General Specifications YA-GEN-9.

4. The Plant Manager shall be responsible for:

a. Evaluation of the recommendations of the Plant Operations Review Committee.

b. Review and approval of proposed design changes.

5. The Yankee Nuclear Services Division shall be responsible for:

a. Establishing and implementing a system for processing design changes.

b. Independent design verification of proposed design changes

~to assure the adequacy,of design.

v

! b,.

\

l 2

j 0329A-RRL

Title:

Section IV. Procurement Document Control Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 IV. PROCUREMENT DOCUMENT CONTROL A. SCOPE This section establishes measures to assure that applicable requirements necessary to assure adequate quality are included or referenced in procurement documents for material, equipment and services.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for:

a. Evaluation and/or audit of procurement document control, including the preparation, review, and approval of purchase . .

requests for material, equipment, and services covered by the Operational Quality Assurance Program,

b. Review of procurement documents to assure that requirements

. necessary to assure quality are included or referenced in the procurement documents for material, equipment, and services.

c. Review of safety classified purchase specifications for inclusion of proper inspection requirements and acceptance criteria.

2. The Materials Management Department shall be responsible for: l

a. Processing and control of requisitions for purchase orders.

b. Control and temporary storage of quality assurance documentation of purchased material.

c. Establishing procedures which prescribe:

1) Preparation of procurement documents.

2) Documentation of the review and approval of procurement documents prior to release and availability of this documentation for verification.

3) Identification of the vendor's quality assurance requirements applicable to the items or services procured.

0329A-RRL ,

Title:

Section IV. Procurement Document Control Page: 2 of 2 Rev. No.: 3 Date: 6/1/86

4) Identification in the procurement documents of the documentation to be prepared, maintained, and/or submitted to the purchaser prior to use, such as:

(a) drawings, specifications, procedures (b) inspection and fabrication plans (c) inspection and test records (d) personnel and procedure qualifications (e) chemical and physical test results of material (f) the company's right of access to the vendor's facilities and records for surveillance to "

procurement specifications.

5) Review and approval of changes and revisions to procurement documents at least equivalent to those for the original document.

6) Control of procurement documents for spare and replacement parts such that the technical requirements are equal to or better than the original and administra-tive control to the current QA Program requirements.

7) Controls for procurement of commercial "off the shelf" items, where controls appropriate for nuclear applications cannot be imposed in a practicable manner, to provide the necessary assurance of an acceptable item.

8) Inclusion of the applicability of the requirements of 10 CFR 21 in the procu'rement documents when 10 CFR 21 applies.

9) Provisions to satisfy Regulatory Guide 1.123, Revision 1 (ANSI Standard N45.2.13 - 1976), as it pertains to procurement document control.

3. The Plant Engineering Department shall be responsible for:

a. Review of purchasing specifications which detail the technical and quality requirements for material, equipment and service purchases.

b. Review technical and quality requirements for material, l equipment, and service purchases.

4. All departments shall be responsible for adhering to the procurement procedures established per 2.c, above.

Title:

Section V. Instructions Procedures and Drawinas Page: 1 of 1 Rev. No.: 3

_ Date: 6/1/86 V. INSTRUCTION

S. PROCEDURE

S. AND DRAWINGS A. SCOPE This section establishes measures to assure that activities affecting quality are prescribed and implemented by instructions, procedures or drawings appropriate to the circumstances.

B. RESPONSIBILITIES

1. 'The Quality Assurance Department shall be responsible for

. perfor ning evaluation of instructions, procedures, and drawings.

2. The Administration Department shall be responsible for establishing procedures which prescribe preparation and implementation of procedures.

3. The Plant Engineering Departinent shall be responsible for establishing procedures which prescribe preparation and implementation of design change installation instructions and drawings including changes.

4. All departments shall be responsible for: ,

a. Preparing and implementing instructions and procedures associated with activities aff,ecting quality i'ncluding computer programs controlled by Maine Yankee.

b. Assuring that specifications, in'structions, procedures and drawings include appropria'te quantitative and qualitative acceptance criteria, as applicable, for determining that activities have been satisfactorily accomplished.

(

\

\

0329A-RRL

Title:

Section VI. Document Control Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 VI. DOCUMENT CONTROL A. SCOPE This section establishes measures to assure that proper documents, such as procedures, instructions and drawings, are available for use in activities affecting quality. The measures provide for review, approval, issuance and control of documents, including revisions thereto.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for:

a. Evaluation and/or audit of document control systems at Maine Yankee and vendors. ,

b. Review and approval of all Quality Assurance Manual procedures (0-series).

c. Review of maintenance, modification and inspection procedures for inclusion of quality assurance requirements.

2. The Administration Department shall be responsible for establishing document control procedures which prescribe:

a. Sequence of actions and responsibilities for review, approval, and control of procedures.

b. Review of procedures by appropriately qualified personnel,

c. Establishment of distribution lists.

d. Action to be taken for obsolete or superseded documents.

i

e. Review and approval of document changes by the same organizations that performed the original review and approval QI by other responsible organizations delegated by Maine Yankee,

f. Inclusion of approved changes in procedures and other applicable documents prior to placing the system in operating status.

0329A-RRL

. . - - - , - - - - - - ,, ,y ., -

.-,r-,-2-------.,.--e-r-----.-----rw- - . . - - - - -- - - . - ---+ --

Title:

Section VI. Document Control Page: 2 of 2 Rev. No.: 3 Date: 6/1/86

g. Availability of proper and current documents at the location where the activity is to be performed prior to commencing the work,

h. Establishment, revision, and distribution of a master list or equivalent to identify the current revision number of procedures, specifications, or other quality assurance documents as applicable.

1. Identification of documents to be controlled which shall include, as a minimum:

1) Design documents, including calculations, drawings, specifications and analyses.

2) Design, manufacturing, construction, and installation drawings

3) Procurement documents

~

4) Operational Quality Assurance Program and manual and maintenance and operating procedures

5) Manufacturing, inspection and test instructions

6) Test documents

7) Design change requests

8) FSAR

9) Nonconformance reports

3. The Plant Engineering Department and/or YNSD shall be ,

responsible for: ,,

a. Controlling the issuance of engineering drawings, General Specifications, welding and nondestructive examination procedures.

~ '

b; Revision and distribution of welding and nondestructive examination procedures.

c. Maintenance and distribution of General Specifications, controlled drawings and installation instructions.

, 4. All departments shall be responsible for adhering to the document control procedures established per 2., above.

0329A-RRL

.o I

Title:

Section VII. Control of Purchased Material . Eauinment & Services  ;

_ . Page: 1 of 3 l Rev. No.: 3 Date: 6/1/86 VII. CONTROL OF PURCHASED MATERIAL. EOUIPMENT AND SERVICES A. SCOPE l

I This section establishes measures to assure that purchased material, i

equipment and services, whether purchased directly or through l contractors and subcontractors, conform to the procurement documents.

i B. RESPONSIBILITIES i 1. The Quality Assurance Department shall be responsible for:

a. Vendor audits, via YNSD Quality Assurance Department, based -

on one or more of the following:

1) Vendor's capability to comply with the applicable 4

criteria of 10CFR50 Appendix B and/or ANSI N18.7.

l 2) Review of vendor's previous records and performances.

3) Surveillance of vendor's facilities / services and QA program to determine his ability to produce the item to the purchase specifications.

4), Review of the Supplier's current quality records -

, supported by qualitative and quantitative information which can be objectively evaluated. The evaluation may include review and evaluation of the Supplier's Quality

! Assurance Program, Manual and Procedures, as appropriate,

b. Planned vendor surveillances, in conjunction with YNSD-QA, which provide for: .

1) Specification of processes to be witnessed or verified, the surveillance method and documentation required, and personnel responsible for performing the surveillance.

i'

2) Assurance that the vendor complies with the quality requirements by surveillance of in-process work at U intervals consistent with the importance, complexity and quality of the item.

c. Documentation and maintenance of the results of vendor audits and surveillances, including a listing of qualified

. vendors, in conjunction with YNSD-QA.

0329A-RRL

---w,---e,r, ,w,ve-sw=--w-, -

---.we.- r-,,-n.rwr,,,m---- ----,.-c - . .

W -

Title:

Section VII. Control of Purchased Material . Eauioment & Services

. . Page: 2 of 3 Rev. No.: -3 Date: 6/1/86

d. Surveillance of material and/or services control,

e. Surveillance of bids to assure adequacy of QA requirements.

f. Receipt inspection of vendor furnished material to assure:

1) Haterial is identified and conforms with receiving documentation.

1 2) Material and documentation are inspected in accordance with predetermined instructions or recognized standards and are determined acceptable prior to use.

3) Inspection, test and other records (or certificates of -

conformance atesting to material acceptability) are on-site prior to use.

Certificates of conformance shall contain as a minimum:

(a) Identification of purchased material or equipment, such as by the purchase order number.

(b) Specific procurement requirements met by the purchased material or equipment, such as codes, standards and other specifications.

(c) Purchase requirements not met and the resolution of the nonconformance.

(d) Attested to by a person responsible for the quality assurance function including their title.

4) Items are identified as to their inspection status prior to release for controlled storage, installation or

.further work. -

g. Verifying the validity of supplier certificates of

.conformance.

h. Establishing procedures, in conjunction with YNSD-QA, to satisfy Regulatory Guides 1.38, Revision 2 (ANSI Standard N45.2.2 - 1972) and 1.123, Revision 1 (ANSI Standard N45.2.13 - 1976), as pertains to vendor audit and surveillance and to receipt inspection.

0329A-RRL O

, , , _ _ . - , . __..m__ ,____ , _ _ . , _ . _ , _ _ _ _ _ _ _ - _ _ _ . . ,

Title:

Section VII. Control of Purchased Material . Eauioment & Services ,

_ . Page: 3 of 3 Rev. No.: 3 Date: 6/1/86

2. The Materials Management Department shall be responsible for:

a. Control of material and equipment until issued.

b. Establishing procedures to satisfy Regulatory Guides 1.38, Revision 2 (ANSI Standard N45.2.2 - 1972) and 1.123, Revision 1 (ANSI Standard N45.2.13 - 1976), as pertains to control of purchased material, equipment and services.

3. All departments shall be responsible for:

a. Control of material and equipment after issuance from Stores.

b. Bid evaluation as applicable. -

c. Evaluation of purchased services during and/or after completion of the service.

O I

e 0329A-RRL l

]

Title:

Section VIII. Identification &

Control of Material. Parts and Components Page: 1 of.1 Rev. No.: 3 Date: 6/1/86 VIII. IDENTIFICATION AND CONTROL OF MATERIAL. PARTS. AND COMPONENTS A. SCOPE 3

This section establishes measures for identification and control necessary to prevent the use of incorrect or defective material, parts, and components.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for: ,

a. Evaluation, audit and/or inspection of the control and issuance of materials, parts, and components covered by the Operational Quality Assurance Program.

b. Review of vendor Quality Assurance programs for traceability of materials through the use of heat number, part number, or serial number, either on the. item or on records traceable to the items.

2. The Materials Management Department shall be responsible for establishing procedures for the identification and control of s materials, parts, and components, including partially fabricated subassemblies and consumables, to prevent the use of incorrect, defective or outdated items. The procedures shall require the following:

a. Identification is maintained either on the item, in a location and with a method which does not affect its fit or function, or on records traceable to the item.

b. Maintenance of traceability of materials and parts to the appropriate documentation such as drawings, spectr' cations, purchase orders, manufacturing and inspection documents, deviation reports, and physical and chemical mill test reports.

l

c. Identification of materials, parts, and components is verified and documented prior to release for use.

3. All departments shall be responsible for adhering to the I identification and control procedures established per 2., above.  !

0329A-RRL  !

l l

Title:

Section IX. Control of Snacial Processes Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 IX. CONTROL OF SPECIAL PROCESSES A. SCOPE This section establishes measures to assure that special processes, including welding, heat treating, and nondestructive testing, are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria and other special requirements.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for: ,

a. Evaluation, audit and/or inspection of the control of

• special processes.

b. Performance and/or evaluation of certain nondestructive tests in accordance with Yankee Nuclear Services Division .

Welding and Nondestructive Examination Procedures.

c. Training, qualification, and requalification of Haine Yankee personnel in nondestructive examination.

d. Review of special process documents provided by vendors for use on-site and when otherwise specified.

2. The Plant Engineering Department shall be responsible for establishing procedures which prescribe control of special processes, including:

Verification that qualification records of procedures, a.

equipment, and personnel connected with special processes are in accordance with applicable codes, standards, and specifications as applicable.

b. Special processes are accomplished in accordance with written process sheets or equivalent with recorded evidence of verification.

c. Maintenance and updating of qualification records of special process procedures, equipment, and personnel as applicable.

3. The Yankee Nuclear Services Division shall be responsible for approving documents for welding, and nondestructive examinations.

l 0329A-RRL  !

l

.. i I

Title:

Section IX. Control of Snecial Processes Page: 2 of 2 Rev. No.: 3 Date: 6/1/86

4. All departments shall be responsible for:

a. Assurance that work involving special processes are performed by qualified personnel in accordance with approved documents.

b. Control of material used in special processes,

c. Review of special process documents, as applicable, provided by vendors for use on-site and when otherwise specified.

1

)

1 0329A-RRL l

~ ~ .

n-m - . - - - - - , -, _

_ . . . --,,,vn,____.--. - - - - - . , _ ,,n_ . - - . , - - - - , , -- ,, .

Title:

Section X. Insnection Page: 1 of 2 Rev. No.: 3 .

Date: 6/1/86 X. INSPECTION A. SCQEE This section establishes measures for inspection of activities affecting quality, to verify conformance with approved instructions, procedures, drawings and specification for accomplishing the

, activities.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for:

a. Review of documentation pertinent to the Inservice ,

Inspection Program.

b. Evaluation of inspection activities and personnel.

c. Establishing and/or reviewing hold and/or notification points for plant activities.

d. Establishing and/or reviewing hold and/or notification points for vendor activities,

e. Writing and approving inspection instructions and check lists.

f. Establishing procedures which prescribe:

1) Independence of personnel performing the inspection from the personnel performing the activity.

2) Use of procedures, instructions or check lists which incorporate the following as applicable:

(a) A description of the type of inspection.

(b) Date and results of the inspection.

(c) Information related to conditions adverse to quality.

(d) Inspector identification.

0329A-RRL

Title:

Section X. Insnection Page: 2 of 2 Rev. No.: 3 Date: 6/1/86 (e) Evidence as to acceptability of the results.

(f) Action taken to resolve any discrepancies noted.

3) Use of drawings and specifications when performing inspections.

4) Inspection of repairs and replacements in accordance with applicable design and inspection requirements or acceptable alternatives.

5) Evaluation of processing methods, equipment, and personnel when direct inspection is not possible.

6) Qualification of inspectors in accordance with ,

. applicable codes, standards, and company training programs; and maintenance of qualifications and ,

certifications.

7) Review of maintenance documents by quallfled personnel knowledgeable in quality assurance to determine the need for inspection, identification of inspection personnel, and documenting inspection results.

8) When inspections associated with normal operations of the plant (such as routine maintenance, surveillance, and tests) are performed by individuals other than those who performed or directly supervised the work, but are within the same group, the following controls shall be met:

(a) The quality of the work can be demonstrated through a functional test when the activity involves

- breaching a pressure retaining item.

(b) The qualification criteria for inspection personnel are reviewed and found acceptable by the QA organization prior to initiating the inspection.

2. All departments shall be responsible for:

a. Assuring that activities requiring quality assurance meet predetermined requirements.

0329A-RRL

.. j

b i

Title:

Section XI. Test control Page: 1 of 2

_Rev. No.: 3 Date: 6/1/86 k

XI. TEST CONTROL A. SCOPE This section establishes measur'es for a test program to demonstrate that structures, systems, and components will perform satisfactorily in service.

l -

8. RESPONSIBILITIES

]

j 1. The Quality Assurance Department shall be responsible for:

! a. Evaluation of the control of the test program. ,

i

b. Evaluation of the documentation generated during the test program.

1

2. The Plant Engineering Department shall be responsible for: '

j a. Preparation or review. of specifications, requirements, and acceptance criteria for testing following plant changes and j maintenance activities.

b. Determination of when testing is required following plant l changes and maintenance activities.

c. Establishing procedures which prescribe that test documents incorporate or reference the following, as appropriate:

1) Purpose 1 2) Requirements and acceptance criteria contained in

applicable design and procurement documents.

3) Reference sources, such as vendor's literature.

4) Instructions for performing the test.

5) Test prer'equisites, such as:

4 j (a) Calibrated instrumentation i (b) Adequate and appropriate test equipment and instrumentation including accuracy requirements i

! (c) Trained, qualified, and licensed / certified personnel

! 0329A-RRL i-

l

Title:

Section XI. Test Control l

~

Page: 2 of 2 l

.Rev. No.: 3 Date: 6/1/86 (d) Completeness of item to be tested (e) Sultable and controlled environmental conditions (f) Provisions for data collection and storage (g) Completion of other procedures

6) Mandatory inspection hold points.for witness by owner, contractor or inspector, when applicable.

I

7) Identification of test prerequisites that must be met.

8) Acceptance and rejection criteria. ,

9) Method of documenting test data and results.

3. The Operations Department shall be responsible for establishing procedures to satisfy the surveillance testing and inspection program provisions of ANSI Standard N18.7 - 1976 (Section -

5.2.8). Documents to implement this program shall be consistent with the requirements of Section 2.c, above, and shall also require recording the as. found condition, corrective actions performed, if any, and as-left condition.

4. All departments shall be responsible for:

a. Supplying qualified personnel and calibrated equipment for testing.

b. Establishing test programs, procedures and acceptance criteria to satisfy the procedures established per 2.c and 3, above.

Scheduling and performing tests.

c.

d. Documenting, evaluating, and approving test results.

0329A-RRL

Title:

Section XII. Control of Measuring and Test Eautoment

- Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 XII. CONTROL OF MEASURING AND TEST EOUIPMfNT A. SCOPE This section establishes measures to assure that tools, gages, instruments, and other mearuring and test equipment, used in activities affecting quality, are controlled and at specified periods calibrated and adjusted to maintain accuracy within necessary limits.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for evaluation and/or audit of the established program for the control of measuring and test equipment.

2. The Maintenance Department shall be responsible for establishing procedures which prescribe:

a. Identification.of measuring and test equipment and traceability to the calibration data,

b. Labelling or tagging of measuring and test equipment to indicate due date for calibration. (Other means may be employed provided there is adequate assurance out-of-calibration devices will not be used).

c. Calibration of installed plant instrumentation and control systems to assure conformance with the Plant Technical Specifications.

d. Calibration of measuring and test equipment (other than c.,

above) at specified intervals based on required accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting the measurement.

e. Traceability of reference standards to nationally recognized standards; 'mt, documentation of the basis for. calibration where national standards are nonexistent.

0329A-RRL

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

] -

1

Title:

Section XII. Control of Measurina and Te'st Eautoment

. . Page: 2 of 2 4 Rev. No.: 3

- Date

6/1/86 i

f. Calibration accuracy requirements shall be as follows:

1) Measuring and test equipment shall be of equal or -

greater accuracy as the installed instrumentation.

2) In general, the inaccuracy of the reference standards

! shall contribute no more than one fourth of the 4

allowable measuring and test equipment tolerance.

l However, when the actual inaccuracy of the measuring and

, test equipment is less than one fourth of the installed plant equipment tolerance, the requirement of one fourth the tolerance between the reference standards and measuring Tnd test equipment may not be necessary.

{ ,

3) Reference standards shall be calibrated against

standards of equal or greater accuracy. ,

i When the foregoing accuracy requirements cannot be attained,

!. the rationale for deviating from these requirements shall be

! justified and documented.and authorized by responsible

! management. The management authorized to perform this 4

function shall be identified.

] _g. Documentation and maintenance of the status of all items

, under the calibration system.

4 l h. Documentation of measures taken to determine the validity of i previous inspections performed when measuring and test equipment is found to be out of calibration.

3. All departments shall be responsible for:

a. Developing implementing documents for control of measuring

, and test equipment including identification and calibration for equipment under their control.

b. Providing calibrated tools, gages and instruments. .

c. Maintaining calibration records.

< d. Preparing and reviewing specifications for measuring and

{

test equipment, to applicable requirements.

1 li e. Adhering to the measuring and test equipment control procedures established per 2, above. l

0329A-RRL 1

l t

i

~

Title:

Section XIII. Handlina. Storaae

-- Page:

and Shionina 1 of 2 Rev. No.: 3 Date: 6/1/86 XIII. HANDLING. STORAGE AND SHIPPING A. SCOPE This section establishes measures to control the handling, storage, shipping, cleaning and preservation of material and equipment to prevent damage or deterioration.

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for:

a. Evaluation, audit and/or inspection of the handling, ,

storage and shipping of materials, parts, and components. -

b. Evaluation and/or audit of handling, storage, and shipping documents.

c. Review of Engineering specifications and procurement documents to assure that proper handling, storage, and shipping requirements have been specified.

2. The Materials Management Department shall be responsible for establishing procedures which prescribe:

a. Specification and accomplishment of special handling, preservation, storage, cleaning, packaging, and shipping requirements by suitably trained individuals in accordance with predetermined work and inspection instructions for critical, sensitive, perishable or high value items.

b. Preparation of instructions in accordance with design and specification requirements to control the cleaning, handling, storage, packaging, shipping and preservation of safety classified materials, components and systems to preclude damage, loss or deterioration by environmental I conditions such as temperature or humidity.

c. Provisions for the storage of chemicals, reagents

~

(including shelf life), lubricants, and other consumable materials under 'their. control. .

d. Provisions to satisfy Regulatory Guide 1.38, Revision 2 (ANSI Standard N45.2.2 - 1972), as pertains to handling, storage and shipping.

e. Provisions for a Preventive Maintenance Program for materials, items and components, as applicable, under their control.

0329A-RRL

Title:

Section XIII. Handlina. Storaae and Shionina Page: 2 of 2

_.Rev. No.: 3 Date: 6/1/86 L

3. The Chemistry Department is responsible for establishing procedures which prescribe provisions for the storage of chemicals and reagents (including shelf life) under their control.

4. All departments shall be responsible for:

a. Developing implementing documents for handling, storage and shipping of materials and equipment to satisfy the procedures established per 2., above as necessary.

b. Providing suitable facilities and equipment for handling, storage, and shipping of materials as necessary. ,

c. Inspecting and testing special handling tools and equipment.

d. Providing and controlling special handling tools and equipment to ensure safe and adequate handling.

s 6

1 0329A-RRL 1 - - - _ _ . . - _ . _ . . _ _ _ _ _ _ _ - - - . --- _ _ __. ___ . , -- __ . ---___-_. _ _ _ _ _ _ .

A . .

o

Title:

Section XIV. Insoection. Test &

Ooeratina Status

_. Page: 1 of 1 Rev. No.: 3 Date: 6/1/86 XIV. INSPECTION. TEST AND OPERATING STATUS A. SCOPE This section establishes measures for indicating the status of items undergoing inspections and tests (via tags, labels, log books, etc.), to prevent the unintentional bypass of required tests. In addition, this section establishes measures for indicating the operating status of components and systems to prevent their inadvertent operation.

B. RESPONSIBILITIES ,

1. The Quality Assurance Department shal1 be responsible for the evaluation of inspection, test and operating status of systems and components throughout fabrication, installation, and test.

2. The Operations Department shall be responsible for:

a. The status of operating equipment or systems removed from service for maintenance, test, inspection, repair, or change,

b. Periodic review and update of standing orders.

c. Periodic review, updating and cancellation of special orders.

d. Periodic review to evaluate plant operations and plan future activities. The important elements of the reviews shall be -

documented.

e. Establishing procedures to satisfy the equipment control provisions of ANSI Standard N18.7 --1976 (Section 5.2.6).

3. All departments shall be responsible for:

a. Informing the Operations Department of the current status of equipment or systems removed for repair, maintenance, test, inspection, or change.

b. Designating personnel who are responsible for the status of equipment and systems.

0329A-RRL

Title:

Section XV. Nonconformina Materials. Parts and Comnonents

_ . Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 XV. NONCONFORMING MATERIALS. PARTS. AND COMPONENTS A. ECQEE This section establishes measures to control items, services or activities which do not conform to requirements.

B. RESPONSIBILITIES

1. The Vice President, Manager of Operations shall be responsible for reviewing significant nonconformance reports.

2. The Quality Assurance Department shall be responsible for: -

a. Evaluation of the system for controlling nonconforming

• material, parts and components.

b. Review and concurrence of dispositions and corrective -

actions of nonconformance reports provided by the applicable department.

c. Establishment of measures to provide for the documented control of nonconforming materials, parts, and components in order to prevent their inadvertent use or installation.

d. Followup and closecut of nonconformances,

e. Establishing procedures which prescribe:

1) Identification, documentation, disposition, inspection and segregation of nonconforming items.

2) Identification of those individuals or groups delegated the responsibility and authority for the disposition and written approval of nonconforming items.

3) Inspection and test of reworked or repaired items which require reinspection and retest to original methods or methods equivalent thereto.

0329A-RRL

Title:

Section XV. Nonconformina Materials. Parts and Comoonents

_ . Page: 2 of 2 Rev. No.* 3 Date: Ell /86

4) Inclu; ion of nonconformance reports dispositioned "acccpt as is" or " repair' as part of the inspection records furnished to the plant.

5) Periodic analysis of nonconformance reports to show quality trends with the results reported to management for review and assessment.

6) Documentation of the identification, description, 4

disposition, inspection and signature approval of the disposition for nonconformances in a nonconformance report.

3. The Plant Engineering Department shall be responsible for: -

a. Review of nonconforming items which cannot be corrected by vendor action.

b. Preparation or approval of implementing documents for repair and/or rework of nonconforming items.

4. The Materials Management Department shall be responsible for establishment of a feedback system between Maine Yankee and Vendor Representatives in regard to nonconforming material.

)

r i

0329A-RRL i

e.

4 e

Title:

Section XVI. Corrective Action Page:

Rev. No.: 3 1 of 2 ,

Date: 6/1/86 XVI. CORRECTIVE ACTION A. SCOEE This section establishes measures to assure that conditions adverse to quality are promptly identified and corrected. For significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and documented, and corrective action taken is to preclude repetition. .

B. RESPONSIBILITIES

1. The Quality Assurance Department shall be responsible for: ,

a. Evaluation and/or audit of plant activities which identify, review and correct conditions adverse to quality.

b. Evaluation and/or review of documentation of corrective action. .

c. Establishing procedures which prescribe: .

1) Identification and correction of conditions adverse to quality.

2) Significant conditions adverse to quality, the cause, and action taken to preclude repetition are documented and reported to management.

2. The Plant Engineering Department shall be responsible for:

a. Review of conditions adverse to quality which involve design deficiencies to determine the cause of the condition,

b. Corrective action to preclude repetition of significant design deficiencies.

3. All departments shall be responsible for:

a. Identification and correction of conditions adverse to quality,

b. Identification and documentation of the cause and preparation of recommendations to preclude repetition of significant conditions adverse to quality.

0329A-RRL

Title:

Section XVI. Corrective Action Page: 2 of 2

_Rev. No.: 3 Date: illL86

c. Implementation of corrective action including, as appropriate, action to preclude repetition.

d. Documentation of corrective action taken. .

9 e

e f

1 0

4 I 0329A-RRL

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, _ , , , , - ,y-.,,_ _ ,,,-----r,,--.--ew,,,--r- , - - - - ,w-e "

Title:

Section XVII. Quality Assurance Records

.. Page: 1 of 2 Rev. No.: 3 Date: 6/1/86 XVII. OUALITY ASSURANCE RECORDS 1A. SCOEE

1. This section establishes measures for maintenance of records which provide documentary evidence of the quality of items and of activities affecting quality. Requirements shall be established for identification, transmittal, retrievability and retention of quality assurance records including duration, location, protection and assigned responsibility.

2. The quality assurance records shall include plant history; operating logs; principal maintenance; design change ,

activities; reportabl.a occurrences; nonconformance reports;.

• results of reviews, inspection, tests, audits and material analyses; monitoring of work performance; qualification of personnel, procedures and equipment; drawings; specifications; procurement documents; calibration documents and reports; corrective action reports; and other records required by Technical Specifications.

B. RESPONSIBILITIES

1. The Quality-Assurance Department shall be responsible for:

a. Evaluation and/or audit of quality assurance record review, control and retention,

b. Maintenance of audit, evaluation, inspection, and vendor surveillance records generated by the Quality Assurance Department.

2. The Yankee Nuclear Services Division shall be responsible fo'r:

a. Maintenance of audit, inspection and vendor surveillance records generated by YNSD.

b. Maintenance of design documents generated by YNSD and not retained by Maine Yankee.

3. The Administration Department shall be responsible for:

a. Providing'for the receipt, storage, preservation, safekeeping, retrieval and final disposition of QA records.

0329A-RRL,

Title:

Section XVII. Quality Assurance Records

_ - Page: 2 of 2 Rev. No,: 3 Date: 6/1/86

b. Maintaining facilities for the permanent and temporary storage of records to prevent destruction of the records by fire, flooding, theft, and deterioration caused by a combination of extreme variations in temperature and humidity conditions. Duplicate records shall be stored in a separate remote location when the type of document is not included in the record storage facility.

c. Establishing procedures to satisfy Regulatory Guide 1.88, Revision 2 (ANSI Standard N45.2.9 - 1974).

4. All departments shall be responsible for:

a. Adhering to the records controls procedures established per 3.c., above.

b. Identifying department QA records and establishing retention periods in accordance with R.G.1.88, Rev. 2 (ANSI N45.2.9-1974).

5

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0329A-RRL

. yi_

e 4 / ,

Title:

.Section XVIII. Audits Page: 1 of 3

'- _Rev. No.: -3

, Date:'6/1/86 XVIII~. ' AUDITS A. SCOPE , 4,'

This se'c tion establishes measures for a system of planned and documented audits to verify compliance with all aspects of the Progra:n and to assess the effectiveness of the Program.

B. RESPONSIBILITIES-

1. Tha Quality Assurance Department, in conjunction with YNSD Quality Assurance, shall be responsible for: ',

a. Providingao,6rovedauditproceduresor-dhe[k'listsfor ,

< audit of activities encompassed by the 18 criteria of 10CFR50 Appendiv B and ANSI N18.7. t

b. Providing for training of audit personnel,

c. Scheduling and coordinating of the Internal Audit Program.

d. Preparing. reviewing and/or approving implementing documents for Internal Audits which prescribes:

1) Occumentation of audit results and review with management having responsibility in, the3rea audited.

2) Necessary action to be taken by' responsible management to correct deficiencies revealed by the audit.

3) Inclusion of an objective evaluation of quality-related practices, procedures and instructions

.and the effectiveness of implementation in the audit.

. 4) Inclusion of an objective evaluation of work areas, activities, processet and itams and the review of documentaton in the audit.

5) Reaudit of deficient creas until corrections have been ' I' accomplished to preclude repetition of the deficiencies, as appropriate.

( p 0329A-RRL ,

-f

,j.

F- ,

i I

Title:

section XVIII. Audits Page: 2 of 3 ,

_Rev. No.: 3 1 Date: 6/1/86

6) Performance of audits where the requirements of Appendix B to 10CFR Part 50 and ANSI N18.7 are being

' implemented.

7) Performance of audits as required by the Plant Technical Specifications.

8) Scheduling of audits regularly on the basis of the status and safety importance of the activities being performed.

9) Regularly scheduled audits shall be supplemented by audits as determined by the Manager, Quality Assurance for one or more of the following conditions-(a) When significant changes are made in functional areas of the quality assurance program such as significant reorganization or procedure revisions.

(b) When it is suspected that the quality of the item is in jeopardy due to deficiencies in the quality assurance program.

(c) When a systematic, independent assessment of program effectiveness is considered necessary.

(d) When necessary to verify implementation of required corrective action.

10) Independence of the auditors from direct

responsibility for the area being audited,

e. Conducting., reporting and following up on audits to c satisfy Regulatory Guide 1.144 - January 1979 (ANSI Standard N45.2'12 - 1977).

f. Preparing information regarding the Internal Audit Program for review by the Nuclear Safety Audit and Review Committee.

g. Perfo'rming random ~ informal evaluation of plant activities.

h. Providing for audits of vendors.

2. The Manager of each audited organization shall be responsible s for evaluation and approval of recommended corrective action l

for Internal Audit deficiencies. -

'0329A-RRL

% b

1

( .

Title:

Section XVIII. Audits {

f Page: 3 of 3  ;

j- _Rev. No.: 3 Date: 6/1/86 f

( 3. All departments shall be responsible for:

a. Investigation and response to audit deficiencies.

b. Implementation of corrective ' action approved by management.

I' 1

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-, 0329A-RRL -

Title:

Anoendix A. Qualification Reauirements

_. Page: 1 of 1 Rev. No.: 3 -

Date: 6/1/86 QUALIFICATION REQUIREMENTS FOR THE MANAGER, QUALITY ASSURANCE The Manager, Quality Assurance must meet the below listed qualification requirements:

EDUCATION: Bachelor Degree in Engineering or related science, or the equivalent in practical experience.

EXPERIENCE: Four (4) years experience in the field of quality assurance, ,

or equivalent number of years of nuclear plant experience in -

a supervisory position preferably at an operating nuclear plant or a combination of the two. At least (1) year of this four years experience shall be nuclear power plant experience in the implementation of the quality assurance program. Six (6) months of the one year experience shall be obtained within a quality assurance organization.

0329A-RRL

Title:

Aooendix B. Maine Yankee Resoonsibilities

_. Page: 1 of 15 Rev. No.: 3 Date: 6/1/86 Appendix B Responsibilities

1. Executive Vice President. Chief Ooeratina Officer Reports directly to the President.

The Executive Vice President, Chief Operating Officer is responsible for:

a. Ensuring that the Operational Quality Assurance Program is implemented. ,

b. Establishing company policies for Operational Quality Assurance.

c. Through YNSD or other internal organizations assuring that an audit of the Operational Quality Assurance Program is performed annually or at his option more frequently if circumstances warrant, by personnel not having direct responsibility in the areas audited.

d. Ensuring that personnel performing Quality Assurance functions have sufficient authority and organizational freedom to:

1. identify quality problems,

2. initiate, recommend, or provide solutions through designated channels, and,

3. verify implementation of solutions.

e. Approving all changes to the Operational Quality Assurance Program.

f. Approving changes to Quality Assurance Manual procedures. l

g. Forwarding NSARC recommendations to the appropriate organizations for review and implementation and/or response.

h. Resolving disputes between Quality Assurance and other departments /

organizations involving quality.

i. The Executive Vice President, Chief Operating Officer has corporate responsibility to ensure that personnel performing activities affecting the management, planning, operations, maintenance and quality assurance for his areas of responsibility.are adequately trained and aualified to perform their assigned tasks.

0329A-RRL f- - - -

1

Title:

Accendix 8. Maine Yankee Resoonsibilities

.. Page: 2 of 15 Rev. No.: 3 Date: 6/1/86 I

2. Vice President - Yankee Nuclear Services Division (YNSD)

Reports directly to the President.

The Vice President (YNSD) is responsible for:

a. Providing review of designated activities via the Nuclear Safety and Audit Review Committee (NSARC), as required by the technical specificatiens or requested by Maine Yankee.

b. Monitoring responses to NSAR committee and Maine Yankee Project Manager recommendations and bringing all safety related disputes, disagreements, or discrepancies, which cannot be resolved at a lower ,

level, to the attention of the Maine Yankee President. -

c. Providing personnel to perform independent audits of the Maine Yankee Operational Quality Assurance Program implementation as requested by Maine Yankee.

d. Providing personnel to perform independent engineering reviews of safety class design changes as requested by Maine Yankee.

e. Providing personnel to develop and maintain special process procedures, such as NDE, Welding, and Heat Treating.

f. Providing personnel for technical, engineering, licensing, compliance, operational, and quality assurance support as requested by Maine Yankee.

g. Providing personnel to perform audits, evaluations, inspections, and vendor surveillances as requested by the Vice President,

• Manager of Operations.

h. Providing emergency preparedness, environmental., fuel management, and nuclear engineering support as requested by Maine Yankee.

i. Providing personnel to develop and maintain Yankee Nuclear Services Division General Specifications.

j. Providing a Fire Protection Engineer to review design changes to fire protection systems and components.

k. Providing document control for all QA documents generated and controlled by YNSD.

1. Ensuring that all Yankee NSD personnel working in behalf of or at Maine Yankee are properly trained and qualified to perform their i

assigned tasks for activities requiring quality assurance.

0329A-RRL l

l --

1

!!!IP'  :

Title:

Annendix B. Maine Yankee l

Resoonsibilities .

_. Page: 3 of 15

. Rev. No.: 3 Date: 6/1/86

3. Vice President. Manager of Ooerations Reports to the Executive Vice President, Chief Operating Officer.

The Vice President, Manager of Operations is responsible for:

a. Reviewing changes to the Operational Quality Assurance Program.

b. Review of and compliance with Federal and State regulations and standards for nuclear power facilities.

c. Providing, by assignment of responsibility to an appropriate organizational element, for review and approval of training programs. .

d. Reviewing and approving or disapproving all design changes.

e. Enforcing company quality assurance policies.

f. Advising the Plant Operations Review Commitee (PORC) and the Nuclear Safety and Audit Review Committee (NSARC)-in engineering, operations, and training, when requested.

g. Training and qualification of all personnel assigned to the Maine Yankee Plant, Plant Engineering Department, Training Department, and Operational Support Department.

0329A-RRL t

l l

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Title:

Annendix B. Maine Yankee Resnonsibilities Page: 4 of 15 Rev. No.: 3 Date: 6/1/86

4. Vice President. Finance and Administration Reports to the President.

The Vice President Finance and Administration is responsible for:

a. Ensuring that the Operational Quality Assurance Program is implemented for his areas of responsibility.

b. Reviewing changes to the Operational Quality Assurance Program'that concern Material Management and Administration.

c. Establishing company policy for Materials Management and Administration. ,

d. Training and qualification of all personnel assigned to .the department. ,

O e

0329A-RRL

9

Title:

Anoendix B. Maine Yankee Responsibilities Page: 5 of 15 Rev. No.: 3 Date: 6/1/86

5. Treasurer Reports to the Vice President, Finance and Administration The Treasurer is responsible for:

a. Processing and control of requisitions for purchase orders,

b. Control and identification of material and equipment upon receipt, storage and issuance by the Stores Department.

c. Control and temporary storage of quality assurance documentation of purchased materials.

d. Control and maintenance of the plant spare parts inventory system. -

e. Selection of qualified vendors for purchasing material from the Approved Vendor's List.or stipulation of additional controls from QAD when an approvcd vendor is not utilized.

f. Accurate translation of quality requirements to purchase documents.

g. Training and qualification of all personnel assigned to the Materials Management Department.

9 0329A-RRL

W t -

Title:

Annendix B. Maine Yankee Resoonsibilities

_. Page: 6 of 15 Rev. No.: 3 .

Date: 6/1/86

6. Plant Manaaer Reports to the Vice President, Manager of Operations.

The Plant Manager is responsible for:

a. Overall plant activities,

b. Reviewing all changes to the Operational Quality' Assurance Program.

c., ' Execution of the administrative controls and quality assurance program

'at the plant to assure safety.

d. Compliance with all State and Federal license conditions, rules and -

regulations through the operating staff and supporting organizational

, elements.

I

e. Advising the NSARC in the areas of maintenance, operation, testing and training when requested. .

f. Interfacing between Maine Yankee.and Yankee Nuclear Services Division for site activities under his responsibility.

g. Resolving and implementing recommendations to industry operating problems. ,

h. Coordinating' activities necessary to support plant reporting requirements.

i. Ccordinating plant activities necessary to support the plant i environmental surveillance program. l r 1

j. Supervision and coordination of the-Fire Protection Program, via the Facilities Section.

k. The. Plant Manager is responsible for the training and qualification of all personnel assigned to the Operations, Technical Support and Maintenance Departments and Facilities Section. -

i 1

l 0329A-RRL I

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

O i

Titla: Annendix B. Maine Yankee Resnonsibilities

! - Page: 7 of 15 Rev. No.: 3 Date: 6/1/86

7. Manaaer. Quality Assurance Reports to the Executive Vice President, Chief Operating Officer.

The Manager, Quality Assurance is responsible for:

a. Maintaining the Operational Quality Assurance Program to the requirements of 10 CFR 50, Appendix B, and ANSI N18.7 - 1976.

b. Revising the program as standards, regulations, and experience dictate.

c. Quality Assurance review of design changes, material purchase requests, nonconformances, and maintenance control documents for .

quality requirements.

d. Providing personnel for audit, inspection and/or vendor s.urveillance of contractor / vendor activities at the plant to assure. compliance with the applicable criteria of 10 CFR 50, Appendix B, and ANSI N18.7 -

1976.

e. Inspection, evaluation and/or audit of activities affecting the quality of structures, systems and ccmponents important to safety.

f. Internal Audits of the QA Program implementation.

g. Maintaining the Internal Audit Program.

i

h. Reviewing and approving' changes to the program.

4

1. Reviewing and approving changes to Quality Assurance procedures.

j. Coordinating interfacing quality assurance activities between the company, Yankee Nuclear Services Division, and outside agencies.

k. Documentation and maintenance of department quality assurance records.

1. Stopping unsatisfactory work and controlling further processing, delivery, or installation of nonconforming material. ,

I m. Management overview and overall direction and coordination of quality

assurance and quality control activities performed by the Quality i Assurance Department personnel located at the plant.

n. The Manager, Quality Assurance is responsible for the training and qualification of all personnel assigned to the department.

0329A-RRL i

1 o

Title:

Anoendix B. Maine Yankee Resnonsibilities

-- Page: 8 of 15 Rev. No.: 3 Date: 6/1/86

8. Manaaer. Nuclear Enaineerina and Licensina Reports to the Executive Vice President, Chief Operating Officer.

The Manager, Nuclear Engineering and Licensing is responsible for:

a. Management overview and overall direction and coordination of reload core design and nuclear engineering analysis of plant systems.

b. Management overview and overall direction and coordination of safety analysis. activities supporting license amendments, FSAR, and

-demonstration that plant design bases are met.

c. Company relations with the USNRC, licensing policy, overall direction -

and co~ ordination to prepare and submit licensing documents, licensing information systems, and monitoring regulatory developments.

d. Management overview of radiological environmental monitoring, radioactive and toxic waste control and disposal, emergency preparedness, radiological monitoring and control and development, maintenance and implementation of ple.ns and programs relating to these areas.

e. Representing the company to government and industry groups.

f. Arranging for and managing support activities of YNSD and outside vendors and contractors in areas of responsibility.

g. The Manager, Nuclear Engineering and Licensing is responsible for the training and qualification of all personnel assigned to the department.

0329A-RRL

3

Title:

Accendix B. Maine Yankee Resoonsibilities Page: 9 of 15

.Rev. No.: 3 Date: 6/1/86

9. Manaaer. Plant Enaineerina Reports to the Vice President, Manager of Operations.

The Manager, Plant Engineering is responsible for:

a. Coordinating the development, review, and implementation of design changes.

b. . Establishing and maintaining the Plant Inservice Inspection Program.

c. Providing personnel to review material purchase requests, nonconformances, corrective actions, maintenance and repair activities. ,

d. Maintaining and disseminating information regarding engineering codes, standards, criteria and guidelines to applicable personnel.

e. Interfacing plant engineering activities between Maine Yankee, Yankee Nuclear Services Division, and outside agencies,

f. Providing personnel to perform surveillance programs and test programs assigned by the Vice President, Manager of Operations.

g. Advising PORC and NSARC in the plant. engineering area when requested.

h. Providing technical support to the plant.

i. Documenting and maintaining quality assurance records associated with plant engineering.

j. The Manager, Plant Engineering is responsible for the training and qualification of all personnel assigned to the department.

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0329A-RRL

't

Title:

Anoendix B. Maine Yankee Resoonsibilities Page: 10 of 15

_.Rev. No.: 3 Date: 5/1/86

10. Manaaer. Ooerational Suocort i Reports to the Vice President, Manager of Operations.

The. Manager, Operational Support is responsible for:

a. Advising PORC and NSARC in regulatory compliance areas when requested.

b. Directing activities to assure compliance with federal and state enforcement documents.

c. Documentation and maintenance of department quality assurance records.

d. Interfacing compliance activities between the company Yankee Nuclear -

Services Division, and outside agencies.

e. Providing personnel to perform independent operational reviews.

f. Coordinating the review of industry operating problems to minimize occurance at the plant.

g. Providing personnel for operational support to the plant.

h. The Manager, Operational Support is responsible for the training and qualification of all personnel assigned to the department.

0329A-RRL

4 i

Title:

Anoendix B. Maine Yankee Resoonsibilities

_ . Page: 11 of 15 Rev. No.: 3 Date: 6/1/86

11. Manaaer. Trainino Reports to the Vice President, Manager of Operations.

The Manager, Training is. responsible for:

a. Developing and implementing general employee training.

b. Provide direct support for operations, skill, technician, and professional training activities.

c. Advising management of any practices, circumstances, deficiencies or personnel problems which impact on the quality, quantity, or ,

availability of training.

d. Advising management on developments in training techniques, industry standards, and regulations which impact on Maine Yankee training policies and practices.

e. Development and maintenance of Maine Yankee training policy and procedures.

f. Coordination with all outside agencies for training matters,

g. Maintaining the training documentation system.

h. The Manager,' Training is responsible for the training and qualification of all personnel assigned to the department.

e 0329A-RRL

e 4

Title:

Anoendix B. Maine Yankee Resoonsibilities Page: 12 of 15 Rev. No.: 3 Date: 6/1/86

12. Manaaer. Maintenance Reports to the Plant Manager.

The Manager, Mai.ntenance is responsible for:

a. The quality of work performed by the Maintenance Department.

b. Scheduling and directing approved maintenance activities.

. c. Preparation and implementation of maintenance procedures utilizing sound engineering policies and practices for the installation of new material, equipment or spare parts.

d. Establishing and maintaining programs for preventative maintenance, calibration and testing for instruments and mechanical / electrical

• equipment in conformance with approved procedures.

e. Implementing a continuing surveillance program as outlined in the Technical Specifications.

f. Documentation and maintenance of Maintenance Department quality assurance records.

g. The Manager, Maintenance is responsible for the training and qualification of al.1 personnel assigned to the department.

0329A-RRL

-# l

Title:

Annendix B.

.. Page:

Resnonsib111 ties 13 of 15 Maine Yankee Rev. No.:' 3-Date: 6/1/86

13. Manaaer. Operations Reports to the Plant Manager.

The Manager, Operations is responsible for:

a. Conducting plant operations in accordance with approved documents and specifications.

b. Operations Department systems surveillance and operational testing.

c. Verifying system and/or component operability following maintenance, or changes using approved test procedures containing acceptance ,

criteria as specified in applicable design documents. -

d. Safe handling of core and reactor components during refueling operations.

e. Preparation and maintenance of quality assurance records of Operations Department activities.

f. Development, control and maintenance of operating and emergency operating procedures.

g. The Manager, Operations is responsible for the training and qualification of all personnel assigned to the department.

9 5

0329A-RRL i

? .. - - , , , - - ,- , ,,.__. - - ._ .,- __ _ ____ - _ . _ _ _ _ _ - _ _ _ _ . _ _ . _ __

. . . __ ._. .~ . . _ _ _ _ _ _ . _ . . _ . _. _ . _ . _

r

Title:

Annendix B. Maine Yankee Responsibilities

. . Page: 14 of 15 Rev. No.: 3 Date: 6/1/86 1

14. Manaaer. Technical Suonort Reports to the Plant Manager.

The Manager, Technical Support.is responsible for:

I

a. Providing personnel to supervise and coordinate reactor physics and nuclear tests for plant operation and adherence to applicable Technical Specifications.

b. Following and reviewing radiation protection programs and activities 1 at the plant.

t

c. Maintaining the radiological and nonradiological effluent release -

control and surveillance program.

l d. ' Maintaining refueling procedures for fuel core components handling and

inspection.

i e. ~Providing personnel to perform fuel cycle, nuclear engineering and economic studies requested by the Plant Manager.

f. Documentation and maintenance of quality assurance records in chemistry, health physics, computer, reactor physics and nuclear fuel, via the applicable group.

I g. Control and maintenance of plant computer systems.

h. Preparation and maintenance of procedures associated with l ' radiological, chemistry, reactor physics, and computer via the '

, applicable group. ,

l 1. Supervision and coordination of the Hazardous Haste Program, i

i

j. Supervising and supporting the Emergency Plan Coordinator in the

! development, exercise and implementation of the Emergency Plan.

k. The Manager, Technical Support.is responsible for the training and ,

l qualification of all personnel assigned to the department.

0329A-RRL t

_.. _ ._. . _ . _ _ _ _ , _ . _ . . . _ . _ _ . , , . - _ _ . . _ , , _ , _ , , , , . - _ - _ , _ _ - _ _ _ _ - _ __,______._m-._,..__,_ . , . - _ - , , - _ _ _ _ _ - _ _ . _ . . , _ . _ _ _ _ , . _ _ .

?

l

Title:

Accendix B. Maine Yankee Resoonsibilities

.. . Page: 15 of 15 Rev. No.: 3 Date: 6/1/86

15. Manaaer. Administration Reports to the Vice President, Finance and Administration.

The Manager, Administration is responsible for:

a. Controlled distribution of the Operational Quality Assurance program.

b. Controlled distribution, storage and retrieval of quality assurance records.

c. Controlled distribution of quality assurance manual procedures.

d. Controlled distribution of vendor procedures used at the plant that affects safety classified structures systems and components.

e. Proper Administration of the Security Plan.

f. Training and qualification of all personnel assigned to the department.

0329A-RRL

-o d  ;

1

Title:

Anoendix C. Maine Yankee Classifications

-. Page: 1 of 8 Rev. No.: 3 Date: 6/1/86 I

MAINE YANKEE CLASSIFICATION OF STRUCTURES. COMPONENTS AND SYSTEMS APPLICABILITY This Appendix lists the systems and structures which are subject to QA Program controls. Items added to the list will be subject to QA Program control

.beginning on the date the addition is approved.

I-I. STRUCTURES -

Containment (Including penetrations) - Safety Class 2 II. ELECTRICAL SYSTEMS AND COMPONENTS -

i Electrical and Instrumentation systems and components designed in accordance with IEEE Standard 279, " Criteria for Protection Systems for Nuclear Power Generating Stations" and IEEE Standard 308, " Criteria for

, Class IE Electric Systems for Nuclear Power Generating Stations" have l

been classified as safety class, and are listed below:

I A. 4160 Volt 5witchgear(EngineeredSafetyFeaturesBuses) i B. 4160 - 480 Volt Transformers (Associated with Engineered Safety Features)

C. 4000 and 460 Volt Motors (Associate rith Engineered Safety Features)

D. 480 Volt Switch gear (Engineered Safety Features Buses) l E. 480 Volt Motor Control Centers (Associated with Engineered Safety ~"

Features)

F. 125 Volt DC Batteries (Associated with Engineered Safety Features)

G. Battery Chargers (Associated with Engineered Safety Features)

H. Inverters,125 Volt DC to 120 Volt AC (Vital Instrument Buses)

I. Vital Instrument Bus Panels J. Regulated Instrument Buses Panels (240/120 Volts AC Single Phase)

K. 125 Volt DC Power Panels (Associated with Engineered Safety Features) i L. Transformers, dry type, 280-120/240 Volt (Associated with Regulated Instrument Buses)

M. Power Cables (Associated with Engineered Safety Features System)

N. Instrumentation and Control Cables (Associated with Engineered Safety Feature System)

O. AC Control Room Lighting 0329A-RRL i

4 q ..

_ . .___ . _ . _ - . _ . _ . , _ - . . _ _ _ _ - . _ _ _ _ _ _ _ . . . . _ . _ . . . _ _ . _ . _ _ . _ ~ . _ _ . - _ . _ _ _____. _ _ _

i'  ?

Title:

Annendix C. Maine Yankee

! Classifications

_. Page: 2 of 8 Rev. No.: 3 Date: 6/1/86 P. Diesel Generators (DG-1A, DG-1B) '

Q. Diesel Generator Control Panels (for DG-1A, DG-1B)

R. Heat Tracing for Boric Acid Injection j S. Reactor Protective Systems i T. Engineered Safety Features Actuation Systems U. Emergency Feedwater Pump Motors l

SECTION.II NOTES: -

I

1. For those electrical and instrumentation systems designated above, Quality Assurance electrical and instrumentation program requirements are applicable only to those portions of systems .

defined in Section IV as necessary to perform the system safety -

function. "

j .

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

3. 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.

4. Certain components are excluded from the QA program requirements if j they meet the criteria described in Section III.

1 l III. ELECTRICAL AND INSTRUMENTATION SYSTEM COMPONENT EXCLUSION CRITERIA 1

1. Any component of an electrical or instrumentation system (Section II) is excluded from the QA Program requirements if it meets the following criteria: .

a. A failure of the component by the' electrical shorting, open circuiting, grounding or mechanical failure would not render the system incapable of performing its intended safety function 4

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

, safety function.

c. It is not used to operate or control a device required by l Technicti Specifications.

0329A-RRL t

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

l 8 ,

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Title:

Annendix C. Maine Yankee Classifications

-- Page: 3 of 8 Rev. No.: 3 Date: 6/1/86

2. Small spare parts having no traceability, such as commercial off-the shelf items, may be purchased as non-safety-related and then accepted for use in equipment requiring Quality Assurance. Examples l of such items are resistors, capacitors, switches, indicators, coils, wire, connectors, solid state devices and miscellaneous '

hardware.

IV. MECHANICAL SYSTEMS AND COMPONENTS Mechanical systems and components have been nuclear safety classified in accordance with ANSI Standard N18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants". .

Instruments, controls, motors, sensors,-etc. associated with the nuclear safety classified components which assist the components in performing a

• safety function are in the same safety class as the component to which ,

they are associated except as noted in Section II above. l Corresponding component supports that provide a safety function are in

. the same safety class as the components for which they provide support.

Component safety class designations are listed in the attached Table C.1 V. OTHER ITEMS REOUIRING OUALITY ASSURANCE Items which require a degree of quality between non-nuclear safety class, and IE or safety class 1, 2 or 3, shall be designated as QA related. QA Related Materials and components shall be in compliance with those parts of the QA program necessary to achieve the desired intermediate level of quality. A list of QA related items follows:

1. Fuel Assemblies

2. Boric Acid

3. Diesel Fuel Oil

4. Weld Rod ,

5. Chemicals

a. Lithium Hydroxide

b. Hydrogen

c. Nitrogen

d. Morpholine

e. Hydrazine

f. Resins -

6. Reagents

a. Those reagents used in performance of analyses required by Technical Specifications.

0329A-RRL

d

Title:

Anoendix C. Maine Yankee Classifications

.. Page: 4 of 8

_Rev. No.: 3 Date: 6/1/86

7. Packaging of radioactive material for transport. (As required by 10CFR71)

8. Control Element assemblies

9. Core Support structure

10. Structures (Seismic only)*

a. Primary Auxiliary Building (PAB)

b. Fuel Building

c. Service Building

d. Containment Spray Building

• Limited to the portion of each structure designed to safely resist hypothetical earthquake loads.

11. Fire protection for safety related areas per YA-GEN-9 -

+

w 0329A-RRL

e

Title:

Anoendix C. Maine Yankee Classifications

. .. Page: 5 of 8 Rev. No.: 3 Date: 6/1/86 TABLE C.1 (Sheet 1 of 4)

HECHANICAL SYSTEMS AND COMPONENTS CLASSIFICATION LIST SAFETY COMPONENT CLASS Reactor Coolant' System Reactor Vessel 1 Full Length Control Rod Drive Mechanism Housing 1 ,

Part Length Control Rod Drive Mechanism Housing 1 Steam Generator (tube side) 1 (shell side) 2 Pressurizer i Reactor Coolant Piping and Fittings 1 Reactor Coolant Surge Pipe and Fittings 1 Pressurizer Safety Valves 1

. Pressurizer Relief Valves 1 Valves to Reactor Coolant System Boundary 1 Reactor Coolant Pump Casing and Cover 1 Feedwater System Emergency Feedwater. Piping and Valves 3 Emergency Feedwater Pumps 3 Demineralized Hater Storage Tank 3 Feedwater Piping (inside containment and outside containment to feed REG Isolation Valve) 2 Auxiliary Feedwater Piping and Valves 3 Auxiliary Feedwater Pumps 3 Service Water System Service Water Pumps -

3 Valves and Piping 3 Containment Sorav System Spray Chemical Addition Tank 2 Containment Spray Pumps 2 0329A-RRL

.O

~ \

c l

Title:

Anoendix C. Maine Yankee Classifications Page: 6 of 8

, _ . .Rev. No.: 3 Date: 6/1/86 TABLE C.1 (Sheet 2 of 4)

SAFETY CLASS COMPONENT ,

Chemical and Volume Control System Regenerative Heat Exchanger 2 Letdown Heat Exchanger (tube side) 2 '

(shell side) 2 -

Reactor Coolant Purification Demineralizers 2 Reactor Coolant Filter 2 Charging Pumps Centrifugal 2 Auxiliary Charging Pump 2 Seal Water Supply Filters 2 Seal Hater Return Filter 2 Seal Hater Heat Exchanger (tube side) 3 (shell side) 3 Boric Acid Storage Tank 3 Boric Acid Transfer Pumps 3 Boric Acid Filter 3 Boric Acid Mix Tank 3 Volume Control Tink 2 Letdown Flow Control Valves 2 Safety Iniection System Refueling Hater Storage Tank 2 Safety Injection Tanks 2 Low Pressure Safety Injection Pumps 2 Residual Heat Removal System Residual Heat Exchangers (tube side) 2 (shell side) 3 Radioactive Gaseous Haste System Haste Gas Compressor 3 Haste Gas Surge Tank 3 Gas Decay Drums 3 0329A-RRL

o-io o

Title:

Anoendix C. Maine Yankee Classifications

_ _ Page: 7 of 8 Rev. No.: 3 Date: 6/1/86 TABLE C.1 (Slieet 3 of 4) .

SAFETY CLASS COMPONENT Comoonent Coolina Water System Component Cooling Water Pump 3 Component Cooling Water Surge Tank 3 .

Component Cooling Hater Heat Exchangers 3 -

Main Steam System Main Steam Piping (from Steam Generator up to and including non-return valves) 2 Safety Valves 2 Atmospheric Dump Valve 2 Steam Generator Blowdown System Piping (up to and incl,uding isolation valve) 2 Emergency Diesel Generator System Diesel Fuel Day Tank 3 Diesel Generator Air Tanks 3 Diesel Engines , 3 Diesel Fuel Oil Transfer System 3 Startina Air System

\

Air Tanks \ 3 Piping and Fittings 3 Valves \ 3 Filters 3 0329A-RRL

---e . - - . . - - - ,. , _,- ,- .--,,--- - ,._ -- - . , . - - . ...-------r - - - - . . - . - -,.-,,,..---,_.n, _-,

E

Title:

Accendix C. Maine Yankee Classifications

_ _ Page: 8 of 8 Rev. No.: 3 Date: 6/1/86 TABLE C.1 (Sheet 4 of 4)

SAFETY CLASS COMPONENT Soent Fuel Pool Coolina and Cleanuo System Spent Fuel Pool Pump 3 Spent Fuel Pool Heat Exchanger 3 Spent Fuel Pool Cooling Loop Valves 3 Spent Fuel Pool Cooling Loop Piping 3 Handlina Eauioment for Fuel and Reactor Vessel Internals Fuel Transfer Tube Outer Sleeve 2 Expansion Joints 2 Fuel Transfer Tube and Flange 2 Eauioment Drainace System High Pressure Drain Cooler 2 Primary Drain Tank 3 Primary Drains Degasifier 3 Primary Drain Pumps 3 Hydroaen Recombiner Taos Piping 3 Valves 3 Ventilation Filter Systems Primary Auxiliary Building Haste Gas Filter System 3 Spent Fuel Pool Deep Bed Filter System 3 Control Room Breathing Air System 3 Control Room Recirculating Air System 3 0329A-RRL

..