ML20010E178

Operational QA Plan,Revision 9

ML20010E178
Person / Time
Site:	Three Mile Island
Issue date:	05/28/1981
From:	Herbein J, Hukill H, Kayanas N METROPOLITAN EDISON CO.
To:
Shared Package
ML20010E173	List: ML20010E172 ML20010E178
References
NUDOCS 8109030173
Download: ML20010E178 (30)

Text

_ _ . . .- .

4 OPERATIONAL Qa PLAN Tne Metropolitan Edison Company GPU Nuclear Corporation Three Mile Isiano REVISION 9 MAY 28, 1981 ,

l b  % Ao Director - Quaiitt/ Assurance O -

Vice Presioent - NUCiedr /VQ8'PfsSfoent - IMI Unit i A s,su ranc e

? M h~ ,

i Vice Presioent - Tecnnicai Vice PrUioen t-sorninis tration j Functions l

h Vi M m

resicent - Waciciogicai

.. /

Vice Presige t - Maintenance l anc Environmental Controi and Cons */ru ion r ,

Ib.0hwL O f fice of tae Presioent - GPUNC NON-CONTROLLED

g This Document Will Not Be Kept j Up .To DMe 1

8109030173 810831 PDR ADOCK 05000289 p PDR

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

STATEMENT OF POLICY AND AUTdORITY It is the policy of the Metropolitan Edison Company to operate the Three Mile Island Nuclear Station so as to ensure the safety and health of the public and personnel on site.

It is also the policy of the Metropolitan Edison Company to comply with the requirements of the Code of Federal Regulations, the NRC Operating ,

Licenses and the applicable codes, guides and standards with respect to op ration, inservice inspection, refueling, maintenance, procurement, repair and modification of the Station.

The operation and management responsibility for TMI-Unit 1 is being implemented for Metropolitan Edison Company by the General Public Utilities Nuclear group (GPUN) which is responsible for all aspects of operations, design, procurement and modification of TMI-Unit 1.

The Executive Office of GPUN, and in particular the Chief Operating Executive - GPUN, has the responsibility and the authority to implenent the Quality As surance Program.

The Director - Nuclear Assurance reports directly to the Chief Operating Executive - GPUN and provides, by way of the Quality Assurance Department, '

the staf f necessary to develop and maintain the Quality Assurance Program consistent with the applicable Federal and State requirements and to verify

() the implementation of the Program.

The Director - Quality Assurance, who reports directly to the Director -

Nuclear Assurance, has the overall authority and organizational f reedom to identify quality assurance or management and control problems and provide recommended solutions. This authority and responsibility includes stop work authority in activitie, associated with operation, maintenance, repair, modification, refueling and manufacturing at or for TMI-Unit 1. With regard to the stoppage of work, including the recommendation that the operating

nuclear unit be shut down, the Director - Quality Assurance has direct i access to the Vice President TMI-Unit 1 and the Office of the Chief L Operating Executive - GPUN. The Director - Quality Assurance shall use this path when dif ferences of opinion regarding quality arise within GPUN.

The ef fectiveness of any Quality Assurance Program is dependent upon the individuals who implement the program. Ac c o rd ing ly , all personnel of the General Public Utilities System and their contractors mast comply with the l requirements of this Quality Assurance Program. All . embers of the t

management must give full support to maintalaing ca effective quality program as defined in this Plan.

I l

i i

i O

O

- ~

l The Quality Assurance Program, as described in this Plan, is approved for implementation at TMI-Unir 1.

l i

(

l l

C 28 ni I Date '

d ,sx N c. / 6 8bn Pfesident,A Metropoli1ran Fdison

$ 38 '{? .- S 2$ 8{

, Da t'e Chief Ophr'a+ing Executive  ; GPU Nuclear l

(

l l

t O

l 1

l l

t t

l 0

I TABLE OF CONTENTS O

Statement of Policy and Authority Introduction 1.0 Organization 2.0 Quality Assurt. ice Program 3.0 Control of Documents and Records 3.1 Instruction, o rocedures and Drawings 3.2 Document Control 3.3 Quality Assurance Records

't . 0 Design Control 5.0 Procurement and Material Control 5.1 Control of Procurement 5.2 '

Identification and Control of Materials Parts and Components 6.0 Control of Station Activities 6.1 Policy 6.2 Requirements 6.2.1 Details 6.2.1.1 Control of Inspection 6.2.1.2 Plant QA Monitoring 6.2.1.3 Control of Special Processes 6.2.1.4 Test Control 6.2.1.5 Control of Measuring i Test Equipment 6.2.1.6 Handling, Storage and Shipping 6.2.1.7 Inspection, Test & Operating Status O Rev. 3

1 I  !

l 6.2.1.3 Housekeeping and Cleanliness j 6.2.1.9 Equipment Control 6.2.1.10 Control o f Construction, Maintenance

( Pre ven t ive/ Co r rec t ive) , and Modifi-s cations '

4 6.2.1.11 Procedural Requirements

! 6.2.1.12 Control of Surveillance Testing and

. Inspection 6.2.1.13 Radiation Control  ;

! 6.3 Responsioilities 7.0 Control of Radioactive wastes i

8.0 Control of Corrective Actions and Nonconformances i

! 9.0 Audits l Appendices:

Appendix A '

Comparison Cnart of Quality Assur- 6 ance Plan Requirements with those of lll various parts of the Code of Federal Regulations and Nuclear Industry Standards Appendix 3 Minimum Document Control Responsi-bility for "Important to Safety" Documents Appendix C NRC Regulatory Guide Commitments and Exceptions Appendix 0 Definitions O Rev. 9 i

OPERATIONAL QA PLAN Introduction This Quality Assurance Plan is formatted in such a manner to provide all users with a functionally workable docu-ment. It is structured to describe how the Quality Assur-ance Program is to be functionally implemented with due regard to the safety and nealth of the public and the personnel onsite. The plan contains a description of the organizations responsible for the implementation of the Quality Assurance Program (Section 1) and an overall des-cription of tne Program (Section 2). The remaining sec-tions are structurea in a functional manner.

The requirements for administrative controls are generic and apply to all subsequent sections. Control of docu-ments and records are contained in Section 3.0; control of design is contained in Section 4.0; control of materials and services including procurement is contained in Section 5.0.

Sections 6.0 and 7.0 contain the program requirements for tnose direct and supportive activities associated with the operation and safety of tne plant; construction and/or modifications associated with corrective maintenance, '

plant improvement, and/or repair; and tne processing and

[

() transportation of radioactive wastes. Specific require-ments sucn as control of measurement and test equipment, inspection, special processes, test control, ano status rf

. inspecticas, tests ano operations are included therein, i

Sections 3.0 and 9.0 again apply to all functions covered l

by tne scope o f tnis Quality Assurance Program. Section 8.0 addresses the identification anc disposition of non-conformances associated with all aspects of tne program.

In addition, this section contains the management controls i

provided for evaluating collectively all nonconformances and determining unat corrective actions should be taken to precluoe tneir recurrence. Section 9.0 contains the requirements and administrative controls applicable to audits. Appendices A, B, and C contain additional Quality Program requirements associated witn the functional areas discussed in the plan. Appendix 0 cont.ains oefinitions o f terms used throughout the plan.

l /~ Rev. S l t.}-

l.0 Oroanization 1.1 Policy It is the policy of GPU Nuclear Corporation (GPUNC) to operate Three Mile Island Unit 1 so as to ensure tne safety and health of the public and the personnel on site. To imple-ment this policy GPUNC will meet the quality assurance requirements of corporate policies, the Nuclear Regulatory Commission as presented in 10 CFR 50, Appendix B, and otner applicable regulatory guides, codes, and standards perti-nent to operation of Three Mile Island Unit 1.

Therefore GPUNC has authorized tne establish-ment of a formal and comprehensive Quality Assurance Program for TMI Unit 1 operation.

The Program, which is described in the follow-ing sections, shall be imolemented in docu-mented approved policies, procedures and instructions which comply with this Plan.

1.2 Resoonsibilities The structure of tne organizations responsible for the operation, maintenance, modification, t repair, inservice inspection and refueling of

() the TMI Nuclear Station is illustrated in Figure 1. The organization chart illustrates the interfaces between the various departments and identifies those functions normally located on site and off site.

1.2.1 President-Met-Ed As tne chief operating of ficer, tne President Met-Ed is ultimately responsible for the safe operation o f tne plant and for QA commitments to the Nuclear Regulatory Commission for Unit 1 operation. The responsibility and authority for assuring that the conduct o f those activi-ties affecting quality are performed in a man-ner consistent witn tnis Quality Assurance Program is delegated to the President-GPUNC.

1.2.2 President - GPUNC The President - GPUNC has the overall respon-sibility for the estaolisnment, implementation and ef fectiveness of tne TMI Unit 1 Opera-tional Quality Assurance Program. This O

I-l Rev. 9

responsibility is administered through his management staf f including:

Executive Vice President - GPUNC Vice President - TMI unit 1 Vice President - Technical Functions Vice President - Nuclear Assurance Vice President - Administration Vice President - Radiological and Environmental Controls Vice President - Maintenance and Construction i

1.2.3 Executive Vice President - GPUNC Tne Executive Vice President-GPUNC reports directly to the President-GPUNC and shares in tne duties and responsibilities o f the O f fice o f the President.

1.2.4 Office of tne President The President and the Executive Vice President constitute the Of fice of the President. The tro officers work in close cooperation and

s. are the executive duties of GPUNC. As used $

in this Plan, the Office of the President

{>g means either the President or the Executive Vice President.

1.2.5 Vice President - TMI Unit 1 The Vice President - TMI Unit 1 reports directly to the Of fice of tne President. He is responciale to operate and maintain the TMI-l plant in a safe, reliable and efficient manner in accordance with corporate policies and all applicable laws, regulations, licenses I and technical requirements. Tne Vice-i President-TMI-1 is responsiole for the follow-ing major functions.

a. Establish and maintain plant level l policies, procedures, standards and practices related to the operation and maintenance of the plant.

l b. Provide and maintain a plant staff t qualified to operate and maintain the plant in accordance with corporate policies and all aoplicable laws, regulations, licenses and technical requirements.

O i I-2 'ev.

. 9 t

i I _ _ , . - - __ _ _ . . , - ,,________ _ - _ . , .

_, . , ,,_m...._. . _ _ _

_..,._m__ , _ , . -

c. Operate the plant in a safe, reliable,

()

and efficient manner in accordance with corporate procedures, the electrical needs of tne GPU System, all applicable laws, regulations, licenses and tech-nical requirements.

d. Establish and implement preventative and corrective maintenance programs to maintain TMI-l in a safe, reliable and efficient manner in accordance with corporate policies and all applicable laws, regulations, licenses and tech-nical requirements.

e. Ensure tnat plant operations and main-tenance activities are carried out in accordance with Corporate Radiological Control, Quality Assurance, Security and Emergency Prepardness Programs.

The Vice President - TMI Unit 1 gives his full support to the quality assurance requirements set forth in this Operational Quality Assur-ance Plan, assuring compliance to the fullest degree by his staff. '

(') 1.2.5.1 Plant Encineerino Director - TMI Unit 1 The Plant Engineering Director reports directly to the Vice-President TMI Unit 1 and is responsiale for maintair,ing technical liaison and cootdination between operating personnel and the technical support engineer-ing staff. In addition, the Plant Engineering Director is responsible for in-plant engineer-ing support in the nuclear, mechanical, instrumentation and control, and electrical engineering areas,

a. Provide day-to-day engineeririg and technical support to plant operations and maintenance,

b. Prepare or assist in preparation and review o f plant operation, emergency, maintenance, alarm, and surveillance procedures.

c. Conduct operations experience assess-ment and problem investigations.

O I-3 Rev. 9

I l

d. Prepare spare parts specification and

(~) assis* in procurement.

\~/

e. Develop, implement and insure com-pliance with the fire protection program.

f. Develop, implement and insure com-pliance with the plant chemistry program.

g. Provide day-to-day incore fuel managment,

h. Coordinates with and requests technical support, as needed, from Technical Functions Dept.

i. Initiates investigation, responses and corrective actions as required by regulatory correspondence.

1.2.5.2 Goerations and Maintenance Director TMI Unit 1 The Operations anc Maintenance Director - TMI Unit 1 reports directly to the Vice-President '

Unit 1 and is responsible for the day-to-day f) operation of Unit 1. He will have a Shift

'/ Supervisor directing the operations of each snift thro'Jh the Control Room Operators and Auxiliary ,perators. A maintenance force under the direction of a Supervisor-Maintenance, covering the areas of electrical, mechanical and instrument control maintenance and surveillance, will also report to the Director. Additionally, the Operations and Maintenance Director - TMI Unit 1 nas respon-sibility for the coordination of start-up and test evaluations and responsibility for administrative control o f the training of Unit 1 personnel. He is responsible for the following major functions:

a. Conduct plant operations and mainte-nance activities to provide maximum capability in a manner consistent with license, regulatory, and corporate requirements.

O I-A Rev. 9

1

! b. Direct the implementation of preventa-() tive and corrective maintenance program including the prioritization to assure the plant is maintained in a safe, efficient and reliaole manner.

c. Direct the operation of the Radioactive I

Waste facility including the conduct of the Radioactive Material Handling and Shipment programs.

d. Coor;inate with plant maintenance, technical support, administrative, radiological control to assure proper

- support and control of activities with respect to plant operations is achieved.

1.2.5.3 Manaaer-Plant administr3 tion TMI 1 The Manager - Plant Administration reports directly to the Vice-President TMI-l and is responsible to plan and coordinate with the

administration division day-to-day activities l in the areas of Personnel, Sudgets/ Cost Control, Security, Facilities, Procedure '

j Control and General Aoministrative Functions.

He is responsible for the following major functions:

a. Day to day coordination with human resources, budgets, safety, security and facilities activities.

b. Assist Vice President TMI 1 in staff planning, corresp ndence, and scheduling.

c. Preparation o f inputs for Board of Directors and other corporate level reports.

1.2.6 Vice President-Tecnnical Functions The Vice President-Technical Functions repcrts directly to the O f fice of tne Presicent. He is responsicle to assure technical and regu-latory adequacy of all aspects of nuclear activities to orovide safe, reliable, and l efficient ooerations in accordance with cor-I parate pol;cies and all applicable laws, ragulations, licenses and technical require-ments. The Vice President-Technical Functions is responsiole for tne following major I functions:

I-5 Rev. 9

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

a. Perform, manage and direct all out-of-() plant engineering, design, safety analysis; and plan and direct startup and test activities.

b. Develop all plant technical basis and configuration control documents in-cluding fuel management.

c. Control and perform interface activi-ties with regulatory groups.

d. Perform plant technical monitoring /

assessment / productivity analysis, in-cluding major equipment failure analysis.

e. Prepare / review / concur with all engineering and licensing procedures and licensing document correspondence and prepare SAR's, Technical Specifica-tions and Environmental 5,a^ifications.

f. Specify, manage, and direct all nuclear fuel material, conversion, enrichment and fabrication contractors. '

() g. Review and assess the safety signifi-cance of NR,C notices, bulletins, and reports and of plant operating ex-perience information.

h. Provice and direct operating plant snift technical advisors.

i. Review and concur in appropriate plant operating, alarm and emergency ,

procedures for tecnnical adequacy.

l j. Define technical requirements for l training programs.

k. Plan / direct e'l 'tartup and test activities.

The Vice President-Technical' Functions and his staff give full support to the TMI Operational Quality Assurance Program described herein, thereby assuring that all work performed under O

I-6 Rev. 9 I

I

their cognizance will conform to and support the requirements o f the Plan.

(])

1.2.6.1 Director-Engineering and Design The Director-Engineering and Design is respon-sible for providing technical support for the operations o f the TMI Nuclear Station. He will assure the maintenance of technical capability in the various disciplines, such as mechanical, civil, electrical and instrumenta-tion, and engineering mechanics. Tne depart-ment will review, and where appropriate, approve the work O f Architect / Engineering Organizations, and will perform casic engineering and design for modifications. The department has capabilities in the following functional areas:

a. Provide design drawings and specifica-

! tions in support of plant modifications.

i D. Maintain central GPU technical capa-bilities in disciplines assigned to the department.

i

c. Perform all GPUN design / drafting.

O d. Investigate plant system and equipment failures, retain cognizance over tecn-nical performance of plant hardware,

e. Provice technical functions review /

concurrences of maintenance programs /

procedures as appropriate.

f. Provide technical functions review /

approval of work performed by outside engineering firms.

l

g. Support plant outages within overall GPUN priorities.

n. Perform GPUN engineering in suoport of design within technical disciplines assigned to tne department.

1. Prepare plant as-ouilt drawings within configuration control guidelines estaolished by Engineering Services.

J. Provide fire protection analysis, s

I-7 Rev. 9

Additionally, he is responsible for the fl identification and classification of items and

activities important to safety, and the development and control of the Quality Classi-fication List.

1.2.6.2 Director-Systems Encineering Tne Director-Systems Engineering is respon-sible for technical support in the areas of nuclear fuel management, process computer, control and safety analysis, and plant operational analysis. His department provides capaci11 ties in the following functional areas:

a. Analyze overall GPU Nuclear plant teCn-nical performance, review industry plant data, and advise plant director and others of status and potential proolems.

b. Provide all nuclear fuels, fuel manage-ment strategies, and basic core physics capaoility.

c. Se a principal contributor to and '

coordinate the review of, operating,

(')

alarm, and emergency procedures; and tne tecnnical content of training programs,

d. Provide technical expertise in risk analysis, numan factors engineering, radiological engineering, and plant dynamics and simulation,

e. Staff, operation, program, and upgrade i o f plant process computers, i

j f. Staff and direct STA's.

1.2.6.3 Director-Engineering Projects Tne Director-Engineering Projects is respon-sible for the coordination, staffing and directing of engineering crojects that are assigned by the Vice President-Technical Func-tions. These activities will vary, depending on tne scope and purpose of the assigned pro-ject. These responsibilites generally include oroviding tne technical support necessary for a study, an evaluation or a modification and include the coordination of the l

O l

l I-8 Rev. 9

Departments within Technical Functions with

(} tnose o f the plant staff. Major functions of the Director-Engineering Projects are as follows:

a. Manage, coordinate, or direct the engineering effort required for any nuclear station physical plant modifi-cation, addition, or major non-routine repairs.

b. Manage, coordinate, or direct, as appropriate, engineering studies or evaluations,

c. Provide on-site Coordination of tech-nical functions division personnel and activities (except fulltime, on-site functional personnel directly support-ing operations, i.e., computers, STA's, plant analysis, licensing),

d. Recommend and function in accordance with approved priorities for engineer-ing projects.

i 1.2.6.4 Director - Licensino and Reoulatory Affairs

( Tne Director - Licensing and Regulatory l

l Af fairs reports directly to the Vice-President

- Technical Functions. He is responsible for i the following major functions:

i a. Provide the principal interface with regulatory agencies interfacing with GPU nuclear and manage GPU nuclear participation in licensing hearings.

i

b. Obtatn all licenses and permits for l nuclear facilities: Federal, State, j and local.

c. Prepare ano coordinate responses to I regulatory agencies including NRC I&E l bulletins, circulars, notices and l inspections.

d. Provide licensing guioance and inter-pretation for all aspects of GPU l nuclear regulated activities including the coordination with legal counsel, as necessary.

l

()

1 l I-9 Rev. 9

e. Maintain long-range involvement in

(]

regulatory affairs, Federal and State register review, trade associations, and owners' groups, and assess evolving licensing requirements and risks (cur-rent and future).

f. Provice systems for control of licens-ing basis documents-tecnnical specifi-cations, SAR's, regulatory guides, standard review plans.

g. Negotiate, within limits established by management, with regulatory agencies on requirements, schedules, or commitments.

h. Coordinate the evaluation and reporting of responsiole items under technical specifications, NPDES permits, 10CFR21, 10CFR50.55(e), or other regulations or licenses.

i. Prepare, coordinate, submit comments to industry or regulatory groups on pro-posed legislation and regulations; establish and maintain contacts with 5 Federal, State, and local regulatory agencies.

(~J)

J. Provide principal interface with NRC's inspection and enforcement inspector, resident inspectors, and industry agencies. Resolve issues in apparent conflic t with licensing or permit docu-ments or GPU nuclear licensing positions.

1.2.6.5 Manaoer - Enoineerino Services The Manager - Engineering Services is respon-I sicle to provide the engineering and manage-l ment tools and systems to the Technical Func-tions Division to permit efficiency of operations. Additionally, ne orovides the interface between the Technical Functions administrative systems and those within GPU l Nuclear. He is responsible for the following major functions:

a. Prepare and cooroinate all engineering and licensing proceoures and standar's.

I-10 Rev. 9 l

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

j 1 b. Analyze technical functions work l

(]) methods and systems.

c. Provide basic engineering data files.

l d. Provide technical docJment release system and configuratier control methods.

i' l.2.6.6 Director - Startuo and Test The Director - Startup and Test is responsible to provide and to perform a startup and test function for GPU Nuclear to assure that '.ew or substantially modified plants, facilities and systems are systematically tested, documented to conform with technical requirements and j turned over to plant operations. His respon-i sibilities include:

l

a. Prepare test plans and implementing procedures.

b. Direct testing, ensure operations, and other supporting personnel have l required special training and skills. *

({) c. Incare preparation o f test documenta-tioi., review and compile same for turn-over to operations.

d. Coordinate technical acceptance of

testing.

e. Provide and obtain operations review of design engineering of plant modifications.

3 1.2.7 Vice President - Nuclear Assurance i

The Vice President-Nuclear Assurance, reports j directly to the Of fice of the President. He l is responsiDie to monitor all safety-related i activities to assure that they provide the required high degree of safety and reliability and are carried out in accordance with corporate policies and all applicable laws, regulations, licenses, and tecnnical require-

! ments. The Vice President-Nuclear Assurance l 1s responsible for the following major functions:

(:)

I-11 Rev. 9 1

l,~..., .- -.-- - . --,-, , ,---.-,, , ,,- - -.r..,,, - - - .-,- , - - -, - - - n ~ ~~ - - - , - - -

_- __ - . . - . _ - -. ___ - = = __ _

l 1

a. Monitor, evaluate, and assure that all

<p activities having the potential for

' v compromising nuclear safety are adequately addressed.

b. Provide and maintain the qualified personnel to develop and administer the

! Operational Quality Assurance Program and assure that it is implemented in all activities important to safety.

c. Develop and implement all necessary general employee, operator, technician l and management training programs.

) d. Develop the site emergency plans and 1 assure that emergency preparedness is maintained.

e. Provide chemistry and metallurgical analytical services and recommended enemistry requirements and specifications.

l

! The Vice President-Nuclear Assurance gives his

full support to the quality assurance require- t ments set forth in this Operational Quality Assurance Plan, assuring compliance to the

(]) fullest degree by his staff.

The Vice President-Nuclear Assurance utilizes the following management staff members in carrying out his responsibilities:

Director - Quality Assurance Director - Training and Education Nuclear Safety Assessment Director

Manager - Emergency Preparedness

! 1.2.7.1 Director - Quality Assurance (Figure 2)

.i The Director-Quality Assurance Department (QAD) nas tne functional authority, indepen-dence and responsibility to verify the effec-I tive implementation o f the administrative controls and compliance to the Quality Assurance Program during the operational phase of TMI Nuclear Station. The Director of QAD a reports directly to the Vice President-Nuclear

!O I-12 Rev. 9

Assurance. Additionally, he has direct unencumbered access to the Office of the President, and the Vice President-TMI Unit 1

() with regard to quality activities.

i This reporting relationship has been estab-lished to provide the Quality Assurance organization with sufficient independence from the influence of costs and schedules to be able to effectively assure conformance to Operational Quality Assurance Program require- <

ments. Figure 2 identifies the Quality Assur-ance Department organizational elements which function under the Quality Assurance Program.

The Director-QAD has no duties or responsi-D111 ties unrelateo to Quality Assurance. He has the authority and responsibility:

1. To develop and administer QA plans and procedures required to assure that all <

GPU nuclear activities pro.vice the j

i required high degree of safety and reliability.

2. To monitor and evaluate activities of GPUN to assure that they provide tne required high degree of safety and i reliability and are carried out in i

() accordance with all applicable laws, regulations, licenses, corporate policies and other requirements.

3. To identify quality problems, and initiate, recommend or provide solu-tions through oesignated channels ann to verify implementation of resolutions.

l i

4 To perform evaluations on a planned and periodic basis to verify that the Quality Assurance Program is Deing effectively implemented.

5. To stop work on non-conforming ,

materials or activities if:

a. it is the only process available to protect the health and safety of I

the puolic and/or plant personnel

b. Its continuance will require significant rework or repair to backfit corrective action O

1-13 Rev. 9 l

i l - -- _

- = _ - _ _ , _ _ _ - _ _ _ . . - _ _ _ __ _ _ _ _ _ _ __ _ _ _ _ _ _ _

i 4

l c. Its continuance may jeoparcize nuclear safety j

(])

! '. Its repetitive frilure to comply

, with program controls constitutes a i significant QA program ceficiency.

t l 6. To initiate unit shutdoun recommenda-l tions unen warranted by a safety

concern.

J l The major functions of tne Director-QAD, in-clude the following:

a. Develop tne plans and procedures neces-sary to fulfill GPUN QA responsi-

! bilities.

! o. Provide for the monitoring and evalua-I tion of the implementation and l effectiveness of the GPUN QA program by l l

means o f,  ;

I r l Review durveillance  !

Survey Monitoring l Audit Inspection i j

{

.l J

() of all organizations, contractors, and vendors for all important to safety l

I activities. l

! c. Stop work or furtner processing, I celivery, or installation or take otner i warrantec actions on non-conforming materials or activities.

d. Initiate unit shutdown recommendations I

unen warranted oy a safety concern and l

! obtain unit shutdown witn appropriate  !

upper management concurrence.

{

I i e. Provide for tne review and acceptance

of contractor and vendor Quality Assur-

ance Programs witnin the scope of tne Quality Assurance Program.

f. Provide for tne review and acceptance i of procedures prepared by other than QA l l organizations within t1e scope of tne l Quality Assurance Program.

j f

f

! C)

J I-14 Rev. 9

}

i i

g. Direct and manage the Quality Assurance

() Department.

h. Provide a working interface and line of communucation uith otner divisions and other appropriate industry and regu-latory groups for all QA matters.

1. Establish witn Training and Education the scope and content of an indoctrina-tion and training program for QA and CC personnel.

J. Assure QA indoctrination of aporopriate personnel outside of the QA organiza-l tion is provided.

i

k. Issue periodic reports to the Office of the President and appropriate Unit Vice-Presidents on tne status of quality activities.

1. Immediately notify tne Of fice of tne President and anpropriate Unit Vice President of any significant, quality related proolem or deficiency.  !

() m. Provide for QA review and acceptance of design and engineering documents.

n. Provide for QA review and acceptance of procurement documents witnin the scope of the QA program.

o. Provide for and maintain QA records generated by QAD until turnover to document control for storage.

1.2.7.l(a) Manaaer-Quality Assurance Desian and Procurement The Manager-Quality Assurance Design ano Pro-curement is responsiole:

3. To review and approve contractor and vendor quality programs for those supplying safety-related services or items.

D. To report quality trends to tne Director-QA and to tne cognizant pur-cnasing or contract manager.

O I-15 Rev. 9

c. To review and accept design control O procedures prepared oy other orgroiza-tions when these procedures contlol or exercise an effect upon safety-related systems, components, or activities.

d. To perform the neccssary post-award quality related activities, including post-award surveys and source surveil-lance, in compliance with the OCNGS Quality Assurance Program.

e. To coordinate with the TMI QA Modifica-tions/ Operations Section to assure that documentation o f the manuf acturing dis- [

crepancies are availaole to tne receiv-ing inspectors and cognizant purenasing or contract manager.

f. To identify quality problems and to initiate, recommend, or provide solu-tions tnrougn designated channels and to verify implementation o f the resolutions.

i 1.2.7.1(o) Manaaer-Quality Assurance Modifications / '

Goerations O The Manager-Quality Assurance Modifications /

Operations is responsible

a.

To monitor the implementation and effectiveness of tne Quality Assurance Program on site.

b. To establish adequate site monitoring and inspection programs necessary to verify conformance to Quality Assurance Program requirements.

c. To coordinate and direct QA activities at the TMI Nuclear Station.

d. To review site procedures from a QA standpoint.

e. To provide nondestructive examination support for TNI.

l f. To notify appropriate station manage-ment and the Director of Quality Assur-ance immediately of any condition tnat warrants operational shutdown cf the O unit as defined in the appropriate QAD procedures.

I-16 Rev. 9

g. To identify quality proolems and to O initiate, recommend, or provide solu-tions through designated cnannels and to verify implementation of the resolutions.

He reports directly to the Director of Quality Assurance and ne periodically reports on the implementation and ef fectiveness of tne Operational Quality Assurance Program to the Vice President - TMI Unit 1. He has the authority to stop work on all important to safety activities associated with the on site TMI Nuclear Station Operational QA Program.

The Manager TMI Quality Assurance Modifica-tions/ Operations is assisted in carrying out his responsibilities by an Operations Quality Assurance Manager, a Quality Control Manager, a Quality Assurance Systems Engineer and their associated staffs located on site.

1.2.7.l(c) Manacer-Procram Develooment and Audit The Manager-Program Development and Audit is responsible:

i

a. To coordinate develooment and main-() tenance of the Quality Assurance Plan and the QAD procedures.

c. To coordinate the oevelopment and administration of the Quality Assurance Department training and certification program.

c. To coordinate the Quality Assurance training and orientation provided for CPUNC and external organizations personnel.

d. To develop, implement, and maintain a comprenensive system of planned and periodic audits to verify compliance with all aspects of tne Quality Assurance Program,

e. To identify quality problems and to initiate, recommend or provide solu-tfons through designated channels and to verify implementation of tne resolu-tions.

O I-17 Rev. 9

)

The Manager-Program Development and Audit

() maintains a full-time staf f of quality assur-ance engineers and qualified quality auditors at both the corporate and site offices. The audit activities and the results of the audits are provided to the audited organization and to the Safety Review Groups who provide the independent management assessments of the significance of the audit findings and the effectiveness of the Quality Assurance Program.

1.2.7.1(d) Manaaer-Materials Technology The Manager-Materials Technology is responsible:

a. To direc and supervise the of f site GPU organizations which have the

responsibility for welding practices q and to establish the requirements for inservice inspection of piping and components, NDE, materials support, and materials evaluations.

l o. To develop and implement the ISI i program.

N

c. To provide welding engineering support.

d. To identify quality proolems and to initiate, recommend, or provide solu-tions througn designated channels and to verify implementation of the resolutions.

e. To provide support related to manu-facturing and systems materials technology problems.

The specific disciplines included in the Materials Technology section are:

1. Nondestructive Examination

2. Inservice Inspection

! 3. Materis'.s En'ineering

4. Welding Engineering

5. Metallurgical Analysis l

)

l I-18 Rev. 9 l

1 _

1.2.7.1.1 Minimum Qualifications of Quality Assurance

()

• Personnel The Director-Quality Assurance shall nave, as a minimum, a baccalaureate degree in Engineer-ing or Science, with at least five years of JA experience in nuclear power plant operations or supporting activities. Additionally, the Director-Quality Assurance must be knowledge-able in QA regulations, policies and standards.

The qualification requirements and experience levels for other key Quality Assurance person-nel are such as to assure competence commen-surate with the responsiollities of each cosi-tion. Quality managers and supervisory personnel are required to have a degree in Engineering or Science and experience in a position having responsibility fcr the per-formance of quality activities. The degree requirement may be waived for personnel with exceptional qualifications and a minimum of seven (7) years related experience.

1.2.7.2 Director-Trainino and Education The Director-Training and Education reports

(') directly to the Vice President - Nuclear Assurance and has the overall authority and responsioility for training, and tne system laboratory. These major functions include, but are not limited to:

a. Develop and implement all necessary general employee, operator, technician and management training programs.

o. Provide the generating statio- with chemistry and metallurical analytical services and recommended chemistry requirements and specifications.

1.2.7.2.1 Manaaer-System Lacoratory Tne Manager-System Laboratory is responsiole for the administration and operation of the l Environmental and Operational Chemistry l Analyses Section of the System Laboratory in l compliance witn the TMI Juality Assurance l Program. This section provides the centr 31-ized lacoratory analyses services for l

O l I-19 Rev. 9 l

[

P" TMI. The specific responsiollities of the O Manager--System Laboratory include the following:

a. Perform analysis of water and waste-water sanples submitted by the generat-ing staticn,

b. Prepare chemical Calibration standards for the labs at the generating stations,

c. Monitor the chemical analysis capa-bilities of the labs at the generating stations through audits and independent analysis o f samples,

d. Assist station personnel in unusual operations such as chemical cleaning,

e. Provide consultation on equipment startup and performance, as requested,

f. Perform enemical analysis of fuels, lubricants, insulating fluids and ion exchange resins, i

g. Ensure that the laboratory is

() adequately staf fed and tnat the lacoratory personnel are adequately trained and qualifi3d to perform their assigned tasks,

h. Ensure that the System Lacoratory meets the applicaole requirements o f the Quality Assurance Program,

i. Develop and implement laboratory pro-cedures covering the control of the laboratory activities and the records documenting the results o f the analysis.

J. Provide support to Materials Tecnnology regarding material specimen preparation and testing.

1.2.7.3 Nuclear Safety Assessment Director The Nuclear Safety Assessment Director is responsible for the development, direction and supervision of the Nuclear Safety Assessment Department. The function o f this group is to:

O I-10 Rev. 9

1. Identify problems in nuclear plant O desion, operations and maintenance which nave a potential for compromising overall safety of the nuclear plant, station personnel, or the general public.

2. Make recommendations for improvements and assure corrective actions are taken to resolve iJentified problem areas.

The Nuclear Safety Assessment Department (NSAO) will nave access to documents and reports including those identifying conditions adverse to quality (audit reports, nonconform-ance reports, surveillance / inspection reports, reportable occurrences, NRC inspections, etc.). NSAO will report, at intervals not to exceed six (6) months, the results o f their evaluations to the Of fice of the President and the Vice President-TMI Unit 1. NSAD serves as an independent of fice of ombudsman for all memoers of tne Corporation naving a concern for nuclear safety. Additionally, the Nuclear Safety Assessment Department, working with Systems Engineering, will evaluate tne opera- 5 tional experience of other nuclear power sta-tions to improve plant operational status and

(]) derive benefit from other stations experi-ence. The major functions of the Nuclear Safety Assessment Director are to:

a. Investigate, assess, and =',ommend action for administrative or functional controls required to assure overall safety.

t l b. Monitor and evaluate trends in activ-l ities having tne potential for compro-l mising overall saf ty.

c. Serve as an Of fice of Ombudsman for all members of GPUN naving a Concern for nuclear plant or personnel radiation safety.

d. Recommend and monitor the establishment l of additional controls, criteria, and/

or procedures whicn may be required to l control the design and operation of i

l nuclear plants in meeting safety con-l siderations.

)

I-21 Rev. 9 l

1

1.2.7.4 Manaaer-Emeroency Precaredness O -

Tne Manager-Emergency Preparedness is respon-sicle to assure that Oyster Creek and TMI Emergency Plans and Preparedness are in accordance with corporate policies and all applicable laws, regulation, licenses, an technical requirements. Additionally, ne is to provide support and guidance in the Emergency Planning area for the Tnree Mile Island and Oyster Creek Stations. The Manager-Emergency Preparedness is responsiale for the following major functions:

a. Coorcinate emergency planning Detween the Tnree Mile Island and Oyster Creek Stations.

b. Monitor, evaluate and assure both Tntee Mile Island and Oyster Cree < Stations nave emergency preparedness programs tnat are coordinated and maintained current, ano assure a high state of preparedness.

c. Assure that Three Mile Island and Oyster Creek Stations' Emergency Plans

() are consistent with the latest require-ments of the NRC and with the FEMA approved Pennsylvania and New Jersey state, and countj and local emergency plans.

d. Interface witn tne Nuclear Regulatory Commission, State and local authorities in emergency planning areas.

l e. Obtain, review, and comment on proposed l legislation, industry guidelines, and

! standards in the area of emergency l planning. Preparation and submittal of l comments will ce coordinared througn the Tecnnical Functions Division.

l 1.2.3 Vice oresioent - Administration The Vice President - Administration reports directly to the Of ice of the President. He is responsible to provide in an efficient and reliable manner and in accordance witn cor-porate policies and all applicable laws, rego-lations, licenses and other requirements, all O

I-22 Rev. 9

required ousiness management and administra-(]) tive support services for prudent conduct of the activities cf GPUNC. The Vice President-Administration is responsible for the follow-ing major functions:

a. Provide contracting and procurement, contract administration, warenousing and inventory control services to the plants anc Services divisions of the Corporation.

b. Develop and administer security and facilities services and industrial safety programs directed to creating a safe, convenient and protected environ-ment for GPU Nuclear employees and procerty,

c. Prepare, review, coordinate issuance and compliance monitoring of coroorate administrative policies, systems and procedures; providing Information Management anc Documentation Control services; and ootain and coordinate legal services in support of GPU '

Nuclear ooerations.

(

l He is assisted in the performance of these responsioilities at the site by indiviouals with assigned responsibility for security, procurement, warenousing, personnel, labor relations and facilities management.

The Vice President-Administration gives nis full support to tne quality assurance require-ments set fortn in this Operational Quality Assurance Plan, assuring compliance to tne fullest degree oy nis staff.

1.2.6.1 Director-Materials Manaoement Tne Director-Materials Management is respon-sicle to provide contract and procurement, I contract administration, warenousing and inventory control services to Oyster Creek and TMI and services divisions of CPU Nuclear Corporation. The Director-Materials Manage-i ment is responsible for the following major functions:

l l

)

I-23 Rev. 9 1

1

a. Source, bid, review quotations, negoti-O ate and award materials, equipment, fuels and service requirements for all plants and services divisions.

b. Administer and expedite performance under these contracts and purchase orders.

c. Receive, inspect, warehouse and issue ordered goods.

d. Maintain inventory levels of repetitively procured items at optimum 12/els.

1.2.3.2 Director-Security, Facilities, Industrial Safety ano Healtn Tne Director-Security, Facilities, Industrial Safety and Health is responsible to develop and administer security and facilities ser-vices and industrial safety programs directed toward creating a safe, convenient and pro-tected environment for GPU NucJ aar employees .

and property. He is responsiola for the '

following major functions:

a. Plant security guard force and sur-veillance systems and controls in-cluding physical security, physical barriers, access requirements, detec-tion aids, communications requirements, security equipment testing and main-tenance, response requirements, records and reports involves sucn activities as:

- Insure that the nuclear generatlng stations are adequately protected against acts of sabotage, arson, l tneft and civil disturoances.

I

- Develop and execute plans and pro-cedures for the anysical security of tr.e nuclear stations.

l

- Provide liaison to regulatory agencies. .

- Implement company and NRC rules and

( regulations.

()

l l I-24 Rev. 9

Screen all non-company employees and contractors far unescorted access to

() the facili~v.

- Provide access control through the use of security surveillance equipment.

- Provide physical access control and carrying out search requirements.

- Plans defenses for civil disturbances and demonstrations.

Investigate all security incidents.

b. Industrial safety systems, surveys and equipment, medical surveillance, first aid programs and training, and fire suppressant systems and standards, industrial safety systems and renula-tions. Policy, procedures and imple-mentation of OSHA, NIOSH and NFPA.

1.2.8.3 Director-Fiscal and Information Manacement The Director-Fiscal and Information Management is responsible for the following major O functions:

i

a. Implement and maintain New Information Systems: CBS, COMEC, A/P Systems, M&S t

i System, REM On-Line System, Purchasing System, Task Tracking, Personnel Track- ,

l ing, GMS/COMEC Inter f ace, Eng ineering Data System and CARIRS (Computer Assisted Records & Information Retrieval System).

b. Provide records management and document control at corporate and site informa-tion centers to meet corporate require-ments and satisfy applicable regulatory requirements.

l l

c. Establish and maintain GPU Nuclear administrative policies and procedures and monitor for control.

d. Provide interface requirements for con-trol to GPUSC Assistant Comptroller and l

i data center management interface for all requirements to GPUSC I.S. Division.

i ()

I-25 Rev. 9 i

e. Provide operations analysis for

(} corportte and plant operations.

f. Manage corporate and plant libraries as required.

g. Provide configuration control supoort.

1.2.9 Vice President-Radiological and Environmental Control The Vice President-Radiological and Environ-mental Control reports directly to the Office o f tne President. He is responsiole to estab-lish and implement uniform radiological and environmental policies, practices and pro-cedures required to assure safe, rellaole and efficient operation in accordance with corporate policies and all applicable laws, regulations, licenses and technical require-ments. The Vice President-Radiological and Environmental Controls is responsiole for the following major functions:

a. Establish and maintain corporate level policies, procedures, standards and '

practices relating to radiological anc

(]) environmental activities.

D. Provide the personnel, orocedures and administrative controls to implement the plant radiation and environmental protection programs.

c. Provide administrative and tecnoical guidance applicable to radiation pro-tection, radioactive materials, respiratory protection and radiological engineering including ALARA programs and dosimetry control.

d. Provide administrative and technical guidance applicable to environmental protection, environmental monitoring and NPDES.

I-26 Rev. 9

Tne Vice President-Radiological and Environ-nental Control gives his full support to the Q' quality assurance requirements set forth in this Quality Assurance Plan, assuring com-pliance to the fullest degree by his staf f.

1.2.9.1 Manacer-Radioloolcal Control - TMI Unit 1 The Manager-Radiological Control TMI-l reports directly to the Vice President-Radiological and Environmental Control. He is responsiole for the Unit 1 on site implementation of the radiological control and related progr.ims.

The Manager-Radiological Control is respon-sible for providing and maintaining up-to-date procedures controlling the activities of the department, providing adequate staf fs of trained personnel to perform the duties o f radiation protection, implementing the "as low as reasonably achievable" policy and making it a formal cart of the Radiation Protection Program. He is responsible for the following major functions:

a. Control external exposure through the i administration of a 00simetry Program.

O o. Control internal exposure through administration of a Respirator Protec-tion, Bioassay and dhole 3ody Counting Program.

c. Centrol radioactive contaminatirn.

d. Control radioacti fe materi'els.

e. Perform reviews of the Radiological Control Program,

f. Maintain procedures to ensure exposure to workers and the general population is as low as reasonaoly achievable.

g. Support normal plant operation and pro-vide additional support prior to, dur-ing and after outages.

h. Assure corporate compliancd with appro-priate Radiologi. cal Regulations and Licensing Requ.r!ments.

O I-27 Rev. 9

1.2.9.2 Radioloolcal Controls Director TMI-Unit 2 The Radiological Controls Director TMI-2 reports directly to the Vice President-Radiological and Environmental Control. He is responsible for the following major functions for both TMI-l and THI-2.

a. Train and qualify radiological tech-nician in Radiological Control Pro-cedures and techniques in TMI-2 and qualify radiological technicians in TMI-1. Approve radiological training of others.

b. Provide dosimetry program services for both TMI-1 and TMI-2.

c. Provide respirator protection, Dioas-say, and whole booy counting services for TMI-l and TMI-2.

d. Maintain and calibrate all radiological equipment used by the TMI-l and TMI-2 Radiological Controls Department. .

t 1.2.9.3 Manaaer-Environmental Control O The Manager-Environmental Control reports directly to the Vice President-Radiological and Environmental Control. He is responsible for the on site implementation of tne environ-mental control and related programs. His responsibilities include:

a. Perform Radiological Environmental Monitoring Programs to assess impact of radiological releases on surrounding populations.

b. Operate and maintain the meteorological towers.

c. Assess the impact of plant operation on terrestrial and aquatic life.

d. Monitor depth of water in adjacent rivers and bays to ensure sufficient cooling water and determine if naviga-bility has been affected oy plant operation.

O I-28 Re /. 9

e. Conduct other environmental mon'toring O and reportinq and assure corporate com-pliance with appropriate Environmental Regulations and Licensing requirements.

1.2.9.4 Coroorate Radiological Engineering Tne Senior Corporate Radiological Engineer reports directly to tne Vice President-Radiological and Environmental Controls. He is responsible for radiological reviews of proposed plant modifications to assure imple-mentation of the ALARA pn11osophy. He is respons1Dle for the following major functions:

a. ALARA reviews of proposed plant modifi-cations.

l

b. Assist in the performance of radio-logical audits at TMI or Oyster Creek as requested. '.

c. Provide radiological engineering support to other divisions of tne Nuclear Co rporation as required.

6

d. Provide radiological engineering

() support to the Radiological Control Departments at TMI or Oyster Creek as l

4aay be needed from time to time.

I 1.2.10 Vice President-Maintenance and Construction The Vice-President-Maintenance and Construc-l tion reports directly to the Of fice of the

! President. He is responsible to establish and

, monitor uniform policies, practices anc pro-l cedures for all maintenance, repair, and con-( struction activities in accordance with I

corporate policies and all applicable laws, l

regulat'ons, licenses and technical require-ments. He is also responsible to carry out assigned plant modifications, repair and con-struction activities and conduct major and specialized maintenance work in accordance l with corporate policies and all applicable j laws, regulations, and licenses and technical i requirements. The Vice President-Maintenance l and Construction is responsible for the l

following major functions:

i l (2) l I-29 Rev. 9 l

l

a. Monitor, evaluate and assure that ,

O maintenance activities at the Generat-ing Stations are being performed in i

accordance with corporate policies, procedures and good maintenance practices.

b. Establish and update the necessary corporate level maintenance and con-struction procedures, standards and practices for the performance of main-tenance and construction activities.

c. Plan, senedule ano direct plant modifi-cations, plant construction projects, and major specialized maintenance joos.

d. Plan, schedule and direct major and special maintenance and construction activities involved in planned and forced outages.

e. Develop preplanned methods, planning and support for forced outages.

Tne Vice President-Maintenanca and Construc- i tion gives his full suoport to the quality

() assurance requirements set forth in this Operational Quality Assurance Plan, assuring compliance to tne fullest degree oy his staff.

1.2.10.1 Maintenance and Construction Director-TMI-l Tne Maintenance and Construction Direc'torTMI-l reports directly to tne Vice President-Maintenance and Construction. He provides i oirect support to tne Vice President-TMI-l and is responsible to conouct assigned major main-tenance and construction activities in support o f the plant. The Maintenance and Construc-tion Director-TMI-l is responsible for the following major functions:

Provide, manage and direct required depart-mental support in the following functional areas:

a. Planning - workload and control, plann-ing and scheduling, estimating and cost analysis.

O I-30 Rev. 9

D. Production - project engineering, con-tractor services, production work, and

({]' materials, tools, equipment ano plant facilities management.

c. Tecnnical Support - welding, turbine, valves / pumps, methods / practices, ana documentation

d. Administrative Support - cersonnel and management assistance.

The Director-Maintenance and Construction is assisted in carrying out nis reponsibilities by a Manager-Planning, a Manager-Production, a Manager-Technical Support, a Manager-Administrative Support and an Outage Manager.

1.2.10.1(a) Manager-Maintenance and Construction Planning TMI-1 The Manager-Maintenance and Construction Planning-TMI-l reports directly to the Main-tenance and Construction Director-TMI-1. He is responsiole for the following major func-tions related to maintenance repair and con- 5 struction activities for TMI-1:

a. Workload planning, inventory and l scheduling.

b. Job planning scheduling and estimating,

c. Materials planning

d. Modification control 1.2.10.1(c) Manaaer-Maintenance and Construction Produc-tion-TMI-l l Tne Manager-Maintenance and Construction Production-TMI-1 reports directly to the Maintenance and Construction Director-TMI-1.

He is responsible for the following major functions related to maintenance, repair and construction activities at TMI-1.

a. Project management

b. Vendor management O

l I-31 R 3v. 9 1

c. Contractor services management

d. Crafts management

e. Plant facilities, equipment and tools 1.2.10.l(c) Manaaer-Maintenance and Construction Technical Supoo r t- T MI-1 Tne Manager-Maintenance and Construction Tech-nical Support-TMI-1 reports directly to the Maintenance and Construction Director-TMI-1.

He is responsible to provide technical support in the following areas related to maintenance, repair and construction activities at TMI-1:

a. Welcing

o. Materials

c. Turbine

d. Auxiliaries, mecnanical

e. Auxiliaries, electrical i

f. Processes Q g. Qualifications

n. Records

1. Documentation J. Metnods K. Procedures 1.2.10.1(d) Maintenance and Construction Outaae Manaaer-TMI-l The Maintenance and Construction Outage Manager-TMI-l reports directly to the Main-tenance and Construction Director-TMI-1. He is responsible to assure that the special activities associated with each outage are planned, scheduled and conducted oy the responsible M&C line organizations.

O I-32 Rev. 9

! < o' . O 4

of fICE OF THE Plit SIDENI FIGUHE 1 l

{

PHE SIDE N r GPU NUCLEAR CORPOHATION

, EXECullVt VICL PHtblOLNT PHOJECT OHGANIZATION TMl UNIT 1 4

I I I I 1 l I VM t PHt Set et NI VH & VH6SetatN1 vt( t l'HL Sitst N t Na #(( E AH li t HNe( At gg g4 , Vit i Pitt $4 at N I % 1eaHi L I( >H M Atra l t N A rdt 4 % W j ASST IH A N( t iiINC Iit >N$ t t IN', I HI n i ti >N , , , , H Al >es se i M ,st At 4 f f 4 /shi .NM6 h l As y,,tVHtMatNT y,9 g g y g g.

( I rN I Hi at 5 1

J I____ ~ ~~l ~

l i___) i I 1

• l uHt C I OH lautt L f oH i j -

Otf Al sl y M^r4At t H ( 06*POH A l t OdattIDH s u ( NSINb s Ht but AlOH -

P1 ANI AlpMihtS f H AIN AN i

AShi sH ant t ,3 l

H Al ste H i n ,H Al -

MA ll HtAt 5 Af f AiHS f I pal i INGH bistPI P/ AreA 8,t Mt *41 l

l i

_ I i

( seit t it att (seett L lt lH i nd<t t l uf t M Atal t re Aht t &

l H AsN#*u & -

t Na,seet t HsNb ( ( uteS I Hi 6t. I h/4 -

4 N't HA l N 'N13N MAf4Abl H .,g g , ,g, y , g u g ,; ,g 3 i De H. A f d >P4 MMNIi N AF44 E *

& N /eH4 sNf Al fJ I Al -

&taiSK.N [nHi( l 6 >H I Mt I d idH f it sH ! Me t gg g p, g g, a g 3 g g g , g LONilH M f)(el( At l')4H1 C i OH & PC 21Nt t Hatc.

' ' I "*" I I ' '" ' ' ' l g i$t. A g g gp,4 g;<y g y g yp,

( ( *N I hot S M AN M,6 M[ r4 i l

l [ M A NAbt H roH, - a OtHiC1OH 6Mtt61NCv -

t Nbitat i HiNb

PHt PAW [sPJt SS H40JIt.I5 l

i l l

M Af 4 Abi H l

t rasir46 i Hir4s;

${ H /it t S l g

laaht C loH Si AltIiJP a II Si e

i OCA1f L KIN SIIf GHL --

-- -- J pNC ilONAl ltf POH ritKi

• HAS(Miti CI N:Cf SS TO THf Of flCf OF 1Hi Pitt Sil4 NI AfD ltil VICI Pitt bit 4 Ni IM 1 WIH lu GAlts TO QUAllIY ACIIV11ll S l 64f V 9 l

l

=-

l 4 0 1 i i

i FIGURE 2 i

i j QU ALITY ASSURANCE DEPARTMENT l PROJECT ORG ANIZ ATION l

' TM1 UNIT 'n .

i I

I f

4 i

}

(

l

! IltHE t'll)H

! (JllA4 II V AShilHAfM i t-1 1 8 bJ V

M AN Abi H M AN A(.I H M AN AG( H l Me t pt I At il y Ab$4 JH APR & M ANAGE H

{ M All HIA! $ O A PHubH AM lif Vt it >PMI N I O A fit blGN Mill >S OPS li t itNt it (hi v ANil AltlellS & PRO ( IJHf Mt NI i

l l

i j

(JLJAlli f LJA ( WE H A l n )PJS g tjHeuH A t t bil t (J A PH4)(,H AM UA Sill (t )HPt )H A l t ( OHP()H All iMe

( ON I H414 b r $l t Mb LIA M A11 HIAL S IS3 N184 (4WgopMtyt Aut ,i l Ai j[ >i l ut sag gl y M ANi tt AD gygg g g y I t Let bl;Ptilit I W t I il g eg,ipat g pregg I OHtP4G g gg g Hg i NbtN1 i Hita, A S5t pH APR [

l L OC All ts ON bif f fu V 9 l

+,

i l

i

C) j i

w" 4

2.0 ;u31ity -5sur3nce P r o g r 3.a

.? . . .J s. ,i .i V 2.1.1 vener31 Ind 6H.

_ , 3 p d 2 3 '.10 n d i <Jj,1*/ & M53d2snCd ? r J y 3 ii n35 09dn 25'.30li5ndC ; ) 4:0Vije c/erl.1 qud-

.i;/ 355Ur5nce Of 2C01/1;19J v i;n..i C.it 3Cupe JT- Cne pCCg23W.. ~Jn:CenCe ;J *ne seg ;i re den t 3 .

Cf p

"nd IH;-i J0e~3~10n3.e,. <vdai'f 4.5ardnCd 0,.3m 4 r i .r J ; tist w 3 . ;w.u n a-9* .J .n o n v a w J ./ *v. d..

3n0 TO: 3 .1 1 3409:331' ;rj3n.ri.;]r's r;/;jinj 10935 Jr 5drVi 95 0)vi"eu under *n: . 3C009.

Inis Ju31it/ %55uranC9 Jian .5 ;19 n i j n e 5 *.

19V91 COCumen; wh1CO Cd5CriJd5 00 wu3ii~f A55ur3nC9 PrOQ~3m. i:iB * . c r:3 "?!3j~wn" 35 u 3 e 'J q a.

. . 2. .:n .in ., .; u v 2. 3 J L g .w.i .s -

~w- ., . . n. a. .w .ir . . .

.3 s- s, .: i1 . .i a. J , -

-m.o sc n , a. u u 2. -J 2nu

, - ., ; -. ,-..i ns.

.nJ.. .ww v An./ v g in : 1.1v.J. ., .- a3-.v , , . s .i q ,,, i e. ..2 n a..... w v p. 3 i w impi9m9n~3;i0n Of ;ni5 ?.30 5n3ii 39 0).Opti f 2,0 w s s ., . ..f- aJJv 3nL,2 (O

-- wcu . 0 .no . - - 31,.2.w .w 3 IS50luti0n. t

.. .2 a v- m vam a.

-?.a.). i -and SC009 Jf One i il sod!3;i0n31 a3.1;f A55U23nCS ?!0;r3m in0.uCd5 3.. . ; e.15 inc '

.:. . . d,..e . 2. J -V Jw, , 2. 2. w, .s w .3 .....,..

. alw V ... . . .. . 4 J2-i 2. w f.H 'l .mi.J ; - =. 2. ] , -

.J w

.s d v. 2. ...ta..

te J 3 4

3...f-

. s. .t ,3.. 2. w, n

. al2 n. G

2. .n4v s. ,---3,

., 8 o wd@Jw J J. J. . .. ..,

J f J . 2. 04 J p f . , . .

3nC 00mpOndn;5 sinCaw0inj nu;192 'v91 dnC r3CW35;e) uni 0n n3 /e 09en ;esigns;ej 35 33f9'/-4di3*dC, 33f9;/ 'i 355, Id-i 3;355 15, g g .iJoy .: ., ,s.2.4gw/ .

. v

.e., 2 2 s . a.wc. . .. s' n .

.. T .7 a.

i av , g w .,2 3a 4 .,,

we - p ,s3, 3..e

..,L .1.v 6 -_. -J .2.u,.e.

a. w J .4 2 ,

.s as

\

w/ . n .a. #,i. . s . 1. ,a 4 . n ] . .

I

3. . $ . p bbd ) N-)d.3. U h'3. 3 w bb5p 2,.. .., .

3.. )o, Mug2n w 4 " J. nd . .

2 , ,

J.J.g,b I w i.2 w .4J ... 4 6. .* 2 *.3 ))dd

. . w b. ,

w J 't l

m.

w i. 1.2 .

J. .s ,2

,'sv. . #. y a. .s , 2 .. 3 .1 -

o. j u, .is..s ..ig 'J ,

l ?3r' 30, mp0dnliX C " W u d i a '. / 453ar3nC9

~

V; *w- a:.3 a i3 a u w. ..,. 26 ., 4 ,. z . 3 .,. w 3 JnG

- - Q23 I w, C .i *ww

,m2 . .

vvw JJ 1.4

.J iO ., J q.I s .J. es O

) , # O 2 .d, js.9J w .,

9 , *

v. no w.. .,., .av. .

M 2.w h. .

g

, 3, Q..

i 3 / .' , M w w Own , .i 4 .--

- ,. te , '

vusi . .,/ 43JU . -

J.n6.sg

'g w a

p. .i aw a .i 3 'g- Q -

.'a. g ; 3.a + 3 .g . .,.w. .s , , Q G*. w .' .j p a

s -.g  % ' ft 9Gww .Ji i

f'%s

'w) . . .

. . , . 5dV. 7

r

d. United States Nuclear Regulatory Com-ll mission Regulatory Guide 1.143 "De sig n Guidance for Radioactive Maste Manage-ment Systems, Structures and Components Installed in Light Water Cooled Nuclear Power Plants"

e. Branch Tecnnical Position ASS 9.5-1

" Guidelines for Fire Protecticn for Nuclear Power Plants".

f. U.S. Nuclear Regulatory Commission Regulatory Guide 1.29 " Seismic Design Classification," and tne seismic asoects of components unicn have imoact on items important to safety.

g. Otner items wnen designated by Tecnni-cal Functions.

Tne TMI Operational Quality Assurance Program applies to all items on tne Quality Classi-fication List (QCL). Tne QCL will ce periodically updated to include new plant modifications or construction, or any changes in classification. The list will he treated '

as a controlled document.

For new design efforts, sucn as plant modifi-cations and new construction, tne classifica-tion cetermination is recorded on design cri-teria documents. New items will De included in the next revisitn to tne QCL. Documents unich control tne installation o f modifica-tions which have ceen classifiec as "important to safety" will oe clearly identified as sucn.

2.1.2.2 Activities whicn are important to safety shall include, but not os limited to:

a. Those activities envered Dy Appendix A o f Regulatory Guide 1.33 and ANSI NlS.7.

o. The repuirements of other Regul3 tory Guides aoplicable to operations, maintenance, mooification, repair ano refueling of a nuclear power plant as identified in Aopendix C nerein.

c. Those activities related to Fire Protection as coverec by aranch Tecnnical Position A$3 9.5-1.

9 II-2 Rev. 9

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

1 l

J. Tnose activities related to Plant 5ecurity 3s coverec of Title 10, ..uJe of Federal Aejulations, Part 7J.25,

' ',4:cui reaan;s f o r e,ny si;.a t -:->;ectivo of Licensed Activities in auclear Jose:

Plants agains: industrial aauotaje."

e. Inose activities coverea of procecures uni:n nave oeen desi;natec Juriaj ne review cycle as "important to safety."

2.1.3 Cuality Assurance Plan Tais Juality Assurance Plan is ne p ri aarf document unicn provices a oescription of tne

, Program. Tne Plan is autnorized oy :ne Presicants of Me:-Ed anc JPJNC to assure tna; tne accropria te levels o f .nanagemen t, as designa:ec nerein, are cirectec to implement ne Program. Tne Plan is controllec to assure

, tnat only One latest approvec revision is 1 implemented. ine Plan is implementec oy approved ce:allec procecures and instructions.

j ine purpose of :nis Plan is :o estaoilsn :ne i crin:1ples unicn, unen impleaentea, nili pro-vice :na; level of quality assurance ani:n is i

aporopria:e to eacn item or activi;y important to safe:j. It is recognize: :na :ne oejree of management con :al or quali / assurance to ce ap0lisc varies ai:n cif ferent systens ano activities, and :ne cegree o f a;;11cacili:y o f anf specific item in :nis Program will ;iffer from item to item anc ac;ivity to activity.

Tne cegree to uni:n :ne requirements af :nis Plan anc 1:s implementing ::ocecures are applie sill as casec upon :ne following:

a. Tne imoar:ance of a malfunction or f ailure of :ne i:en :o safe:/;

c. Tne cesign anc faori:a:ior. complexi;f

;ni;ueness of tne 1:ea;

c. Tne neec for special con; ols anc sur-veillance or acnitoring af aracesses, equi ment anc operational activities;

. Tne :egree ;c union funccional ;om-oliance can ce oemons;:stec cy inspec.

ion or

ss:; anc

) e. Tne uali;y nis;or/ ano aegree of stan-carcization of :ne item or actisity.

II-3 d ev. 7 l

i 1

]

i 1 ine quali:/ require.nents far items 1,aportant to safe y 4'.11 De es 30li3heu using dpproved p;cc2dures ]asec on :ne " General Logic Cansi- l Cera: 130s" .isted in tne magendi< Co mo t -

aa3.2.13-1976. Guali / requirements alix ae estaJiisnec of tne resacnsiale -njineiring i Depa rtmen t and concurreu nitn oy tne quali:/ l l Assurance ;3aart.nent f a r cno se ite;ns .vnian a re '

l impo r:an t to safety.

SPUNC is coanittea to a comorenensive ,uality

Assurance ? ograin consisting of a three level j ac0 caco

o assure s.itisfactory anc ceiaaieta i imoleinen:a:ian of :ne program Co.amensurate witn i s recairements far safety ano aerfor-nance. Tne Program's foremost considerations are ne statec 10n af :ne ,enerai puolic's ,.

nealtn an; safe:f. '

2.1.3.1 Level : - activities a: nis level ;onsis; af i

inspections, One04s anc tests.

Mnere :ne first level ac:1vities involve ince-cencen; inspection fa purposes of accep;ance an /;: verifi:s-10n ;f +acalfica:icns :c ,

1300 3n: :C 3afet/ systems, Cne aC ivi~/ *111 Oe Oerf3raed 3/ *ne Ja Je03rtaent ar Jf Jrgan103 icn3 autn0 ized 0 Oe:f]r.3 :no3e j

aO*ivi ieS Oy :ne WA JdO3!~nent.

n c:ner ca;es, tais level of activi y maj se s,a - e . . . ,- ../.

^

j

1. Opers:icns Or raciological Oont:ci personnel fc: activities sucn as surveillance :es:3, Caliora-ion af ins; aments, racia:ian surveys, analyses af sa.n les, valve line-ups, e:C.

2. Ine Cu311 / Con !ci decti0n Jy reCeiOO ins 0s0*i0n Or insOe00 ions Of moGifiO3-ti

n :: 00 rec"ive uain:enance 3 0 ". i v i ". i e s .

J. .' o n '. : 3 0 ~ 0 s 3 3 ,0 a r : Of "neir scope af 4a:4.

.c i. a. .t .) ,.._,

.sa-s, .. n a. 1 w.

.. . . ./ : ./ 4

. 2 g..-

42

.v.uc.m, 4 -

J,/

19CiviOU31s kn0dieCjed31e Of One S C ;i v i ". /

Oeing Oe:f0?as0 an0 kJalifiec O J e f f 0 0.3 :ne d0:4 (re fer !] de0* ion s.2.1.1). Cae0411s~s O 2a:3 snSe!s are ;se0 f0r 00cumenting "ne

• -e Rev. 9 1

l l

j i results of the activity anc for gravijing a i peraanent recora of tne Je far.aance ar :ne activity.

2.1.3.2 L? val II - :ne activi:les at e n i s 1 s v -s ' are ,

primarily tnase of surveillance ;; aoni: grin, i

and are se.for aea as ee?aea ne ;essarf s/ tae WA :40cifica: 10ns/Operatians a: wa Jesign anc I arocurement sections, in e levei ;f surveii-1ance/:acnitoring applied is consistent si:n

ne im;ortance of :ne iteia ;o saf.;ty. For

! activi:le s, enere wuali;y Cont: 21 is us:-

i for.ning first level irsaec:ian, no 2 e':and level activity will ce requirec.

l 4: tnis level aracecu:es anc ins;;u::Lans are estaolisneo anc surveillance re:c:cs 4i11 ce comple:ec anc maintainea. 2aco sur<citlance/

monitoring normally inclu;es caservation af tes:s anc inspections, cos2:vation af selec:ec operations, review o f reco:0s, verifica ians of test reco::s, anc cirec: insjection an a spot Onec< casis. Tne o rganiza tions pe rf a r.n-ing :nis activity nave ne levais or autncri:f, :ne lines of internal anc externai i communication for aanagement direction, ana

ne croce 1/ ::ainec personnel far implementa-tion of :nese activities.

3...>.2 u ,. v ,. . it. - .. n e ., u, -u

_,s.e ..

,,a. . 2 ,_v

. . i v .r ac:ivi:/ is ;o assare :n:Jugn 2 ca;aaranensi/e p;cgram Of review anc auai:ing :na: :n: firs; anc seconc levels of :ne ;;;; 3.a are ; ]perly functioning. Tne pu rpose O f :nis level is also :o estaclisn :na: all ::ne argani:ations inciacing ocerations, aain:enance, ingineer-1 ing, m ateriais Aanagemen:, e::. are arncerly

, satisfying ali :ne require:aen:s of :ne 00erstional Juali:/ Assurance ?:]; am.

At :nis level p ccecures anc ins ue:icos are es aalisnee including :ne ;32 af comorenensive ene xlists far cocumen;stian a f :ne auci: a

qire level a

ivi:y. The ; ;;g r a.a recuire-ments a f ANil A45.2.12 snal; ce satisfiec.

, Qual;fiec auai; cers;nnel snali se a ;11:ec

na sa:isff :ne re0J1:emen~s of .' N 5 I ca 3 . 2 . 2 3 .

A;ci i:nal :e:nni:31 ex;er:s f:;m areas di:n acminis :ative re00 :ing Jutsi0e :ne f;nc ian

na is aeing aJc1*ec sile Oe inClJCe; li Ge i

I 1 .. .

3 42v. 9 i

I .. - _._.._.m . . . _ __. _ . _ _ _ _ . _ _ . _ _ _ , . , _ . . . _ . _ _ . . _ _ . _ _ _ , _ _ _ _ . . _ _ _ , _ , , . . _ _ _ _ . . _ _ _ _ . _ _

) Aucit Team Leader ceems necessary. Tne Orga-nization perforaing Unis activitj nas suffi-Cient autn0rity anc lines of internal anc external coaaunications f ar 30taining tne nec es sa ry mana ;:.a e n t alrection.

2.i.3.e Aa encix 4, nerein, is inciaced to ,;;aviae a comparison of tne sections of One Plan nitn tne requirements of luCFd50, Aspendi< a, 10CFR71, mppencix d , Madi .416.7, anc saal N45.2.

2.1.4 Juality Assurance Procram devie.v ine TAI luality Assurance Hr; gram effective-ness anc implementation is periodically evaluated oy GPuidu aan a j e:ae n t . Tne Juality Assurance oeaartment concocts evslaattons ani:n gravide iaana;ement nitn Anformation pertaining to e f fectiveness anc imste nenta-tian, utner aivisions provice accitional infor. nation / evaluations as requestec.

2.1.5 Trainin; Tne TAI Juality assurance Pragram nciaces i require.aents for f armal training programs for personnel perf 00'aing or verifying activities imoortant to safety.

2.2 decuirements 2.2.1 Jualit/ es3aranca Plan Tne Operational saality Assurance ?lan and any significant revisions snail ce approvec oy tne folioning:

O f fice o f tne Presicent - a?uaC vice Presicent -

TMI unit 1 Vi0e Presi0ent -

auCl33r mss Jr3nCe Vice PresiJent -

Tecnni0ai FunCtiCOs vice cresi;ent - Maintenance anc ConstruC; ion Vice ?re3i0ent - dJministrdti0n N

II-d deV. 9

,) Vice Presicent - dadiological and Environmenta; ontrol Director - vaaii;f Assurance Ine Plan includes a a:atement af .-oiicy anian is signed Dy tne Presiaents - u?UNC ano Metra-politan iJiSon. ine statement Of ?olicy gra-vices thorization anc evicence o f management c om.a i t m t , t to :na Juality Assurance ?rogran.

Revisions to tnis plan snall ce considerec significan: if :ney alter :ne ce;ree a f ;a,n-pliance ai:n regulato ry requirements committea to in Appencix C, nerein. .nanges to tne TAI-l organization in assign.nent of responsioilities to :ne extent descrioca celow the vice Presicent's level snill not ce consicerec significant except in tne area af Quality Assurance. Changes in name or title enanges aito no casic cnange in function snali not ce consicerec significant, ici:arial and typograpnical errors snicn ao act Onange tne intent o f tne ao rcs o r scope of tne aragram snall na ce consicerec ;ijnificant. i significant plan revisians snall oe suomitted T to :na duclear segulatory Commiss.ian. 4dC

/ approval is requirec prior to imalementation.

Plan revisians not consicere; ay :ne airectar

- Guality Assurance to ce significant can ae issued .o aporoval af :ne Jarec tor uali:/

Assurance anc cne Vice Presicen; - auclear Assurance. ine Jirector-Quality Assurance .s resoonsiale f ar notifying tne adC of sucn

nanges :o :ne ?lan aitnin 30 Jays o f cne cnange.

uopies ;r <uaA1:y ,ssurance rian aaf ae ais-trioutec as "Controllec" or "uncontrollec" copies in accordance witn tne requirements estaclisned in 3ection 3.

2.2.2 213ssificatiJn Z...:.. Seneral ine ;uality assurance veaar:aent will concur dita One pr00ecures used far ' ;;ifica; ion, and auci :ne prJcess f0 im'

• en!a:icn.

ACJiticoall f, enjineering 5 a4 i. .aticn Of 4 ..

l sJ 1 -e_ dev.

b I

I

. - . , , - - - - - , - - - . , , . - - , - . . , - . . - _ . -v.,_-,-- - - - , - - - . . . - - . - ,

items "important to safety" will be subject to

() independent design verification by Technical runtions. .

2.2.2.2 'Trts Classification The Quality Classification List (QCL) will normally list systems and major components but not parts. For procurement of spare or re-placement parts, classification will be on a case by case basis. Plant Engineering or Technical Functions will classify the parts to De ordered. QA concurrence is required. The determinations will not necessarily be added to the QCL.

2.2.3 Reculatory Commitments Records of commitments to regulatory require-ments are maintained oy Technical Functions.

Appendix C, nerein, lists those regulatory guides which are quality related or affected with stated company position, exceptions and or clarifications. These must be complied with in conjunction with the QA Plan. [

Appendix C will be revised to reflect any

() cnange iri the GPUNC Commitment to those Regulatory Guides shown with an asterisk.

2.2.4 Safety Reviews Safety review groups have oeen establisned to perform regulatory required reviews. These groups provide management with visability and recommendations for improved plant safety.

2.2 ',.1 Plant Doeracions Review Committee (PORC)

The PORC is an on-site coerations review organization functionally reporting to the Vice President-TMI Unit 1. This group reviews all matters which potentially require ince-pendent review cy GRC.

II-S Rev. 9 A

U

PORC is made up of plant senior technical

() personnel with day-to-day responsibility and accountability for safe operation. Its mem-bers shall provide, as part of the normal duties of plant supervisory personnel, timely and continuing monitoring of operating activi-ties to assist the Vice President - TMI Unit 1 in keeping abreast of general plant conditions and to verify that the day-to-day operating activities are conducted safely and in accor-dance with applicable adminstrative controls.

These continuing monitoring activities are considered to be an integral part of the routine supervisory function and are important to the safety of plant operation. The Vice President-TMI Unit 1 in carrying out his responsibility for overall safety of plant operations, shall be responsible for timely referral of appropriate matters to management and the GRC.

2.2.4.2 Generation Review Committee (GRC):

The GRC is an of f-site organization reporting to the Vice President - Technical Functions.

This group is responsible to provide indepen-  !

s dent safety review o f operations, nuclear q engineering, chemistry and radiochemistry, metallurgy, nondestructive examination, instrumentation and control, radiological safety, mechanical and electrical engineering, radwaste, administrative controls, quality assurance and other appropriate fields associated with the unique cnaracteristics of TMI. The GRC is responsible for reviewing the following specific subjects:

l a. Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes in procedures as descrioed in the Safety Analysis Report and tests or experi-ments not described in the Safety Analysic Report whicn are completed without prior NRC approval under the l provisions o f 10 CFR 50.59(a)(l) . This review is to verify that sucn changes, tests or experiments did not involve a cnange in tne technical specifications or an unreviewed safety question as defined in 10 CFR 50.59 (a)(2).

l II-9 Rev. 8 l

I

_ m g Any proposed change in'procecures or the g)

(

b.

facility or proposed tests or experi-ments which involve a change in the technical specifications or an unreview-ed safety question as defined in 10 CFR 50.59(c). Matters o f this kind shall be referred to the GRC by PORC following its review, or by other functional orga-nizational units within the GPU Nuclear Corporation, prior to implementation.

c. Changes in the technical specifications or license amendments relating to nuclear safety prior to submittal to the NRC for approval,

d. Violations, deviations and reportable events which require reporting to the NRC in writing within 24 nours, sucn as:

1. Violations o f applicable codes, regulations, orders, technical specifications, license require-ments, internal procedures or instructions having safety significance. '

() 2. Significant operating abnormal-ities or deviations from normal or expected performance of plant structures, systems, or compo-nents important to safety.

3. As defined in the plant technical specifications.

e. Violations, deviations and reportable events as described in 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. Section 50.72, shall be reported to the NRC Dy tele-phone within one nour.

GRC reviews of these items (c and e)

I normally occur after the NRC has been notified. GRC reviews shall include the results of any investigations mace and the recommendations resulting from sucn investigations to prevent or reduce tne probability of recurrence o f tne event.

II-10 Rev. 9 O

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

s f. Any a;ne: olatter invalvin.J safe apera-tion af tne auclea: sower slant anica an incepencen; re sie ne r eee.as app ro-pria:e f o r ;ons i:Je:a tion, ;; ani;a .3

eferrec ta toe indepenaent reviewers oy tne ansite Joe:ating ;;janizatian ar oy otner functional organizational units aitnin tna TAI arjanization.

2.2.4.3 .4uclear safety assessment oeaa rtment (aaau):

N540 is ao incepencent c ganiza:ian reporting to One vice President .4uclear Assuranca 7" ae:for.as eva,uatons 2na investija: ions as it asems appropriate or as assignec ay tne vice President - Nuclea Assurance. Namu perf0:ns special evaluations o f inf]I nation from external sources for spolicacility ;o TAI.

N5A0 .aay 3150 p e r f 0 .3 evaluations Of existing na: aware and saftaare sys; ems anian 3ffect tne safe, reliaale operation O f :ne piant. Iney in:erface ai:n ne 440 aucit section ;o assare complete coverage and utilization Of taa aucit p 0 gram.

2.2.w.a ouality -ssurance veaar: nent: '

O)

\_ Ine normal auci: aragram concuc;ea oy ;ne Juality -ssurance vecar: men; and cescrioed in 5ection 3.0 aisc provices manage nent ui:n assess.aen; af 2 gram sta;;s and effec-iveness.

2 . .. 3 IncCC; inati0n anc Traininc Encoct:ina;ian anc ::aining  : :a;:ams a:e estaClisnec fC 00;n On-site anC Off-si~e per-sonnel Je:f0:. ling im00:~an; 00 safety dCtiVi-ies Oy ne o rganizational uni;s resconsicie f0: :ne aC ivities. Inese J:09:ains 3:e imclementec cy aap cgria:e ::aining plans anc

- , ..,,,n . ..

W o. a. w u .- a. n3 W .- n 4 84. 46 333,,,J.-,. wnd.

a. F"" a. .nJu.- m nms i t . .! a .a s.

=

.l ee 3 w .a , . %

6 ww..n g w a3- .. wv

• n s.o Ou:p0se, 5000s, ana .mCle.nenta;13n ;f manuals, p:Oce0ures, anc instructions;

w. s 2. . G- w, n -2 l e .1 22 . . 3 .4as.G

,2 - G44V -- ,

2.

.w.8 4 24 . ,a 4n

ne a inciples anc tecr.niJues af :ne

(

a ^. ". .i v .' w .' a. a' v' 2

.*4 ,'. 3' s' a. .- f s' .- .i a.- C . 4 L' v

s.s" ~. a n C a.

[

,w., . . J .m .i3 - a .j.

+*

.e m s a.

g- m

. 3 . d .mb .I .5 3es.L**g *

.swq n ) .I 3%witw

^ *b am*

ai:n One im00 :ance ;0 safe;y Jf ;ne 3 6, =. 4 s/ .: = . ,y . a. c ,w J A... 4 n g. W. ,J a .i ., s. .tw, a u .4 v , n .,

g .. .

u-u ,

sev. z l

I

_ ,_ , , _ , _ _ _ _ - . _ _ _ _ - , - - - ,- + - -*

. N ,) c. Jr0f10iency is maint3ined Oy retrain-Ing, re-e x a.nining , 3r recertif f i ng;

c. rne ;00pe, netnCO and 00jective Of :ne training is 00cu.aenteu;

e. decarcs Of training sessi0ns are pre-pa!c0 dnu iddintained, inciacing identi-ficdtion Of Cne Content, tne attenddes, and ;ne Ja:e tne ; raining ads donducted.

2.2.5 F0 r pe r30nn 91 pe r fo rming inspec ti0n, exaaina-t;]n, Inc svecial pr; cesses, :ne qualificati0n criteria sna:1 Oe celineate0 to tne tecnniques of inspectir.n or items Oeing inspected and ;ne

.ecnnical acilities of tne pers0n oeing certi-riec s'1' .o ~0nsistent aitn :ne assignea

ases s'e.g., e.Iectrical inspecti0n, .neenanical insaec;i0n, etc.).

2.3 se50cnsicill;ies 2.3.1 jffice af :ne are31cen; - a?uaC Ine Jffice Of :ne Pre 31 cent - J?Uik is resa0n- '

sicle to regularly assess tne scope, status, aceuuacy 2nc compilance Of cne ,uality Assurance ?ragram ;0 :ne recuire nents Of lu

.r 4 20, -apencix 3. .

.inis assessmen; snail Oe One 00m0ine0 resul; Of:

3. -evi9a Of Suci~. 23000:3, JeriOdiO s;atv3 0ep0005, etc., on tne effective-neS3 3nc i2013 mentation Of One Juali;j Assurance Progra.n.

O. O erfarmance at lea 3; ance , fe3: af a pre?lannec anc 00CuQentec 3s3ess.nen; O f tne effectiveness Jf cne .uality Assurance Prog rain 00 assure Onat One pr0,;r32 mes;3 rejui300rf re.aui remen t s ,

Snc One p011cies anc cireCCives Of IA'.

Ini3 335e53 Men; Ga/ Oe Jerfor.lec ;;i;-

1;in] One safet/ review jr0ups, an incScencent CCOsultant, Jr .lis dan starf. Any C0rrec;ive action snicn nay 09 29e390 necessar/ 33 3 resul; af Ene3e 353essmen;5 Sn311 Os f]rmalif 10eS;ifie0 inC OraC<e0 Cn!0ugn re301J-

.,n.

e '

11 .j 4 dev. )

2.3.2 vice ?resiaent - Nuclear as;urance Tne Vice Presiaant - 4ac t 2a r s ai;!2nce ol; overall respan3icility f u r 3 ; u c l i ; n...c . i t af tne Jperational Jualic/ %3suranct r' r a j r a .a . 1e also nas o 'er311 respon3iaitiity far e3taa-lisnment and iaanajement ;f ;ne 4u;1 ear asfety ,

As s e s sinen t dep a r t.nen t 3n0 tne ,ualit/

Assurance Jepart.aent, inc luding .le noo;/?ro-gram / Audit 5ection. He in311 prcvide perlu JiC status reports 00 Cne J f f1;e af sne .-;.3ident on the Quality Assurance ?ragrm.a.

2.3.3 Jirector - Juality 43surance Tne Jirector-Ouali;y 433 uran:e, ias .nu Jirect responsialli;y for verifying tne dffecr.1ve Imo.i e nen ta tion a f tne auali;/ -3 saran;e Program. ne snali estaallsn anc iaulaaent a formall/ cocumentec and afsce;urill / ;cn-trolleo program to ev31uate anc repart ta tne viCe Pre 31 cent - :4ucle a r e s 3a rance an tne adecuaCy anc Continuec effectiveness af tne overdi.3 TM L J0 erat 1Ona. J u a a, l t/ 4 3 50 0)'i0 e drOgr3m. Keports of au0its perf):med Of ne

• Qualit/ 433urance uspar; ment ) Oneir $ gents, and Quality trenc analysds Ca3ec on nOncQnfor-33nCe anc de fiCiency repo:*.s alli provide tne casis fJr Onis evaluation. Carrecti.e action I

saali De implementec Jy re sp an31a le ata la jemen t aC aseme0 app!OJriate cinen anaiy3es 0 2 Mdl adverse Quali*./ trend 3. In d 3e ac t iar.3 ..la y involve Specific 3CtiC35 *0 CICvi0e 0]iaaliance .

witn tne auality assurance ?r;; ram, sac siay inCluce folloa-up system attricate cua;;3 ana even revision ;o tne TAI sperati:nal saalit/

Assurance ?:0 gram. Imple:nant a tion anc clase-out of corrective acti;ns snail ae ef rcctively monitorec of One director uualit/ Assurance to assure ti.nely Carrection ana ra.aaliance.

Tne Jirectar-Quality ss3urance is re3acosiale s.3 .,o ,

.; s.

. . . . . 0 . . ..

r 3 n .2

. .n.

. . w -2

.4 .r . /

. ,22

. 4.,,,a.

. .a .i a .,.

anc far ensuring Onat tad Juali;y 433urance Pi30 .3 mCCifieC anc uOCa;ec as 3 r.a n0a r;3, regulatian, re'auirements and e.(Je'ience JiO-Cate. 2 00003eC revisions .0 '. D e . i a n <ay DJ

, Suggestec Oy '?J .4uClear 00 :00:37.L2n ;arsonnel ay suamittin; :ne reauest, ;n . r i r. t n u, ta .ne JireC Or-Ouality -s3Jrance f]r .2/iew and 30 tion. Tne Jirec;Jr-Cuali;f 433urance a5

\

) a.-a)7 .

.d e l . ?

1

. - . _ _ . _ _ _ . _ _ - - - , , , , _ _ . _ _ _ _ . _ _ _ _ _ . _ , _ _ _ _ , . _ _ , , _ _ . . _ _ _ _ , . , _ , _ . . . . , . _ _ - - , , _ _ . , . . . , , , , ..._,_._m -, -- ..

_j resconsiale fO r tne .aunito ring , surveillance and auciting Or Jualit/ sssurance er;g.:am i.ap le me n ta t io n .

ne is also resp;nsiale to JrJvije tne r e.;;i r e J i trainia; ana qualification Or wuali;/

Assurance Jepartment persannel.

2.3.a Directo r - Enainee rin; 4 ueriyn Tne Jirector af ingineering a Jes1;n is responsi0le fur cave 10pment anu .naintenance o f tne uCL. me solicits input anc OcorJina; s aitn af fectec organizations to assure a Jn1T0ria aOp!]acn ;o 013ss1T10at10n Or, items and aC;ivities important to safetf.

2.3.5 G+JdC - Mana,;e.nent Manageaent persannel in eacn depa rtiaan; ire responsi0le f0 Quali;f Assurance Program im0lem9ntati0n Oy Oneir leCartment Or Jr.ups.

Inef are furtner responsi0le f0 c e v e 100me.' t Of prQCecures, far Scope Of involvement, far activities impor ant to safety, anc far {

training anC inCoCtrinatian af personnel.

N Y 2.3.5 dXternal Jr0ani;3; ions Quality assarance ? Ograms anc . mole:nenting pr0cecures far su0 pliers Jr ;Jntrac;;rs gra-v.v..g a a ". 3. .' .' s'.'.-' and a' ". ~ ~/ .i ' " a' fs'~ ..

. 'n'. . i .'

iiuclear 3;ation anicn are c0verec uncer One scope of :nis wuali;y -ssurance Hrugram anall Oe su0 ject, anen specifiec in pr]curement cocuments, ;0 revisa anc accep;ance Of ne Quality Assurance Departmen; prior t0 :ne c c am e n C e.nen t Jf any inportan; ". O safe:/

a v,s.. ; ,l .; . y .

I 2.4 4isalutiJn Of Jis0utes Res0lutiOn Jf dispu~es .nvolving .uali'y, arising from a Cifference Of opiniJn Je: deen JA/JG personnel snC J;ner 0 Janizati0n ( e n-j i-neerinj, p 0CJre aent , ninufacturing, Construc-ti0n, 00eri~i0n, naintendnCe, e:C.) Jers0nnei 2 .q a .1 .' , ..

g22i.1.,

a.2 e2 u 3 4. . g m ~- l .t a .4 2. ,a* 3 r. + .q- a.

1 3 ,/ a. .i ,<--

2.,,,.wd .. . a g u . .2. a. mo , .

u. . e

.n .; 2 -

r, a n a .4 , :s.2 .,e e

.;i.2. . 2.n42 w

wT-4, 4

a 1 v, v g . n . u, n a n 3 .s .i s 2 es03.atec :n20u;n supervis0ry/adnajemen".

le/els until res0lu;100 is aCnieveQ.

v Il-14 Sev. )

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

E try

c. -.

I I

I O

i 595ueuo ufTseo Jr c :unu*e: T nb e: TEDTuere: ;c ucT;r:e:c:stuT fuTU:PoUOc F o;;rT UO UOTsTOer au a

• F u' IIPuf C uC'i 0 ouni TF. Tuuorf - tunrisF:s tota aui s:unt"o 7nba CourTTcease c; pour:dacoE ouf uni:onceu, r u;u a cuc. s:nnaer oc ucTsTcar eu:

F u r'" T T r u s p ou r: r's s e /;TTenh - Joace: Tr auf h

3.0 Control of Documents and Records 3.1 Instructions, Procedures, Drawinos and Policies 3.1.1 Policy The TMI Quality Assurance Program requires that activities important to safety be pre-scribed by documented procedures, instruc-tions, and/or drawings and that these quality-affecting activities be accomplished in accordance with these documents. All user personnel must be indoctrinated to the above prior to implementation.

3.1.2 Reouirements Procedures, instructions, drawings, and/or policies which prescribe the performance of activities important to safety shall comply with requirements o f this Plan. To accomplish this these documents shall:

a. Include quantitative (such as dimen-sions, tolerances, and operating limits) and qualitative (sucn as work- 1 manship samoles) acceptance criteria

(..-) sufficient for determining that important activities nave been satisfactorily accomplished.

b. Require aoproval of responsible personnel prior to the initiation of the quality-affecting activity.

c. Describe the action to be accomplisned.

d. Define the responsibilities and author-ities of personnel performing the activity.

e. Descrice interfaces with other company elements or other organizations.

f. Se distributed in a controlled manner to preclude the use of obsolete docu-ments.

g. Se distributed with sufficient con-trolled copies to assure availability to ressonsible personnel.

. III-l Rev. 9

h. Require that changes be documented and approved prior to being implemented.

i. Require that revisions be reviewed and approved by the same organizations that performed the original review and approval or by organizations designated by the originating organizations.

Appencix S identifies organizational respons-ibilities for the preparation, review, ap-proval, concurrence and issuance of documents important to safety.

3.1.3 Resconsibilities 3.1.3.1 Deoartment Manaaers The Manager of eacn cepartment performing activities important to safety is responsible for the preparation, approval and imple-mentation of procedures, instructions and/or drawings necessary to effectively implement the Quality Assurance Plan. He is responsible to assure that provisions are made for inter-face controls for internal and external lines '

f- of communications among participating organ-(_)j izations and technical disciplines. Addition-ally, ne is responsible to insure that the procedures reference the documents used in their preparation and the extent to which the procedures meet the requirements of the re fe rence s.

3.1.3,2 Duality Assurance Decartment The QAD snall review those administrative pol-icies, procedures, instructions and/or draw-ings unich delineate the methods of complying with the requirements of this Plan.

Selected vendor Quality Assurance Plans /

Manuals, special orocess procedures, and in-spection and test prncedures shall oe reviewed and approved by QAD prior to releasing the l vendor to implement such documents. Selected contractor Quality Assurance Plans / Manuals, work plans, drawings, instructions and pro-l III-2 Rev. 9 i

(

l

cedures shall be reviewed and approved by QAD

() prior to releasing the contractor to start work. Compliance shall be verified by audit, surveillance and inspection programs.

3.1.3.3 External Organizations Tnose activities important to safety which are performed by contractors, agents, or vendors shall be delineated by documented, approved, and controlled procedures, instructions or drawings.

3.2 Occument Control 3.2.1 Poliev Measures shall be established and " umented to control the issuance of documents, such as program documents, design documents, instruc-tions, procedures, and drawings, including changes thereto, whicn prescribe activities as defined in Section 2.0 of tnis Plan. These measures shall assure that documents, includ-ing changes, are reviewed for adequacy and .

approved for release by authorized personnel 9 and are distributed to, and used at, the lo-() cation where the prescribed activity is cer-formed.

3.2.2 Reauirements Written document control procedures shall De establisned to provide for control of the 'fol-

, lowing documents as a minimum:

a. As-built Drawings

b. Quality Assurance Plans / Manuals, and Procecures

c. Operating Procedures & Instructions

d. Maintenance Procedures & Instructions

e. Design vacuments (e.g., calculations, drawings, soecifications, analyses) including documents related to computer Codes.

III-3 Rev. 8 O

b

l j

() f. Manufactaring, Construction and Instal-lation Drasings a

l g. Manufacturing, Construction Modifi-cation, Installation, Test, and Inspec-l tion Procedures and Instructions

! h. Procurement Documents a i. FSAR and Related Design Criteria Docu-i ments i

j. NonConformance Reports

, k. Design Change Documents

1. Test Specifications l Operating and Special f,roers i

n. Equipment & Material Control Procedures i

o. Refueling Procedures l p. QCL i

() q. GPUNC Topical Reports i All procedures established for document con-

, trol sr.all meet the following requirements:

1. Review, approval and issuance criteria j for documents and tnelr revisions shall

{

be specified to assure adequate tech-nical and quality requireme.its are met

prior to issue.

l t 2. Tne organizations or positions re-sponsible for reviewing, approving and issuing documents and their revision shall be specified.

l

3. Changes must be docua.ented and approved prior to being implemented.

l III-A Rev. 9 O

4 Revisions shall be reviewed and ap-proved by the same organizations that

(} performed the original review and ap-proval or by organizations designated by the originating organizations.

5. Document distribution must be suf-ficient to assure that the documents are readily available at convenient locations to responsible personnel prior to commencement of work.

6. Document transmittal and maintenance measures shall be incorporated in docu-ment control systecas to prevent in-advertant use of voideJ, superseded or obsolete docuaents. Holders of con-trolled documents are resoonsible for maintaining their assigned copies in a current status. Documents distributed for information only will not be con-i sidered a controlled copy, and, as such, must be clearly marked and will not be used in performing an activity important to safety since they will not ,

be maintained current. ,

Master lists or equivalonts w.ll be

(]) 7.

established and maintaineo to identify the current revision numbe o f instruc-tions, procedures, soecitications, drawings, and procurement documents.

This list will be distributed to pre-determined responsible personnel to preclude the use of superceded docu-ments.

3.2.3 ResocnslDilities 3.2.3.1 vice President - Administration Responsible via the Director-Fiscal and Information Manacement to estaolish corporate policies in proceoures for GPUN of f-site documant control ano to estaolish ano implement the TMI Site Document Control Program.

III-5 Rev. 9 O

l l

3.2.3.2 Vice President - Nuclear Assurance Responsible via the Director - Qualit/

Assurance

a. for the review ano aoproval o f docu-ment control procedures for quality assurance requirements and document control measures;

b. to evaluate the document control system effectiveness ;hrough review and audit.

3.2.3.3 All Functional Mananrys Pesponsiole for specific document control procedures, as required, wnich meet the corporate occument control policy.

Respcnsible to ensure that documents are available when required; to properly review and approve documents such as procedures, instructions, specifications, dr2aings, etc.

to ensure that changes to documents are reviewed and approved by the sarde organization that performed the original review and approval of the document; to ensure that i

, approved changes are promptly transmitted for s_) incorporation into documents; to ensure that obsolete or superseded documents are eJiminated from use.

3.3 OJality Assurance Recoros 3.3.1 Policy Quality Assurance records for items and ac-tivities covered under the scope of the TMI QA Prc: ram shall be identified, reviewed, retained, and retrievaole. These requirements are imposed on all organizations performing activities important to safety. Quality Assurance record systems shall be described and controlled by approved written procedures and instructions.

3.3.2 Recuirements The procedures established for the generation, collection, storage, maintenance, and re-trieval of TMI Quality Assurance records snall meet the following minimum requirements:

() III-6 Rev. 9

a. Design specifications, procurement doc-

' () uments, test procedures, and opera-tional procedures shall specify the records to be generated, supplied and maintained by or for the owner.

Typical records to be specified include inspection and verification procedures (exclude completed checklists when re-sults are documented in a separate report), results of reviews, in-spections, tests, audits, and material analysis; monitoring of work per-formance; qualification of personnel, procedures, and equipment; and other documentation such as calculations, design verifications, drawings, speci-fications, procurement documents, cali-Dration procedures and reports; non-conformance reports; and corrective action reports.

b. Sufficient records and documentation shall be maintained to provide evidence of tne quality of items or activities important to safety. Inspection and ,

test records shall contain the fol- 1 lowing where applicaole:

1. A description of the type of observation.

2. The date and results of the inspection or test.

3. Identification of any conditions adverse to quality.

4. Inspector or data recorder identification.

3. Evidence as to the acceptability of the results.

i

6. Action taken to resolve any dis-crepancies noted.

III-7 Rev. 8 l

l O

I

c. Documented and approved measures shall

() be established for complying with the requirements of codes, standards, and procurement documents regarding record transmittal, retention, and maintenance subsequent to completion of work.

d. Record storage facilities shall be estaolished and utilizeo to prevent oestruction of quality records oy fire, flooding, theft and deterioration oy environmental conditions such as temperature or numidity in compliance with the standards, codes and regu-latory guides endorsed in Appendix C of tnis Plan.

3.3.3 Resoonsibilities 3.3.3.1 Vice President - Nuclear Assurance Responsible via the Director - Quality Assurance

a. For reviewing procedures for CPU .

Nuclear departments who perform 5 activities related to the maintenance

(]) of Quality Assurance records.

b. For estaolisning a program for tne identification, storage, retrieval, ano maintenance of Quality Assurance records generated by QAD, until they are turned over for storage,

c. For performing planned and periodic audits to verify adequacy and imolemen-tation of Quality Assurance records requirements oy both internal TMI organizations and external organiza-tions.

3.3.3.2 GPUN Vice Presidents Each Division Vice President is:

a. ResponsiDie for the initiation, collec-tion, maintenance, and storage of records in accordance with approved written procedures wnich conform to the requirements and policy of this section

() III-8 Rev. 9

until such time as they are transferred

(') to the Vice President-Administration for storage.

b. Responsible for providing procedures which ensure the maintenance of records sufficient to furnish objective evi-dence that activities affecting quality are in compliance with the standards, codes and regulatory guides endorsed in Appendix C o f the TMI Quality Assurance Plan.

3.3.3.3 Vice President Administration

a. Responsible via the Director-Fiscal and Information Management for tne collec-tion, maintenance, ano storage of records in accordance with approved written procedures and instructions which conform to the requirements and policy o f this section.

b. Responsible via the Director-Fiscal and Information Management for providing ,

proceoures anicn ensure the maintenance i o f records suf ficient to furnish objec-(s) tive evidence that activities affecting quality are in compliance with the standards, codes and regulatory guides endorsed in Appendix C of tne TMI Quality Assurance Plan.

c. Responsible vil the Director-Fiscal and Information Management to estaolisn and implement tne TM1 Records Control System.

3.3.3.4 External Orcanizations Records generated by contractors shall be controlled according to contractor procedures until such time as they are turned over to the QAD for review, acceptance, and transmittal to tne permanent records file. Purchased equip-ment records shall De retained by the vendor until the equipment is released for shipment.

III-9 Rev. 9 O

1 l

1 When required by the procurement documents, l

lh -

contractors and vendors shall establish procedures to control Quality Assurance records. Implementation of these procedures l shall De assured by performance of source i surveillance and audits performed by QAD.

I I

Records to De submitted with the shipment or retained by the vendor will be specifically identified in procurement documents. These '

records will be reviewed as necessary by QAD to provide the required degree of confidence in the adequacy of compliance of the vendor with the requirements o f this section.

i t

lh I

III-10 Rev. 8 i I

k

4.0 Desion Control O 4.1 Policy Measures shall be established and documented to assure that the applicable specified design requirements, such as design cases, regulatory requirements, codes and standards are cor-rectly translated into specifications, draw-ings, procedures or instructions. These measures shall include provisions to assure that appropriate quality standards are speci-fled and included or referenced in design documents for design of systems and struc-tures; external design of systems and structures.

4.2 Reouirements 4.2.1 Design control measures require that:

4.2.1.1 The organizational structure be defined, and authority and responsibility of personnel in-volved in preparing, reviewing, approving and verifying design documents ce delineateo. ,

9 4.2.1.2 The FSAR design bases, FSAR safety analysis, O, design regulations, codes and standards and Plant Technical Specifications including all amendments will be reviewed in tne design process. They will be adhered to unless specific Technical Specification or FSAR '

changes are requested.

4.2.1.3 The materials, parts and processes selected oy design are reviewed to assure that they are suitable for the intended application, includ-ing compatibility of materials, accessioility for inservice inspection, maintenance and re-pair, associated computer programs, and quali-ty standards. The review will also evaluate suitability with regard to hu:aan f actors which may effect safe operation.

4.2.1.4 Internal and external design interface con-trols, procedures, and lines o f communication among participating design organizations and across technical disciplines are established and described for the preparation, review, approval, release, distribution, and revision of documents involving design interfaces.

()

IV-1 Rev. 9 L

J 4.2.1.5 Errors and deficiencies in approved design documents, including design methods (such as computer codes) that could adversely affect items and activities important to safety shall be documentec, and action snall be taken to assure that these errors or deficiencies are correctec.

4.2.1.6 Deviations in specified quality standards snall be icentified and procedures snall be estaolishec to assure their resolution and control.

4.2.1.7 Review of standard "o f f the snelf" commercial materials, parts, and equipment for suita-bility o f application with structures, sys-tems, anc components important to safety shall De concucted prior to selection.

4.2.1.3 Cesign verification methods (cesign review, alternate calculations or qualification test-ing) snall ce estaclishec.

a.2.1.9 Design verification procecures snall be estab-lisnec wnich assure tne following: i O

(j a. The verifier is qualifiec and is not directly responsitle for the design,

b. Verification snall be complete prior to turnover o f the component or system to Operations.

c. Design documents suoject to procedural control incluce, out are not limited to, specifications, calculations, com-l

' puter programs, system descriptions, and drawings, including flow oiagrams, piping anc instrument systems for major i facilities, site arrangements, and equipment locations.

l c. The responsioilities o f tne verifier, tne areas and features to ce verified, I

' anc the extent cf cocumentation snall be identified in procecures.

l i

i l

f's O

IV-2 Rev. 9

( 4.2.1.10 wnen verifications are to be accomplished by test:

a. Prototype, component or feature testing snall be performeo as early as possible prior to installation o f plant equip-ment, or prior to the point when the installation would become irreversible,

c. Verification by test shall be performed under conditions that simulate the most adverse oesign conditions as determined by analysis.

4.1.2.11 Procedures shall be established to assure that computer codes are verified prior to use.

4.1.2.12 Design and soecification changes, including fielc changes, will be suoject to design con-trol measures commensurate with those appliec to the most recently verified cesign. Design changes shall De reviewed and approved by the organiration responsible for the original de-i sign or oy anotner organiration with compar- (

aole expertise designated to review ano ap-prove changes.

4.2.1.13 Measures snall be provicec to assure that re-sponsiale plant personnel are made aware of cesign enanges anc/or modifications, wnich may a f fec t the performance o f tneir Cuties.

4.3 Resconsibilities 4.3.1 Vice Presicent - TMI Unit 1 The Vice President - TMI Unit 1 is responsible through the Plant Encineerino Director for the cevelopment anc implementation o f aesign

' control measures related to routine maintenance anc minor plant modifications.

4.3.2 Vice President - Tecnnical Functions The Vice President-Technical Functions is responsicle for One cevelopment ano implemen-tation o f tne design control measures utilired oy the Technical Functions engineering departments.

IV-3 Rev. 9 s l n.. - - - . , , - - - , , - ~ . , , - . - . , - _ , _ , , . . , , _ , - . , , . _ , . . - - - . . . . - - - . - ,.,,-.,,--., - ,,. .,.. - - -. ,-..,,.___.- n. _ - - - , - .

-. .- - . . - ~ . . . -

( 4.3.2.1 The Vice Presiaent-Tecnnical Functions is responsible througn the Director-Encineering Projects for coorcination anc cirection of plant moaification projects unicn are outside of the normal scope o f Plant Engineering. To fulfill these responsioilities, tne Director-Engineering Projects will:

a. Control and coorcinate the activities of A/E's and tnose contractors with design responsio111ty.

o. Coordinate One ef forts o f tne System Engineering Department anc the Engi-neering anc Design Department. Per-sonnel from tnese home office depart-ments will oe utilized to support tne assignec staf f or to orovice special expertise as requirec.

c. deview anc approve caseline cesign documents such as selected cesign criteria, flow d i s.q r a ms , system descriptions, arrangement crawings, [

one-line ciagrams and logic diagrams, as appropriate.

O Note: This aesign review does not re-place or eliminate One need for cesign verification y One organ-iration wna performec tne cesign.

d. Ensure Quality Assurance review and concurrance o f criteria cocuments and specifications, j 4.3.2.2 The Vice Presicent-Tecnnical Functions, l througn the Director-Systems Encineering, is i

responsiole for:

a. Provicing conceotual anc analytic engineering service to otner engi-i i

neering groups as requirec.

For tecnnical acministration o f nuclear i

c.

fuel-relatec engineering activities.

c. For provicing direct tecnnical suoport to One Unit 1 operating sta f f oy provicing snift tecnnical acvisors.

i l

l IV-4 Rev. 9

() 4.3.2.3 The Vice Presioent-Tecnnical Functions is responsiole, through the Director-Engineerina and Design, for providing cetailea design anc orafting services and for the preparation and maintenance o f the Cuality Classification List (QCL).

4.3.3 Vice President - Nuclear Assurance a

The Vice President - Nuclear Assurance is responsible tnrough the Director Quality Assurance for providing Quality Assurance review anc concurrence with cesign and engineering occuments relating to items anc activities important to safety to assure that appropriate quality requirements have been included. In addition, Qu a!. i t y Assurance will perform planned and periccic audits of responsiole design organizations to verify implementation o f aesign control measures.

i 4.3.4 Other Design Organizations All design organizations performing design activities for TMI shall nave quality progran.s I

which include design control provisions equi-O- valent to tnase provided in tne TMI Quality j Assurance Program.

1 O

IV-5 Rev. 9 v--- ame- 9me t-N w- -p. v-- -v.-w m-,m-- - e3g+e--ww%g e----g,*- .

wy.-g ,-+w q--* - g.* -m-gg- ,-3--m--= y yww-- y -=vw- - rey--w-y

1 _ . .. -

() 5.0 Procurement and Material Control 5.1 Control o f Procurement 5.1.1 Policy

, Procurement o f material, equipment and ser-vices wnicn are consicered important to safety snall be performec in accordance with written i

policies, procedures and instructions. These shall establisn metnads for preparation, i

review, approval, and control of procurement cocuments anc snall provide measures to comply witn applicaole regulatory requirements. Ap-propriate measures shall De estaolisnec to

', evaluate procurement sources, monitor tne ac-tivities o f consultants, vendors anc contrac-tors, and confirm that purenased i tems and services conform to procurement cocument re-quirements. The programs o f all pa rticipant s shall ce i. accordance witn the requirements o f tne TMI Quality Assurance Program.

Tne general ano specific requirements for the 3 Quality Assurance Program of all vendors and I contractors, inclucing tneir suovendors anc l; (]) suocontractors suoplying material, equipment, or services wnich are considered important to l

sa fety , snall ce celineatec by procurement documents. Tnese quality program requirements snall be commensurate witn tne cegree o f com-plexity, tne uniqueness, and One importance to safety of tne items and services ceing per-formed.

Quality Assurance measures snall apply to the procurement o f materials inclucing spare parts, replacement parts, o f f- ne-snelf items and consume'sle . Procurement o f spare or re-placement var;s for structures, systems, anc componen e scall ce sucject to current Quality Asse?.nc ~ rcs am controls and to coces, stan-car o s, an. . r.nical recuirements equal to, or cetter tnan, original tecnnical requirements, or in accorcance witn an approvec engineering cocument. '

I i

V-1 Rev. 8 O

=r ywww e wyy-y y.w wwqv-wwi.,-ww _w --w

--e---e-w .e--.e-aw--n_ ,,.y qwm>

p-my- - , . 9-w----erm --ee m w ay 9 -.mv--w e-- .myi.m.. -ww- ',e---- ---w+ r g y ---

5.1.2 Reouirements 3.1.2.1 Procurement Cocuments The requirements for the preparation, review, approval and control of procurement documents snall be delineated in detailed procedures.

These procedures shall delineate requirements to assure that procurement documents:

a. Specify quality assurance requirements commensurate with the requirements of this QA Plan.

b. Require applicable quality program re-quirements to be passed on to suo-vendors and suocontractors,

c. Specify or reference design bases tech-nical requirements, including applic-able regulatory requirements, material, and comoonent identification require-ments, drawings, specifications, codes and standards, test and inspection re-quirements, and special process in- ,

structions. I

() d. Identify the documentation to oe pre-pared, maintained, and submitted for review, approval and record information as applicable.

e. Include an identification of those items and activities important to safety.

f. Identify those recoros which vendors or contractors shall retain, maintain, and control; and those which vendors or contractors shall deliver prior to use or installation of the item.

g. Include right of access to vendors or contractors and tneir suotier vendor and contractor facilities and records for source inspection and/or aucit.

h. For spare or replacement parts, contain technical requirements at least equi-valent to tnose used for the original procuremenr. The original procurement document may be used as tne technical requirements for purchase of spare or

) replacement parts.

V-2 Rev. 8

1 l

1

() 1. Include the provision that suppliers snall refrain from implementing proce-dures whicr. require owner approval prior to obtaining such approval.

Measures shall be established for the review, approval, and release o f procurement documents and suosequent revisions. The reviews shall assure the inclusion o f the applicable techni-cal, quality, and administrative requirements in procurement cocuments prior to their use.

Review of procurement documents shall be cocu-mented to provice objective evidence of their approval prior to their release.

5.1.2.2 Qualification and Selection of External Organizaticos Evaluations of prospective suppliers shall ce

' conducted and documented to demonstrate quali-fications caseo upon one or more o f the fol-lowing criteria:

i

a. Review of performance histories wnich '

provide records o f suppliers previous

(])

I capaoility to provide similar products or services.

b. Review o f One external organization's caoacility to comply with the criteria o f 10 CFR 50, Appencix S, applicable to the items or services to ce supplied and otner stancarcs.

c. A pre-award survey o f external organi-l zation's facilities and Quality Assur-l ance program to cetermine his capa-i bility to supply the items or services that meet the design and quality requirements o f tne specification.

7 Procecures snali ce estaclishec to accomplisn tne evaluation and selection o f external l organizations. Contracts or purchase or ers i

for material, equioment or services covered oy l tne scope of the Quality Assurance Program

(

I shall De awardeo either to:

i 1. External organizations wno have been l' qualifiec oy the QA0 as naving a Qual-ity Assurance program commensurate with i p v

the equipment or services to ce pro-vided, or V-3 Rev. 8

4 2. The external organization will be re-

quired, by procurement documents, to i

work under the direct control o f the TMI Quality Assurance Program. In these instances, the supplier will not be required to have a separate quality assurance program.

When an external organization quality program 1 is required, it snall be reviewec and approvea prior to initiation of the activity af fected

, by their program.

5.1.2.3 Manufacturina Assurance Measures shall be established to provide con-trol o f manufacturing activities o f vendors.

These methods shall be descricea in aetailed written procecures. The extent to wnich these specific controls will be appliec to vendors will be descricea in inoividual veddor insoec-tion plans. A vendor inspection plan will be prepareo for each major contract witnin the scope of tne TMI Quality Assurance Program.

[

The attributes of the manufacturing assurance

() program sna11 include:

a. Provisions for One review and apareval of the vendor's drawings, Quality 1 Assurance manual and selectec manufac-l turing and quality procedures prior to l fabrication. Vendors may not implement

)

procecures until written notice o f approval is received, if applicaole.

I b. Estaclished vendor inspection plans ,

I that delineate, as required the hold and/or witness points in the manuf ac- {

turing process for specified review, inspection, verification anc test.

c. Metnocs for resolution of nonconfor-mance enere tne vencor's suggestec dis-position is "Use-as-is" o r " Repair" .

j Such nonconformances require approval i

(

V-A Rev. 9 l

O l

I I

l a - __. - . - - - - - - . - - . - _ - -_- .___ - --..- - . ~ _.

i i

r l

l i

. of tne responsible Quality Assurance

' organization. QA0 will also provide follonup of cc rrective action 4 implementation.

i i d. Planned and systematic audit and sur-veillance o f vendor quality activities. l j

Scope of coverage and frequency shall l be determined by the criticality of the  :

4 furnished items and the evaluated re- '

4 suits o f vendor qualifications, includ- i

' ing pre-award surveys and quality proc-ecure reviews. Revisions to audit anc j surveillance plans shall oe made as warranted oy vencor performance.

I l e. Control o f vendor cocument package in-

! cluaing review for completeness and

{ acceptaoility. Inadequate records shall ce suf ficient cause to reject tne items furnished cue to tneir indeter-minate quality status.

4

f. Assessments o f vencor control o f qua.1- ( l ty sna11 De mace at a frequency and depth commensurate with the importance, 1

O complexity and quantity o f tne items furnisned. These. assessments sna11 utilize the qualitative and quantita-tive information provided by vendor noncompliance cocuments; surveillance, inspection and aucit reports; and re-ceiving inspection and test recorcs.

g. Receiving inspection procedures assure tnat:

1. The material, component, or equipment is clearly identified i

and tnat the identification and l quantity correspana to the infor- .

mation on the snipoing cocuments

) and quality records.

l 2. The item's handling anc shipping, j

requirements nave been met ey tne vencor and maintained oy tne car-rier.

T ,

v-5 Rev. a t i ()

l i

rn,- --, r- , ,r.- -

-w.-, ---,v-.- n,w,w--,ec---ne-- ,,a-,ng,_ww ,,me,. -m e.e - - m ,m n w. -,n wnnm me , - ~

3. The item's quality recorc package or compliance certificate is com-plete and acequate.

4. Items celiverac nicn are not in ompliance ni:n requirements are documented in accordance with tne nonconformance procecu e, taggec, segregated (if possiole), and prevented from being inadver-tently issued for installation or use.

5. Items acceptec and released are identified as to neir inscection status prior to forwarcing tnem to a controlled storage area or releasing them for installation or further wor' <.

5.1.3 Resoonsioilities 5.1.3.1 Vice Presioent - Administration The V!;* President - Acministration is respon-gs sicle tncough tne Director - Materials Manage-(_) ment for:

a. tne acministration and operati:n o f procurement anc narenousing activities associatec witn the operation o f :ne TMI NUClea r Sta tion.

o. the assurance na the technical and quali:y requirements, as estaolisned nv engineering, are incorporatec into pro-curement cocuments without revision.

c. the assurance tnat tne contractural, legal anc commercial requirements are incorporatec into tne procurement cocu-ments in a manner unicn nill enforce tne tecnnical or quall;y requirements.

c. The assurance nat cocuments a7c recorcs, as required oy prncurement occuments are suomit ec in c timely manner anc nat :ney are comolete anc i

legiole.

V-6 Rey, p 1

1

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

{} 5.1.3.2 Vice President - Nuclear Assurance The Vice President - Nuclear Assurance is re-sponsible through the Director - Quality Assurance to:

a. Assure that QAD procedures for the con-trol of purchased equipment, material and services are established, approved, '

implemented and effective.

b. Appi)ve all TMI procedures necessary for the control of purchased equipment, material, and services within the scope

.l of the TMI Quality Assurance Program.

c. Approve supplier Quality Assurance Programs to the extent required in the procurement documents.

d. Review and accept supplier record packages.

e. Establish and implement an adequate program of source inspection, survell- -

lance and receipt inspection to assure '

supolier compliance with contract re-O quirements.

f. Rc<iew and concur with the adequacy of quality requirements to determine that they are correctly stated, inspectable and controllable, that there are ade-quate accpetance/ rejection criteria and that the procurement documents have been processed in accordance with es-tablished requirements.

E.1.3.3 Director-Engineerino Projects The Director-Engineering Projects snall maintain a status reference of all external design documents requiring suomittal and distribute such information as required.

5 . .? Indentification and Control of Materials, Parts ano Comoonents 5.2.1 Policy Measures shall ce established to orovioe for the identification and control of materials,

(~'

parts and components important to safety.

j These measures shall assure that incorrect or V-7 Rev. 9 t

I._.. -- -.

() nonconforming items are identified and con-trollec in c rcer to prevent tneir inadvertaqt installation or use, where requirec oy design cocuments, the system estaelisnec snall provice traceasility o f components from tne receipt o f material tnrougn f abrication and testing. Verification shall incluae review of ocjective evidence of inspections and tests which demonstrate tnat procuct identification and control is maintained at various stages of manufacture, installation, or erection.

Identification requirements sna11 oe specifiec in tne applicaole design anc procurement documents.

5.2.2 Recuirements

a. Identification and traceaollity re-quirements shall be incluced in soeci-fications and crawings.

b. Material, pa rt s , and components, in-cluding partially faoricated sucassem-olies or suodiviced materials sna11 se ,

identifiec to precluce tne use of in- i correct or defective items.

O c. Materials anc parts imoortant to safety shall ce identifiec so nat they can ce traced to the appropriate cocumenta-tion, ircluding, out not limitea to:

1. Specifications

2. Drawings (including as-cuilts)

3. Procurement Documents 4 Physical and Chemical Test Reports

5. Nonconformance Reports

6. Inspection Reports anc Cnecklists

7. Storage Maintenance :nstructions

8. NDE Reports

9. Vendor Certificates o f Compliance V-8 Rev. 9 O

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

i 1

i 1

1 I

() d. The location and method o f identifica-tion snall be specified so as not to affect the form, fit, function or  ;

quality o f the item being identified.

l 1

j e. Correct identification of materials,

, parts and components snall be verified j

prior to release for fabrication, snip- ,

j ping, installation, and testing.  !

f. where pnysical identification is eitner i impractical or insuf ficient, physical separation, procedural control, or j otner aoproved means may be employed.

, g. A receipt inspection at the site t i verifles that identification for l received items is complete and accom-

panied oy appropriate documentation.

4

{ 5.2.3 Resoonsioilities (

5.2.3.1 All Encineerino Decartments 4

The Responrible Engineering Department Manager i i is responsible for ensuring that procurement

()

) documents contain appropriate requirements for i the identification and control of materials, r parts, or components.

• 5.2.3.2 Vice President - Nucidar Assurance The Vice Presicent - Nuclear Assurance is responsible tnrougn the Director - Quality Assurance for:

i a. Quality Assurance review and concur-

rence of procedures for maintaining identification in accordance witn tne requirements o f tnis section.

(

I c. Verification o f identification curing

{ receipt inspection.

1 l'

c. Monitoring anc conducting inspections, surveillances and audits to verify con-formance to tne requirements of tnis

section.

, p V-9 Rev. 9 i U l

i

.-__,_-- __- --.,._ -__.,, ...___m,--_.-,,,___ . . - _ . . . , , , _.,...,__._,..._m. , - _ . , - . . . - , .

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

() 6.0 Control o f o f Station Activities 6.1 Poliev Station activities considered important to safety snall ce conductea in accordance witn tne requirements o f tnis Plan. Tnese activi-ties incluce design enanges, procurement, facrication, nandling, snipping, storage, cleaning, erecting, installation, inspection, 1 testing, operation, maintainance, repair, refueling anc modification.

i 6.2 Recuirements Tne Quality Assurance requirements for station activities are containea in this Plan and include compliance wi*1 applicable USNRC Regulatory Guices ano ANSI Standarcs 1.'dicatec

( in Appencix C. Tnese requirements sna11 ce im-piementec in appropriate TMI procedures govern-ing station activities. Tne requirements o f tne Plan apply to all organizations or posi-tions performing functions wnicn a f fect tne ,

i quality o f structures, systems, components, or ' '

activities important to safety.

()

6.2.1 Details Tne following suosections ciscuss typical activities wnicn are representative of tne oroac scope of administrative controls anc quality assurance requirements that are appli-caole to station activities. Tne organiza-tional structures anc functional responsioil-ities governing station activities sna11 De structurec so tnat attainment o f Quality As- I surance Plan oojectives is accomolisnea oy tnose ano nave been assignec or celegatec responsicility for performing tne work; and verification of conformance to estaclisnea requirements is accomolisned oy qualified personnel uno ao not nave cirect responsioility for performing or directly supervising One work. Quality Assurance Department activities sucn as inscection, monitoring, surveillance, reviews and aucits are performed to indepen-cently verify conformance to tnis plan, appli-caole station administration controls, anc applicaole regulatory anc licensing ccmmit-ments. These incepencent verifications are A(_j VI-1 Rev. S

-*vwi w---%-- ------+-- - --

>--++-ig-w-% --e y+-w,------,-s--r,-- w- 7---m-y-wg--y r wg-yww--3,e r m w w-mwpg,-- rp--,-- w w,-,r7-,ww 9-w ww w w ,-wr+ ww-ww viwyvy w'-etr w- vyw gy-

I k s) applied to station activities on a graded approach and to tne extent necessary to provide adequate conficence tnat structures, systems, components, anc personnel perf orm satis f ac-torily to maintain the sa fety o f One station.

Station work functions suen as routine and abnormal operations, maintenance, repair or rework, in-service insoections, tecnnical specification compliance, fuel nancling, rac-waste nandling, radiation protection, enemical analysis, nousekeeping and cleanliness, fire protection, security, training, environmental requirements, nealtn anysics, and otner act.vi-ties consicerec imcortant to safety *nicn are discussec in :ne Quality Assurance Plan are controlled to an extent consistent with their importance to safety.

6.2.1.1 Control of Inscection A program f or inspection o f activities a f fect-ing quality snall ce estaclisned anc executec by, or for, tne organization performing tne activity to verify conformance to tne cocu- ,

mentec instructions, procedures, anc drawings i 7s for accomplisning the activity. Design speci-(,) - -- --

fications, crawings, procecures, or instruc-tions snall incluce tne necessary inscection requirements. Tnese repuirements incluce acceptance criteria anc reference to coces, stancarcs, anc regulatory cocuments. These requirements sna11 ce furtner ::anslatec into inspection procedures, instructions, or enecklists unicn snall centain, as required, tne following:

a. Icentification o f enaracteristics anc activities to ce inspected.

b. Inspection me tnccs.

c. Icentifica icn o f crganization resoonsicie for performing :ne inscection.

c. Acceptance anc rejection criteria.

e. Identification o f acplicaole revisions o f recuirec crocedures, crawings anc scecifications.

("3 v'

VI-2 Rev. S

Documentation of inspection results

()

f.

including identification of tne inspector.

g. Listing of necessary measuring and test equipment including their accuracy requirements.

Inspectors (including NDE personnel) shall be qualified in accordance witn applicable codes, standards and TMI training programs and tneir qualification and certification shall be kept current and documented.

Individuals performing inspections snall be other than those who performed or directly supervised the activity being inspected and shall not report directly to the immediate supervisors who are responsiole for the work activity being inspected. If the in1ividuals performing inspections are not part cf the responsible Quality Assurance organization, the inspection procedures ano personnel qualifica-tion criteria shall ce resiewed and concurred with by the responsible Quality Assurance ,

organization prior to the initiation of tne  !

inspection activity. Inspection of activities O. as defined in ANSI N45.2.10 may be conducted by second line supervisory personnel or oy other qualified personnel not assigned first line supervisory responsiollity for tne conduct of work. These inspections, i.e., those performed by individuals not assigned first line super-visory responsibility, are not intended to dilute or replace the clear responsibility of first line supervisors for the quality of work performed under tneir supervision. When inspections associated with normal operations of the plant (such as routine maintenance, l surveillance and tests) are performed oy individuals otner tnan those wno performed or directly supervised the work, out are within tne same group (reporting to different super-

visors), tne following controls shall be met

1. The quality of the work can be l demonstrated through a functional test when tne activity involves creaching a pressure retaining item.

VI-3 Rev. 9 i

l L

2. The qualification criteria for inspection personnel are reviewed and

' O found acceptable by the Quality Assurance organization prior to initiating the inspection.

Work authorization documents relating to work considered important to safety shall be re-viewed and concurred with by Quality Assurance Department personnel to determine the need for:

a) inspection, b) identification of inspection organization, c) identification of inspection witness and hold points, d) documenting inspection results.

i When hold coints have been established, either contractually by procurement or internally by plant procedures, work may not proceed until either insoection is performed or waived by the responsible Quality Assurance organization.

Inspection of modifications, repairs, and replacements shall be by the same method and to tne same criteria as the original inspection or by an approved, documented, engineering and QA alternate. Where verification of inspection is .

being performed on previously accepted lots, 8 sampling inspection shall be representative and O only to the extent necessary to assure adequacy of control. The sampling plan shall be deter-mined by Quality Assurance. Inspection person-nel shall be provided with suitable equipment and tools, which are calibratuJ as necessary, and controlleo to assure that accuracy requirements are satisfied and that inspections are complete.

Inspection data and results shall be evaluated 4

by designated personnel to assure that the inspection objectives have been Tiet and that items requiring action or follow-up are iden-tified and documented.

Records shall be kept in sufficient detail to provide adequate confirmation of an inspection program.

6.2.1.2 Plant GA Monitorino s

A program for QA Monitoring of activities affecting important to safety materials, parts, VI-4 Rev. 9 O

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

I l

f

() components or processes shall be estaclished and executed by Quality Assurance.

i Monitoring is used to estaolish adequate con-fidence levels that important to sa fety activi-ties are being performed in accordance witn i

Quality Assurance Program requirements and plant administrative controls. Monitoring will '

be performed on a graded approach and the aegree of monitoring performed shall be typically based upon the status and safety importance o f activities, degree o f previous experience, consistency of overall coverage, unicueness o f testing or operating activities and trending data.

Monitors snall be qualified in accordance witn a documented Quality Assurance Department '

procedure that insures that Monitors are knowledgeaole in the activities tney are moni-toring to the extent tnat tney can readily verify compliance of tne activity ceing performed.

i Monitoring reports shall contain as a minimum I the following:

a. Identification o f activity oeing monitored including specific reference to tne program or procecural requirements governing the activity.

l

. b. Indication of compliance.

c. Identification o f monitor

d. Appropriate distrioution to supervisory or managerial personnel that have responsiollity for the performance o f the activity.

, e. Identification o f eacn nonconformance l cocument wnen sucn nonconformances exist t

and are identified as a result of tne monitoring.

Raccres sna11 ce kept in suf ficient detail to

, provice adequate confirmation of a monitoring program.

VI-5 Rev. 8 i

O l

l I

_ _ _ _ _ - - . _ - - - . - - - - - - - - - - - - - - - - - - - - - - ~ - - - ~ ~ ~ - - - - - - ~ ~ ' - - -

6.2.1.3 Control of Soecial Processes O Special processes are those that require inter-im in process controls in addition to final inspection to assure quality including, out not limited to, such processes as welding, heat treating, chemical cleaning, and nondestructive examination.

Measures shall De established and documented to assure that special processes are accomplished under controlled conditions in accordance with applicable codes, standards, applications criteria, and other special requirements in-Ciuding the use o f qualified personnel and procedures.

Procedures for special processes shall be established to meet the requirements, applic-able codes and standards or to meet the recuirements of s,cacial process specifications whicn may be produced for TMI. These proce-dures shall provide for recording evidence of acceptable accomplishment of special pro-cesses. Procedures and instructions for the ,

control of special processes shall be reviewed I and approved by qualified personnel.

() dures, equipment, and personnel performing special processes shall ce qualified in accord-Proce-ance with applicable codes, standards, and specifications. Organizational responsioili-ties shall be delineated for the qualification of special processes, equipment and personnel.

Qualification records of personnel, equipment, and procedures associated with special pro-cesses snall be estaolished, maintained and kept current. For special processes not covered by tne existing codes or standards, or when item quality requirements exceed the requirements of establisned codes or standards, the necessary qualifications of personnel, procedures and equipment shall be defined in the procedure.

6.2.1.4 Test Control A documented test program shall De established to assure that all testing required to demon-strate that tne structure, system or component considered important to safety will perform satisfactorily in service. The tests shall De performed in accordance with written, approved, and controlled test procedures unich incor-() porate or reference the requirements and VI-6 Rev. 9 i

I')

\~/ '

acceptEnce standtrds contained in the appli-cable ec s ign docui.'en ts. The extent of testing snall ce basec cn the complexity of the mocifi-cation, replacemen , or repair. Testing, including proo f tests prior to installation and preoperational tests, necessary to cemonstrate that structures, systems and components will perform satisfactorily in service, shall De accomplisned in accorcance with written approved procedures. Tnese procedures snall ce based on requirements and acceptance limits contained in applicaole design anc procurement documents. These test procecures or instruc- '

tions shall provice for the following as requirec:

a. A description of the test ocjective.

D. Instructions for performing tne test, including caution or safety notes in sufficient detail to avoic operator interpretation.

c. Test prerequisites sucn as calibratec .

instrumentation, adecuate test eculoment i es

(,) anc instrumentation including accuracy requirements, completeness of item to ce testec, suitaole and contro11ec environ-mental concitions, anc trained qualifisc and licensec or certifiec cersonnel,

c. Provisions for cata collection and storage.

e. Acceptance and rejection criteria as specifiec in cesign and procurement cocuments.

f. Metnocs o f documenting or recorcing test cata and results, in sufficient cetail to prevent misinterpretation,

g. Provisions for assuring tnat test pre-requisites have Deen met.

n. Mancatory noic or witness points for inspection oy TMI Quality Assurance and/or otner designated oersonnel.

1. Provisions for control o f jumpers, lifted leads anc juriscictional or safety tags.

VI-7 Rev. S

l f () J. Provisions for returning a system to normal configuration upon completion o f the test, including verification.

Test results shall be documented, evaluatec, and their acceptability determined by a responsiole individual or group.

l The test program snall cover all required tests including.

1. Preoperational tests of cumponents or l' systems to demonstrate that performance is in accordance with the design intent.

2. Tests curing initial operation to demonstrate system performance (that could nct be tested prior to operation) to confirm compliance to design criteria.

3. Tests during the operational phase to provide assurance that failures or

, suostandard performance do not remain undetected and that the required rella- .

i bility of systems important to safety is i maintained.

1

4. Tests during activities associated wita plant maintenance during the operational phase and to demonstrate satisfactory performance following plant maintenance or procedural enanges.

' Tests performed following plant repairs or replacements snall be conducted in accordance with the original design and testing require-

, ments or engineering approved, documented alternatives. Testing snall be suf ficient to confirm that the changes reasonaoly produce expected results and that tne cnange does not reduce sa fety o f operations.

6.2.1.5 Control o f Measurinc anc Test Eculamen t Measures snall be estaolisned to assure tnat tools, gauges, instruments, anc other measuring and testing cevices used in activities a f fect-ing tne function or quality o f structures, systems, anc components coverec under the scope of ne TMI Quality Assurance Program oe properly controlled, caliarated, anc adjusted

() VI-8 Rev. 9

'1 1

f

l j . . . .. _. .. ._ _ ._ .

' (} at specified periods to maintain accuracy within specified limits. Additional measures shall be estaolisned to ensure the range, type and accuracy o f test equipment conforms to the specified testing requirements.

Requirements for eacn control program shall include inspection and verification o f accuracy upon receipt o f equipment, identification of all gauges and instruments, calibration an.

schedulec recall for calibration and trace-aoility to an accepted Standard. Thesc

activities snall be a oject to QA0 monitoring anc auditing. Procedures snall be estaolisned i

to implement the fcllowing requirements:

l a. To estaolisn the calibration technique and frequency maintenance, and control

' of all measurirg and test equipment wnich are used in the measurement, inspection, anc monitoring o f compo-nents, systems, and structures covered under the scope o f tne TMI Quality Assurance P cgram (instruments, tools, k gauges, fixtures, reference and transfer '

standards, and nondestructive examina-(]) tien equipment).

b. Tne identification of measuring and test equipment traceacle to tne calioration l test data.

c. Installed operations measuring and test equipment requiring calloration shall be labelled, tagged or otnerwise controlled in accorcance witn written, approved procecures to assure that approved calibration intervals are not exceeded.

Portable measuring and test equipment may be similarly controlled; out snall, as a minimum, be clearly labelled to indicate tne date on snich tne current calibration expires. Portacle measuring anc test equipment that nas exceecec tne approved caliaration interval snall not ce used for measurements or tests.

d. Estaolisn calloration frequency for measuring and test equipment casec on requirec accuracy, purpose , degree o f VI-9 Rev. 8

-,~~n,- .------, -, ,. w.,- - --,---.n --r 1.- NT ?,T ?,.X,1. , i ^ , : : ?  ;--,- - , - - - - - , - , - , - . , , - - , - - - - - , - - .. ----

() usage, staDility characteristics, and/

or any other condition wnich may hffect the c ;asurement. A calibration recall sy..em shall be implementee to assure recalloration witr.in tne required period for eacn piece o f me suring and test equipment covered unaer the scope of this program.

e. Metnocs for determining the validity of previous inspections performed when tne measuring and test equipment is founc to j

.ce out o f calibration. Inspections or tests are repeatec on items determined to De suspect. Such cetermination is to be documented in suitacle form. If any calibration, testing or measuring device is consistently founc to ce out of calibration, it snall be repaired or replaced.

1

f. Calibratio snall ce against standards that have an accuracy o f at least four i

times the requirec accuracy o f the ,

equipment being callorated. When this i l 1s not possible, stancaras snall have an Q

accuracy tnat assures tne equipment being calibrated will be witnin requirec talerance anc :nat the casis o f accept-ance is documen*.ec ano authorized oy the supervisor o f tne callarating organiza-tion.

g. A status of all measuring and test equipment under the calibration program is to be maintainec.

n. Utilization o f reference anc transfer stancards traceacle to nationally

[ recognizec stancarcs. Where national

( stancards do not exist, provisions snall ce estaolished to cocument tne basis for the calibration.

i. NDE equioment, sucn as ultrasonic equipment, sna11 ce contro11ec anc callorated in accordance with tne ASME coce governing its use.

VI-lO Rev. 6 O

l 6.2.1.6 Handlinq, Storage and Shiocing O Measures shall be established and documented to control handling, storage, and shipping, including cleaning, packaging, and preservation of it3ms important to safety in accordance with established instructions, procedures, and draw-ings to prevent damage, deterioration or loss.

4 Procedures shall be established to control the <

cleaning, handling, storage, packaging, and shipping of materials, comprnents, systems in acccrdance with design and procurement require-ments to preclude damage loe.s or deterioration 1 oy environmental conditions such as temperature or humidity. These procedures shall oe implemented by suitably trained individuals.

The procedures shall include an assessment of, but not limited to, the following:

a. Dackaging and preservation procedures to provide assurance of adequate protection against corrosion, contamination, physi-cal damage or any ef#ect which would lower the quality of the items or cause ,

them to deteriorate during snioping, I handling or storage. Special protective

(]) environments, special coverings, inert gas atmosphere, allowable moisture con-tent, and temperature level shall be specified as required and their existence verified and documented.

b. Cleaning methods to provide assurance that necessary cleaning operations are carried out prior to packaging, storage or installation. The level of cleanli-ness required, and verification and l documentation requirements shall oe i specified in the procedures.

c. Detailed handling methods for all items that require special handling. Special handling tools and equipment snall oe provided and controlled to ensure safe and adequate handling. Tnese tools and equipment shall be maintained, inspected and tested in accordance with written procedures at estaolished intervals to ensure their reliaoility and availa-bility for use.

l

() VI-11 Rev. 9

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

Storage practices to provide for methods f'T s/

d.

of storage and the control of items in storage which will minimize the pos-siollity of demage or deterioration during storage. Periodic inspections of storage areas shall oe performed and documented to verify compliance with storage procedures. Release of items for installation shall also be proce-durally controlled.

e. Provisions to assure that proper marking and labeling of items and containers is accomplished to provide identification and necessary instructions during packaging, shipment and storage.

f. Provisions for documenting and reporting nonconformanc0 to handling, and shipping requirements.

g. Provisions for the storage of chemicals, reagents, lubricants and other consum-able materials which will be used in conjunction with systems which are ,

important to safety. '

h. Provisions for " Limited Life" require-ments (including " Shelf Life" and

" Service Li fe" for applicable materials).

6.2.1.7 Insoection, Test, and Goerating Status Measures shall be established and documented to ensure that the required inspections and tests are performed and that the acceptability of items with regard to inspection and tests per-formed is known throughout manufacturing, installation, and operation. Status of items covered by the scope of the TMI Quality Assur-ance Plan shall De controlled in accordance with approvcd procedures. These procedures shall inclide the use of appropriate tags, markings, .ists, logs, diagrams, or otner suitable means, to assure that required inspections and tests are satisfactorily completed to prevent inadvertent cypassing of required inspections and tests and to prevent inadverent operation.

VI-12 Rev. 9

[}

i

( ~

The requirements for an acceptable inspection, test and operating status program for 1 l' structures, systems, and components throughout faorication, installation, test and operation 4

include:

a. Design and quality cocuments *nich address the requirements for tne identification o f. inspection, test, and operating status of structures, systems and components.

i

o. Procedures wnien include controls for the application and removal o f inspec-tion anc welcing stamps, and other status indicators such as tags, markings, labels, and stamps.

4

c. Procedures for centrolling the bypassing '

or altering of the sequence of required l inspections, tests or other critical i operations procedurally controlled by

~ngineering procedures with concurrence by the appropriate quality organization. -

Where necessary to preclude inadvertent I 3

() oypassing of required inspections anc '

tests, the procedures sna11 provide for the icentification o f items wnien nave ~--

passed such inspections and test.

d. In cases unere cocumentary evicence is not available to confirm that an item nas passec required inspections anc tests, tnat item shall te considerec nonconforming until such evidence becomes availacle. Affected systems shall also be consicered to be in-l cperaole and reliance sna11 not be placed on such systems to fulfill their intended safety functions.

j

e. Procedures to be provided to require identification of the operating status o f systems, components, controls, or i support equipment in order to prevent l inaavertent or unautnorized operation.

' These 'JroCecures shall require Control measures suen as locking or tagging to 1 secure anc identify equipment in a controlled status. Incependent verifi-cation snall ce required, where

, appropriate, to ensure that necessary

! )

VI-13 Rev. 9

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

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

l 1

() measures, such as tagging equipment, have oeen implementeo correctly.

f. Metnods wnien ensure tempora ry i

modifications snall be controlled by approvec procecures *nien include a requirement for indepencent verifica-tion. A log shall oe maintained o f the current status o f sucn temporary mocification.

g. Methods ahlen ensure nonconforming services and inoperative or malfunctioning structures, system, components or materials snall be

.l identified in accordance with the requirements o f tnis Plan.

6.2.1.8 Housekeecino anc Cleanliness Housekeeping practices on a regularly senedulec casis shall be utilired recogniring the requirements for tne control of radiation renes and the control of work activities, conditions .

and environments tnat can af fect tne quality of f important parts o f tne nuclear plant. House-O keeping encompasses all activities related to the control o f cleanliness o f f acilities, materials, equipment ' ire prevention and pro-tection inclucing cioposal o f comousticle material and decris and control a f accesses to areas, protection o f equicment, radioactive contamination control ano storage o f solic radioactive waste. Housekeeping practices shall assure tnat only proper materials t

equipment processes, anc procecures are, utilired anc tnat ne quality of the item is i

not cegraced as a result of nousekeeping practices or techniques. During maintenance l

activities, certain portions o f sa fety-relateo systems or components may de subject to poten-tial contamination witn foreign materials. To prevent sucn contamination, control measures, inclucing measures for access control, sna11 ce estaclisnea. Accitionally, immediately prior l to closure o f system (s) or component (s), an inscection snall ce concucted anc documentee to l ensure cleanliness. Special nousekeecing considerations snail oe mace for maintenance o f

! racloactively contaminatec systems for l comoonents, r

I

() VI-14 Rev. 9 y+== ---------m.g,w--m

y. i'-g.ai g9wwm,pm e-,ymi, 9:H.a,g.&--- ,w g-. .-m,.y.,ny.,m.--.. ,,-gi...,9%,.v-.--,a,,w-y-,---g---w. ,

6.2.1.9 Equipment Control Permission to release installed equipment or

, systems for maintenance shall be granted by 4 designated NRC SRC licensed operations personnel. Procedures shall be provided for control of equipment, as necessary, to maintain personnel and reactor safety, to avoid '

unauthorized operation of equipment, and to assure that operational equipment is in a ready status. These procedures shall require:

a. Contrcl measures such as locking or tagging or secure and identify equipment in a controlled status,

b. Independent verifications, where appropriate, to ensure that necessary measures, such as tagging equipment, has been implemented correctly.

c. Control measures for temporary modifica-tions, such as temporary by-pass lines, electrical jumpers, lifted electrical leads, and temporary trip point set- ,

tings. Included shall ce a requirement i for independent verification. (A log O, shall ce maintained of the current status of temporary modifications.)

d. Control of inspection and test status on individual items by the use of markings such as stamps, tags, labels, routing caros or other suitaole means.

e. When equipment is ready to be returned to service, operating personnel shall place the equipment in operation and verify and document its functional acceptability.

f. When traceabi.lity is required as determined by Engineering and Quality Assurance, the components / equipment shall De identified in such a manner that they can be traced to its associated documentation.

VI-15 Rev. B

p 6.2.1.10 Control o f Construction, Maintenance (Preven-tive/ Corrective) ano Mocifications Construction, maintenance or modifications which has tne potential to af fect the function-ing o f structures, systems or components important to safety snall be performed in a manner to ensure quality at least equivalent to that specified in original design bases and requirements, materials specifications and inspection requirements. A suitaole level of confidence in structures, systems or components on wnich maintenance or modifications nave been performed snall oe attained by appropriate inspection ano performance testing. Cons tru c-tion, maintenance ur modj fication o f equipment snall be preplanned and performeu in accordance with written procecures, documented instruc-tions or drawings appropriate to the circum-stances wnich conform to applicaole codes, standarcs, specifications, and criteria. Skills normally possessed by qualified maintenance personnel may not require cetailea step-by-step da;ineations in a written procedure but are -

sucject to general administrative procedural '

controls tnat govern or define the following

(]) areas:

a. Methods for ootaining permission and clearance for operation personnel to work and for logging sucn worx.

c. Factors to ce taken into account, including the necessity of maintaining occupational raciation exposure as low as is reasonably acnievable (ALARA).

c. Metnad for identification o f what orocecural coverage is necessary for tne maintenance, construction and modifica-tion activity.

( d. Considerations for system / equipment cleaniness control.

I

e. Metnod for icentification o f post maintenance, construction or mooifica-tien, testing, including system / equip-ment functional caoacility to meet i operational requirements in all respects.

t l

) VI-16 Rev. 8 1

1

f. Metnod for ensuring that maintenance, contruction or modification activities, performed either on-site or of f-site, are properly reviewed.

The following type of activities are among those that may not require detailed step-by-step written procedures:

1. Gasket replacement

2. Trouble snooting electrical circuits

3. Replacing chart or drive speed gears or slide wires on recorder.

Means for assuring quality of maintenance, modifications or construction activities (for example, inspections, measurements, tests, welding, heat treatment, cleaning, nondestruc-tive examination and worker qualifications in accordance with applicable codes and standards) and measures to document the performance thereof shall be established. Measures shall be established and documented to identify the ,

inspection and test status of items to De used i in maintenance modification, and construction O activities.

A corrective maintenance program shall be oeveloped to maintain structures, systems and components important to safety at the quality required for them to perform their intended functions. Corrective maintenance shall be performed in a timely manner to insure tnat important to safety items are adequately maintained in the original, design, functional status.

A preventative maintenance program including procedures as appropriate for structures, systems, aru components important to safety shall be estaolished which prescribes the frequency and type of maintenance to be per-formed. In all cases, maintenance shall be seneduled and planned so as not to compromise the safety of the plant. Planning shall consider the possible safety consequences of concurrent or sequential maintenance, testing or operating activitias. Preventive mainte-nance shall be performed in a timely manner to O( / VI-17 Rev. 9 i

p)

(, insure tnat important to safety items are aceauately maintainec in tne original, cesign, functional status.

6.2.1.11 Procecural Reouirements Measures snall be establisned to control and coorcinate tne approval and issuance o f docu-ments, including enanges, wnien prescrice all activities affecting quality. Those documents which are consicerec important to safety require a documentec Quality Assurance Depart-ment review. Tnis review is to provice an incepencent verification tnat the procecures have Deen oreparec, reviewed and approved in accorcance witn establisned policy and program controls; tney contain the necessary policy and program requirements including tne inspection anc verification requirements unere applicaole; and tney contain clear descriptions relatec to tne extent o f documenting results o f completec actions anen required. These documents include operating anc special orders, operating proce-dures, test proce "res, equipment and material ,

control procecures, maintenance or mocification i proceaures, and refueling orocedures. Plant

(~')

procecures snali ce reviewec oy an incivicual knowiecgeaole in ne area af fectea cy tne pro-cecure no less frequently tnan every two (2) years to determine if change,s are necessary or cesiracle.

6.2.1.12 Control o f Surveillance Testinc and Inscection A surveillance testing and inspection program shall ce estaclisnec to insure tnat imoortant to safety structures, systems, and components will continue to coerate, keeping parameters witnin normal counas, or will act to put tne plant in a safs concition if they exceed normal bouncs.

Provisions snali ce mace for performing re-cuirec surveillance tasting and inscections, inclucing inservice inspections. Sucn provi-sicns snal incluce tne estaclisnment af a master surveillance senecule reflecting tne status o f all plannec inplant surveillance tests anc inspections. Frequency o f surveil-lance tests anc inspections may oe relatec to tne results r f reliacility analyses, tne

() VI-18 Rev. 3

frequency and type of service, or age of the

() item or system, as appropriate.

i Additional control procedures shall be insti-

tuted, as necessary, to assure timely conduct of surveillance tests and inspections and appropriate documentation, reporting, and evaluation of the results. Following the completion of testing, procedures shall be established to assure the return of systems to an operable status. These procedures shall include provisions for the documentation of authority, conduct, respons10ility, and verification involved in returning the sye.em to an operable status. Such provisions anall include the use of procedures, checklists, and independent verification as appropriate, considering the degree that system status was altered during the performance of the test.

6.2.1.13 Radiation Control Procedures shall be provided for the implementation of a radiological control program. The radiation control program i.

involves the acquisition of data and provision I of equipment to perform necessary radiation

() surveys, measurements and evaluations for tne assessment and control of radiation conditions associateo with TMI.

6.3 Resoonsibilities 6.3.1 GPUNC Management GPUNC Managers with direct responsibility for activities described herein are responsible for the implementatien and compliance of tne Quality Assurance olan and directly responsible to insure their respective activities and responsibilities are conducted in accordance with applicable administrative controls,

regulatory and licensing requirements.

6.3.2 Delecated Autnorities Contractors or other agents outside G?UNC who are assigned or delegated responsibilities and/or activities governed oy this Plan shajl comply with the applicable requirements of the Plan.

O VI-19 Rev. 9

4 i

i i

() 7.0 Control of Radioactive daste

{ 7.1 Policy j ,

Measures sna11 oe estaolisnec anc cocumentec to assure tnat :ne applicaole requirements of the Code of tne Federal Regulations, Title 10,

! Part 71 anc Title 49, Parts 100 enrougn 129 l applicaole to tne pacxaging anc transporting '

of radioactive wastes are satisfied. Appencix i

E to 10 CFR 71 identifies tne quality as- ,

surance criteria applicaole to tne control of j *acicactive waste.

i  !

ine applicaole portions of tnis Plan :nat -

] relate to One criteria in Appendix i to 10 CFR 71 describe to a large extent tne acmini-

! strative controls anc quality requirements to i

j ce appliec in tne control, packaging and transpor:ation of racioactive material. Tne applicaole sections of tnis Plan will oe implemented to satisfy tne requirements of '

Appencix E to 10CFR 71. Typically, Sections 6.2.1.1 :nru 6.2.1.6, 6.2.1.9 anc 6.2.1.13 4

apply to Control of Racicactive naste. g

! 7.2 Recuirements i

4 i

7.2.1 P:ccecures snali ce developed and implemented to cover tne following:

a. Processing of racicactive eastes including tne collection, nancling anc preparation for snigment of racioactive i'

liquias anc solics. These proceoutes sna11 ce consistent 41:n :ne ALARA program and snali clearly icentify :ne administrative controls anc o rganiza-tional responsioilities.

c. Training and qualifica:lon of personnel j operating racioactive waste processing eculament, neal:n pnysics monitoring, i

packaging anc snipping and otner opera-tions ceeme: appropria:e oy management.

c. Tne activities associatec witn tne  ;

packaging of racioactive eastes to I include

ne proper selection of :ne receptacles to ce usec for containing

, the easte materials, tne selection of One snipoing containers (structures

()

1 VII-1 Rev. S 4

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

() used to contain and support tne receptacle and its contents) Health Physics inspections of the packaging prior to release, proper markings on the outside of the package anc the preparation of snipping papers anc certificates.

d. Movement of radioactive .aaterials witn-in and outside tne protected area to assure personnel protection at all times.

e. The shipment of radioactive material from tne Station to be in accordance with tne regulations of tne U.S.

Department of Transportation for tne transportation of nazardous materials (49 CFR) anc of tne NRC (10 CFR 71).

f. Tne packaging used for transporting of radioactive wastes, whetner purenased from an outsice supplier or oesigned oy GPUNC, shall meet the applicaole re- ,

quirements of 10 CFR 71 and 49 CFR.

{

O 7.2.2 The carriers to ce used for transporting of radioactive wastes shall ce selected on tne .

basis of neir experience, knowledge of 00T regulations, control anc maintenance of eneir equipment and tne selection anc control of tneir drivers. Tne carrier is requireo to have or snali ce supplieo documented proce-dures covering acceptance of ;naterials f rom a snipper, certification requirements, placard-ing, stowage control, reporting of incicents anc security.

7.2.3 Radwaste operations snall ce controlled to minimize personnel exposures or environmental i

contamination consistent witn 4LARA.

( 7.2.4 Operations procecures sna11 ce reviewec oy QA0 to estaolisn any necessary witness or nold points or activities to be monitorec.

l l

l VII-2 Rev. 8 i

I

() 7.3 Resconsicilities 7.3.1 Vice Presicent - TMI Unit 1 7.3.1.1 Ine Vice Presicent - TMI Unit 1, tnru tne Operations and Maintenance Director-TMI-l snall develop anc implement procecures for processing activities anc movement of radioactive materials.

7.3.1.2 The Operations and Maintenance Director-TMI-l snali ce responsicle for tne processing anc packaging of liquid wastes anc for tne pacxaging of solic was:es in preparation for snipment.

7.3.1.3 Ine Oparations and Maintenance Director-TMI-1 is responsicle for tne collection and icentification of radioactive solics, sucn as rags, papers, Occts, gloves, etc., and naving tnem movec to One Radwaste facility for packaging.

7.3.1.4 Tne Operations anc Maintenance Jirector-TMI-l ,

is responsiole for tne selection of the proper i packaging for tne soecific contents to ce

,q snippec, taking into consideration tne U raciation levels, contamination limits ano snipping requirements. Raciological Control surveys One packaging for raciation level and, if acceptaole, tne Operations Jepartment marks tne outsice of :ne package witn :ne appro~

priate .narkings, completes tne snipping papers and certificates, attacnes One security seal anc advises tne carrier tnat the shipment is ready.

7.3.1.5 Ine Operations and Maintenance Jirector-TMI-1 shall review and accept carrier procecures specifiec cy ne procurement cocuments covering :ne acceptance of racicactive 4aste materials for snigment.

l 7.3.1.6 Plant Engineering Jirector-TMI-1 is responsi-cle to oo:ain review and accectance of :ne cesigns of packaging purenasec f rom an outsice supplier.

i i

VII-3 Rev. 9

()

l

7.3.2 Vice President -

Raciolocical anc Environmental Control ine Vice Presicent - .4adiological anc Environmental Cont:ci is resocnsiale, :nru :ne Manager, Radiological Control, for monitoring all raciological activities associatec aitn ene processing anc nancling of radioactive sastes and fcr provicing advice on radiological matters relating to processing, packaging and shipping.

7.3.3 Vice President -

Nuclear Assurance The Vice Presicent - auclear Assurance is responsicle, tnru :ne Director-Quality Assurance:

a. -or review anc concurrence with procedures descricing con;;o1 of radioactive waste.

c. To monitor, inspect ano audit radioactive waste processing operations to tne extent to verify :ney are f performec in accorcance with estaclisne:

procedures, applicaole acministrative O- - - - -

controls anc regulatory requirements.

7.3.4 Eacn manager snali es aclisn :ne requirements for personnel cualification anc institute training and incoc :1 nation :: satisfy :nese requirements. Training requirements sna11 ce consisten: witn tne importance anc complexity of tne activity performec.

l l

i l

1

($) VII-u Rev. 9

- - --- r - = = - -

t

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

l

! 8.0 Control of Corrective Actions and j Nonconformances 1

8.1 Policy Nonconfor.ning materials, parts, components, .

services or activities witnin the scope of tne l

QA Plan shall ce controlled to prevent neir inadvertent ut111:ation. Measures snall be ,

established whien ensure tnat conditions adverse to quality, sucn as f ailures, inalfune-tions, ceficiencies, deviations, cefectise material anc equipment, anc nonconformances ce promptly identifiec ano correctec. ine cause of tne condition adverse to quality sna11 De determined and appropriate action taken to precluce repetition. The icentification, cause, and actions taken to correct conditions aaverse to quality shall ce cocumented ano reoorted to One aapropriate levels of ma.;agement.

Significant conditions witnin tne intent of 10CFR 50.55(e) or 10 CFR 21 sna11 be reportec 2, to approcriate mar,ogement levels within tne i af fected organization for review and evalua-tion.

S.2 Recuirements Procecures shall ce estaolishec unicn etail i

anc implement ne following corrective action i

system measures:

1'

a. Conditions adverse to quality saall ce evaluated to determine tne neec for

! corrective action.

j o. Corrective action cocumentation sna11 include identification, cause, anc

! actions taken to correct anc to pre-clune tne similar recurrence for conci-tions adverse to quality. Corrective action documentation requires con-i currence oy QA0.

c. Follow-up activities snall ce concucted to verify implementation of corrective actions ano to close cut corrective action in a timely manner.

! 3. Significant ca.^1ciencies, noncon-formances anc cefects, potentially l VIII-l Rev. 5 i e i

i I

O reportaole under 10 CFa 50.55(e) o r 10 CFR 21 snall ce reported to appropriate .

management levels for evaluation anc possiole reporting to the Nuclear Regulato ry Commission.

e. Procedures snall ce estaclished for control of nonconforming materials, '

parts, components, services, or activ-ities. These procecures sna11 aadress and detail measures to implement the following requirements:

1. .4easures for the identification, documentation, segregation, and dispositions of nonconforming materials, parts or components.

2. Disposition of nonconformances shall ce made oy tne organization that estaolishec tne governing l requirements or, if tnis is not possible, oy tne organization with current cesign engineering '-

responsibility for tne item. QA0 concurrence is requireo if the I.

cisposition is "use-as-is" or

() " repair."

3. NonConformance reports snall ce used to identify materials, parts, components, and activities

( *nien are not in compliance witn

] tne requirements of specifica-

)

' tions, codes, crawings, ana ce-tailed installation or manufac-turing program requirements.

I This sna11 include use of noncon-formance reports on items unose status is indeterminate due to the lack of cocumentation. Non-conformance reports on items sna11 contains One following minimum information:

(a) Icentification o f tne acn-conforming item or activity ano cate of inspection.

(c) Icentification o f tne initi-ator of cne nonconformance repo rt .

t i O v VIII-2 Rev. 9 3

I

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

i

() (u) Description of the noncon-fo rmance. .

(d) Disposition of tne noncon-formance ( repair, re ork, j use as is, or scrap).

I 4

(e) Inspection requirements.

( f) Aequired approval signatures of the disposition and tne verification.

(g) Evicence of review for re-porting per 10 CrR 50.55(e) or 10 CFR 21.

4 Reworkea, repaired, and replace-

! ment items snall ce reinspected 1

and tested in accordance with the original inspection and test equirements or acceptacle alter-

.iatives as cetermined oy dngi-

' neering and Quality Assurance.

All inspection, testing, rework, j' and repairs sna11 be oy approveo (

O procedures and tne results cocu- '

mented.

5. Identification of nonconforming items oy appropriate means (tags, labels, etc.) and segregation, if practical, until cisposition o f tne nonconforming item nas oeen

! ceterminea.

l 6. Prior to the initiation of a preoperational test on a safety-related item all nonconformances snall be evaluated for signifi-

, cance or impact on furtner test-ing or operation.

7. Nanconformance reports snali ce periccically analyreo to snow quality trencs. Suen analysis will ce casec upon severity, numoer, f requency o f nonconfor-mances, tne causes o f tne noncon-formances, anc cne timeliness anc acequacy of the recorting and

() VIII-3 dev. 3 1

.f

, _ _. -- __ . - = _ _ .

i 1

1 i resolution of nonconformances.

Significant results snall oe reported to management for review and assessment.

6.3 Resoonsiollities S.3.1 The Vice Dresicent - Nuclear Assurance tnrougn tne Director - Coality Assurance is respon-sible for tne revieu ano concurrence of all procedures for reporting anc controlling of nonconformances for compliance witn the requirements of tne Operational Quality Assuras:e Plan.

8.3.2 ine vice President-TMI Unit 1 is responsible

, for ensuring tnat nonconformances are reporteo

', and correctec for plant personnel activities involving operation, maintenance, repair, re-g placement, accition, modification, radiologi-cal control, environmental monitoring, fuel i nandling, anc inservice inspection. Plant

' items sucn as f ailures, aalfunctions, cefi-ciencies, ceviations anc cefective materials, 3,,

' parts or comocnents are nancied in a manner r consistent uita tneir imaortance to safety anc O reviewed in accorcance uita appropriate proce-cures anc tne applicacle Tecnnical 5pecifica-tions. 1 1

S.3.3 Eacr Manager is resconsi:le for One disposi-tion anc cc rective action of nonconformances identified as uitnin tne scope of nis respon-i sioliities. In tne specific case of mate-rials, patts, comoonents, or systems unicn nave not been installeo or acceptec as opera-tional at the Station, One responsicle Manager approves anc tne Quality Assurance Department concurs uita the resciution of nonconformances.

i 8.3.4 Eacn Manager is responsiale for ensuring tna nonconforming concitions are identified ana

, controllea in accorcance uita approvec l procecures.

j l

l l

l 1

l i

l l

VIII-a Rev. 9 l

l

4 4

s

() 9.0 Audits 9.1 Poliev A comprenensive system of plannec anc cocu-mented audits snall ce estaolisnea anc exe-cuted:

i

a. To ensure that Quality Assurance re-quirements are adequate, effective and

implemented.

c. To ensure that nonconformance anc Quality Assurance ceficiencies are identified and corrected.

c. To verify compliance 41:n :ne TMI l

i Quality Assurance Program.

In addition, this aucit program snall provice data for a continuing evaluation of tne effac-tiveness of the TMI Quality Assurance Program.

9.2 Recuirements 2, r

4 A comprenensive system of audits sna11 ce estaolishec for cotn internal anc external s

functions unicn affect structures, systems, components, operations and activities covered oy the scope of tne TMI Quality Assurance Program.

Plannec anc seneculed aucits snall verify i,

compliance witn tne following:

a. TMI quality Assurance Program j o. 10 CFR 50, Aopendix 3

c. Regulatory Guides, ANSI, anc otner coces anc stancaras as encorseo in tne TMI Quality Assurance Program.

c. Operating procedures

e. Plant tecnnical specifications i

f. Acministrative procecures i

O IX-1 Rev. 5 i

i

g. Otner procecures and instructions a f-fecting quality

n. Procurement accuments 9.2.1 Audit Procram Audits snall ce performed in accordance witn pre-estaclishec written procedures ano eneck-lists, ano snall ce conductec oy trained and qualified personnel naving no direct responsi-oilities in the areas ceing audited. Tne audit program snall incluca:

a. Audit senedules

o. Procecures for preparation, pe r fo rmanc e anc reporting of audits

c. Analysis of audit cata and reporting results to appropriate levels of management

, d. Follow-uo action to ce taken cased upon inoividual anc collective auait reports

• I

e. Qualification of auditors

f. Delineation of tne autnority, responsi-cility, anc orgsnizational incepencence of tnose responsiole for ne aucit program.

Audits snali ce regularly seneculec cased upon tne status and safety imcortance o f activities being performea anc sna11 ce initiated in a timely manner ;c assure tne e f fectiveness during design, procurement, manufacturing, construction, installation, inspection, test-ing and as required oy tne tecnnical t?ecifi-cations for TMI. In addition, aucits may be

, scheduled and performeo as required oy manage-ment or One safety review groups for soecial evaluations. Implementation of corrective action snall ce verifiec in a timely manner.

Unseneculed aucits may oe concuctec at any time on any ascect of :nis Quality Assurance Plan.

Sotn GPUNC and organizations providing gcccs anc/or services are suoject Oc :ne acci requirements of tnis Program.

IX-2 dev. 5 l

'+--=-----=ge--m->-- ,-,4 wy e-,- yw.m.-%-->+e-a-- w--- ,,,,ppy 9m-wwa--mm-,v.,-y wtg+,,,e 9 m g~9., ,, ,m---- y.mp--%---+y9-y-- -- -.-

3-,y -ws--- -w-- y- ~+

Aucits will ce performeo oy tne Quality As-surance Metnocs/ Programs / Audit Section.

Each audit team snali ce lec oy a qualifiec Audit Team Leader. Aucit team memoers snall ce utilized as requirec and will ce classifiec as eitner aucitors or tecnnical specialists, cepencing on tneir function on the aucit team.

Procurement cocuments shall include audit access requirements in insure vencor com-pliance to tne audit program. Aucited organi-

ations shall cooperate witn tne auciting organization, provicing ana:ever assistance is necessary in tne performance o f tne aucit.

The audited organization shall take corrective action for fincings anc resolve coservations in a timely manner.

9.2.2 Audit Frecuency Aucit frequencies sna11 oe cased upon :ne status anc safe;y imoo r:ance o f activities, cegree of previous experience, consistency of  :,

overall coverage, unique testing / operating i-activities, anc follow-up on previous aucit

{} fincings.

9.2.3 Documentation Auci: resul:s snail ce cocumentec in a 4ritten report :o :ne aucitec organization. Tne guality Assurance organization concucting :ne aucit is resconsiale for conducting follow-uc actions including re-aucit of ceficient areas, as requirec, to assure correction of the cefi-ciencies.

9.2.4 Traininc Audits snall ce performec cy personnel uno are

ainea and qualifiec to tne requirements cefinec in AN$I N45.2.23. Tnese requirements orovice :ne means to assure that aucits are t

perf ormec in a :norougn anc professional man-ner. Documentec ::31ning programs snali ce o rg anized to orovide aucitors witn :ne neces-sary training ano knowlecge of regulatory requirements, coces, standarcs, procecures, etc. acclicaol< :o ne ac:ivi:les ceing auditec.

) IX-3 dev. 9

9.3 Resconsibilities 9.3.1 Vice President - Nuclers Assurance t

The Vice President - r4uclear Assurance is responsiale tnrougn tne Director - Quality Assurance to:

a. Estaolisn ena implement tne overall 4

Quality Assurance audit program. He assures tnat all applicaole areas are aucitec and that tne auciting organira-tion acets the requirements o f tnis Plan. He evaluates One effectiveness of tne overall aaoit program, anal fres tne reports and related information for quality trencs and appraises Vice President - TMI Unit 1 and tne Vice Precicent - declear Assurance o f signi-ficant findings of tne program. Tne Director-Quality Assurance furtner en-sures tnat an overall Quality Assurance Audit Program Senecule is estaclisnec anc implemented. g

.r D. Senecule and perform aucits anc to icentify quality or management control proolems ano provide recommendec solu-tions.

1

] ,

)

i l

O IX-4 Rev. 9

APPENDICES APPENDIX A Comparison Chart of Juailty assurance Plan Requirements with tnose of various parts of tne Code of Federal riegulations anc Nuclear Incust ry Stancarcs APPENDIX 3 Minimum CoCument Control Kesponsioility for "Impo rtan t to Safety" Occuments APPENDIX C NRC Regulatory Guice Comaitments ano Exceptions t O

APPENDIX 0 Definitions l

l l

t l

[

Rev. 9 l

D

(

APPkruilX A

(

COMPARISON CHART OF OllALI . ASSIIRANCE PLAN REQUIREMENTS WITH TIIOSE OF VARIOllS PARTS OF Tile CODE OF FEDERAL RECULATIONS AND NIICLEAR IHbliSTRY STANDARDS 10 CFR 50, App. B ANSI N45.2 10 CFR 71, App. E ANST NIH.7 - 1976 Criterion QA Plan _ Paragraph QA Plan _ Criterion QA Plan . Paragraph QA Plan Pa rag raph QA Plan 1 1.0 2.0 2.0 1.0 3.1 1.0 1

5.2.11 8.0 11 2.0 3.0 1.0 2 2.0 3.2 5.2.12 1.0 3.3 III 4.0 4.0 4.0 3 4.0 3.3 1.0 5.2.13 5.0 IV 5.1 5.0 5.1 4 5.1 3.4 1.0 V 3.1 5.2.14 8.0 6.0 3.1 5 3.1 3.5 2.0 5.2.15 3.0 VI 3.2 7.0 3.2 6 3.2 VII 5.1 4.1 2.0/9.0 5.2.16 6.2.1.5 8.0 5.1 7 5.1 4.2 2.0/9.0 5.2.17 6.2.1.1 VIII 5.2 9.0 5.2 8 5.2 4.3 2.0 5.2.18 6.2.1.3 IX 6.2.1.3 10.0 6.2.1.3 9 4

.2.1.3 4.4 2.0 5.2.19 6.2.1.4 X 6.2.1.1 11.0 6.2.1.1 7.0 4.5 9.0 5.3 6.2.1.11 XI 6.2.1.4 12.0 6.2.1.4 10 6.2.1.4 5.1 2.0 XII 6.2.1.5 13.0 6.2.1.5 7.0 5.2.1 2.0 XIII 6.2.1.6 14.0 6.2.1.6 11 6.2.1.4 5.2.2 3.1 XIV 6.2.1.7 15.0 6.2.1.7 7.0 5.c.3 3.1 XV 8.0 16.0 8.0

12 6. 2.1. 5 5.2.4 3.1 XVI 8.0 17.0 8.0 7.0 5.2.5 3.1 XVII 3.3 18.0 3.3 13 6.2.1.6 5.2.6 6.2.1.9 XVIII 9.0 19.0 9.0 7.0 5.2.7 6.2.1.10 14 6.2.1.7 5.2.8 6.2.1.12 7.0 5.2.9 6.2.1.2.0 15 8.0 5.2.10 6.2.1.8 16 8.0 17 3.3 18 9.0 Oa I

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

i I

1 P.

i Eq ! m-

.a '

4 l

~- ^Je l

9  :

s.'

a

, Le d

l = r O e

- .'.P si  %

1 C I

O

.L, d 2 o e a n A

J 6 J eC .4 -'

L 9 U s "a h C -i d ti L -C *d

• J s s a -1 d.

.u .

l u .c

t. <

u a a M 1 # *1 agl M M

d. a. .:i. ;s. G"I. W

• )

^

J G V y y T) *4 7 O Q Q Q O  ;*  :: 'T e,l 3 ~) O

$ ** < er e  ; 4

-s a $ J J Cf' a r3 M I

C i

Ul I J .

. +9' I . .s u

.a i

, .s -

1'

&. J 8 ns  ; (

.>= 0 1 s i D OO C S  %

4: p S - 3 0 g -L

• ) O 1 it O Q  :

c" l b-~

-8 a's . C mt 5 .s i..

9

, O ms 3 4 > b

{

2 ;uj

01 <: - -

a. b .a *:

~J 3 M 4  :

-- ,1

.* D n, s s b J q *; A *)

m u s u o .

• aJ a. m

. <'2=*

• C 6 -a' a: "I egl C C

• eg; .;*

^=q a l u *s s. d *? 9 'y - , 3 .J s ,*

i* , C L s C ." , ; 6 L g L

b. ' b 6 g o g l g L l {' a .-.J  ;  : 5 --

.a 3 ll  ; >

<;l

.== a a<

a *

.t:

Ij =

t s. . . .; --=.u><..a a

v.3 . o ~.S

., z y

,1, , s. ,

i pg

-e

.= ; .- . ,

"J 2 I" S '* cb %

3 %

< L "J

<4 L.

• D :

A ,, n *g** .

b : y :)

! C

-*C"> ,b 7 O,eI:". C =': * .a. h <. N h *. Den w .* s

• • ~.'%. w s 1.. - -c ti  ; 9

.- 2 L

. ."* cC6 - h s

i  : -

e O c .- C ed a s-c : -

-c a = .

. -a Z w .v.: a '. s ; .s k *

• t t *7 .da E 1

-~ =,

1 t = b

-., Cw

d Z -J J.; ;

e.* 7 e

., + s* *

".*!.e* 7'3 ,.J .".;. L7  :: l*

s A

1

• 1 -** 9 9 L"Ta' 9.~=. ca 5  ;> ; t > [

c  %. n -n of I a n 1 3 ea u L. y *  ;.

2 O 9 ,

.u % 4' % a k 4 .' D 4 L 2

L t 6

% % 2 6

2 e L ;

3 4

.a. ;p a 1 3 ;,

.1

3 L l L. ] u '.)

, -- - a A .^

• as as *d a ; , +3 *d .# *# ; Q J QL -. ed +2

.d

>, u'J '> U u "y y 3 u m _. *J

- e ;p 'a; y GL- [l

- ~

t

..*a 6 D s y b kt ?"

• ) .e. y y , G y > u y

_j -

I'

.a

= .a.- u. >e -

a

> > ^:..

uu"J ** t.) .-* . .-

.A,.

'.s.

'. y ;h g . ..a'a z-s- ;l

<, , g.O.>*>>>> . . . . .

=~

.e d .O ;;. .L O' 2> Q c

Q r

&~~ ** l

< 'r.

= **

E- O g

$n a r.-- l i b

J2 l s

=

a a a b c = = 1 5

..I >j d u a u  %

I s a a a = -

., =l

2. "u 1.

a a u

u >

El d'

-i .? -

T 7 0 f.2 -

ul 0 I .S-i i

.2 ) y 2- y'a 2>-

z - .

'.i.;, .: -.

p "

2 & e d d e e s 5 5 7 2_

M d 9 d O< U 6

e a

.) 'A C

.J t

'. G

=~2 er'e se x., . . 2

. " .C .D.

9

.s 9, h

'"

• 3 s j 9 25  ; 41 u 6 O ty a m

~* O = 4 b J k

'4 ,~^ u' Z*-.=* 7% 9 C.=.Q  ;; L ~: C u 3 sa  :  :

.e ,

.,* =~ -

.* L y 5, .e.a y v * .. >  ; ,.

,~ O.,.-^*t. z

• . , -r , c .

c .;. .

- u

" ~ - ** p

• i.' s v

%, l '7.

• r s. O .L a

- 6

".".. e. . ;6

- I *C - % *C, w  ;'l A OL J1

• 1 (> *; el I

l l

I l

l rem n --- - - , . w. ._. - ~ - - - - . - - -

..m__._.-_m.a .m . ___ _ _ _ . ___u__. . ~m.- _ _ _ _ . . --..___ . _ _ m. _ _ . . _ . _ _ _ . _ _ _ _.--_.___ _ _ _ .

t i i

I

' se H=

t- 9 CO Q w "'

• 1 L

O & y

>> 4e ., s

.'4= ) e

• a m; 4 .~>. . ir.*

\@ 4 a

C S M l

a .s  !

.nJ .-+ c

h. he s)

6. 6 C 4 M a O

e4

.) .) 1 - -

o .

-=1 4 4 .1 6 e ss e es s' t 4

1 d5

'* Le t 4'J L"9 *.3 .4 3 i

C, o.e N *$p I w

? O 1

s .*

• d 4e O s .: '.46 se ,; A la.

,e o -e 3 vt -. p a -< > -e a .j ana so 4 o 4

..9 C 19 4  % a 4 n q

s- 4 % cC 1 >> b t c:

<> qe .a -4 o . s y  ; e, o ca .4 uu 94 v o 3 4 .

- 'l ve

• a

}

• • =C *j e4 6,4 C -C

• g

-e o 4 4

.. % 7 l

4 .)

.. 6. 2

• J. 4 a3 n ie y [

• Le la.. na te <% a .p i. l l

i 4

3

-1 m

6. h

> 4 >

as 4 -e

. b1 k

4) c 4

s. d p

) es v. O .,Je 1)

.*,J

i o

J -e 2 ) y H 4 4.

l 4 ~J .a L1 % .o J s.

p 3

• f ::1 c. 4 2 4 N. e s ne 4w 4

.,4 A

\

9 4a 4 O m J 6.

y wt

.a p

-a u M a a w

., \

J v a to O M .s  ; ; M a t

, *3 D .h U g -3,.4 O'-*O p d

e i L. i j

s 4% v 1

• .; o %2 s J *) .b.s t. N -1 '*e C. 19 t'  ! 9 J I

e a 1 0 1 - o 4

• I .: g v .u* st 6 j :_: s  ? , -

. 4 3 .. ,;: 4 1 a  % - ]

+=

.- . )

3, O

..~> t 64 a. r

ri s.* .*.1 '. - *

{ a" ' ' =

-e 4 y s' .3, ) - -

> :- o *-

J se a

I

~) ..a.-o>-, +<

1

> c e

-4 '>

.J c

-,4 +9 3

--. U ee

.4

.J s

'.)

L.

1.' 4

'. L.j i -

.,. 4 v J . 4N1 a ~.

4

.O

--y a s 4

' :1. a e . ,

A 3 a w I v

-e. .>u .n.

M - ~ -- r n -4 n a  : a u 2 14u+,.

, ,s -

. -. o

-. s v~  ;: i ee .2 -

c e .c4 i

-e,. ,

J i a, N L .- . 32* as a

• .1 L. .o.,. 't- ao :;. 91;. u y

.v-J u

.4, s

,n.u6 a u 1

. .3 ,

a 4,

=

1- -. 4 a< q 1.,

. 6 . .c -c ,a a . 4 -c L1 +

a

o. .o 1 .: - s a c 7 a n -. s 1 - a-:

.; i I-q 4 --

1 6.

s i

e >

e3 .. w 3

u> .

w u -.%

3 a s.

% c

• 11 u s s, 3 u a -*

s n 1 3

l 2*

.J 1

')

+4 u

1 as o 1 N o

d c .e .J u '-

. Le y 3s .a .

t.

p .s 3 3 J Le )

6

.a e u v 4

f I

e

• A m-* .n

'al .J @M J p *1

= 'e <. A 's .a y a*

-,  % 4 "J U .e

1. d M Z as <t  % et J 4 > .* > % 2 * -4 J A FJ a- . ,1 4 t* g,. ,1 m.

)

.C2 -

8 4

j.

C C 1 4

) 3 y ** .j* se

.%.e.j e 4 3-k . ; 4 e e 3

e .

o e

e) e a :$ a: La

44 - 4 4 . -.4-8

. Ca e i

t

-4 )

3 3 -

vt et s.

l 7 0 .m

) 3 J c .J e.

l -* ** -4

'4 .) 4 -)

M **J 4 ,a a 2 m'* .J n a

2. _* 1 <3 p 4  ;

J 3 ') 4 > > c g

+'

• b C .4 N 4 6 e

.J*

3 J

4 0 1

)

e es et d

-e

.*')J.

6

• =)

k.

v-l 3

e e

a 1

-j

.j

• J

.A. .* .a .J 4 n a .") 4 A 3

.'- ') '.-} ') *4) ) *

,'d. *)

i

'y.8 s .

• J ,)

e -

u *3 y "b --

'. .j )

.j y ') 64 .) *9  ; es 'e

=

Q

2. 4 .-e .a.

= b 8"* 5"* M a'1.

', J Q g ry i

(

t t

J

'1 e,J I

% ,1 U >

a'\ 4 te O 4 S e 4 't -1 eJ .3 O eo

) U 3 1 3 > +1 *

• 4 m me 4 ~ 4 -

• J J 4 .eA 9 < * ,- 'J r> d )

3 4 J 4 J '9 ) ) w

• l tj .se 0 ,

e f 1 ) -

2.. .-3 4

.)a 4 -) -1 , .

7 L'se3a I

,~~,

.e  ;) e *> .~)^L.. *e 1 3 me

% J

-e J

T

• • ajs 3 4 vs Al

• • ~* a.o 9 -e 4 L. ) **+4 +4 ,e

) J 1 .a 7.s e3 -< a

-s

-* w .4

-t. M. 1 a . , L cs .J -

- [

- , a .. , a.

-1 9 1

)

J e.s b "

x .u A 1 '

u h,,g l ~ d . . F.

3 0 .1 J.

a .% 4.J* 4 98

• 3.

-.T. 4 ,

• c '.). 'C .k.

.4 3 f y 9 ,c

'J Q k . ~w 'J ~' '.) ** 3 .% sh 4 e'. LJ t

t

3 I

.b

.d.

el

..I a .

I @l

.~

f ',

.I' O C L O d

• n u b

• 't -

• )

1 0' O M

• i.

4 -4

.a L3 4' L $

)  %

o -

• O a

' D .

8

" O "* ,"

S.

• ( o

% '" b

' Wv.. -

bJ

c. L w 4 0

• U -+ *

• ' O ,Q 7

Ahhy

)

i -

. .e A

• a >

a ** -

2

- O t a

t 0 - . g5

^

J a 5 '. O

,, .O J a D

, d L e 2 2 -G, :b.

, c U 4 *1 0 -* O O

i .".

-  % +.)  % ,7

- o 3 -e i - .- = " O t1

• J

~3 k o 3 0 '*#

C J Q U -A e G O A E Q

a 7 +J 4 " .. y 5 o d b .e4 "

U -* O t o -4 ~4

+J .- H  :: - "

w C "*Q . I3 E 3 .C TU 0 - <' O

-4 E4 o 0 -

y I, '

E 0 7 *' 0 +>

• : 4

.e4 4 *J = ,J M.

U = 0 E d O 3

m o o a = L U O ~3

m = o = = o X o .- w o- a o u u l?

L o . p 3 0

• G  % c3 M. 4 f C. . > 4 A <>  % T a C D d i9 d u o a e L a "J

• dd i

b a .=, c  : o w-a o L

0 UA

' 1 h L

. w s

< C..4 M u O L L. +-

&~ d C M e .*

E *J

. 5 O D

= a -

2 v =

U y k c:. 1-~

n ..-. > -< a  : -~

a v '.J

= .: J -

3 ^* ,J 3 )  % 2 +> **

• • C  %  % T a

~-*

2 O y < D O * 'd7, ,E o = c = u a m 4 .-

w  : u  :

.- +' ~

- L h O 5 .'J Q -J = d O L 0 ,

- o o a .

e Q t 4 l

= - L 4 L .a - a -

L = .) U =

-d a d M d c w 0 0 L >

e u o a s aL h m *J H E o  :

E O

L T .2

~

E L U L ~- 0 4  : L > 4 C .2 O O 1 0 Q > . * * ' '

- 'O L L

- a O c '

L O

) O

"'.' 'f i

E L L = q d L 3 D A 0 M > n ~

0 D C = D C 3. .D n *D ^ "$*

% a g y -

O 4 L

~*

OO

.o J V U < o

.r..

4

-O b.6 O

.u.6

• M M O C C 07 d ;3

.e e ." ...

8 =.r 3 Q 3 3 M M W

4.ig a

• J - y eU D *r*

a a +2

n a v **

.~s y

~ $

- : e 2  :  :  : >

a

.: a 2 e s a . o

-4 N a .-

.- o .- -

a .** *

• L L

a L L 0 4 0 :'-'

2 *i

.  % C "J *.-* *j

, ,L-s .=.- ,e

< = a

- - C.. o .> -

s ~

.I .- e

.O.

.- =

1 a

a. -

c. 'e- n Z

U a .

~ ~- .. , * :*

h h O b O H < ,

e  % e A A ^

.e 04 ^

M J Ii V C'-

5 4

e i

l

,-wW"NN' _

_ _ - . _ - - - _ _ --~ - " - _ _.

APPENDIX C O

QUALITY ASSURANCE PROGRAM NRC REGULATORY GU fDE '

COMMITMENT 5 AND EXCEPTIONS Engineering, in establishing specific requirements for design will use regulatory guice positions controlled by Technical Functions in a project criteria document.

Examples of positions taken relative to regulatory guides are listed. Thuse identified by an asterisk cover regulatory guides wnich are specifically quality related or impacted and are therefore controlled by tnis manual.

The TMI Quality Assurance Program complies with Section C of the NRC Regulatory Guides indicated below. Alternatives to NRC Regulatory Guide position are detailed in Part 2 of this Appendix.

I This Appendix addresses additional Reg. Guides not listed in Rev. 3 of tne Operational Quality Assurance Plan.

Compliance with these added Reg. Guides will apply to modi- .

fications, additions and activities performed after issue '

o f Rev. 9 and does not imply backfitting and/or retroactive

() compliance. It is also to be recognized that existing plant conditions, may prevent or preclude the satisfaction of all requirements of a specific design related regulatory guide. The deviation will oe documented and, along with the jus;ification, will be approved by tne Director -

Engineering and Design.

O C-1 Rev. 9

i l

l e

a "%

.'* I.; s 3

') '

O 3

. -e 4 . . .

w . -

.s s S -. - w -1 -1 ~* p

~e -

we .v m 9

. y' 4 41 2 4 '

1 O ) J

-J

% &-) 9 1 "i n-. .'4 .1. .1 1 4 J

> w .s > .=

%  % ., 2 .n .> h .> .s e  % '.

6 L L r 4 1 4 "

as L 9 Q *) )

.O, a

d

. g e ,, -. .. y 2j ++ .'. u 3 3 d i a 3 --*

~'.

• re J u  ; -4 .' .a . -M.  ;*

1 3 3 se e 3 .a - e 3 g j 6g s -

sa p .

L ti  : v t; a .

-J. 1' . L".

a u -d.

.> .e. a

3

., e t.

.C .: * ** .0 at 1 7 .7

.e

.* es E; 4 .; .c.s i;

,e w L L e.

. w 6, .. --

3 's ;8 '

s J ., V 9 ;s.

~

% N N

.JJ s.'

• 8 2 s v * .""

-4 eg h 4 --4

• 4, -4 -4 -. e' O 1 -4 s 0 -J eh

- a L 4

• , 'i u ti t' W *J ti *J J b t.

A s J s.i D D es 3 il b b Q 1 O U ".) ') ', ) 63 f.J bl ') (4 ) Q *'">

.b '. .-.

. Q L. +1 ** '** . -9 -9 +* ,

.. .. b b L & P '

~

4; 4 : w e

W

.b. -

m

4. b

.b<

w m

.a. , ,,,, a.4 .4 w -.* 4 .-4 1 c.

4 ,,,, .-. -. -, ..* ,.e

- -'l 3 a -

( y

-9 e

m n .

5. 4. G i  ;[' u. ;a. p. *

• t .a. O . . ..

c;

• h 4

La

-e M (J ) M cJ M 04 t

%  % p_ . p  % p. 3 M.

c

= 3

-, ,.% 4

.h

-4 3e

.--e

-g Ch,

, ,h.

-)%%.,w

,h4 -

4 .

4

~ m 7 -4 Q .* O. -g -*

,,u

• *J

" J. ". . a 6-4 -.

• J *

.7 93 0

=. OJ. ' l. i. J. OJ. OJ. .

L< D D. \ p D D A ,,% e< O a B L  : ~ *  : -e -

! C t

• r U M M 1* **, 2 'J " * *

.O 6-J L

. 2 L "J 9

-Q a b O )

< = 4 7

- _' a 9

~ r

) .a4 w

.* 2.;

s ed c1 a '* . 1

. 4 'J 19 i} 'J A u a'el v C

.s

• 2 24. .s.a S .* n'a. .:

2 '; 1 "

J M V a .'

.- *-1, "u - a - _/3 a -

n' t M J

• 3 e4 Q 3 .' - ra V

.1  %  :- *J C. 3  % v  : J

s * * - * .a a ~1 3 ~a 2 *J a% .a 4 ) "

.'n  :

.e eC ".d a " U a. e o .a ~* y  : a e

.M u 2.  : a 4 s 3 1 J  ?

wg 3 3 E'. -. 4 .--% M ed 0 -* b .= =

i -.

v "J a  ; 4 3 9.a ) . b ** -') ..

-i

, .D. 1 3 .s. .a .2  ; 1 O e C

-- ! .: * -e b S * 'r; 3 L.  ;; .,  ;

• '* .1 -. d -.*e O ;7. 4 L V ~ 2 ~

• 3 f<

f

~

X s .J

~

.J e

L

?

4 -)

• E 4

-=

2 3 2

'n 4

3

> J

-.-e

'e 3

u%

'- a'a .A 3

.J 2

~

F

~*

y

• J 1 -. ~% - . .: L

• ~

e (* Ei - - ., s  ; sg . ;,.1: n ;., s g -

Of 4 3 3 .A a g ::: L. s

• w .s.

y .: ....~;~

r= .3 *s 's "

• ":: 4Q  % ~ ab

.s d ~* J  %

^: ".a

~~ a

• ]

A

=

T- t " .=*i e 4  : U - 0 -- i 6:.. 7c .

J W 6 Q4s 3 .1 7 .*s .>+ ., 1 **

-4'" 3 3

1

• 1 W

b

4

.J 4 6 b s7 .s. s.J L. ] d A '. -=

• C ) Q .'

E.

=~ >

r,

> n u a

--e 1.,

$ n* .O. x3J L=$ ': ,-* 1 U u e D

y a

. .-* J -* y 4

.J 7 ,s 2 * .e 1 . L v

^'

2

. J .: ;, s % .- .'J -1

.e .W-  ;

D 4 s'l s .-

2

' Ji J,

~

b Q C O .  ; ;# 6 w L 2 9 .; 1 ) m.

. 3

.1 J G' T 3

- ==.

.- .e 'J J

C d'.

. ** ] *) 3 'J '3  : 2; 2 ~

4 G

3 3 - -'" .s

'A 'G > a - : a .** 3 D -4 3 L a ) '1 a  :

== < $ ed a;; 2 J 4 W , 'J.=')

, ".;. .J " 1 "'*

a --.L .J- J - ,L J 7 .ee 0

~ J y

• J a

*n'%

; a *. ..o 4 - a 4 < M m a *

.M e y .%  ?> 3 4 3 3* 9D  % .%,o *> .a

'vt.V* ~-

i

)9 +=% - i 'a'S

.i < "

s -* E 4 J.,-.

• 1 s

-= %  ; 'J .*=.7* , :; ..e I *'* 3L*

C1 ;f.

. 3 4 + '

D '2 _ka 2 m

s J

• 3.,.%)  :

- 2

)

-? s

.% 1 0

~ g *

~

im  ?'==' **.) *. 4 Aw 'o'

.*5

'; .L -. .G 2 .E'

• G .1 .4 w*

s 'i

...m 4

e

-.Y e, e

=4 TJ

==* O.

s . . s  ;'*

.4 4 . 4

'*4 4 .L - .

e.,

. s . .

"* * , 'g &  % $ *

's)

- = -%  %

_,-)

% & e.$.

N' N N N N N N T w N s *1 a Og Q  % g a y c C O '*'  % '  % J) .. J

. -s T 1 e. 1 q w r

. = .

. . . . e.

.e$ .". .-'O 8'*4 d d ".

M e4 -a$

e e e e e k _ . _ _ _ _ _

._.;__ _ma_. a-.i.ri.-wo- .a- h;s;;

_ & - --u._A-.2- _ - . _ _ _ - _ , - - - . ..w a.._a---s2 Cu -i& 5 . __.- -a.m.m.aa . a i

l i

.5 f

i

• l Y

d

-J 3 e

s.

• ) m g -

. 4 e "s m - s - g

, J J ***

~. . .: 0 .s.*.' -

.e o

hp

') ) ') M 4

a w w ,

)

• e3 2 .. .

%s 63 1 a 4 4 . 4 it R

d g h.

" n +3 .c

'J w .O 5 5 3 a

3* 3 1' 4 0 a

~n 4 1 L 3 0

.+ -1 4.e  ;

E'

.' *4 & U 3 m

e'J c J s ei - a  ;

, 1 J 6 -

~'* , I b *

• m J a eJ  ?) J

==

G i .*I .n P O ""4 '

-+

.e  ;= 4 **

W L ,e p 6 -* g' .e.

s

. i .s 4 L a w (J s .3

~~

a d _,3 m ,< -4 u n

~'. v u .n.

~

• )

G k

. C.

U u -

6. L . J & .& V J ,2

' )' O O a  ;

Q tl Ll  ;) La

~

' *) 'J U *? *?

n

• U u u M

=*

w u

-. ** *.J 4

's.

--*

• y.

- ., * .e.

h h 'e e- r.

. * -. a 4

? W w

'"I 5 ** *'-.

.) '")'

.a. m =,.

g.

-. .. g.

+ +

A id AJ N N 4 3 .h  :=

! .a

.h LT O 3 M .T

- m -a - H

.: " e.

N l a =

3 .% C - .*

"8 b OJ 4

-. 4+. .+ gg+ - +

l l}  % a'* 7,.*. .3 a*. M M f

C I

a tN

%* I U

4

=.3 1 }

1 L E D p f- s L

' ~* e  ; w 0  : L l' 7 .J O L 3 4

6 3 A 2

'\

~"z 3 m3 .- s m uh 2 e2 L  %

z' 2 J .d L u *)

• C

• 3 -=*

1 3 J *e t 'a .J.o I J D $ ** 'O Y Y A e='n%  ?

.,o

.e.D

) .J' w :e *$ 3 : A  : J  :

W ;p a -* a n 6 6  : n l

', -4 4 ea

3 %  %  %- -* G =-*  %

O - .J v V w 3- '.J 3

( L * .  ; 'B --* b 3

> -a u"*  ; u > .10, n

2 , 4

~ ,

.o ea -5 'o - e".a.  ? .A 3 A 4 .1 o - **'

a

.g

-- . .* v : 3=

-.  % 4 7

7* ;3; md W' '1

. 'J - -

4 .> ; _1 3 2 -* .'

=y.-=2 .;

3 ;*I a* C' L b: *-  :

'J -* '

= .x.o

--*O

-- .a

-. ;.; -d 2

^J O  :* J L -e U3 J -

L.

• = ** ==l -2*- m 1 ** GJ" os 1 3

\ ^J .2

b 4 w

z a

• C' =. *

.* os a  : 3 ~;~ ) W

^3 2 ~ ^3 . - *

-1* 5-=* ;  ; L .a 1 w

.J ,

,m,m -

%

• C. t ~* *J  : <$

% m J - s

. 6

= ;

1 O

.O.

- 6

=

• 2

> L U

3 . ..- l a 6

L L : L 3 5 .J e "2 J = u, '

D : 3 *)  : A n; D * -* -~ A ~

% .~. 3 s,

.: 1 a  % y e  : '2' .U a a % -4 i,,.

3a E U L ; 3 s 2 * - 1 O

- . 31 1 -* J 5 W :*

a 6s w .. b L

; O

.J W 3

.e >

3 6 W .*Z e -

• .* b

.e 4.

J

=-

7 3.

' L *- U '. -

L s 6' ;tJy- d'./ .

y b E.i -*

^

.7

1 6

• 2 -Z3 "J aZ  : ; ..  ;

..m

~;2 .

J

~e

-~u~3 .A  % 2 3 -*

.~.L.~~

.., 5

[ --. .a r* .e 1 1

'.J w I

? -

T% %

2

=Ta

'_1

?

3 .3 E.' d

-1 2

-~

b

~.2 --*2 ..; g-4 : =: ) A u VH : & .u* e) or 4k a n

--. '.: *~ ?Qan

~ ~ *

==< ') =a ~

l

> 1 ~~%

• x M u *3 L .* ~J .. : , . *;

- ?

u=

7

.-?

1 :

.)' =

4 e

-} ~ = :

.a -L 6 a .u

<!* 4 J

, 3 J

? w -=

J'

..J -a i

j . -

m Jau un - h a :-. 3 :.'.

=

f g

O =e M M I4 e

> . . . = * *

") $ > > > > > >

4 ,- ~J . -

^

b 4 a!,  %  %

e  ;

a e a a e .

--  ;  % %a

..,  %  % .  % %3  % 7%

dJ 1, 7 S

%  % N N s 'J N N  %  %

.'.,? -4  ? /%  % _ N.a-7J .7 '"- p )

] M g l' .r m 4 r .,

--* * ^

.w -

k 8 4

c4

" O W

[-

8' 8.=. ==6 W ==.9 -- M

.'-@ m 4 P

e--- , - - - ,- . x . . , - , - _ . - - , _ - ... -

() APPENDIX C, PART 2 NRC Regulatory Guide 1.30, Aucust 1972 Quality Assurance Requirements for the Install & tion, Inscection anc Testino o f Instrumentation ano Electric Ecuiament

+

TMI sna11 comply with the Regulatory Position estab-11sned in tnis Regulatory Guide in that QA program-matic/ administrative requirements included tnerein shall app?y to maintenance and modification activities even tnougn sucn requirements were not in e f fect originally.

Tecnnical requirements associated with maintenance anc

mocifications shall be tne technical requirements or better j'

(e.g., ode requirements, material properties, design mar-gins, manufacturing processes, ano inspection requirements).

NCR Reculatory Guide 1.33, Rev. 2, February 1978 i

Qualitv Assurance Program Recuirements (Oceration}

I Tne TMI QA Program complies with the regulatory position o f this guice with the following clarifications:

f

1. Paragrapn C.A.a is interpreted to mean audits will

() ce made once eacn 6 months to verify tne nonconfor-mances and corrective action program is properly implemented and cocumented, particularly as related to actions taken to correct deficiencies tnat affect items important to safety.

2. Paragraph 5.2.8 o f ANSI NIS.7 - 1976 titled "Sur-veillance Testing and Inspection" i

In lieu of a " master surveillance" schecule, a technical soecification surveillance testing schedule shall be estaolished reflecting tne status of all inplant surveillance tests anc inspections.

l

3. Paragrapn 5.2.15 o f ANSI NIS. 7 - 1976 titled i

" Review, Approval anc Control o f Procedures" The tnirc sentence o f the third paragrapn is inter-pretec to mean applicaole procecures snali ce reviewea following a reportaole incident sucn as an accident, an unexpected transient, significant operator error, or eculament malfunction.

4 Paragrapn 5.2.17 o f ANSI N18. 7 - 1976 titlec

, " Inspections"

()

C-4 Rev. 8 i

l J

-w---y g- ., y,,,-w--.--w- y-- , . , ~ - ,7%ey,w w w-,.,-- _~._v-r.,----,,ww,v-wrv -

w e vv r-v--w ,-r w wm w- - -*rwww- ww--n+-*y--_-- ---

APPENDIX C, PART 2 O Not all inspections will require a separate inspec-tion report. Inspection requirements may be inte-grated into appropriate procedures or other documents with the procedures or documents serving as the record; however, rect;ds of inspections will be identified and retrievable.

NRC Ragulatory Guide 1.37, March 16, 1973 Cuality Assurance Requirements for Cleaning, Fluids Systems ano Associateo Comoonents of Water Cooleo Nuclear Power Plants The TMI Quality Assurance Program camplies with the regula-tory position of this guide with the following clarifi-cations:

1. The second sentence of paragraph C.3 should be amended to read:

"The water quality for final flushes cf fluid sys-tems and associated components shall be at least equivalent to the quality required for normal oper- ,

ation. This requirement does not apply to disolved t-oxygen or nitrogen limits nor does it infer that

()

7 chromates or other additives normally in the system water will be added to the flush water."

2. Paragrapn C.4 should be amended to add:

Material such as inks, temperature indicating cray-ons, labels, wrapping materials (other than poly-ethylene), water soluble dam materials, lubricants, NDT penetrant materials and Couplants, which Con-tact stainless steel or nickle alloy material sur-f aces shall contain no more than trace elements of lead, zinc, copper, mercury cr other low melting alloys or compounds. Maximum levels of water leachable chloride ions, total nalogens ano sulfur compounds shall be imposed on the aforementioned materials.

t l C-5 Rev. 9

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

i l

1 1

() APPENDIX C, PART 2 NRC Reculatory Guide 1.38, Rev. 2. May 1977 Quality Assurance Reauirements for Packaoinc, Shiocinc.

Receivino Storace anc Manolinc o f Items f or Wa ter Cocied Nuclear Power Piants Tne TMI Quality Assurance Program complies with ne regulatory position o f this guice with tne following modifica- tions:

1. Section 3.6 o f ANSI NA5.2.2 - 1972 Concerns preven-4 tion of nalogenated materials from contacting

stainless steel or nickel alloy materials. Tn e position statec in Reg. Guice 1.37 also applies to

tnis guice.

2. Section 3.7.1 o f ANSI N45.2.2 - 1972 Cleated, sheathec coxes will ce used up to 1000 los. rather than 500 lbs. as soecified. This type of box is safe for, anc nas oeen tested for, loacs up to 1000 los. Other material stancarcs (i.e., ,

FE0 Spec. PPP-B-601) allow tnis. Special qualifi- i cation testing snall be requirec for loads in excess o f 1000 los.

{)

! 3. Section 6/2/1 o f ANSI N45.2.2 - 1972 i

For storage o f level 0 items access will be con-trollec and limited oy posting. Otner posir.ive 4

controls sucn as fencing or posting of guarcs will ce provided for nigner storage levels.

I 4 Section A.3.4.1 Appencix to ANSI 45.2.2 - 1972

The last sentence o f A.3.4.l(4) anc (5) shoulc be j corrected as follows

I

(4) "However, preservatives for inaccessible j insice surf aces o f pumps, valves and aice syster.is containing, reactor alant water sna'.. ce tne water flusnacle type."

(5) "'The name o f ne preservative usec sna11 be incicated to facilitate toucn up."

, 5. With regarc to Section A.3.5.2 o f tne Aopendix to ANSI Na5.2.2 - 1972 entitled "Taces ano Acnesives":

iaces will meet a sulanur limit o f 0.30% oy aeign:

instead o f 0.10% as specified in A.3.5.2(1)(a).

( C-6 Rev. s l

t.

e-- m.e-w-

~ - ,,n- - - -

.,.mn,,~..w..w-,n,.-n- , , , , ~ - - - - - - - - - - .n,-. -- - - - - - - - - - - - -- .

i l

() APPENDIX C, PART 2 This limit is reasonacle based upon the chemical content of commercially availaole tapes. Tapes will ce of a contrasting color rather than

" Brightly Colored" as required by A.3.5.l(3'.

6. With regard to Section A.3.7.1 o f the Appendix to ANSI N45 2.2 - 1972 entitled " Fiberboard Boxes":

In lieu o f A.3.7.l(3) and (4), the following will be imposed: Fiberocarc coxes shall ce securely closec either witn a water resistant adhesive applied to the entire area of contact between tne flaps, or all seams anc joints snall be sealed with not less than 2-inen wide, water resistant tape.

NRC Reculatory Guide 1.39, Rev. 2. Sectemoer 1977 Housekeecino Reouirements for Water Coolec Nuclear Power Plants Enoorses ANSI N45.2.3 - 1973 The Operational Quality Assurance Program complies with this guide with the following clarification: k r

1. With regard to Sections 2.1 and 3.2 o f ANSI N45.2.3

(]) - 1973 entitled "Plannino and Control o f Facilities", respectively:

The TMI Nuclear Station will not utilize the five level zone designation system referenced in ANSI N45.2.3, but will utilize stancarc janitorial and work practices to maintain a level o f cleanliness commensurate with company policy in tne areas of housekeeping, protection.

plant and personnel safety, and fire Cleanliness will ce maintainec, consistent witn the t

work being performed, so as to prevent tne entry o f j

' foreign material into systems consioered important to safety. This will incluce as a minimum cocu-mented cleanliness inscections unicn will be per-f o rme d immeciately prior to system closure. Con-trol o f personnel, tools, eouloment, and supplies will be estaclisned unen major portions of the re-actor system are opened for inspection, maintenance o f repair.

Acoltional nousekeeping recuirements will ce imple-mented as required for control or raciaactive con-i

' amination.

l C-7 Rev. 8 i

APPENDIX C, PART 2 NRC Regulatory Guide 1.54, June 1973 Quality Assurance Requirements for Protective Coatings Acolieo to Water Cooled Nuclear Power Plants Endorses ANSI N101.4 - 1972 The Operational Quality Assurance Program complies with this guide with the following clarification:

1. TMI shall comply with the Regulatory Position established in this Regulatory Guide in that QA programmatic / administrative requirements included therein shall apply to maintenance and modification activities even though such requirements were not in effect originally. Technical requirements associated with maintenance and modifications (e.g., code requirements, material properties, design margins, manuf acturing processes, and inspection requirements) shall be the original requirements or better.

2. The guidance of Regulatory Guide 1.54 shall be i followed for organic protective coatings selected I and evaluated in accordance with pertinent sections w/ of ANSI N101.2 when applied to interior surfaces of the containment. The supplier's quality assurance program shall be approved prior to implementation.

Quality Assurance documentation may not ce similar to records and documents listed in Sections 7.4 througn 7.8 o f ANSI N101.4 but will oe evaluated to assure that they provide at least the same degree of documentation as required by tnis standard.

NRC Regulatory Guide 1.58, Rev. 1 - Sectember 1980 Qualifications o f Nuclear Power Plant Insoection, Examination, and Testino Personnel Endorses ANSI N45.2.6 - 1978 The Operational Quality Asssurance Program complies with this guide with the following clarification:

1. The guidance of Regulatory Guide 1.58 shall oe followed as it pertains to the qualifications of personnel who verify conformance of work activities to quality requirements. The qualifications of plant operating personnel concerned with day-to-day

() C-8 Rev. 9 t

1 I

() APPENDIX C, PART 2 operation, maintenance, anc certain technical ser-vices snall ccaform to Regulatcry Cuice 1.8.

2. Not all personnel who:

A. Review and approve inspection and testing procedures, B. Evaluate the acequccy of activities to accomplish tne inscection anc test objectives, C. Evaluate tne adequacy of specific programs used to train anc test inspection and test personnel, D. Certify Level III incivicuals in scecific categories or classes, Will ce certifiec as meeting the Level III capacility requirements o f ANSI N 45.2.6-1978.

Ratner these personnel will ce cetermined by k management tnrougn evaluation of their ecucation f experience, and training to se fully qualified anc Q' competent to perform enese functions.

for the determination will be cocumentec.

The casis NRC Regulatorv Guice 1.6a. Rev. 2, June 1976 i

Quality Assurance Recuirements for One Design of Nuclear Power Plants Encorses ANSI NA5.2.ll - 1974 TMI sna11 comply with One Reculatorv :osition estaclisnec in this Reguletary Guice in tnat QA programmatic /aominis-trative requirements incluced tnerin snall apply to main-

! tenance anc mocification activities even tnougn sucn recuirements were not in e f fect originally. Tecnnical recuirements (e.g., code requirements, material properties, l cesign margins, manufacturing oracesses, anc insoection i

requirements) associatec vita maintenance and mocifications l snall ce tne original requirements or cetter, l

Tne Operational Quality Assurance Program complies with

, tnis guice ith ne follo.ing clarification to paragraon l C.2(1) o f Pegulatory Guice 1.6a: If an an exceptional i circumstance tne cesigner's immeciate Supervisor is the only tecnnically qualifisc incividual availaole, tnis i

i C-9 Rev. 9

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

I t

(:) APPENDIX C, PART 2 I review can be concuctec by the Supervisor, providi.1g that:

(a) the other provisions of the Regulatorf Guide are

) satisfied, and (o) tne justification is indivicually cocumented and approved in acsance by the Supervisor's management, and (c) quality assurance audits cover frequency and ef fectiveness o f use o f Supervisors as design verifiers to guard against abuse.

NRC Regulatory Guide 1.94, Rev. 1, Acril 1976 Quality Assurance Recuirements for Installation. Insoectio.2 ana Testinc o f Structural Concrete anc Structurai Steel curina tne Construction Pnase o f Nuclear Power Plants Enaorses ANSI N45.2.5 - 1974 The Operational quality Assurance Program complies with

, tnis guice witn the following clarification:

TMI sna11 comply witn the Reculatory Position estao-lisned in this Regulatory Guice in tnat QA program- ,

matic/acministrative requirements included tnerin shall apply to maintenance anc modification activities even {

tnougn such requirements were not in effect origin-O ally. Technical requirements associated witn main-tenance and modifications shall ce tne original recuirements or cetter (e.g. , coae requirements, material properties, design margins, manufacturing processes, anc inspection requirements).

NRC Reculatorv Guice 1.116, Rev. 0-R. May 1977 Quality Assurance Recuirements for Installation, Insoecticn ana Testing o f Mecnanical Eauioment anc Systems Encorses ANSI N45.2.3 - 1975 The Operational Quality Assurance Program comolies witn tnis guide dita the following clarification:

i TMI snali comoly witn tne Regulatory Position estac-

'. lisned in tnis Regulatory Guice in tnat CA program-matic/accinistrative requirements incluced tnerein

(

snall a7 ply to maintenance anc modification activities even tnougn sucn requirements were not in ef fect j originally. Tecnnical requirements associacea witn maintenance anc maaifications, snall oe tne original requirements or cetter (e.g. , coce requirements,

)

material procerties, design margins, manufacturing processes, anc insoection requirements).

I (

C-10 Rev. S

)

APPENDIX C, PART 2 NRC Reculatory Guide 1.26, Rev. 3, February 1976 Quality Grouc Classifications and Standard for dater, Steam ano Raoicactive aaste Containina Components of Nuclear Power Plants Since tne original design and construction of the Three Mile Island Plants was to dif ferent classification criteria than contained in tnis guide; TMI will comply with the regulatory position of this guide with the following clari-fications:

1. For modifications to existing plant systems and for new construction, items will be classified by Technical Functions according to tne original basis or tnis guide. This classification will not degrade tne safety of the system being modified.

2. Tie-in's to existing plant systems will be maoe to the same or more recent applicable code, standard and technical requirements which were applicaole to tne system to whicn the tie-in is to be made, v

NRC Reaulatory Guice 1.63, Rev. 2, July 1978 I

( ~)

Electric Penetration Assemblies in Containment Structures for Lignt hater Coolea Nuclear Power Plants TMI will comply with the regulatory position of this guide aitn tne folloaing clarification:

For modifications to existing structures and to new constructions, this guide will oe utilized providing its use will improve tne safety of the structure oeing modified or make a significant improvement in overall plant safety. Otherwise, the same or more recent applicable coc , stancard and technical requirements applicaole to tne original design and corstruction will be utilized.

NRC Reoulatory Guide 1.144 January 1979 Aucitina of Cuality Assurance Proarams for Nuclear Power Plants TMI is in caric agreement with the position set forth in the Reg. Guide suoject to the following comments:

- C-ll Rev. 9 ss

() 1. Section C.3.a(2)

The proposed seneculing requirement for internal aucits appears to enange the basis for naving a rational, programmatic approach to auditing. In its olace, the new regulatory guide requires manda-tory auciting of all program elements on a yearly casis. The latter would require that all elements octain tne same attention regarcless o f importance, past performance, or to what extent other aspects of quality assurance measuring and evaluating tech-niques are useo; as an example, the extent to wnicn surveillance and process monitoring is useo.

Accorciagly, minimum senedule frequency will be as defined in R.G. 1.33.

2. Section C.3.b(1)

Source inspection provides a controlled basis for replacing tne need for ext:rnal audits. The use o f quality assurance program surveillance will also be used as anotner alternative.

3. Section C.3.b(2) 2, I

while tne licensee is responsiole for procurement

({} control, this can be exercised tnrougn an annual evaluation of tne contractor's performance using pertinent results from manuf acturing surveillance ,

source inspection, receiving inspection, and otner applicaole factors. The evaluation woulc include a recommencation as to tne need for a scheculed program or proolem area audit. Hence, auditing, like surveillance anc inspection, will be treated as a quality assurance tool usec for evaluation.

Furtnermore, tne recommendation to audit will include provisions for reviewing tne imoortance and impact of the particular contractor's scope and status.

NRC Regulatory Guide 1.88, Rev. 2. October. 1976 Collection. Storace, and Maintenance o f Nuclear Power Plant Ava11ac111tv Assurance Recorcs Tal will comply witn the intent of cnis regulatory guide by compliance with tne requirements o f ANSI / ASME NQA-1-1979, Sucolement 175-1 ano Appencix 17A-1.

O C-12 Rev. 8

-w,w e,--e --y_---.i-e,_ ,m,-,.*,m, ,---,,,.--_e.c -------m-g ,,y _ _ . , ,---..--_+.-mw--.-.e w,w,. -..--_._....-

,79,p y r_e--_ ,.._- %,,w. -uy., -.. .,_,.m9 ..-,pg.g -

. APFENDIX 0 Ocfiniticns Words anc phrases useo in tnis Plan snali ce as cefined in ANSI N45.2.10, 1973, as encorsed oy Regulatory Guice 1.74, " Quality Assurance Terms anc Definitions," and as listed celow. Items shown below witn an asterisk (*) nave oeen modified from tne ANSI definitions.

1. Acceptance Criteria: Specifiac limits placec on anarac-teristics of an item, process, or service definec in coces, stancards, or a:ner cocuments.

2. Alara: (Acronym for As Lcw As Reasonacility Acnievaale)

- a metnod of analysis of :ne cerformance of activities-in raciological areas to cetermine specific metnocs for reducing man-rem exposure.

3. Arenitect/ Engineer (A/E): A firm unoer contract to pro-vice engineering or cesign services.

4 Agent: A person or firm emoonerec to provice a service on cenalf of GPUNC and under tne GPUNC QA Program. 't I

5. Approval:+ An act of endorsing and accing positive autn-orization (signature) to a cocument oy :ne person (s) res-ponsicle for One document.

, 6. As-Suil: Data: Occumenteo ca a :na descrioes One conci-tion actually acnieveo in a procuct.

7. Ccncurrence: Agreement 41:n :ne content of a cocument indicated oy signature prior to issuance.

8. Concition Acverse to Quality: An all inclusive term usec in reference to any of :ne following: failures, malfunc-tions, ceficiencies, cefective items, anc nonconfor-

mances. A significant concition acverse to quality is

{ one unicn, if uncorrected, coulc nave a serious effect on

, safety or operacility.

! 9. Contractor:+ A person or fira under contrac: to provice an on-site service anc worxing uncer :ne requirements of

neir own Quali;y Assurance Program. irms engageo in

construction managemen; are consicered contractors.

i f

0-1 Rev. 9 i

]

10. Corrective Action: Measures taken oy tne respons1'le a

,_f Manager to initiate action to correct cne coserved ceficiency anc others like it in tne system, and will modify operating prac Ices so as to prevent future

recurrence.

l

11. Engineering (Engineer): inis term refers to tne tecn-nical responsioilities of Tecnnical Functions, Plant

, Engineering or A/E's.

12. External Organirations: Any organization participating in the project whien is not a part of General Puolic utilities. Tnis term includes vencors, A/E's and con-tractors.

13. Important to Safety: As used in tne Introcuction to Appencix A to 10CFR50, this term refers to, " structures, systems,'and components that provice reasonacle assurance

• tnat tne facility can ce operatec witnout uncue risk to I

the neal:n and safety of ne putlic." The G?uNC inter-pretation is:

Items or activities naving direct or incirect affect on ene pnysical, functional or numan aallity to operate ne facility; to protect tne integrity of tne core; anc to co so witnout uncue ris< to tne' health and safety of One puolic.

() 14. Independent Review Groups: Committees or organizations witn responsibill:les for tne celicerately critical evaluation of metnods, procecures or concitions. Tney nave no cirect resconsioliity for tne cocuments, netnocs ,

or activities being evaluatea.

4 l 15. Monitoring: An act of assuring compliance of activities to program requirements oy direct ooservation.

16. Qualification (Personnel): The cnaracteristics or acili-ties gained tnrough ecucation, training or experience, as I

measurec against estaclisnea requirements, sucn as stan-cards, or tests, that qualify an indivicual to perform a required function.

17. gA Plan (Plan): Tne casic document whicn cescrices :ne 4

metnca anc extent o f compliance o f :ne gA s rogram o One applicaole regulatory requirements.

13. QA Program (Program): Ine plannec anc systematic actions j anien cons;i:ute como11ance witn regulatory auality assurance requirements anc :ne controllac cocuments unicn descrioe anc prescrice nose actions.

i D-2 Rev. 9 1

ww*g w-vg - wr7m mmem swmgr-musm*v,.-*-m-emy.gy g 7y---* d' imp-ggg9 g e wge p.gw--g y # pgw p*-.--=w- *

19. QA Recorcs: Tnore documents required to De maintained in

() accordance with the requirements o f k.sI/ ASME NQA 1979, Supplement 175-1 and Appendix 17A-1.

20. Quality Classification List (QCL): The controlled docu-ment used to record the results of quality classification evaluations.

21. Safety Review Groups: Committees or organizations with responsibilities for evaluation of methods, procedures or conditions affecting plant safety during the operational phase.

22. Special Process: A process, tne results of which are highly dependent on the control of tne process or the skill of tne operators, or Doth, and in wnich the speci-fied quality cannot be readily determineo oy inspection or test of the product.

23. Surveillance: An act of assuring compliance of a manu-facturing process or activity to specified requirements.

24. Traceability: The ability to trace th? history, applica-tion, or location of an item and like items or activities by means of recorded information.

I

25. Trenc Analysis: A quantitative method of collecting and

() analysing nonconf or nance / deviations events with tne goal of systematically cetermining programmatic / procedural weaknesses.

26. Vendor: A firm which manufactures items at an off-site facility and operates under the requirements of their own quality assurance pre, ram.

27. Verification:* An act of confirming, substantiating and assuring tnat an activity or condition is suitacle, proper and has been implemented in conformance with the specified requirements.

l l

() 0-3 Rev. 9