ML20072L190

QA Manual,Vol II

ML20072L190
Person / Time
Site:	Pilgrim
Issue date:	07/07/1983
From:	Harrington W BOSTON EDISON CO.
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ENCLOSURE (A)

Q'JAllTY ASSURANCE MANUAL

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QUALITY ASSURANCE MANUAL VOLUME II OPERATION OF PILGRIM NUCLEAR POWER STATION FOREWORD The Boston Edison Quality Assurance Program for operation of Pilgrim Nuclear Power Station (PNPS) is defined in this Manual, it is the governing document for control of quality related and quality assurance activities. The requirements herein were established to comply with the requirements of Title 10, Code, of Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants." All Boston Edison Company personnel who perform quality related and quality assurance activities associated with operation of PNPS are responsible to comply with the requirements of this Manual.

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QUALITY ASSURANCE MANUAL VOLUME II OPERATION OF PILGRIM NUCLEAR POWER STATION TABLE OF CONTENTS I Title Page il Foreword til Table of Contents v Table of Exhibits v1 Table of Figures vii List of Effective Pages Section C./g*.*

. _ Title I zation 2 Qua b k h surance Program 3 Design c.

4 Procurement Dongnet Control 5 Instructions, Proce

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and Drawings 6 Document Cor. trol 7 ControlofPurchasedMaterial,(sipment,ancServices 8 Identification and Control of MateMa Parts, and Componentu 9 Control of Special Processes .*

10 Inspection lI Test Control 12 Control of Measuring and Test Equipment

, 13 Handling, Storage and Shipping 14 Inspection, Test, and Operating Status

, Rev. 5 l 111 Date: 7/20/S3

TABLE OF CONTENTS Cont.

15 Nonconforming Material, Parts, or Components 16 Corrective Actton 17 Quality Assurance Records 18 Audits C.r-

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QUAllTY ASSURANCE MANUAL VOLUME ll OPERATION OF PILGRIM NUCLEAR POWER STATION TABLE OF EXHIBlTS s Exhibit No. Title 11-2-1 Quality Assurance Manual Change Request 11-4-1 Requirements for o Certificate of Conformance 11-5-1 PNPS Procedures, Vol. 3, Quality AsLLrance f,. Program Related Station Maintnenace and V

• Calibration Procedures 11-16-1 Corrective Action Request / Plan

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QUALITY ASSURANCE MANUAL VOLUME II

. OPERATION OF PILGRIM NUCLEAR POWER STATION TABLE OF FIGURES Figure tb. Title Il-I-l Corporate Organizatton 4

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LIST OF EFFECTIVE PAGES SECTION PAGE NOS. SECTION REV. NO. DATE ,

l i Title Page 7/20/83

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iI i&2 7 7/20/S3 12 1-3 6 7/20/83 13 I 5 7/20/S3 14 1-3 5 7/20/53 15 i-3 7 7/23/63 16 l-4 12 7/20/83 16 Exhibit 11-16-1 12 ,7/20/63 17 l-4 7 7/20/53 18 l-3 8 7/20/83 Rev. 20 viii Date: 7/20/83

ORGANIZATION I.0 PURPOSE This section describes the Nuclear Organization and other organizational units of Boston Edison Company (BECo) involved in the operation of Pilgrim Nuclear Power Station (PNPS). In addition, it describes the responsibilities and authority of key management individuals who control activities governed by the Quality Assurance Program, l.1 Organization The BECo Nuclear Organization is depicted in Figure No. 11-1-1.

The organization for Pilgrim Nuclear Power Station is further detailed in the Technical Specifications. Changes in Boston Edison's Nuclear Organization are reported to the Nuclear Regulatory Commission in accordance with the Technical Specif ication

/, requirements. Quality related activities associated with the

% g rptionai phase of nuclear power plants are performed primarily Fy,Vg Nuclear Organization. These operational phase activities are y ed by the requirements established in the Boston Edison Quellt urance Manual (BE0AM) for Operation of Nuclear Power Plants. Departments within Boston Edison that are subject to certain r ments of the BEQAM are:

(a) Purchasing # ] ment (b) StoresDepartmeh,/

(c) Engineering, Plannin Research Department, Testing and Standards Section Boston Edison has established the fo14owing committees which perform quality related functions: ( *,..,

'v' NuclearSafetyReviewandAuditCommihe,(NSRAC)

Operations Review Committee (ORC) #

The makeup, qualifications, and responsibilities of these committees are described in the Technical Specifications for the nuclear power plant and/or in Committee charters. NSRAC members are appointed by the Senior Vice President (Nuclear).

The corporate organization is more fully described in Boston

- Edison's Bulletin Book, Section A. Revisions or additions to the Bulletin Book are controlled by the Chief Executive Of ficer of Boston Edison Company.

REV: 8 Il-l-l DATE: 7/20/a3

1.2 Key Management Responsibilities and Authority 1.2.1 Office of the President The President, as chief administrative officer of Boston Edison Company subject to the direction of the Board of Directors, supervises the administration of the business and affairs of the corporation. He is a member of the Executive Committee of the Board of Directors as well as President and Chief Executive Of ficer.

The Executive Vice President has such powers and duties as may from time to time be prescribed by the Board of Directors or the Chief Executive Of ficer. During the absence or inability of the President, the Executive Vice President shalI possess alI the powers and perform all the duties of the President.

The Senior Vice Presidents are senior corporate officers

., responsible for the administration and conduct of Company f**

• business relating to specific areas as assigned within e the Office of the President.

1.2.2 (glor Vice President-(Nuclear)

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Tt/ d of Directors has designated a Senior Vice Pres as the corporate officer with responsibility and aut y to manage and direct the Nuclear Organization.

He is res n iele for all activities related to the operation o = nd reports to the Chief Executive Officer. He e nsible to establish overall policies and to assure e e Tive implementation of those policies.

Boston Edison has established a Quality Assurance Program to implement the requirements in Appendix B to 10 CFR Part 50 and the Senior Vic[% resident is assigned responsibility for assurinM*Wi; the Program is aggressively implemented'. He*d4e delegated responsibilities and authorities to accomplish r red activities accordinc ~

to his written policies. [*

The Senior Vice President-U:rlear) ic designated as the of ficer to whom defects and non-compliances relating to nuclear safety hazards are to be reported and is designated as the officer responsible for notifying NRC of defects and non-compilances when required by 10 CFR Part 21.

The assignment of corporate responsibilities for implementation of 10 CFR Part 21 is more fully described in Boston Edison Company's Bulletin Book, Bulletin B-2.

The foilowing vice presidents and managers report to the Senior Vice President:

REV: 8 11-1-2 DATE: 7/20/83 '

I (1) Vice President-Nuclear Operations (2) Vice President-Nuclear Engineering and Quality Assurance (3) Director, Nuclear Operations Review (4) Director, Outage Management (5) Planning, Scheduling and Cost Control Manager 1.2.3 Vice President-Nuclear Operations The Vice President-Nuclear Operations is responsible for all activities related to operation and maintenance of PNPS. He is responsible for establishing procedures and controls to assure that requirements of the BEQAM are effectively implemented by Departments within his organization, The Vice President-Nuclear Operations is responsibie to j.*

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, develop, maintain and control interdepartmental Nuclear

. *g'.* Operations Procedures (NOP's). The QA Manager reviews t

each NOP to assure that the described quality-related activities meet the requirements of the BEQAM.

• e h ilowing departments report to the Vice President-Nu/le Operations:

(l) Nu Operations Department v.-

(2) NucleargeplonsSupportDepartment iA (3) Nuclear Managwe.ent Scrvices Department (4) NuclearTrainingDepargment 1.2.4 Vice President-Nuclear Engi. @ g and Quality Assurance v

The Vice President-Nuclear Engin e 13 and Quality Assurance is responsible for all activities r ted to engineering and design for PNPS, including design changes and plant modifications. He is also responsible to oversee implementation of those quality assurance and quality control activities assigned to the Quality Assurance Department by the Senior Vice President (Nuclear).

The following departments report to the Vice President-Nuclear Engineering and Quality Assurance:

(l) Nuclear Engineering Department (2) Quality Assurance Department REV: 8 Il-I-3 DATE: 7/20/83

I.2.5 Qust ity-Related R:sponsibilities Common to All Department Man gers and Directors Each of the Department Managers and Directors identified in following paragraphs have certain quality-related responsibilities in common, as follows:

o Provide and implement policies and procedures for all quality-related activities which fulfill the requirements of this manual; ensure policies and procedures applicable to quality-related activities are approved by the QAD.

e Choose qualified, competent personnel to maintain a staff adequate to perform all quality-related activities.

Identify indoctrination and training needs and ensure they are fulfilled; coordinate training with the Nuclear Training Department. Evaluate the performance of personnel and take required actions.

e Provide the means and conditions (e.g., facilities, tools, f*

e/ . supplies, etc.) to allow personnel to carry out quality-related activities within the constraints of corporate eP$**

budget controls.

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• nsure coordination of activities across the interf h other departments and organizations.

e Be zant and maintain departmental awareness of appl yeregulatoryrequirements,aswelI as EECo commitr%gt

• and related industry codes and standards, e Recognize, o a/4 evaluate, and act upon feedback information, f M internal and external sources, to improve management controls and personnel performance.

f activities and potential Apprise upper and actual managementp'un problems. Ch cate and resolve prctlems with other departments. I xd corrective action when it is warranted, including me es to prevent proble-recurrence.

4 The functional roles and responsibilities of departments and organizational units that implement the OA progra~

are more fully described in Nuclear Operations Procedures, department procedures, or charters approved by appropriate levels of management.

l.2.6 Director-Nuclear Operations Review (DNDR)

The Director-Nuclear Operations Review is responsible to perform a daily surveillance of plant operations, REV: 8 II-1-4 DATE: 7/20/53

to ensure appropriate feedback information is provided to responsible corporate management-level review of operational decisions important to safety, to monitor implementation of nuclear safety-related activities, and to ensure corporate management is informed of operational problems and the status of corrective actions in response.

He is responsible to make reports directly to the Chief Executive Of ficer, both routinely and on request.

The DNOR chairs the NSRAC.

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l.2.7 Director of Outage Management The Director of Outage Management is responsible to cocrdinate planning and to direct scheduled plant outages necessary to maintain, modify,and refuel the plant.

Planning, Scheduling and Cost Control (PS&CC) Manager h*48 I !E V'D V

The PS&CC Manager is responsible for planning, scheduling, and cost control services and for coordinatina

,A*scurement interfaces between the Nuclear Orcanization

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ahd h e Purchasing Department.

l.2.9 Nuc Qegrations Department (NOD) y.

TheP1Igr1(St,ptionManagerisheadoftheNuclearOperations Department a. I spensible for the overall safe, reliable, and economic op t policles and regu @p n of PNPS in accordance with corporate ry requirements.

1.2.10 Nuclear Operations Support Department (NOSD)

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The Nuclear Operations Supp& Q partment is responsible for certain on-site activitief4h h support the Cilgrim Station Manager and the Vice Pre i a t-Nuclear Operaticns.

1.2.11 Nuclear Management Services Department (NMSD)

The Nuclear Management Services Department is responsible for certain on and of f-site activities which support The Pilgrim Station Manager and the Vice President-Nuclear 0;erations; The Department is responsible for maintenance and control cf the Facility Operating License and the PNPS Final Safety Analysis Report, and for Records Management / Document ConTrc! activities for the Nuclear Organization.

l.2.12 Nuclear Training Department (NTD)

The Nuclear Training Department is responsible to establish and coordinate implementation of a training program for all Boston Edison personnel who perform Il-1-5 REV: 8 DATE: 7/20/83

quality-related activities. This overall program shall indoctrinate all personnel in the Boston Edison Quality Assurance Program for PNPS and other management controls, and provide suitable training to permit personnel to perform their assigned activities. It includes special qualification training and certification activities, as required. Training responsibilities assigned to other managers are carriea out within the framework established by this program.

1.2.13 Nuclear Engineering Department (NED)

The Nuclear Engineering Department is responsible for engineering and design activities and construction associated with plant design changes and modifications, including safety evaluations required by 10CFR50.59.

j* lt is also responsible for all engineering evaluaticr.s

. g *. (e.g., studies, analyses, reviews) to support PNPS operation, maintenance, and refueling. These

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• responsibilities include establishment and maintenance h.qfasystemtoincorporateapproveddesignchangesirTo neering documents.

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l.2.14 Qual W surance Department (QAD)

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The SeniokVi@ President (Nuclear) has delegated authority an r administering % p nsibility for directing andg lity Assurance Manager of the Qu'Mty Assurance Department. Specifically, the Quality Assurance Department is accountable for:

o Establishing, maintaini 7 and assuring the implementat on of a Qual ssurance Program, which effectively complies i . 10CFR50, Appendix E, applicable codesandstanca.s,gr,dthe Nuclear Organization's policies.#

e Providing quality assurance expertise to assist line departments in the planning and implementation of design, procurement, construction, operations, and maintenance activities for the Pilgrim Nuclear Power Station. g REV: 8 li-I-6 DATE: 7/20/83

e Establishing, mair taining, and implementing an ef fective quality control f t.1ction for the Nuclear Organizations.

e Assuring that detailed, approved procedures are utilized throughout the Nuclear Organizations and by interfacing departments subject to Quality Assurance Program requirements such as Purchasing, Stores, Engineering, Planning and Research, etc.

e Preparation, revision, and control of the Boston Edison Quality Assurance Manual (BEQAM), which is the primary quality assurance document, in order to implement these responsibilities, the Quality Assurance Manager is provided with "Stop Work" authority whereby he can suspend any quality related activity or f'* . process which nay,in his opinion, adversely affect the safe operation of Pilgrim Nuclear Power Station.

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eP O ersonnel have sufficient authority and organizational to identify quality problens; initiate, recommend, o p de solutions through designated channels; and verl . ementation of solutions. The QA Manager and his sub ates communicate directly with cognizant departmenfhungp*ag rs and responsible personnel for the identi f icatl% resolution of deficiencies.

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The QAD Manager is responsible for the review, evaluation and approval of selected contractor, supplier, and engineering service organization quality assurance ;rograms prior to the issuance of BECo Purchase Orders / Contracts.

After award of BECo Purchase Orders / Contracts, he is responsible for performance of audits and source / surveillance inspections, as appropriate, at contractor, supplier, and engineering service organization facilities to assure compliance with BECo Purchase Order / Contract requirements.

The Quality Assurance Manager is responsible to review all procurement requirements, includ;ng technical anc quality assurance requirements of specifications, preliminary procurement Il-1-7 REV: 8 DATE: 7/20/83

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documents, and supplier exception /ceviations, to ensure proper consideration and incorporation of quality assurance and quality control requirements.

l The QAD is responsible to establish and maintain the Inservice Inspection and Test Program required by ASME Section XI and the PNPS Technical Specifications.

I 1.2.15 Purchasing Department The Purchasing Department is responsible to coordinate J ,.

P procurement of items and services required for PNPS

%e .3 , including approval of commercial conditions associated j?,*g with procurement activities. The Purchasing Department 4 is not authorized to change technical and quality assurance quirements specified by the department requesting

• • ement action. The Purchasing Department is responsible ment procedural controls according to requirements es a hed in the BEQAM.

.=g I.2.16 Stores jpEtment ws f

The Stores De$e t is responsible to coordinate preparation of purchase ord gf r material based on approved preliminary procurement documeRIs and is also responsible to receive, store, and control purchased material before it is released to PNPS. The Stores Department is not authorized to change technical and quality assuIan*gs., requirements specified by the department requesting the*y rement action. The Stores Department is responsibt jmplement procedural controls according to requireren s eteeblished in the EEQAM.

t l.2.17 Engineering, Planning and Research Department, Testing and Standards Division The Testing and Standards Division is responsible to direct and coordinate the activities within the Testing and Standards Section and to implement the requirements of the BEQAM related thereto.

REV: 8 11-1-8 DATE: 7/20/83

BOST0tl EDISON COMPANY NUCLEAR ORGANIZATION PRESIDENT b.

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• VICE NUCLEAR PRESIDErlT SAFETY NUCLEAR e, REVIEW ^

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I /' r," ' VICE PRESIDENT VICE PLANNING , p%, DIRECTOR NUCLEAR 4 PRESIDEtlT NUCLEAR SCHEDULING & NUCLEAR ENGINEERING &

, gIRECTOR OPERATIONS COST , UTAGE OPERATIONS QUALITY '

CONTROL 8, ' NAGEMENT REVIEW ASSURANCE i

MANAGER _

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NUCLEAR NUCLEAR $ ,,) NUCLEAR QUAllTY NUCLEAR ENGINEERING ASSURANCE

! MANAGEMENT NUCLEAR OPERATIONS TRAINING DEPARTMENT DEPARTMENT SERVICES OPERATIONS SUPPORT DEPARTMENT DEPARTMENT DEPARTMENT DEPARTMEtk' l l l

OPERATIONS l

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Date: 7/20/83 FIGURE 11-1-1 l

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QUALITY ASSURANCE PROGRAM 2.1 PURPOSE This section establishes requirements for the Boston Edison Quality Assurance Program for operation of PNPS, the applicability of the program, and the indoctrinatior, and training program to ensure its proper implementation and effectivenes3.

2.2 POLICY A Statement of Policy, which was signed by the President, establishes the overall quality assurance policy of the Boston Edison Company (BECo). This statement sets the goal of safe and reliable operation of PNPS: commits the Company to a quality assurance program designed to ensure compliance with regulatory requirements, Company commitments, and established practices for efficient plant operation; and requires every person involved in quality assurance program related activities to comply with the provisions of the program.

Employees should refer to Boston Edison Company Bulletin B-5 for specific details ,this corporate quality assurance policy.

2.3 PROGRAMRE[ 'TS

.y 2.3.1 The Bo Edison Quality Assurance Manual (BEQAM) for Operation of Nuclear r Plants establishes the Quality Assurance Program applicable

• ation of Pilgrim Nuclear Power Station. The requirement i BEQAM were established to comply with the requirements of if)e10,CodeFederalRegulations,Part 50 (10 CFR 50), Appendix *ff #'

Plants" and are struk[ Quality ed in Assurance accordance Criteriacriteria.

with its eighteen f or Nuclear P This program requires im [tingprocedurestobewritten. These procedures may be prepared af Nuclear Operations Procedures (50P's),

Department Procedures, or Group procedures / instructions. Specific assignment of responsibilities for epsuting and controlling activities related to the program are identifie%i.I g hese procedures.

Activities falling within the scope of e , Program categorically include: itedling, shipping, storing, designing, purchasing, cleaning, erecting, f abricating, installing, insl $cting, testing, operating, maintaining, repairing, refueling, training, and modifying.

Changes to the BEQAM are controlled in accordance with the requirements of 10 CFR 50.54(a).

Operational phase activities are a!;o controlled in accordance with the requirements of the Facility Opt. rating License No. DPR-35 for

. the Pilgrim Nuclear Power Station and 10 CFR 50.59 requirements.

Rev: 11 II-2-1 Date: 7/20/53

2.3.2 This QA Program conforms to the following NRC Regulatory Guides and associated ANSI Standards to the extent that they are applicable to operational phase activities:

Regulatory Guide 1.8 Personnel Selection Rev. IR, 1975 and Training (ANSI N18.1-1971/ANS3.1)

Regulatory Guide 1.33, Rev. 2 QA Program Requirements 1978 (Operational)

(ANSI N18.7-1976/ANS 3.2)

Regulatory Guide 1.64 QA Program Requirements Rev. 1, 1975 for the Design of Nuclear (ANSI N45.2.ll-1974) Power Plants Regulatory Guide 1.88 Collection, Storage and Rev. 2, 1976 Maintenance of Nuclear Plant Quality Assurance Records f.jANSIN45.2.9-1974) tory Guide 1.123 QA Requirements for Control of Rev '977 Procurement of Equipment, Materials and Services for Nuclear Power (ANSIh.f13-1976)

.*y' Plants QA Program Auditing Regulatory n h 1.144 Requirements for Rev. 1, 1980 K#4 (ANSI N45.2.12-1934.* Nuclear Power Plants ANSI N45.2.16 N *g.* h Requirements for the Calibration (IEEE Std. 498-1975) S *** A. and Control of Measuring and Test Equipment used in the Construction and Maintenance of Nuclear Power p.

Generating Stations Regulatory Guide 1.146 # alification of Quality Assurance 1980 r am Audit Personnel for (ANSI N45.2.23-1978) Nceg. Powerplants Regulatory Guide 1.58 Qualification of Nuclear Power Rev. 1 (9/80) Plant Inspection, Examination (ANSI N45.2.6-1978 and and Testing Personnel ASNT-SNT-TC-1A-1975) 2.3.3 Certain plant modification work can be expected to be comparable in nature and extent to related activities during the initial design

. and construction of the plant. The requirements of this manual and the current implementing procedures may need to be supplemented or replaced for such work. The Quality Assurance Manager will review upcoming modification work and shall determine whether a Project Quality Plan is needed for a s pecific modification.

Rev: 11 II-2-2 Date: 7/20/E3

When needed, the Project Quality Plan is developed before modification work begins at the plant. The Project Quality Plan is prepared with appropriate input assistanc'e from other managers. It describes the activities included in the work, and identifies requirements which differ from, or are in addition to, the requirements in this manual.

It identifies participating organizations and their interfaces, and the governing procedures which implement the QA Program. Each Project Quality Plan is approved by the Quality Assurance Manager.

2.3.4 The following Regulatory Guides and Standards contain requirements which will be applied to those cot..;truction related activities associated with major modifications during the operational phase that are comparable in nature and extent to related activities occurring during initial plant design and construction:

Regulatory Guide 1.28 QA Program Requirements Rev. 2, 1979 (Design and Construction)

(ANSI N45.2-1977)

[peulatoryGuide1.30 QA Requirements for the Installa-4 0, 1973 tion, Inspection and Testing of

'45.2.4-1972 Instrumentation and Electric Equipment

4. QA Requirements for Cleaning Regulato8;Cuh

/ e 1.37 Rev. O, 197 V of Fluid Systems and Associated (ANSI N45.2.1 Components of Water-Cooled

. Nuclear Power Plants Regulatory Gudie 1.3 / QA Raquirements for Packaging, Rev. 2, 1977 p* Shipping, Receiving, Storage (ANSI N45.2.2-1972) . and Handling of Items for Water-Cooled Nuclear Power Plants Regulatory Guide 1.39 ***. Housekeeping Requirements for

• 4dster-Cooled Nuclear Power Plants Rev. 2, 1977 (ANSI N45.2.3-1973) .c' g b

Regulatory Guide 1.54 QA Re ements for Protec t ive Rev. O, 1973 Coatings Applied to Water-Cooled (ANSI N101.4-1972) Nuclear Power Plants Regulatory Guide 1.55 Concrete Placement in Rev. O, 1973 Category 1 Structures Regulatory Guide 1.74 QA Terms and Definitions Rev. O, 1973 (ANSI N45.2-10-1973)

Regulatory Guide 1.94 QA Requirements for Installation, Rev. 1, 1976 Inspection and Testing of Structura (ANSI N45.2.5-1974) Concrete and Structural Steel ,

During the Construction Phase of  !

Nuclear Power Plants Regulatory Guide 1.116 Quality Assurance Requirements for Rev. 0-R, 1977 Installation, Inspection and Testig of Mechanical Equipment and Systemd (ANSI N45.2.8-1975) l Rev: 11 11-2-3 Date: 7/20/65

2.4 PROGRAM APPLICATION 2.4.1 The BEQAM is applied to activities affecting structures, systens, and components which have been designated safety related because they prevent or mitigate the consequences of postulated accidents which could cause undue risk to the health or safety of the public. Structures, systems, and components which are designated as safety related are classified as Q and are identified on the Q-List.

2.4.2 In addition, the Q-List may include other structures, systems, and components for which the Vice President-Nuclear Operations and the Vice President-Nuclear Engineering and Quality Assurance have agreed to utilize the management controls and implementing procedures of this QA Program for the control of selected work activities.

2.4.3 The BEQAM is also applied to activities af fecting fire protection systems and equipment required to limit fire damage to safety related rtructures, systems and components so that the capability to safely saut down the plant is ensured. Applicable fire protection

/,systemsandequipmentareidentifiedontheFireProtectionList.

v 2.4.4 rdance with the requirements of 10 CFR 71.51, the BEQAM is al's ied to Boston Edison activities, including procurement activi related to delivery of licensed material to a carrier for tran nder the license provisions of 10 CFR 71.12. Applicable shipping co s or transport packages are identified on the 10 CFR 71.12 Lic Shipping Container List.

4 2.4.5 Provisions have b ma(e for establishing and maintaining the Q-List and the Fire Protec L t under the control of the Nuclear Engineering Manager.

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2.4.6 . Provisions have been made foY establishing and maintaining the 10 CFR 71.12 Licensed Shipping Container List under the control of the Pilgrim Station Manager. ,.*.,

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2.4.7 To the extent necessary to ensure the 4 p1 y procured items and services, suppliers and subsuppliers are required t qvide quality assurance programs which implement the pertinent provispens of 10 CFR 50, Appendix B. Specification of this requirement and evaluation of supplier quality assurance programs by the QAD are covered in Section 4.

2.5 PROGRAM CONTROL 2.5.1 The Quality Assurance Manager is responsible for establishing and maintaining the BEQAM and for assuring the implementation of a Quality Assurance Program which effectively complies with 10 CFR 50, Appendix B, applicable cons and standards, and corporate policies.

2.5.2 Proposed revisions to the Boston Edison Quality Assurance Manual are prepared by BEco personnel based on predetermined need and NRC regulatory requirenents and guides using a Boston Edison Quality Assurance Manut.1 Change Request, Exhibit 11-2-1.

Rev: 11 II-2-4 Date: 7/20/63

The Quality Assurance Department is responsible to review each Change Request to verify conformance with QA Program requirements and to control BEQAM changes in accordance with the requirements of 10 CFR 50.54(a). The resulting Change Requests are approved for implementation by both Vice Presidents after approval by the Quality Assurance Manager.

1 Holders of controlled Boston Edison Quality Assurance Manuals are responsible for insertion of the latest revisions in their assigned Manuals, and are required to sign and return the revision transmittal form thereby acknowledging receipt.

2.5.3 The Quality Assurance Program is implemented using procedures prepared and controlled according to BEQAM Section 5. Review and approval by the QA Department is required to assure compliance with BEQAM requirements and for ensuring that such procedures are approved by the QAD prior to use.

2.5.4 he Nuclear Training Department is responsible to establish and coordinate lementation of a training program for all Boston Edison nuclear el who perform quality-related activities. This overall program sh*e ctrinate all personnel in the Boston Edison Quality Assurance Progra PNPS and other management controls, and provide suitable training mit personnel to perform their assigned activities. It includes s qualification training and certification activities, as required. 'ning responsibilities assigned to other managers are carriedoutwik e framework established by this program.

Department Managersk

• Directors are responsible f or assuring that their personnel are a u in the use of departmentproceduresap[plytrainedandproficientr,p A by the Qua

,t' hat training is performed bdi scheduled in compliance with the requirements of the Boston Edison Training Program.

2.5.5 ImplementationofanaggressiveQuakiAssuranceProgramisessential toachievethegoalofcontinuedsafeahreliableoperationof the Pilgrim Nuclear Power Station. EacWphoninvolvedinquality relatedactivitiesconcerningdesign,construgion,preoperational testing, operation and maintenance of PNPS is* responsible for attaining quality in his/her work and for compliance with the requirements of the applicable quality assurance approved procedures. Each person is also responsible for promptly reporting to his/her supervisor whenever a noncompliance with a QAD approved procedure occurs and whenever a potential unsafe condition is recognized.

2.5.6 Audits are conducted by QAD on a regularly scheduled basis to assure

. compliance with established BEQAM requirements, and the results of these audits are reported to responsible management personnel.

If a difference of opinion arises between Quality Assurance personnel and those of another department, resolution is first attempted by the Quality Assurance Manager and the other cognizant manager. If a solution acceptable to the QA Manager cannot be obtained, the matter shall be promptly referred by the QA Manager to the Vice President-Nuclear Engineering and Quality Assurance for resolution. If a resolution Rev: 11 11-2-5 Ihte: 7/20/63

acceptable to the QA Manager is not obtained after it has been referred to the Vice President. the matter shall be promptly referred by the QA Manager to the Senior Vice President (Nuclear) and, if necessary, to the President, for resolution.

2.5.7 The scope, implementation, and effectiveness of the Boston Edison Quality Assurance Program is assessed at least bi-annually; the results are reported to the NSRAC and to upper management (vice presidents and abote).

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Reo 11 11-2-6 Date, .}/20/B3

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(GJ.ITY ASSURANCE MANUAE NGE EQEST 90EEME SECTION PARAGRAPH NO. PAGE NO. REV. NO.

REVISIOV_tp act Wordind i'

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ORIGINATOR DATI.

APPROVAE SIGNATLT.ES:

QUAEITY ASSURANCE MANAGER DA3 VICE PRESIDENT-NUC12AR OPE. RATIONS DA~E l

VICE PRESIDENT-NUCII.AR EJdGINEERING A.'C Q' CIU l g ASSURANCE 1

Rev.: 1I Exhibit II-2-1 Date: 7/20/83

(QAl-A41)

DESIGN CONTROL 3.1 PURPOSE l

This section estrblishes the requirements for the control of design activities to assure that appropriate quality standards are specified and design reviews are accomplished in a planned and orderly manner.

3.2 GENERAL 3.2.1 Engineering and design activities associated with plant design changes and modifications of nuclear safety related structures, systems, and components are accomplished according to ANSI N45.2.11-1974 as amended by Regulatory Guide 1.64, Rev. 1.

3.2.2 Before implementation plant design changes and modifications are reviewed by responsible NED, QA, ORC, and Station personnel, and jr

• safety evaluations are performed for design changes to ascure gja . compliance with 10 CFR 50.59. If the Operations Review Committee J(**

E C) determines that an unreviewed safety item is involved, the ear Safety Review and Audit Committee (NSRAC) review, and a Regulatory Commission (NRC) approval is required through N0 to performing the change. Approved design changes are imple under .the direction of NED.

3.2.3 Whenservf . ige purchased by the NED for performance of work associated sMg fplant design changes and modifications, QAD reviews and appgpuls the procurement documents to assure that appropriate qual surance program requirements are in-cluded. 'p/*,

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3.2.4 ' controls are established in written procedures to assure that revised design do ments which describe the design changes to safety re li, structures, systems, and components that performed the are reviewed original either TD design, j(gl@the or by a organization responsible alternateorganizationdesignatedbyBostig. Edison.

3.3 DESIGN CHANGE PROCESS 3.3.1 A Plant Design Change (PDC) Request is used by BECo personnel to obtain authorization for and to implement plant design changes and modifications to systems, structures and components at the Station. Subsequent changes to an approved PDC package are made using Field Revision Notices (FRNs).

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3.3.2 The cognizant personnel within the BECo Nuclear Organization, or approved supplier of engineering services, who are respon-sible for the engineering design inputs and design verifica-tions perform their functions according to written procedures to assure the following:

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3.3.2.1 Design documents are identified and controlled, and I

revisions thereto are reviewed, approved, collected, stored, and controlled in a systematic manner.

Rev.: 8 II-3-1 Date: 7/20/S3 1 ,

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(QAl-A42)

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3.3.2.2 The individuals or groups responsible for design re-views and other design verification activities and their authority and responsibilities are identified and design interfaces are controlled.

3.3.2.3 Plant design changes and modifications are reviewed, approved and controlled to assure compliance with 10 CFR 50.59.

3.3.2.4 Applicable regulatory requirements and design cases are correctly translated into specifications, draw-ings, written procedures, and instructions.

3.3.2.5 Appropriate standards for quality are specified in design documents and deviations and changes from such standards are controlled.

(.*,3.3.2.6 Suitable design controls are used in applying prin-ciples of reactor physics and in making seismic,

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• stress, thermal, hydraulic, radiation, and accident V analyses.

3.3.i.Y Mesign changes and revisions to design documents are

/ ropriately controlled to assure compatibility of

'als; accessibility for inservice inspection, ma ance, and repair; and delineation of accep-tanc4c'eriaforinspectionsandtests.

3.3.2.8 Methods ifying design changes, such as design reviews, a ative calculations, and qualification testing are properly chosen and followed; the most adverse design conditions are specified for test programs used to va(IIy the adequacy of designs.

3.3.2.9 Individuals or groups rI*agIogble for design verifi-cation meet the requiremeetv for independence pre-scribed in Regulatory Guide 1.(p4*,*Rev. 1.

3.3.2.10 Design documents, including drawing and specification registers and approved revisions thereto, are con-trolled and distributed to responsible individuals in the user organization in a timely manner, to preclude inadvertent use of superseded material.

3.3.2.11 Errors and deficiencies that adversely affect safety related structures, systems, and components in the design process are documented and appropriate cor-rective action is taken.

I 3.3.2.12 Standard off-the-shelf commercial or previously approved materials, parts, and equipment essential to the safety functions of structures, systems and cornonents are reviewed for suitability of applica-tion before procurement.

Rev.: 8 II-3-2 Date: 7/Z/53

(QAl-A43)

PROCUREMENT DOCUMENT CONTROL 4.1 PURPOSE This section establishes the requirements for preparation, review, approval and control of procurement documents for items and services to assure applicable technical requirements and quality assurance require-ments are included and that spare or replacement parts are subject to controls at least equivalent to those used for the original equipment.

4.2 PROCUREMENT PROCESS 4.2.1 Preliminary procurement documents prepared for equipment, parts and services shall include appropriate technical requirements, and QAD-approved quality assurance requirements. In addition, these documents shall specify when quality category Q applies and identify any other specific or special requirements; in particular, storage level, shelf life, and storage maintenance requirements. Additional information to be provided should in-f/$'. clude as appropriate:

Applicable Specifications and Drawings

- egulatory Requirements c ponent Identification Requirements (including Q LNo.)

d) 'W e) Test %gbleCodesandStandards d Inspection Requirements f) Documeh(;apon Requirements (See Paragraph 4.2.2) g) ng, shipping, and handling requirements.

h) Special ptG@( QQgrating Installatiot and Maintenance manuals, including Preventive Maiheenance Instructions i) Suggested Suppliers based on QAD's Approved Suppliers List  %

4.2.2 The originator of the prelim (inprocurement documents shall identify any documentation req pobesubmittedbythe supplier, including documentation to Be, submitted to BECo. for review and approval and documentatio/Io be submitted for acceptance of the items or service. Required documentation shall also include documents to be provided to BECo. for records retention purposes.

For quality category Q items and services, supplier documenta-tion for acceptance may be a Certificate of Conformance, unless requirements of the applicable Codes and Standards preclude this option (i.e. , more specific documentation is called for).

If a Certificate of Confonnance is required, the procurement documents shall also specify that the Certificate of Confor-mance must meet the requirements given in Exhibit 11-4-1. In addition, the originator shall determine if additional docu-mentation is required from the supplier to support the Certifi-cate of Conformance; and identify any such documentation in the procurement documents.

Rev.: 10 II-4-1 Date: 7/20/S3 l

(AQl-A44) 4.2.3 Pr:Ilminnry procurement documents shall be rsview3d to ensura proper identification of items and inclusion of appropriate technical requirements for items and/or services being procured.

This review shall verify the quailty category and the completeness of the requirements.

4.2.4 Preliminary procurement documents for all items and services shall be submitted to QAD for review to ensure inclusion of appropriate quality assurance requirements.

4.2.4.1 If the preliminary procurement documents require the supplier to submit a Certificate of Conformance, end BECo QA/QC will not perform source inspection (off-site),

surveillance inspection (on-site), or audits, the QA reviewer shall identif y acceptence inspections or tests by BECo, OQC which will verify the validity of the supplier'!

certificate and the ef f ectiveness of his certification syster 4.2.5 The procurement documents for spare or replacement parts are subject to controls at least equivalent to those applied for original

. * . equipment.

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4.3 PURCHAS[M,ERS/ CONTRACTS 4.3.1 Ttr urement documents (Purchase Order and accompanying cocuments) shal 't'e)4ssued according to corporate policies and procedures and shall od'nt all the technical requirements and QA requirements specified Nuclear Organization. Added technical or quality assurance re ments and any changes to the issue Purchase Order /

Contract are s to the same review, and approval as the original preliminary procu documents.

4.4 $UPPLl.ER QUALITY ASSURANCE PR 4 EVALUATION AND APPROVAL 4.4.1 Evaluation of the Quality Assura e Programs of potential suppliers of Q ltems and services shall performed by QAD or by others when authorized by the QA Manager._ re protection systems and components, evidence of UL or FM a I will be accepted in lieu of supplier evaluation. An evaluation i gges review of the sucolier's QA Program Description and a survey of h)S*' implementation of that program before the supplier initiates any activities af fected by the program under a BECo P0. The supplier's QA Program Description is reviewed to ensure inclusion of pertinent requirements of the SEQAM and 10 CFR 50, Appendix B. The evaluation must be completed and the supplier approved by QAD. The names of approved suppliers are placed on the SECo QA-Approved Suppliers List which is maintained by QAD.

4.4.2 Q items and services may be procured from suppl ers with quality assurance programs that have not been approved by BECo Quality Assurance. BECo Purchase Orders / Contracts to suppliers who have not been approved must, however, contain detailed supclementary quality assurance requirements to assure that material, equipment, parts, and services meet the BECo Purchase Order / Contract requirements. in such cases the preliminary procurement documents are reviewed by QAD to assure additional Rev.: 10 11-4-2 Date: 7/20/83 i

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(QAl-A45)

QADaction(s) are planned, e.g. , source inspection, additional receipt inspection, as deemed necessary to provide the required assurance that quality standards have been met.

4.5 DEVIATION REQUESTS FROM BECo PURCHASE ORDER / CONTRACT REQUIREMENTS 4.5.1 When a Deviation Request is submitted by a supplier to BECo Purchasing, the cognizant BECo Purchasing Agent shall forward the Deviation Request to the Nuclear Organization for initial action. The Deviation Request, after it is approved /

disapproved by the cognizant BECo Manager and reviewed by QA, is returned to the BECo Purchasing Department which notifies the supplier. The BECo Purchasing Department issues a change to the Purchase Order / Contract based on approved procurement documents revised to reflect the approved Deviation Request.

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( Rev.: 10 l II-4-3 Date: 7/20/63 l

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(QAl-A48)

Requirements for a Certificate of Conformance I

When a Certificate of Conformance is required by the procurement documents to be submitted by the Supplier, it shall:

1. Identify the purchased item or services by BECo's purchase order number.

2. Identify the specific procurement requirements met by the item or service, either by verbatim quotation of the requirements, or by specific reference to the document (s), and location (s) with the document (s), where the requirements are specified. The requirements identified must include any changes, waivers, or deviations, approved by BECo, which apply to the item or service.

3. Identify any procurement requirements that have not been met, and refer to the document (s) which record BECo's approval of the disposition of such nonconformances.

4. attested to by the person responsible for assuring the quality of the r service, as described in the supplier's BECo - approved Quality A

e Manual.

The supplier q,lity Assurance Manual, as approved by BECo's QA Department, shall describe stem to control Certificates of Conformance, including a procedure for cqilp 'ng the certificates which meetsthe above requirements, and a procedure for and approval of certificates.

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1 Rev.: 10 EXHIBIT 11-4-1 Date: 7/20/53

(QAl-A52)

INSTRUCTIONS, PRCCEDURES, AND DRAdlNGS 5.I PURPOSE This section establishes the requirements to assure that activitles af fecting the quality of safety-related systems, structures, and components are delineated, controlled, and implemented through use of written instructions, procedures, or drawings.

5.2 BECO QUALITY ASSURANCE PROGRAM-RELATED PROCEDURES 5.2.1 The requirements of this quality assurance program shall be implemente by Nuclear Operations Procedures (NOP's), issued by the VP-Nuclear Operations, and Departnent Procedures, issued by each Department Manager. Procedures required to implement the BEQAM i1 are called quality assurance program related.

5.2.2 Each quality-related activity shall be governed by an appro;riate combination of procedures, instructions, and drawings. Requirements pertaining to drawings, including sketches, diagrams, schematics, and f,**

e . similar terms, are in Section 3. Detailed instructions may be provide

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• n various ways controlled by quality assurance program related NOP's partment Procedures. This appropriate combination of procedures, i ctions, and drawings shall be identified in the work authorizinc dc and, in all cases, the management controls specified in appr ;DP's and Department Procedures shal I be implemented.

5.2.3 Procedure Mgtructions, and drawings shall include appropriate quantitativ bl qualitative acceMance criteria, aopropriate methods for documentinh op* recording data obtained during the performance of the activity, % p ,riate requirements for equipment and instrumentation to g@gd, and suitable control for environmental conditions. ***

5.2.4 Every new NOP and Department Pr,qr,edure, unless exempted by Paragrar .

5.2.5, shalI be submitted to tgga,1Ity Assurance Manager to deternir if the procedure is quality assurfi program related. If so, the Quality Assurance Department shal P@rgw the procedure and a subsequent revisions to assure the requigents of the Boston Edison Qualit'/ Assurance Manual are met. Afte# review, the Quality Assuranct Manager shall approve. If the procedure is determined to be not quality assurance program related, review by QAD and approval oy the Quality Assurance Manager is not required, and the procedure will be so marked by QAD. However, any major revisions (additions) to such a procedure will require the revised procedure to be submitted to the Quality Assurance Manager for review to determine if the revision makes the procedure quality assurance program related.

5.2.5 For PNPS Procedures, all of the procedures in Section I of the PNPS Procedures Manual and selected Section 3 procedures shall be reviewed by the Quality Assurance Department and approved by the Quality Assurance Manager. The applicable procedures in Section 3 are listed in Exhibit 11-5-1. Although all of the PNPS Procedures in Sections 2-8 are quality assurance program related, only the selected procedure which describe the overall implementation of the quality assurance program at PNPS will be reviewed by the QAD and approved by the Quality Assurance Manager.

Rev: 9 11-5-1 Date: 7/20/83

5.2.6 Changes to procedures are reviewed, approved, controlled, and distributed in the sanie manner as the original issue.

5.2.7 AII maintenance and modification activitles affecting Station structures, systems and components are controlled by the Maintenance Request system. All Maintenance Requests are reviewed by the Quality Assurance Department to assure that appropriate requirements are specified for quality related activities and to incorporate appropriate quality control hold points.

5.3 SUPPLIER PROCEDURES 5.3.1 When the procurement documents require the supplier to submit procedures for BECo approval, the department which originated the procurement documents shatI ensure the appropriate reviews and approvals are obtained. Reviews and approvals are required from those departments which would review and approve similar

[ BECo procedures. In particular, procedures for quality assurance

= ,. and quality control activities shall be reviewed by the QAD.

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.i PNPS-l VOLUME IIl QUALITY ASSURANCE PROGRAM RELATED STATION MAINTENANCE AND CAllBRATION PP00F3;:E5 3.M.1 GENERAL 3.V.1-1 PREVENTIVE MAINTENANCE 3.v.l-l.1 Instrument and Control 3.M.1-1.2 Electrical 3.M.1-I.3 Mechanical 3.M.l-5 PROCUREMENT OF ITEMS AND SERvlCES 3.M.l-5.1 Preparation of the Quality Verification Documentation List l'

3.'/. lM. d . Handling and Storage of Material, Equipment, and carts j*.

3.M.l-7.2* val and/or Return of Inventoried Material, Equicrent, P qF, rom Warehouse 3.M. I-8 DlSPO OF NONCONFORMING MATERIAL 3.t!.l-10 CAllBRATIOF. h ONTROL OF MAINTENA*CE TOOLS AND EOLIP'/

3.t! . l- 10.1 Torque Wrench bl r + ion 3.M.!-10.2 Linear t/easurement [entCalibration 3.M.1-10.3 Calibration of Non-Controlled Lab Equipment 3.M.2 INSTRU'/ENT AND CONTROL ,.,

3.?> . 2- 8. 2 Pressure Working Standards Calibrati % }..'

3.M.4 MECWANICAL 3.M.4-IS WELDIN3 PROCEDURES 3.M.4-15.1 Welding Filler Material Control l

Exhibit 11-5-1 Rev. 9 Page I of I Date: 7/:?/E3

DOCUMENT CONTROL 6.I PURPOSE This section establishes the requirements Tbr review, approval, control, and distribution of documents and changes there'o'.

6.2 GENERAL REQUIREMENTS AND RESPONS1BIL1 TIES '

6.2.1 Boston Edison Company requires that dccument control measures be established to control issue and revision of documents which prescribe activities affecting quality. These measures assure that documents, including changes,are reviewed for adequacy in4'cpproved for release by authorized personnel and that cocuments are ' distributed to and used in the performance of the preceribed'a:tivity.

6.2.2 Department Managers are responsible to establ ish' pro'cdcures JP for the identificatior. of documents prepared within their

- %e,..% . Department which prescribe activities af fecting qualit y

,%'f=qpch as instructions, procedures, design specifications and V ings. Such documents are classified as " controlled d nts" and each Department is responsible to provide a 1 WE " " controlled documents" which they identif y to the t ument Control Center. Department procedures require t ontrolled documents, including changes, prepared within the rJ ment are reviewed for adequacy and approve'd for use withi he Department or for release outside the Department by a gbri d personnel.

6.2.3 Controlled document ved for release outside the Department are transmit ed to the BECo Document Control Center for distribution to other departments within BECo and to external organizations wWhg appropriate, in accordance with written procedures which ups that controlled d:cumer's including changes, are distributedgp,br use to the Department-where the prescribed activity is perf 44 The SECo DocumentControlCenterisrequiredtomptainamaster list of " controlled documents" and records of incation to which they are distributed. Acknowledgement forms will accompany the transmittal of controlled documents. Sucer-seded copies of controlled documents are destroyed or stamped " void" by the recipient of the controlled document.

6.2.4 Department Managers are also responsible to establish tracedures to identify all controlled documents required for the perforrance of activities affecting quality, to assure appropriate controlled documents are used to prescribe quality requirements, and t,o ,

assure that the latest applicable document for the prescribed activity is used in the performance of the work done by the Dep artment. _

Rev: 8-11-6-1 Date: 7/20/83

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6.3 TECHNICAL SPECIFICATION CHANGES 6.3.1 Changes to the Technical Specifications are originated via a _nemo transmitted to the Nuclear Management Services Department (NMSD).

6.3.2 NMSD reviews the proposed Technical Specification change in light of other licensing considerations that may be going on in parallel with this proposed change, prepares a draf t transmittal to the NRC (Licensing Branch), and assures that a safety evaluation is performed.

6.3.3 NMSD forwards the proposed Technical Specification change to ORC for review. The' ORC recommends to the Station Manager

• Specification Change

[.* approval gnd renders /disapprovaloftheTechnical a determination in writing whether an unreviewed

*# questic 1 is involved. The Station Manager approves olr roves the proposed Technical Specification change and it to NMSD.

7h 6.3.4 NMSD then fc8w the proposed Technical Specification change to NSRAC for r 7

6.3.5 d Technical Specification chance NMSD for submitthen*tal L,repares 'Th kop#4

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to t he NRC . % *.*

6.3.6 NRC approved Technical Specification chuges are distributed toholdersofcontrolledcopiesofthegtgcaISpecifications.

Holders the approved are changes.

responsible The to update Nuclear their co Training D y @sgoon receipt rtmynt revie s of J

changes to formulate any new training required. f 6.4 OPERATING LICENSING CHANGES 6.4.1 Changes to the Operating License are processed in the sa-e manner as Technical Specification changes, above.

6.5 FINAL SAFETY ANALYSIS REPORT CHANGES 6.5.1 Changes to the Final Jafety Analysis Report (FSAR) are controlled in accordance with the requirements of 10 CrR 50.59 and 50.71e.

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< , - / \ Rev: 8 e !I-6-2 Date: 7/20/53 r -c 5

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' CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICE 7.1 PURPOSE This section establishes the requirements for control of purchased material and equip'ent (hereaf ter called items) and services to assure conformance to specified technical and quality assurance requirements. Measures to obtain objective evidence of quality furnished by suppliers include supplier evaluation and selection, audits and inspections at the source, and inspections and tests upon receipt.

7.2 GENERAL REQUIREMENTS 7.2.1 The quality of purchased items and sersices is assured by an appropriate combination of supp!!er and BECo activities which is decided during pr6paration and review of procurement documents as specified by the requirements f* . of Section 4. When quality assurance activities by the inciuding provision of documentation, 4* JI(** suppl ier are he BECo QADspeci f ied, the supplier's quality assurance evaluates I ram and its inplementation to ensure the pertinent p lons of 10 CFR 50, Appendix B will be met by the sup Qu as a h ,ality acceptance assuranceof_the activities by SECo item or service uponinclude, receipf mpletion; methods include final inspection at the sou *greceipt inspection, review of supplier-provided doc ,/tation, and tests. Other quality assurance activities by BECy*m include audits, surveillance inspections, in-ph incpections, witnessing suoplier activities, and rev suppiler documents, such as

- engineering doucments hWt procedures, before use.

7.2.2 The QAD maintains an Approved S niters List (QA-ASL) which identifies suppliers for whom "* evaluated and approved as satisfactory quality assurance arams and implementation.

This list permits the use of certa Mpliersonanongoing basis. The QAD reviews supplier doccmenigtion of his quality assurance program and performs,or obtair4 evidence of, a survey which assures its implementation. At least annually, QAD performs an evaluation of a supplier's quality performance, and at least triennially, re-surveys or audits the supplier to cortinue the approved status. Supplier surveys may be by BECo or by others under contract to BECo for this service, or obtained via the Coordinating Agency for Supplier Evaluation (CASE). In addition, ASME Certificates are used as evidence

, of supplier quality assurance program implementation, for the items and services covered by the certificates.

Rev: 5 11-7-1 Date: 7/20/83

7.2.3 Certain items used in fire protection systems, which are UL or FM approved,are purchased without the supplier evaluation described above. In gen'eral, receipt inspection and test upon receipt are performed to accept these items.

7.2.4 Certain items, called " commercial items" may be purchased with assurance of quality by receipt inspection and selective testing.

These " commercial items" are specified in a Nuclear Operations Procedure which is approved by QAD. Requituments for such items include pre-established receipt inspection supplemented by test requirements, when applicable. Suppliers of such items are not required to implement any quality assurance program requirements.

7.2.5 Certain services performed by suppliers at PNPS or in other BECa f acilities may be performed according to BECo's QA program. Suppliers of such services are governed by BECo

'rocedures and BECo quality assurance requirements.

'...* Nonconformance to procurement requirements or BECo approved supplier documents, which is identified by the supplier or MggECosource/surveillanceinspection,andwhichconsistsof dNW'pg rrore of the following,must be submitted with technical j u*si4f lon to BECo for approval of recommended disposition as pro in Section 15:

(l) Technic rial requirements are violated.

(2) Supplierdocumen%afprgedbyBECoareviolated.

(3) Nonconformance cannot rected by continuation of the original manufacturing process or by rework.

s" (4) The item does not conform to the orb.iget requirements even though it can be restored to.a cok /t

• in which its capability to f unction is unimpaired. ,

7.3 SUPPLIER EVALUATION AND SELECTION 7.3.1 Supplier evaluation and selection is an integrated action which involves Nuclear Organization Departments, Purchasing, and QAD. This cooperative effort ensures that items and services are purchased from qualified suppliers, i.e.,

suppliers capable to provide items and services which meet technical, quality,and commercial requirements.

7.3.2 The department which originates the procurement and identifies the technical requirements is responsible to determine the capability of the selected supplier to meet the technical requirements.

1 Rev: 5 l 11-7-2 Date: 7/20/83 l

7.3.3 The QAD is responsible to determine the capabGilty of the selected supplier to meet the quality assurance requirements imposed, if any.

7.4 SUPPLIER AUDITS When warranted by the complexity or duration of the supplier's activities, the QAD performs audits of the supplier's cuality assurance program implementation and effectiveness according to Section 18.

P 7.5 SDURCE INSPECTION 7.5.1 Source inspection includes surveillance inspection. in-process inspection (hold points), wi+nessing suppeler's activities (cften requiring notification points), and final Inspection (notd point). QAD determines what source insDection is necessary, based on the nature, co plexity, ar.d inscriance ci supplier activities, and perforrs it to ensure procurement docu~ent requirements are met and purchased items and services are ep 4 ,acceptaDIe.

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7.5.2 Ific hold points and notification points are included in p ment document requirements.

7.5.3 Survet h e inspections are performed by QAD if conformance with ttf5 Irements of the procurement documents for a particula + cannot be determined when the item is received or when know, g6blems exist during the Drocurement phase. The purpose of sucSgs eillance is to provide a selective review of the implementa f the supplier's quality assurance crc; ram or of the conforman @ ls product to requiremeits of the procurement documents.*4 uality Assurance determines the cepree of supplier surveillance inspection to be performed.

7.5.4 Sourceinspectionsmaynotberhssarywhenthequality of the item can be verified by reviewi D supplier documents, or inspection or test upon receipt. nTs e of source inspections are docurented and maintained by BEC . * *,.

7.6 PECEIPT AND INSPECTION AND TESTS 7.6.1 Upon receipt at PNPS, purchased items are separated from already processed items until perfccmance of receipt inspection.

7.6.2 The QAD performs receipt inspections according to the requirements of the BECo Purchase Order / Contract and pre-established inspection instructions. Documentary evidence that items conform to procurement requirements shall be available at the PNPS site before installation and/or use of such items to assure that:

Rev: 5 11-7-3 Date: 7/20/83

( .' ) The item is properly identified and that its identification corresponds with the documentation received.

(2) Stated packaging and shipping requirements have been maintained.

(3) All procurement requirements have been met.

(4) Documentation records are acceptable in accordance with predetermined inspection instructions.

7.6.3 After identification per Section 8, accepted items are located in a controlled storage area.

7.6.4 When document deficiencies or nonconforming items are identified, items are held in a segregated area, and identified and handled according to Section 15.

7.6 . * , A written record of the results of receipt inspection and

,#{,*thedispositionofreceiveditemsismaintainedaspartof e h e permanent plant records.

All items issued bear a g rmance tag and have documentation to support their a5ee 1Iity. If traceability is lost or the documentation revi )*i (Kunsatisfactory,an control item becomes subject to the e blished for nonconforming items.

7.6.6 AcceptanceohpmsmayrequiretestingbyBECoorby anotherqualif%dgnJppller. Tests are controlled according to Section 11. #

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Rev: 5 11-7-4 Date: 7/20/83

(QAl-A68)

IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS 8.I PURPOSE This section establishes the requirements to identify and control materials, parts and components, Inc.luding partially f abricated subassemblies, to assure they can be traced to associated documentation.

8.2 PROCUREMENT 8.2.1 The originator of procuremant documents includes appropriate SECo identification of the materials, parts and components being procured.

8.2.2 BECo issued procurement documents for safety related items require the Supplier or Contractor to have a material iden+Ification and control system which provides for traceability of the materials, parts and components being procured to objective Gyality evidence by use of heat number, part number, or serial number, or by other appro:riate eJhods.

8.3 RECEIPT IN N 8.3.1 Receip 44apctions are performed at PNDS to verify that materials, parts an& Mn)gnents are properly identified.

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8.2.2 Subsequent to 4{ ance of the materials, parts and components at receipt inspect . pe MRIR number assigned by QAD may be placec on the accepted mat i s, parts and components to identify and control the item (s). rking should be permanent but shalI not interfere with the f unc the item, if the materials, parts and c,omponents cannot be mark cause of size, shape, material or quantity, a QA Material Conformance Tag is af fixed to the accepted materials; parts; and components with the appropriate MRIR number indicated to provide the proper ide ication.

8.3.3 MRIR numbers are assigned in such 'a mar'hEr hat they provide trace-abilliy to objective quality evidence and q) 'of assigned numcers is maintained by QAD. "

8.3.4 Nonconforming materials, parts and conDonents are identified according to Section 15.

8.4 CONTROL OF MATERIALS, PARTS AND COMPONENTS 8.4.1 Procedures are established for the control of quality during f abrication and/or installation which will ensure that material, components, items and workmanship conform to the stated specifications. These controls ensure materials, parts, and components can be related to fabrication and installation history.

Rev: 5 11-8-1 Date: 7/20/83

(QAl-A-69) p 8.4.2 Material for pressure retalning parts and component supports shall carry identification markings which will remain distinguishable until the component is assembled or installed. If the original identification markings are cut of f or the material divided, the marks shall either be transferred to the parts cut or a coded marking shall be used to ensure identification of each piece of material during subsequent fabrication or installation. For studs, bolts, and nuts it is permissible to identify the Certified Material Test Reports or codes for material used in each component in lieu of identifying each piece of material. Welding and brazing material shall be identified and controlled so that it can be traced to each component of a pressure retaining system.

8.4.3 Traceability shall be provided for parts and equipment that require a separate or special operation to cualif y the item for use in nuclear pIants to the appropriate documentation f urnished by the suppIier.

For other material, parts and components identification control shall assured by surveillance inspections and inspection hold or witness a ists as appropriate.

6.4.' in Sventthattheidentificationofanitembecomeslostor l Illeg$ the materials, parts, and components are considered nonconfo d are identified according to Section 15.

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Rev: 5 11-8-2 Date: 7/20/63

(QAl-A71)

CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE This section establishes the requirements for control of special processes by the use of qualified personnel, procedures, and equipment.

9.2 GENERAL 9.2.1 Special process controls require:

1) Compliance with codes, standards, specifications, criteria and other special requirements of applicable design and procurement documents.

2) Special processes be performed by qualified personnel according to qualified procedures that comply with applicable regulatory f,, requirements.

V *

• MV entification of parameters to be considered; applicable ds of documentation; and the codes, standards, specifica-tid g or criteria which govern the qualification.

4) Ident

• n of the necessary qualification of personnel, procedu r equipment when special processes are not covered by existin g s or standards or when quality requirements for an item excePe /he* requirements of established codes or stan-iards. \ f 9.3 PURCHASED MATERIAL, EQUIPMENT 8

...&RTS 9.3.1' When material, equipment or parts which use special processes are purchased, the originator o ,he BECo procurement document specifies the special proces r4 personnel and equipment qualification requirements by 'ng applicable codes, standards and specifications or , identifying detailed specific requirements on or with t e Junocurement document.

9.3.2 QAD identifies inspection hold points. Special process docu-mentation requirements may be placed on the procurement document.

9.3.3 The quality verification documentation required by the Purchase Order is reviewed at receipt inspection of material, equipment and parts by QAD as part of the requirements for satisfactory

. acceptance of the material, equipment and parts and maintained in the Station or QAD File as appropriate.

Rev.: 5 II-9-1 Date: 7/20/53

l (QAl-A72) l l

l 9.4 SPECIAL PROCESSES PERFORMED AT THE PNPS 9.4.1 Special processes used during operation, maintenance, modifi-fication and refueling at PNPS are performed by qualified Station, contractor and engineering service organization personnel according to detailed written procedures which are reviewed and approved by the responsible Department before the performance of the associated work.

9.4.2 QAD assures that Station, contractor and engineering service organization special process procedures used during operation, maintenance, modification and refueling of the operational nuclear power plant are reviewed and approved and that per-sonnel and equipment involved in special processes are quali-fied before the start of the associated work.

9.4.3 The cognizant Department is responsible for the qualification f, of Station procedures, equipment, and personnel and for 9 ,*, , assuring these qualifications are periodically maintained.

9.4.4 * %'#

nal processes are performed according to the requirements s t 'ed on a Maintenance Request which identify appropriate app i procedures and appropriate equipment.

9.4.5 The dat3 documentation associated with the performance of special pr es are reviewed by the QAD Department for completeness. / *

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9.4.6 Special process s, qualifying data, personnel and equipment qualificat cords, and the data and documentation associated with the performance of special processes are main-tained in the Station or QAD File as appropriate.

9.5 SPECIAL PROCESS PURCHASED SERVICES PERFOR Qiif-SITE ey 9.5.1 When special process services arehr, chased from service organizations who perform the associate 4.= work off-site, the originator of the procurement documents # specifies any special process procedures, personnel, and equipment qualification re-quirements by invoking the applicable codes, standards and specifications or by identifying detailed specific requirements on or with the procurement documents.

9.5.2 QAD identifies inspection hold points, and special process documentation requirements may be placed on the procurement

. document.

9.5.3 The data and documentation associated with special processes are reviewad by QAD and maintained in accordance with the requirements of Section 17.

l Rev.: 5 II-9-2 Date: 7/20/S3

i l

(QA2-A1)

INSPECTION 10.1 PbRPOSE This section establishes requirements for inspection activities related to operation, maintenance, modification, replacement, additions, altera-tions and refueling of systems, structures and components to assure compliance with associated instructions, procedures and drawings.

10.2 SURVEILLANCE INSPECTIONS 10.2.1 Surveillance inspections are documented and reviewed by QAD personnel.

10.2.2 Deficiencies identified as a result of surveillance inspections are documented and entered into a Follow Program.

Nonconformances identiiled as a result of surveillance in-10.g* *N*

,spections are documented and entered into a Follow Program.

10.2.4

• h illance Inspection Reports and related documentation are a gedintheQualityAssuranceDepartmentFile.

10.3 INSTALLATION IN

h. DNS 10.3.1 Insta11atiot @ pections are required at PNPS to assure that work associafWtI/with maintenance, modification, and refueling of safety refhtpf stems, structures and components is properly performed %

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10.3.2 Installations inspecti ofl*s are performed at PNPS by QAD per-sonnel, other qualified individuals designated by QAD, or contractors having a BECo acc g ed QA Program. Individuals assigned to perform installatba,.(nspections shall not be directly involved in the perfornNge of the work being in-spected and shall have the qualifica g necessary to perform the inspection. ,2**

10.3.3 Installation inspection results should indicate, as appro-priate, the inspection procedure used, the applicable accept /

reject criteria, any qualitative and quantitative data obtained during the inspection, the inspection status, identification of the inspector, date the inspection was performed and any other information pertinent to the inspection.

. 10.3.4 Installation Inspection Reports and associated documentation including copies of the Maintenance Requests are maintained in the Quality Assurance Department File.

10.4 INSERVICE INSPECTIONS Inservice inspections are performed under the cognizance of QAD in accor-dance with Section XI, ASME Boiler and Pressure Vessel Code, and the PNPS Technical Specifications.

Rev. 8 II-10-1 Date: 7/20/E3

(QA2-A2) 10.5 INSPECTION CONTROLS Controls exercised during inspection assure that:

10.5.1 When direct inspection is either impossible or not feasible, indirect control shall be provided by monitoring processing, operational tests, methods, equipment and personnel.

10.5.2 Procedures for maintenance, modification, and/or alterations are reviewed by QAD personnel to determine the need for independent installation inspections and incorporation of " hold points".

10.5.3 Inspection procedures or instructions are available with necessary drawings and specifications before inspection activities are performed.

Inspection controls require that objective acceptance criteria, prerequisites for performing inspections, limiting conditions, and special equipment requirements be prescribed as appropriate to the i,nspection activity.

10.5.4 T

/q*g'qdmeasuringequipmentiscalibratedwithinrequiredlimits, acto t to Section 12.

10.5.5 etion results are recorded, evaluated and retained in Testanfh*w accordance the requirements of Section 17.

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Rev.: 8 11-10-2 Date: 7/20/83 l

(QA2-A4)

TEST CONTROL 11.1 PURPOSE This section establishes the requirements for testing systems, structures and components to assure that they will perform satisfactorily during operation of PNPS.

11.2 GENERAL REQUIREMENTS The Boston Edison Company has overall responsibility for test activities performed on safety related structures, systems, and components during operation, surveillance, maintenance, and modification activities.

Tests are performed to verify that plant behavior conforms to design criteria, to assure that failure and substandard performance are identified and controlled, and to demonstrate ratisfactory performance after plant modification and maintenance activities.

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• Document test activities are maintained by BECo in accordance with require, of Section 17. Deficiencies identified during tests are contro11e p eordance with requirements of Section 15. Tests performed are claw Tests and contro11e s$(digd k scribedas Proof below.Tests, Post Work Tests, and Surveillance 11.3 PROOF TESTS Lg .-

11.3.1 The originator of p c ment documents specifies appropriate requirements for proo associated with the purchase of naterial, equipment and tg 11.3.2 QAD assures that selected proof tests are witnessed at supplier facilities, or are selectively witnes ed at PNPS when these proof tests are not performed at sup r facilities. Proof tests are witnessed by qualified oersonnel M** approved procedures or checklists. g b..

11.3.3 Proof Test Data Reports, submitted by supplie $*,*are reviewed by QAD during receipt inspection of material, equipment, and parts at PNPS and are considered a requirement for satisfactory acceptance of the material, equipment, and parts at receipt inspection.

11.3.4 Deficiencies identified during proof testing are controlled according to Section 18.

11.4 TOST WORK TESTS 11.4.1 Post Work Tests are performed at PNPS after satisfactory completion of installation inspections associated with maintenance, modification and refueling of systems, structures, and components.

Rev: 7 11-11-1 Date: 7/20/83

(O2-A5) 11.4.2 Post-Work Tests are performed by qualified personnel in accordance with w-Itten, approved test procedures. These procedures identify all test prerequisites and environmental conditions which must be satisfied before performance of the Post Work Test. The Watch Engineer, or his designee, reviews and approves the post-work test data results and signs off and approves the test data sheets.

11.4.3 Deficiencies identified during the performance of Post Work Tests are controlled according to Section 18.

1. 5 PERIODIC SURVEILLANCE TESTS 11.5.1 Periodic surveillance tests are tests required by the Technical Specifications or other commitments which are performed to demonstrate that systems, structures and components perform satisfactorily during operation of the nuclear power plant.

11.5.2 f 411 periodic surveillance tests are identified on a Master QS veillance Test List which is controlled by N0D. This Master lance Test List identifies the type of test activity, fr*e interval and cognizant NOD Manager responsible for perford the periodic surveillance tests. Special handling tools an ment are included in the scope of periodic surveillan s to assure that they are adequately maintained.

11.5.3 Periodic surveiF1 ),testsareconductedbyqualifiedpersonnel according to writ

• approved test procedures. Personnel assure that equipment and Ihspu tation utilized in performing the periodic surveillance tests is cib ed within the specified interval. These procedures identify all erequisites and environmental conditions which must be satisfied bef fe the performance of the periodic surveillance tests.

11.5.4 The NOD Manager is responsible to as g.4 hat surveillance tests are performed when required, test results a g*e* luated, and test requirements are satisfied. ,

l 11.5.5 Deficiencies identified during the performancf of periodic surveillance tests are controlled according to Section 18.

Rev: 7 11-11-2 Date: 7/20/E3 l

(QA2-A6)

CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 PURPOSE This section establishes requirements for the control of measuring and testing devices used for the measurement, inspection, and testing of material, equipment, and parts and instrumentation and control systems to assure that they are calibrated, adjusted and maintained at specified intervals to assure accuracy within required limits.

12.2 CALIBRATION PROGRAM 12.2.1 Measuring and Test Equipment List 12.2.1.1 All tools, gauges, instruments and other measuring and testing devices which are used for inspecting, testing, monitoring and calibrating material, equip-f,. ment, and parts and instrumentation and control V .* , systems are itemized.

• ' .\**9 1.2 The list contains the names of each measuring and

'42 .

test equipment, its identification number, the max-

• v 4 *gmum calibration interval, the group responsible for p m 'ntaining the measuring and test equipment, and rence to the associated calibration procedures.

12.2.1.3 The i7pnt Group Leader designated on the list is res ib, to develop a Group List which identi-fies th 'ng and test equipment controlled by the Group equires calibration, the calibration interval, appropriate calibration procedure number, scheduled calibration date and actual calibration date. **,

12.2.2 Identification of Measuring and Tes( 2qs pment N.

12.2.2.1 Each piece of measuring and te,je equipment itemized on the List is marked with its identification number by the Group responsible for its maintenance.

12.2.2.2 For new measuring and test equipment, the cognizant Group Leader assigns an appropriate serial number and identifies the measuring and test equipment accordingly.

. 12.2.3 Calibration of Measuring and Test Equipment by Station Personnel 12.2.3.1 The cognizant N0D Group Leader is responsible for as-suring measuring and test equipment is calibrated on or before the designated calibration due date. ,

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Rev.: 6 II-12-1 Date: 7/2C/E3

(QA2-A7) i i

12.2.3.2 The cognizant NOD Group Leader is responsible for calibrating the measuring and test equipment using written procedures, af fixing the calibration date and the next calibration due date on the measuring and test equipment, and for maintaing records of calibration data.

12.2.3.3 Calibration intervals are established on the basis that sufficient redundant or equivalent test equip-ment is maintained to adequately resolve suspected or verified inaccuracies resulting from the degree of usage, stability characteristics, and other condi-tions affecting use of the measuring and test equipment.

12.2.3.4 Working standards used for calibrating equipment are f,. traceable to the National Bureau of Standards and are v*,

• supported by certifications, test reports and data as required.

5 equipment is found to be out 12h.*y.'f When measuring calibration, andon test an investigati is conducted and i ented to determine the validity of previous urements or tests performed with the measuring a t equipment and to determine the acceptability of e Jtems previously measured or tested. Mar-ginal car test equipment is acceptable for use if calibh ata is approved by the appropriate Group Supe p.

12.2.4' Calibration of Measuring and Test Equipment by EP&R 12.2.4.1 For measuring and te eA pment which is requested to be calibrated by-EP& N t originator of the re-quest shall provide the ap siate accuracy toler-ances and the test data require % s to EP&R.

12.2.4.2 Upon return of the measuring and test equipment, N0D assures the calibration data submitted by EP&R is as originally specified.

12.2.5 Calibration of Measuring and Test Equipment by an Engineering Service Organization

. 12.2.5.1 For measuring and test equipment which is required to be calibrated by an engineering service organization, the originator of the procurement document references l the appropriate accuracy tolerances, and the appro-priate calibration test data requirements in the procurement documents, or supplies manufacturer's calibration specifications for the specific device.

Rev.: 6 I1-12-2 Date: 7/20/E3

(QA2-A8) 12.2.5.2 Upon return of the measuring and test equipment, NOD assures that the calibration data submitted by the engineering service organization is reviewed and affixes the calibration data and next calibration due date on the measuring and test equipment.

12.2.6 Calibration Records / Data 12.2.6.2 Calibration records and data for all measuring and test equipment listed are maintained in the Nuclear Records Management System.

12.2.7 Control Measuring and test equipment is controlled to prevent the use of uncalibrated or defective equipment, the spread of radio-active contamination, the introduction of impurities into high purity systems and damage to or loss of equipment. Iden-(,p,%*.tification tags are placed on measuring and test equipment to icate such special conditions as radioactive cleanliness or limitations.

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11-12-3 Rev.: 6 Date: 7/ 3/E3

(QA2-A9)

HANDLING, STORAGE AND SHIPPING 13.1 PURPOSE This section establishes requirements for handling, storage, shipping, cleaning and preservation of material and equipment to preclude damage, loss or deterioration.

13.2 PROCUREMENT OF MATERIAL AND EQUIPMENT 13.2.1 The originator of a procurement action specifies on the in-itiating document requirements for handling, storage, shipping, cleaning and preservation of material and equipment in accor-dance with applicable codes, standards, specifications, sup-plier technical manuals, or Station Special Orders / Procedures.

Special consideration is given to critical, sensitive, perish-able, or high-value articles, including the need for special

. handling tools and equipment.

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13.2.2(V tructions shall be provided for marking and labeling for ing, shipment and storage of items. Marking shall be ad ge to identify, maintain and preserve the shipment, in-ciudshy*ged for special environmental or other controls.

13.3 RECEIPT OF MATERI hFQUIPMENT 13.3.1 o.

Upon receipt orrfategial and equipment, Operational Quality control personnel reviewTjpE urement documentation and identify any additional handling) r e, shipping, cleaning, and preservation rer"irements to be co gt! with at the site warehouse.

13.4.2 Handling, storage, shipping, cleaning, and preservation re-quirements accomplished by a s @ ier are verified by source inspection or at receipt inspec h g.gt PNPS and include visual inspection of crates, boxes and cVa ' ers for damage. When deficiencies are noted at receipt in 'on (such as shipping damage), they are noted on the Receipt Inspection Report, and a BECo NonconformanceMaterip**is Report issued and con-trolled according to Section 15.

13.4 HANDLING, STORAGE, SHIPPING, CLEANING AND PRESERVATION AT PNPS 13.4.1 The Stores Department Superintendent designates an individual who performs handling, storing, cleaning, and preserving opera-tions required for material and equipment at the PNPS ware-

. house.

13.4.2 cleaning and preservation are performed as required to maintain an

! item in its original and useable condition after withdrawal from l

the warehouse. Such activities are normally required after i

installation of material and equipment and are performed by designated Station personnel.

1 Rev.- 5 I1-13-1 Date: 7/::/E3

l (QA2-A10)

INSPECTION, TEST AND OPERATING STATUS 14.1 PURPOSE This section establishes requirements for identification of the inspection, test and operating status of materials, parts, and components from receipt inspection through installation and subsequent operation to preclude bypassing of requirements and inadvertent operation.

14.2 REQUIREMENTS 14.2.1 N0D is responsible for establishing procedural controls to assure that the status of nonconforming, inoperative, of malfunctioning structures, systems, or components is identified to prevent inadvertent use.

14.2.2 tis responsible for establishing procedural controls for bypassing ope t ons, such as temporary removal of electrical leads or temporary inst n of jumpers.

14.2.3 Controls (m>Et)heestablishedforapplicationandremovalofstatus indicators sd'c tags, markings, labels, and stamps to assure that the inspe g test, and operating status of structures, systems, and components is%sPpprly indicated.

gg 14.2.4 During operation, main , testing, or modifications Station personnel are responsib ogjaligning, isolating, and appropriately tagging equipment and systeta*to prevent inadvertent operation so that activities can be safely performed.

N0D assures that the appropriate in etion and testing status of 14.2.5 systems, structures and components.is rly identified during maintenance, modification, and refuelin PS to preclude the bypassing of specified requirements. ,,

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i Rev: 5 i

11-14-1 Date: 7/22/53

I NONCONFORMING MATERI AL, PARTS, OR CO'PONENTS 1

15.I PURPOSE This section establishes the requirements and methods used within the Boston Edison Company f or the docu-entation and control of nonconforming materials, parts, and components to prevent their inadverten+ installation or use.

This section also establishes the requirements and retrods to identif y end segregate nonconforming items, provide for. '

their disposition, anc not if y offected organizations.

15.2 CEOUIREMENTS .

15.2.1 A ll materials, parts, or ccmponents which co not conform to 5:>eci f ied requirements shall be documented as cescribed herein.

15.2.la. All nonconforming meterials, parts, or coconents

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Identified at receipt inspection or instalIation V ', inspection shall be documented or a Nonconformance

• Report (NOR) except as noted in D. below.

Document Deficiency Notice (DDN) shall be usec when 15.2. Th *

. ,5 g/; ~entation is f ound to be incomplete, Or incorrec i ate during receipt inspection, thereby mak I g it ind ate that the item conforms to specified requi

s. If an item with an caen DD', is with::ra e for use, . N;R shall be initiated.

15.2.ic. Nonconformin 4h. docunented on an NCR or ite-s fee which a DDN ha initiated shall be clearly ice-ti;iec withaNonconformbceTag.

15.2.10. Nonconforming materials, Js, or components icen+ i f ie::

during operation, mainten e,p.

are documented and reported5eQ,or surveillance rai l ure and t'al f ur testi t ier g Report. ,

15.2.2 when recuired by Purchase Order or contract,*' contractors, suorIie s, and engineering service organizatiens working under their ow e BE:0 approved QA Program shall submit nonconformances dispositionec "a::e:t as is" or " repair" to BECo for approval. The cognizant f.EC discis t ine group shall review the supplier's disposition and its .iust if i:stic ;

this review and approval may be docu-ented direct ly on the suer t ier's report. NED shall assign a BECc control number to each suct report.

As an alternative, NED may request CAD to issue a BECc NCR to cceer

. the report . NED shalI notif y the supplier of BECO's approval.

15.2.3 Nonconforming materials, parts, or components shall be physically segregated f rom conforming items and controlled to prevent ina:sertent installation or use. Installed nonconforming items shall be icentified l

and the status of the system shall be controlled to prevent inadvertent use. Any system, component, or structure may not be declare: operatie Rev: 7 11-15-1 Date: 7/20/E3

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in accord:nc] cith the definition of the Tcchnical Specificction until the Nonconformance Report is dispositioned, implemented, and approved and the Nonconformance Tag is removed.

15.2.3a. Tagged nonconforming items shall be placed in a segregated and controlled storage area designated for this purpose.

15.2.3b. When physical segregation is not practical, for exar;te, with large items which are stored in place, suitable means, such as roping off the area,shall be used to clearly irdicate the nonconforming status.

15.2.3c. Nonconforming material, parts, and equipment, whict,because of their makeup and intended use, cannot readily be returned to a conforming state (such as chemicals, weld rod, concrete, etc.) shall not be released for instellation, if the non-conformance which caused the item to be classifie: as un-acceptable or indeterminate can be corrected af ter instei f ation, the item may be released for installation. Tech-ical justidica-tion for the installation shall be prepared and F. ace rart of the documentation, including the limits on examinaticn. testing,

,%*A or inspection activities that can be performed on tre structure,

• he system, or component with the nonconforming iter irsta! led.

e intenance Pequest process provides the necessa y co , including review by the Quality Assurance De: art-ent, to p nt inadvertent installation and inacvertent use c' the struc )gystem,orcomponentpriortodisDesitionir;cf the nonce abregnce.

15.2.3d. Nonconformanch ,g shall only be removed by Quality Assuranceperso.qfjeftersatisfactoryresolutionofthe NCR or DDN.

15.2.3e. The Quality Assurance Depar#=pnt shall keep recor:s cf all unresolved nonconformanceshq.aonitor Station act is it ies to assure that:

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1. Tags have not been removed c tered or items Sti1!

classified as nonconforming.

2. Unauthorized personnel have notJ.* modified the segrega'ics or use requirements on tags.

3. Activities have not been conducted that violate requirements specified on tags or in this procetre.

15.2.4 All nonconforming items shall be reviewed for accertance (use-as-is),

rejection (scrap, salvage, or return-to-vendor), repair, or re.ork in accordance with the appropriate departrent procedures. Repaire:

- and rework.1 items shall be re-inspected for acceptability using the original or equivalent criteria. All rework or repair shall be performed using approved procedures. All dispositions of nonecrforming items shall be properly documented.

15.2.4a. The Nuclear Engineering and Nuclear Operations Departments, as appropriate, are responsible for the evaluation and disposition of identified nonconformances. The Nuclear Rev: 7 11-15-2 Date: 7/20/E?

Engine: ring Department must cpprovo "acesot" or " repair" dispositions; and the Quality Assurance Department must approve " accept" or " repair" dispositions which affect the quality assurance requirements associated with the nonconforming item.

15.2.4b. The Quality Assurance Department is responsible for assuring dispositions are implemented, inspecting for acceptability of rework and repair actions, maintaining a file of closed NCR's, and for periodic auditing of the Nonconformance Report Syste~ to assure compliance.

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Rev: '

tt-\5-3 Date 7/20/S3

i CORRECTIVE ACTION I

16.1 PURPOSE This section establishes the requirements to be met by the Boston Edison Company to identify, document, and correct items or conditions adverse to quality and to ensure these items or conditions are evaluated to determine causes ano appr op r i a te action is taken to prevent recurrence.

Cond i t i o n s adverse to quality include faalures, malfunctions, deficiencies, defective material and equipment, abnormal occurrences, and nonconformances.

In addition, the corrective action program ensures that the Pilgrim Nuclear Power Station operates in a safe and reliabl manner, minimizes down-time, and optimizes the use of '

able resources by providing for a team effort in reso roblems. The preventive action portion of the prograq frequency an vides a cost- effective way of reducing the rity of problems.

l 16.2 REQUIREMENTS 7 16.2.1 All Nuclear Org ation personnel shall perforrn their normal acti h e in a manner which will avoid or minimize q -related problems by adhering to approved work methods. *** ures, instructions, and 16.2.2 Each Vice President, Manager, o *girector responsible for the effective mentatiori of f

the BECo corrective action progr%@g tnin their Department. f4. ,

16.2.2a. Each Department shall continually , assess its operations to assure that mechanisms are in place to identify aeviations from specifiec r equiremen t s or conditions adverse to quality which might result in potential problems.

16.2.2b. Each Manager, Assistant or Deputy Manager,

• Group Leader, or Supervisor will ensure that all af f ectea personnel within the Depart-ment / Group are fully aware of the corre c t i v e action program and of the Department implementing procedures. When necessary, personnel shall be trained (or retrained) in proper procedures and work l methods. i l

11-16-1 Rev: 12 Date:

! 7/2:/53

16.2.3 It is tha rcsponsibility of all Nuclocr Organizcticn personnel to make sure that any incipient, suspected, or actual conditions adverse to quality, such as failures, malfunctions, deficiencies, defective material and equipment, and nonconformances is promptly identified and properly documented.

16.2.3a. All identified itens or conditions adverse to quality will be docunented and reported in accordance with the appropriate procedures.

16.2.3b. All Technical Specification or FSAR deviations shall be pronptly evaluated and reported to the NRC, as appropriate, in accordance with Department procedures.

16.2.3c. The Nuclear Safety Review and Audit Connittee (NSRAC) shall review reported f* . conditions adverse to cuality as required

(* JN(** by the PNPS Technical Specification.

16.2.4 All iden Ik ' d conditions adverse to quality shall be corrected

• eported to appropriate levels of management. p 16.2.4a. Each r is responsible for taking prorpt and effe She corrective action to satisfactorily resolve ad% j ems or conditions adverse to quality discovered V or assigned for action to the Department. /\

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16.2.4b. Items or conditions noted during normal in-process or activit review prior to final are considered part of ap(agoval of a document ggt, process and not subject to the reporting requirements (,ppntained herein.

16.2.4c. Corrective action (s) in resp [ (,to reported problems will be provided in writing. Provisiens for review and approval will be incorporated.

16.2.4d. Logs shall be maintained by each Department to sufficiently identify conditions and the corrective action (s) taken.

16.2.4e. Appropriate reports of status will be submitted to the cognizant Managers and Vice 11-16-2 Rev: 12 Date: 7/2:/E3

Precid;nto on G rcgulcr Cnd timely b;cio.

In any case, this interval will not exceed six months. ,

16.2.5 All resolved items or conditions will be further evaluated to identify cause(s) and determine appropriate preventive action (s).

16.2.5a. For those iters or conditions adverse to quality deemed significant during the evaluation process, immediate action will be taken to determine the cause(c) and appropriate preventive action (s).

16.2.5b. The term "significant" applies to a condition adverse to quality which warrants further evaluation for cause(s) and requires management attention / action because it represents:

e a breakdown in any portion of the Quality f 7, Assurance Program conducted in accordance gr* a with the requirements of Appendix B to 10CFR50; ef(}

4. a deficioney in design such that the design

.%*)does not conform to the criteria and bases

/ ted in the final safety analysis report; e dahrtoastructure, system, or component which*gv' 1 require extensive evaluation, extens design, or extensive repair to meet th p ria and bases stated in the final saf y.4nalysis report, or to otherwise establish the adequacy of the structure, system, or component to perLorn its intended safety function;

{=O a deviation from per % ce specifications or e

design drawings which vdn trpquire extensive evaluation, extensive rede8Ign, or extensive repair to establish the adequacy of structure, system, or component to meet the criteria and bases stated in the final safety analysis report or to otherwise establish the adequacy of the structure, system, or component to perform its intended safety function; II-16-3 Rev: 12 Date: 7/2:/E3 i

e the failure or malfunction of, or ute of nonconforning material in a structure, system, or component which will require extensive evaluation, extensive redesign, or extensive repair to establish the adequacy of a structure, system, or component to meet the criteria and bases stated in the safety analysis report or to otherwise establish the adequacy of the structure, system, or component to perform its intended safety function.

e the repetitive recurrence of a deficiency not covered by the items above.

16.2.5c. The recommendations for preventive action will be forwarded via a Corrective Action Request /

Plan (CAR /P), Exhibit II-16-1, to the responsible Department Manager.

For those items or conditions not deemed significant

! during the evaluation, periodic trend analysis l

([)illbeperformedtoidentifyadversetrendsor urring problems. Problems identified will be f

ated for cause (s) and recommended preventive a gg(s) transnitted via a CAR /P.

16.2.5e. Corpod p' policy requires that a significant conditidA verse to quality is promptly reported to the ap ate higher levels of BECo management with a desc g#tn of the condition, the cause of the condition,*Whd the corrective action taken or l P l anned to prevent recurrence.

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II-16-4 Rev: 12 Date: 7/20/E3

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l CORRECTIVE ACTIEN REEUEST/ PLAN TO:

SUBJECT:

REFERENCE (5):(ATTACH IF NECESSARY)

CORRECTIVE ACTION REQUESTED:(ULE ADDITIONAL PAGES IF NECESSARY)

PREPARED BY; DATE RESPONSE REQUEST y GATE:

P .' DATE REVIEWED BY; ' e' DATE APPROVED BY:

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I APPROVED BY: DATE l REVI WED BY: DATE EXHIBIT 11-6-1 Rev: 1.'

l DaTe: 7/20/63

(QA2-A19)

QUALIIT ASSURANCE RECORDS 17.1 PURPOSE This section establishes requirements for collection, storage, maintenance, retentio:

and retrievability of Quality Assurance Records associated with the operation of PNP.

17.2 GENERAL REQUIREMENTS The Boston Edison Company program for control of quality assurance records provides methods to assure proper receipt and acceptance, classification and identification, protection from loss or damage, replacement when obsolete and retrievability.

Records are maintained to provide documentary evidence of the quality of quality related items and activities. Requirements and responsibilities for completion of work are consistent with applicable codes, standards, and procurement documents.

Types of quality assurance records are identified utilizing the guidance of Regulatory Guide 1.88; however, it is recognized that the nomenclature of actual records may vary. The record type most nearly describing the record in question will be 11 owed in determining the retention period.

17.3 RECORD s' M RATION 17.3.1 Cen artn of Quality Assurance Records - Applicable design specifica-tions,igsfg4y,rement documents, test procedures, operations procedures, any othef $6c) gents specify the quality assurance records to be generated by, supplie #t r held for BECo. All such quality assurance records are reviewed e that they are legible, completely filled out and adequately identi e to the item involved.

17.3.2 Identification - Quarik urance records provide sufficient information to permit identification g p*e record with the item or activity to whi h f,t applies. ...

17.3.3 Index - The quality assurance records are listed in an index. The index contains, as a minimum, record rete {hn times, where the records are stored, and the location of the recoTt!s,.Vithin the storage area.

v' g 17.3.4 Classification - Quality assurance recordsdrreg classified as "Lif e-time" or "Sonpermanent" according to ANSI N45.2.9-1/fC.

17.3.4.1 Lifetime quality assurance records are to be maintained for the life of the particular item while it is installed in the plant or stored for future use. Lifetime records are those which meet one or more of the following criteria:

! (a) Those which would be of significant value in demonstrating capability for safe operation.

l (b) Those which would be of significant value in maintaining, reworking, repairing, replacing, or modifying the item.

(c) Those which would be of significant value in determining the cause of an accident or malfunction of an item.

(d) Those which provide required baseline data for inservice inspection.

Rev: 7 11-17-1 Date: 7/22/63

(QA2-A20)  ;

l 17.3.4.2 Nonpermanent records are required to show evidence that an activity was performed according to the I applicable requirements but need not be retained for the life of the ites. Nonpermanent records are those which meet none of the above criteria:

17.3.5 Supplemental Information to Quality Assurance Records - Quality ,

assurance records are corrected or supplemented according t<>

procedures which provide for appropriate review or approval by the originating organization. The correction or supplement includes the date and identification of the person authorized to issue such corrections or supplements.

17.3.6 Retention of Records i

17.3.6.1 Quality assurance records retention complies with ANSI N45.2.9 recommended minimum retention period

(.* . requirements.

m!p3.6.2 For records generated - before commercial operation, the retention period began on the date of commercial O.4. nperation, December, 1972. For. records generated on

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I e tems installed after commercial operation, the ntion period begins on the date upon which satis-operation of the item, as part of a system, has n demonstrated. For periodic maintenance, inspe

, and test records, such as calibration records, ated after the date of commercial operation, g,T etention time begins on the date of their generat%pn. When a record 'is generated as a result of an operations activity, the classification of those records. will hg the same as those types of records generated du di the initial construction '

period. .

17.3.6.3 When there is no minimum re eMedretentionperiod records may be dispositioned on#the day following the date the retention period begins. One-year retention is intended to require maintenance of the record for the customary period of warranty. Two-year retention is intended to require maintenance of the record through the first overhaul or next refueling. Six-year retention is intended to achieve compliance with regulatory requirements.

17.4 RECEIPT OF RECORDS

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17.4.1 Timeliness - To assure ' their availability, quality assurance records are turned over to the 30SD Records Management Group l

and processed into the Nuclear Records Management System in a

! timely manner.

5 Rev.. 7 II-17-2 Date: 7/CH_

(QA2-A21)

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17.4.2 Receipt ControI_ - Each department responsible for the receipt of quality assurance. records shall designate a person respon-sible for receiving the records. This responsibility includes organizing and implementing a system of receipt control for quality assurar ce records.

- 17.5 STORAGE, PRESLEVATION AND SAFEKEEPING 17.5.1 Location of Facilities - Quality assurance records are stored in predetermined locations in a manner which meets the require-sents of applicable Standards, Codes and Regulatory Agencies.

17.5.2 Storage - Storage procedures are prepared and custodians are designated. The procedures include the following:

17.5.2.1 A description of the storage area.

17.5.2.2 The filing system used.

/g** 5.2.3 A method to verify the records received match the

• transmittal document, and the records are in good O/ condition.

17.5 2 method to verify the records types agree with the established record checklist.

17.5.2.5 The s, governing access tc and control of files.

17.5.2.6 A metho paintain control of and accountability for recordsNestped from storage.

%e 175 2.7 A rethod to file supplemental information and dispose of superseded records. ,

17 5.3 Preservation -

To preclude deterihi n of the records, the following requirements apply: ,

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17.5.3.1 Condensation -

Storage is in in area where damage from condensation will not occur.

/ 17.5.3.2 Loose Records -

Records are not stored loose. They are firmly attached in binders or placed in folders gr envelopes for storas,e on shelving in containers or in steel file cabinets.

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l , , 17.5.3.3,,be:ial Processed Records -

Special processed re-cords (such as radiographs, photographs, negatives and microfilm) are packaged and stored as recommended

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by the manufacturers of these materials.

, , 17.5.4 Safekeeping - A system is established to preclude the entry of l ,

unauthorized personnel into designated storage areas.

1 s Rev.: 7 11-17-3 Date: 7/20/53

(QA2-A22) 17.5.5 Facility '

17 5.5.1 Permanent and temporary record storage facilities are constructed or located to protect contents from possible destruction by fire, flooding, tornadoes, insects, and rodents and from possible deterioration by variations in temperature and humidity conditions.

17.5.5.2 Records are appropriately classified for fire pro-tection purposes as National Fire Protection Associa-tion Class I and, as such, are afforded the equiva-lent protection of a NFPA Class A, two-hour minimum rated facility with provisions for the proper storage of microfilm and radiographs.

17.6 RETRIEVAL

17. .* . Accessibility nih6.1.1 Storage systems provide for the retrieval of informa-tion without undue delay.

17.6.ieY cess to the record copy files is via the Records gement Group.

17.6.1.3 Qua assurance records maintained by a supplier at hi%

BECo.peility or other location are accessible to 4* ime records for the life of the items involved, n38 gmanent records for the designated retention perfees.

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r Rev.: 7 II-17-4 Date: 7/ :/E3 l

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(QA2-A23)

AUDITS 18s1 PURPOSE This section establishes requriements for an auditing program to verify the implementation and to assess the effectiveness of the Boston Edison Quality Assurance Program.

18.2 PERFORMANCE OF AUDITS 18.2.1 QAD performs internal audits of all quality-related activities associated with operation of PNPS. The frequency intervals are based on the requirements of regulations, Regulatory Guides, and ANSI Standards identified in Paragraphs 2.3.2 and 2.3.4 of Section 2; audits are also done when significant changes or problems arise, and upon management request. A specific scope for each audit is prepared by the QAD before performance of the audit.

18.2.2 When suppliers perform work related to operation, maintenance, 4 41fication and refueling of PNPS,QAD may perform audits at and at the supplier's facilities to verify implementation of, r quality assurance programs as determined necessary 18.2.3 by Q O- /

Audits req 8r by Section 6.0 of PSPS Technical Specifications will be perf under the cognizance of the Nuclear Safety Review and Aud ittee by Quality Assurance Department personnel.

• p 18.2.4 QADperformsaudits/gke' su nce inspections, as necessary,to verify that corrective a opesulting from identified deficiencies have been properly implement!%[and are ef fective.

18.2.5 Audits are performed by qualified per nnel using checklists or marked up written procedures to effe ely evaluate conformance to specified requirements. Auditors 4 not have direct responsibility in the areas being audit &.

18.3 REPORTING OF AUDIT FINDINGS 18.3.1 After reviewing audit findings with the cognizant manager of each organizational unit which has been audited, an aucit report is prepared by QAD.

l 18.3.2 As a minimum, audit reports shall include:

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1. Description of the audit scope.

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2. Identification of the auditors.

3. Persons contacted.

4. Summary of audit results including an evaluation statement of the effectiveness of the QA Program elementc which were audited.

Rev: 8 11-18-1 Date: 7/:0/e3

(QA2-A24)

5. Detcilo cf cudit findings.

6. Recommendations for correcting deficiencies or improving The QA Program, as appropriate.

18.3.3 Audit deficiencies are recorded on a Deficiency Report and are entered into the Deficiency Follow Program to be dispositioned.

18.4 DISPOSITIONING OF AUDIT DEFICIENCIES 18.4.1 Audit deficiencies recorded on Deficiency Reports shall be reviewed by QAD to determine whether a significant (see paragrpah 16.2.5b) condition adverse to quality exists.

18.4.2 A deficiency deemed to be significant is designated "immediate" and corrective action must be initiated promptly by the responsible Manager and appropriate levels of higher management notified.

A response shall be submitted to the QA Manager within one week and a copy of the Deficiency Report and the response shall be forwarded to the appropriate Vice President.

18.4.3 er Deficiency Reports require that a written response be arded to the QA Manager within thirty (30) days.

18.4.4 For ea ency Report, the official start of the time clock for the in on, implementation, and completion of the required corrective a shall be the date of the QA Manager's signature.

18.4.5 in the event that 9m#greetive action cannot be completed by the initial response dud %dagh a schedule date for corrective action completion shalfgp,'nndicated and shall not exceed 90 days from the issue date phy Deficiency Report without first providing the appropriate fiee President with a request for xtension along with written justification and securing his approval.

18.4.6 Should Quality Assurance not concur (ith actual / proposed corrective action,andbeunabletoobtainsatisfafE$ryresolutiondirectly with the responsible Manager, a formal rTq for a second response shallbeforwardedtotheappropriateVicePre[jdent. The Quality Assurance Manager may, if deemed appropriate,dimplement the require-ments of Paragraph 2.5.6 of this Manual.

18.4.7 Upon completion of planned corrective action, the recipient of the Deficiency Report shall provide timely written notice to the QA Manager, stating the actual corrective action (s) taken and the completion date(s) thereof.

,18.4.8 Quality Assurance should verify corrective action within 30 calendar days of the receipt of the notification of completien.

Verification shall also assure effectiveness of corrective action.

Rev: 8 11-18-2 Date: 7/20/53 i

i

(QA2-A25) l 1

18.4.9 For those Deficiency Reports that are issued to suppliers who are I performing on-site safety-related activities in accordance with their approved QA Programs, the process defined in Section 18.4 shall apply. Interface shall be directly with the supplier's site manager with a copy of the Deficiency Report forwarded to the applicable BECo Manager for information only. -

18.4.10 Corrective actions for deficiencies identified during inspections /

audits of suppliers at their facilities are documented and resolved on a Deficiency Report, and the process defined in Section 18.4 is used, were practicable. Interface shall be directly with the supplier's QA manager.

18.4.11 The status of dispositioning audit deficiencies recorded on Deficiency Reports shall be reported periodically to Department Managers and to higher levels of management.

18.5 RECORDS /E EORTS OF AUDITS 18.5.1 4f(eW t records, reports and associated documentation .ertinent to. dits are maintained in the QAD file and the Nuclear Record gement System.

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Rev: 8 11-18-3 Date: 7/20/83