B13530, Rev 13 to QA Program

Rev 13 to QA Program

ML20059L943
Person / Time
Site:	Haddam Neck, Millstone  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/29/1990
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
References
B13530, NUDOCS 9010020222
Download: ML20059L943 (139)

Text

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I NORTHEAST UTILITIES

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O QUALITY ASSURANCE PROGRAM (NUQAP) j g

TOPICAL REPORT TRANSMITTAL FORM i

?o c u mem t control D r: 0 smittal No.:

OSD-90-5232 Wit Jilf.

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Santamber 14. 1990 Washtngion D. f..

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No.

t 41i9 Trom: Director, Quality Services Northeast Utilities Services Co.

Post Office Box 270 Hartford, Ct.

06141-0270

Subject:

NUGAP TOPICAL REPORT REVISION Revision Effective Section Paan(s)

Number Date complete Revision 13 08-29-90 Notice of Recelot of the NUOAP Tonical Reoort/Revison(s) 1 To:

Director, Quality Services (Berlin, NUS-129 Copy Number Northeast Utilities Service Co.

Post Office Box 270 Hartford, Ct.

06141-0270 This acknowledges receipt of the Northeast Utilities Quality Assurance Program (NUQAP) Topical Report / Revision (s) listed in the transmittal letter, QSD-90-5232, dated September 14, 1990.

Signature of Topical Report Holder Date p* nu unik Sk

ABSTRACT NORTHEAST UTILITIES OUALITY,\\SSURANCE PROGRAM (NUOAP) p)

TOPICAL REPORT (t

Northeast Utilities (NU) has developed and is implementing a comprehensive Quality Assurance Program to assure conformance with established regulatory requirements, set i

forth by the Nuclear Regulatory Commission (NRC), and accepted industry standards.

The participants in the NU Quality Assurance Program assure that the design, procure.

ment, construction, testing, operation, maintenance, repair and modification of nuclear power plants are performed in a safe and effective manner.

The NU Quality Assurance Program (NUQAP) Topical Report complies with the requirements set forth in Appendix B, of 10 CFR Part 50, along with applicable sections of the Safety Analysis Report (SAR) for each licensed application, and is responsive to the United States NRC Regulatory Guide 1.70, which describes the information required to be presented in the Quality Assurance Section of the SAR's for nuclear power plants.

The NUQAP is afso established, maintained and executed with regard to Radioactive Material Transport Packages as allowed by 10 CFR 71.101(f). Quality Assurance Provisions for Fire Protection activities are detailed in the Northeast Utilities Fire

,O Protection Program.

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This NUQAP is applicable in its entirety to Category I systems, structures, components, materials, equipment, parts, and services. Appendix A defines Category I systems, structures, and components. The NUQAP is also applicable to other quality programs including Anticipated Transient Without Scram (ATWS) and Environmental Equipment Qualification (EEQ) as dLGned by NU commitments. Portions of the NUQAP are also applicable to Fire Protection Quality Assurance (FPQA) and Radwaste Quality Assurance (RWQA) which are delineated in established procedures.

The NUQAP is committed to uti'-!ze the guidance obtained from the Regulatory documents and their endorsed Staadards as referenced in Appendix D of the Topical Report.

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QAP Abstract Rev.: 13 Date: Aug.29,1990 Page1 of1 i

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I June 4, 1990 Docket Nos. 50-213 50 245 50-336

$0-423 B13530 l

Re:

10CFR50.54 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos.1, 2, and 3 O

Annual Reporting of Changes to the Quality Assurance Program Proposed Revision 13 to the Northeast Utilities Ouality Assurance Procram Tonical Reoort In accordance with 10CFR50.54(a)(3), transmitted herewith is proposed Revi-sion 13 of the Northeast Utilities Quality Assurance Program (NUQAP) Topical Report Proposed changes to the Topical (Attachment B) for your review and approval. Report are indicated The issue and basis for each change are detailed in Attachment A which is arranged in a sequence which coincides with the Topical Report sections.

Attachment A does not include minor editorial changes in accordance with 10CFR50.54(a)(3)(ii),

All changes included in proposed Revision 13 of the NVQAP Topical Report have the effect of upgrading our Quality Assurance Program which continues to meet the criteria of 10CFR50 Appendix B.

Please note that the draft NVQAP Topical Report is shown' as Revision 13 i

l without a date.

This draft will be issued as Revision 13 and dated the same as your effective date of approval when we receive it or sixty days following this submittal as prescribed in 10CFR50.54(a)(3)(iv).

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1 U.S. Nuclear Regulatory Commission B13530/Page 2 June 4, 1990 If you have any questions regarding this submittal, please contact Mr. Donald O. Nordquist at (203) 665 5447.

Very truly yours, NORTHEAST UTILITIES SERVICE COMPANY M

E. J./Mroczka g/

Senior Vice President cc:

T. T. Martin, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No.1 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 A. B. Wang, NRC Project Manager, Haddam Neck Plant W. J. Raymond, Senior Resident inspector, Millstone Unit Nos.1, 2, and 3

.J. T. Shediosky, Senior Resident inspector. Haddam Neck Plant P. K. Espen, Chief, Quality Assurance Section, Region 1 O

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ATTACHMENT A Summay of Proposed Changes to NUQAP Topical Report Revision 12 General

. Various sections of this revision have been changed to reflect the new organizational titles.

OAP 1 Q Paragraph 1.4.2.3b, c Deleted because their activities are not Quality related.

o OAP 2.0 Paragraph 2.2.2 Revised Quality Services Department (QSD) involvement in o

the review and concurrence with quality procedures Appendix C List typical procedces that QSD reviews and concurs with.

OAP 3.0 Paragraph 3.2.2b - Deleted " Environmental." 10CFR50.59 does not address o

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Environmental questions.

OAP 5.0 Paragraph 5.2.1 Revised, QSD lnvolvement in the review and concurrence with o

quality procedures, Appendix C List typical procedures that QSD reviews and concurs with, Paragraph 5.2.2 - Revised to reflect the current.esponsibilities for the review o

and approval of drawings.

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I DAPl '

k Paragraph 7.2.1c 1 eleted Coordinating Agency Supplier evaluation (Case) o which is no longer used. Nuclear Procurement issues Committee (NUPIC) is current.

Paragraph 7.2.5 Revised to reflect current Commercial Grade terminology.

o OAP 15.0 t

Total rewrite to simplify and clarify requirements.

o Specifics removed (covered by implementing procedures).

o Deleted 15.2.2. Incorporated these requirements in other paragraphs.

o Deleted specific references to engineer-constructors, contractors, etc., and o

NUSCO Project organizations in that differences in implementing procedures have been eliminated.

OAP 16.0 f

o Total rewrite to simplify and clarify requirements.

k Recurrence control was better defined. '

o Definitions in Appendix E were added or changed in conjunction with this o

clarification.

Deleted specific references to engineer-constructors, contractors, etc., and o

NUSCO Project organizations in that differences in implementing procedures have been eliminated.

Apoendix A Added Gas Turbine Fuel to reflect this emergency power source at Millstone Unit o

No.1.

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Anoendix C

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o Update procedure List to reflect current revisions within. the various departments.

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Appendir D Deleted Regulatory. Guide 1.74. This was cancelled by the NRC letter dated o

l September 1,1989.

l Expanded the commitment to Regulatory Guide 1.152 to apply to all four units.

o Anoendix E 1

Definitions revised to provide consistency with ANSI definitions and/or NU o

usage.

Anoendir F 1

Added exception to ANSI N45.2.131976 that establishes NU as determining the o

required Post Installation Test requirements and acceptance documentation.

o Added exception to ANSI 45.2.21977 that establishes the Northeast Utilities Quality Service Organization to verify, through Inspections, Receipt Inspections, and Survey activities compliance to ANSI 45.2.21977 requirements.'

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HARTFORo. CONNECTICUT 061410270 L

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(903) e46 8000 June 29, 1990-Docket Nos. 50-213 50-145 i

Re: 10CFR50.54(a)(3) 7 U.i. Eclear Regulatory Commission Attention: Documt tretrol Desk i

Washington, DC 20 H5 Gentlemen:

Haddam Neck Plant

_ _ _... _.;;.m Millstone Nuclear Power. Station, Unit Nos.1, 2, and 3 Amendment to Annual Reporting of Changes to the Quality Assurance Program Proposed Revision 13 to the Northeast Utilities cuality Assurance Procram Tonical Reoort The purpose of this letter is to amend.the proposed : Revision 13 to the' l

Northeast Utilities QualitQssurance Program (NUQAP) Topical Report which was submitted on June 4, 1990.

Revision 12 of the NUQAP T ical Report that was submitted on.May 25,1989(2) and subsequently approved, committed to Regulatory Guide 1.152 for only the' Haddam Neck Plant-in Appendix 0 of the NVQAP Topical Report.

Thgcommitment to this Regulatory Guide is also for Millstone Unit Nos.1,.2, and 3. : This submittal is to amend the proposed Revision 13 of the.NUQAP Topical that was J. Mroczka letter to U.S.

Nuclear Regulatory Commission- " Annual (1)

E.Reporting of Changes to the Quality Assurance-Program Proposed Revision 13 to the Northeast Utilities Quality Assurance Program Topical Report,"

l dated June 4, 1990.

E. J. Mroczka letter to U.S.

Nuclear Regulatory Comission- " Annual.

(2)

)

Reporting of Changes to the Quality Assurance Program Proposed Revision-12 to the Northeast Utilities Quality Assurance Program Topic Report,"

dated May 25, 1989.

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(3)

U.S. Nuclear Regulatory Commission letter to E. J. Mroczka- "10CFR50.54 Quality Assurance Program Description Change Review," dated July 13,

1989, osuu nev.44e 1

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U.S. Nuclear Regulatory Commission l

B13559/Page 2 June 29,1990 submitted for your review and approval on June 4,1990.

It is requested that as part of your you include this change, as reflected in the attachment,This change does not r review of Revision 13.

commitments.

If you have any questions regarding this letter, please contact Mr. Donald O.

Nordquistat(203)655-5447.

Very truly yours, NORTHEAST UTILITIES SERVICE COMPANY

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E.J.MP5Kka

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Senior Vice President Attachment cc:.T. T. Martin, Region-I Administrator

~A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shediosky, Senior Resident Inspector, Haddam Neck Plant O

M. L. Boyle, NRC Project Manager, Millstone Unit No. I G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2,.and 3 L

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1 TABLE OF CONTENTS NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM (NUOAP)

TOPICAL REPORT 1

BRY P.AgfJi Abstract 13 1

-Table of Contents 13 1-2 l

Policy Statement 13 1

Introduction 13 1-2 I

Quality Assurance Program QAP 1.0 Organization 13 1 13 i

. -. __ Organizational Charts _

13.

Fig.1.1 1.7 QAP 2.0 Quality Assurance Program 13 1-7 QAP 3.0 Design Control 13 1-6 QAP.4.0 Procurement Document Control 13 1-3 O.

QAP 5.0 Procedures, Instructions and

- Drawings -

13 1-3 QAP 6.0

- Document Control 13 13 QAP 7.0 Control of Purchased Material, Equipment and Services 13 1-4 QAP 8.0 Identification and Control of Materials, Parts and Components 13 1-2 QAP 9.0 Control of Special Processes 13 1-2 QAP10.0 Inspection 13 14 QAP11.0 Test Control 13 1-3 QAP12.0 Control of Measuring and Testing Equipment 13 1-3 QAP2 3.0' Handling, Storage, and Shipping 13 1-2 QAP14.0 Inspection, Test, and Operating Status 13 1-2 QAP15.0 Nonconforming Materials, Parts, Components, or Senices 13 12 QAP Table of Contents Rev.: 13 Date: Aug.29,1990 Page 1 of 2

5 B.es Pus.s l

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w QAP16.0 Corrective Action 13 12 i-l QAP1A0 Quality Assurance Records 13 12 QAP18.0 Audits 13 13 l

1 Appendices i

A.

Category I Systems, Strictures and Components 13 1-3 B.

Qualification and Experience Requirements, NUSCO Manager, 13 1

Quality Assurance C.

List of Typical Quality Assurance j

Related Procedures 13 1-34 i

D.

Regulatory Guide and ANSI Standard

-Commitments-13-12-E.

Glossary of Quality Assurance Terms 13 1-7 I

i F.

Program Exceptions 13 1-3 O

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O QAP Table of Contents Rev.: 13 Date: Aug.29,1990 Page 2 of 2 i

l POLICY STATEMENT NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT l

The policies, requirements and tasks contained in this No-theast Utilities Quality Assurance Program description have been developed to achieve a recognized need for quality assurance during the design, procurement, construction, testing, operation, l

maintenance, repair, and modification of our nuclear facilities.

l Northeast Utilities procedures which implement this program are described in various l

manuals which are referenced herein.

This NUQAP is applicable in its entirety to Category I systems, structures, componem, materials, equipments, parts, and services. Appendix A defines Category I systems, structures, and components.

Portions of the NUQAP are also applicable to Fire I

Protection Quality Assurance (FPQA) and Radwaste Quality Assurance (RWQA) which are delineated in established procedures, and Anticipated Transient Without Scram Quality Assurance (ATWS Quality Assurance is applicable to MP 1, 2 only; MP 3 commits to Generic Letter 85 06), and Equipment Environmental Qualification as defined bv NU commitments.

The development and overall responsibility for this QuaLy Assurance Program lies with the Senior Vice President - Nuclear Engineering and Operations. Corporate authority is delegated to the. NUSCO Director, Quality Services for the preparation and administration of the Quality Assurance Program. Individual group Vice Presidents are responsible for the implementation of their portion of the Northeast Utilities Quality Assurance Program.

Revisions, additions to, and audits of this program are the responsibility of the NUSCO Director, Quality Services. Any revisions or additions shall be approved by affected Departments prior to the incorporation of such changes into the program. Final approval of revisions or additions to this policy statement rests with the Senior Vice President - Nuclear Engineering and Operations.

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E.J.s1grzk'a

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Senior vice President -

Nuclear Engineering and Operations.

Northeast Utilities QAP Policy Statement Rev.: 13 Date: Aug.29,1990 Page 1 of 1

INTRODUCTION NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM pq TOPICAL REPORT This Northeast Utilities Quality Assurance Program (NUQAP) Topical Report contains the quality assurance requirements which are relevant to the safety of the nuclear power plant. The Topical Report consists of the following three parts:

1.

Introduction, which delineates the purpose of the Topical Program, and summarizes its scope and applicability, j

2.

The NUQAP, which is applicable in its entirety to Category I systems, structures, components, materials, equipments, parts, and services. Appendix A defines Category I systems, structures, and components. Portions of the NUQAP are also applicable to Fire Protection Quality Assurance (FPQA) and Radwaste Quality Assurance (RWQA) programs, and Anticipated Transient Without Scram Quality Assurance (ATWS Quality Assurance is applicable to MP 1,2 only; MP 3 commits to Generic Letter 85-06), and Equipment Environmental Qualification as defm' ed by NU commitments.

3.

Appendices, which provide supporting statements and tabulations.

This NUQAP Topical Report has been prepared to document that a meaningful quality assurance program has been established and implemented to ensure that adequate quality requirements are being complied with to safeguard NU employees, contracted personnel and the public, from the conceptual phase through the operations phase of nuclear power plant life.

The controls which implement the actions identified in the NUQAP Topical Report are departmental procedures and instructions which delineate actions and steps necessary l

to accomplish quality requirements.

Procedures and instructions are written by company groups, divisions, departments, branches, or sections, which have the respon-sibility for implementing actions assigned to them as delineated by the NUQAP. Quality procedures and revisions thereto are reviewed by and concurred with by the NUSCO Quality Services Department in accordance with QAP 2.0 and QAP 5.0.

QAP Introduction l

Rev.: 13 Date: Aug.29,1990 Page 1 of 2

The NUQAP is responsive to applicable codes, Nuclear Regulatory Commission C) regulatory requirements, accepted industrial standards and revisions thereto. Provisions V

are established to update the NUQAP Topical Report in accordance with revisions to codes, standards and regulatory requirements, and to inform cognizant personnel to implement appropriate action to assure the highest standard of quality is achieved for systems, structures, components and services for nuclear power plants.

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Donald O. Nordquist NUSCO Director, Quality Services i

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i s.g QAP Introduction Rev.: 13 Date: Aug.29,1990 l

Page 2 of 2

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1.0 ORGANIZATION

1.1 INTRODUCTION

Northeast Utilities (NU) is a holding company.which owns all of the common stock in several companies as illustrated by Figure 1.1..

i The Connecticut Light and Power Cepany (CL&P) and Western Massachusetts Electric Company (WMECO) are the owners of Millstone Unit Nos. I and 2 with 81% and 19% ownership, respectively. They are the principal owners of Millstone Unit No. 3 with 65% ownership and, by contract have the authority to make all of the decisions affecting the design, procurement, modifications, construction and operation of that unit. This decision making authority would be similar for any future units.

The NU Companies jointly own 44% of the Connecticut Yankee Atomic Power I

Company (CYAPCO). By contract, NU and Northeast Utilities Service Company (NUSCO) have been delegated operational control of CYAPCO. NUSCO provides

_j technical support for the operation of that plant.

l Northeast Nuclear Energy Company (NNECO) and CYAPCO are the operating companies established to operate their respective facilities. NNECO is delegated the responsibility for operating the Millstone Units by the owners. NNECO in turn has contracted for the services of NUSCO for the design and construction management of all of the units at Millstone and may solicit. technical support during plant operations. NNECO and:CYAPCO comprise.the Nuclear Plant Operating Companies (NUPOC) as illustrated in Figure 1.1..

NUSCO, parts of which are organized as shown in Figures 1.2,1.3,1.4, and 1.5 l

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provides services such as engineering, quality assurance, accounting, planning and procurement for the NU system operating companies where these services can be efficiently and economically performed on a systemwide basis.

The NUPOC and NUSCO interrelationship shown in Figure 1.6, for quality activities, indicates how conflicts are resolved. As indicated, the Senior Vice 1

President Nuclear Engineering and Operations NUSCO is also the Senior Vice President Nuclear Engineering and Operations NUPOC. He resolves disputes arising from a difference of opinion between Quality Services personnel and other department personnel.

i QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 13

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t 4 1.2 GENERAL (refer to Figure 1.2)'

1.2.1 The President and Chief Operating Officer of NU is also the President and Chief Operating Officer of NUSCO and directs specified nuclear related activities within NU.-

He has the. ultimate responsibility for the establishment and execution-of the NU Quality Assurance Program (NUQAP). Reporting to the President and Chief Operating Officer is the Executive Vice President Engineering and Operations and the Senior Vice President Administrative Services. Authority for the establishment and execution of the NUQAP is delegated to the SeniorVice President Nuclear l

- Engineering and Operations (see Para 1.2A),

w 1.2.2 The Senior. Vice President Administrative Servihes is responsible for Procurement and Information Resources activities within NU. The Vice President Purchasing and Materials Management reports to the Senior Vice President Administrative Services and is responsible for ensuring that.

procurement requirements of the NUQAP are carried out within' his division (see Para.1.5.1)

The Vice President Information Resources Group operates and maintains j

corporate mainframe computer systems and provides support for quality activities as requested by Nuclear Engineering and Operations / NUPOC 9

personnel (see Para.1.5.2).~

1.2.3 The NUSCO Executive Vice President Engineering and Operations is also the Executive Vice President Engineering and Operations for NUPOC.

Specific nuclear related responsibilities rest with the following individual i

who is responsible for ensuring that the requirements of the NUQAP are carried out, a.

Senior Vice President Nuclear Engineering and Operations (see Para.1.2.4).

1.2.4 The Senior Vice President Nuclear Engineering and Operations is also the Senior Vice President Nuclear Engineering and Operations for NUPOC.

He is responsible for nuclear engineering, construction, operation, mainte-nance, modification and quality assurance.

1.2.4.1 The responsibilities of the Senior Vice President Nuclear Engineering and Operations relating to the - Quality Assurance Program are described in the Nuclear Engineering and Operations Policies and Procedures Manual.

He has contact with the quality assurance activities through the receipt of various d,cuments such as:

a QAP - 1.0 Rev.: 13 Date: Aug.29,1990 l

Page 2 of 13

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Weekly progress reports, Nuclear Review Board Meeting O

Notes and:other reports, and audits related to NUPOC l

V nuclear plant operations activities.

1.2.4.2-The Senior. Vice President Nuclear Engineering and_

Operations is responsible. to assess the scope, status, i

implementation and effectiveness of the NUQAP. To meet this responsibility, he appoints a qualified team of individuals to perform an annual Management Quality Assurance Review.

This Management Quality Assurance Review is:

1 a.

A systematic evaluation;--

b.

Preplanned toward the objective of determining the adequacy of the NUQAP and its compliance with Appendix B to 10 CFR Part 50 and other regulatory

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requirements; Capable ofidentifying, communicating and tracking c.

any required corrective action.

The team is made up of individuals knowledgeable in quality assurance, quality, activities, auditing, management responsibilities, and the -NUQAP-Topical Report.

1.2.4.3 The following division Vice Presidents report to the Senior Vice President Nuclear Engineering and Operations:

i a.

Vice President Generation Engineering and Construction (see Para.1.4.1)-

b.

-Vice' President Nuclear, and Environmental Engineering (see Para.1.4.2.)

c.

Vice President Nuclear Operations (see Para.1.4.3) 1.3 RESPONSIBHJTIES (Refer to Figure 1.6) 1.3.1 Overall responsibility for the NUQAP is assigned to the NUSCO Director, Quality Services who reports to the Vice President Nuclear and Environmental Engineering. These responsibilities include: directions of QAP 1.0 Rev.: 13 L

Date: Aug.29,1990 Page 3 of 13 o

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the Quality Assurance Program;. implementation of policies, plans, j]

requirements, procedures, and audits; verification to' assure compliance

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Q with-10 CFR 50 Appendix B and other regulatory requirements; and verification of-the implementation. of the NUQAP Topical Report Requirements.

1.3.2 Overall responsibility for the implementation of the NUQAP Topical Report at the NUPOC Nuclear Plant is assigned'to a NUPOC Director.

1.3.3 The head of each NU departtr:nt or organization performing. quality activities is responsible for:

j Administering those activities within his organization which are a.

defined by the NUQAP Topical Report; b.

Ensuring implementation of the Quality Assurance Program; Establishing and clearly defining the duties and responsibilities of c.

._-_..__.-personnel within his organization who perform quality activities; d.

Planning, selecting, ' and training personnel. to meet the requirements of the NUQAP Topical Report;-

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Performing and coordinating quality matters within his department and interfacing with NUSCO Quality Services on quality activities.

1.3.4 Each individual, performing or verifying activities.affecting quality, is responsible to conduct those activities in accordance with the requirements of the NUQAP and implementing procedures.

1.3.5 The responsibility, authority, and organizational relationship for.

performing quality activities within each organization is established and delineated in the NU Organizational Charts, jurisdictional statements, and written job or functional descriptions.

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1.4 NU PARTICIPATING GROUPS - NUSCO' NUCLEAR ENGINEERING AND OPERATIONS GROUP The Senior Vice President Nuclear Engineering-and Operations Group is responsible for providing and directing projects and for providing technical and support personnel to meet responsibilities during engineering, construction,-

maintenance, testing, modification and operation of nuclear power plants.

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L QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 4 of 13 w

The Nuclear Engineering and Operations Group is divided into three divisions:

a.

Generation Engineering and Construction (Figure 1.3);

b.

Nuclear and Environmental Engineering (Figure 1.4); and c.

Nuclear Operations (Figure 1.5)

In addition to the three divisions,.there is the Nuclear Safety Concerns and Generation Facilities Licensing groups.

The functions of-the personnel, who perform quality activities within these divisions and groups, are as follows:

l 1.4.1 The Vice President Generation. Engineering and Construction is.

responsible for engineering and design, and modification, backfit, and Generation Construction projects for existing NU generating facilities.

The following department heads report to him: (See Figure 1.3) 1

[.k The Director Generation Engineering and Design Department is responsible to provide technical and support personnel to. provide Project Engineers and support-for Generation Construction projects in Generation Facilities a

directed by the Generation Projects Department. Technical support is also_ provided for operations and. maintenance activities of generating. facilities.-

.The-Generation Engineering and Design Department provides expertise for

-systems, specifications and procurement of_ equipment and j

material; it provides design expertise for the preparation

- I and maintenance of de% documents for generating q

facilities.

These generai.an Engineering and Design-Department activities are performed by personnel.within the following department branches:

a.

Mechanical Engineering;_

b.

Electrical Engineering; c.

Civil Engineering; d.

Engineering Design.

O QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 5 of 13 I

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i 1.4.1.2 The Superintendent-Generation Construction Department is I

responsible for the following areas in generation facility

.V projects: 1) the direction and coordination of processes and assurance of necessary resources for construction: and

2) coordination of start up activities with NUPOC. When assigned projects, the department is responsible for 1

providing construction management for construction work i

on the generation facilities.

J 1.4.1.3 The Manager Generation Projects Department is responsible l

for providing the program management and coordination of capital and expense type projects undertaken to improve the safety and reliability of NU's operating nuclear facilities.

The department also provides cost and schedule control of projects, project estimates, and cost engineering and outage planning and scheduling. -

H 1.4.1,4 The Superintendent, Generation. Test. Services, is

.a..-

responsible.for Quality production test activities which include:

a.

Providing electrical testing services to the Nuclear py Plant Operating Companies (NUPOC).

b.

Planning and coordinating periodic and corrective maintenance of electrical equipment.

c.

Conducting acceptance-tests, calibrations, adjustments, functional.chackout, and commissioning of electrical systems, i

d.

Overseeing electrical preoperational testing for nuclear generation facilities projects and start up testing for backfit/ Generation Construction projects, as requested.

1.4.2 Tne Vice President Nuclear and Environmental Engineering is responsible for Nuclear Engineering and Operations Services (including Reilability Engineering, Generation Facilitiep Records, ' Nuclear Materials and Chemistry, and Nuclear Safety Engineering); Environmental Programs;.

Quality Services; Nuclear Engineering -(including:

Radiological Assessment, Reactor Engineering, and Nuclear Fuel); and Nuclear l

Training.

The following department Directors report to the Vice President-Nuclear and Environmental Engineering (see Figure 1.4):

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QAP - 1.0 t

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-i 1.4.2.1 The Director Nuclear Engineering and Operations Services 1

is responsible to. direct and coordinate the support services as required for NUSCO / NUPOC Departments during the -

design, modification, maintenance, construction, and operation of nuclear power plants. He has reporting to him the following managers /

1 a.

Manager, Generation Facilities Rewrds is responsible to provide guidance by the establishment of a:

corporate Nuclear Plant Records. Program and i

Manual for the effective operation of all Northeast k

Utilities Nuclear Plant Records Facilities to meet l

corporate nuclear records objectives.

i b.

Manager, Reliability Engineering is responsible to.

establish and implement specific programs that are intended to monitor and improve the reliability or capacity of the generating facilities.

c.

Manager, Nuclear Materials and Chemistry 'is responsible to provide evaluations of nuclear plant coolant chemistry and materials and to recommend -

controls in accordance with the Nuclear Plant Water Chemistry Program.

1.4.2.2 The NUSCO Director, Quality Services is responsible for 6 preparation and issuance of the NUQAP-TopicaliReport, i

and verification of the implementation of its requirements 1

by the applicable NUSCO / NUPOC Departments. Verifica-tion is performed by a : planned, program = of audits,-

surveillance, inspection, and in-process verifications by'the Quality Services Sections. He provides management with-objective evidence of the performance of activities affecting quality, independent of the individual or group directly responsible for performing the specific activity._-

He has the authority and organizational freedom to assure all necessary quality affecting activities are performed and is independent of undue influences and responsibilities for schedules and costs.

He has.the responsibility and authority, delineated in writing, to stop unsatisfactory work and control further processing, delivery, or installation of nonconforming materials.. He also has the responsibility and authority to identify quality problems, to provide QAP - 1.0 Rev.: 13 Date: Aug.29,1990-'

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solutions, and to verify theh implementation. He maintains -

an overview of NUPOC quality assurance activities through-a planned and systematic program of audits, surveillances, i

and in process verifications.

The following Managers and Supervisors rcport directly to the NUSCO Director, Quality Services (See Figure 1.6).

a.

The Manager, Procurrment Quality Services assures '

y that quality assurance responsibil!'.!es, as they relate 1

to procurement activities - for the NU Nuclear j

Generating Facilities, are being implemented, b.

The Manager, Plant Quality Services assures that-qtGBy assurance activities associated with the -

costruaion, modification, operation, maintenance ed refualing of the NU Nuclear Generating i

FkriRties are being implemented.

c.

The Supervisor, Assessment Services assures that quality assurance responsibilities, as they relate to the operatior al phases and Generation Construction O

a projects of NU Nuclear Generating Facilities are 4

being implemented.

1 d.

The Supervisor, Assessment and Staff Services

]

assur,es that quality assurance activities, as they relate to the design, modification and operations of the NU Nuclear Generating Facilities are being implemented.

These managers / supervisors have positions which are free from non-Quality Assurance; duties and.can give full attention to assure that the Quality Assurance Program is being - effectively -implemented and have appropriate

. organizational responsibilities and authority to exercise l

proper control over the Quality Assurance Program. They have the responsibility. and authority to identify quality problems, to provide solutions, and to verify their imple-mentation. - Stop Work Orders initiated by NUSCO Quality Service personnel are delineated in writing with the concurrence of a

NUSCO Quality Services Manager / Supervisor.

QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 8 of 13

The responsibilities and duties of all NUSCO - Quality Services personnel are described in NUSCO implementing procedures and job descriptions.

The Quality Services Department Personnel routinely attend and participate in daily plant work schedules and status meetings to assure they are kept aware of day to-day work -

assignments throughout the plant. This also assures that there is adequate Quality Service coverage relative to-i procedural and inspection control, acceptance criteria, and Quality Services staffing and qualification of personnel to.

i carry out Quality Services assignments for quality activities, 1.4.2.3 The Director Environmental Programs is responsible for the planning, design, coordination and supervisien of all scientific / engineering ~ studies of problems related to

- environmentalimpacts of NU activities affecting proposed and operating generation facilities. He has,' reporting _ to him, the following Manager:

a.

- Manager, Environmental Services is responsible for.

the preparation of atmospheric dispersion calculations required to estimate dose to the public from both autine releases and postulated accidents.

He provides criteria and studies to assure that such calculations reflect state of the art techniques and -

adequately. support the corporate program for Nuclear Emergency Preparedness.

1.4.2.4 The Director Nuclear Engineering is responsible to direct i

and coordinate the activities of Radiological Assessment, Reactor Engineering and Nuclear Fuel.

The ' following managers report to the Director Nuclear Engineering:

a.

Manager Radiological Ar.sessment is responsible to provide technical services in radiological matters relating to nuclear plant design, operation and Generation Construction projects. It includes'the studies of radiation exposure to plant personnel and the general public, liaison with regulatory agencies, j

and responsibility for. the corporate program for Nuclear Emergency Preparedness.

O QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 9 of 13 m

b.

The System Manager Reactor. Engineering is b

(

respon@'e to provide reactor engineering, NSSS safety ancvsis, probabilistic risk assessments, fuel i

4 design, and reactor core analysis and performance evaluation services for Generation Construction projects and operations of nuclear generation j

facilities. This includes services during reload of nuclear reactor cores, direction for optimal opera.

tions of reactor cores, evaluation of design and analysis of reactors, and NSSS transient evaluations.

l L

c.

Manager Nuclear Fuel is responsible for the planning, scheduling and coordination of the nuclear t

fuel supply requirements for operating. nuclear generation facilities.

This includes. contract engineering for technical administration-of fuel contracts and technical support for the procurement of all-elerr. ants of the nuclear fuel cycle, the handling of fuel removed from operating facilities,,

...._.--.w._..

and determination of nuclear fuel costs.

1.4.2.5 Director Nuclear Training is responsible for Nuclear Training and Training Evaluation activities. The following q

managers report to the Director Nuclear Training:

a.

Manager Operator Training is responsible for 1

providing initial and requalification. training

- i D

programs for Nuclear Plant Operators.

b.

Manager Technical Trai ting is responsible for providing technical training in ' areas such as:

I Electrical and Mrchanical Maintenance, 1

Instrumentation and Control, Health Physics, and-

.i Chemistry.

c.

Manager-General Nuclear Training is responsible for providing training in areas such as: Radiation Work,_

)

Emergency Plan, General Employee, Plant Systems, ALARA, New Employee, Fire Brigade, and Technical -

Support Staff.

d.

Manager Simulator Technical Support is responsible for ensuring the quality of the computer controls for the nuclear plant simulators.

QAP - 1.0 Rev.: 13 Date: Aug.29,1990 Page 10 of 13 v

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1.4.3 The Vice President Nuclear Operations is responsible for plant G

modifications, refueling, maintenance and operation of operating nuclear generation facilities. The division consists of a Nuclear Operations--

Engineering staff and the NUPOC organizations (see Figure 1.5).

1.4.3.1 The Supervisor-Nuclear Operations is responsible for the-coordination of activities between the NUSCO Engineering l

personnel ~ and the NUPOC personnel.

Engineers are' j

assigned to perform the coordination of the activities for i

NUPOC operating nuclear generating facilities.'

i 1.4.3.2 NUPOC Nuclear Station Directors (Millstone and Connecticut Yankee) are responsible for the operation, maintenance, plant modifications, refueling and services of operating generation facilities, a.

NUPOC Station, Site, and Nuclear Services Directors ~

j (Millstone and Connecticut Yankee) report to the individual Nuclear Station Directors and - are responsible for the service functions of each station.

o (See Figure 1.6 A & B.)

j These functions include:

o Building Services o

Chemistry o

Computer Services (Millstone only) o Health Facility o

Health Physics o

Nuclear Records o-Radioactive Materials Handling o

Security o-Stores b.

NUPOC Nuclear-Unit Directors (Millstone and

' Connecticut Yankee) report to the individual Nuclear -

1 Station Directors and are responsible for the -

operation, maintenance, plant modifications, and-refueling of their respective generating facilities, j

The following functions report to each Nuclear Unit Director: (See Figures 1.6A and 1.6B.)

o Operations o

Engineering QAP 1.0 Rev.: 13 Date: Aug.29,1990 Page 11 of 13

o Instrumentation and Controls

{

o Maintenance QJ -

1.4.4 Manager-Generation Facilities Licensing is responsible for corporate liaison with the Nuclear Regulatory Commission and coordi.tation of f

responses to regulatory requirements for changes to operating ncilities.

This includes the preparation and coordination of ' documents for submittal to various regulatory agencies.

1 1.4.5 _ The Director, Nuclear Safety Concerns Program, is responsible hr the development and administration of NU's program implemented to e'isure that nuclear safety concerns receive appropriate management attention and that all such concerns are addressed in a timely manner.

.i 1.5 OTHER NU PARTICIPATING GROUPS Nuclear Engineering and Operations /NUPOC may request the services of these-M1 Participating Groups as necessary to support quality activities under Nuclear Engineering und Operation /NUPOC's' jurisdiction.

1.5.1 PURCHASING AND MATERIALS MANAGEMENT

(

The Vice President Purchasing and Materials Management is responsible to the Senior Vice President Administrative Services;for procurement activities within NU. Reporting to the Vice President Purchasing and Materials Management, are several Purchasing Directors"and. Managers responsible for:

The procurement of materials and services from qtglified suppliers a.

in accordance with predetermined commercial... technical, and quality requirements; b.

Issuing Purchase Orders / Contracts and' changes thereto; c.

Maintaining traceability of. purchasing records from NUSCO / NUPOC; l

)

d.

Processing of purchase requisitions through the preparation of-payment for the purchased item.

l L

The Vice President Purchasing and Materials Management. controls purchasing procedures.

1 O

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- QAP ' 1.0 Rev.: 13 Date: Aug.29,1990 Page 12 of 13-

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1 1.5.2 INFORMATION RESOURCES GROUP (See Figure 1.7)

. n The Vice President Information Resources Group operates and maintains corporate mainframe compv"

. ems and provides support for quality activities as requested by Nuclear Engineering ard Op-ations/NUPOC personnel Reporting to the Vice President-Information Resources Group are:-

- l a..

The Director Information Resources Systems Development.

t -

b.

The Director Information Resources Operations and Technical 4

Support.

3 The Manager Information Resources Planning and Control.

c.

d.

The Director Information Resources Administration.

e.

The Director Communication Systems.

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QAP - 1.0 Rev.: 13 Date: Aug.29,1990

- Page 13 of 13

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2.0 OUAUTY ASSURANCE PROGRAM j

2.1 GENERAL REOUIREMENTS Northeast Utilities (NU) has established a Quality Assurance Program (NUQAP)

)

which complies with the criteria of 10 CFR 50, Appendix B, and follows the guidance referred to in Appendix D of this report. The quality assurance I

requirementa set forth herein and the attached Policy Statement, supplemented by the Quality Assurance Procedures, provide the primary basis of the Program l

and the NU Policy with regard to quality assurance. This prcgram is established for each plant site in a manner intended to accompHsh the required level of quality and is carried out throughout the life of nuclear power plants. It i

includes quality acth'ities during - the operation, maintenance, testing, and modification of the in service nuclear power plants.

The requircraents of the NUQAP apply, as a minimurn, to nuclear safety related systems, structures and components as functionally identified in Appendix A,

" Systems, Structures and Components" and other items or services which are -

1 specifically identified in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide 1.70.

F The requirements of the Program are implemented by Northeast Utilities Service i

Company (NUSCO), Nuclear Plant Operating Companies (NUPOC), engineer constructors, contractors, suppliers and engineering service organizatio'as performing activities affecting quality systems, structures and component., of nuclear power plants.

Procedures define the required'indoctnnation 'and training of personnel performins, activities affecting quality, as necessary, to assure that suitable proficiency is achieved and maintained.

l Training sessions are documented, the content described, who attended, when they attended and the results of the training sessions.

A periodic program review of the status and adequacy of the NUQAP is accomplished by NUSCO Quality Services audits, surveillances, inspections, and in process verifications by Nuclear Review Board (NRB) Reviews, and by the independent audit team described herein and in QAP 1.0, Section 1.2A.2.

Organizations outside NU are required to review the status and adequacy of that part of the Quality Assurance Program for which they have designated responsibility.

L

(

QAP 2.0 Rev.: 13 Date: Aug.29,1990 i

l Page 1 of 7 1

n 1

2.2 IMPLEMENTAT1QH 2.2.1 GOALS AND OBJECTIVES As stated in the Policy Statement of NU, the goals of the NUQAP are to maintain quality levels in an effective and efficient manner and to assure a high degree of functional integdty and reliability of yaality systems, structures and components. To meet this goal, the following objectives of the NUQAP have been defined:

Define through documented procedures, the quality activities that a.

apply to the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of nuclear power plants; b.

Establish, assign and document the respon:ibilities for the conduct of those activities affecting quality systems, structures and components; c.

Establish confidence that (a) the design, fabrication, construction and operat!on of nuclear power generation faci!! ties are performed in a manner consistent with NU Policies and (b) quality activities are performed by responsible personnel, and are verified through a system of audits, surveillances, inspections, and in process verifications of those organizations with quality responsibilities; d.

Appraise the Senior Vice President, Nuclear Engineering and Operations of unresolved problems and trends which could have a significant effect on nuclear power plant safetyyd; c.

Prevent schedule delays and high cost due to poor quality.

l i

2.2.2 PROGRAM DOCUMENTATION This NUQAP Topical Report defines the NU vuclear policies, goals and objectives, and is used as guidance for the development of the various implementing divisional, departmental, branch, or section procedures.

Revisions to the NUQAP Topical Report will be made as needed to reflect current requirements and desedptions of activities prior to implemen:ation. These revisions will be made in accordance with a Nuclear Engineering and Operations Group Procedure.

O QAP 2.0 Rev.: 13 Date: Aug.29,1990 page 2 of 7 w

7 _

Revisions to the NUQAP Topical Report, which reduce commitments

(]

previously accepted by the MC, are submitted to the NRC for review and V

approval prior to implementation.

Revisions which do not reduce previously accepted commitments are periodically sabmitted to the NRC as required by 10CFR50.54(a)(3) and 10 CFR 50.55 (f)(3).

Quality procedures are developed by the departments performing quality activities.

These procedures are reviewed by the depanments which are responsible for portions of these procedures. These procedures are approved by the departments which initiate these procedures.

The NUSCO Quality Services Department reviews and concurs with Quality Procedures such as those listed in Appendix C for compliance with the NUQAP Topical Report. Changes to procedures are subjected to the same degree of control as that utilized in the preparation of the original document.

Each NUSCO Department Head / NUPOC Nuclear Station and Unit Director is responsible for implementation of the NUQAP, which includes individual departmental procedure requirements applicable only to his O

respective activities. In addition, he is responsible for the preparation, approval and distribution of those instructions, operating procedures, testing procedures or other instructions where further guidance is necessary.

2.2.3 ENSTEMS. STRUCTURES. AND COMPONENTS l

The requiiements of the NUQAP Topical Report shall apply, as a minimum, to all activitles affecting the safety functions of the systems, structures, and components, as addressed in the Safety Analysis Reports (SARs). Safety systems, structures and components are functionally identified in Appendix A of the NUQAP Topical Report and also as specifically identified in each FSAR c:ldressing Section 3.2.1 of NRC Regulatory Guide 1.70.

For systems, components, and structures covered by the ASME Code, NUSCO / NUPOC Procedures describe the measures taken to assure that the quality asr.unce requirements contained in the codd are supplemented by dw pecific guidance of the applicable regulatory guides listed in Appendix D of this Topical Report.

l*

QAP 2.0 6

Rev.: 13 Date: Aug.29,1990 Page 3 of 7

1 i

For systems, components and structures, Regulatory Commitments and i

O NUSCO / NUPOC procedures describe tt measures taken to assure that I

the quality assurance requirements are mt.

The degree of control over aethities affecting quality systems, structurca q

and components is consistent with their importance to safety. Such I

controls include use of appropriate equipment, establishment of suitable environmental conditions and assurance that all prerequisites for a given activity have been satisfied.

This NUQAP Topical Report provides controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test.

NUSCO Quality Services Department and applicable NUSCO / NUPCC i

technical organizations jointly determine and identify the extent quality assurance controls are to be applied to quality stmetures systems and components. The quality assurance controls are in conformance with this NUQAP Topical Report, which complies with the 18 criteria set forth in Appendix B, to 10CFR Part 50.

2.2.4 PARTICIPATING ORGANIZATIONJ The NU organizations with responsibilities for activities affecting quality O

systems, structures and components are identified in QAP 1.0, which also V

bdefly describes their assigned responsibilities.

t NUSCO Quality Services is responsible for:

a) the development, coordination, and control of the NUQAP including coordination of i

NUSCO Quality Services Department Procedure review and approval; b) control and issuance of the NUQAP Topical Report as a controlled document (as described in QAP 6.0) and; c) review and concurrence with quality assurance procedures and revisions written by other departments.

Procedure reviews will be performed in accordance with QAP 5.0.

NU requires that their engineer-constmetors, contractors, suppliers, engineering service organizations invoke upon their subcontractors, via procurement documents, requirements for a quality assurance program to meet the applicable criteria of Appendix B to 10 CFR, Part 50, including the applicable elements of the Regulatory Guides and their endorsed Standards identified in Appendix D of the Topical Report. However, NU retains overall responsibility for the QA Program. The specific quality.

activities performed by these organizations are specified-in the procurement documents. NUSCO Quality Services reviews and approves tliese organizations quality assurance programs prior to initiation of s

contracted activities, and performs audits, surveillances, inspections, and QAP 2.0 Rev.: 13 Date: Aug.29,1990 Page 4 of 7

-m..

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1 in. process verification on subsequent activities for compilance to their procedures.

The object of the review is to verify that the engincedng-constructors,

)

contractors, suppliers and engineering service organizations have an adequate quality assurance program to meet applicable requirements of Appendix B, to 10 CFR, Part 50.

In addition to the initial review, the engineer-constructor, contractors, supplien and engineering service organizations' quality assurance programs shall be periodically audited by NUSCO Quality Services to assure continued implementation of quality requirements.

l Contractors may be delegated the execution of quality assurance functions.

by contract. These contracts are reviewed and approved in accordance j

with NUQAP requirements.

2.2.5 INDOCTRINATION AND TRAINING A

oha~m is established and maintained for quality assurance indoctrination and training which provides confidence that the required level of personnel competence and skill is achieved and maintained in the O

performance of quality activities.

Quality procedures delineate the V

requirements for an indoctrination program to assure that personnel respons'ble for performing quality activities are instructed in the purpose, scope a' Iimplementation of quality procedures and instructions and that compliance to these documents is mandatory. The NUSCO Director, Quality Services is responsible for the indoctrination of personnel within l

his department who perform quality activities.

Nuclear training programs shall be developed and implemented to provide j

training for all individuals attached to or associated with NU nuclear facilities.

Additional guidance is established in NUSCO / NUPOC Procedures.

i implementing NUSCO / NUPOC Procedures describe the nuclear training program requirements which assure that:

a.

Documentation of formal training and qualification programs includes the objective, content of the program, attendees, and date of attendance; b.

Proficiency of personnel performing and verifying activities affecting quality is established and maintained.

Personnel O

'O QAP 2.0 Rev.: 13 Date: Aug.29,1990 Page 5 of 7 i

- t

proficiency is established and maintained by

training, 9

examination / testing, and / or certification based upon the (V

requirements of the activity. Acceptance criteria are developed to determine if individuals are properly trained and qualified c.

Certificates or other documentation of qualification clearly delineate the specific functions personnel are qualified to perform i

and the criteria used to qualify personnel in each function.

i This program also requires the head of each department _ (including NUSCO Qurifty Services) to be responsible for a training plan which assures that personnel performing quality activities are trained in the j

principles and techniques of the activity being performed.

2.2.6 MANAGEMENT PARTICIPATION i

l t

NUSCO Department Heads / NUPOC Nuclear Station and Unit Directors are responsible for implementing the NUQAP Topical Report within their

-Departments / Plants. The NUSCO Director,QualityServiceswillassistin i

development, coordinatien and review of the Program.

The Senior Vice President Nuclear Engineering and Operations ensures that a management review of the program is conducted on an annual basis, by an independent audit group, to assess the scope, status, implementation, effectiveness and to assure compliance to NRC licensing commitments, f

Acdons considered by the Management Review may include, but are not limited to, the following:

a.

Review of selected procedures and documents, b.

Verification of the implementation of selected procedural requirements, Review of past audit results such as those conducted by previous c.

Management Reviews, the NRC or other departments.

The Management Review's findings of deficiencies and recommendations for program improvement are forwarded to the Senior vice President-1 i

Nuclear Engineering and Operations, who will ensure appropriate corrective action is taken.

O l

QAP - 2.0 Rev.: 13 Date: Aug.29,1990 Page 6 of 7 1

-,,_.,,.,c r

The quality assurance programs of the engineer-constmetor, NUSCO C

contractors, suppliers and engineering se4vice organizations that perform

(

quality activities are reviewed by NUSCO Quality Services to assure that their managcment regularly reviews the status and adequacy of their part of the NUQAP.

4 1

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_ _. _. ~. _ _.

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i QAP 2.0 Rev.: 13 Date: Aug.29,1990 Page 7 of /

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3.0 DESIGN CONTROL 3.1 GENERAL REOUIREMENTS NUSCO/NUPOC is responsible for controlling design work, administering design control activities (including design interface) and design modifications for quality systems, structures and components.

The NUQAP for design is established to assure that the applicable design requirements, such as design bases, regulatory requirements, codes, technical standards and quality standards are identified in design documents which are reviewed, approved and controlled in accordance with established procedures.

Such controls include review for suitability of application of materials, J

equipment, parts and processes that are essential to the functions of the systems, structures and components.

Changes to, and deviations from specified i

requirements are identified, documented and controlled.

The responsibility for design control program implementation rests with NUSCO/

[

NUPOC for all NU nuclear generating facilities. The division of responsibilities and jurisdictional boundaries are set forth in the Nuclear Engineering and Operations Procedures (NEOs). Although other organizations may be delegated the task of establishing and executing the design control program or any part thereof, NUSCO/NUPOC will retain the t.!timate responsibility for the program.

The applicable requirements of the NUQAP will be imposed on other organizations delegated the task of establishing or executing the program in accordance with QAP 4.0 and QAP 7.0.

The interface controls, both internal and external, for organizations performing design work for quality systems, structures and components are identified and implemented in accordance with documented procedures. This identification includes those organizations providing criteria, designs, specifications and technical direction.

Measures are applied to verify the adequacy of design. The extent of design verification is specified and documented by the respondble organization. The individuals performing design verification should not (1) have immediate supervisory responsibility for the individual perfonning the design, (2) have specified a @ gular design approach, (3) have ruled out certain design considerations, or (4) have established the design inputs for the particular design aspect being verified. The independent design verification should not dilute or replace the responsibility of the supervisors far the quality of work performed under their supervision. Where changes to previously verified designs have been made, design verifications are required for the change, including evaluation of the effects of those changes on the overall design. Design verification may be QAP - 3.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 6

4 accomplished by testing. Test to demonstrate adequacy under adverse design conditions shall comply with the requirements of QAP 11.0, ' TEST CONTROL" l

Design ciron and deficiencies which advenely affect quality systems, structures and components in design process are documented, and appropriate corrective action is taken. These design erron und deficiencies are documented in accordance with design change procedu'.es or as defined in QAP 15.0.

j 3.2 IMPLEMENTATION NUSCO/NUPOC is responsible for the design, design review, engineering approval of design changes, design evaluation and design control of nuclear power plants. The function may be delegated to other organizations to petform the design activity, or any part thereof, but the responsibility for overall design remains with NUSCO/NUPOC. In all cases, final engineering decisions and ultimate design control of systems, structures and components related to nuclear 1

power plants is the responsibility of NUSCO/NUPOC.

NUSCO Quality Services performs audits, surveillances, inspections, in process verifications to verify that the engineering constructort, sontractors, suppliers, engineering service organizations and NU departments are e5ectively complying with the NUQAP and procedural requirements for design control.

3.2.1 DESIGN PROCESS Design control measures are applied to design analyses, such as, reactor physics, stress, thermal, hydraulic, nuclear radiation, accident and seismic analyses; compatibility of materials; accessibility for in service inspection, maintenance, and repair; and delineation of acceptance criteria for inst 7ctions and test. Measures established to control design documents are described in QAP 6.0.

Program procedures and instructions define the method of implementing i

design control measures. These measures require that applicable design requirements, such as, design bases, regulatory requirements, codes and standards, are translated into specifications, drawings, procedures or instructions.

Instructions further require that appropriate quality standards are specified and included in design documents, All materials, equipment, parts and processes, including standard "off the shelf" commercial or previously _ approved items essential to the quality functions, are selected and reviewed for suitability of application. The basis for selection may include industry standards, material and prototype hardware testing programs, and design review.

i QAP - 3.0 Rev.: 13 Date: Aug.29,1990 l -

Page 2 of 6

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NUSCO Procedures assure that a documented check is performed to verify the accuracy and completeness of design drawings and specifications before release to construction. Design drawings receive a documented check to verify dimensional accuracy.

Design drawings and specifications, issued for plant design changes during the operations phase of an in service nuclear plant, are reviewed for complec.-9 and accuracy before release to operations, in accordance with NUSCO/NUPdC Procedures defining Design Control.

NUSCO/NUPOC Procedures describe the provisions to assure that design drawings and specifications are prepared, reviewed and approved in accordance with company procedures, and that the documents contain the necessary quality assurance requirements, such as inspections and test requirements, acceptance requirements, and the extent of documenting inspection and test results.

3.2.2 DESIGN CHANGE CONTROL Procedu~reiarid instructions governing design change control during construction, modifications to operating plants, control of discrepant or deficient design conditione, and reported unsatisfactory performance, provide for the identification of the need for design changes and a documented method to control these changes. Design and specification j

changes are subject to design control measures commensurate with those applied during the original design.

An independent review and approval of design changes is performed by the organization that conducted the original ~ design reviews, unless NUSCO/NUPOC designates another qualified organizationso perform this function.

Proposed design change modifications are submitted to the in service units management for processing and review. This review includes the Plant Operations Review Committee (PORC)/ Site Operations Review Committee (SORC). PORC/SORC is advisory to the appropriate NUPOC Nuclear Station and Unit Directors on matters relating to nuclear safety.

Its composition, responsibilities, and authority are defined in Section 6 of each in service unit Technical Spreification. If the change involves a quality system structure or component, the change will be reviewed by qualified engineering personnel for technical adequacy. Reviews of the design change requests are performed by the Nuclear Review Board /Erwironmental Review Board on safety evaluations / environmental QAP 3.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 6 l

m questions. The sequence of the NRB review depends upon the determina-tion of whether an unreviewed safety question is involved (i.e., in p) accordance with ANSI N18.7, if a proposed change in the facility involves (V

an unreviewed safety question then the NRB review is conducted prior to implementation).

The combination of these independent reviews by the PORC/SORC and NRB/ ERB are performed to assure that:

the adequacy of the proposed change is determined; a.

b.

unreviewed safe.ty questions are properly identified and handled per 10 CFR 50.59; J

nuclear safety / environmental requirements have been considered.

c.

Errors ard deficiencies in design, including the design process, that could adversely affect quality structures, systems, and components are documented and conective action is taken to preclude repetition.

During the operations phase, notification of plant design changes are l

transmitted to responsible plant personnel as part of the design package

/'

close out. NUSCO/NUPOC Procedures describe this notification which

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assures that personnel are made aware of design change modifications which may affect the performance of their duties.

3.2.3 DESIGN INTERFACE CONTROL l

During design, construction or modifications of nuclear power plants, the I

Nuclear Engineering and Operations Group is responsible for review, coordination and documentation of design interfaces. Procedures provide the method for identification of design interfaces, design interface changes, and modifications affecting drawings and design documents.

During plant design and construction phases, control ofinterfaces may be delegated to the engineer constructor and/or Nuclear Stream Supply System (NSSS) supplier.

During the operations phase procedures and instructions identify design interfaces which are controlled by the appropriate NUPOC Nuclear Station and Unit Director. Resolution of design intcrface questions are documented.

I l

QAP - 3.0 i

Rev.: 13 f

Date: Aug.29,1990 Page 4 of 6

-->e

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I 3.2A INDEPENDENT DESIGN VERIFICATION Original designs and design modifications are reviewed for adequacy and the sign off perfonned by a person other than the originator of the design. Design vedfication is documented in accordance with procedures or instructions. Simplified calculations or computer programs may be utilized as alternate means of design verification.

When design verification is perfonned by testing, the tests -are performed using approved procedures, which specify the authority and responsibility of design verification personnel. Ultimate responsibility for design adequacy and evaluation is retained by NUSCO/NUPOC, as appropriate.

Design venfication (if other than by quali;ication testing) is normally I

completed prior' to release - for procurement, manufacturing, and i

construction, or to another organization for use in other design activities.

For those cases where design verification cannot be completed prior to release for procurement, manufacturing, and construction, procedures l

ensure that design verification is completed prior to the point when the installation is declared operational.

NUSCO/NUPOC Procedures describe the requirements which assure the foliowing when testing is considered as an alternate method of design verification:

l Specifications or procedures provide criteda that specify when a.

verification should be by test.

b.

Prototype, component or feature testing is performed as early as possible prior to installation of plant equipment, or prior to the point when the installation is declared operational.

Vedtiation by test performed under conditions that simulate the j

c.

most adverse conditions as determined by analysis.

Particular emphasis is placed on assuring that designs are in conformance i

with applicable codes, ed on selecting the proper design verification or l

checking method. Procedures and instructions provide the requirements and necessary controls for design verification. These controls include a i

review to assure that design characteristics can be controlled, verification that there is adequate accessibility for inspection or test, and that inspection and test acceptance criteria are incorporated. During the operations phase, documentation of reviews is provided.

1

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QAP - 3.0 i

Rev.: 13 Date: Aug.29,1990 Page S of 6

i NUSCO/NUPOC Procedures _ include requirements which identify the responsibility of design verifiers, the areas and features to be verified, and the extent of the documentation.

~ NUSCO/NUPOC Procedums assure that procedural control is established for design documents that reflect the commitments of the SAR. These procedural controls vary for design documents which receive formal design verification by several disciplines or organizations, and those which can be reviewed by a single individual. The specific design documents and specialized reviews are determined and used as required by the design changes and modifications.

NUSCO/NUPOC Procedures are established to assure that verified computer programs are certified for a specific use.

NUSCO/NUPOC is responsible for assuring that the design documents generated by the engineer. constructor, contractors, suppliers and engineering service organizations are adequately generated, approved and maintained.

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QAP - 3.0 Rev.: 13 Date: Aug.29,1990 Page 6 of 6

b 4.0 PROCUREMENT DOCUMENT CONTROL 4.1 GENERAL REOUIREMENTS 1

The procurement of materials, equipments, parts and/or services required during the design, construction, testing, operation and maintenance of quality systems, structures and components in nuclear power plants is performed in a controlled manner which assures compliance.with applicable regulatory requirements, procedures, quality assurance standards and regulations affecting procurement documents. Changes to procurement documents are subject to the same degree i

of control as utilized in the preparation of the original documents.

l 4.2 IMPLEMENTATION 4.2.1 PROGRAM I

A Project Manager and/or a Project Engineer are selected for each I

modification to an in service nuclear power plant. The project engineer coordinates the preparation, review and approval of procurement documents for quality material, equipment, parts or services, and ensures the technical adequacy and inclusion of quality assurance requirements.

NUSCO/NUPOC Purchase Requisitions are reviewed for technical adequacy and verification of the quality designation. The appropriate NUSCO Project Engineer /NUPOC Nuclear Unit Director reviews and approves NUSCO/NUPOC Purchase Requisitions, when applicable.

NUSCO Quality Services personnel then review the purchase requisition, for the inclusion and adequacy of quality assurance requirements, prior i

to the issuance oi the purchase order.

Any engineer constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance, and modifications to nuclear power plants are responsible to implement measures for control of procurement documents associated with quality material, equipment, parts and services to ensure applicable requirements including quality assurance

+

requirements are specified. NUSCO Quality Services performs on site and off site audits, surveillances, inspections and in-process ve:ifications to ensure organizations utilized by NUSCO/NUPOC are effectively complying with their requirements for the control of procurement documents.

l Changes to procurement documents, whether initiated by NUSCO/NUPOC or their representative, are subjected to the same degree of control as Ob QAP - 4.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 3 l

. ~

i l

that utilized in the preparation of the original document.

The O

procurement of spare or replacement parts for quality systems, structures, i

V or components is subject to the controls of the latest NU QA Program and i

NUSCO/NUPOC procedure requirements. The spare or replacement parts are subject to controls equivalent to original or subsequent codes and i

standards, t

Procurement documents are reviewed by Quality Services personnel to determine that:

i The quality assurance requirements are correctly stated, auditable a.

and controllable; I

b.

There are adequate acceptance and rejection criteria.

j The procurement document has been prepared, reviewed, and i

c.

approved in accordance with the NU QA program requirements.

l 4.2.2 PROCUREMENT DOCUMENT PROVISIONS Procurement documents are prepared, reviewed nnd approved in accordance with approved procedures of the issuing organization or department and are available for verification. These procedures require that procurement documents consist of the following, as necessary:

a.

The scope of work to be perfonned; b.

Technical requirements (specified or referenced) including the applicable components and materials identification requirements, drawings, specifications, procedures, instructions, codes and i

regulations, and the identification of applicable test, inspectica and acceptance requirements, or special process instructions; c.

Quality Assurance Program requirements to be imp'esed on contractors which include the applicable require.nents of 10 CFR 50, Appendix B, and the NRC regulatory position contained in the Regulatory Guides and their endorsed ANSI Standards listed in Appendix D of this Topical Report; d.

Right of access which provides, as appropriate, for access to contractor facilities and records for inspection or audit by NUSCO or its designated representative; and provides access for events such as those requiring notification of hold points;

(*

QAP 4.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 3

I The documentation required to be prepared, maintained, and / or

)

e.

submitted to NUSCO/NUPOC or its representative for review, j

approval or historical record.

The time of submittal of this documentation and the retention and disposition of quality j

assurance records which are not submitted to NUSCO/NUPOC is prescribed, as applicable, for NUSCO/NUPOC Nuclear Grade j

procurements.

4.2.3 SRIFCTION OF PROCUREMENT SOURCES i

If the engineer-constructor, contractor, or supplier is not delegated the function of procurement source selection, the NUSCO Purchasing i

Department verifies that the procurement document has been reviewed and approved, and that the supplier has been approved for procurement prior to issuing the purchase order for the material, equipment, parts and services.

Supplier approval is not required for the procurement of commercial grade items.

Procurement documents may be issued to organizations with unapproved l

quality assurance programs.

These procurement documents to unapproved organizations contain detailed supplementary quality assurance requirements and/or witness / hold point to meet NUSCO requirements.

Procurement documents are reviewed by NUSCO Quality Services to ensure appropriate quality assurance requirements are specified. These requirements, included in the procurement document as necessary, include acceptance criteria, audits and/or inspections at the suppliers facilities with scheduled witness / hold points during the fabrication 1

process and/or prior to shipment of the procured item. Acceptance inspections and tests determined by NU shall be performed after receipt at NU but prior to operation.

O QAP 4.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 3 i

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l 5.0 PROCEDURES. INSTRUCTIONS. AND DRAWINGS l

5.1 GENERAL REOUIREMENTS The NUQAP provides measures for the preparation, review, approval, control and distribution of procedures, instructions and drawings of aethities affecting quality systems, structures and components during design, construction, testing, maintenance, modifications, and operation of nuclear power plants.

The documents include appropriate quantitative and qualitative acceptance criteria which specify the activity to be perfortned, the methods of construction and testing to be employed, material, equipment or parts to be used, a sequence of operation and the required documentation.

5.2 IMPLEMENTATION Quality Procedures provide direction for personnel perfortning quality functions.

)

NUSCO Quality Services Department reviews and concurs with Quality Procedures such as those listed in spendix C. Comments concerning compliance with the NUQAP Topical Report and regulatory requirements are resolved prior i

tcdssuance of the procedure. NUSCO Quality Services receives controlled copics

]

of Quality Procedures that are listed in Appendix C. Any engineer constructors,

(

contractors, suppliers, and engineering service organizations utilized by NUSCO/

NUPOC in the design, construction, testing, operation, maintenance and modifications to nuclear power plants may be delegated responsibility for prepar:ng, maintaining, issuing and verifying the implementation of appropriate program documents which are selectively reviewed / approved by the appropriate NUPOC Nuclear Unit Director, NUSCO Superintendent, Generation Construction, or Project Engineer, as appropriate. In this case, NUSCO Quality Senices performs on site and off site audits /surveillances/inspecRons/in process verifications of the quality assurance programs to ensure the engineer-constructor, contracto, suppliers and engineering service organizations are offectively complying with their requirements for compliance with their requirements for procedures and instructions. Contractor programs are required to clearly delineate the actions to be accomplished in the preparation, review-and control of procedures, instructions and drawings and the methods for complying with 10 CFR 50, Appendix B, 5.2.1 PROCEDURES AND INSTRUCTIONS

. Procedures and instructions for activities affecting quality are prepared, reviewed, and approved in accordance with written procedures and instructions.

O QAP - 5.0 Rev.: 13 Date: Aug. 29,3990 Page 1 of 3 L

l s

l The NUSCO Superintendent, Generation Construetion, or NUSCO/NUPOC f3 Project Engineer, ensures that any engineer-constructors, contranets, l

suppliers and engineering service organizations utilized by NUSCO/

L (')

NUPOC in the design, construction, testing, operation, maintenance and modifications to nuclear power plant, implement quality assurance i

programs which contain written instructions for preparation, review and approval of procedures and instructions affecting quality, in addition, contractor's site construction procedures and quality controlinspection procedures are reviewed for concurrence by NUSCO Quality Services to l

assure compliance with the Program.

The NUPOC organization is responsible for the preparation, review and approval of plant Quality Procedures.

The procedures include test i

procedures and overall site sdministrative procedures which implement the requirements of the NUQAP Topical Report.

Each NUPOC organization is also responsible for the preparation, review and approval of procedures covedng quality activities in accordance with individual license requirements. The NUSCO Quality Services Department reviews and concurs with quality procedures, such as those listed in Appendix C.

5.2.2 DRAWINGS f)

The design control and verification measures described in QAP 3.0, U

are applicable for the review and approval of drawings. The

-Engineering Design Supervisor and the Engineedng Supervisor have the responsibility, which can be delegated, for review and approval of new drawings or modifications to existing drawings, i

The originating organization may delegate to other organizations or departments the work of design and review activities, or any part thereof, but retains responsibility for this work.

The measures taken to assure the preparation of as. built drawings and related documentation in a timely manner to accurately reflect the actual plant are described. in NUSCO/NUPOC Procedures.

Drawings critical to operation are updated prior to system turnover to operation and are available to the operating personnel.

5.2.3 ACCEPTANCE CRITERIA Cognizant Department Heads review and approve departroental procedures, instmetions and drawings to ensure the inclusion of adequate quantitative and qualitative acceptance criteria, as QAP 5.0 Rev.: 13 Date: Aug. 29,1990 Page 2 of 3

I appropriate, for determining satisfactory work performance and quality compliance. These criteria apply to activities such as design, operations, maintenance, test control, inspection and plant modifications.

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O QAP 5.0 Rev.: 13 Date: Aug. 29,1990 Page 3 of 3

6.0 DOCUMENT CONTROL 6.1 GENERAL REOUIREMENTS The NUQAP provides measures to assure controlled distribution of documents pertinent to quality assurance for the design, constniction, testing, maintenance, operation and modification of nuclear power plant quality systems, structures and components in accordance with NUSCO/NUPOC quality procedures and 10 CFR 50, Appendix B.-

Documents such as procedures, instructions, drawings, specifications and reports are prepared, reviewed for appropriate qualitative and quantitative acceptance criteria, and approved by authorized personnel in the affected organization.

Approved controlled documents are distributed to affected locations in accordance with controlled distribution list. Changes to controlled documents are reviewed and approved by the same organization which perfonned the original review and approval, unless otherwise specified in the implementing procedures.. Measures are provided for controlling documents to preclude the pordbility of the use of outdated documents.

6.2

'MPLEMENTATION t

6.2.1 RESPONSIBILITY NUSCO/NUpOC Procedures and Instructions delineate the measures for l

controlling documents including direction for the review for adequacy, approval by authorized pen;onnel, distribution of controlled documents and verification that changes are promptlyincorporated and implemented.

These control measures apply to documents affecting quality systems, structures and components during design, construction, maintenance, testing, operation and modifications thereto such as:

a.

Design Specifications; b.

Design, Manufacturing, Construction and Installation Drawings; c.

As Built Dccuments; d.

Quality Assurance Program Manuals, Procedures and Instructions; 4

I c.

Manufacturing, inspection and Testing Instructions; f.

Test Procedures; O

V QAP - 6.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 3

g.

Final Safety Analysis Report; h.

Procurement Documents; y

i.

Design Change Requests; j.

Topical Report; 3

k.

Nonconformance Report; 1.

Computer Codes.

NUSCO/NUPOC Procedures describe the measures taken by NUSCO Quality Services or indh'iduals other than the person who generated the document but qualified in quality assurance, for the control of documents to assure review e.nd concurrence, as necessary, for such documents listed above with regards to quality assurance aspects.

.,Jhe requirements for control of procurement documents are contained in QAP 4.0. During all phases of plant life, it is the responsibility of each organization issuing controlled documents to employ document control procedures. The issuing organization is additionally responsible for distribution of the documents to appropriate locations. There shall be 1

provisions to assure that approved changes are included in instructions, procedures, drawings and other documents pnor to implementat')n of the changes.

Any engineer constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance, and modifications to. nuclear power plants are responsible for implementing measures for review, approval, control and distribution of controlled documents, to ensure they are effectively complying with the requirements for document ec,ntrol.

NUSCO Quality Services performs periodic on site and off. site audits, surveillances, inspections, and in process verifications of the engineer-constructors, contractors, suppliers and engineering service organizations l

to verify compliance with their approved quality assurance programs..

6.2.2 DISTRIBUTION OF CONTROLLED DOCUMENTS NUSCO/NUPOC Procedures, specify in what manner controlled documents and revisions thereof, are distributed to appropriate locations,

- prior to commencing the work.

Holders of controlled copies of documents complete acknowledgement of receipt forms and return them QAP 6.0 Rev.: 13 Date: Aug.29,'1990 Page 2 of 3 s

i I

to the distributor in order to assure that obsolete or superseded T

documents are removed from the work areas in a timely manner. NUSCO j

Quality Services perform pedodic on site and off site audits, surveillances, inspections, and in process vedfications to verify compliance with the i

requirements of procedures for document control.

6.2.3 DRAWING CONTROL The NU Generation Facilities Records Organization is responsible to implement a program, as per approved procedures, for the retention and retrieval of drawings and records submit:ed by the cognizant NUSCO/

j NUPOC project personnel.

The NU Generation Facilities Records Organization maintains a drawing status file for in service units which includes drawings newly issued or revised with latest revision and current status.

)

i The engineer-constructor, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC during the design, construction i

and modification to nuclear power plants may be delegated the function of drawing control and must furnish periodic status reports listing the revisions of applicable drawings which they issue.

NUSCO Quality Services Department performs on site and off site audits, surveillances, inspections, and in process verifications of suppliers to verify they are effectively complying with their programs for document control of drawings.

6.2A INSTRUCTION AND PROCEDURE CONTROL NUSCO Quality Services Depar' ment performs audits, surveillances, inspections, and in process verifications of NU departments and any engineer constructors, contractors, suppliers and engineering-servae organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance, and modification to ensure they are effectively complying with their QA program for control of procedures and instructions.

l The originating department is responsible for establishing adequate control over quality procedures and instructions issued by them. The responsible organization also issues status reports or revised indices listing the latest revision of applicable controlled documents issued by them.

QAP - 6.0 Rev.: 13 Date: Aug.29,1990 l

Page 3 of 3 l

i 1

7.0 CONTROL OF PURCHASED MATERIAL EOUIPMENT AND SERVICES r

(

7.1 GENERAL REOUIREMENTS Measures for the control of procured material, equipment, parts and services by

)

or for NU related to the safety of nuclear power plants are established and j

imposed by the NUQAP during design, construction, testing, operation,

)

maintenance and modification, to ensure conformance to procurement documents.

These measures include provisions for source evaluation and selection, submission of objective evidence by the contractor or subcontractor, inspection.at the supplier source and examination of items upon delivery.

Control of quality by contractors and subcontractors is assessed for effectiveness at intervals consistent with the importance, complexity and quantity of the product or service.

]

7.2 IMPLEMENTATION The word supplier is used in this section to designate what is otherwise described as the engineer-constructor, contractor, supplier or engineering service organization.

(

The evaluation and selection of suppliers is performed in accordance with

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procedures, which specify that procurement source evaluation and selection i

measures are performed to determine supplier capability and ' delineate responsibilities of qualified personnel involved in the evaluation and selection process.

7.2.1 NUSCO Quality Services utilizes one or more of the following methods v

in evaluating the qualifications of a potential supplier: o Audits and/or coordinated review of a potential supplier utilizing a.

one or more departments (i.e., Engineering, Construction, Operations and/or Purchasing);

b.

Engineer constructor or other utility supplier audits and evaluations; c.

Nuclear Utilities Procurement issues Committee (NUPIC) audits, d.

ASME N, NA, NPT, NV, or MM/ MS Certificate of Authorization.

t i

QAP - 7.0 Rev.: 13 Date: Aug.29,1990 page 1 of 4 l

l

i i

Commercial grade periodic surveys and/or coordinated review of e.

3 a potential supplier utilizing one or more depanments, (i.e.,

)

(O)

Engineering, Construction, Operations and/or Purchasing).

l Evaluations ensure that NU suppliers employ a quality assurance program that conforms to applicable portions of the NUQAP Topical Repon.

NUSCO Quality Services maintains documented evidence of the evaluation and acceptance of the suppliefs quality assurance program.

The determination of supplier approval is based on such factors as prior performance, historical quality performance data, audits, commercial grade periodic surveys, surveillances and evaluations of the suppliefs

)

quality assurance program.

Suppliers Certificates of Conformance are periodically evaluated by audits, commercial grade periodic surveys, surveillances, independent intpections and tests, to assure they are valid. This verification of Certificates of Conformance is documented.

i 7.2.2 SOURCE INSPECTION NUSCO Ouality Services is responsible for the performance of source O

inspect' a at suppliers facilitics to ensure that the requirements of a V

Purchase Order contract have been met.

Source inspections are performed in accordance with written procedures which provide for:

a.

The method of inspection and the extent. of documentation required and those responsible for implementing those instructions; b.

Inspection of those items where verifications 'of procurement requirements cannot be dete:Tnined upon receipt.

7.2.3 RECEIPT INSPECTION s

Receipt inspection for procured items is performed under the direction of NUSCO Quality Services Department in accordance with quality procedures which delineate requirements and responsibilities neebssary to perform inspection functions. Contractual obligation fulfillment and quality assurance requirements are verified during receipt inspections.

QAP. 7.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 4

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I Receiving inspection of supplier furnished material, equipment, and services is performed to assare that material, components, equipment and acceptance records are inspected and judged acceptable in accordance with predetermined inspection instructions prior to installation or use.

Receipt inspections include, as appropriate:

a.

Measures for verifying that the shipment is complete, properly identified, undamaged and corresponds with the receiving documentation; b.

Measures for inspection of the item and review of supporting documentation (e.g., mill test reports, NDE reports) as required by the purchase documents; I

c.

Measures for inspection and acceptance of items to inspection instructions; d.

Measures for identifying and controlling acceptable items including identification of inspection status prior to release from the.

receiving inspection area; e.

Measures for identifying, segregating and handling nonconforming O..

items; f.

Measures to ascertain that inspection records or certificates of conformance are available prior to release to construction / plant for installation.

7.2.4 SUPPUER FURNISHED RECORDS Records required to be furnished by the supplier are specified in the procurement document.

Certifications or documentation verifying conformance, provided by the supplier, identify that all the specific procurement requirements have been met (either by reference to the purchase order or by delineation).

The supplier must furnish the following records as a minimum:

a.

Documentation that identifies the purchased material or equipment and the specific procurement requirements, (e.g., codes, standards and specifications) met by the items; QAP 7.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 4

)

+

b.

Documentation that identifies any procurement requirements which have not been met, together with a description of those nonconformances dispositioned " accept as is" or " repair" i-The responsible NUSCO Quality Services personnel shall review for i

acceptability those documents which pertain to the requirements in the procurement document, in accordance with the NUQAP Topical Report I

and its applicable procedures.

j 7.2.5 NUSCO/NUPOC Procedures address the measures taken to assure that for commercial grade items, where specific quality assurance controls for nuclear applications cannot be imposed in a practicable manner, that special dedication requirements are established and described, h-a These mersures follow the guidance in Regulatory Guide 1.144, paragraph C.3.b (1) and Regulatory Guide 1.123 and applicable paragraphs of Section 10 of ANSI N45.2.13.

.These.. measures include appropriate requirements for special i

categorization and identification within the procurement document, receiving inspection, and additional controls during the installation and testing process to be performed by NUSCO Quality Services Department, NUPOC and/or other appropriate groups.

2

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QAP 7.0 Rev.: 13 Datc: Aug.29,1990 Page 4 of 4

8.0 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS 8.1 GENERAL REOUIREMENTS NUSCO/NUPOC organizations assure that the identification ofinspections, tests, and operation status of structures, systems, and components is known by affected organizations.

The NUQAP provides measures for the identification and control of material, parts and components, including panially fabdcated assemblies, daring design, construction, testing, operation, maintenance and modifications thereto. To ensure that each item can be traced to associated documentation, the identification of the item is maintained by heat number, lot number, part number, serial number, or other appropriate methods, and is physically marked on the item and/or on records traceable to the item. Documentation associated with material, equipment, and components verify that these items have been designed, fabricated, manufactured, tested and/or inspected in accordance with the specified requirements. The object of these controls is to prevent the use of incorrect or defective materials, parts and components, in accordance with 10 CFR 50, Appendix B.

8.2 IMPLEMENTATION NUSCO/NUPOC Procedures establish the responsibilities and requirements for the identification and control of materials, parts and components.

The procedures assure that identification and control is maintained throughout fabrication, receipt, handling storage and installation of items.

Provisions include:

a.

Requirements for traceability to appropriate documentation such as:

procurement documents, manufacturing documents,

drawings, specifications, certifications, inspection -and test

records, and nonconfonnance reports, b.

Controls to assure that the correct identification of an item is verified and documented prior to release for fabrication, assembly, shipping or installation.

c.

Requirements which assure that the method or location of markings do i

not affect the function or quality of an item, i

i QAP - 8.0 Rev.: 13 Date:- Atig. 29,1990 Page 1 of 2 n1 U

~N

1. 7

s.

l d.

Establishment of identification requirements in specifications, drawings,

- procurement documents, procedures or instmetions.

During the design, construction, testing, operation, maintenance or modifications to nuclear power plants,.NUSCO/NUpOC may delegate any portion of the iniplementation of.the identification and control program to any engineer-constructors, contractors, suppliers and engineering service organizations utilized 1

by NUSCO/NUPOC in the design, construction, testing, operation, maintenance and modification to nuclear power plants, as appropriate. If delegated, contracts requirs that the contractor establish an identification and control program which j

meets the NUQAP Topical Report requirement. In this case NUSCO. Quality Services performs on. site and off site audits, surveillances, inspections, and in-process verifications of the. engineering-constructor, contractor, supplier, g

engineering service ' organization's. quality asurance program to ensure they are effectively complying with these requirements for identification and control of d

material, equipment and componentsi i

Receipt' inspections are performed to verify that materials, equipment and components-are properly identified in' accordance, with procurement-requirements. NUSCO Quality Services is responsible for assigning and applying permanent identification to the items in accordance with approved procedures.

If the application of a serial number is not practical, other -means of identificttion are implemented to assure proper identification' and traceability.

l In the event that the eq Gment, material or coinponent is nonconforming or the

.j identification becomes lv> r Olegible, the items are considered nonconforming and are identified and controlled in accordance with QAP 15.0.

r l

[

. QAP - 8.0 Rev.: 13 Date:- Aug. 29,1990 Page 2 of 2

9.0 CONTROL OF SPECIAL PROCESSES 9.1-GENERAL REOUIREMENTS q

l The NUQAP provides measms to assure control of special processes assodated p

with quality systems, structures and components by the use of q*.,alified, approved procedures, equipment and personnel during design, construction, testing, operation, maintenance and modifications to nuclear power plants. -

Special processes are performed under controlled conditions in accordance with special requirements and may include, but are not limited to: welding, cleaning, heat treating, and nondestructive examination and/or testing.

4 9.2 IMPLEMENTATION During design, construction testing, operation, maintenance, and modification of nuclear power plants, NUSCO/NUPOC Project Engineer is responsible for i

ensuring that.special process data.and documentation is reviewed, and that j

contractors, engineer-constructors, suppliers, and/or engineering service organizations special process procedures utilized at nuclear power plants are qualified and approved, and that-personnel and equipment utilizing spe':ial processes are properly-qualified prior to start of work.' NUSCO Quality Services personnel perform on site and off. site audits,

- leillances, inspections, and in-procest verifications to ensure - the engu..aing-constructors, contractors, suppliers, and engineering servbe organizations are effectively complying with their quality assurance progra.

equinments for control of special processes.

~

NUSCO/NUPOC specia. process procedures utilized during testing, operation, maintenance, modification and refueling of the in service nuclar power plant i

dre prepared, reviewed and approved in accordance With procedures as'specified in QAP S.O.

9.2.1 PROCEDURE OUALIFICATION AND CONTRO.L -

NUSCO / NUPOC' Procedures specify that written process control-documents are utilized and ' qualified, as required, in accordance the applicable specification, codes or standards.

1 9.2.2 PERSONNEL OUALIFICATION AND CERTIFICATION Codes. standards and NUSCO/NUPOC procedures specify personnel qualification / certification requir::ments. Personnel responsible for the performance and verification of special processes are trained, tested, and QAP - 9.0 Rev.: ' Ib Date: Aug.29,1990 i

Page 1 of 2

certified as required. by applicable specifications, codes and standards.

Requirements for the period of certification, retesting, and recertification of personnel are also;specified.

Contractors qualify personnel and:

maintain records of qualified personnel in accordance with applicable 1

codes, standards, specifications, and contractor procurement document requirements. Quality Services Department is responsible for the review of records of qualified personnel, equipment and procedures associated with special processes.

The NUSCO Director, Quality Services is responsible for the training,-

i testing, and certification of! all NUSCO/NUPOC NDE; personnel in -

accordance with the requirements of Regulatory Guide 1.58 (Rev.1, 9/80) and ASNT Recommended Practice No. SNT-TC-1A.

I i

9.2.3 ' SPECIAL PROCESS RECORDS Records provide objective evidence that special processes were performe_d in accordance with approved procedures, by qualified personnel, 'and that.

whea required by procedures, specifications, and codes, such performance -

was verified. Resulti of nondestructive examinations ate recorded in i

accordance_with appil:able specifications, codes and standards. These records are retained btthe supplier or_ supplied to NUSCO/NUPOC2s O

required by contract or pr. chase orders. If records are to be retained by the supplier, the contract or purchase order specifies the retention period and instruction for final disposition of records.-

1 Special process documentation such 'as special process procedures,-

1 qualifying - data, and l personnel - and equipment. qualification ' records associated with the performance of special processes at nuclear power plants, are kept current and maintained in appropriate NUSCO/NUPOC files, with final disposition to the appropriate NU Nuclear Plant Records Facility.

i QAP - 9.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 2 m

m 10.0 I'NSPECTION 10.1 GENERAL REOUIREMENTS Inspection of activities to ' verify - the quality of systems, structures and components,' which are pu%rmed by or for Northeast Utilities (NU), are j

executed in accordance wah the Quality Assurance Program (NUQAP) and appropriate procedures,. instructions and drawings by qualified personnel i

. independent from the individual or group performing the activity being l

inspected. _ If inspection is impossibic or disadvantageous, indirect controls by monitoring processing methods, equipment and personnel are provided.

Inspection notification and hold points -are identified,-as required, in the i

applicable documents.

10.2 IMPLEMENTATION 10.2.1 INSPECTION RESPONSIBILITIES l

y During construction, testing, maintenance, modification, and.

j operation, qualified NUSCO_ Quality Services personnel shall

)

review work orders in order to determine the need for; t

O a.

Inspections (e.g., receipt inspections, installation, system turnover, and product acceptance);

b.

Identification of inspection personnel; Documentation of inspection results.

c.

The review also ensures that -the necessary inspection requirements, methods, and acceptance criteria have been 1

identified.

NUSCO. Quality Services performs

audits, surveillances, inspections, and' in process verifications to verify that" any engineer-constructors, contractors, suppliers, and engineering service organizations utilized by NUSCO/ NUPOC in the design, construction, testing, operation, maintenance, and modification to nuclear power plants are effectively complying with their quality assurance program requirements for inspection and for performing / witnessing inspections at " hold" or " notification" points identified in NUSCO/NUPOC procurement documents. All audit, surveillance, inspection, and in process verification activities are QAP - 10.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 4 T

/

?

performed under requirements specified in written quality assurance procedures.-

10.2,2 INSPECTION PLANS AND SCHEDULES-l Documented inspection plans may be either a separate document or an integral part of work instruction documents. The plans are based on design specifications, procurement documents, drawings, other specifications, or previous experience, as appropriate..

Inspections are scheduled to assure that. sufficient time ' and resources are available,, and to ' assure inspections are not inadvertently omitted or bypassed.

During NU;CO-directed activities' of nuclear plants,L NUSCO.

Procedures provide criteria _ for the determination of. accuracy requirements of inspection equipment and when inspections are

~

~ hese proceares describe requirements for the required.

T preparationiof inspectio.. plans and schedules by thel NUSCO

- Quality Services Department. NUSCO Procedures also' describe._.

requirements for audits and surveillances performed by the NUSCO Quality Services Department _to assure the implementation of the inspection plans and schedules, n

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During the oper.

..s phase of nuclear plants, inspection activities are perfonned in accordance with NUPOC/NUSCO procedures.

NUSCO Quality Services participates in h spection activities by the review of the work pn eedures and the preparation and approval of inspection plans.

The inspection criteria, including the use of inspection equipment and their accuracy requirements, are -specified in the-Job Packages / Inspection Plans.

10.2.3 INSPECTION PERSONNEL AND-INSPECTION DOCUMENT ACCESS a.

Inspections are performed by individuals other than those who performed or directly supervised the; activity being inspected.

Inspection _ personnel are' qualified and/or.

certified in accordance with appropriate codes, standards, and/or NU training programs; b.

Inspections are performed by NUSCO Quality Services personnel or by qualified contracted personnel who are QAP - 10.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 4

1 independent. from undue - pressure such as cost and schedule.

When NUPOC plant personnel / contracted personnel perform inspections, their inspection plans /

procedures and personnel qualification criteria are reviewed y

and found acceptable by the NUSCO Quality Services

. Department prior to the initiation of the ectivity; c.

Access to drawings, procedures, specifications or other-documented criteria necessary for the performance of aupections is provided prior to performing the inspection activity.

-i c

10.2.4 INSPECTION PROCEDURES Required inspection or surveillance activities are performed i

a.

and documented according to written, approved procedures and/or. checklists.

Inspection procedures, p.ans Lor' i

checklists contain the following:

(1)

_ Identification of characteristics to be inspected; (2)

Identification of the individual or groups responsible I

for performing the inspections; -

Requirements fo' the necessary measuring and test

-(3) r equipment and the required accuracy. of this -

equipment; (4)

Acceptance criteria; (5)

A description of the method ofinspection; (6)

A record of the results of the inspection; (7)

Record of inspector or data recorder, b.

- Written approved procedures. specify surveillance of processing methods or testing and operation of equipment when inspection is impossible, inaccessible or not applicable.

l c.

Modification, repair, replacement or rework items are inspected in accordan;c. with original inspection requirements or approved altematives.

QAP - 10.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 4 -

_. m v

p 10.2.5 MANDATORY HOLD AND NOTIFICATION POINTS

_ Mandatory hold points are utilized when an inspection / operation j

must be performed or witnessed and signed off by the responsible personnel before work can proceed. Notification points' are used to identify the operations or completed processes that NUSCO/

NUPOC or its representatives may elect to witness and/or inspect -

during the manufacturing, constniction, installation process.

Mandatory hold and notification points, as required, are identified in procurement documents and procedures. These documents are subject to the review and concurrence of NUSCO Quality Services.

l for adequacy of inspection, notification and/or mandatory hold controls.

q 10.2.6 INSPECTION RESUI,TS EVAI,UATION -

inspection results are evaluated for acceptability in accordance with approved NUSCO/NUPOC Procedures which identify the -

1

- -responsible organization.

The evaluations are performed by the responsible NUSCO /. NUPOC l

personnel who are qualified in accordance with the appropriate l

Regulatory Guide / ANSI Standard commitments listed in I

Appendix D.

NUSCO Quality Services performs audits, surveillances, and m-process verifications to assure that inspections are performed per the requirements of applicable NUSCO/NUPOC Procedures.

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QAP - 10.0 Rev.: 13 Date: Aug.29,1990' Page 4 Of 4 h

11.0 TEST CONTROL j

11.1 GENERAL REOUIREMENTS A documented test control program is estab!ished by the NUQAP for systems, structures and components to ensure that they will perfonn satisfactorily in.

service and that test results are documented in accordance with 10 CFR 50,'

Appendix B and other pertinent regulatory and/or technical requirements. -

The test control program identifies the systems, structures and components to be tested, method of conducting tests, evaluation of tests and documentation 'of tests by qualified personnel to assute requirements have been satisfied.

The test' control program is' systematic and includes proof tests prior. to' Installation, construction tests, operational tests, surveillance tests, and retest 1

following repairs, replacements, preventative maintenance or modifications, i

11.2 IMPLEMENTATION _

11.2.1 TEST PROGRAM Test requirements to determine or to verify the capability of an item tc' meet specified requirements - in accordance with' I

engineering / design documents, Safety Analysis Reports (SAR),

technical specifications, procedures or procurementndocuments, as 1

appropriate, are accomplished by subjecting the item to a set of j

physical, chemical, environmental or operating conditions. Retest -

1 following repair, replacement'or modification is performed in I

accordance with the original design requirement 9 or acceptable.

1 alternatives and is performed when original test results are invalidated.

NUSCO/NUPOC procedures are written and approved to delineate the methods and responsibilities for controlling, accomplishing and documenting testing during construction, maintenance, operation i

and modification of nuclear power plants.

Any engineer-constructors, contractors, suppliers, and engineering service organizatione utilized by.NUSCO/NUPOC in the design, cautruction, testing, >peration, maintenance and modification to a

nuclear power plant. are responsible for implementing measures.

for the control of tests to ensure that materials, equipments and parts will perform satisfactorily. NUSCO Quality Services performs QAP - 11.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 3 i

L 1

on site and off site audits, surveillances, inspections, and in-i f

process verifications of. selected proof tests when " notification" j

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points have been identified in Purchase Order / Contracts of the

~

engineer-constructors, contractors, suppliers-and engineering _

i service organizations to verify they' are complying with their quality assurance program requirements for test control.

Documentation associated with these observations are maintained j

by NUSCO Quality Services..

l i

Proof tests, product acceptance tests, retests, and periodic surveillance-tests are conducted by qualified personnel _ in

.i accordance with approved procedures. Personnel performing tests ensure that calibrated equipment and instrumentation utilized are within the calibration interval specified. Documentation including.

test procedures and approved data sheets-are maintained in appropriate files.

11.2.2-TEST PROCEDURE PREPARATION AND TEST PERFORMANCE '

Testing is accomplished in accordance' with approved. test procedures which incc,rporate or reference the requirements and-

)

l acceptance criteria in the applicable design and procurement-l-

documents. The test procedure or test program documents include l

the following as a minimum:-

a.

Instructions for the testing method used; b.

Required test equipment and instrumentation; l

Test requirements, such as acceptance and rejection criteria; f

f c.

d.

Hold, notification, inspection and data collection points; c.

Test prerequisites such a's:

calibrated instrumentation; trained, qualified, ar.d-licensed' or certified personnel; preparation, condition and completeness of item to be tested; suitable and controlled environmental conditions; f.

Methods for documenting or. recording test data and-1 results; g.

Provisions for data collection and storage.

QAP - 11.0 Rev.: 13 l

Date: Aug.29,1990 Page 2 of 3

11.2.3 TEST EOUIPMENT c

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- NUSCO/NUPOC Procedures provide the criteria for determining when a test is required and the accuracy requirements of test equipment.

During the operations phase of a nuclear plant, the following steps are taken:

To ensure accuracy, test instrumentation is checked and-a.

calibrated in accordance with NUSCO/NUPOC procedures.

b.

Plant instrumentation used-in testing is calibrated. It is maintained in calibration at regular intervals in accordance with established surveillance and / or preventative maintenance procedures, Where special instrumentation is required for testing, the -

c.

~

requirements are stated in the procedures.- Instrument characteristics, including accuracy requirements, are -

equivalent to or better than those specified by the vendor.

j l

11.2.4 EVALUATION OF TEST RESULTS The documented test results, are evaluated. Lagainst the-l>

predetermined acceptance criteria by an individual or group having appropriate qualifications.- The acceptance status of the test is documented.

Deficiencies noted during the. evaluation are documented and dispositioned.in accordance Lwith approved procedures.

The evaluation of test results may also be delegated to other organizations. The evaluating organization is required to assure l

the use' of qualified personnel, evaluate the data against predetermined criteria and document the results of the evaluation l

- and acceptance status of the test.

NUSCO Quality Services l

performs audits, surveillances,' inspections, and-in process E

verifications to verify that these organizations are effectively complying with their quality assurance program requirements for test control, l

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V QAP 11.0 Rev.: 13 Date: Aug.29,1990-Page 3 of 3

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12.0 CONTROL OF MEASURING AND TESTING EOUIPMENT

-12.1 GENERAL REOUIREMENTS The NUQAP provides measures for the control of measuring and testing equipment (M&TE) used as the basis for acceptance in activities affecting quality during inspection, testing and measurement of materials, equipments j

and parts. - Periodic calibration and adjustment of measuring'and test equipment is performed and controlled to assure accuracy is maintained -

within limits necessary to verify that design and operating condition

~

requirements have been met. Documentation is retained such that all items

- of M&TE are traceable to their calibration records.

12.2 IMPLEMENTATION 12.2.1 Approved procedures delineate the methods and responsibilities y

for the control, maintenance and calibration of M&TE (including; j

l

__ portable and installed instmments, tools, gages, fixtures, c

reference and transfer standar'ds, and nondestructive test' equipment).

All documentation associated with M&TE is maintained in

-l appropriate files, with eventual incorporation into the.NU' Nuclear Records Organization.

During NUSCO directed activitie~s on a nuclear plant, with the j

exception of Generation Construction's directed activities, the calibration program is implemented in accordance with the requirements defined in~ NUSCO Procedures. NUSCO functional.

groups are responsible for implementing these procedures which

~

comply with the requirements contained in specifications and-drawings. ; NUSCO Quality Services Department is responsible

{

for verifying that receipt of calibrated equipment is in i

conformance with the requirements of procurement documents,.

q and to control calibrated M&TE used.during their inspections.

During NUPOC/ Generation Construction directed activities, the calibration program is implemented in accordance with the requirements defined in NUPOC Procedures. The Site / Plant Operations Review Committee (SORC/PORC) reviews and l

approves procedures related to the calibration program. Depart-ment heads / Job Supervisors are responsible to ensure that M&TE equipment is calibrated, issued, and controlled in 'accor-QAP - 12.0 Rev.: 13 Date: Aug.29,1990 1

Page 1 of 3

dance with the requirements of the procedures. ' During' Genera-

,-Q tion Constnaction directed activities, the Job Supervisor shall.. _

iV ensure that the users of the M&TE are properly instructed in the use and control of the M&TE. Department Heads are.

- t responsible for calibrating M&TE within the required frequency and for reviewing calibration data associated with M&TE calibration by outside vendors in accordance with the.

procedures.

NUSCO Quality Services performs audits, surveillances~,

inspections, and in process verifications to verify implementa-l tion of the calibration program.

~

- Any engineer-constructors, contractors, suppliers and engineering sewice organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance and, modification to eclear power plants are responsible for-4 implementing measures for the control of M&TE to ensure they r

---are properly calibrated, adjusted and maintained at specified intervals in order to maintain accuracy within required limits.

NUSCO Quality Servic'es performs on site and off site audits, surveillances, inspections, and in process verifications of the quality assurance programs of the engineer constructors, contractors, suppliers and engineering service organizations to L

verify they are effectively complying with their requirements for control of M&TE.

12.2.2 CALIBRATIOll_S_TANDARDS Measuring and test equipment is calibrated at specified intervals l

based on the required accuracy, purpose, degree of usage, 4

stability characteristics, and other conditions affecting the -

measurement. Measuring and test equipment shall be labeled or tagged to indicate the date' calibrated and next calibration date.

NUSCO/NUPOC Procedures describe the measures taken to assure that referene and transfer standards are traceable to

' nationally recognized rtandards and that, where national standards do not exist / provisions are established to document the basis for calibration.

' Calibration of this equipment should be against standards that c

p have accuracy of at least four times the required accuracy of the QAP - 12.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 3

i equipment being calibrated. When this is not possible, the f

standards shall have an accuracy that assures the equipment

(

being calibrated will be within required tolerance and the basis of acceptance is documented and authorized by the applicable manager of the functional group (for NUSCO-directed activities).

or the SORC/PORC (for NUPOC/ Generation Construction-directed activities). In addition, the calibrating standards shall'

- have greater accuracy than secondary standards being calibrated. - Calibrating standards with the same accuracy may be used if they can be shown to be adequate for the requirements and the basis of acceptance is documented and authorized by the applicable NUSCO manager of the functional:-

group or PORC / SORC.-

Implementing procedures describe the measures utilized in order.

to maintain the proficiency of the measuring and test equipment.

12.2.3.u ~ "OUT OF TOLERANCE" CONTROL M&TE and reference standards when found out of tolerance are so identified and removed from service. A review is' conducted i

?

l to determine the validity of previous inspection or test results gained through use of the instrument, and of the acceptability of items previously measured or tested, i

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' b.

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'h QAP 12.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 3 i

2

9 i:

13.0 HANDLING. STORAGE AND SHIPPING 13.1 GENERAL REOUIREMENTS Measures are established by the NUQAP using approved procedures, instructions and procurement documents to ensure proper handling, storage, shipping,-

cleaning and preservation of material, equipment and parts. These measures are -

imposed during the design, procurement, construction, testing and operation of nuclear power plants and modifications thereto, i. order to preclude damage, loss or deterioration'of materials, equipments and parts.

13.2 IMPLEMENTATION 13.2.1 GENERAL Procedures, instructions and procurement documents define the requirements and responsibilities for the handling, storage, shipment, cleaning and preservation of material, equipment, parts and required implementation of established design and specification requirements.

' Handling, storage, cleaning and preservation requirements of 1

material, equipment and parts is conducted in accordance with written procedures and procurement documents. Any engineer-constructors, suppliers, and engineering service organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance and modifications to nuclear power plants are responsible for implementing measures for handling, storage, shipping, cleaning and preserving materials equipment and parts to preclude damage, loss or deterioration.

NUSCO Quality Services performs audits, surveillances, inspections, and in-process verifications to verify that NUSCO/NUPOC, contractors, suppliers and engineering service organizations are effectively implementing and complying with the approved procedures and instructions for handling, storage, shipping, cleaning and preservation of materials, equipments and parts.

13.2.2 ESTABLISH MEN r OF SPECI AL H ANDLING. STORAGE. SHIPPING.

CLEANING AND PRESERVATION REOUIREMENTS Special or additional handling, storage, shipping, cleaning and preservation requirements are to be identified and implemented as specified in procurement documents and approved procedures.

QAP 13.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 2

~_

1 These established requirements are consistent with ~the regulatory positions of the is,'O Regulatory Guides'and their endorsed ANS!

Standards listed in Appendix D of the NUQAP Topical Report, or specifications and/or supplier technical manuals, and will be consistent with accepted industry standards.

NUPOC Procedures describe the measures taken for the storage of-chemicals, reagents (including control of shelflife), lubricants, and 1

other consumable materials.

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QAP - 13.0 i

Rev.: 13 i

Date: Aug.29,1990 l-Page 2 of 2 L

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14.0 INSPECTION. TEST AND OPERATING STATUS 14.1 GENERAL REOUIREMENTS The NUQAP. provides measures for indication, by the use of marking such as stamps, tags, labels or other suitable means, the status of tests and inspections of material, equipment 'and' parts' throughout design, construction, testing, operation,' maintenance and modification of nuclear power plants, to preclude the inadvenent bypassing ofinspection and test requirements. These measures provide for the identification of items which have satisfactodly passed required -

inspections and tests.. Measures are also established for indicating the operathig.

status of systems, structures and components.o prevent inadvertent operation.

14.2 IMPLEMENTATION 14.2.1 GENERAL

_. Any engineer constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance and modification to nuclear power plants are responsible for implementing approved O

measures for the identification of inspection and test status of matedal, equipment and parts to preclu& the bypassing of requirements. NUSCO Quality Services perfo. uf on site and off-site audits, surveillances, inspections, and in ptocess verifications of the engineer constructors, contractors, suppliers and engineering service organizations to verify that they are effectively complying with their requirements for identification of inspection and test status, in compliance with approved procedures and instructions.

Elements of this system require that suppliers and contractnrs have a controlled manufacturing and test operation, in order tc eclude:

I the inadvertent bypassing of process inspections or tes and to l

provide a positive identification of component status tl sughout L

all phases of manufacturing, testing, and inspection by means of l

tagging, routing cards, stamping, manufacturing or test reports, L

labeling or other appropriate methods.

. When Receipt Inspections are performed at the NU Nuclear:

Generating Facilities, NUSCO L Quality. Services ensures-that traceability is maintained of acceptable matedals, equipments and-parts, to. indicate conformance to Purchase Order / Contract i

requirements. Nonconforming materials, equipment and parts are identified in accordance with QAP 15.0.

p QAP - 14.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 2 l

y l

I During tests and inspections of operating nuclear power plants, a status tagging system is implemented, as per approved procedures and instructions, to prevent inadvertent operations of systems, structures and components.

i NUSCO/NUPOC Procedures describe the measures taken to control -

the altering of the sequence of required tests, inspections and 1

other operations taken by Generation Construction / Operations.

The review and approval for these actions is subject to the same i

control as taken during the original review and approval of tests,-'

inspections and other operations.

i 14.2.2 STATUS IDENTIFICATION AND CONTROL i

- Procedures and instructions describe control of the application and removal of markings such as stamps, tags, labels, and other suitable means to indicate _the status of systems, structures and components to prevent inadvertent operation, and to preclude

_. omission of inspections,' tests or other critical operations. These

~

procedures and instructions delineate the requirements, methods ~

and responsibilities for indicating the status of the affected items.

The complete status of all items under the calibration system is recorded and maintained, j

Records associated with status identification are maintained-in l

accordance with approved procedures.

3 O

QAP - 14.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 2

i J

15.0 NONCONFORMING MATERIALS. PARTS. COMPONENTS. OR SERVICES V

15.1 GENERAL REOUIREMENTS LThe NUQAP requires that documentation and control of nonconforniing

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materials, parts, components, or services utilized in systems, structures and components dudng design, construction, testing, operation and maintenance of

~

nuclear power plants and modifications thereto, be' performed in 'accordance l

with approved procedures in order to prevent inadvertent use or installation, These procedures include -appropriate requirements for identification, documentation, segregation and disposition of nonconforming items, and notification to affected organizations.

15.2 IMPLEMENTATION 15.2.1 PROGRAM Approved procedures define personnel responsibilities and establish various measures for identification, documentation, segregation, review and disposition of nonconforming item reports.

Report mechanisms are available to all NU personnel and utilized based on the scope of their departmental responsibilities and-O procedural guidance.

'15.2.2 DOCUMENTATION Documentation of nonconforming items requires identification of J

the items, description of the nonconformance,' disposition of the -

nonconformance, inspection requirements and signature approval

. of the disposition.

A trend ' analysis-of"nonconformances:

documenting program / procedural problems is performed by s

NUSCO Quality Services in accordance with approved procedures.

The trend analysis results are periodically reported to upper management, including the ' Senior Vice President, Nuclear Engineering and Operations, for review and assessment.

Tagging systems are utilized to physically identify nonconforming items. NUSCO QSD utilizes tags for received matedal, parts and -

components.

An engineering evaluation is performed, if necessary, prior to the resolution of nonconformances.

QAP - 15.0 Rev.: 13 Date: Aug.29,1990 l

Page 1 of 2

1 15.2.3 EVALUATION AND DISPOSITION

(

Evaluations are performed to determine the! disposition of i

nonconforming items.and services. The evaluation determines whether an item or service is to be used as is, returned to supplier, j

repaired, reworked, scrapped ar salvaged. These evaluations assure that the final condition does not adversely affect safety,'

'l l

L operation or maintenance of the item or.' service, or of the component or system. Reports involving deviation from design j

bases such as "use as is" or " repair" are forwarded to the l

appropriate engineering organir.ation for review, and disposition.

Applicable information is accumulated and records are maintained.

p The need to release /use ' nonconfonning materials, parts or -

components shall be based on such considerations as-1 a.

Impact on plant safety; b.

Safety of personnel; Suitability of material or items in the "as is" condition, i.e.,

c.

probability of eventual satisfactory resolution of the O

nonconformin'g without repair, rework or replacement.

V d.

Accessibility of material lor items after release; l

Cost of removal and repair or replacement should material i

e.

or items - eventually have. to. be removed, repaired, or replaced; L

f.

Effect on the orderly progress of work.

Items repaired are verified by reinspec+ing the items as originally inspected or by a documented meth.ad which is equivalent to the original inspection method.

items reworked may require reinspection as defined in apreoved procedures.

NUSCO Quality Services-performs audh arveillances and in-process verifications to verify that 4 position for reports documenting nonconforming conditions we adequate.

l

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L QAP - 15.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 2 1

16.0 CORRECTIVE ACTION O

16.1 GENERAL REOUIREMENTS The NUQAP requires that an effective corrective action program be established for NUSCO/NUPOC and their contractors / service organizations to ensure that conditions adverse to quality are promptly identified and corrected as soon as practicable, end documented in accordance with approved procedures. These procedures shall include measures for the documentation of the cause of the condition and action to preclude recurrence when the condition is evaluated as significan:.

16.2 IMPLEMENTATION 16.2.1 PROGRAM Approved procedures define personnel responsibilities and establish various measures for identification, documentation, review, engineering evaluation and disposition of conditions adverse to quality. Report mechanisms are available to all NU personnel and utilized based on the scope of their departmental responsibilities and procedural guidance.

16.2.2 CORRECTIVE ACTION AND FOLLOW-UP O

Procedures describe the measures taken to evaluate if conditions adverse to quality exist and to determine the need for immediate corrective action or disposition.

NUSCO Quality Services Department performs audits, surveillances shd in-process verifications to verify that NUSCO/NUPOC and their contractors / service organizations comply with the corrective action program and that corrective action is adequate and properly implemented in a timely manner. The Senior Vice President -

Nuclear Engineering and Operations has the final authority in the event that agreement on the action to be taken is not reached at lower levels for NUSCO/NUPOC.

16.2.3 RECURRENCE CONTROL The organization which is responsible for the condition adverse to quality, shall review the condition for significance.

When a significant condition is identified, the cause of the condition must also be identified along with actions to prevent recurrence. In QAP - 16.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 2

these cases, the immediate corrective action, the cause, and recurrence control actions must be documented.

Procedures establish the responsibilities and measures taken to accomplish these actions.

A trend analysis report which identifies program / procedural-

. problems is issued to appropriate levels of NU management. The -

NUSCO Director, Quality Services is responsible for follow up of the trend analysis items. Trends concerning specific contractor's performance shall be reported to the affected contractor for resolution and recurrence control, if appropriate.

O QAP - 16.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 2

1 t

1:

L 17.0 OUALITY ASSURANCE RECORDS 17.0 GENERAL REOUIREMENTS i

The NUQAP provides for the maintenance, identification, retention and retrieval of records to furnish evidence of activities affecting quality during design, construction, testing, operations, maintenance and modification of nuclear power l

plants. The records include but are not limited to: operating logs and the results of reviews, inspections, tests, audits, monitoring of work performance'and material analyses.

The records also include closely related data such as qualifications of personnel, procedures and equipments. Inspection and test records contain as a minimum but are not limited to: identification ofinspector or data recorder and the acceptability and the action taken in connection with any deficiencies and Reportable Occurrences noted.

Approved procedures establish requirements concerning record retention such as duration, location' and assigned responsibility, i

17.2 IMPLEMENTATILN NUSCO/NUPOC Procedures and Instructions establish the responsibilities and -

requirements for the maintenance, identification, retention and retrievability of O

records pertaining to materials, equipments, parts, processes or operations relating to systems, structures and components. which when founded on observations, measurements or tests can be fully verified, and documented by cognizant personnel.

l Any enginnr constructors, contractors, suppliers' and engineering service organizations utilized by NUSCO/NUPOC in the desi n, construction, testing, F

operation, maintenance and modification to nuclear power plants are responsible to implement measures for identification, maintenance, retention, retrieval and.

turnover to the NUSCO/NUPOC personnel of documented and approved records which contain objective' evidence of quality, as specified in Purchase Order /-

Contracts.

NUSCO Quality Services performs on site -and off site' audits, surveillances, inspections, and in process verificationsi of the engineer-constructors, contractors, suppliers and engineering service organizations, as' appropriate, to vedfy they are effectively complying with their progtam for quality assurance records.

NUSCO/NUPOC records are identified, controlled and maintained in appropriate

?

files and are identifiable to specific systems, structures and components within l

the nuclear power plant. When identification to a specific system, structure or component is not practical, records are filed by category (e.g. specification, nonconformance reports, audits, etc).

Rev.: 13 Date: Aug.29,1990 Page 1 of 2

~.-

H i

17.3 RETENTION A

NU quality assurance records are classified as life records or nonlife records as I

delineated by Generation Facilities Records.

Nonlife records are those documents that are maintained for a specific period of time other than the lifetime of the in service nuclear power plant or the particular component or-part. Life records are those documents that are maintained for the lifetime of the in-service nuclear power plant or for the life of the particular component or part. Life records are those which would be of significant value in meeting one 1

or more of the following criteria:-

Demonstrating capability for safe operations; a.

b.

Maintaining, reworking, repairing, replacing or modifying the item; Determining the cause of an accident or malfunction of an itemi c.

d.

Providing required base line data for in service inspection.

RecordsIr$ riviewed and approved by the cognizant quailfiad personnel of

~

NUSCO/NUPOC, engineer constructor, etc., as appropriate, and are transmitted to the appropriate Nuclear Plant Records Facility. The responsibility of the O

appropriate Nuclear Plant Records Facility upon receipt of records, is to maintain and provide controlled retrievability of records affecting nuclear power plants, in such a manner as to prevent destruction of records by fire, flood, theft, and environmental conditions, such as temperature or humidity, as delineated in!

procedures.

l l

l:

QAP - 17.0 Rev.: 13 Date: Aug.29,1990 Page'2 of 2

18.0 AUDITS i

IP GENERAL REOUIREMENTS Se NUQAP requires that measures be pr avided to implement an effective audit pror., ram. These measures are applied during the design, construction, testing and operation of nuclear power plants and modifications thereto, through the performance of-audits.

Audits, surveillances, inspections, and in. process' verifications are conducted in accordance with preestablished procedures and written checklists by qualified personnel not having direct responsibilities in the-areas being reviewed to ensure compliance with the NUQAP Topical Report.

The results of audit, surveillance, inspection, and in. process verification findings -

are documented and then reviewed with management having responsibility in the area audited.

-i 18.2 IMPLEMENTATION 18.2.1_,

PROGRAM The NUSCO Audit program requires audits,- surveillances, and in.

l process verifications of corporate and plant quality activities.

O-Audits, surveillances, and in process verifications are scheduled on the basis of the status and safetyimportance of the activities being

-performed. Schedules are originated and maintained by NUSCO Quality Services Department.

In addition, provisions are established to require that audits be l

performed of those activities where the requirements of Appendix j

B to 10 CFR, Part 50, are being implemented and associated with:

l a.'

The determination of site features which affect plant safety (e.g., core sampling, site and foundation preparation);

b.

The preparation, review, approval and control of procurements; I

c.

Indoctrination and training prcgrams; d.

Interface control among the licensee and the principal contractors.

QAP 18.0 Rev.: 13 Date: Aug.29,1990 Page 1 of 3

e l

Measures are provided to perform audits of the following g

operations activities:

t

\\

Operation, maintenance, and modifications; a.

1 i

b.

The preparation, review, approval and control of design documents, specifications, procurement - documents, instructions, procedures and drawings; c.

Receiving and plant inspections; d.

Indoctrination and training programs; The implementation of operating and test procedures; e.

f.

Calibration of measuring and test equipment.

Audits are performed as specified in procedures by qualified personnel using a preestablished written audit plan prepared by the auditing organization. Auditors evaluate the work areas, activities, processes, items; review -documents and records-to determine the effectiveness ofimplementation and conformance to the NUQAP.

. Any engineer constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC in the design, construction, testing, operation, maintenance, and' modification to nuclear power plants ~

- responsible for developing and' are implementing a system of planned and periodic audits to verify compliance with the effectiveness of all aspects.of their quality assurance programs including reporting and resolution of deficien.

cies. NUSCO Quality Services personnel perform on-site and off -

site audits, surveillances, inspections, and in process verifications to ensure these organizations are effectively complying with their j

quality assurance requirements for audits.

Departments with the NUSCO/NUPOC organizations are.

responsible for implementing their functions in accordance with approved procedures. and - instructions.

Internal' audits are performed to verify.nplementation of the requirements prescribed j

in the NUQAP To cal Report and implementing departmental r

procedures.

[

1

\\

QAP 18.0 Rev.: 13 Date: Aug.29,1990 Page 2 of 3 i

18.2.2 REVIEW OF AUDIT FINDINGS Audit results are documented,= reviewed, and analyzed with' management having responsibility in the area audited.

The responsible management is required to take the necessary action to correct the deficiencies identified by the audit.

i 18.2.3

' REPORTING OF ' AUDIT RESULTS

[

Audit results are reviewed and approved by the NUSCO Quality Services' Department in accordance with approved procedures.

Based on the audit documentation, the audit reports are issued to the appropriate management of the area audited to ensure timely -

corrective action is taken to rectify deficiencies. In addition, audit data and reports are accumulated as part of the review for quality trends and to assess the effectiveness of the quality assurance i

program. This report is then submitted to the Director, Quality

.l Senices.

18.2d IkEEidLUTION OF AUDIT DEFICIENCIES Appropriate action to resolve deficiencies identified during audits O

is to be taken by the cognizant engineer-constructor, contractor, supplier, engineering service - organization or. NUSCO/NUPOC i

before the scheduled resolution date.

Follow.up audits are performed as necessary to verify appropriate actions'have been -

1 taken to resolve deficiencies. Items which exceed the scheduled resolution date and cannot be resolved by, affected management are submitted for resolution to the Senior Vice President Nuclear Engineering and Operations.

i 18.2.5-RECORDS / REPORTS OF AUDITS-i Audit records, reports and associated documentation pertinent to audits are maintained in the appropriate NUSCO files with g

disposition to the appropriate Nuclear Plant Records Facility, as specified in procedures.

QAP - 18.0 Rev.: 13 Date: Aug.29,1990 Page 3 of 3

i 1

APPENDIX A CATEGORY I SYSTEMS. STRUCTURES. AND COMPONENTS The following systems, structures and components of a nuclear power plant, including their foundations and supports, are designated as Category 1. The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50, should be applied, as a minimum, to all quality activities affecting the safety function of these systems, structuras, and components as listed below and to other items and servict specifically identified by NU in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide 1.70.

(a)

The reactor coolant pressure boundary.

(b)

The reactor core and reactor vessel internals.

(c)

Systems or portions of systems that are required for (1) emergency core cooling; (2) post-accident containment heat removal or; (3) post accident containment atmosphere cleanup (e.g., hydrogen removal system),

(d)

Systems or portions of systems that are required for (1) reactor shutdown; (2) residual heat removal or; (3) cooling the spent fuel storage pool.

(c)

Those portions of the steam systems of boiling water reactors extending from the outermost containment isolation up to but not including the turbine stop valve, and connected piping of 21/2 inches or larger nominal pipe size up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.

(f)

Those portions of the steam and feedwater systems of pressurized water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves, and connected piping of 21/2 inches or larger nominal pipe size up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.

(g)

Cooling water, component cooling and auxiliary feedwater systems or por: ions of these systems including the intake structures, that are required for:

(1) emergency core cooling; (2) post accident containment heat removal; (3) post-accident containment atmosphere cleanup; (4) residual heat rerhoval from the reactor or; (5) cooling the spent fuel storage pool.

QAP - Appendix 4 Rev.: 13 Date: Aug.29,1990 Page 1 of 3

(h)

Cooling water and seal water systems or portions of these systems that are required for functioning of reactor coolant systen. components important to safety, such as reactor coolant pumps.

(i)

Systems or portions of systems that are required to supply fuel for emergency equipment.

(j)

All electrical and mechanical devices and circuitry between the process and the actuated devices invoked in generating or responding to signals that provide-protective functions of safeguard systems.

(k)

Systems or portions of systems that are required for (1) monitoring of systems safety related and; (2) actuation of systems safety related, i

" Required for monitoring,"i.e. Those parameters that provide information that is essential to permit the control room operator to take specific manually controlled actions for the direct accomplishment of the specified safety function.

(1)

The spent fuel storage pool structure, including the fuel racks.

1 (m)

The reactivity control system (e.g., control rods, control rod drives, and. boron j

injection system),

(n)

The control room, including its associated equipment and all equipment needed to maintain the control room with safe habitability limits for persc;.nel and safe environmental limits for vital equipment.

(o)

Primary and secondary reactor containment.

(p)

Systems other than radioactive waste management systems not covered by items i

(a) through (o) above which contain or may contain radioactive materials and whose postulated failure would result in conservatively calculated potential offsite doses (using meteorology as prescribed by Regulatory Guides 1.3 and 1.4) which are more than 0.5 rem to the whole body or its equivalent to any pt ; of the body.

i (q)

The Class IE electric systems, including the auxiliary systems for the orua electric power supplies, that provide the emergency electric power needed for-functioning of plant features included in items (a) through (p) above, u

(r)

Those portions of systems, structures or components whose continued ftmetion is not required but whose failure could reduce the functioning of any plant feature included in items (a) through (q) above to an unacceptable safety level QAP - Appendix A Rev.: 13 Date: Aug.29,1990 Page 2 of 3

j or could result in incapacitating injury to occupants of the control room should

[

be designed and constnieted so that the SSE would not e luse such failurec.

(s)

Items and services associated with Radioactive Material hasport Packages as described in 10CFR71.

CONSUMABLES The following specific consumables when utilized in safety related systems shall be included in those portions of the NUQAP, as applicable.

1.

Emergency generator diesel fuels 2.

Hydraulle snubber fluids 3.

Reagents.

4.

Resins

{

5.

Boric Acid c

6.

Lubricants 7.

Gas Turbine Fuel 4

h 5

l O

QAP Appendix A l

Rev.: 13 Date: Aug.29,1990 Page 3 of 3 1L - -

j 4

APPENDIK,B

)

(h

(

/

htQRTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT 4

OUALIFICATION AND EXPERfENCE REOUIREMEicS NUSCO DIRECTOR. OUALITY SERVICES I

The NUSCO Director, Quality Services shall sansfy the following requirements:

4 Graduate of a four year accredited engineering or science college or university, plus fifteen (15) or more years of hdastrial experience including five years in positions of leadership, such as lead engineer, project engineer, audit team leader, etc. At least two years of this experience should be associated with nuclear Quality Assurance Activities, and at least one year of this experience is in a Quality., Assurance Organization. A masters degree in engineering or business management is considered equivalent to two years of experience.

O' Not!" 'he education and experience requirements should not be treated as absolute when similar training or an outstanding record will provide res k nable assurance that a person can perform the required tasks.

I i

q QAp - Appendix B Rev.t 13 Date: Aug.29,1990 Page 1 of 1 r.

APPENDIX C NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT LIST OF TYPICAL OUALITY ASSURANCE RELATED PROCEDURES INDEX PAGES NUSCO QUALITY SERVICES DEPARTMENT 23 NUCLEAR ENGINEERING AND OPERATIONS POLICY AND 47 PROCEDURES MANUAL NUSCO GENERATION ENGINEERING AND CONSTRUCTION 89 DMSION PROCEDURES MANUAL NUCLEAR PLANT RECORDS MANUAL 10 13 INFORMATION RESOURCES PROCEDURES 14 NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES IS MILLSTONE QA AJMINISTRATIVE CONTROL PROCEDURES 16 22 CONNECTICUT YANKEE QA PROCEDURES 23 27 NORTHEAST UTILITIES WELDING MANUAL 28 l

NU PURCHASING BUSINESS PROCEDURES 29 l

NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 30 REACTOR ENGINEERING BRANCH PROCEDURES 31 32 l

GENERATION FACILITIES LICENSING BRANCH PROCEDURES 33 NUCLEAR ENGINEERING AND OPERATIONS 34 g

QUALITY SOFTWARE PROCEDURES ON QAP - Appendix C Rev.: 13 L

Date: Aug.29,1990-L Page 1 of 34' l

l

~

NUSCO QUALITY SERVICES DEPARTMENT PROCEDURES O

10 CFR 50, APP. B CRITERIA QSD - PROCEDURES

!!. Quality Assurance QSD 1.08 Quality Services Depart-Program ment Indoctrination and Training Program QSD 2.01 Preparstion,

Issuance, and Control of the Northeast Utilities Quality Assurance Program Topical Report QSD 2.04 Training and Qualification of Lead Auditors

~

QSD 2.07 Selection, Training, Qualification and Certification cf Non NDE Inspection andTesting Personnel IV. Procu.ement Documerat QSD 3.01 Procurement Document Control Review QSD 3.04 Performance of Commercial Grade Periodic Sgrveys V.

Procedures, Instructions, QSD 1.02 Quality Services and Drawings Department Procedures VI. Document Control QSD 1.10 Control of Correspondence Vil. Control of Purchased QSD 3,02 Supplier Evaluations Material, Equipment, and Services QSD 3.03 Review and Approval of Supplier QA Programs

]

QSD 3,05 Issuance and Control of the Approved Suppliers List QAP Appendix C Rev.:~ 13 Date: Aug.29,1990 Page 2 of 34

NUSCO QUALITY SERVICES DEPARTMENT PROCEDURES 10 CFR 50, APP. B CRITERIA QSD - PROCEDURES IX. Control of Special QSD 2.07 Selection, Training, Processes Qualification and Certification of Nondestructioil Examination Personnel X,

inspection QSD 2.03 Performance, Reporting and Follow up of Surveillance Actisities QSD 4.02 Performance and Reporting of Inspection and Inspectbn Surveillance Activities XV. Nonconforming Materials, QSD 1.06 Procedure to Stop Work O

Parts, or Components, or Services XVII. Quality Assurance QSD 1.04 Retention, Turnover, Records and Transmittal of Quality Service Department i

Records for Permanent Storage XVI!!. Audits QSD 1.07 Computer Tracking Programs 1

QSD 2.02 Performance, Reporting, and Follow up of Assessnent and Staff Services and Assessment Services Audits

]

QSD 2.09 Performance, Reporting, and Follow up of in Process Verifications QSD 2.10 Joint Vendor Audits I

l

. QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 3 of 34

NUCLEAR ENGINEERING AND OPERATIONS 1

i POLICIES AND PROCEDURES MANUAL V

10 CFR 50, APP. B CRITERIA NEO - PROCEDURES 4

i I.

Organization NEO i.01 Organization of the Nuclear Engineering and Operations Group j

NEO 2.02 Charter for Nuclear Review Boards i

II. Quality Assurance NEO 1.02 The Nuclear Engineering Program and Operations Policies and Procedure Manual i

NEO 2.08 Management Review of the Northeast Utilities Quality Assurance Program NEO 2.14 Nuclear Plant Fire. Protection Program NEO 2.24 NEO for Quality Software Program NEO 2.26 Departmental Training 4

NEO 3.08 Processing Proposed Revisions to the Northeast Utilities Quality Assurance Program NUQAP Topical Report

!!!. Design Control NEO 3.03 Preparation, Review and Disposition of Plant Design Change Records (PDCRs) 1 NEO 3.12 Safety Evaluations NEO 5.04 Engineering Specifications O

V QAP Appendix C Rev.: 13 Date: Aug.29,1990 l

Page 4 of 34

f NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL 10 CFR 50, APP. B CRITERIA NEO PROCEDURES NEO 5.05 Design

Inputs, Design Verifications, and Desig:

Interface Reviews NEO 5.06 Preparation, Review and Approval of Design Analyses and Calculations NEO 5.11 Design Change Notices for Design Documents NEO 5.12 Performance of Fire Protection Reviews NEO 6.01 Material, Equipment, and Parts k

Lists for In Service Nuclear Generation Facilities IV. Procurement Document NEO 6.02 Preparation and Review Control of Quality Related Purchase Requsitions NEO 6.04 Preparation and Review of Proposals NEO 6.11 'rocessing, Dedication, Upgrading and Utilization of Commercial Grade Items V.

Procedures, Instruc-NEO 1.04 Preparation, Revision, tions, and Drawings Issuance, Delet.an, and Control of NEO Procedures NEO 3.10 Revisions and Changes to In-service Inspection Program O

QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 5 of 34

NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL O

V 10 CFR 50, APP. B CRITERIA NEO PROCEDURES P

Y VI. Document Control NEO 4.01 Communications with the i

Nuclear Regulatory Commission NEO 4.02 ProposedTechnicalSpecification Change Requests and Emergency Waiver Requests NEO-4.03 Changes and Updates to Final Safety Analysis Reports for Operating Nuclear Power Plants NEO 4.04 Review and Approval of Proposed Changes to Selected License Requirements NEO 5.03 Controlled Distribution and Transmittal of Design Documents l

VII. Control of Purchased NEO 6.03 Transfer of Materials, Material, Equipment, Equipment, and Parts and Services

~

NEO 6.05 Processing and Control of Purchased Material, Equipment, Parts, and Services NEO-6.11 Processing, Dedication, Upgrading, and Utilization of Commercial Grade Items IX. Control of Special NEO 3.11 Nondestructive Examination Processes Procedures l

QAP Appendix C Rev.: 13.

Date: Aug.29,1990 Page 6 of 34 r

NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL i

10 CFR 50, AP?. B CRITERIA NEO - PROCEDURES X.

Inspection NEO 2.07 Management of In Service Inspection Programs XI. Test Control NEO 7.04 Administration of Plant Design Change Turnover and 1

Preoperational Testing XV. Nonconforming NEO 2.01 !mplementation of the Materials, Parts, 10 CFR 21: Reporting of Components, or Defects and Noncompliances

]

Services -

XVI. Corrective Action NEO 2.11 Trend Analysis from Quality Related Documents NEO 2,18 Corrective Action Requests 4

NEO 3.05 Nonconformance Reports NEO 3.07 Response to Audit Findings XVII.

Quality Assurance Records NEO 2.10 S a f e g u a r din g Supp1ier Proprietary Material NEO 2,12 Control of Nuclear Facilities Safeguard Infonnation NEO 2,13 Nuclear Plant Records Program XVIII. Audits NEO 3.01 Conduct and Format of Nuclear Review Board Audits l

QAP - Appendix C l

Rev.: 13-Date: Aug.29,1990 Page 7 of 34 L

1 l

NUCLEAR ENGINEERING AND OPERATIONS l

POLICIES AND PROCEDURES MANUAL I

m lU l

10 CFR S0, APP. B CRITERIA NEO PROCEDURES i

1.

Organization NEO/QS S Interface Pltns for Quality Software II. Quality Assurance NEO/QS 3 QualityRequirementsforQuality i

Software NEO/QS 12 Additional Requirements for Category I Software III. Design Control NEO/QS 4 Software Requirements for

- --- - ~~

Quality Software

)

NEO/QS 8 Installation and Modification of Quality Software O.

V.

Procedures, Instructions, NEO/QS 1 Preparation, Issuance, and Drawings and Control of the NEO/QS Procedures and hfanual XI. Test Control NEO/QS 9 Validation and Verification of Quality XV. Nonconforming NEO/QS 11 Error Reporting and Corrective Materials, Parts, Action for Quality Software Components, or Services XVI. Corrective Action NEO/QS 11 Error Reporting and Corrective Action for Qualify Software XVII. Quality Assurance Records NEO/QS 10 Backup and Storage of of Quality Software-O QAP Appendix C f

Rev.: 13 Date: Aug.29,1990 Page 8 of 54

NUSCO GENERATION ENGINEERING AND CONSTAUCTION DIVISION PROCEDURES MANUAL, C

(

l 10 CFR 50, APP. B CRITERIA GE&C PROCEDURES 1.

Organization GE&C 1.01 Generation Engineering and Constniction Division II. Quality Assurance GE&C 1.02 Applicability and Use Program of Generation Engineering and Construction Procedures Manual GE&C 1.03 Procedure for Review of Generation Engineering and Construction Division Procedures as Required by Revisions to NUQAP Topical Report O

GE&C 1.05 Generation Engineering and ConstructionTraining Program III. Design Control GE&C 2.01 Preparation, Review, Approval,

Revision, and Control of NUSCO Generation Engineering and. Construction Division Specifications GE&C-4.02 Review of Engineering Service.

Organization,

Supplier, Engineer Constructor, and Contractor Design Documents GE&C 4.06 Materials List IV. Procurement Document GE&C 2.06 Purchase of Materials Control List Equipment fb QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 9 of 34

I NUSCO GENERATION ENGINEERING AND CONSTRUCTION t

DIVISION PROCEDURES MANUAL l

f t'

10 CFR SO, APP. B CRITERIA GE&C PROCEDURES r

GE&C 4.09 CommercialGradeProcurement V.

Procedures, Instructions, GE&C 1.04 Preparation, Issuance and Drawirqs and Control of Generation Engineering and Construction Division Procedures GE&C 3,01 Design Information GE&C 3.05 Preparation and Control of Design Drawings VI. Document Control GE&C 3.04 Design Document Summary Log O

VII. Control of Purchased GE&C 2.02 Review of Proposals Material, Equipment, Submitted by Engineer-and Services ing Service Organizations, Suppliers, Vendors and Contractors IX. Control of Special GE&C 5.03 Control of Special Processes Processes XV. Nonconforming Materials, GE&C 5.05 Issuance of a Stop Work Parts or Components or Order Services GE&C 5.07 Processing Nonconformance Reports XVII. Quality Assurance GE&C 2.05 Retention, Control and Records Final Disposition of Project Document Files for Betterment Projects f

\\-

QAP Appendix C Rev.: 13 Date: Aug.29,1990 l

Page 10 of 34 l

NUCLEAR PLANT RECORDS MANUAL 10 CFR 50, APP. B CRITERIA NPRM - PROCEDURES r

I.

Organization NPRM 1.07 Generation Facilities Records Branch and Responsibilities II. Quality Assurance NPRM 6.01 Training Requirements Program V.

Procedures, Instru:tions, NPRM 1.02 Issuing of the Nuclear and Drawings Plant Records Manual NPRM 1.04 Preparation of Nuclear Plant Records Manual VI. Document Control NPRM 1.03 Document Review and Acknowledgement O

NPRM 2.02 Maintaining Nuclear Plant Records Vendor and Manufacturer File NPRM 2.04 Indexing Quality Checks NPRM 3,01 NUSCO Generation Facilities l

Records Branch's Functions in Implementing the Generation Records Information Tracking System (GRITS)

NPRM 3,06 Request for Nuclear Plant Drawing or Aperture Card Copies NPRM 3,09 Maintenance of Backup Reports for the Generation Records Information Tracting System (GRITS)

O' QAP Appendix C' Rev.: 13 Date: Aug.29,1990 l

Page 11 of 34 l

1

NUCLEAR PLANT RECORDS MANUAL q

l 10 CFR 50, APP. B CRITERIA NPRM PROCEDURES XVII. Quality Assurance NPRM 1.05 Establishing Submittal Records Schedules for Transfer of QA Records Into Nuclear Plant Records Facilities NPRM 1.06 Nuclear Power Plant Quality Assurance Records Generated, Collected and/or Transmitted by External Organizations NPRM-1.08 Retention and Conrol of Quality Assurance Records Generated in Support of the Nuclear Plant Records System NPRM 2.01 16MM Roll Film Microfilming Procedure NPRM 2.05 Inspection of Permanent Storage Vaults for Temperature, Humidity and General Condition i

NPRM.2.06 D o c u m e n t of Record Inspection / Inventory l

NPRM 2.07 Storage of Documents of Record l

NPRM 3,08 35MM Apperature Card l

l Microfilming Procedure NPRM-4.01 Housecleaning Guidelines for Records l

O QAP - Appendix C Rev.: 13 Date: Aug.29,1990 l

Page 12 of 34

NUCLEAR PLANT RECORDS MANUAL

(

10 CFR 50, APP. B CRITERIA NPRM PROCEDURES 11PRM 4.02 Transmittal and Receipt

)

NPRM 4.03 Access to Nuclear Plant Records Facilities and Records NPRM-4.04 Disposition of Nuclear Plant Records NPRM 4.05 Checklist of Required Nuclear Power Plant Records Including Quality Assurance Records

{

NPRM 4.06 Descriptions of Nuclear Plant Records Storage Vault O

~

NPRM 4.07 Guide for Writing Implements and Paper Stock to be Used for Documents Intended for Microfilming NPRM 4.08 Proptietary / ConfidentialReconi Control NPRM 4.09 Assignment of Source Record Storage Locations to Nuclear Records NPR Computer File Entries NPRM 5.01 Nuclear Records System Description NPRM-5.02 NPR/GRITSComputerProgram DictionaryandValidationTable Maintenance i

(

QAP - Appei. 'ix C Rev.: 13 i

Date: Aug. L' 1990 Page 13 of 34 J

l v

w

1 NUCLEAR PLANT RECORDS MANUAL a

t 10 CFR 50, APP. B CRITERIA NPRM PROCEDURES NPRM 5.03 NPR/ GRITS Computer File Integrity Verification NPRM 5.04 Indexing Requirements l

NPRM 5.05 Standard Indexing Guidelines (SIGS)

NPRM 6.01 Training Requirements l

NPRM 602 GFR Training Implementation and Record Keeping O

A 1

j l

QAP Appendix C l

Rev.: 13 Date: Aug.29,1990 Page 14 of 34

INFORMATION RESOURCES PROCEDURES 10 CFR 50, APP. B CRITERIA IR PROCEDURES 1

I.

Organization IR 1.01 Organization of the Information Resource Group

!!, Quality Assurance IR 2.01 QA Indoctrination and Program Training Ill. Design Control IR 3.07 QA Requirements for Quality Related Computer Software IV. Procurement Document IR 1.04 Request for Computer Control Services and/or Equipment Acquisition V.

Procedures, Instructions, IR1.02 Format and Content of and Drawings IR Procedures IR 1.03 Preparation,

Issuance, and Controls of Information Resources Procedures VI. Document Control IR 1.05 Maintenance, Control and Distribution of the Quality Related Software List IR 3,02 Allocation, Removal, Access, and Control of Quality Related Software - Stored on Magnetic Media in the IR Offsite Magnetic Media Vault IR 3.04 IR Offsit! Magnetic Media Yault XVill. Audits IR 3.01 Resolution of Audit Findings O

QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 15 of 34

NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES b) 10 CFR 50, APP. B l

CRITERIA NOD PROCEDURES I.

Organization NOD 1.01 Organization III. Design Control NOD 3.03 Safety Evaluations for Station Procedures NOD 3.05 Plant Design Change Records (PDCR) Evaluation V.

Procedures, NOD 1.02 Preparation, Issuance, Instructions, and Control of Depart-and Drawings ment Procedures NOD 1.03 DistributionandAccountablility of Department Procedures VI. Document Control NOD 1.04 Distribution of Design Documents XIV. Inspection, Test and NOD 3.04 Jumper, Lifted Lead, Operating Status and Bypass Control XVII. Quality Assurance NOD-1.05 Quality Assurance Records Records i

l V

QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 16 of 34

r L

MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS) i OO l

10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS) 1.

Organization ACP-QA 1.01 Millstone Administration ACP-QA 1.02 Organization Responsibilities ACP-QA 1.04 Plant Operations Review Committee ACP-QA 1.05 Site Operations Review Committee II. Quality Assurance ACP-QA 1.06 Quality Assurance /

Program Quality Control Program ACP -QA 1.10 Fire Protection Quality Assurance Program Boundary ACP-QA 2.01 -

QA Program Boundary 1

ACP-Q A 2.01 A Radioactive Material and Waste Packaging, Shipping, and Processing

- QualityAssurance Program ACP-QA 2.02C Work Orders 1

ACP-QA 2.05 Fire Protection Program ACP-QA 2.16 N u c1e a r P1 ant Environmental Qualification Program (NEO 2.21) n f

(V) i

- QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 17 of 34

MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)

/

10 CFR 50, APP. B CIUTERIA MILLSTONE QA (ACPS)

ACP-QA 8.07 QA Tre! ring Program ACP-QA 8.16 Tralr.ing, Certification, &

IndentificationofQualified Inspection and Testing Personnel 111. Design Control ACP-QA 2.13A Computer Softwarc Implementation ACP-QA 2.13B Maintenance and Control of Site Computer Systems ACP-QA 2.17 Setpoint Change Control ACP-QA 3.08 Safety Evaluation (NEO 3.12)

ACP-QA 3.09 -

Preparation, Issuance, and Control of Proj ect Assignments l

l ACP-QA 3,10 Preparation, Review, and l

Disposition of Plant Design Change Records (PDCRs) 1 (NEO 3.03) l l

ACP-QA 3.11 Preparation,

Review, Approval, Revision, and i

Control of Specifications (NEO 5.04)

QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 18 of 34

L MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES t

(ACPS)

O 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS)

\\

~

ACP-QA 3.12 Design

inputs, Design Verifications, and Design Interface Reviews (NEO 5.05)

ACP-QA 3.13 Preparation, Review, and Approval of Design i

Analyses and Calculations (NEO 5.06)

~-

ACP-QA 3.14 Design Change Notices for 1

Design D o c urr e n t s

' (NEO b.21)

O ACP-QA 3.15 Performance of Fire Protection Reviews (NEO 5.12)

ACP-QA 3.26 PDCR Evaluation (NOD 3.05)

IV. Procurement Docume, ACP-QA 4.020 Preparation and Review of Control Purchase Requisitions ACO-QA 4.03A Upgrading Spare Parts for Use in QA Application -

Commercial Grade item Procurement and Dedication V.

Procedures, Instructions ACP-QA 3.05 Review & Approval and Drawings Vendor Procedures t'

QAP - Appendix C.

Rev.: 13 Date: Aug.29,1990 Page 19 of 34 J

l MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)

O 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS)

ACP-QA 3.07 Maintenance of Station Implementing Procedures in Accordance With l

NUSCO Governing Documents VI. Document Control ACP-QA 3.01 ACPs & Station Forms i

ACP-QA 3.02 Station Procedures and Forms

)

ACP-QA 3.03 Document Control

]

ACP-QA 3.19 Controlled Distribution and Transmittal of Design Documents (NEO S.03)

ACP-QA 3.23 Control %f Vendor Technical Material ACP-QA 3.24 Drawing Change /

Submittal Request (NEO 5.09)

VII. Control of Purchased ACP-QA 4.05 Product Acceptance Material, Equipment Inspection &

Senices Testing ACP-QA 4.02B Receipt, Control and Identification of QA Material QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Fage 20 of 34

MILif-!ONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS) 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS)

I VIII. Identification ACP-QA 4.03B Material, Equipment, and and Control of Part Lists for In. Service Materials, Parts Nuclear Generating and Components Facilities (NEO 6.01)

ACP-QA 4.07 Control of Weld Material IX. Control of ACP-QA 2.03A Non Category 1 Special Processes Welding ACP-QA 2.07 Control of Special Processess X.

Inspections ACP-QA 9.06 Revision and Changes to In Service Inspection Program Manuals (NEO 3.10)

ACP-QA 9.07C Quality Services Surveillance Program XI. Test Control ACP-QA 2.02B Retests ACP-QA 2.21 Administration of Plant j

Design Change Turnover and Freoperational Test ACP-QA 9.02 Station Surveillance Program ACP-QA 9.02A Surveillance Master, Test Control List ACP-QA 9.02B Unit 2 Surveillance Master Test Control List i

\\

QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 21 of 34

MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS) i j

N 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS)

)

I I

ACP-QA 9.02C Unit 3 Surveillance Master l

Test Control List ACP-QA 9.03 In Service Plant Testing XII. Control of ACP-QA 9.04 Control & Calibration i

Measuring and of Measuring and Test Equipment Test Equipment J

XIII. Handling, Storage, ACP.-QA 4.01 Plant Housekeeping Sidpping ACP-QA 4.01 A System and Component Housekeeping 4

ACP-QA 4.04 Instructions for Packaging,

Shipping, Receiving, Storage and Handling ACP-QA 6.04 Radioactive Material Shipping Requirements XIV. Inspection, Test ACP-QA 2.06A Station Tagging and Operating Status ACP-QA 2.06B Station Bypass / Jumper Control (NOD 3.04))

ACP-QA 2.06C Station Bypass / Jumper Control for Troubleshooting, Redlining and Calibration ACP-QA 2.12 System Valve Alignment Control XV. Nonconforming Materials, ACP-QA 5.01 Nonconforming O

QAP Appendix C Rev.: 13 Date: Aug.29,199^

l Page 22 of 34 l

MILLSTONE QA ADMINISTRAT!VE CONTROL PROCEDURES (ACPS) 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS) r i

Parts, Components, or Materials and Parts Services XVI. Corrective Action ACP-QA 5.02 Trend Analysis from Quality Related Documents (NEO 2.11)

ACP-QA 10.01 Plant Incident Report

i ACP-QA 10.06 NRC Commitment Follow.

up Program ACP.QA 10.09 Licensee Event Report ACP-QA 10.10 Corrective Action Request (NEO 2.18)

XVII. Quality Assurance ACP-QA 10.04 Nuclear Power Plant Records Records XVIII. Audits ACP.QA 9.01 Quality Assurance Audits 1

1 QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 23 of 34 l

~

CONNECTICUT YANKEE QA PROCEDURES i

10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA PROCEDURES Organization ACP 1.0 3 The Connecticut Yankee i

Organization Responsibility and Authority i

ACP 1.21.1 Plant Operation Review Committee

11. Quality Assurance ACP 1.2 2.1 Material, Equipment Program and Parts List for CY ACP 1.2 2.3 C e'r t i fi e a t i o n and Identification of Qualified Testing Personnel ACP 1.2 2.4 Housekeeping and Foreign Material Exclusion Control Requirements ACP 1,2 2.8 NEO 6.10, Use of the PMMS Data Base to Indicate Quality Assurance or Special Program Applicability (NEO 6.10)

ACP 1.2 2.9 RadwasteQualityAssurance Program (NEO 6.07)

III. Design Control ACP 1.2 3.1 NEO 3.03, Preparation, Review and Disposition of Plant Design Change Request (PDCRs)

ACP 1.2 3.3 Setpoint Change Reg '.est i

(SCR)

QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 24 of 34

CONNECTICUT YANKEE QA PROCEDURES 10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA PROCEDURES ACP 1.2 3.4 NEO 5.04, Preparation, Review, Approval, Revision and Control of Specifications ACP 1.2 3.6 NOD 3.05, PDCR Evaluations ACP 1.2 6.9 NEO 3.12, Safety Evalua,tions ACP 1,2 6.12 Safety Evaluations for Station Procedures (NOD 3.03)

IV. Procurement Document ACP 1.2 4.1 Procurement Control Document Preparation and Review V.

Procedures,

. ACP 1.2 5.1 PMMS Trouble Instructions, Reporting System and Drawings and Automated Work Order VI. Document Control ACP 1.2 6.1 Document Distribution and Accountability ACP 1.2 6.2 Master Document Index ACP 1.2 6.4 Temporary Procedure Change ACP 1.2 6.5 Station Procedures O

QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 25 of 34

CONNECTICUT YANKEE QA PROCEDURES n

10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA PROCEDURES ACP 1.2 6.10 Maintenance of Station Implementing Proceduresin accordance with NUSCO Governing Documents ACP 1.211.6 NEO 4.02, Revision 2 Prcposed Technical Specifi.

cation Change Requests and EmergencyWaiverRequests VII. Control of Purchased ACP 1.2 7.1 Receipt, Inspection, Material, Equipment and Identification of and Services Materials,

Parts, e.nd Components Vill. Identification and ACP 1.2 8.2 Material Issue and Control of Mr-erials, Transfer Parts and Components a

IX. Control of Special ACP 1.2 9.1 Control of Special Processess Processess,

ACP 1,2 9.2 Cleaning of Fluid Systems &

Associated Components ACP 1.2 9.3 NondestructiveExamination Procedures ACP 1,2 9.4 NEO 3,13 In Service Inspection Indication Reporting QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 26 of 34

CONNECTICUT YANKEE QA PROCEDURES l

10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA PROCEDURES E

X.

Inspections ACP 1.210.3 Authorized Nuclear i t Inspector (ANI) / Authorized 1

Nuclear!n ServiceInspector (ANII)

[

XI. Test Control ACP 1.211.2 Review of Test Data A '?.'.2 11.3 Retests / Functional Verification ACP 1.211 t Product Acceptance Test ACP 1.211.7 Special Testing j

XII. Control of Measuring ACP 1.2-12.1 Control of Measuring and Test Equipment and Test Equipment.

XIII. Handling, Storage ACP 1.213.1 Handling of Material o

and Shipping and Equipment ACP 1.2-13.2 Storage of Material and Equipment ACP 1.2-13.6 Packaging and Shipping Requirements for Material Parts and Components ACP 1.2-13.8 Shipment rd Radioactive Material XIV. Inspection, Test ACP-1.214.1 NOD 3.04, Jumper, and Operating Status Lifted Lead and Bypass Control -

ACP 1.2-14.2 Equipment Control QAP - Appendix C Rev.: 13 Date: Aug.29,1990 i

Page 27 of 34 i,

b A

A N" /

1 CONNECTICUT YANKEE QA PROCEDURES i

i 10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA PROCEDURES

.i XV. Nonconforming ACP 1,215.1 Nonconformance Materials, Parts, Reports i

Components, or 5ervices XVI. Corrective Action ACF1.216.1 Plant Information Reports ACP 1.216.2 Corrective Action Request l

(NEO 2.18) j XVII. Quality Assurance ACP 1.217.2 Nuclear Power Records Plant Records ACP 1,217.3 Identification of Radiographs XVIII. Audits ACP 1.218.2 NEO 3.07, " Response to-Audit Findings" 5

i i

4 QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 28 of 34

NU WELDING MANUAL 10 CFR 50, APP. B WELDING MANUAL CRITERIA QA PROCEDURES 1.

Organization AP 700 Organization Control of Northeast Utilities Welding and l

Brazing Manual II. Control of Special AP 701 Preparation, QuaHfi-Processes cation, Approval & Revision of Northeast Utilities Welding i

Procedures AP 702 -

Control of Welder and Brazer Qualifications AP 703 Preparation, Review & Approval 4

of Detailed Welding Procedures -

AP 704 Preparation,

' Approval, and

. 'f Revision of Northeast Utilitien General Welding Standards-f AP 705 Preparation, Qualification, Approval,- and - Revision of Northeast Utilities Material.

l Process Procedures i

AP 706 Preparation,

Approval, and Revision of Northeast Utilities Technical-Guideline'.and Standards AP 707 Preparation, Approval and Revision of Northeast Utilities Miscellaneous Weld Documents and Infonnation O-QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 29 of 34

)

l

r NU PURCHASING BUSINESS PROCEDURES 1 0 C F R 5 0,.' J P. B PURCHASING CRITERIA QA PROCEDURES I

w IV. Procurement Document BP-3.1 Requisition: Standard Control and Repeating BP 3.3 Purenase Orders BP 3.4 Changes to Purchase Orders BP 3.19 Blanket Purchase Orders

.a - - -.

i i

?

V O

QAP Appendix C Rev.: 13 Date: Aug.29,1990 l.

l Page 30 of 34 l

l

- - * = = - < * ~

NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 10 CFR 50, APP. B CRITERIA RE PROCEDURES-I.

Organization QRE 1.01 Organization II. Quality Assurance QRE 1.06 Training Program Program QRE 2.09 Training of In Service Inspecticn and Nondestructive Examination Personnel

.QRE-2.10 NTE Section Responsibilities and Condo of ISI Planning and On bi e Activities. for Refueling Outages V.

Procedures, QRE 1.04 Preparation, Issuance Instructions and and Control of Drawings Engineering Department Procedures IX. Control of Special QRE 2.16 - Nondestructive Examination Procedures m

XVII. Quality.%surance QRE 1.12 Control of Documents O

QAP Appendix C Rev.: 13 Date: Aug.29,1990 Page 31 of 34 n

REACTOR ENGINEERING BRANCH PROCEDURES -

10 CFR 50, APP. B CRITERIA REB PROCEDURES I

i I.

Organization REB 1.01 Reparation, Revision,Issurance,

-1 Deletion, and Control of REB Procedures

)

III. Design Control 2.01 Project Follow, Review and Documentation for Initial Core and Reload Fue Campaigns 1

REB 3,03 Generation anc.

valuation of Incore Code-kesults for QA i

Category I Applications l

REB 3.07 Qualification of Analysis Methods which Use Quality O

Related Software REB 3.08 Review of Engineering Service Organizations," Suppliers, Engineering Contractor, and Contractor Design Documents REB 3.09 Communication of Probabilistic Risk Assessment Findings to NU Management REB 3.10 Transmittal of Design Input and/or Results of Design Analysis and Calculations by Memoranda and Reports REB 3.12 Initiation of Projects to Address Probabilistic Risk Assessment Findings O

QAP - Appendix C Rev.: 13 Date: Aug.29,1990 Page 32 of 34

REACTOR ENGINEERING BRANCH PROCEDURES O.O 10 CFR 50, APP. B i

CRITERIA REB PROCEDURES t

REB 3.13 Repor:ing Requirements Concerning Changes to and Errors in ECCS Evaluation Models or Applications I

V.

Procedures,.

REB 1.01 Preparation, Revision, Issuance, Instructions Deletion, and Control of. REB Drawings Procedures XVII. Quality Assurance REB 1.02 Reactor Engineering Branch Records-Record Retention Management of Nuclear Power Plant Records

'v l

L l

QAP - Appendix C l

Rev.: 11 3 Date: Aug.29,1990 l-Page 33 of 34

GENERATION FACILITIES LICENSING BRANCH PROCEDURES 10 CFR 50, APP B i

CRITERIA GPL PROCEDURES V.

Instniction, Procedures, GFL-1.01Q Prepamtion, Issuance and Contml and Drawings of Generation-Facilities Licensing Branch Procedures VI. Document Control GFL-3.01Q N u c 1 e a r Regu1atory-Commission Correspondence I

1 GFL-3.03Q Disposition of NRC and NRC Related Publications GFL-3,06Q Documentation -of GFL Telephone Conversations GFL 3,07Q ' Forward Commitments

\\

GFL 3.08Q Preparation and Submittal of Special Nuclear Source

Material, and Byproduct 3

Material License Application XVIII. Quality Assurance GFL 3.02Q Management of Nuclear Power l

Plant Records GFL 3,09Q Integrated Safety Assessment -

l Program O

QAP - Appendix C

'Rev.: 13 Date: Aug. 29,1990 Page 34 of 34

)

i APPENDIX D I

NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS NOTE:

The NUQAP is committed to utilize the guidance obtained from the following regulatory documents and their endorsed standards ~ Exceptions to these positions are listed in Appendix F of this Topical Report.

Appendix B to 10 CFR, Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

10 CFR 50, Section 50.54, Condition of Licenses.

t 10 CFR 50, Part 55 - Operator's Licenses and its Appendix A Requalification Programs

(

for Licensed Operators of Production and Utilization Facilities, y

Regulatory Gliife~1.8' 1 R - 5/77 - Personnel Selection and Training - Endorses ANSI ^

~

N18.1 1971.

Regulatory Guide 1.28 - 2/79 4 Quality Assurance Program Requirements (Design and 1

Construction) Endorses ANSI N45.21977.

Regulatory Guide 1.30 - (Safety Guide 30),81172 - Quality Assurance Requirements for the Installation, inspection, and Testing of Instrumentation and Electrical Equipment - Endorses ANSI N45.2.41972.

Regulatory Guide 1.33 - 2/78 - Quality Assurance Program Requirements (Operation) -

(

Endorses ANSI N18.71976/ANS3.2.

Regulatory Guide 1.37 - Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants,3-16 Endorses ANEi N45.2.1 1973.

Eegulatory Guiue 1.38 - Quality Assurance Requirements for Packaging, Shipping, R3ceiving, Storage and Handling of iterr.s for Water Cooled Nuclear Power Plants, 5/77 - Endorses ANSI N45.2.2 - 1972.

Regulatory Guide 1.39 - Housekeeping Requiremen:s for Water Cooled Nuclear Power Plants,9/77 - Endorses ANSI N45.2.3-1973.

O QAP Appendix D Rev.: 13 Date: Aug.29,1990 l

Page 1 of 2 m

l Regulatory Guide 1.58 - Qualification of Nuclear Power Plant Inspection, Examination, g

and Testing Personnel, Rev.1,9/80 Endorses ANSI N45.2.61978.

Regulatory Guide 1.64 - Quality Assurance Requirements for the Design of Nuclear Power Plants,6/76 - Endorses ANSI N45.2.111974.

Regulatory Guide 1.70 " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants LWR Edition" Revision 2, September 1975 is utilized for Connecticut Yankee, Millstone 1, and Millstone 2. Revision 3 has been used in the update process for Connecticut Yankee and Millstone 1 for format and to the nearest extent practical for content. No new analyses have been performed which would be required by Revision 3. Revision 3, November 1978 is utilized for Millstone 3.

Regulatory Guide 1.88 Collection, Storage, and Maintenance of Nuclear Power Plant Qualit / Assurance Records - 10/76 Endorses ANSI N45.2.9-1974.

Regulatory Guide 1.94 - Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plant.4/.76 - Endorses ANSI N45.2.5 1974 and Section 6.11 of ANSI N45.2.5-1978.

Regulatory Guide 1.116 - Quality Assurance Requirements for Installation, Inspection, h

and Testing Mechanical Equim.ent and Systems - 5/77 - Endorses ANSI N45.2.81975.

v Regulatory Guide 1.123 - Qm Jity Assurance Requirements for Control of Procurement ofItems and Services for Nuclear Power Plants - 7/'7 Endorses ANSI N45.2.131976.

Regulatory Guide 1.144 - Auditing of Quality Assu ance Programs for Nuclear Power Plants - Rev.1 - 9/80 Endorses ANSI N45.2.12 1977.

Regulatory Guide 1.146 - Qualification of Quality Assurance Program Audit Personnel For Nuclear Power Plants - 8/80 Endorses ANSI N45.2.231978.

Regulatory Guide 1.152 " Criteria for Programmable Digital Computer System Software in Safety Related System of Nuclear Power Plants," November 1985 - Endorses ANSI /IEEE ANS 7.4.3.2 1982.

! O l

QAP - Appendix D Rev.: 13 Date: Aug.29,1990 Page 2'of 2

APPENDIX E NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT GLOSSARY OF OUALITY ASSURANCE TERMS Accent As Is - (also known as "Use As Is") A disposition which may be imposeu for a nonconformance when it can be established that the discrepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.

As Built Documents - Documents which accurately describe the condition actually achieved in a system, structure, or component. These documents include: material certification and test data; reports of inspections, examinations, and test.results; drawing, specifications, procedures, and instructions; and records of nonconformance and their resolution.

Audit - A formal, documented activity performed in eccordance with vnitten checklists or procedures to verify by evaluation of objective evidence that a quality assurance program has been developed, documented, and implemented in.accordance with

\\

applicable requirements.

Calibration - The process by which measuring and test equipment are checked against standards of known higher accuracy and adjusted as necessary to ensure their compliance with designated specifications.

Category 1 - Designation given to systems, structures, and components of a Northeast i

Utilities nuclear power plant that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.

Category I Systems. Structures. and Components - Defined in Appendix A.

Cleaning - Those actions performed to maintain an item in accordance with cleanliness requirements.

Commercial Grade Item (CGD - An item or service which is:

l 1.

not subject to design or specification requirements unique to the nuclear l

industry, and l

2.

used in applications other than the nuclear industry, and

.O V

QAP - Appendix E Rev.: 13 Date: Aug.29,1990 Page 1 of 7 s

i

u 3.

to be ordered from the manufacturer / supplier based on the description 1

l supplied in the manufacturer's published product description, e.g., a

(

I

\\

catalog.

Commercial Grade Survey - Activities conducted by the purchaser to ascertain and verify that a supplier, or manufacturer of commercial grade items, controls the technical and quality characteristics determined to be critical for satisfactory performance of specifically designated commercial grade items, as a method to accept those items for l

l safety-related use.

l l

Condition-Adverse to Ouality Failures, malfunctions, deficiencies, deviations, defective l

materials and equhn'.*nt, and n0Monformances.

i Contractor - Any organization under contract for furnishing items or services. It includes the terms Vendor, Supplier, Subcontractor, Fabricator and subtier levels of these where appropriate. The Nuclear Steam Supply System Supplier (NSSS Supplier) is included in this category.

Corrective Action. Aetion taken in order to correct conditions adverse to quality.

Deficiencies - Departures from specified requirements.

O' Denartment - The use of the word department, throughout the NUQAP Topical Report, can refer to any portion of the NUSCO / NUPOC organization (i.e., Group, Division, Department, Dranch, Section, or Unit, as applicable).

O Departmental Measuring and Test Eauipment List - A list of all departmental measuring and test equipment in the departmental calibration program.

I Design - Technical and management processes which lead to and inchae the issuance of design output documents such as drawings, specifications, and other documents defining technical requirements of systems, structures, and components.

Design Chances Changes in drawings and specifications that define the design of systems, structures, and components of nuclear power plants.

l Rgsien Documents The drawing, calculation, specification, or other document (s) that define the Technical requirements of systems, structures, or components.

Desien Phase /Constmetion Phase /Preoperational Phase - Refers to work phase prior to the issuance of operating license.

I QAP - Appendix E Rev.: 13 Date: Aug.29,1990 Page 2 of 7

l Drawing Change Reouest (DCR) - A document used to initiate and control requests for revisions to generating plant drawings which exist in the Northeast Utilities drawing control system (i.e., having a previously assigned Northeast Utilities Service Company (NUSCO) drawing number).

Engineer-Constructor - The principal organization contracted by NUSCO that performs the overall engineering, procurement, constructim and installation of systems, structures, and components of a nuclear power plan:.

Engineerine Service Organization Organizations that provide services such as analysis, testing, computer software, and inspection.

Generation Facilities Records - The organization responsible for establishing the Corporate Nuclear Plant Records Program which is implemented at each Nuclear Plant Records Facility.

Bandling - An act of physically moving an item by hand or by mechanical machinery, but not including transport modes.

Identification - A means by which material, equipment and parts can ta traced to their associated documentation through the use of heat numbers, lot numbers, part numbers serial numbers, or other appropriate means.

In Process Verifications - An in. depth review of an activity done with an approved written checklist to verify that the activity is being completed in accordance with the approved documents, utilizing auditing techniques.

Inspection - A phase of quality control which, by means of examination, observation, or measurement, determines the conformance of material, supplies, components, parts, requirements. appurtenances, systems, processes, structures, or services to predetermin Insocetion Status Identification of material, equipment, and parts that have completed inspection, either acceptable or unacceptable.

Life Records - Those quality documents that are maintained for the lifetime of the in-service nuclear power plant or for the life of the particular component or part.

Life records are those which would be of significant value in meeting one or more of the following criteria:

(1) demonstrating capability for safe operation.

(2) maintaining, reworking, repairing, replacing or modifying the item.

QAP - Appendix E Rev.: 13 Date: Aug.29,1990 Page 3 of 7

(3) determining the cause of an accident or malfunction of an item.

(

providing required base line data for in service inspection.

(4)

Measuring and Test Eauioment - Those instruments, gages, tools, fixtures, reference and transfer standards, nondestructive test equipment, and measuring devices used during inspection and testing to determine that the measudng and test parameten comply with appropriate requirements in specifications and drawings.

Nonconformance - A deficiency in characteristic documentation or procedure which renders the quality of an item unacceptable or indeterminate.

Examples of nonconformance include:

phyical defects, test failures, incorrect or inadequate documentation, or deviation from prescribed processing, inspection, or test procedures.

Non Life Records - Those quality documents that are maintained for a specific period of time other than the lifetime of the in-service nuclear power plant or the particular component or part.

Northeast Utilities (NU) - A public utility holding company which owns Northeast Utilities Service Company and The Northeast Nuclear Energy Company and through its operating subsidiaries has a controlling interest in The Connecticut Yankee Atomic Power Company, V

Northeast Utilities Service Company (NUSCO) - A wholly owned subsidiary of t

Northeast Utilities that provides engineering, procurement, construction, and quality assurance services for Northeast Utilities relating to design, construction, and I

preoperational testing of nuclear power plants and major modifications theieto.

Northeast Utilities Ouality Assurance Procram (NUOAP) - Consist of the NUQAP Topical Report, Quality Services Department Procedures and other Northeast Utilities Group / Division / Department / Branch / Section quality procedures.

Nuclear Plant Operating Companies (NUPOC) Northeast Utilities Companies which perform preoperational testing of systems, structures and components of nuclear power plants, performs major modifications during the design and construction phases and I

operates the nuclear power plants. The companies which comprise NUPOC are the I

Connecticut Yankee Atomic Power Company and the Northeast Nuclear Energy Company.

1 Nuclear Plant Records Facilities (NPRF) - A facility which has been established for the purpose of handling Nuclear Power Plant records in accordance with the NRS (Nuclear Records System).

O QAP - Appendix E Rev.: 13 Date: Aug.29,1990 Page 4 of 7

NUSCO Ouality Assura:ee Contractor. Sucolier. and Engineering Service Organization h)

Lig A list identifying 'he approval status of the quality assurance programs of V

contractors, supplien, and engineering service organizations.

"Obiective Evidence" - Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the' quality of an item or service based on observation, measurements, or tests which can be verified.

Ooerational Phase - Refers to work phase after plant has received its operating license.

Preservation - Those actions performed to maintain an item in its original and usable condition.

Procedures and Instructions Documents that specify how an activity is to be performed. They may include methods to be employed; material, equipment, or parts to be used; and a sequence of operations.

Procurement Documents - Letters of intent, contracts, purchase requisitions, and purchase orders, including drawings, specifications, and instructions which provide contractual basis for services, supply of equipment and parts, and installation, inspection, and testing. They define the requirements which items and services must l

meet in order to be acceptable to the purchaser.

l l

Product Acceptance Test Activities conducted as part of the receiving or source i

inspection process to verify acceptability of one or more critical characteristics of the item being inspected.

Pmiect Enzineer - A NUSCO / NUPOC employee assigned the responsibility to coordinate the engineering activities addressed in NUQAP.

Purchased Material. Eauioment and Parts (MEP) - Items procured for installation in nuclear power generating facilities systems, structures, and components, and items procured as construction and Power Generating Facility (PGF) spare MEP for potential installation of those systems, stmetures, and components.

i Purchased Service - Service provided by a contractor or consultant on a QA requisition l

when activities and personnel are under a quality assurance program other than the NUQAP.

i Ouality Assurance fecords - Any record pertaining to the quality of material, equipment, parts, processes, or operations relating to systems, stmetures and components which are founded on observations, measurements, or tests which can be fully checked or verified. Such statements may be recorded on a written or preprinted QAP - Appendix E Rev.: 13 Date: Aug.29,1990 Page 5 of 7

r t

document or tag. The statements are autho.ized with a signature or stamp identifiable O

to the person making the statement of fact, t

g l

Ouality Activities - Activities involving parts, components, structures and services for Category I, Radwaste QA (including Radwaste Packaging and Shipping), ATWS, FPQA, EEQ, and other regulated programs in accordance with the requirements mandated by those regulations. Appendix A dennes Category I program controls.

l Ouality Procedures - Those procedures which implement the requirements of the NUQAP Topical Report. Appendix C lists typical Quality Related Procedures that are reviewed and approved by NUSCO Quality Services Department.

Repair - A disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose which are modified by the use of additional operations and / or p ocesses so that they are suitable for their intended purpose but may not meet all specified requirements.

Retest A test conducted prior to operation following installation inspHons of work associated with maintenance and refueling to verify that systems, arectures, and components will function satisfactorily when in operation. A retest may also be performed when original test results are invalidated.

O Return to Sucolier A disposition applied to nonconforming material, equipment, and V

parts that are unsuitable for their intended purpose but which are feasible to repair or reworl, at a supplier's facility.

Rework - A disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose due to incomplete operations or variations from original engineering requirements but which are modified through the use of additional operations or processes to meet all specified requirements.

1 Safety Related Systems and Components - Systems and components required to shut down the reactor, mitigate the consequences of postulated accidents, or maintain the reactor in a safe shutdown condition.

Siznificant Condition A condition adverse to quality that:

1.

violates the plant's technical specifications or results in a plant shutdown as required by the technical specifications.

2.

results in the condition of the plant, including its principal safety barriers, being seriously degraded.

QAP - Appendix E 1

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Date: Aug.29,1990 l

Page 6 of 7 l

t 3.

results in manual or automatic actuation of any engineering safety feature.~

4.

prevents the fulfillment of the safety function of a safety related system.

S.

results in a release of radioactivity in excess of plant limits.-

6.

poses an actual threat to the safety of the plant or significantly hampers site personnel in the performance of duties-necessary for the safe operation of the plant.

q l

7.

involves repetitive programmatic / procedural violations or a f'ailure to 1

4 comply with regulatory requirements.

Special Processes - An operation performed under controlled conditions in accordance.

with special requirements utilizing qualified procedures, equipment, and~ personnel.

These special processes may include, but are not limited to welding, brazing, soldering, cleaning, heat treating, and nondestructive testing.

i Storare - The act of holding items at the construction site or in an area other than its

~

~

permanent location in the plant.

(

Sucolier - Organizations that provide material,. equipment, parts, and services, or computer software.

Surveillance - A documented record of the observation of work operations performed at NUSCO / NUPOC or vendor's site to assure compliance with applicable codes, standards, specifications, procedures, drawings, and procurement documents.

Surveillances are not performed to a preplanned checklist.

Test and Ooerating Status Identification of material, equipment, and parts that are ready for test or operation, or an existing stage of a test operation.

Ie. sling - The determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physical, chemical, environmental, or j

operating conditions.

QAP - Appendix E i

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. ~

b MPENDIX F O

NORTHEAST UTILITIES OUALITY ASSURANCE PROGRAM TOPICAL REPORT Program Exceptions 1.

ANSI N45.2.9. states in part, " structure, doors, frames, and hardware should be Class A fire related with a recommended four hour minimum-rating." The-records storage vault door and hardware at NNECO has a two hour rating and:

the record storage vault door and hardware at CYAPCO has a three hour rating.

i Both NNECO and CYAPCO's vaults are used for storage of documentation that is unsuitable for filming or awaiting filming.

A records organization exists along with written procedures addressing the control of quality assurance records.

r ib.725~hEparagraph 4.3.2.3 " Quorum" states in part: "A quorum for -

2.

ANSI 9

formal meetings of the (Independent. Review) Committee -held under the provisions of 4.3.2.2 shall consist of not less than a majority of the principals, or duly appointed alternates..."

The usc of Alternates was eliminated fro.n the Northeast Utilities Nuclear Review Board (NRB) Charter due to the difficulties of keeping the Alternates up-I to date. The elimination of Alternates forced the creation of a larger NRB membership (eight to eleven members) for greater diversity, resources, and i

availability.

i A quorum of the Nuclear Review Board shall consist of the Chairman or Vice Chairman and at least enough members to constitute a majority of the assigned members. No more than a minority of the quorum shall be from the Nuclear Operations Department.

3.

ANSI N45.2.91974. paragraph 1.4, definition of " Quality Assurance Records" states in part: "For the purposes of this standard, a document is considered a quality assurance record when the document has been completed."

Northeast Utilities ha:: developed the following alternative definition to provide guidance during the interim period from the time a document is completed until it is transmitted to the Nuclear Plant Records Facility:

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i l

"A record is considered a working document until it is transmitted to the h:

appropriate Nuclear Plant Records Facility (NPRF) at which time it is designated d

as a Quality Assurance Record.

The following maximum time limits are established for the transmittal of working documents to the NPRF:

Operations Documents - Documentation generated during; Plant Operations may be maintained, as needed, by operating plant departments, for up to one year.

New Construction or Betterment Documents - Documents which evolve during new construction or betterment projects shall be transmitted to NPRF within 90 days of completion' of a new construction project or turnover of a betterTnent project or plant operations.

Procurement Documents -

Inspection / Surveillance / Audit. Reports -

generated during vendor oversight activities which are used to maintain vendor status for current and future procurements may be maintained, as needed, by :.e Quality Services Department, for up to three years.

'~li Otlier Working Documents - All other working documents shall be transmitted to NPRF_with 6 months of their receipt or completion."'

The requirements of ANSI N45.2.91974 do.not apply to these '.' working

(

l' documents" based on paragraph 1.1.of the ANSI standard which states:

"It (ANSI N45.2.9) is not.ntended to cover the preparation of the records o

l' nor to include working documents not yet designated as Quality _

l Assurance Records."

4.

Regulatory Guide 1.64 6n6, the Regulatory position states, in part, "It should not be construed that such. verification constitutes the required independent design verification." Northeast Utilities has developed the following alternative to allow for adequate independent design verification:

l This review may be performed by the originator's Supervisor, only if the Supervisor:

Did not specify a singular design approach; l

Did not establish the design inputs or did not rule out certain design _

considerations; 1s the only individual in the organization competent to perform the review.

b V

QAP - Appendix F Rev.: 13 Date: Aug.29,1990 Page 2 of 3

Y Where the Supervisor performs the design review, the next level of management I

shall fulfill the Supervisofs responsibilities.

V 5.

ANSI N45.2.13 1976. paragraph 10.3.4, states in part, " Post-Installation Test requirements and acceptance documentation (should) shall be mutually established by the purchaser and supplier." Involvement by.the supplier in establishing Post Installation Test requirements and acceptance documentation is requested only when it is deemed necessary and proper by the responsible engineering organization.

Northeast Utilities no longer has any nuclear plants under construction. As a result, most procurements are made for spare parts from suppliers who are not the original equipment manufacturer. In these cases, the supplier may have little or no understanding or knowledge of either the operation of the system the component is to be installed in, or applicable Post Installation Test requirements '

and acceptance documentation.

As such, Northeast Utilities assumes-responsibility for establishing Post Installation Test requirements and acceptance documentation.

6.

ANSI N45.2 2-1972. paragraph 1.2, states in part that,"The requirements of this standard apply to the work of any individual or organization that participates in l

the packaging, shipping, receiving, storage, and handling 'of items to be incorporated into nuclear power plants."

Since a portion of Northeast Utilities procurement activities involve commercial suppliers which do not fully comply with the requirements of ANSI N45.2.2, Northeast Utilities Quality Services organization verifies through source inspections, receipt inspection, and/or survey activities that the quality of the materials, items, components or equipment is preserved by those suppliers to the extent that packaging, shipping, storage and handling methods are employed which are commensurate with the nature of the product.-

Q' QAP - Appendix F.

Rev.: 13 Date: Aug.29,1990 Page 3 of 3 6'

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