B13245, Forwards Proposed Rev 12 to QA Program Topical Rept for Review & Approval.Changes Have Effect of Upgrading QA Program
| ML20247R581 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 05/25/1989 |
| From: | Mroczka E NORTHEAST UTILITIES, NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B13245, NUDOCS 8906070260 | |
| Download: ML20247R581 (136) | |
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) Y-t N UTILITIES conor i 0,, ice. . seio.n sir..i. seriin, Connecticut Y S
- P.O. B0X 270 k k J , " *U 7,"7."'$'f""/C, HARTFORD, CONNECTICUT 06141-0270 (203) 66 5 5000 May 25, 1989 Docket Nos. 50-213 50-245 50-336 50-423 f!13245 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 Annual Reporting of Changes to the Quality Assurance Program Proposed Revision 12 to the Northeast Utilities Ouality Assurance Proaram Topical Report In accordance with 10CFR50.54(a)(3), transmitted herewith is proposed Revi-sion 12 of the Northeast Utilities Quality Assurance Program (NUQAP) Topical '
Report (Attachment B) for your review and approval. Proposed changes to the Topical Report are indicated by the vertical line in the right-hand margin.
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 12 of the NUQAP Topical Report have the effect of upgrading otr 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 12 without a date. This draft will be issued as Revision 12 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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[sg. a U.S. Nuclear Regulatory Commission BI3245/Page 2 .
May 25, 1989 ,
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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 44s an/
E. J. W zRa- ./' ~
Senior ce Presidbnt cc: W. T. Russell, Region I Administrator 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 L 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. Eapen, Chief, Quality Assurance Section, Region 1
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ATTACHMENT A -
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U-- Summary of Proposed Changes to NUQAP Topical Report Revision 12
- f-Abstract. Polley' Statement. Introduction o Deleted Fire Protection Quality Assurance (FPQA), Radwaste Quality Assurance
- o Added
- Portions of the NUQAP are also applicable to Fire Protection Quality ' Assurance (FPQA) . and Radwaste Quality Assurance (RWQA) which are delineated in established procedures.
QAP 1.0 o Changes in this section reflect the current Organization and responsi-bilities at NU.
-o. Paragraph 1.2.2 - Revised description of duties of Vice-President -
Information Resources Group to reflect quality activities.
o Paragraph 1.2.3b and 1.5.3 - Deleted due to reorganization involving Production Test. Transmission and Distribution Engineering and Operations is no longer responsible for ensuring the requirements of the ' NUQAP are carried out.
o Added Paragraph 1.4.1.4 - Added to include functions of Production Test due to reorganization.
o Paragraph 1.4.2.3 - Revised titles and responsibility descriptions for Environment Programs, o Paragraph 1.4.3.2 - Added NUPOC Unit Superintendent responsibilities and added functions reporting to the NUPOC Station Servlees and Unit Superintendents.
o Paragraph 1.5:1 - Revised title to read Purchasing and Materials
. Management.
o Paragraph 1.5.2 - Revised Information Resources Group responsibility in relation to the support of quality activities.
o Paragraph 1.5.2.5 - Revised title of Director, Communication Systems.
QAP 4.0 o Paragraph 4.2.1 - First line changed to read "and/or."
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Appendix C f3 L
o Deleted cancelled procedures and updated. titles to reflect current -
procedures issued by various organizations within NU.
o Added Listing of Quality Software Procedures.
Appendix D -
o Added ' Regulatory Guide 1.152 (Connecticut Yankee Commitment only).
Appenddc E '
o Revised definitions to provide consistency with ANSI definitions and/or NU usage. Added commercial grade periodic survey definition.
Appendix F o For ANSI N45.2.9-1974, added item for " Procurement Documents."
o Added an exception to Regulatory Guide 1.64, " Quality Assurance Requirements for the Design of Nuclear Power Plants, 6/76," that allows an independent design review by a supervisor in certain cases.
/N o For ANSI N18.7-1976, revised minimum NRB membership from seven h to eight.
General o All other changes not specifically identified are editorial changes for continuity throughout the Topical Report.
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, : D)' o Paragraph 5.2.2 - Deleted "the Nuclear Engineering and Operations Group" and now reads "The appropriate NUPOC Superintendent has the ultimate responsibility, which can be delegated, . . ."
d QAP 7.0 1 o Paragraph 7.2.1 - Added the use of commercial grade periodic surveys and surveillance as methods for evaluating the qualifica-tions of a potential supplfer.
l o Paragraph 7.2.2 - Revised to reflect use of inspections, not sur-veillances.
QAP 12.0 o Paragraph 12.2.1 and 12.2.2 - Revised to reflect Generation Construction directed activities in relation to M&TE equipment.
QAP 15.0 l o Paragraph 15.2.2 - Redefined to reflect NU's physical identification and control of nonconforming items.
o Paragraph 15.2.4 - Deleted "NUSCO Director" and replaced with "NUSCO Discipline Engineering Supervisor." Technical aspects of
, (A) an- engineering disposition to a nonconformance report are provided a more comprehensive review at the Engineering Supervisor level versus the Director level.
o Paragraph 15.2.4 - Deleted NUSCO Quality Services review and approval of nonconformance reports dispositioned "use as is" or
" repair" and added NUSCO Quality Services method of verifying that NUSCO/NUPOC dispositions for nonconformance reports are adequate. Nonconformance reports receive appropriate review and approval by engineering.
- Q AP 16. 0 o Paragraph 16.2.1 - Deleted secpn'd paragraph. Redundant to QAP 5.0', Paragraph 5.2.1. Deleted Quality Services concurrence
. and in-line review function of the adequacy of corrective action and added that the adequacy of corrective action will be verified through audits, surveillance, and in process verifications.
Appendix A o Better defined (j) and (k).
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- W TABLE OF CONTENTS '
4.: ' NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)
- , \# TOPICAL REPORT .
'Rev. :Pages L . .
, , Abstract ,
12- l' a Table ' of Contents - 12 1-2 b, : Policy Statement '12 1-Introduction 11. 1-2 i
Qualityi Assurance Program K
QAP 1.0 Organization i12- 1-13 Organizational Charts 12 Fig. 1.1-1.7 i a- QAP 2.0f ' Quality- Assurance Program' '12 1-7.'
QAP 3.0 : Design Control- .
12 1-6 QAP E 4.0 2 Procurement- Document Control 12 1-4 QAP ' 5.0 ; Procedures, Instructions and Drawings -- .
12 1-3 i
QAP 6.0_- Document Control- 12 1 , .
.QAP 7.0: . Control of Purchased Material, Equipment and Services 12 1-4 (Mj
~ QAP 8.0_ Identification and Control of Materials, Parts and Components 12 1-2 Control of Special Processes 1-2
. QAP. 9.0 12 1-4 i
- QAP 10.0 Inspection? 12 Y QAP 11.0. Test Control 12 1-3 QAP 12.0. Control of . Measuring and Testing Equipment .12. 1-3 QAP -13.0 ~ Handling,. Storage, and Shipping .
12 1-2
-QAP; 14.0 Inspection, Test, and
. Operating Status 12 1-2 QAP '15.0 Nonconforming. Materials,
. Parts, Components, or
. Services 12 1-4 QAP 16.0 - Corrective Action 12 1-2 -
QAP 17.0 Quality Assurance Records 12 1-2
, QAP 18.0 Audits 12 1-3
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QAP Table of Contents
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Rev.: 12 Date:
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- Appendices A. Category I Systems, Structures and '
Components 12 1-3 B, Qualification and Experience
_ Requirements, NUSCO Manager, Quality Assurance 12 1 C. List of Typical Quality Assurance Related Procedures 12 1-32 D; Regulatory Guide and ANSI Standard
. Commitments 12 1-2' E, . Glossar/ of Quality Assurance Terms 12 1-7 F. Program Exceptions 12 1-2 4
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ABSTRACT
) NORTHEAST UTILITIES Q.UALITY ASSURANCE PROGRAM (NUQAP)
~ NJ TOPICAL REPORT Northeast Utilities (NU) has developed and is implementing a compre-hensive Quality Assurance Program to assure conformance with estab- !
11shed regulatory requirements, set forth- by the Nuclear Regulatory
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'l Commission (NRC), and accepted industry standards. The pa-ticipants in the NU Quality Assurance Program assure that the design, procure-ment, construction, testing, operation, maintenance, repair and modifi-cation 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 l' Regulatory Guide 1.70, which describe,s the information required to be presented in the Quality Assurance Section of the SAR's for nuclear power plants. j This NUQAP is also established, maintained and executed with regard to i Radioactive Material Transport Packages as allowed by 10 CFR 71.101(f) .
Quality Assurance Provisions for Fire Protection activities are detailed i in the Northeast Utilities Fire Protection Program. !
This NUQAP is applicable in its entirety to Category I systems, struc-tures, components, materials, equipments, parts, and services.
Appendix A defines Category I systems, structures, and components. l The NUQAP is also applicable to other quality programs including l Anticipated Tradslent Without Scram (ATWS) and Environmental Equipment Qualification (EEQ) as defined 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 utilize the guidance obtained from the Regulatory documents and their endorsed Standards as referenced in Appendix D of ,the Topi, cal Report. ,
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POLICY STATEMENT G NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM
\v' TOPICAL REPORT The policies, requirements and tasks contained in this Northeast Utilities Quality Assurance Program description have been developed to achieve a recognized need for quality assurance during the design, procurement, construction, testing, operation, maintenance, repair, and modification of our nuclear facilities. i Northeast Utilities procedures which implement this program are described in various manuals which are referenced herein.
This NUQAP is appilcable in its entirety to Category I systems, struc-tures, 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) which are delineated in established procedures, nnd Anticipated Transient Without Scram Quality Assurance (ATWS Qun' ty Assurance is applicable to MP-1, 2 only; MP-3 commits to Generic Letter 85-06), and Equipment Environmental Qualification as defined by NU commitments.
The development and overall responsibility for this Quality Assurance g 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 portien of the Northeast Utilities Quality Assurance Progrr.m. 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 edditions to this policy statement rosts with the Senior Vice President-Nuclear Engineering and Operations.
/ *C E. JT jdro'czka [/
Senior Vice President -
Nuclear Engineering and Operations Northeast Utilities ,
( QAP Policy . Statement Rev.: 12 Cate:
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.-m INTRODUCTION
) NORTHEAST UTILITIES Q_UALITY ASSURANCE PROGRAM
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\ 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.
- 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 app!1 cable to MP-1, 2 only; MP-3 commits to Generic Letter 85-06), and Equipment Environmental Qualification as defined by NU commitments.
- 3. Appendices, which provide supporting statements and tabulations.
(^) This NUQAP Topical Report has been prepared to document that a C/ meaningful quality assurance program has been established and imple-mented 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 to accomplish quality require-ments . 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 Servicen Dapartment in accordance with QAP 2.0 and QAP 5.0.
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C/ QAP Introduction Rev.- 12 Date:
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- The NUQAP is responsive to applicable codes, Nuclear Regulatory i Commission regulatory requirements, accepted industrial standards and
\ revisions thereto. Provisions 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. ,
' _k__ ._, ( 'c N Donald O. Nordquist NUSCO Director, Quality Services
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QAP Introduction Rev.: 12 Date:
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- 1.0 ORGANIZATION jf3 y '
1.1. - INTRODUCTION f- -- Northeast Utilities (NU) is a holding company which ' owns all of the
> common stock in several companies as 111ustrated by--Figure 1.l.
The Connecticut Light and Power Company '(CL&P) and Western Massachusetts Electric. Company-(WMECO) are the owners of M111 stone'
. Unit Nos, ul- 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 ;&ny future units.
The NU Companies jointly own 44% of the Connecticut Yankee Atomic Power Company (CYAPCO). By contract, NU and Northeast Utilities Service Company (NUSCO) have been delegated operational' control of CYAPCO. NUSCO provides technical support for the operation of that plant.
Northeast Nuclear Energy Company (NNECO) and CYAPCO are the.
operating companies establish'ed to operate their respective facill-
. ties. . NNECO is delegated the responsibility for operating the
- Millstone ~ Units by the owners. NNECO.in turn has contracted for h (-
the services of NUSCO for the design and construction management of all of the units at Millstone and may solicit technical support Lt 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 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 in /
cated, the Senior Vice 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.
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 QAP - 1.0 Rev. : 12 Date:
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- - l s directs specified nuclear-related activities within NU.
He has the ultimate responsibility for the establishment I
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w/ 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 Sen. tor Vice President-Administrative Servlees . Authority for the establishment and execution of the NUQAP is delegated to the Senior Vice President-Nuclear Engineering and Operations (see Para.1.2.4) .
1.2.2 The Senior Vice President-Administrative Services 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 corporate mainframe computer systems and provides ' support for quality activities as requested by Nuclear Engineering and Operations /NUPOC personnel (see Para, 1.5.2).
1.2.3 The NUSCO Executive Vice President-Engineering and Operations is also the Executive Vice President-Engi-7"S neering and Operations for NUPOC. Specific nuclear-('~# / related responsibilities rest with the following individual 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 respon-sible for nuclear engineering, construction, operation, maintenance, 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 l
through the receipt of various documents such as: Weekly progress reports, Nuclear Review Board Meeting Notes and other reports, and l
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. ,m ' audits.related to NUPOC nuclear. plant operations activities.
1.2.4.2 ' The Senior Vice President-Nuclear Engineering .
and Operations is responsible to assess the scope, status, implementation and effectiveness of the NUQAP. To meet this responsibility, he appoints aj qualified team of individuals to perform an annoal Management Quality Assurance Review.
'This Management Quality Assurance Review is:
- a. A systematic evaluation;
- b. Preplanned toward the objective of deter-mining the adequacy of the NUQAP and its compliance with Appendix B to 10 CFR Part 50 and other regulatory requirements;
- c. Capable of identifying, communicating and tracking 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.
.d['N- 1.2.4.3 The following division Vice Presidents report to the Senior Vice President-Nuclear Engineering and Operations:
- a. Vice President-Geneiation 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 Pars. 1.4.3) 1.3 RESPONSIBILITIES (Refer to Figure 1.6) 4 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 the Quality Assurance Program; implementation of policies, plans, requirements, procedures, and audits; verification to assure compliance with 10 CFR 50 Appendix B and other n.
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regulatory requirements;- and' verification of the~ imple- ' ~~'
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. mentation.of the NUQAP Topical Report Requirements.
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'1.3.2. ' Overall responsibility: for the implementation of the NUQAP Topical Report at the NUPOC' Nuclear Plant ~ is assigned tola NUPOC Superintendent. e m
.1.3.3 The head of each NU department or. organization 5 performing quality activities is responsible for a
' Administering those activities within his organization ,
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which are defined by the .NUQAP Topical Report;-
-b. Ensuring Implementation of the Quality Assurance Program;
- c. ' Establishing and clearly defining the duties and-responsibilities of personnel within his organization-who perform. quality activities:.
.d. Planning, selecting and training personnel to meet -
the requirements of the NUQAP Topical Report;
- e. Performing and coordinating quality matters within 7 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 rela-w, -
tionship for' performing quality. activities within each' organization is established and delineated in the NU Organizational Charts, jurisdictional statements, and written job or functional descriptions.
1.4 NU PARTICIPATING GROUPS - NUSCO NUCLEAR ENGINEERING AND OPERATIONS . GROUP ,
The Senior Vice President-Nutlear 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.
' The Nuclear Engineering and Operations Group is divided into three divisions:
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g6 Generation' Engineering and Con'struction (Figure -1.3);
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AI b. Nuclear and Environmental Engineering (Figure :1.4)'; and P, c. - Nuclear l Operations (Figure l'.5) .
< The' functions of the personnel,, who perform quality activities within' these. divisions, are as follows:'
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" > 1. 4.1 - The Vice' President-Generation Engineering and Construction is responsible for engineering and design, and modifica-F - tion,i backfit, and Generation Construction projects for existing.NU generating facilities. The following depart-ment heads report to him: L(See Figure 1.3) .
[ '1.4.1.1. The Director Generation' Engineering and i
Design Department is responsible to provide technical and ~ support personnel to provide
, Project Engineers and support for Generation
' Construction projects in Generation Facilities ,
{ directed. by the Generation Projects Department.
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. Technical support is also provided for opera-tions and maintenance activities of generating facilities. The Generation Engineering and
Design Department provides expertise for
. systems, specifications and" procurement of fN equipment and ' material; it provides _ design expertise for the preparation and maintenance
~o f design. documents for. generating facilities.
These generation 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.
1.4.1.2 The Director-Generation Construction' Department is responsible for the following areas in genera-tion facility 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 depart-ment is responsible for providing' construction O -
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- I" management for' construction work on the i y Af
[Y ~ generatioq facilities. 'I L .
1.4.1;3 The Director-Generation Projects Department .is -
'b responsible for providing the program management ,
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- g. and. coordination of capital and expense type ~1 L projects undertaken to. improve the safety and ? l W 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.
>1.4.1.4 ~ The' Superintendent, Production Test, L is responsible for Quality production test
- activities which include:
- a. Providing ' electrical . testing _ services to the Nuclear Plant Operating Companies -
(NUPOC).
- b. Planning and coor dinating' periodic and corrective maintenance of electrical' equipment.
- c. Conducting acceptance tests, calibrations,-
adjustments, functional checkout, and q commissioning.of electrical systems.
- d. Overseeing electrical preoperational
- testing for nuclear generation facilitias projects and start-up testing for backfit/ Generation Construction projects, as requested.
1.4.2 The Vice President-Nuclear and Environmental Engineering is responsible for Nuclear Engineering and Operations :
Services (including Reliability Engineering, Generation Facilities Records, Nuclear Materials and Chemistry, and Nuclear Safety Engineering); Environmental Programs; Quality Services; Nuclear Engineering (including: Radi-ological Assessment, Reactor Engineering, Licensing, and Nuclear Fuel); and Nuclear Training. The following department- Directors report to the Vice President-Nuclear and Environmental Engineering (see Figure 1.4):
1.4.2.1 The Director-Nuclanr Engineering and Operations Services is responsible to direct and coordinate the support services as required for NUSCO/
NUPOC Departments during the design, modifi-cation, maintenance, construction, and QAP 1.0 Rev.: 12 Date: i Page 6 of 13 ;
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., operation.of nuclear power plants. He has reporting to him the following managers /
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, ;e a. Manager, Generation Facilities Records is responsible to provide ' guidance by the establishment of a corporate Nuclear Plant Records Program and Manual for the effective operation of all Northeast Utili-
- ties Nuclear Plant Records Facilities to meet corporato nuclear records objectives.
- b. . Manager, Reliability Engineering is respon-sible 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.
- d. Manager, Nuclear Safety Engineering is responsible to provide nuclear safety engineering evaluations of operational p\jf experience at NU and Industry nuclear power plants.
1.4.2.2- The NUSCO Director, Quality Services is responsible for the preparation and issuance of the .NUQAP Topical Report, and verification of the implementation of its requirements by the applicable NUSCO/NUPOC Departments. Verifica-tion is performe.d by a planned program of audits, surveillance, inspection, and in-process verifications by the Q,uality Services Sections. He provides management with objective evidence of the performance of activities affecting quality, independent of the individual or group directly responsible for perforn.ing the specific activity.
He han the authority and organizational freedom to assure all necessary quality affecting activi-ties 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 13 QAP - 1.0 Rev.: 12 Date:
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= _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ _ _ , _ _ _ _ .
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em unsatisfactory work and control further processing, t ) delivery, or installation of nonconforming materials . He also has the responsibility and authority to identify quality problems, to provide solutions, and to verify their implemen-tation. He maintains an overview of NUPOC -
quality assurance activities through a planned and systematic program of audits, surveillance, and in process verifications.
The following Managers and Supervisors report directly to the NUSCO Director, Quality Services (See Figure 1.6) .
- a. The Manager, Procurement Quality Services assures that quality assuranca respon-sibilities, as they relate to procurement activities for the NU Nuclear Generating Facilities, are being implemented.
- b. The Mans.ger, Plant Quality Services Assures the quality assurance activities associated with the construction, modification, operation, maintenance and refueling of the NU Nuclear Generating Facilities are being implemented.
- c. The Supervisor, Assessment Services assures that the quality assurance respon-sibilities, as they relate to the operational phases and Generation Construction projects of NU Nuclear Generating Facilities are being implemented.
- d. The Supervisor, Assessment and Staff Services assures that the 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 proper control over the Quality Assurance Program. They have the respon-sibility and authority to identify quality .
(
n)
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y ,
. ,m problems, to provide solutions, and .to verify
(' '); ' their implementation. Stop Work Orders initi-ated by NUSCO Quality Service personnel are delineated in writing with the concurrence of a NUSCO Quality Services Manager /St pervisor.
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 assign-ments' throughout the plant. This also assures that there is adequate Quality Service coverage relative to procedural and inspection control, acceptance criteria, and Quality Services staffing and qualification of personnel to carry out Quality Services assignments for quality
' activities.
1.4.2.3 The Director-Environmental Programs is respon-sible for the planning, design, coordination and supervision of all scientific / engineering
[] studies of problems related to environmental
\._/ impacts of NU activities affecting proposed and operating generation facilities. He has, reporting to him, the following Managers /
Supervisors:
- a. Manager, Environmental Services is responsible for the preparation of atmospheric dispersion calculations required to estimate dose to the public from both routine releases and postulated accidents. He provides criteria and studies to assure that such calculations reflect state-of-the-art techniques and j adequately support the corporate program for Nuclear Emergency Preparedness,
- b. Supervisor, Benthic Ecology of NU Environmental Laboratory directs ecological impact studies for the operating j generation facilities.
- c. Supervisor, Fish Ecology of NU Environmental Laboratory directs QAP - 1.0 Rev.: 12 Date:
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w _ ecological impact assessment studies for
_ the operating generation facilities.
ll - ,
4
'154.2.4 The Director-Nuclear Engineering is responsi,ble to direct and coordinate the activities of:
- Radiological Assessment,. Generation Facilities Licensing, Reactor Engineering and Nuclear (
. Fuel. : The following managers report to _ Director-Nuclear Engineering:
- a. Manager-Radiological Assessment is respon-
, sible to provide technical services in4 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,Lliaison
,> > with regulatory agencies, . and responsibility for the corportte program for Nuclear Emergency Preparedness.
- b. . Manager-Generation' Facilities Licensing is responsible for corporate liaison .with the -
Nuclear Regulatory Commission and coordina-tion of responses to regulatory require-ments for changes t9 operating facilities, n ] ..
_ This includes the preparation and coordi-(./ nation of documents for submittal to various regulatory agencies.
'c. The System Manager-Reactor Engineering is responsible to. provide reactor engi-neering, NSSS safety analysis, probabilistic risk assessments, fuel design,. and reactor core analysis and performance evaluation services for Generation Construction projects and operations' of nuclear generation facilities.. This includes services during reload of nuclear reactor cores, direction for optimal operations of reactor cores, evaluation of design and analysis of reactors, and NSSS transient evaluations ,
- d. Manager-Nuclear Fuel is responsible for the planning, scheduling and coordination of the nuclear fuel supply requirements for operating nuclear generation facilities.
This includes contract engineering for j
. technical administration of fuel contracts
+
b QAP - 1.0 i
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., y and technical. support for the procurement of all elements of the nuclear fuel cycle, 1
'f the handling of. fuel removed from operating facilities, and determination of nuclear fuel costs.
1.4.2.5 Director-Nuclear Training is responsible for Nuclear Training:and Training Evaluation activities. The following managers report to the Director-Nuclear Training:
- a. Manager-Operation Training is. responsible for providing initial and requalification training programs for Nuclear Plant Operators.
- b. Manager-Technical Training is ' responsible for providing technical training in areas such as: Electrical and Mechanical Maintenance, Instrumentation and Control, Health Physics, and' 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 j^V) 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.
1.4.3 The Vice President-Nuclear Operations is responsible for plant modifications, refueling, maintenance and operation of operating nuclear generatfor. 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 respon-sible for the coordination of activities between the NUSCO Engineering personnel and the NUPOC personnel. Engineers are assigned to perform the coordination of the activities for NUPOC operating nuclear generating facilities.
1.4.3.2 NUPOC Station Superintendents (Millstons and Connecticut Yankee) are responsible for the 1 operation, maintenance, plant modifications,
.R) .
QAP - 1.0 Rev'. : 12 D:L :
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- refueling and services of operating generation facilities. l f,\.a:3 ,+i ,
- a. NUPOC Station ' Services Superintendents -
- , . (Millstone and- Connecticut Yankee) report -
- to the individual Station Superintendents and are responsible' for the service func-tions of each station. (See Figure 1.6 A.& B.).
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 Unit Superintendents (Millstone and Connecticut Yankee) report to the individual Station Superintendents and are responsible for the operation, . maintenance, plant modifications, and refueling of their 4(
' . respective generating facilities. The following functions repbrt to each Unit' Superintendent: (See Figures. l.GA and
- 1. 6B . )
o Op~erations o ' Engineering o- Instrumentation and Controls o . Maintenance 1.5 OTHER NU PARTICIPATING GROUPS Nuclear Engineering and Operations /NUPOC may request the services of these NU Participating Groups as necessary to support quality activities under Nuclear Engineering and 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, '
O- Q AP - 1. 0
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are several Purchasing- Directors end Managers responsible
,- for: ' .
l
[ ;a; The: procurement of materials and services from
_ quallfled suppliers In accordance with predetermined l4 .
. commercial,; technical, and quallt;; requirements;-
- b. Issuing' Purchase. Orders / Contracts and changes
' ~
. thereto;-
- c. . Maintaining traceability of purchasing records ~ from NUSCO/NUPOC;
- d. Processing of purchaseirequisitions through the preparation of payment for the purchased item.
.The:Vice President Purchasing and Materials Management controls purchasing procedures.
- 1. 5. 2 '- INFORMATION RESOURCES - GROUP '(See Figure 1.7)
The'Vice President-Information Resoure'es Group operates
.and maintains corporate mainframe computer systems and provides support for quality activities as requested by Nuclear Engineering and Operations /NUPOC personnel.
. Reporting- to the Vice President-Information Resources f' : Group are:
- a. The Director-Information Resources - Systems -
Development.
- b. The Director-Information Resources Operations and Technical Support.
- c. The Manager-Information Resources Planning and Control. .
- d. The Director-Information Resources Administration. ;
- e. The Director-Communication Systems.
QAP - 1.0
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s 2.0 QUALITY ASSURANCE PROGRAM .
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2.1 GENERAL REQ.UIREMENTS Northeast Utilities (NU) has established a Quality Assurance Program (NUQAP) which complies with the criteria of 10 CFR 50, Appendia B, and follows the guidance referred to in Appendix D of this report. The quality assurance requirements set.forth herein and the attached Policy Statement, supplemented by the Quality Assurance Procedures, provide the primary basis of the Program and the NU Policy with regard to quality assurance.
This program is established for each plant site in a manner intended to accomplish the required level of quality and is carried out throughout the life of nuclear power plants. It includes quality activities during the operation, maintenance, testing, and modification of the in-service nuclear power plants.
The requirements of the NUQAP apply, as a minimum, to nuclear safety-related systems, structures and components as functionally identified in Appendix A, " Systems, Structures and Components" l and other items or services which are specifically identified in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide-1.70.
The requirements of the Program are implemented by Northeast Utilities Service Company (NUSCO), Nuclear Plant Operating V]
f Companies (NUPOC), engineer-constructors, contractors, suppliers and engineering service organizations performing activities affecting quality systems, structures and components of nuclear power plants.
Procedures define the required indoctrination and training of personnel performing activities affecting quality, as necessary, to assure that suitable proficiency is achieved and maintained.
Training sessions are documented, the content described, who attended, when they attended and the results of the training sessions, q A periodic program review of the status and adequacy of the NUQAP is accomplished by NUSCO Quality Services audits, l
surveillance, inspections, and in process verifications by ]
Nuclear Review Board (NRB) Reviews, and by the independent 1 audit team described herein and in QAP 1.0, Section 1.2.4.2. {
I Organizations outside NU are required to review the status and adequacy of that part of the Quality Assurance Program for l which they have designated responsibility. j l
' QAP - 2.0 ,
Rev.: 12 l Date: !
Page 1 of 7
4 s
2.2 IMPLEMENTATION 3
'vj 2.2.1 GOALS AND OBJECTIVES As stated in the Policy Statement of NU, the goals of the NUQAP are t6 maintain quality levels in an effective and effielent manner and to assure a high degree of functional integrity and reliability of quality systems, structures and components. To meet this goal, the .
following objectives of the NUQAP have been defined:
- a. Define through documented procedures, the quality activities that apply to the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of nuclear power plants;
- b. Establish, assign and document the responsibilities for the conduct of those activities affecting quality systems, structures and components;
- c. Establish confidence that (a) the design, fabrica-tion, construction and operation of nuclear power generation facilities are performed in a manner consistent with NU Policies and (b) quality activi-ties are performed by responsible personnel, and f^3 are verified through a system of audits, survell-( ) lances, inspectio,ns, 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 safety and;
- e. Prevent schedule delays and high cost due to poor quality.
2.2.2 PROGRAM DOCUMENTATION This NUQAP Topical Report defines the NU nuclear
- policies, goals and objectives, and is used as guidance for the development of the various implementing divi-sional, departmental, branch, or section procedures.
Revisions to the NUQAP Topical Report will be made as needed to reflect current requirements and descriptions of activities prior to implementation. These revisions will be made in accordance with a Nuclear Engineering and Operations Group Procedure.
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-m Revisions to the NUQAP Topical Report, which reduce -
commitments previously accepted by the NRC, are i'v) submitted to the NRC for review and approval prior to implementation. .
Revisions which do not reduce previously accepted .
commitments are periodically submitted 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 departments which are responsible for portions of these procedures.
These procedures are' approved by the departments which initiate these procedures and are reviewed and concurred with by NUSCO Quality Services Department 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 Superintendent is responsible for implementation of the NUQAP, which includes individual departmental procedure requirements
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applicable only to his respective activities. In addi-tion, he is responsible for the preparation, approval j and distribution of those instructions, operating pro-cedures, testing procedures or other instructions where further guidance is necessary.
2.2.3 SYSTEMS. STRUCTURES. AND COMPONENTS The requirements of the NUQAP Topical Report shall apply, as a minimum, to all activities affecting the safety functions of the systems, structures, and components, as addressed in the Safety Analysis Rrports (SARs) . Safety systems, structures and camponents are functionally identifled in Appendix A of the NUQAP Topical Report and also as specifically identified in each FSAR addressing 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 assurance requirements contained in the code are supplemented by the specific guidance of the applicable regulatory guides listed in Appendix D of this Topical Report.
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For systems, components and structures, Re'gulatory Commitments and NUSCO/NUPOC procedures describe
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() the measures taken to assure that the quality assurance requirements are met.
The degree of control over activities affecting, quality systems, structures and components is consistent with
. their importance to safety. Such controls include use of appropriate equipment, establishment of suitable environmental conditions and assurance that all pre-requisites 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/NUPOC technical organizations jointly determine and identify the extent quality assurance controls are to be applied to quality structures 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 ORGANIZATIONS
( ) The NU organizations with responsibilities for activities
'd' affecting quality systems, structures and components are identified in QAP 1.0, which also briefly describes their assigned responsibilities.
NUSCO Quality Services is responsible for: a) the development, coordination, and control of the NUQAP including coordination of NUSCO Quality Services Department Procedure review and approval; b) control and issuance of the NUQAP Topical Report as a con-trolled 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-constructors, 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 q
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identified in Appendix D of the Topical Report.
T However, NU retains overall responsibility for the QA J-Program. The specific quality activities performed by these organizations are specified in the procurement documents. NUSCO Quality Services reviews and 1 approves these organizations quality assurance programs prior to initiation cf contracted activities, and performs audits, surveillance, inspections, and in- ;
process verification on subsequent activities for compliance to their procedures.
The object of the review is to verify that the engineering-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, suppliers and engineering service organizations' quality assurance programs shall be periodically audited by NUSCO Quality Services to assure continued implementation of quality requirements.
Contractors may be delegated the execution of quality assurance functions by contract. These contracts are reviewed and approved in accordance with NUQAP rm requirements.
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~~'} 2.2.5 INDOCTRINATION AND TRAINING A program 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 performance of quality activities. Quality procedures delineate the requirements for an indoctrination program to assure that personnel responsible for performing quality activities are instructed in the purpose, scope and implementation 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 his department who perform quality activities.
Nuclear training programs shall be developed and implemented to provide training for all individuals
' attached to or associated with NU nuclear facilities.
Additional guidance is established in NUSCO/NUPOC Procedures.
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nuclear training program requirements which assure that:
a Documentation of formal training and qualification programs includes the objective, content of the L. program, attendees, and date of attendance; Proficiency of personnel performing and verifying b.
activities affecting quality is established and maintained. Personnel proficiency is established
- and maintained by training, examination / testing, and/or certification based upon the requirements of the activity. Acceptance criteria are developed to determine if individuals are properly trained and quallfled;
- c. Certificates or other documentation of qualification clearly delineate the specific functions personnel are qualified to perform and the criteria used to qualify personnel in each function.
This program also requires the head of each department (including NUSCO Quality Services) to be responsible for a training plan which assures that personnel performing quality activities are trained in the prin-O ciples and techniques of the activity being performed.
2.2.6 MANAGEMENT PARTICIPATION NUSCO Department Heads /NUPOC Superintendents are responsible for implementing the NUQAP Topical Report within their Departments / Plants. The NUSCO Director, Quality Services will assist in development, coordina-tion and review of the Program.
The Senicr 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 liciensing commitments.
Actions 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, N QAP - 2.0 Rev.: 12 Date:
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- c. Review of past audit resdits such as those conducted by previous Management Reviews,
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- the NRC or other departments.
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The Management Review's findings of deficiencies and recommendations for program improvement are forwarded to the Senior Vice President-Nuclear Engineering and Operations, who will ensure appropriate corrective action is taken.
- The quality assurance programs of the engineer-constructor, L NUSCO contractors, suppliers and engineering service organizations that perform quality activities are reviewed by NUSCO Quality Services to assure that their management regularly reviews the status and adequacy of their part of the NUQAP.
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. j 3.0 DESIGN CONTROL l
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() 3.1 GENERAL REQUIREMENTS
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NUSCO/NUPOC is responsible for controlling design work, admini-stering design control activities (including design interface) and design modifications for quality systems, structures and compo-nents.
The NUQAP for design is established to assure that the applicable design requirements, such as design bases, regulatory require-ments, 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, equipment, parts and processes that are essential to the functions of the systems, structures and components. Changes to, and deviations from specified requirements are identified, documented and controlled.
The responsibility for design control program implementr. tion 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 estab-lishing and executing the design control program or any part
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y]f thereof, NUSCO/NUPOC will retain the ultimate 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 organiza-tions performing design work for quality systems, structures and components are identified and implemented in accordance with documented procedures. This identification includes those organi-zations 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 responsible organization. The individu2.ls performing design verification should not (1) have immediate supervisory respon-sibility for the individual performing the design, (2) have specified a singular 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 for the quality of work performed under their supervision. Where changes to previously verified designs have been made, design verifications are required for the change, p
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, including evaluation of the effects of those changes on the overall p design. Design verification may be accomplished by testing. Test v to demonstrate adequacy under adverse design conditions shall comply with. the requirements of QAP 11.0, " TEST CONTROL."
Design errors and deficiencies which adversely affect quality systems, structures and components in design process are docu-mented, and appropriate corrective action is taken. These design errors and deficiencies are documented in accordance with design change procedures or as defined in QAP 15.0.
1 3.2 IMPLEMENTATION I NUSCO/NUPOC is responsible for the design, design review, engi-neering approval of design changes, design evaluation and design control of nuclear power plants. The function may be delegated to other organizations to perform the design activity, or any part i thereof, but the respc,nsibility for overall design remains with NUSCO/NUPOC. In all cases, final engineering decisions and I ultimate design control of systems, structures and components related to nuclear power plants is the responsibility of NUSCO/ L NUPOC.
NUSCO Quality Services performs audits, surveillance, inspec- l tions, in process verifications to verify that the engineering- I constructors, contractors, suppliers, engineering service organizations and NU departments are effectively complying with (m
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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; com-patibility of materials; accessibility for in-service inspection, maintenance, and repair; and delhichtlon of ;
acceptance criteria for inspections and test. Measures established to control design documents are described in QAP 6.0. j Program procedures anci instructions define the method for implementing design control measures. These measures require that applicable design requirements, such as, i design bases, regulatory requirements, codes and stan-dards, 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 suitabil- o em i 'l !
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ity!of application. The basis for selection may include j
- Industry standards, material and prototype. hardware L]. ' testing programs, and design reviews.
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 completeness and accuracy before release to operations, in accordance with NUSCO/NUPOC 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 require-ments, and the extent of documenting inspection and test results.
3.2.2 DESIGN CHANGE CONTROL g
( ) Procedures and instructions governing design change control during construction, modifications to operating plants, control of discrepant or defielent design condi-tions, 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 changes are subject to design control l 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 quallfled organization to perform this ]
function.
Proposed design change modifications are submitted to the in-service units. management for processing and i review. - This review includes the Plant Operations Review Committee (PORC)/ Site Operations Review Committee (SORC) . PORC/SORC is advisory to the appropriate NUPOC Superintendents on matters relating to nuclear safety. Its composition, responsibilities, and authority '
are defined in Section 6 of each in-service unit Technical l
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.c , Specification. If the change involves a quality system
.l )- structure or component, the change vill be reviewed by
qualified engineering personnel for technical adequacy.
Reviews of the design change requests are performed by the Nuclear Review Board / Environmental Review Board on safety evaluations / environmental questions. The sequence of the NRB review depends upon the determina-tion of whether an unroviewed safety question is involved (i.e. , in accordance with ANSI N18.7, if a proposed change in the facility involves 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:
- a. the adequacy of the proposed change is determined;
- b. unreviewed safety / environmental questions are properly identified and handled per 10 CFR 50.59;
- c. nuclear safety / environmental requirements have been considered.
Errors and deficiencies in design, including the design process, that could adversely affect quality structures,
'l systems, and components are documented and corrective
, ) action is taken to preclude repetition.
During the operations phase, notification of plant design changes are transmitted to responsible plant personnel as part of the design package close out. NUSCO/NUPOC Procedures describe this notification which assures that personnel are made aware of design change modifications which may affect the performance of their duties.
3.2.3 DESIGN INTERFACE CONTROL During design, construction or modifications of' nuclear power plants, the Nuclear Engineering and Operations Group is responsible for review, coordination and docu-mentation of design interfaces. Procedures provide the method for identification of design interfaces, design interface changes, and modificatk,ns affecting drawings and design documents.
During plant design and construction nhases, control of interfaces may be delegated to the engineer-constructor and/or Nuclear Stream Supply System (NSSS) supplier.
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During the operations phase, procedures and instructions
/ ) identify design interfaces which are controlled by the V appropriate NUPOC Superintendent. Resolution of design interface questions are documented.
3.2.4 INDEPENDENT DESIGN VERIFICATION Original designs and design modifications are reviewed for adequacy and the sign-off performed by a person other than the originator of the design. Design verifi-cation 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 performed by testing, the tests are performed using approved pro-cedures, 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 verification (if other than by qualification testing) is normally completed prior to release for procurement, manufacturing, and 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, manufac- i a turing, and construction, procedures ensure that design
(") verification is completed prior to the point when the installation is declared operational.
NUSCO/NUPO'C Procedures describe the requirements which assure the following when testing is considered as an alternate method of design verification:
- a. Specifications or procedures provide criteria that specify when 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 instal-lation is declared operational.
- c. Verification by test performed under conditions that simulate the most adverse conditions as determined by analysis.
I Particular emphasis is placed on assuring that designs are in conformance with applicable codes, and on selecting the proper design verification or checking method. !
Proce.dures and instructions provide the requirements I ,
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. rs . and necessary ' controls for design verification. These
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controls include a review to assure that design charac-V)~ teristics 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.
NUSCO/NUPOC Procedures include requirements'which -
identify the responsibility of design verifiers, the areas and features to be verified, and the extent of the docu -
mentation.
NUSCO/NUPOC Procedures assure that procedural control is estab)1shed 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. -
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( ). NUSCO/NUPOC is responsible for assuring that the design documents generated by the engineer-constructor, contractors, suppliers and engineering service organiza-tions are adequately generated, approved and maintained.
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V).. 1 4.1 GENERAL REQUIREMENTS The procurement of materials, equipments, parts and/or services 'l required during the' design, construction, testing, operation and j
. maintenance of quality systems, structures and components in :'
nuclear power plants is performed in a controlled manner which assures compliance with applicsble regulatory requirements, proce- 1 dures, quality assurance standards and regulations affecting
, procurement documents; Changes to procurement documents are subject to the same degree of control as utilized in the preparation i of the' original documents. i i
e 4.2 IMPLEMENTATION 4.2.1 PROGRAM A Project Manager and/or a Project Engineer are selected l for each 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 adequ acy and inclusion of quality assurance requirements.
NUSCO/NUPOC Purchase Requisitions are reviewed for technical adequacy and verification. of the quality desig-nation. The appropriate NUSCO Project Engineer /NUPOC Superintendent 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 to the issuance of the purchase order.
Any engineer-constructors, contractors, suppliers and engineering service organizations uttilzed 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, surveillance, inspections and in process verifications to ensure organizations utilized by NUSCO/NUPOC are effectively complying with their requirements for the control of procurement documents.
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- - j Changes to procurement documents, whether initiated by l z
n) NUSCO/NUPOC or their representative, are subjected to q" ~-
the same degree ~ of control as - that utilized in the prepa-ration of the original document. The procurement of spare or replacement parts for quality systems, structures, or components is subject to the controls of ,{
the latest NU QA_ Program and NUSCO/NUPOC procedure !
requirements. The spare or replacement parts are l
- subject to controls equivalent to original or subsequent '
codes and standards.
Procurement documents are reviewed by Quality Services personnel to determine that:
- a. The quality assurance requirements are correctly stated, auditable and controllable;
- b. There are adequate acceptance and rejection criteria.
- c. The procurement document has been prepared, reviewed, and approved in accordance 'with the NU -
QA program requirements. -
l 4.2.2 PROCUREMENT DOCUMENT PROVISIONS Procurement documents are prepared, reviewed and N
( 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 performed;
- b. Technical requirements (specified or referenced) l including the applicable components and materials - !
identification requirements, drawings, specifica- ,
tions, procedures, instructions, codes and regula-tions, and the identification of applicable test, I
inspection and acceptance requirements, or special l process instructions; 1 .
- c. Quality Assurance Program requirements to be imposed on contractors which include the applicable requirements 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; 1
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- d. Right of access which provides, as appropriate, for
( access to contractor facilities and records for V} .-
inspection or audit by NUSCO or its designated representative; and provides access for events such
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1 as those requiring notification of hold points; 1
- e. The documentation required to be prepaied, maintained, i and/or submitted to NUSCO/NUPOC or its representative for review, approval or historical record. The time )
of submittal of this documentation and the retention and disposition of quality assurance records which l
are not submitted to NUSCO/NUPOC is prescribed, as applicable, for NUSCO/NUPOC-engineered procurement.
i 4.2.3 SELECTION OF PROCUREMENT SOURCES i I
'If the engineer-constructor, contractor, or supplier is j not delegated the function of procurement source selection, I the NUSCO Purchasing Department verifles 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 ~i required for the procurement of nonengineered items j which are: (
! (q a. Re!atively simple and standard in design, manufacture, f I and test (i.e. , off-the-shelf item, the catalog I number is in effect, a specification which controls the manufacture of the item) and;
- b. Adaptable to standard or automated inspections and/
or tests of the end product to verify quality charac- >
teristics after delivery and;
- c. Of such a nature that product acceptancs laspections/ ,
test performed upon receipt of items do not require operations which could adversely affect the integrity, function, or cleanness of the item.
Procurement documents may be issued to organizations
, with unapproved quality assurance programs. These procurement documents to unapproved organizations
- contain detailed supplementary quality assurance require-ments and/or witness / hold point to meet NUSCO require-ments. j l
Procurement documents are reviewed by NUSCO Quality Services to ensure appropriate quality assurance f
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requirements ~are specified. These requirements,-
F:/ }. Included in :the procurement document as: necessary,
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' include acceptance' criteria, audits and/or inspections. at the suppliers facilities with scheduled witness / hold points
'during the; fabrication process .and/or' prior to shipment of the procured item. Acceptance inspections and tests
'R determined by. NU shall' be . performed ' after receipt at NU but prior (to operation.
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f,ss-5.0 PROCEDURES. INSTRUCTIONS. AND DRAWINGS U' ~
-5.1 GENERAL REQUIREMENTS The NUQAP provides measures for the preparation, review, approval, control and distribution of procedures, instructions and drawings of activities 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 performed, the methods of construction and testing to be employed, materk'., equipment or parts to be used, a sequence of operation and ;ae required documentation.
5.2 - IMPLEMENTATION
, Quality Procedures provide direction for personnel performing quality functions. NUSCO Quality Services Department reviews and concurs with- Quality Procedures. Comments concerning compliance with the NUQAP Topical Report and regulatory requirements are resolved prior to issuance of the procedure. NUSCO Quality Services receives controlled copies of Quality Procedures issued by other departments. Any engineer-constructors, contractors, suppliers, and engineering service organizations utilized by NUSCO/
NUPOC in the design, construction, testing, operation, maintenance Q and modifications to nuclear power plants may be delegated respon-() sibility for preparing, maintaining, issuing and verifying the implementation of appropriate program documents which are selec-tively reviewed / approved by the appropriate NUPOC Superintendent, NUSCO Director, Generation Construction, or Project Engineer, as appropriate. In this case, NUSCO Quality Services performs on-site and off-site audits / surveillance / inspections /in process verifications of the quality assurance programs to ensure the engineer-constructor, contractor suppliers and engineering service organizations are effectlyely 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 accor-dance with written procedures and instructions.
The NUSCO Director, Generation Construction, or Project Engineer, ensures that any engineer-QAP - 5.0 Rev.: 12 Date:
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- constructors, contractors, suppliers and engineering
( ) service organizations utilized by NUSCO/NUPOC in the v' design, construction, testing, operation, maintenance and modifications to nuclear power plant, implement quality assurance 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 control inspection procedures are reviewed for concurrence by NUSCO Quality Services to assure compliance with the Program.
The NUPOC organization is respon' s ible for the prepa-ration, review and approval of plant Quality Procedures.
The procedures include test procedures and overall site administrative procedures which implement the require-ments of the NUQAP Topical Report. Each NUPOC organization is also responsible for the preparation, review and approval of procedures covering quality activities in accordance with individual license requirements. The NUSCO Quality Services Department reviews and concurs with all quality procedures.
5.2.2 DRAWINGS The design control and verification measures described in QAP 3.0, are applicable.for the review and approval (j}
j of drawings. The appropriate NUPOC Superintendent has the ultimate responsibility, which can be delegated, for review and approval of new drawings or modifications to existing drawings. The originating organization may delegate to other organizations or departments the work of design and review activities, or any part thereof, but retains ultimate 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 I are available to the operating personnel.
5.2.3 ACCEPTANCE CRITERIA Cognizant Department Heads review and approve depart-mental procedures, instructions and drawings to ensure the inclusion of adequate quantitative and qualitative acceptance criteria, as appropriate, for determining satisfactory work performance and quality compliance.
These criteria apply to activities such as design,.
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L. 6.0 DOCUMENT ' CONTROL
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4k 6.1 ' GENERAL REQUIREMENTS The' NUQAP provides measures to assure e ntrolled distribution of documents pertinent to quality assurance for the design,' construc-tion', 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, ins.tructions, drawings, specifica-g tions and; reports are prepared, reviewed for appropriate qualita-l tive 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 performed the original' review and approval, unless otherwise specified in the implementing procedures. Measures are provided for controlling documents to preclude- the possibility of the use of outdated documents.
6.2. IMPLEMENTATION l 6.2.1 RESPONSIBILITY N
'V NkJSCO/NUPOC. Procedures and Instructions delineate the
. measures for controlling documents including' direction for the review for adequacy, approval by authorized personnel, distribution of controlled documents and verification that changes are promptly incorporated 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 Documents;
- d. Quality Assurance Program Manuals, Procedures and Instructions;
- e. Manufacturing, Inspection and Testingr Instructions;
- f. Test Procedures; O QAP - 6.0 Rev.: 12 Date:
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- g. Final Safety Analysis Report;
- h. Procurement Documents: .
- 1. Design Change Requests; ,
J. Topical Report;
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- k. Nonconformance Report;
- 1. Computer Codes.
l NUSCO/NUPOC Procedures describe the measures taken by NUSCO Quality Services or individuals other than the person who generated the document but qualified in quality assurance, for the control of documents to assure review and concurrence, as necessary, for such documents listed above with regards to quality assurance aspects. {
The 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 doctunents to appropriate locations.
There shall be provisions to assure that approved changes
/ are included in instructions, procedures, drawings and V] other documents prior to implementation of the changes.
Any engineer-constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/
NUPOC .% the design, , construction, testing, operation, maintenance, and modifications to nuclear power plaats 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 control. NUSCO Quality Services performs periodic on-site and off-site audits, surveillance, inspections, and in process verifications of the en'gineer-constructors, contractors, suppliers and engineering service organizations to verify compliance with their approved quality assurance programs.
6.2.2 DISTRIBUTION OF CONTROLLED DO_CUMENTS NUSCO/NUPOC Procedures, specify in what manner controlled documents and revisions thereof, are distrib-uted to appropriate locations, prior to commencing the work. Holders of controlled copies of documents complete acknowledgement of receipt forms and return them to the TN QAP - 6.0 Rev.- 12 Date:
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distributor in order to assure that obsolete or supeiseded
/ ) documents are removed from the work areas in a timely
'v' manner. NUSCO Quality Services perform periodic on-site and off-site audits, surveillance, inspections, and in process verifications to verify compliance with the 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 submitted by the cognizant NUSCO/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.
The engineer-constructor, contractors, suppliers and -
engineering service organizations utilized by NUSCO/
NUPOC during the design, construction 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.
( N. NUSCO Quality Services Department performs on-site and
() off-site audits, surveillance, inspections, and in process verifications of suppliers to verify they are effectively complying with their programs for document control of drawings.
6.2.4 INSTRUCTION AND PROCEDURE CONTROL NUSCO Quality Services Department performs audits, surveillance, inspections, and in-process verifications of NU departments and any engineer-constructors, contractors, suppliers and engineering service 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.
The originating department is resp'onalble 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.
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- 7 7. 0 CONTROL F PURCHASED MATERIAL. EQUIPMENT AND SERVICES 7.1 GENERAL REQ.UIREMENTS
. 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 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
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otherwise described as the engineer-constructor, contractor, supplier or engineering service organization.
The evaluation and selection of suppliers is performed in accordance with procedures, which specify that procurement source evaluation and selection measures are performed to determine supplier capa-(3 bility and delineate responsibilities of qualified personnel involved
() in the evaluation and selection process.
7.2.1 NUSCO Q' u ality Services utilizes one or more of the following methods in evaluating the qualifications of a potential supplier:
- a. Audits and/or coordinated review of a potential supplier utilizing one or more departments (i.e. ,
Engineering, Construction, Operations and/or Purchasing) ;
- b. Engineer-constructor or other utility supplier audits and evaluations;
- c. Coordinating Agency for Supplier Evaluation (CASE) evaluations . j
- d. ASME N, NA, NPT, NV, or MM/MS Certificate of
. Authorization. .
- e. Commercial grade periodic surveys and/or coordinated review of a potential supplier utilizing V QAP - 7.0 Rev.: 12 Date: '
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v 73 one or more department:, (i. e . , Engineering,
- l j j Construction, Operations and/or Purchasing) .
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Evaluations ensure that NU suppliers employ a quality assurance program that conforms to applicable portions ,
I of the NUQAP Topical Report. -
NUSCO Quality Services maintains documented evidence of the evaluation and acceptance of the supplier's 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, surveillance and evaluations of the supplier's quality assurance program.
Suppliers Certificates of Conformance are periodically evaluated by audits, commercial grade periodic surveys, surveillance, independent inspections and tests, to assure they are valid. This verification of Certificates of Conformance is documented.
7.2.2 SOURCE INSPECTION NUSCO Quality Services is responsible for the performance of source inspections at suppliers facilities to ensure that the requirements of a Purchase Order Contract have
- Q been met.
%)
Source inspections are performed in accordance with written procedures which provide for:
- a. The method of inspection and the extent of documen-tation required and those responsible for implementing those instructions;
- b. Inspection of those items where verifications of procurement requirements cannot be determined upon receipt.
7.2.3 RECEIPT INSPECTION Receipt liispection for procured items is performed under
- the direction of NUSCO Quality Services Department in accordance with quality procedures 'which delineate requirements and responsibilities necessary to perform inspection functions. Contractual obligation fulfillment and quality assurance requirements are verified during receipt inspections.
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Receiving inspection of supplier-ftirnished material, j i equipment, and services is performed to assure that V ~
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;
- 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 items;
- f. Measures to ascertain that inspection records or rm certificates of conformance are available prior to release to construction / plant for installation.
7.2.4 SUPPLIER 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 require-ments , (e.g. , codes, standards and specifications) met by the items;
, b. Documentation that identifies any procurement I
requirements which have not been met, together with a description of those nonconformances dispositioned " accept as is" or " repair" QAP - 7.0 Rev. : 12 Date:
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3,.-q The responsible- NUSCO Quality. Services personnel shall.-
-t t review for acceptability those documents which pertain', to V the~ requirements:in the procurement document, in accordance with the NUQAP Topical Report and its-applicable procedures.
7.2.5 NUSCO/NUPOC Procedures address the measures taken to assure that for nonengineered. "off-the-shelf" items, where specific quality assurance controls for nuclear ~
, applications can be imposed in a practicable manner, ..
j' l that special verification requirements are established and described.
These.' measures 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 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.
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,.3 _ 8.0 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND cl )- COMPONENTS i
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8.1 GENERAL REQUIREMENTS NUSCO/NUPOC organizations assure thet the identification of inspections, 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 partially fabricated assemblies, during design, construction, testing, operation, main-tenance 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. Documenta-tion associated with material, equipment, and components verify that these items have been designed, fabricated, manufactured, tested, and inspected in accordance with the specified require-ments. The object of these controls is to prevent the use of incorrect or defective materials, ~ parts and components, h1 accordance with 10 CFR 50, Appendix B.
8.2 IMPLEMENTATION f~%
(')
NUSCO/NUPOC Procedures establish the responsibilities and require-ments for the identification and control of materials, parts and component: The procedures assure that identification and control is maintained throughout fabrication, receipt, handling storage and instr.llation of items, Provisions include:
- a. Requirements for traceability to appropriate docuntentation such as: procurement documents, manufacturing documents, .
drawings, specifications, certifications, inspection and test records, and nonconformance 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 not affect the function or quality of an item.
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- d. Establishment of identification requirements in specifications, drawings, procurement documents, procedures or instructions.
During the design, construction, testing, operation, maintenance or modifications to nuclear power plants, NUSCO/NUPOC may QAP - 8.0 Rev.: 12 Date:
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"4 ,, 9d delegate any portion of'the implementation of the identification and
. control program to any engineer-constructors, contractors, suppliers
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L and engineering service organizations utilized by NUSCO/NUPOC in I the design, construction, testing, ' operation, maintenance and modification to nuclear power plants, as appropriate. If delegated, :
contracts require that the contractor establish an identification and control program which meets the NUQAP Topical Report requirement.
In this caso NUSCO Quality Services performs on-site and off-site ;
audits, surveillance, inspections, and in process verifications of the engineering-constructor, contractor, supplier, engineering serv' ice organization's quality assurance program to ensure they are effectively complying with these requirements for identification and control of material, equipment and components. ,
Receipt inspections are performed to verify that materials, equip-ment and components are properly identified in accordance with procurement requirements. NUSCO Quality Service.- 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 identification are implemented to assure proper identification and traceability.
In the event that the equipment, material or component is noncon-forming or the identification becomes lost or illegible, the items are considered nonconforming and are identified and controlled in accordance with QAP J 5.0.
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4 9.0 CONTROL OF SPECIAL PROCESSES
- l. L] 9.1 GENERAL REQUIREMENTS The NUQAP provides measures to assure control of special processes associated with quality systems, structures and components by the use of qualified, 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.
9.2 IMPLEMENTATION During design, construction testing, operation, maintenance, and modification of nuclear power plants, the NUSCO Project Engineer is responsible for ensuring that special process data and docu-mentation is reviewed, and that contractors, engineer-constructors, suppliers, and/or engineering service organizations special process procedures utilized at nuclear power plants are qualified and approved, and tlat personnel and equipment utilizing special processes are properly qualified prior to start of work. NUSCO o Quality Services personnel perform on-site and off-site audits, I
j surveillance, inspections, and in process verifications to ensure the engineering-constructors, contractors, suppliers, and engineer-ing service organizations are effectively complying with their quality assurance program requirements for control of special processes.
NUPOC special process procedures utilized during testing, operation, maintenance, modification and refueling of the in-service nuclear power plant are prepared, reviewed and approved in accordance with procedures as specified in QAP 5.0.
9.2.1 PROCEDURE Q. QUALIFICATION _AND CONTROL NUSCO/NUPOC Procedures speevy that written process control documents n're utilized Md qualified, as required, in accordance the applicable specification, codes or standards.
9.2.2 PERSONNEL QUALIFICATION AN_D_ C. CERTIFICATION Codes, standards and NUSCO/NUPOC procedures specify personnel qualification / certification requirements.
Cl QAP - 9.0 Rev.: 12 Date:
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.- Personnel responsible for the performance and verifi-
[ ) cation of special processes are trained, tested, and i certified as required by applicable specifications, codes and standards. Requirements for the period of certifi-cation, retesting, and decertification of personnel are also specified. Contractors qualify personnal and maintain records of quallfled personnel in accordance with applicable codes, standards, specifications, and contractor procurement document requirements. Quality Services Department is responsible for the review of records of qualified personnel, equipment and procedures i, associated with special processes.
The NUSCO Director, Quality Services is responsible for the training, 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- 1 A .
9.2.3 SPECIAL PROCESS RECORDS Records provide objective evidence that special processes were performed in accordance with approved procedures, by qualified personnel, and that when required by procedures, specifications, and codes, such performance was verified. Results of nondestructive examinations are
~~T recorded in accordance with applicable specifications, I
,1 codes and standards. These records are retained by the supplier or suppl!ed to NUSCO/NUPOC as required by contract or purchase 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.
Special process documentation such as special process procedures, qualifying data, and personnel and equipment qualification records associated with the performance of special processes at nuclear power i plants, are kept current and maintained in appropriate NUSCO/NUPOC files, with final disporeition to the *
} appropriate NU Nuclear Plant Records Facility .
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. 10.0 INSPECTION i .
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10.1 GENERAL REQUIREMENTS Inspection of activities to verify the quality of systems, structures and components, which are performed by or for Northeast Utilities I
l (NU), are executed in accordance with the Quality Assurance '
Program (NUQAP) and appropriate procedures, instructions and drawings by qualified personnel independent from the individual or j group performing the activity being inspected. If inspection is -
impossible or disadvantageous, indir.ect controls by monitoring processing methods, equipment and personnel are provided.
Inspection notification and hold points are identified, as required, in the applicable documents.
10.2 IMPLEMENTATION 10.2.1 INSPECTION RESPONSIBILITIES During construction, testing, maintenance, modification, and operation, quallfled NUSCO Quality Services personnel shan review work procedures in order to determine the need for:
- a. Inspections (e.g. , receipt inspections, installation, a system turnover, and product acceptance);
)
V Identification of inspection personnel; b.
- c. Documentation of inspection results.
The review also ensures that the necessary inspection requirements, methods, and acceptance criteria have been identified.
NUSCO Quality Services performs audits, surveillance ,
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 per forming /
witnessing inspections at " hold" or " notification" points identified in NUSCO/NUPOC procurement documents. All audit, surveillance, inspection, and in process verifi-cation activities are performed under requirements specified in written quality assurance procedures.
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o 10.2.2 INSPECTION PLANS AND SCHEDULES 4
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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 NUSCO-directed activities of nuclear plants, NUSCO Procedures provide criteria for the determination of accuracy requirements of inspection equipment and when inspections are required. These procedures describe requirements for the preparation of inspection plans and schedules by the NUSCO Quality Services Department.
NUSCO Procedures also describe requirements for audits and surveillance performed by the NUSCO Quality Services Department to assure the implementation of the inspection plans and schedules.
During the operations phase of nuclear plants, inspection activities are performed in accordance with NUPOC/
NUSCO procedures. NUSCO Quality Services participates in inspection activitics by the review of the work proce-(' dures and the preparation and approval of inspection Q} plans .
The inspection criteria, including t"1e 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 appro-priate codes, standards, and/or NU training programs;
- b. Inspections are performed by NUSCO Quality Services personnel or by quallflod contracted personnel who are independent from undue pressure such as cost and schedule. When NUPOC plant personnel / contracted personnel perform inspections, their inspecticn plans / procedures and personnel qualification criteria are reviewed and found acceptable by the NUSCO g) i
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Quality Services Department prior to the initiation
- ' /qO - of the activity; li ( f
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- c. Access to drawing:, precedures; ' spec!MenMene er f' other documented criteria necessary for the perfor-l mance of inspections-is provided. prior to perprming the inspection activity.
10.2.4- INSPECTION PROCEDURES
- a. Required inspection or surveillance activities are performed and documented according to' written, ,
approved procedures' and/or checklists. Inspection procedures, plans or checklists contain the .following:
(1) Identification of characteristics to be inspected; (2) Identification of the individual or groups responsible for performing the inspections; (3) Requirements for the necessary measuring and test equipment and the required accuracy of this equipment; (4) Acceptance criteria;
' p (5) A description of the method of inspection;
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(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.
- c. Modification, repair, replacement or rework items are inspected in accordance with original inspection requirements or approved alternatives.
10.2.5 MANDATORY HOLD AND NOTIFICATION POINTS Mandatory hold points are utilized when an inspection /
operation must be performed or witnessed and signed o:f'
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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, construction, installation process. Mandatory hold and y+
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, ,. noillication: points, as required, are identified in procure-- {
.( L ment documents. and procedures. ' These documents are :
ML/): subject to the review and concurren'ce of NUSCO Quality .
Services. for adequacy of inspection, notification and/or- I mandatory hold controls.
10.2.6 INSPECTION RESULTS EVALUATION Inspection restilts are evaluated for acceptability in accordance with approved NUSCO/NUPOC Procedures which identify the responsible organization.
1 The evaluations are performed by. the responsible NUSCO/
. NUPOC persennel who are qualified in accordance with the appropriate Regulatory Guide / ANSI Standard commit-ments listed in Appendix D.
NUSCO Quality Services performs audits, surveillance, and in process verifications to assure that inspections
' are performed'per the requirements of applicable NUSCO/
NUPO,C Procedures, r
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. 11.0 TEST CONTROL
) i a-11.1 GENERAL REQUIREMENTS i A documented test control program is established by the NUQAP for systems, structures and components to ensure that they will perform 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 assure 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 following repairs, replacements or modifications.
11.2 IMPLEMENTATION 11.2.1 TEST PROGRAM Test requirements to determine or to verify the capa-
'n J bility of an item to meet specified requirements in accordance with engineering / design documents, Safety
'"' Analysis Reports (SAR), technical specifications, procedures or procurement documents, as appropriate, are accomplished by subjecting the item to a set of physical, chemical, environmental or operating conditions. Retest following repair, replacement or modification is performed in accordance, with the original design requirements or acceptable 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 and modification of nuclear power plants.
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 measures for the control of tests to ensure that materials, equipments and parts, will perform satisfactorily. NUSCO Quality Services
,m IV) QAP - 11.0 Rev.: 12 Date:
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7 7s performs on-site and off-site audits, surveillance, j inspections, and in process verifications of selected w/ proof tests when " notification" points have been iden-tified in Purchase Order / Contracts of the engineer, constructors, contractors, suppliers and engineering service organizations to verify they are complying with their quality assurance program requirements for test control. Documentation associated with these observa-tions are maintained by NUSCO Quality Services.
Proof tests, product acceptance tests, retests, and periodic surveillance tests are conducted by quallfled personnel in accordance with approve'd procedures.
Personnel performing tests ensure that calibrated equipment and instrumentation utilized ara within the calibration interval specified. Documentation including test procedures and approved data sheets are maintained in appropriate files.
11.2.2 TEST PROCEDURE PREPARATION A_ND TEST PERFORMANCE Testing is accomplished in accordance with approved test procedures which incorporate or reference the requirements and acceptance criteria in the applicable design and procurement documents. The test procedure or test program documents include the following as a minimum:
7
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- a. Instructions for the testing method used;
- b. Required test e,quipment and instrumentation;
- c. Test requirements, such as acceptance and rejection criteria;
- d. Hold, notification, inspection and data collection points;
- e. Test prerequisites such as: calibrated instrumen-tation; trained, qualified, and licensed or certified personnel; preparation, condition snd completeness of item to be tested; suitable and controlled environmental conditions;
- f. Methods for documenting or recording test data and results;
- g. Provisions for data collection and storage.
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11.2.3 - TEST EQUIPMENT t
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' NJ t NUSCO/NUPOC Procedures provide the criteria for 4 determining when a test % required and the accuracy -
l requirements of test eqi nent .
During the operations phase of a nuclear plant, the following steps are taken:
- a. To ensure accuracy, test instrumentation is checked and calibrated in accordance with NUSCO/NUPOC proceilures,
- 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. ,
- c. Where special histrumentation is required for testing, the requirer. ants are stated in the procedures. !
Instrument characteristics, including accuracy requirements, are equivalent to or better than those specified by the _ s endor.
11.2.4 EVALUATION OF TEST RESULTS
.e The documented test results are evaluated against the
(^j predetermined acceptance criteria by an individual or
- group having appropriate qualification'ns. The acceptance -
- status of the test is documented. Deficiencies noted
- during the' evaluation are documented and dispositioned in accordance with approved procedures.
The evaluation of test results may also be delegated to other organizations. The evaluating organization is required to assure the use of qualified personnel, evaluate the data against predetermined criteria and document the results of the evaluation and acceptance status of the test. NUSCO Quality Services performs audits ,' surveillance n , inspections, and in process verifications to verify that these organizations are .
effectively complying with their quality assurance program requirements for test control.
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j.. , 12.0 CONTROL OF MEASURING AND TESTING EQUIPMENT
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Nj 12.1 GENERAL REQUIREMENTS 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 measure-ment of materials, equipments 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 respon-sibilities for the control, maintenance and calibration of M&TE { including portable and installed instruments, tools, gages, fixtures, reference and transfer standards, and nondestructive test equipment) .
All documentation associated with M&TE is maintained in appropriate files, with eventual incorporation into the NU Nuclear Records Organization.
(y During NUSCO-directed activities on a nuclear plant,
( "') with the 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 conformance with the requirements of procurement docu-ments, 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 approves procedures relate r to the cabbration program. Department heads / Job Supervisors are responsible to ensure that M&TE equip ment is calibrated, issued, and controlled in accordance with the requirements of the procedures. During Genera-tion Construction-directed activities, the Job Supervisor 1 p)
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shall ensure that the users of the M&TE are properly j instructed in the use and control of the M&TE. Depart-p () ment Heads are responsible for calibrating M&TE within L
, the required frequency and for reviewing calibration L data associated with M&TE calibration by outside vendors in accordance with the procedures.
NUSCO Quality Services performs audits, surveillance, inspections, and in process verifications to verify implementation of the calibration program.
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 measures for the control of M&TE to ensure they are properly calibrated, adjusted and maintained at snecified intervals in order to maintain accuracy within required limits. NUSCO Quality Services performs on-site and off-site audits, surveillance, inspections, and in process verifications of the quality assurance programs of the engineer-constructors, contractors, suppliers and engineering service os mi-zations to verify they are effectively complying with their requirements for control of M&TE.
( 12.2.2 CALIBRATION STANDARDS
- Measuring and test equipment is calibrated at specified intervals based on the required accuracy, purpose, degree of usage, 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 reference and transfer standards are traceable to nationally recognized standards 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 have accuracy of at least four times the required accuracy of the equJpment being calibrated. When this is not possible, the 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-n k._) QAP - 12.0 Rev.: 12 Date:
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i directed activities)- In addition, the calibrating standards.
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- shall have greater accuracy ti.an secondary standards" .
'v' 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.
I ' Implementing procedures describe the measures utilized in ordor to maintain the proficiency of the measuring and test equipment. I 12.2.3 "OUT OF TOLERANCE" CONTROL s
M&TE and reference standards when found out of tolerance are so identified and removed from service. A review is conducted to determine the validity 'of previous inspec-tion or test results gained through use of the instrument, and of the acceptability of items previously measured or tested.'
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13.0 HANDLING. STORAGE AND SHIPPING , .
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13.1 GENERAL REQUIREMENTS 1 Measures are established by the NUQAP using approved procedures, instructions and procurement documents to ensure proper handling, storage', shipping,- cleaning and preservation of material, equip-ment and parts. These measures are imposed. during the design, procurertent, construction, . testing and operation of nuclear, power plants.and modifications thereto, in 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 implemen-tation of established design and specification require-ments.
Handling, storage, cleaning and preservation require-i ments of material, equipment and parts is conducted in l q. accordance with written procedures and procurement Q 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 hnplementing measures for handling, storage, shipping, cleaning and preserving materials equipment and parts to preclude damage, loss or deterioration. NUSCO Quality Services performs audits, surveillance, inspections, and in process verifications to verify that NUPOC, contractors, suppliers and engineering service organizations are effectively implementing and complying with the approved procedures and instructions for handling, storage, shipping, cleaning; and preserva-tion of materials, equipments and parts.
13.2.2 ESTABLISHMENT OF SPECIAL HANDLING. STORAGE2 l SHIPPING. CLEANING AND PRESERVATION REQ.UIREMENTS Special or additional handling, storage, shipping, cleaning and preservation requirements are to be
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requirements are consistent with thej regulatory. positions
, of th'e NRC Regulatory Guides and their endorsed ANSI Q- ,
Standards-listed in: Appendix D of the NUQAP Topical ~
Report,' or specifications and/or supplier technical +
1-manuals, and will be consistent with accepted industry l standards.
NUPOC Precedures describe the measures taken for the storage of chemicals, reagents (including control of shelf l life), lubricants, and other consumable materials.
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14.0 INSPECTION. TEST AND OPERATING STATUS -
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14.1 GENERAL REQUIREMENTS .
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 inadver-tent' bypassing of inspection and test requirements. These measures provide for the identification of items which have satisfactorily !
passed required inspections and tests. Measures are also estab-lished for indicating the operating status of systems, structures and components to 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 measures for the identification of inspection and test status of material, equipment and parts to preclude the bypassing of require-((~N) ments. NUSCO Quality Services performs on-site and j off-site audits, surveillance, inspections, and in-process verifications of the engineer-constructors, contractors, suppliers and engineering service organi-zations to verify that they are effectively complying with their requirements for identification of inspection ard test status, in compliance with approved procedures and instructions. Elements of this system require that 3 suppliers and contractors have a controlled manufac-turing and test operation, in order to preclude the inadvertent bypassing of process inspections or tests, and to provide a positive identification of component status throughout all phases of manufacturing, testing, and inapection by means of tagging,. routing cards, i stamping, manufacturing or test reports, labeling or l other appropriate methods. I When Receipt Inspections are performed at the NU Nuclear i Generating Facilities, NUSCO Quality Services ensures I that traceability is maintained of acceptable materials, equipments and parts, to indicate conformance to Purchase Order / Contract requirements. Nonconforming materials, i I
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equipment and parts are identified in. accordance with f-s-
-(v ).. QAP 15.0.
During tests and inspections of operating nuclear power plants, a status tagging system is implemented,' as per approved procedures and instructions, to prevent inad-vertent operations of system;, structures and' components.
NUSCd/NUPOC Procedures describe the measures taken -
to control the altering of the sequence of required tests, inspections and other operatione taken by Generation Construction / Operations.' The review and approval for these actions is subject to the same control as taken during the original review and approval of tests, inspec-tions and other operations.
14.2.2- STATUS IDENTIFICATION AND CONTROL -
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 op9 ration, 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. #
Records associated with status identification are maintained in accordance with approved procedures.
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3 '15.0 NONCONFORMING MATERIALS. PART_S, COMPONENTS, OR SERVICES
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'j 151 GENERAL REQUIREMENTS The NUQAP requires that documentation and control of noncon-forming materials, parts, components, or services utilized in systems, structures and components during destgn, construction, testing, operation and maintenance of nuclear power plants and modifications thereto, be performed in accordance with approved procedures in order to prevent inadvertent use or installation.
These procedures include appropriate requirements for identi-fication, dwumentation, segregation and disposition of nonconfortedng items, and notification to affected organizations.
In accordance with procedures, nonconforming materials, parts, components, or services are reviewed and accepted, rejected, repaired or reworked.
15.2 IMPLEMENTATION 15.2.1 PROGRAM Approved procedures define the responsibuities and establish measures for identification, documentation, segregation, review and disposition of nonconforming materials, parts, components, or services, and notifi-O cation to affected organizations. Each NU department is x ) responsible for the identification, control and disposition of nonconformances within the scope of their departmental responsibilities.
NUSCO Quality Services performs on-site and off-site audits, survelilances, inspections, and in process verifications of any engineer-constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC to verify these organizations are effectively complying with their quality assurance program requirements for documentation and control of l nonconforming materials, parts, components, or services.
15.2.2 DOCUMENTING AND CONTROLLING NONCONFORMANCES Nonconformances of systems, structures and components are documented and reported as requiring corrective action. Approved procedures delineate contrt,ls required for further processing and installation of nonconforming items. These controls include:
- a. Physical identification of received materials, parts, j or components as nonconforming is maintained by a b QAP - 15.0 Rev.: 12 Date:
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'[ .n . system of tags'which is a*dminihtratively controlled by NUSCO Quality Services,
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- b. Installed nonconforming items are controlled by suitable tags and/or documentation, until properly dispositimted by NUPOC procedures.
15.2.3 DOCUMENTATION Documentation ~ of nonconforming items requires identi-
.fication of the items, description of the nonconformance, disposition of the nonconformance, inspection require-ments and signature approval of the disposition. A trend analysis, which includes nonconformances, is performed by NUSCO Quality Services in accordance with
. approved procedures. The trend analysis results are F
periodically reported to the NUSCO Director, Quality Services and then to upper management, including the Senior Vice President, Nuclear Engineering and Operations, for review and assessment.
' An engineering evaluation is performed, if necessary, prior to the resolution of nonconformances relating to systems, structures and components.
15.2.4 EVALUATION AND DISPOSITION A
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Evaluations are performed to determine the disposition of nonconforming items and services. The evaluation deter-mines whether an item or service is to be used as is, returned to supplier, repaired, reworked, scrapped or salvaged. These evaluations assure that the final condition does not adversely affect safety, operation or
, maintenance of the item or service, or of the component or system in which the item is installed or on which the service is performed. Applicable information is accumu-lated and records are maintained.
The engineer-constructors, contractors, or NUSCO/
NUPOC personnel are required to report to the NUSCO Discipline. Engineering Supervisor (Nuclear Engineering and Operations Organizations), or the appropriate NUPOC Superintendent, as applicable, to obtain release of nonconformist item ^ or service prior to its installation or use. These release items are identified by a noncon-formance Tagging System which defines the description L of the nonconformance and its nonconformance status.
L Nonconformance reports dispositioned "use as is" or
" repair" are forwarded to the appropriate NUSCO Discipline Engineering Supervisor (Nuclear Engineering
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w;9 and Operations Organizations), NUSCO' Project Engineer, i 4 or the appropriate NUPOC Superintendent, as applicable,
- 'd for reviewand- approval. The NUSCO Discipline Engineering Supervisor may approve NCRs generated under their area of responsibility for work that is being performed prior to system turnover and testing.
NUSCO Quality Services performs audits, . survelliances and in process verifications to' verify that NUSCO/NUPOC dispositions for nonconformance reports are adequate.
In addition,. the status of all matorials, parts, or components is maintained by a system of tags, which is administratively controlled by NUSCO Quality Services.
During NUSCO-directed activities of a nuclear plant, NUSCO Generation Construction and NUSCO Quality Services are responsible' for documenting the status of nonconforming, inoperative, or malfunctioning struc-tures, systems, components, and services as described in NUSCO Procedures. During NUPOC-directed activities
.of a nuclear plant, the status of nonconforming, inoperative, or malfunctioning systems, structures, components, and services is documented as necessary by NUSCO Quality Services and NUPOC Operations personnel as described in applicable NUPOC Procedures.
Ine need to release nonconforming materials, parts or p components shall be based on such considerations as:
- a. Impact on plant safety;
- b. Safety of personnel;
- c. Suitability of material or items in the "as is" '
condition, i.e. , probability of eventual satisfactory resolution of the nonconformity without repair, rework or replacement; .
- d. Accessibility of material or items af ter release;
- e. Cost of removal and repair or replacement should material or items eventually have to be removed, repaired, or replaced; i
l f. Effect on the orderly progress of work. I Items reworked or repaired in accordance with proce-dures are verified by reinspecting the items as originally 1
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16.1 GENERAL REQUIREMENTS 1
The NUQAP provides documented measures for corrective action to ensure that nonconforming systems, structures and components are identified and promptly corrected. These measures shall include, as appropriate, procedures for identification', documentation, segregation, disposition, notification to affected organizations and follow-up to prevent recurrence. Nonconforming items shall be reviewed and accepted, rejected, repaired or reworked in accor-dance with approved procedures. When conditions, adverse to quality, are identified through trend analysis, measures are taken to ensure corrective action and to prevent recurrence of the problem.
16.2 IMPLEMENTATION 16.2.1 CORRECTIVE ACTION AND FOLLOW-UP Evaluation of conditions adverse to quality such as, nonconformances, failures, malfunctions, deficiencies ,
deviations, and defective material and equipment is conducted to determine the need for corrective action in accordance with established procedures. NUSCO/NUPOC o Procedures describe the measures taken to evaluate l ) conditions adverse to quality, to determine the need for V ' corrective action, to document the evaluation. NUSCO Quality Serv'ces Department performs audits, survell-lances ar.d in process verifications to verify that NUSCO/NUPOC complies with the corrective action pmgram and that corrective action is adequate and properly implemented in a timely manner.
NU personnel and 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 are responsible for informing the Senior -
Vice President, Nuclear Engineering and Operations, through their respective organizational chains of command, of significant conditions which are adverse to quality, .
the cause of the condition and the corrective action taken. NUSCO Quality Services identifies deficiencies by audits, surveillance, inspections and in process veri-fications of the engineer-constructor's, contractor's ,
supplier's, and engineering service organization's quality assurance programs for corrective action. A reaudit, !
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- m. inspection, surveillance, and in process verification to i verify implementation of correctiv,e action and close-out )
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of corrective action <*meumentation shall be accomplished by the original auditing organization.
- NUSCO Quality Services performs audits to identify deficiencies in departmental corrective action programs.
The appropriate NUSCO Department Director / Branch Manager /Section Supervisor or the appropriate NUPOC Superintendent, is responsible to implement timely corrective action. NUSCO Quality Seivices may reaudit the affected department to verify corrective action has been implemented and documentad.
If corrective ection is inadequate or not timely, the follow-up organization requests corrective action from management as delineated in procedures. The Senior Vice President-Nuclear Engineering and Operations has the final authority in the event that agreement is not reached at lower levels.
Wh'ere corrective action is required of contractor personnel, NUSCO/NUPOC defines in procedures and contracts the corrective action interface between NUSCO/
NUPOC and the contractor. NUSCO/NUPOC requires the engineer-constructor, contractor, suppliers and engi-G neering service organizations, as appropriate, to have a
(
/) documented corrective action program for materials and services.
16.2.2 RECURRENCE CONTROL The organization which is responsible for the condition adverse to quality, shall ensure that the corrective action will not only correct the immediate condition, but also prevent the adverse condition from recurring.
NUSCO/NUPOC proedures establish the responsibilities and measures taken to identify trends of conditions, adverse to quality, and to ensure that corrective action is taken for those conditions to prevent their recur-rence. A trend analysis report which identifies the conditions adverse to quality is issued to appropriate levels of NU management. The NUSCO Director, Quality Services is responsible for follow-up of the trend analysis items and their corrective action.
Trends concerning specific contractor's performance shall be reported to the effected contractor for resolution and corrective action to prevent recurrence of the problera.
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'17.0 GENERAL REQUIREMENTS r
The NUQAP provides for the maintenance, identification, retention and retrieval of records to furnish evidence of activities affecting quality during design, construction, testing, operations, mainte-nance and modification of nuclear power plants. The records include but are not limited to: operating logs and the results of reviews, inspections, tests, audits, monitoring of work perfor-l Nnce 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 L are not limited to: identification of inspector or data recorder and the acceptability and the action taken in connection with any deficiencies and Reportable Occurrences noted. Approved proce-dures establish requirements concerning record retention such as duration, location and assigned responsibility.
17.2 IMPLEMENTATION NUSCO/NUPOC Procedures and Instructions establish the respon-sibilities and requirements for the maintenance, identification ,
retention and retrievability of records pertaining to materials, i equipments, parts, processes or operations relating to systems, structures and components which when founded on observations, f]'
Q measurements or tests can be fully verified, and documented by cognizant personnel.
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 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, surveillance, inspections, and in process l
L verifications of the engineer-constructors, contractors, suppliers
} and engineering service organizations, as appropriate, to verify l
they are effectively complying.with their program for quality l
assurance records.
NUSCO/NUPOC records are identified, controlled and maintained in appropriate files and are identifiable to specific systems, struc-tures and components within 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).
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n 17.3 RETENTION o< i-I \ NU quality assurance records are classified as life records or nonlife records as delineated by Generation Facilities Records.
p Non11fe 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 doctanents thri are maintained for the lifetime of the in-service nuclear power plant or ice the life of the particular component or part. Life records are thou which would be of significant value in meeting one or more of da following criteria:
- a. Demonstrating capability for safe operations;
- b. Maintaining, reworking, repairing, replacing or modifying the item; f
L c. Determining the cause of an accident or malfunction of an item; e d. Providing required base line data for in-service inspection.
Records are reviewed and approved by the cognizant quallfled personnel of NUSCO/NUPOC, engineer-constructor, etc. , as appro-priate, and are transmitted to the appropriate Nuclear Plant Records Facility. The responsibility of the appropriate Nuclear I' Plant Records Facility upon receipt of records, is to maintain and h' 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 temper-ature or humidity, as delineated in procedures.
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J 18.1' GENERAL REQUIREMENTS' The NUQAP requires that measures he provided to implement an L effective audit program. These measures are applied during the design, construction, testing and operation of nuclear power plants and modifications thereto, through the performance of audits.
g Audits, surveillance, inspections, and in process verifications are
' conducted in accordance with preestablished procedures and written chocklists by qualified personnel not having' direct responsibiHties .
in the areas being reviewed to ensure compliance with the NUQAP
[ Topical Report. The results of audit, surveillance, inspection, i and in process verification findings are documented and then reviewed with management having responsibility in the area audited.
- 18. 2 IMPLEMENTATION 18.2.1 PROGRAM The NUSCO Audit program requires audits, surveillance, and in process verifications of corporate and plant quality activities. Audits, surveillance, and in process verifications are scheduled on the basis of the status and safety importance of the activities being performed.
"""""" "'" ' ' ' ' " " * " " " " " ~ " ' " ' " ' " " " " " " " "
- l. CJ' Quality Services Department.
In addition, provisions are established to require that audits be performed of those activities where the require-ments of Appendix B to 10 CFR, Part 50, are being implemented and associated with:
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 procurement; ,
c.
Indoctrination and training programs;
- d. Interface control among the licensee and the prin-cipal contractors.
Measures are provided to perform audits of the following operations activities:
- a. Operation, maintenance, and modifications-;
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I o b. The preparation, review," approval and control of i(" ) des!gn documents, specifications, procurement documents, instructions, procedures and drawings;
- c. Receiving and plant inspections;
- d. Indoctrination and training programs;
- e. The implementation of operating and test proce- .
dures;
- 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 effective-ness of implementation and conformance to the NUQAP.
Any engineer-constructors, contractors, suppliers and engineering service organizations utilized by NUSCO/
NUPOC in the design, construction, tetting, operation, maintenance, and modification to nuclear power plants are responsible for developing and implementing a system of planned and periodic audits to verify compliance with
['i the effectiveness of all aspects of their quality assurance
( ,/ programs including reporting and resolution of deficien-cles . NUSCO Quality Services personnel perform on-site and off-site audits, surveillance, inspections, and in-process verifications to ensure these organizations are effectively complying with their quality assurance requirements for audits.
Departments with the NUSCO/FUPOC organizations are responsible for implementing their functions in accor-dance with approved procedures and instructions.
Internal audits are performed to verify implementation of the requirements prescribed in the NUQAP Topical Report and implementing departmental procedures.
16.2.2 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.
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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 p 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 program. This report is then
' submitted to the Director, Quality Service.s.
18.2.4 RESOLUTION OF AUDIT DEFICIENCIES Appropriate action to resolve defielencies identified during audits is to be taken by the cognizant engi-neer-constructor, contractor, supplier, engineering service organization or NUSCO/NUPOC before the scheduled resolution date. Follow-up audits are performed as necessary to verify appropriate actions have been 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.
V 18.2.5 RECORDS / REPORTS OF AUDITS Audit records, reports and associated documentation pertinent to audits are maintained in the appropriate NUSCO files with disposition to the appropriate Nuclear Plant Records Facility, as specified in procedures.
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APPENDIX A O -
. CATEGORY I SYSTEMS. STRUCTURES. AND COMPONENTS 1
The following systems, structures and components of a nuclear power -
plant, including their foundations and supports, are designated as Category I. The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50, should be applied,' as a minim tm, to all quality activities affecting the safety fur.ction of these systems, structures, and components as listed below and to other items and services specifically identified by NU in each FSAR addressing l 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) .
t (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.
(e) 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 2-1/2 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 2-1/2 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 portions 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 removal from the reactor or; (5) cooling the spent fuel storage pool.
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'~~'N (h) Cooling water and seal water systems or portions of these systems
) that are required for functioning of reactor coolant system com-ponents important to safety, such as reactor coolant pumps.
l (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 involved in generating or responding to signals that provide protective functions of safeguard systems.
(k) Systems or portions of systems that are required for (1) moni-toring of systems safety-related and; (2) actuation of cystems safety-related.
" 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 accom-plishment of the specified safety function.
(1) The spent fuel storage pool structure, including the fuel racks.
(m) The reactivity control system (e.g. , control rods, control rod drives, and boron injection system) .
/m (n) The control room, including its associated equipment and all (v) equipment needed to maintain the control room with safe habit-ability limits for personnel 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 (a) through (o) above which contain or may contain radioactive materials and whoce 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 part of the body.
(q) The Class IE electric systems, including the auxiliary systems for the onsite electric power supplies, that provide the emergency electric power needed for functioning of plant features included in items (a) through (p) above.
(r) Those portions of systems, structures or components whose con-tinued function 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 or could result in incapa-A QAP - Appendix A Rev. 12 Date:
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,P citating injury to occupants of the control room should be designed and constructed so that the SSE would not cause such failures.
(s) Items' and services associated with Radioactive Material Transport-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. Hydraulic snubber fluids
- 3. Reagents
- 4. Resins
_5.
- 6. Lubricants >
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. /'~'x s
, APPENDIX B NORTHEAST UTILITIES Q.UALITY ASSURANCE BOGRAM TOPICAL REPORT QUALIFICATION AND EXPERIENCE REQ.UIREMENTS NUSCO DIRECTOR. QUALITY SERVICES The NUSCO Director, Quality Services shall satisfy the following requirements:
Graduate of a four-year accredited engineering or science college or university, plus fifteen (15) or more years of industrial experi-ence 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 exper.ience is in a Quality Assurance Organization. A masters degree in engi-neering or business management is considered equivalent to two years of experience.
Note: The education and experience requirements should not be treated as absolute when similar training or an outstanding
[-sC} record will provide reasonable assurance that a person can perform the required tasks.
- \
LJ QAP - Appendix B Rev.- 12 Date:
Page 1 of 1
4 m l .. ,- ,
APPENDIX C
\#
l NORTHEAST UTILITIES QUALITY ASSURANCE _ PAO _ GRAM TOPICAL REPORT LIST OF TYPICAL QUALITY ASSURANCE RELATED PROCEDURFJ INDEX l
PAGES NUSCO QUALITY SERVICES DEPARTMENT 2-3 NUCLEAR ENGINEERING AND OPERATIONS POLICY AND 4-7 PROCEDURES MANUAL NUSCO GENERATION ENGINEERING AND CONSTRUCTION 8-10 DIVISION PROCEDURES MANUAL NUCLEAR PLANT RECORDS MANUAL 11-13 INFORMATION RESOURCES PROCEDURES 14 NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES 15 MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES 16-21 CONNECTICUT YANKEE QA PROCEDURES 22-26 NORTHEAST UTILITIES WELDING MANUAL 27 NU PURCHASING BUSINESS PROCED'URES 28 NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 29 REACTOR ENGINEERING BRANCH PROCEDURES 30 GENERATION F CILITIES LICENSING BRANCH PROCEDURES 31 1
NUOLEAR ENGINEERING AND OPERATIONS 32 (MLITY SOFTWARE PROCEDURES ,
O QAP - Appendix C Rev.: 12 Date:
Page 1 of 32
d
-. - . NUSCO QUALITY' SERVICES DEPARTMENT PROCEDURES ,
- 10 CFR 50, APP. B CRITERIA - QSD - PROCEDURES II. Quality Assurance- QSD-1.08 Quality Services Depart-Program ment-Indoctrination and Training Program QSD-1.12 Preparation and . Issuance of. Quality Services ;
Department Quarterly and Annual ~ Activity Reports QSD-2.01 Preparation, Issuance, and Control of the Northeast Utilities Quality Assurance Program Topical Report QSD-2 06 Training and Qualifi-cation of' Lead Auditors -
( QSD-2.07 Selection, Training, .
Qualification and Certi-fication of Non-NDE Inspection and Testing Personnel g IV. Procurement Document QSD-3.01 Procurement Document Control Review QSD-3.04 Assignment of- Suppliers to Periodic Surveillance Status V. Procedures, Instructions, QSD-1.02 Quality Services and Drawings . Department Procedures VI. Document Control QSD-1.10 Control of Correspon-dence VII . Control of Purchased QSD-3.02 Supplier Evaluations Material, Equipment, E and Services QSD-3.03 Review and Approval of Supplier QA Programs QAP - Appendix C 2ev.: 12 Date:
Page 2 of 32
, . NUSCO QUALITY SERVICES DEPARTMENT PROCEDURES
, ('^'g _ _ _ _ ,
\ l .
10 CFR 50, APP. B CRITERIA QSD - PROCEDURES QSD-3,05 Issuance and Control of the Approved Suppliers List IX. Control of Special QSD-2.07 Selection, Training, Processes Qualification and Certi-fication of Nondestruc-tion Examination Personnel X. Inspection QSD-2.03 Performance, Reporting and Fonow-up of Sur-veillance Activities QSD-4.02 Performance and Reporting of Inspection and Inspec-tion Surveillance Activities XV. Nonconforming Materials, QSD-1.06 Procedure to Stop Work Parts, or Components, or Services p/
L-XVII . Quality Assurance QSD-1.04 Retention, Turnover, Records and Transmittal of Quality Service Depart-ment Records for Perma-nent Storage XVIII. Audits QSD-1.07 Computer Tracking Programs QSD-2.02 Performance, Reporting, and Follow-up of Audits QSD-2.09 Performance, Reporting, and Follow-up of In-Process Verifications QSD-2.10 . Joint Vendor Audits (V- QAP - Appendix C Rev.: 12 Date:
Page 3 of 32
.: a.:
- a. .. NUCLEAR ENGINEERING AND OPERATIONS-POLICIES' AND PROCEDURES . MANUAL.
1 n .
1 10 CFR ' 50, APP. B CRITERIA . NEO - PROCEDURES I. . Organir.ation . NEO-1.01 ' Organization 'of the Nuclear Engineering'and .
Operations Group NEO-2.02 Charter for Nuclear Review Boards II. Quality Assurance NEO-1.02 The Nuclear Engineering Program and Operations Policies and Procedure Manual NEO-2.08 Management ' Review of.
the Northeast Utilities Quality Assurance Program NEO-2.14 Nuclear Plant Fire Protection Program NEO-2.24 NEO Program for Quality Software NEO-2.26 Departmental Training NEO-3.08 Processing Proposed Revisions to the Northeast Utilities Quality' Assurance Program Topical Report NEO-7.02 Turnover and Rework of Systems, Components, and Structures III. Design Control NEO-3.03 Preparation, Review and Disposition of Plant Design Change Records ~
(PDCRs)
NEO-3.12 Safety Evaluations NEO-5.04 Preparation, Review, Approval, Revision, and Control of Specifications O -
QAP - Appendix C Rev.: 12
'Date:
Page 4 of 32
_]
. . {
. .- NUCLEAR ENGINEERING AND OPERATIONS {
POLICIES AND PROCEDURES MANUAL
\- '
10 CFR 50, APP. B i CRITERIA NEO - PROCEDURES l
I l
NEO-5.05 Design Inputs, Design Verifications, and Design l
Interface Reviews NEO-5.06 Preparation, Review and Approval of Design Analyses and Calcula-tions NEO-5.11 Design Change Notices for Design Documents NEO-5.12 Performance of Fire Protection Reviews NEO-6.01 Material, Equipment, and Parts Lists for In-Service Nuclear Generation Facilities (n,l IV. Procurement Document NEO-6.02 Preparation and Review Control of Quality Related Purchase Requisitions NEO-6.04 F eparation and Review
.f Proposals V. Procedures, Instruc- NEO-1.04 Preparation, Revision, tions, and Drawings Issuance, Deletion, and Control of Nuclear Engineering and Opera-tions Procedures NEO-3.10 Preparation and Pro-cessing of Proposed New Issues, Revisions, Change or Interim Change, to an In-service Inspection Program VI. Document Control NEO-4.01 Communications with the Nuclear Regulatory Commission
,O QAP - Appendix C Rev.: 12 Date:
Page 5 of 32
', NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL
.~
~
10 CFR 50, APP. B CRITERIA . NEO - PROCEDURES NEO-4.02 Proposed Technical S;iecification Change Requests and Emergency Walvor 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 VII. Control of Purchased NEO-6.03 Transfer of Materials, V(3 Material,. Equipment, Equipment, and Parts and Services NEO-6.05 Processing and Control of Purchased Material, Equipment, Parts, and Services IX. Control of Special NEO-3.11 Preparation, "Qualifi-
- l. Processes cation, Approval snd j Revision of Northeast Utilities Nondestructive
. Examination Procedures I
X. Inspection NEO-2.07 Management of In-Service Inspection Programs XI. Test Control NEO-7.03 Preoperational Testing of Plant Modifications l
1 NEO-2.01 Implementation of the XV. Nonconforming Materials, Parts, Requirements of Part 2.1 Components, or of Title 10, Code of l ,~
! t '
b QAP - Appendix C l Rev.- 12 l
Date:
! Page 6 of 32
, . NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES MANUAL
( )
'/
~
10 CFR 50, APP. B CRITERIA NEO - PROCEDURES Serv. ices Federal Regulations:
Reporting of Defects and Noncompliance XVI. Corrective Action ,
NEO-2.11 Trend Analysis from Quality Related Documents NEO-2.18 Corrective Action Requests NEO-3.07 Response to Audit Findings XVII. Quality Assurance Records NEO-2.10 Safeguarding Supplier Proprietary Material NEO-2.12 Control of Nuclear Facilities Safeguard CN Information N] NEO-2.13 Nuclear Plant Records Program XVIII . Audits NEO-3.01 Conduct and Format of Nuclear Review Board Audits
(^)
\2
~ QAP - Appendix C Rev. 12 Date:
Page 7 of 32 L _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
NUSCO GENERATION ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL
.. V) 10 CFR 50, APP. B CRITERIA GE&C - PROCEDURES
- 1. Organization GE&C-1.01 Generation Engineering
. and Construction Division II. Qual.ity Assurance GE&C -1.02 Applicability and Use Prograrn of Generation Engi-neering 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 GE&C-1.05 Generation Engineering and Construction Training Program p,
t
() 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 V. Procedures, Instructions, GE&C-1.04 Preparation, Issuance ;
and Drawings and Control of Genera-tion Erigineering and Construction Division Procedures k~' .
QAP - Appendix C Rev.: 12 Date:
Page 8 of 32 ,
.____-__-_x-___-
4
- NUSCO GENERATION ENGINEERING. AND CONSTRUCTION DIVISION PROCEDURES MANUAL
[ : ?
- s' 10 CFR 50, APP. B CRITERIA GE&C - PROCEDURES GE&C-3,01 Design Information l
GE&C-3.05 Preparation and Control I of Design Drawings VI. Document Control GE&C-3.04 Design Document Summary Log VII . Control of Purchased GE&C-2.02 Review of Proposals Material, Equipment, Submitted by Engineer-and Services ing Service Organiza-tions, Suppliers, Vendors and Contractors IX. Control of Special GE&C-3.03 Control of Special Processes Processes XV. Nonconforming Materials, GE&C-5.05 Issuance of a stop Work Parts or Components or Order Services lV '}
GE&C-5s07 Processing Noncon-formance Reports XVII . Quality Assurance GE&C-2.05 Retention, Control and Records Final Disposition of Project Document Files for Betterment Projects 5
I
\d ) QAP - Appendix C Rev.- 12 Date: ,
Page 9 of 32
NUCLEAR PLANT RECORDS MANUAL
,c"*n
.l' '- 'I 10 CFR 50, APP. B CRITERIA NPRM - PROCEDURES.
I. Organization NPRM-1.07 Generation Facilities Records Branch and Responsib111tles II. Quality Assurance NPRM-6.01 Training Requirements Program V. Procedures, Instructions, 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 N.PRM-2.02 Maintaining Nuclear Plant Records Vendor and Manufacturer File
,/~
(j NPRM-2.04 Indexing Quality Checks l NPRM-3.01 NUSCO Generation Facilities Records Branch's Functions in Implementing the Northeast Utilities Drawing Control System NPRM-3.06 Request for Nuclear Plant Drawing or
' Aperture Card Copies NPRM-3.09 Maintenaner of Backup Indicles for the Drawing Control Computer Program DWG XVII. Quality Assurance NPRM-1.05 Establishing Submittal Records Schedules for Transfer of QA Records Into Nuclear Plant Records Facilities
\/ QAP - Appendix C
- Rev.: 12 Date:
Page 10 of 32
4 p -
[ .
NUCLEAR PLANT RECORDS MANUAL
- "~
kJ '10 CFR 50, APP. B CRITERIA -
NPRM - PROCEDURES NPRM-1.06 Nuclear Power Plant
. Quality Assurance Records Generated, Collected and/or Trans-mitted by External .
Organizations NPRM-1.08 Retention and Conrol of Quality Assurance Records Generated in Support of the Nuclear Plant Records System NPRM-2.0116MM Roll Film Micro-filming Procedure NPRM-2.05 Inspection of Permanent Storage Vaults for Temperature, Humidity and General Condition Q(/ _
NPRM-2.06 Document of Record Inspection / Inventory NPRM-2.07 Storage of Documents of Record NPRM-2.08 Use of Updateable Microfiche Systems NPRM-3.08 35MM Aperature Card Microfilming Procedure NPRM-4.01 Housecleaning Guide-linos for Records NPRM-4.02 Transmittal and Receipt NPRM-4.03 Access to Nuclear Plant Records Facilities and Records
- NPRM-4.04 Disposition of Nuclear Plant Records
(^)
k- QAP - Appendix C Rev.:. 12 Date:
Page 11 of 32
IN l*: ,
_ .a .
..- 4 "' . NUCLEAR PL NT RECORDS MANUAL 4 _c_, . .
/% a
- 10: CFR 50, APP. B
- - CRITERIA - NPRM - PROCEDURES' n ,
NPRM-4.05 Checklist of Required
- i. . Nuclear Power Plant -
o Records Including
- - Quality Assurance .
> Records NPRM-4.06 Descriptions. of Nuclear .
Plant Records Storage Vault NPRM-4.07 Guide for Writing Implements and Paper Stock to be Used for Documents Intended for -
Microfilming NPRM-4.08 Proprietary / Confidential Record Control NPRM-4.09 Assignment of Source
'l Record Storage Locations to Nuclear. Records NPR Computer File Entries NPRM-5.01 Nuclear Records ~ System Description NPRM-5.02 NPR/DWG Computer Program Dictionary j - Maintenance -
- NPRM-5.03 NPR/DWG Computer File
- Integrity Verification NPRM-5.04 indexing Requirements L
O QAP - Appendix C Rev.: 12 Date:
Page 12 of 32 I-L L __ _ . _ _ m _ __ _ _ _ _ _ _ _ ________.._.________m.__. . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _________ ___ _
4
. INFORMATION RESOURCES PROCEDURES
- '-) 10 CFR 50, APP. B CRITERIA IR - PROCEDURES I. Organization IR-1. 01 Organization of the IR Group II. Quality Assurance IR-2.01 QA Indoctrination and Program Training III. 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 Equip-ment Acquisition V. Procedures, Instructions, IR- 1. 02 Format and Content of and Drawings IR Procedures IR- 1. 03 Preparation, Issuance, and Controls of Informa-tion Resources Pro-(3) s_ cedures 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 Offsite Magnetic Media Vault XVIII. A udits IR-3.01 Resolution of Audit Findings
(~ .
D - QAP - Appendix C Rev.: 12 Date:
Page 13 of 32
'* NUSCO NUCLEAR OPERATIONS DEPARTMENT PROCEDURES ,
\ '~' /
10 CFR 50, APP. B CRITERIA NOD - PROCEDURES 1
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 Distribution and Accountability of Department Procedures VI. Document Control NOD- 1. 04 Distribution of Design Documents l
- NOD-3.02 Production Maintenance
\ s) Management System (PMMS) Automated Work Order System 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
(/ ~
QAP - Appendix C Rev.: 17.
Date:
Page 14 of 32
--___- _ -- . _ _ _ _- _ _ _ _ - . _ _ _ _ _ _ - _ - _ _ _ - - _ - - _ - - _ _ __-__-_____1
o :-
I. , . - .. MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES
. s..
( ACPS) .
73 ,
D '
10 CFR 50, APP. B
- CRITERIA MILLSTONE QA- (ACPS) .
I. Organization ACP-QA 1.01 Millstone .
Administration 4 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 ACP-QA 2.01 A Radioactive Material and Waste Packaging, Shipping, and Processing Quality Assurance Program ACP-QA 2.02C Work Orders ACP-QA 2.05 Fire Protection Program ACP-QA 2.14 Turnove'r of Systems, .
Components, and Structures (NEO 7.02)
ACF-QA 2.16 Nuclear Plant Environmental Qualification Program (NEO 2.21)
ACP-QA 8.01 Millstone Station Training QAP - Appendix C Rev.: 12 D:te:
Fage 15 of 32
[J--- -. ._ _ _ . - _ - . - . . _ _ _ _ _ _ . _ __ _m __.-.--.a.____m-*__---.____.-m m_____,_,___m.__ m _mm._ __h
4 '
. ' MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS) m
(#).
10 CFR 50, APP. B
~
CRITERIA MILLSTONE QA (ACPS)
ACP-QA 8.07 QA Training Program ACP-QA 8.08 Millstone Reactor Operator Training Program ACP-QA 8.16 Training, Certifi-cation, & Indenti-fication of Qualified Inspection and Testing Personnel III. Design Control ACP-QA 2.13A Computer Software Implementation ACP-QA 2.13B Maintenance and Control of Site Computer Systems
)
(/
L ACP-QA 2.17 Setpoint Change Control ACP-Q A 3.08 Safety Evaluation (NEO 3.12)
ACP-QA 3.09 Preparation, Issuance, and Control of Project Assignments ACP-QA 3.10 Preparation, Review, and Disposition of Plant Design Change
- Records (PDCRs)
(NEO 3.03)
ACP-QA 3.11 Preparation, Review, Approval, Revision, and Control of Specifications (NEO 5.04) l l
r
'~' QAP - Appendix C Rev;: 12 Date:
Page 16 of 32 1
L - - - - - - - - - - - - _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _
MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES
, ( ACPS) r /m I ;
V 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 Analyses and Calculations (NEO 5.06)
ACP-QA 3.14 Design Change Notices for Design Documents (NEO 5.11)
ACP-Q A 3.15 Performance of Fire Protection Reviews (NEO 5.12)
("N 3 ACP-QA 3.26 PDCR Evaluation U- (NOD 3.05) ,
IV. Procurement Document ACP-QA 4.02B Receipt, Control, Control ao Identification of QA Material V. Procedures, Instructions ACP-QA 3.05 Review & Approval and Drawings Vendor Procedures ACP-Q A 3.07 Maintenance of Station, Implementing Procedures in Accordance With NUSCO Governing
- Documents VI. Document Control ACP-Q A 3.01 ACPs & Station Forms ACP-QA 3.02 Station Procedures and Forms ACP-QA 3.03 Document Control r
" QAP - Appendix C Rev.: 12 Date:
Page 17 of 32
p ,- ,
a
- p h.[
l , .; _
' MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES '
. (ACPS) ~
.O~ 10 CFR 50, APP. B-CRITERIA - MILLSTONE-QA (ACPS)
ACP-QA 3.19 Controlled Distri-bution and .
Transmittal of.
Design Documents
, (NEO 5.03) . .
ACP-QA 3.23 Control of 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 & ,'
Services Testing .
VIII. Identification ACP-Q.A 4.03A Classifying and Up-and Control of grading Spare Parts Materials, . Parts For Use in QA and Components Application ACP-QA 4.03B Material, Equipment, and Part Lists for :
Lists for In-Service Nuclear Generating 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 l
ACP-QA 2.07 Control of Special l Processess X. Inspections ACP-QA 9.06 In-Service Inspection Program ACP-QA 9.07C Quality Services Surveillance Program LO QAP - Appendix C
. Rev.: 12 Date:
Page 18 of 32 ,
L - __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
7 ,
[ g< ,
[ ,. MILLSTONE QA ADMINISTRATIVE-CONTROL PROCEDURES ,
b1 . < . ,
'^'"' -
10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS)
XI. Test Control ACP-QA 2.02B Retests ACP-QA 2.15 Prooperational Testing of Plant Modifications (NEO 7.03) l ACP-QA 9.02 Station Surveillance Program ACP-QA 9.02A Unit 1 Surveillance Master Control List ACP-QA 9.02B Unit 2 Surveillance Master Control List ACP-QA 9.02C Unit 3 Surveillance Master Control List ACP-QA 9.03 In-Service Plant O Testing XII. Control of ACP-QA 9.04 Control & Calibration Measuring and of Measuring and Test Equipment Test Equipment XIII. Handling, Storage, ACP-QA 4.01 Plant Housekeeping Shipping ACP-QA 4.01 A System and Component Housekeeping ACP-QA 4.04 Instructions for Packaging, Shipping, Receiving, Storage and Handling ACP-QA 6.04 Radioactive Material Shipping Require-ments XIV. Inspection, Test ACP-QA 2.06A Station Tagging and Operating Status O ~
QAP - Appendix C Rev.: 12 Date:
Page 19 of 32
! ,' . MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES !
(ACPS) e 10 CFR 50, APP. B CRITERIA MILLSTONE QA (ACPS) ;
l l
ACP-QA 2.06B Station Bypass /
Jumper Control (NOD 3.04))
ACP-QA 2.06C Station Bypass /
Jumper Control for Troubleshooting, Red 11ning and Calibration ACP-QA 2.12 System Valve Alignment Control XV .- Nonconforming Materials, ACP-QA 5.01 Nonconforming Parts, Components, or Materials and Parts Services XVI. Corrective Action ACP-QA 5.02 Trend Analysis for Quality Related Documents ACP-QA 10.01 Plant Incident Report ACP-QA 10.06 NRC Commitment Follow-up Program ACP-QA 10.09 Licensee Event Report ACP-QA 10.10 Corrective Action Request XVII . Quality Assurance ACP-QA 10.04 Nuclear Power Plant Records Records XVIII . Audits ACP-QA 9.01 Quality Assurance Audits O QAP - Appendix C Rev.: 12 Date:
Page 20 of 32
f CONNECTICUT YANKEE QA PROCEDURES f- .
l 10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA .
QA PROCEDURES :
.I. Organization ACP 1.0-3 The Connecticut-- ,
' Yankee Organization Responsibility and Authority ACP 1.2-1.1 Plant Operation Review Committee II. Quality Assuranco ACP 1.2-2.1 Material, Equipment- !
Program and Parts List for {
CY .
ACP 1. 2-2. 3 Certification and ;
Identification of Qualified Testing Personnel !
ACP 1.2-2.4 Housekeeping Requirements
/~' (Foreign Material Exclusion Control) l ACP 1.2-2.7 NEO 3.08, Rev. 3, Processsing Proposed ;
Revisions to the i Northeast Utilities !
Quality Assurance l Program (NUQAP) l Topical Report j l
ACP 1.2-2.8 NEO 6.10, Use of l' the PMMS Data Base to Indicate Quality Assurance Program Applicability j i
ACP 1.2-2.9 Radwaste Quality l Assurance Program (NEO 6.07)
III. Design Control ACP 1.2-3.1 NEO 3.03, Preparation, Review and Dispost-tion of Plant Design i
QAP - Appendix C
~
Rev.: 12 Date: ,
Page 21 of 32 l
I I. CONNECTICUT YANKEE QA PROCEDURES
_yy.
10 CFR 50, APP. B CONNECTICUT YANKEE CRITERIA QA' PROCEDURES Change Records (PDCRs) .
ACP 1.2-3.3 Setpoint Change
, Request' (SCR)
ACP 1.2-3.4 NEO 5.04,' Preparation,
- Review,- Approval, Revision and Control of Specifications t
ACP 1,2-3.6 NOD 3.05, PDCR Evaluations ACP 1. 2-6.9 NEO 3.12, Safety Evaluations ACP 1.2-6.12 NOD 3.03, Safety Evaluations for Station Procedures 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-G.5 Station Procedures ACP 1.2-6.10 Maintenance of Station Impleinenting 0- - QAP - Appendix C Rev.: 12 Date:
Page 22 of 32
_ _. ._ -________-__________a
^'
CONNECTICUT YANKEE QA PROCEDURES 1
10 CFR 50, APP. B CONNECTICUT YANKEE L CRITERIA QA PROCEDURES Procedures with NUSCO Governing Documents ACP 1.2 o.11 NEO 5.09, Drawing Change / Submittal Request ACP 1.2-11.6 NEO 4.02, Proposed Technical Specifi-cation Change Requests VII . Control of Purchased ACP 1.2-7.1 Receipt, Inspection, Material, Equipment and Identification of and Services Materials, Parts, and Components VIII. Identification and ACP 1. 2-8. 2 Material Issue and -
(
\ Control of Materials, Transfer U l Parts and Components ACP 1.2-8.3 Weld Material Control IX. Control of Special ACP 1.2-9 1 Control of Special Processess Processess ACP 1.2-9.2 Requirements for Cleaning of Fluid Systems & Associated Components ACP 1. 2-9.3 NEO 3.11, Preparation, Qualification, Approval and Revision of Northeast Utilities Nondestructive Examination Procedures ACP 1. 2-9.4 In-Service Inspection Indication Reporting X. Inspections ACP 1.2-10.3 Authorized Nuclear Inspector (ANI)/
Authorized Nuclear 7
b QAP - Appendix C Rev.: 12 Date:
Page 23 of 32
L CONNECTICUT YANKEE 'QA PROCEDURES l:
. ("~i 10 CFR 50. APP. B ' CONNECTICUT YANKEE
, CRITERIA QA PROCEDURES In-Service Inspector (ANII)
XI. Test Control ACP 1.2-11.1 Technical Specif1-cation Surveillance Tracking
)
ACP 1.2-11.2 Review of Test . Data.
ACP 1.2-11.3 Retests ACP 1.2-11.4 Product Acceptance Test ACP 1.2-11.7 Special Testing XII. Coritrol of Measuring ACP 1.2-12.1- Control of Measuring and Test Equipment and Test Equipment O XIII. Handling,' Storage ACP 1.2-13.1 Handling of Material and Shipping and Equipment ACP 1.2-13.2 Storage of Material and Equipment ACP 1.2-13.5 Entry and Exit from Station of Transporter for Nuclear By-Product Material (Radwaste)
ACP 1.2-13.6 Packaging and
,- - Shipping '
l Requirements for Material Parts and Components -
ACP 1.2-13.8 Shipment of Radio-active Material XIV. Inspection, Test ACP-1.2-14.1 NOD 3.04, Jumper, and Operating Status Lifted Lead and Bypass Control
(. ,
() QAP - Appendix C Rev.: 12 Date:
Page 24 of 32
.' _ __ _ ._ __.__m__ .___ ___I___ _ _
O
,'_ '. CONNECTICUT YANKEE QA PROCEDURES
,~
l )
- u> 10 CFR 50, APP. B CONNECTICUT YANKEE CRIT,ERIA QA PROCEDURES l .
ACP 1.2-14.2 Equipment Control (Locking & Tagging)
XV. Nonconforming ACP 1.2-15.1 Nonconformance Materials, . Parts , Reports Components, or Services ACP 1.0-14 Determination and Follow of Substantial Safety Hazards (SSH)
XVI. Corrective Action ACP 1.2-16.1 Plant Information Reports ACP 1.2-1G.2 Corrective Action Request XVII. Quality Assurance ACP 1.2-17.2 Nuclear Power Records Plant Records
) ACP 1.2-17.3 Identification of Radiographs XVIII. Audits ACP 1.2-18.2 NEO 3.07, Response to Audit Findings 1
i l
I k.- QAP - Appendix C '
Rev.: 12 Date:
- Page 25 of 32 j
'.* f I' . NU WELDING MANUAL' i ..
8 -
f (d-) -
10 CFR 50, APP. B .-WELDING MANUAL-CRITERIA QA PROCEDURES -
I. Organization AP 700 Organization &- Control of
!. Northeast Utilities -
Welding and Brazing .
Manual II. Control of Special AP 701. Preparation, Qualifi-Processes cation, Approval &
Revision of Northeast Utilities Welding
' Procedures -
AP 702 - Control of Welder and Brazer Qualifications AP 703 Preparation, Review &
Approval of Detaned Welding Procedures AP 704 Preparation, Approval,
/ and Revision of
(]/ _
Northeast Utilities General Welding Standards AP 705 Preparation, Quall-fication, Approval, and Revision of Northeast Utilities Material Process Procedures AP 706 Preparation, Approve.1, and Revision of Northeast Utilities
. Technical Guidelines and Standards AP 707 Preparation, Approval and Revision of Northeast Utilities Miscellaneous Weld Documents and Infor-mation
. y--
QAP - Appendix C Rev.: 12 Date:
Page 26 of 32
t NU PURCHASING BUSINESS PROCEDURES
' 10 CFR 50, APP. B PURCHISING' CRITERIA QA ' PROCEDURES
,i.
IV. Procurement Document BP-3,1 Requisition: _ Standard.
Control ' and Repeating BP-3.3 Purchase Orders
~ '
BP-3.4 Changes to Purchase Orders BP-3.19 Blanket Purchase Orders O
(
O QAP - Appendix C Rev.: 12 .
Date:
Page 27 of 32
.p ' 'g
, ;+c '-n i- . ...4 L. NUSCO RELIABILITY ENGINEERING L . .-
I PRO'CEDURES ' MANUAL -
j; -
10 CFR 50,. APP. B l- CRITERIA RE PROCEDURES E .
'2 -
' I. ' Organization QRE-l'.01 Organization i: .II. Quality Assurance QRE-1.06 Training Program L QRE-2. 09 Training of In-Service -
. Inspection and Non-l ' destructive Examination l Personnel p
QRE-2.10 NTE Section Respon-
. sibilities and Conduct of ISI Planning and y
On-Site Activities for-Refueling Outages l ' V. - Procedures, QRE- 1.04 Preparation, Issuance Instructions and and Control of Drawings . Engineering Department Procedures t
O IX. Control of Special Processes QRE-2.16 Nondestructive Exami-nation Procedures XVII. Quality Assurance QRE-1.12 Control of Documents Records 11 r
I QAP - Appendix C Rev.: 12
' Date:
Page 28 of 32 i- - _ - --_____-_--______.______-_ _____ _ _ -
REACTOR ENGINEERING BRANCH -
PROCEDURES p . -
- 10. CFR 50, APP. B .
CRITERIA REB PROCEDURES I. ' Organization REB-1.01 Preparation, - Revision, Issuance,, Deletion, and Control of REB I
Procedures III'. Design Control REB-2. 01 Project Follow, Review and Documentation for Initial Core ' and Reload Fuel Campaigns REB-3. 03 Generation and Evalu-ation of Incore Code Results for. QA .
Category I' Applications I- REB-3.07 Qualification of Analysis Methods Which Use Quality Related Software I REB-3. 08 Review of Engineering l..
\ Service Organizations, Suppliers, Engineering- ?
Constructor, and Contractor Design Documents REB-3.09 Communication of Probabilistic Risk Assessment Findings to NU Management l REB-3.10 Transmittal of Design
, Input and/or Results of Design Analysis and Calculations by Memoranda and Reports REB-3.11 Fuel Performance Program REB-3.12 Initiation of Projects to Address Probabilistic Risk Assessment Findings O QAP - Appendix C Rev.: 12 Date:
Page 29 of 32 E _ _ . - - . . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l> .1 ; .. .
' REACTOR ENGINEERING ~ BRANCH '
l-l * .,
- PROCEDURES 10 CFR 50, APP. B;.
i; CRITERIA REB PROCEDURES l
i.. , y.
V. Procedurcs, . REB-1.01 l Preparation, Revision, Instructions issuance, Deletion, and Drawings and Control of REB '
1 Procedures' XVII. Quality Assurance REB-1.02. Reactor Engineering Records Branch Record Retention Management of Nuclear Power Plant.
Records O
1.
l-QAP - Appendix C Rev.: 12 Date:
i .. Page 30 of. 32 1
GENERATION, FACILITIES LICENSING BRANCH i
PROCEDURES
,3 .
l
\ ) l
'- ' 10 CFR 50, APP. B CRITERIA GFL PROCEDURES V. Procedures, Instruc- GFL-1.01Q Preparation, Issuance tions and Drawings and Control of Genera-tion Facilities Licensing Branch Procedures and Instructions VI. Document Control GFL-3. 01Q Regulatory Agency Correspondence GFL-3. 03Q U.S. Nuclear Regulatory Commission NUREGs GFL-3. 04Q U . S . Nuclear Regulatory Commission Federal Register Notices GFL-3.05Q U.S . Nuclear
( ~' Regulatory Commission C)T Regulatory Guides GFL-3.06Q Documentation of (
Telephone t Conversations GFL-3. 07Q Forward Commitments i
G FL-3. 08Q Preparation and Submittal of Special Nuclear Material, Source Material, and Byproduct Material License Application XVIII . Quality Assurance GFL-3. 02Q Management of Nuclear l Power Plant Records Records p
QAP - Appendix C
! Rev.: 12
! Date:
Page 31 of 32 a.____ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
e GENERATION FACILITIES LICENSING BRANCH PROCEDURES
- i t
'v/
' ~
10 CFR 50, APP. B CRITERIA GFL PROCEDURES I. Organization NEO/QS-5 Interface Plans for Quality Software II. Qtrality Assurance NEO/QS-3 Quality Requirements for Quality 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 V. Procedures, Instructions , NEO/QS-1 Preparation, Issuance, and. Drawings and Control of the NEO/QS Procedures
' ('~} and Manual
(/
XI. Test Control NEO/QS-9 Validation and Verification of Quality Software XV. Nonconforming NEO/QS-11 Error Reporting and Materials, Parts, Corrective Action for Components, or Quality Software Services XVI . Corrective Action NEO/QS-11 Error Reporting and Corrective Action for Quality Software XVII. Quality Assurance NEO/QS-10 Backup and S+.orage of Records Quality Software l
,/
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QAP - Appendix C Rev.: 12 Date:
Page 32 of 32 lu - - . - - _ - - - - - - - - - - _ - - - . - _ _ _ _ _ _ _ _ _ _
i .
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,s, APPENDIX D NORTHEAST UTILITIES Q.UALITY 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 stan-dards. Exceptions to these positions are listed in Appendix F of this Topical Report.
Appendix B to 10 CFR, Part 50 - Quality Assurance Crit'eria for Nuclear Power Plants and Fuel Reprocessing Plants.
10 CFR 50, Section 50.54, Condition of Licenses.
10 CFR 50, Part 55 - Operator's Licenses and its Appendix A -
Requalification Programs for Licensed Operators of Production and Utilization Facilities.
Regulatory Guide 1.8 R - 5/77 - Personnel Selection and Training -
Endorses ANSI N18.1 - 1971.
Regulatory Guide 1.28 - 2/79 - Quality Assurance Program Requirements
. (Design and Construction) Endorses ANSI N45.2-1977.
,m Regulatory Guide 1.30 - (Safety Guide 30), 8-11 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instru-mentation and Electrical Equipment - Endorses ANSI N45.2.4-1972.
Regulatory Guide 1.33 - 2/78 - Quality Assurance Program Requirements (Operation) - Endorses ANSI N18.7-1976/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 ANSI N45.2.1 1973.
Regulatory Guide 1.38 - Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling 'of Items for Water-Cooled Nuclear Power Plants, 5/77 - Endorses ANSI N45.2.2 - 1972.
Regulatory Guide 1.39 - Housekeeping Requirements for Water-Cooled Nuclear Power Plants, 9/77 - Endorses ANSI N45.2.3-1973.
Regulatory Guide 1.58 - Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel, Rev. 1, 9/80 - Endorses ANSI L N45. 2. 6-1978.
g-.s
" QAP - Appendix D Rev.- 12 Date:
Page 1 of 2
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Regulatory Guide 1.64 - Quality Assurance Requirements for the ' Design of Nuclear Power Plants, 6/76 - Endorses ANST N45.2.11-1974.
! Regulatory Guide 1.70. " Standard Format and Content of Safety l Analysis Reports for Nuclear Power Plants - LWR Edition" Revision 2, l 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 Minstone 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 l for Millstone 3.
1 Regulatory Guide 1.74 - Quality Assurance Terms and Definition, Feb.
i 74 - Endorses ANSI N45.2.10 - 1973.
Regulatory Guide 1.88 - Collection, Storage, and Maintenance of Nuclear
~
Power Plant Quality. Assurance Records - 10/76 Endorses ANSI N45.2.9-1974.
L Regulatory Guide 1.94 - Quality Assurance Requirements for Installa-tion, 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 ANST N45.2.5-1978.
Regulatory Guide 1.116 - Quality Assurance Requirements for Instal-lation, Inspection, and Testing Mechanical Equipment and Systems -
l 5/77 - Endorses ANSI N45.2.8-1975, I',
l ' Regulatory Guide 1.123 - Quality Assurance Requirements for Control of l Procurement of Items and Services for Nuclear Power Plants - 7/77 -
Endorses ANSI N45.2.13-1976.
Regulatory Guide 1.144 - Auditing of Quality Assurance Programs for l 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. 23-1978.
Regulatory Guid'e 1.152 " Criteria for Programmable Digital Computer System Software in Safety Related System of Nuclear Power Plants,"
l'
- November 1985 - Endorses ANSI /IEEE-ANS 7.4.3.2 - 1982. Commitment .
for Connecticut Yankee only.
O QAP - Appendix D Rev.: 12 Date:
Page 2 of 2
. , , APPENDIX E .
=
NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT GLOSSARY OF Q.UALITY ASSURANCE TERMS Accept As Is - (also known as "Use-As-Is") A disposition which may be imposed for a nonconformance when it can be established that the dherepancy will result in no adverse conditions and that the item under consideration will continue to meet all engineering functional require-ments including performance, maintainability, fit and safety.
As Built Documents - Documents which accurately describe the condition actually achieved in a system, structure, or component. These docu-ments 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 accordance with written checklists or procedures to verify by evaluation of objective evidence that a quality assurance program has been devoloped, docu-mented, 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 I - Designation given to systems, structures, and components of a. Northeast 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 Periodic. Survey - A documented activity, performed in accordance with a written checklist or procedures to verify, by l evaluation of objective evidence, that a supplier of commercial grade items or services controls, through quality activities, the critical l characteristics of specifically designated commercial grade items or services, as a method to accept those items for a safety-related use.
[
Contractor - Any organization under contract for furnishing items or services. It includes the terms Vendor, Suppiler. Subcontractor,
\ QAP - Appendik E Rev.: 12 Date:
Page 1 of 7
s 5 -4 Fabricator and subtier levels of these where appropriate. The Nuclear
-(O) . Steam Supply System Supplier (NSSS Supplier) is included in this
' category.
Corrective Action - Action taken to correct conditions adverse to
. quality in order to preclude recurrence of the conditions.
Deficiencies - Departures from specified requirements. .
Department - The use of the word department, throughout the NUQAP Topical Report, can refer to any portion of the NUSCO/NUPOC organi-zation (i.e., Group, Division, Department, Branch , Section, or Unit, as applicable) .
Departmental Mensuring and Test Eauipment List - A list of all depart-mental measuring and test equipment in the departmental calibration program.
Design - Technical and management processes which lead to and include the issuance of design output documents such as drawings, specifi-cations, and other documents defining technical requirements of systems, structures, and components.
Design Changes - Changes in drawings and specifications that define the design of systems, structures, and components of nuclear power
. plants.
Design Documents - Are the drawings and specifications that define the technical requirements of systems, structures, and components; the Finni' Safety Analysis Report (FSAR); the License Document; Technical Specifications; and Environmental Protection Plan.
Design Phase / Construction Phase /Preoperational Phase - Refers to work phase prior to the issuance of operating license.
Drawing Change Recuest (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 pre-viously assigned Northeast Utilities Service Company (NITSCO) drawing number) .
Engineer-Constructor - The principal organization contracted by NUSCO that performs the overall engineering, procurement , construction, and installation of systems, structures, and components of a nuclear power plant. .
L. Engineering Service Organization - Organizations that provide services such as analysis, testing, and inspection.
[_
A QAP - Appendix E Rev.- 12 Date:
Page 2 of 7
s Generation Facilities Records ~- The organization responsible for estab-m 11shing the Corporate Nuclear Plant Records Program which is imple-mented at each Nuclear Plant Records Facility.
Handling - An act of physically moving an item by hand or by mechani-
! cal machinery, but not including transport modes. '
Identification - A means by which material, equipment and parts can be 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, appurtenances, systems, processes, structures, or services to predetermine quality requirements.
Inspection 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 f' 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.
(3) determining the cause of an accident or malfunction of an item.
(4) providing required base line data for in-service inspection.
Measuring and Test Eculpment - Those instruments, gages, tools, fixtures, reference and transfer standards, nondestructive test. equip-ment, and measuring devices used during inspection and testing to determine that the measuring and test parameters comply with appro-priate requirements in specifications and drawings.
Nonconformanca - A deficiency in characteristic documentation or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformance include: physical defects, test failures, incorrect or inadequate documentation, or deviation from prescribed processing, inspection, or test procedures.
- QAP - Appendix E Rev. 12 Date:
Page 3 of 7
__________.____..__-.__-_._._._-________-____-m___ _ . - - _ . _ _ I
s- .
G6 L. ,.l
- Nonengkneered Items - Items which are:
(1) Relatively simple and standard in design, manufacture and test.
(2) Adaptable to standard or automated inspections and/or tests of the end product to verify quality characteristics after delivery.
(3). Of such a nature that product acceptance inspections / tests performed upon receipt of the items do not require operations which 'could adversely affect the integrity, . function, or cleanness of the item.
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.
Northeast Utilities Service Company (NUSCO) - A wholly owned subsi-diary of Northeast Utilities that provides engineering, procurement, i
construction, and quality assuranco services for Northeast Utilities O
(/
relating to design, construction, and preoperational testing of nuclear power plants and major modifications thereto.
- Northeast Utilities Quality Assurance Program (NUQAP) - Consist of the L NUQAP Topical Report, Quality Services Department Procedures and l
other Northeast Utilities Group / Division / Department / Branch /Section
- j. quality procedures.
L Nuclear Plant Operating Companies (NUPOCl - 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 operates the nuclear power plants. The companies which comprise NUPOC are the Connecticut Yankee Atomic Power Company and the Northeast Nuclear Energy Company.
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) .
NUSCO Quality Assurance Contractor. Supplier, and Engineering Service Organization List - A list identifying the approval status of the quality assurance programs of contractors, suppliers, and engineering service organizations.
QAP - Appendix E Rev.: 12 Date:
Page 4 of 7
" Objective $vidence" - Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item or O- service based on observation, measurements, or tests which can be verified.
Operational 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 tilat 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 operatious.
Procurement Documents - Letters of intent, contracts, purchase requisi-tions, 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 meet in order to be acceptable to the purchaser.
Product Accentance Test - Activities conducted as part of the receiving or source inspection process to verify acceptability of one or more critical characteristics of the item being inspected (from NEO G.11/
Rev. 0) .
Proof Test - A test conducted prior to installation of systems, structures and components to verify specification requirements have been met.
! Project Engineer - A NUSCO/NUPOC employee assigned the respon-l sibility to coordinate the engineering activities addressed in NUQAP.
Purchased Material. Equipment, and Parts (MEP,)_ - Items procured for i installation in nuclear power generating faellities systems, structures ,
and components, and items procured as construction and Power Generating Facility (PGF) spare MEP for potential installation of those systems, structures, and components.
Purchased Service - Services procured to assist in operat:on, main-tenance, modifications, and refueling of nuclear power plants.
Quality Assurance Records - Any record pertain!ng to the quality of material, equipment, parts, processes, or operations relating to systems, ~ structures 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 document or tag . The statements are authorized with a signature or stamp iden-tifiable to the person making the statement of fact.
6 QAP - Appendix E Rev. 12 D_ ate :
Page 5 of 7
i ) Q.uality Activities - Activities involving parts, components , structures and services for Category I, Radwaste QA (includhig Radwaste Packaging and Shipping), ATWS, FPQA, EEQ, and other regulated programs in accordance with the requirements mandated by those regulations.
Appendix A defines Category I program controls.
Quality Procedures - Those procedures which implement the require-ments 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 a'pplied to nonconforming material, equipment, and parts that. are unsuitable for their intended purpose which are modified by the use of additional operations and/or processes 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 inspections of 'vork associated with maintenrace and refueling to verify that systems, structures, and components will function satisfactorily when in operation. A retest may also be performed when original test results are invalidated.
Return to Supplier - A disposition applied to nonconforming material,
! equipment, and parts that are unsuitable for their intended purpose but
- (] which are feasible to repair or rework at a supplier's facility.
Q,)
Rework - A disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose due to i incomplete operations or variations from original engineering I requirements but which are modified through the use of additional operations or processes to meet all specified requirements.
Safety Related Systems and Components - Systems and components required to shut down the reactor, mitigate the consequences of l postulated accidents, or maintain the reactor in a safe shutdown l condition.
l Special Processes - An operation performed under controlled conditions in a.ccordance with special requirements utilizing qualified procedures, equipment, and personnel. These special processen may include, but are not limited to welding, brazing, soldering cleaning, heat treating, and nondestructive testing.
t Storage - The act of holding items at the construction site or in an area other than its permanent location in the plant.
Supplier - Organizations that provide material, equipment, parts, and services, or computer software.
f1 QAP - Appendix E Rev.. 12 Date:
Page 6 of 7
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Surveillance - A documented record of the observation of work opera-
'tions performed at NUSCO/NUPOC or vendor's site to assure compliance with applicable codes, standards, specifications, procedures, drawings, and procurement documents. Surveillance are not performed to a preplanned checklist. -
Test and Operating Status - Identification of material, equipment, and parts that are ready for test or operation, or an existing stage of a j test operation.
Testing - 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 operating conditions. i l
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i i V QAP - Appendix E Rev.: 12 Date:
Page 7 of 7 L _ _ _ _ _ - - _ - - - - . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _
8 I APPENDIX F NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL FXPORT 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 hard-ware at NNECO has a two-hour rating and the record storage vault door and hardware at CYAPCO has a three-hour rating.
Both NNECO and CYAPCO's vaults are used for storage of docu-mentation that is unsuitable for filming or awaiting fliming.
A records organization exists along with written procedures addressing thn control of quality assurance records.
- 2. ANSI N18.7-1976. paragraph 4.3.2.3 " Quorum" states in part: "A quorum for 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 use of Alternates was eliminated from the Northeast Utilities Nuclear Review Board (NRB) Charter due to the difficulties of keeping the Alternates up to date. The elimination of Alternates O forced the creation of a larger NRB membership (eight to eleven members) for greater diversity, resources, and availability.
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. 9-1974, paragraph 1.4, definition of " Quality Assurance Records" states in part: "For the purposes of this standard, a document is considered a quality assurance rocord when the docu-ment has been completed."
Northeast Utilities has 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:
"A record is considered a working document until it is transmitted to the appropriate Nuclear Plant Records Facility (NPRF) at which time it is designated as a Quality Assurance Record. The following maximum time limits are established for the transmittal of working documents to the NPRF:
l O QAP - Appendix F Rev.- 12 Date:
Page 1 of 2
+.
8 l
l 1
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-x Operations Documents - Documentation generated during Plant l } Operations may be maintained, as needed by operating plant
\ departments, for up to one year.
j New Construction or Betterment Documents - Documents which evolve during new construction or betterment projects shall I be transmitted to NPRF within 90 days of completion of a new construction project or turnover of a betterment 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 procurement may be maintained, as needed, by the Quality Services Department, for up to three years.
All Other Working Documents - All other working documents shall be transmitted to NPRF with 6 months of their receipt or completion. "
The requirements of ANSI N45.2.9-1974 do not apply to these
" working documents" based on paragraph 1.1 of the ANSI standard which states:
"It (ANSI N45.2.9) is not intended to cover the preparation of the records nor to include working documents not yet
/]/ designated as Quality Assurance Records."
l 1
~ 4. Regulatory Guide 1.64 - 6/76, the Reguitatory 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 aUow for adequate inde-pendent design verification:
This review may be performed by the originator's Supervisor, only if the Supervisor: ,
Did not specify a singular design approach; ;
Did not establish the design inputs or did not rule out certain design considerations; Is the only individual in the organization competent to perform the review.
Where the Supervisor performs the design review, the next level of management shall fulfill the Supervisor's responsibilities.
v QAP - Appendix F Rev.- 12 Date:
Page 2 of 2
_____-__a