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Draft Identification & Ranking of Nuclear Plant Structures,Sys & Components & Graded QA Guidelines
	ML20071C668
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Site:	Diablo Canyon
Issue date:	11/30/1982
From:	Kubicek L, Nitschke R, Wilhoit J; EG&G, INC.
To:	Haass W; Office of Nuclear Reactor Regulation
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EGG-EA-6109 NOVEMBER 1982 IDENTIFICATION AND RANKING 0F NUCLEAR PLANT STRUCTURES, SYSTEMS, AND COMPONENTS, AND GRADED QUALITY ASSURANCE GUIDELINES--DRAFT J. Michael Wilholt John K. Rawlins Robert L, Nitschke Ronald E. Dafoe e Larry D. Kubicek Theodore L. Kinnaman Idaho National Engineering Laboratory Operated by the U.S. Department of Energy

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6 This is an informal report intended for use as a preliminary or working document 8303030765 830217 PDR ADOCK 05000275 P PDR Prepared for the U.S. NUCLEAR REGULATORY COMMISSION g E E E E ldaho Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6479 Q

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FORM EGSG 396 INTERIM REPORT Accession No. .

Report No. EGG-EA-6109 C:ntract Program or Project

Title:

Identification and Ranking of Plant Structures, Systems, and Components, and Graded Quality Assurance Requirements Subject of this Document.

Identification and ranking of nuclear plant structures, systems, and components, and

. graded quality assurance guidelines--draft Type of Document:

Draft Author (s):

J. Michael Wilhoit, Robert L. Nitschke, Larry D. Kubicek, John K. Rawlins, Ronald E. Dafoe, and Theodore L. Kinnaman D:te of Document:

November 1982 Responsible NRC Individual and NRC Office or Division:

Walter Haass, Division of Engineering This document was prepared primarily for preliminary or internal use. it has not received full review and approval. Since there may be substantive changes, this document should not be considercd final.

LG&G Idaho, Inc.

Idaho Falls, Idaho 83415 s

Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.

Under DOENRC Contract FIN No. No.AkbAC07-761001570 9

INTERIM REPORT

ABSTRACT Two sets of lists are pres ='ted. One list places nuclear plant structures, systems, and components into one of three graded quality assurance levels (QALs), based on the item's importance to safet;. Separate lists for pressurized water, boiling water, and gas cooled reactors are provided.

The other list provides the specific quality assurance guidelines appropriate for each of the three QAls.

FIN No. A6479 Identification and Ranking of Plant Structures, Systems, and Components and Graded Quality Assurance Requirements ii

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SUMMARY

The purpose of the task was to identify nuclear plant items important to safety, to rank the items into three categories in accordance with their importance to safety, and to develop graded quality assurance guidelines applicable to each category for both the construction and operational phases. The results of the program will be used to develop regulatory guidance for use by the Nuclear Regulatory Commission staff and industry in

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implementing the proposed rule.

The results of the task are included with QA guidelines and the plant item lists, divided by plant type.

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CONTENTS ABSTRACT .............................................................. 11

SUMMARY

............................................................... iii INTRODUCTION .......................................................... 'l

. Development of Graded Quality Assurance Guidelines ............... 2 Objective ........................................................ 2 Background ....................................................... 2 1 1

Development ...................................................... 4 Final Approach.................................................... 10 Usage Guidelines ................................................. 15 QA GUIDELINES ......................................................... 19 IDENTIFICATION AND QA RANKING OF NUCLEAR PLANT STRUCTURES, SYSTEMS, AND COMPONENTS ........................................................ 79 Notes for Ranking Lists .......................................... 80 RANKING 0F NUCLEAR PLANT STRUCTURES, . SYSTEMS, AND COMPONENTS . . . . . . . . . . 83

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IDENTIFICATION AND RANKING OF NUCLEAR PLANT STRUCTURES, SYSTEMS, AND COMPONENTS, AND GRADED QUALITY ASSURANCE GUIDELINES--DRAFT INTRODUCTION A revision to Part 10, Code of Federal Regulations (CFR) has been proposed that identifies the quality assurance (QA) program required to satisfy General Design Criterion 1 of 10 CFR 50, Appendix A for nuclear plants as the QA program required by 10 CFR 50, Appendix B. Currently,' Appendix B

applies only to safety-related structures, systems, and components, i.e.,

those items that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. With the adoption of the proposed revision to the regulations, the applicability of the Appendix B QA program will be expanded to include all structures, systems, and components important to safety, i.e., those items that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.

The purpose of the task was to identify nuclear plant items important to safety, to rank the items into three categories in accordance with their importance to safety, and to develop graded quality assurance guidelines applicable to each category for both the construction and operational phases. The results of the program will be used to develop regulatory guidance for use by the Nuclear Regulatory Commission (NRC) staff and industry in implementing the proposed rule.

e The results of the task are presented with QA guidelines first, followed by plant item lists, divided by plant type.

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DEVELOPMENT OF GRADED QUALITY ASSURANCE GUIDELINES Objective The objective of this portion of the task was to establish a system of graded QA program guidelines commensurate with the relative importance to

. safety for three categories of commercial nuclear power plant structures, systems, and components. This system is intended to apply to both the design / construction and operational phases. -

Background .

The equipment categories encompassed by the task were generally defined as follows:

Quality Assurance Level I Plant items that in past licensing reviews have been characterized as

" safety related." These items are generally identified in Regulatory Guide 1.29.

Quality Assurance Level II Plant items that have a lesser role regarding safety than do QA Level I items, but nevertheless could affect safety in a direct or substantive manner by failure, thereby initiating a transient, or by serving as a potential backup to a QA Level I item. l l

Quality Assurance Level III i .

Remaining plant items that have a smaller effect on safety than do QA ,

Level II items.

1 Several ground rules were established by the NRC to be used as guidance in accomplishing the task. These were:

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1. Sections 17.1 and 17.2, Acceptance Criteria of the Standard i Review Plan, NUREG-0800, have already identified the QA requirements for QA Level I items and no further effort or definition would be required in this area.

2. The following were to be used for baseline documents:

A. 10 CFR 50 Appendix B quality assurance criteria B. Sections 17.1 and 17.2 of NUREG-0800 l C. All applicable regulatory guides and endorsed standards D. ANS 51.1 and 52.1 on the safety classification of nuclear power plant components under development by the Ad Hoc Committee on Importance to Safety E. Codes and Standards, 10 CFR 50.55a.

3. The quality assurance guidelines for each level will serve as the minimum for the next higher level and maximum for items in that level. With reasonable justification, users will be permitted to depart from the maximum for a level in establishing guidelines for a specific' item (i.e., a graded approach may be used to determine specific guidelines consistent with an items importance to safety) through considerations of the factors such as those identified in ANSI /ASME NQA-1, Appendix 4A-1, Section 5.0.

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4. Use existing techniques, to the maximum extent possible, developed by other organizations involved in nuclear plant design and construction.

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Development ,

With the above ground rules, specific objectives were developed to further guide the performance of this task. The approach taken would have to result in a quality assurance program structure that would

1. Maximize user flexibility Maintain consistency with existing regulations 2.

3. Se practical in application -

4. Be cost effective

5. Provide a graded QA program with three categories of guidance.

Telephone interviews were held with knowledgeable quality assurance personnel in the nuclear industry to obtain information on graded approaches in use by their firms and also to determine if the specific objectives above would be acceptable, on the whole, to those interviewed.

The consensus was 'in general agreement with those objectives.

There were two recurring items in these interviews that affected the direction of the detailed development of the task. The term " graded approach" has different meanings to different individuals, ranging from a highly detailed checklist type approach for every task that is done, to an approach where experienced and qualified individuals use sound engineering

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and management judgment applying only the necessary controls from the endorsed quality assurance standard for the particular circumstance at hand. In the former case, interviewees were quite unanimous that checklist QA approaches' specific to items or categories of equipment would pose a real danger by removing or minimizing the individual assessment process that must take place. The message was clear: develop an approach that would result in a program that was not toward the checklist end of the spectrum. The other recurring theme was that many organizations already use a graded approach as described by the opposite end of the spectrum 4

(individual assessment) whether they recognized it as such or not.

Therefore, this additional guidance was factored into the detailed development of the task.

In order to meet the above objectives and guidance, the approach was developed along the philosophy visually depicted in Figure I where the need for QA rigor decreases with lessening importance to safety and industry latitude increases. QA program rigor at the top of QAL I would remain

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highly proscriptive and decrease to a minimum at the bottom of QAL III.

QAL I QAC II QAC III NITS

I I I I I I REdJLATION I I

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l LAT TUDE g

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Not Important i l . To Safety Figure 1. QA program rigor.

Research was also conducted on the various approaches taken by other organizations that have investigated the graded approach problem. Most notable among these were the Canadian Standards Association Z-299 Series documents, the International Atomic Energy Agency Paper IAEA-SM-253/SM, similar work being conducted by the Tennessee Valley Authority, and work done by the ASME NQA-1 Committee on a draft report titled QA Requirements for Nuclear Safety Related Equipment. The listing of QA program documents and studies researched for information and further guidance is contained in Table 1. This table is a supplement to the documents contained in Table 2, which relates directly to the final approach taken.

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I TABLE 1. DOCUMENTS USED IN LITERATURE SEARCH 7 ANS 51.1, Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants ANS 52.1, Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants ANSI /ASME NQA-1 1979, Quality Assurance Program Requirements for Nuclear Power Plants MIL-I-45208A, Inspection System Requirements MIL-Q-9858A, Quality Program Requirements MIL-C-45662A, Calibration System Pequirements -

ASME Boiler and Pressure Vessel Code 1980 Edition, Summer 82 Addenda, Sections I, III, IV, and VIII RDT F2-2, Quality Assurance Program Requirements, 1973 RDT F2-4T, Quality Verification Program Requirements, 1974 IAEA-SM-253/101, The Selective Application of Quality Assurance Aptivities to Nuclear Plant Items and Services, May 1981, (J. W. Anderson, Chief, Quality Assurance, Clinch River Breeder Reactor Plant Project, Project Management Corporation, Oak Ridge, TN)

QA Requirements for Nuclear Safety Related Equipment, prepared by the Design and Procurement Sub-Committee Task Group on Quality Assurance by Classification, 1980.

TVA Construction Specification N3G-881, Identification of Structures, Systems, and Components Cevered by the Watts Bar Nuclear Plant Quality Assurance (QA) Program, Preliminary Copy, June 16, 1982 Report by NRC QA Review Team on Quality Assurance (QA) Practices for NRC's Confirmatory Research Programs, Rev. 2, October 25, 1979, (G. L. Bennett, Chief, Research Support Branch, Division of Reactor Safety Research)

Canadian Standards Association:

Z299.1 - 1978, Quality Assurance Program Requirements Z299.2 - 1979, Quality Control Program Requirements Z299.3 - 1979, Quality Verification Program Requirements Z299.4 - 1979, Inspection Program Requirements 6

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TABLE 2. DOCUMENTS USED FOR STRUCTURING GUIDELINES 10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

10 CFR Part 50, 50.55a, Codes and Standards NUREG 0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 17, Rev. 2, July 1981.

Regulatory Guides

!* 1.8, Rev. 1-R, Personnel Selection and Training 1.26, Rev. 3, Quality Group Classification and Standards for Water, j= Steam, and Radioactive Waste Containing Components of Nuclear Power Plants.

1.28, Rev. 2, Quality Assurance Program Requirements (Design and Construction).

1.29, Rev. 3, Seismic Design Classification.

1.30, Rev. , Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment.

1.33,- Rav. 2, Quality Assurance Program Requirements (Operation).

1.37, Rev. , Quality Assurance Requirements for Cleaning for Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants.

1.38, Rev. 2, Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants.

1.39, Rev. 2, Housekeeping Requirements for Water-Cooled Nuclear Power Plants.

1.54, Rev. , Quality Assurance Requirements for Protective Coatings

- Applied to Water Cooled Nuclear Power Plants.

1.58, Rev. 1, Qualification of Nuclear Power Plant Inspection,

! , Examination, and Testing Personnel.

1.64, Rev. 2, Quality Assurance Requirements for the Design of Nuclear Power Plants.

1.88, Rev. 2, Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records.

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TABLE 2. (continued) ,

1.94, Rev._1, Quality Assurance Requirements for Installation, I_nsgection, and Testing of Structural-Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants.

1.116, Rev. 0-R, Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems.

1.123, Rev. 1, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants.

1.144, Rev. 1, Auditing of Quality Assurance Programs for Nuclear -

Power Plants, i

1.146, Rev. , Qualification of Quality Assurance Program Audit .

Personnel for Nuclear Power Plants.

ANSI N45.2 Series N45.2-1977, Quality Assurance Program Requirements for Nuclear Facilities.

N45.2.1-1980, Cleaning of Fluid Systems and Associated Components for Nuclear Power Plants.

N45.2-1978,_ Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants.

N45.2.3-1973, Housekeeping During the Construction Phase of Nuclear Power Plants.

N45.2.4-1980 (IEEE 336), Installation, Inspection, and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations.

N45.2.5-1978, Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete,.

Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants.

I N45.2.6-1978, Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants.

l N45.2.8-1975, Supplementary Quality Assurance Requirements for

! Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants.

N45.2.9-1974, Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants.

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TABLE 2. (continued)

N45.2.11-1974, Quality Assurance Requirements for the Design of Nuclear Power Plants.

N45.2.12-1977, Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants.

N45.2.13-1976, Quality Assurance Requirements -for Control of Procurement of Items and Services for Nuclear Power Plants.

N45.2.23-1978, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants.

ANSI N101.4-1972, Quality Assurance for Protective Coatings Applied to Nuclear Facilities.

ANS 3.1--Draft, October 1980, Selection, Qualification, and Training l

of Personnel for Nuclear Power Plants.

ANS 3.2--Draft 8, April 1981, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.

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Final Approach The final approach selected is based on a program structure that has all the elements of 10 CFR 50, Appendix B, the Standard Review Plan Sections 17.1 and 17.2, Regulatory Guide positions, and endorsed ANSI standards applying to the maximum for QAL I. At the other extreme, the minimum guidelines for QAL III are structured basically around an inspection and test program. Between the two extremes lies a graduated program that is structured to the maximum extent practical to the document '

hierarchy shown in Table 3. Some deviations were necessary from this logic due to overlap from one standard to another. In developing the detailed a structure presented in the QA Program Guidelines Listings, or.ly programmatic QA elements were extracted from the referenced documents.

Programmatic QA requirements are those that impose a system / organization control, e.g. " activities affecting quality shall be accomplished under suitably controlled conditions" (from 10 CFR 50 Appendix B, Criteria III) but don't address the " technical" details of how this is to be accomplished. It is expected that the user will apply appropriate

" mechanics," or technical requirements, to assure the programmatic requirements will be met.

In many cases, redundancies between standards were noted. Some were identical on a word-for-word basis while others were stated in different terms but were evaluated to be addressing the same element. Where these conditions existed, the redundancies were eliminated and only a single reference made in the listing. ,

With this approach, the objectives stated earlier can be met:

The necessary flexibility is maintained within each category.

Sufficient latitude is retained to allow a variety of methods to meet the programmatic requirements and also allow tailoring of those requirements to meet specific circumstances.

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l The overall QA program structure for items important to safety still reflects those QA programmatic elements that are in use in the industry. Therefore, the structure is consistent with existing regulations and should have a high degree of understanding by industry. QAL III minimum level, while not reflecting an extensive 18-criteria program, does in fact, remain consistent with higher level guidelines but to a lesser degree.

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Three grades of QA guidelines have been provided with a maximum and a minimum established for each category.

The approach is also practical. This objective is met partially by the fact that the first two objectives (flexibility and consistency) were met and partially by the fact that new or different requirements are not being imposed. Because guidelines for the program structure are extracted from currently existing regulations, minimal impact to existing systems currently in place in the nuclear industry should occur.

As stated previously, the detail of the program structure is presented in the QA Program Guidelines Listing. The Xs under the columns for quality assurance level indicate whether the element should be considered for application to items within that level. In interpreting the tables, the reader is urged to keep in mind that the minimum guidelines for one level serve as the maximum guidelines for the next lower level and that the maximum would normally apply to a level unless suitable justification is documented for deviation. .This documentation need only be retained by the owner / applicant. The reader should also be aware that while these guidelines have been broken down into three levels, users may develop programs utilizing more levels. Also, individual parts of components, systems, or structures may be placed into a lower QAL as determined by the user's judgement.

For commercial "off-the-shelf" items, application of all QA controls consistent with nuclear industry practice is not always possible or practicable. In these instances, special verification requirements need to 11

TABLE 3 GRADl:D QA REQUIREHLNTS CRITLRIA QAL i M.t x i mum: 10CfR50, Appendix B, Regulatory Guides

1.8,.1.26, 1.28, 1.29,.1.30, 1.33, 1.31, 1.38, 1.39, 1.58, 1.64,-1.74, 1.88, 1.94, 1.116, 1.123, 1.144, 1.146 and all endorsed ANSI and ANSI N45.2 series standa rds.

CAL I Mi7imum: 10CFR50 Appendix 0, and Regulatory Guides

1.8, 1.28, 1.30, 1.33, 1.38, 1.39, 1.58, QAL II M.t x i mum: -1.64, 1.88, 1.94, 1.116, 1.123, 1.144 and 1.146. These Regulatory Guides endorse:

ANSI N45.2, quality Assurance Program Requirements for Nuclear Facilities ANSI N45.2.2, Pach_asi_nA ShippJng. Rec e_iy_i_0g , Sto rqLgo a n,djia nd l i nq of Items for

- Nuclea r Power Plants ANSI N45.2.3, llousekeepino During the Construction Phase of Nuclea r Power Plants i

ANSI N45.P.4 (IEEE-336), installa11og. Insnectionm_and Testino Requi rements for

!!1strumenta t ion and_(iegiri.c_E. qui.pment Durina the Const ruct ion of Nuclea r Power Ge ne ra tinLS_La Li on_s ANSI N45.?.5, Supplementa ry Qua l i ty Assurance Requi rements for installation.

Inspe_clio3 _and Tesi_ing o f Stuc_(u ra l Concrete and Structural Steel Durina the Construction Phase of Nuclear Power Plants ANSI N45.2.6,-Qualifications of Inspection. Examination. and-Testino Personnel for the Construction Phase or Nuclear Power Plants ANSI N45.2.8, - Stj pp leme_nla ry Qua l i ty Assurance Requi rements for Insta l lat ion.

inspection and Testino of Mechanical Eauipment and Systems for the Construction Phase of Nuclear Power Plants -

ANSI N45.2.9, ' Requi rements for Col lect ion. S to ra ce. and Maintenance of Quality Assurance Records for Nuclear Power Plants ANSI N45.2.11, Qua lity Assurance Reaui rements for the Desian of Nuclear Power Plants ANSI N45.2.12, Requi rements for Auditino of Qua l i ty Assurance Programs for Nuclea r Plants ANSI N45.2.13, Qua l i ty Assurance Requi rements for Control of Procurement of items and Services for Nuclear Power Plants ANSI N45.2.23, .qua l i fication of Qua li ty Assurance Program Audit Pe rsonne l for Nuclear Power Plants 12 a

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ANSI /ANS 3.1, Selection. QualificaJion and T ra in i nq of Personnel for Nuclea r Power Plants ANSI /ANS 3.2, Administrative controls and Quality Assurance for the Operational Phase of Nuclea r Power Plants QAC 18 Minimum 10CFR50, Appendix B, ANSI /ANS 3.1, RG 1.8 and 1.33 QAC 111 Maximum: ANSI /ANS 3.2, and ANSI N45.2.6, RG 1.58.

i QAC 111 Minimum: Cri teria 5, 10, 11, 12, 15, and 17 of 10CFR50, Appendix B:

Criteria 5, Instructions. Procedures. and Drawings Criteria 10, inspection Criteria 11, Test Control Criteria 12, Control of Measuring and Test Eauipment C r i te ri a 15, Nonconforming Ma te r i a l s . Pa rts. and Components criteria 17, Quality Assurance Records

Qua lity assurance programmatic requirements only.

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be invoked so that overall acceptability can be established, e.g., if design cannot be verified by in process reviews or analytical studies, appropriate alternates could be the performance of a suitable testing program or obtaining operational performance data that would demonstrate adequacy for intended use.

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l Usage Guidelines

1) Minimum guidelines for I and II are identical to the maximum for II and III, respectively. Guidelines for I maximum and III minimum define the matrix extremities.

2) For a given QAL, the maximum applies unless the applicant can establish reasonable justification for departing from them. If

departure from the maximum guidance occurs, actual guidelines should not go below the minimum guidance given for that QAL. Grading of the o guidelines within a given QAL, where appropriate, can be accomplished by examining the guideline for parameters that allow for some form of gradation, e.g. frequency, how often is this performed (audit once per year). The following list contains areas for consideration when reviewing the guidelines for possible reductions in rigor.

a. Frequency or duration of activity

b. Need for certification, qualification, or training

c. Degree of organizational independence required

d. Level of management involvement desired

e. Need for preventive measures--design verification, audits, supplier surveys

f. Need for identification, status, and/or traceability

g. Review and approval requirements

h. Documentation needs for program, corrective action, procurement, design, discrepancies, tests, inspections, and work planning

i. Need for appraisals--source, receipt, in process.

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3) The applicant should maximize use of existing flexibility within the SRP (or _other documents) via the "as necessary," "as required" verbage it contains to justify grading of QA requirements.

4) Unless otherwise noted in the reference column (Ref.), entries are from the SRP.

5) Individual parts of a component system, or structure may be placed in a lower QAL than the component, system or structure as determined by -

the user.

6) Grading of specific hardware within a given QAL recognizing that some parts will be a lower level than the system level can be accomplished by examination of the following parameters as they apply to the system, structure, or component in question:

a. Importance to safety (consequences of failure / malfunction) of the !

plant

b. Margin of safety designed into item

c. Time available for corrective action before failing/ failed item starts affecting the safety of the plant

d. Item availability

e. Item cost

f. Item uniqueness

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g. Item complexity

h. Ease of damage l

1. Previous experience with the item: operational, maintectnce, procurement 16

j. Time required to obtain a replacement I

k. Manufacturer's experience / expertise

1. Sold source

m. Previous problems developing similar items

n. Is item first-of-a-kind l

o o. Need for process controls or special equipment / skills / environment

p. Can functional test replace in process inspections

q. Industry's experience with the item

r. Degree of item's standardization

s. Schedule constraints

t. Item's redundancy in system (s)

u. Common mode failures

v. Code stamped item (does it have third party inspection) ti. Need for vendor document submittals

x. Need for first article inspection.

Note: Some changes to the wording of the SRP have been made for the sake of clarity. These changes are all identified with an asterisk (*) and explanatory notes added where necessary.

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Page 12 1 Min 11 Min CUIDELINE Ref. I Max 11 Ma x ill Max Ill Min The OIganization (17.1.1) elements responsible for the QA program a re. acceptable ,

if:

i 1A1 The responsibility for the overall program is retained and exercised X X X by the applicant.

1A2. The applicant has identified and ' described major delegation of work X X X involved in establishing and implementing the QA program or any part thereof to other organizations.

1A3. When major portions Of. the applicant's program are delegated:

a. Applicant describes how responsibility is exercised for the X X X ove ra l l p rog ram.

The extent of. management oversight should be addressed X' X including the location,- qualifications, and criteria for determining the number of personnel performing these

' functions.

b. Applicant evaluates the performance ( frequency and method X X X stated - once per year although longer cycle acceptable with other evaluations of individual elements) of work by the delegated organization. 3

! c. Qualified individual (s) or organizational element (s) a re X X X identified within the applicant's organization as responsible for the quality of the delegated work prior to initiation of activities.

IA4 Clear management controls and effective lines of communication exist X .X X for QA activities among the applicant and the principal cont racto rs to assure direction of the QA program, 1AS. Organization charts clearly identify all the "onsite" and "offsite" X X X o rga n i za t iona l elements which function under the cognizance of the 1

QA program (such as design, engineering, p rocu rement, manu fac tu ri ng ,

' construction, inspection, test, instrumentation and control, nuclear eng ineering, etc. ), the ' lines of responsibility, and a description of the criteria (for determining the size) of the QA organization including the inspection staff.

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Page 2Q 1 Min il Min CUIDELINE Re f. I Max 11 Max ill Max Ill Min 1A6. The applicant (and principal contractors) establishes the QA X X X responsibilities of each of the organizational elements noted on the organization charts.

181. The applicant (and principal cont rac to rs ) identifies a management X X X position that retains overall authority and responsibility for the QA program (norma l ly, this position is the QA Manager) and this position has the following characteristics:

a. Is at the same or higher organization level as the highest line X X X manager directly responsible for performing activities arrecting quality (such as engineering, procurement, construction, and operation) and is sufficiently independent from cost and j schedule.

b. Has errective communication channels with other senior X X X management positions,

c. Has responsibility for approval of QA Mart;al(s). X X X

d. Has no other duties or responsibilit.es unrelated to QA that X X X would prevent his full attention to QA matters.

182. Verification or conformance to established requirements (except for X X X*

designs, rer. 3E2) is accomplished by indsviduals or groups within the QA organization who do not have direct responsibility fer performing the work being verified or by individuals or groups t ra ined and qua l i f ied in QA concepts and practices and independent or the organization responsible for performing the task.

1B3. Persons and organizations performing QA functions have direct access X X X to management levels which will assure the ability to:

a. Identify quality problems. X X X

b. Initiate, recommend, or provide solutions through designated X X X channels,

c. Verify implementation or solutions. X X X

De lete ". . .wi thin the QA o rganiza t ion. . ." fo r 11 min./Ill max, e e

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Those persons and organizations with the above authority are X X X identified and a description of how those actions are carried out b i s p ro,vided.

184. .a. , Dessgnated QA personnel, sufficiently free f rom direct pressures X~

3 for cust/sc,hedule, have. the responsibility delineated in ,

wriCing to stop unsatisfactory work and control rurther

> ocessing, dnl ive ry, or,insta l lation of noncon fo rr.i ng ma te ria l .

b. Thr, organ!zati$nal positibns with 'stor. work authors ty are X X X

, identified. ,

185. Provisions are estabifahed for the resolution cf' disputes X X ,

involving quality, arising f rom a dirrorence or opinion' between .( -

3 3A personnel and other department (engineering, procurement, ',# s .

tr.Jeuractur ing, etc. ) personnel .

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1B6.

Designated QA individuals,are involved in day-to-day'pfant'activitics X X X*

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f;;- ? ,

important to safety (3.2., the QA organization routinely attends,and participates in daily plant work schedLie shd Status meetings to t assure they are kept abreast or day-to-day work assignments i i, throughout the plant and that there is adequate QA ccverage 'reintive -[ .

to procedural and inspection controls, acceptarse- criteria, an4JQA; ~3

/ starring and quaii.rication of personnel to carry out QA ass 8cnments). i

, _ . . i-IC1. Policies regarding the implementation of the QA program are - -X X X. --

documented and inade mandato ry. These policies are established

, atlthe .CorporJta Prcsident or Vice President level. 1: ,_] --

, 3 a . , r X

i

' IC2. - Position description (s?e 181) assures that the individuit directly X X #

tesponsible for the definition, direction, and errectiveness or the overall QA program has sufficient authority to errectively implement responsibilities. This position is to be sufficiently free from cost and schedule responsibilities. Qua li fication requi rements for this individual are established in a position description vhech _

includps the rollowing prerequisites: f" -

a. Management experience through assigreents to responsible 'X 'X X positions.

De l e te " . . . QA. . . " a nde " . .' , the QA o rg a n i za t i on. . . " fo r i l min./III ma~x. e , ,'

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

Page 22 i Min il Min GUIDELINE Re r, 1 Max II Max 111 Max ill Min

! b. knowledge of QA regulations, policies, practices, and X X X standards.

c. Experience working in QA or related activity in reactor design, X X X construction, or operation or in a similar high technological industry.

The qualifications of the QA Manager should be at least equivalent X X X to those described in " Selection and Training of Nuclear Power Plant Personnel," is endorsed by the regulatory positions in Regulatory l Guide 1.8. -

4.4 PROFESSIONAL-TECHNICAL The on-site professional-technical groups leaders shall possess ANS 3.1 X X X the following qualifications in the indicated disciplines. A single individual may be qua l i f i ed a nd pe rf o rm i n mo re tha n one discipline.

4.4.5 QUALITY ASSURANCE i

s. EDUCATIDN: Bachelor Degree in Engireering or related~

ANS 3.1 X X X.

science. ,.

i C.2 When the phrase " bachelor's degree or equivalent" is used, R.G. 1.8 X X X [

the qualifications considered as minimum acceptable substitutes for a bachelor gree are a nigh school diploma or its equivalent anu one of the following:

i

a. Fou r yea rs o f fo rma l school i ng in science or eng i nee ring; ;

I

, b. Four years of applied experience at a nuclear racility in the area for which qualification is sought;

c. Four years or operational or technical experience or i training in nuclear power; or ;

d. Any combination of the above totaling four years, i i

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. .

a t

9 8 e 9 Page 2]

I Min il Min GUIDELINE Ref. I Max il Max 111 Ma x ill Min

b. EXPERIENCE: At the time of initial core loading or X X X appointment to the active position, the responsible person shall have four (4) years experience in the field of quality assurance, or equivalent number of years of nuclear plant experience i n a supe rvi so ry

position preferably at an operating nuclear plant or a combination of the two. At least one (1) year of this four years experience shall be nuc lea r powe r plant experience in the implementation of the quality assurance prog ram.

c. TRAINING: As requi red by 5.3.2 and 5.4. X X X 1C3. The person at the construction site responsible for X X X directing and managing the site QA program is identified by position and has appropriate organizational position, a responsibilities, and authority to exercise proper control over the QA program. This individual is free f rom non-QA duties and can thus give full attention to assuring that the QA program at the plant site is being effectively implemented.

3.3 The persons or organizations responsible for verifying ANS 3.2 X X X that the administrative controls and quality assurance program are implemented or of assuring that an activity has been correctly performed may report functionally to an offsite organization, or this responsibility can be divided between organizations reporting onsite and offsite.

If this responsibility is divided, the organization reporting offsite shall perform independent audits to verify program compliance, whereas the organization reporting shall perform surveil lance, inspection, and review activities for the purpose of process control, product acceptance, and to verify that various activities conform to specified requirements, i.e., the quality control function.

3.4.2 Requirements for the Onsite Operatine Organization The onsite operating organization shall include, a s ANS 3.2 X X X a minimum one or more individuals knowledgeable in the

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C- r i Page 22 t

I Min .Il Min GUIDELINE Re f. I Max 11 Max Ill Man ill Min rad iochemi st ry. These personnel shall be available (at the station or on call and capable of responding to the plant within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) for the purpose of providing technical advice to the shif t supervisor on a 24-hour-a-day ba si s. They may be part of the plant organization or they may be part of the offsite technical support for the plant staff, except that an individual-appropriately qua lified in the first four a reas listed above shall be onsite and capable of responding to the control room within 10 minutes after the start or an eme rgency.

3.5 Indoctrination and Training Provisions shall be made for indoctrination and training ANS 3.2 X X X of those personnel in the owner organization performing activities affecting quality to assure that suitable proficiency is achieved and maintained. Such personnel also shall be provided training concerning the administrative controls and quality assurance program which, as a minimum, shall include the following areas:

ove ra l l company policies, procedures, or instructions which establish the program; procedures or instructions which implement the program related to the specific job-related activity.

i r l

l

Page 26 i Min 11 Min Cul0ELINE Ref. I Max il Max til Max lli Min The Organization (SRP Section 17.2.1) elements responsible for the QA Program are acceptable if:

1. The criteria in 17.1.1 are satisfied except for: X X X

a. Item 1A4. (delete for this part) X X X

b. The organizational elements within the parenthesis in item 1A5 X X X be expanded to include operations and maintenance.

4

c. The requi rements that principa l contractors describe QA T. X X responsibilities be deleted in item 1A6.

d. The requirements that a QA position be identified for principal X X X contractors as described in item IB1, be deleted,

e. "The person at the construction site responsible for directing X X X and manag ing the si te QA prog ram. . ." described in item IC3, be changed to The person. . . responsible for. . . the onsi te QA Program," and continue on with remaining sentence starting with "has appropriate organizationa l . . . ."

Activities related to Quality Assurance Program (17.1.2) are acceptable if:

2A1. The scope of the QA program includes-

a. A commitment that activities arrecting structures, systems, X X X and components important to safety will be subject to the applicable centrols of the QA program.

The structures, systems, components, and related consumables Not add ressed--included covered by the QA program are identified (QA list) in in the equipment listings.

Section 3.2.1 of the SAR.

b. A commitment that the preoperational test program will be X X X conducted in accordance with the QA program and a description o f how the QA p rog ram wi l l be applied.

, c. A commitment that the development, control, and use of computer X X X code programs will be conducted in accordance with the QA program and a description of how the QA program will be applied.

Editorial change.

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' * > e Page 21 1 Min 11 Min CUIDELINE Ref. I Max ll Max lit Max ill Min

d. The identification of fire protection in SRP Section 9.5.1 as Not addressed as equipment a system covered by the QA program or identification of the QA listings include fire controls for fire protection. These controls are reviewed and p rotection accepted using the guidelines contained in BTP ASB 9.5-1 and 10 CFR Part 50 Appendix B as appropriate.

e. A commitment that special equipment, env i ronmenta l conditions, X X X skills, or processes will be provided as necessa ry, 2A2. A brief summary of the company's corporate QA policies is given. X X X 2B1. a. Provisions are established to assure that quality-affecting X X X procedures required to implement the QA program are consistent with QA program commitments and corporate policies and are properly documented, controlled, and made mandatory through a policy statement or equivalent document signed by the responsible officia l,

b. The QA organization reviews and documents concurrence with X, X X these qua l i ty-rela ted p rocedu res.

c. The organizational group or individual having responsibility X X X for the policy statement should be identified.

d. The quality affecting procedural controls of the X X X contractors should be provided for the applicant' principal s review with documented agreement of acceptance prior to initiation of activities affected by the program.

2B2. Provisions are included for notifying NRC of changes (1) for review X X X and acceptance in the accepted description of the QA program as presented or referenced in the SAR or SSAR prior to implementation, and (2) in organizational elements within 30 days af ter announcement.

Note - editorial changes or personnel reassignments of a non-substantive nature do not require NRC notification).

~

2B3. The applicant (and the principal contractors) commits to comply with X X the regulatory position in the appropriate issue of the Regulatory Guides listed in Subsection VI;

. to comply with 10 CFR Pa rt 50, 50.55a; X l

Page .?Q l Min il Min GUIDELINE Ref. I Max 11 Mas lli Max 114 Men to conduct activities under 10 CFR Part 50, 50.55(e) in accordance X with the QA program; X X X X and to comply with 10 CFR Part 50 Appendix A, Gene ra l Design Criteria 1.

X

For systems, components, and structures covered by the ASME Code Section Ill (Classes 1, 2 and 3), the quality assurance code requirements should be supplemented by the specific guidance addressed in the regulatory nositions of the applicable Regula to ry Guides. The commitment identifies the Regulatory Guides and ANSI standa rd by number, title, and revision or date. Any alternatives or exceptions are clearly identified and supporting information presented in the docket. QA Regulatory Guides should be addressed which have an implementation date prior to the submittal or docket date of the QA program description.

Although prima ry responsibli ty for Regulatory Guides 1.26 and 1.29 No t a QA p rog ramma t ic requirement--info only is assigned to ASB (SRP Sections 3.2.1 and 3.2.2), their use as acceptance criteria in this SRP section is necessary to assure that adequate quality assurance requirements are specified for systems, i

components, and structures addrested by those guides.

X X X X*

The QA organization and the necessary technical organizations participate early in the QA program definition stage to determine and identify the extent QA controls are to be applied to specific structures, systems, and components. This errort involves applying a defined graded approach to certain structures, systems, and components in accordance with their importance to safety and arrects such disciplines as design, p rocu rement, document control, inspection tests, special p roce s se s , records, audits, and others described in 10 CFR Part 50, Appendix B.

X

- 2B4. QA procedures reflect that Regulatory Guides listed in subsection VI, X X X X General Design Criterion 1 of Appendix A to 10 CFR Part 50, 50.55a, and each criterion or 10 CTR Part 50, X 10 CFR Pa rt 50, Appendix B will be met by documented procedures. In addition, activities conducted under 10 CFR Part 50, 50.55(e) shall con fo rm to the requirement of the QA program.

X 285, A description is provided that emphasizes how the docketed QA program description, particularly the 10 CFR Part 50 regulations and Regulatory Guides listed in subsection VI, will be property ca rried out.

Delete ". . . The QA organization and.. ." for 111 min.

- Editorial changes.

s e-

.s e - y e.

Page 22 i Min il Min GUIDELINE Ref. 1 Max il Max ill Max 518 Min 2C1 A description is provided of how management (above or outside X X X the QA organization) regularly assesses the scope, status, adequacy, and compl iance of the QA prog ram to 10 CFR Pa rt 50, Appendix B.

These measures should include:

a. Frequent contact with program status through reports, meetings, X X and/or audits,

b. Performance of an annua l assessment preplanned and documented. X X Corrective action is identified and tracked.

l 2C2. Quality-related activities (such as design, p rocu rement, and site X X X investigation) initiated prior to formal NRC acceptance of the QA program are controlled under a QA program in accordance with this SRP and, accordingly, with the requi rements or 10 CFR Pa rt 50, Appendix B. Approved procedures and a sufficient number of trained personnel should be available to implement the applicable portion of the QA program prior to the initiation of the activity.

2C3. A summa ry description is provided on how responsibilities and control X X X of quality-related activities are transferred f rom the principal contractors to the applicant during the phaseout of design and construction and during preoperational testing and plant tu rnove r.

2D. Indoctrination, training, and qualification programs are established X X X such that:

a. Personnel responsible for performing quality-affecting X X X activities are instructed as to the purpose, scope, and implementa tion of the qua l i ty-rela ted manua l s, instructions, and procedures,

b. Personnel verifying activities affecting quality are trained X X X and qualified in the principles, techniques, and requi rements of the activity being performed.

- c. For formal training and qualification programs, documentation X X X includes the objective, content of the program, attendees, and date of attendance.

Page 33 i Min il Min Cul0ELINE. Per. I Max ll Ma. lit M.i . lis Min

d. Proficiency tests are given to those personnel performing and X X X veri fying activi ties a rrecting quality, and acceptance criteria are developed to determine if individuals are properly trained and qualified.

e. Certificate or qualifications clearly delineates (a) the X X X specific functions personnel a re qua li fied to perform and j (b) the criteria used to qualiry personnel in each function.

f. Proficiency or personnel performing and verifying activities X X X affecting quality is maintained by retraining, reexamining, and/or recertifying as determined by management or program commitment.

l

g. The training program provisions listed above satisfy the SitP review note regulatory position in Regulatory Guide 1.58. I f

The Qua lity Assurance Program (SRP Section 17.2.2) is acceptable'ir: ;

1

1. The criteria in 17.1.2 are satisfied except for: X X X l

i l a. The requirement for the principal contractors to provide X X X a commitment to comply with the regulations and regu l a to ry positions in the Regulatory Guides addressed in item 2B3.

2. Provisions are established for ' assuring the QA program for operations X X X is implemented at least 90 days prior to fuel loading.

3. Confirmation is provided to commit to continued implementation of X X X the PSAR QA program for the remaining design and construction activities and the preoperational test program or an acceptable alternative is provided.

( Activities related to Design Control (17.1.3) a re acceptable ir:

3A. The scope of the design control program includes design activities X X X associated with the preparation and review of design documents including the correct translation or applicable regulatory requi rements and design bases into design, procurement and procedural documents. Included in the scope are such activities as field design engineering; physics, seismic, stress, the rma l , hyd ra u l i c ,

Ed i to ria l changes.

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9 e Page 11 1 Min 11 Min l CUIDELINE Re r. I Max 11 Max til Max Ill Min i

radiation, and the SAR accident analyses; associated computer programs; compatibility of materials; accessibility for inservice inspection, maintenance, and s epa i r; and qua l i ty standa rds.

3B. Organizational responsibilities are described for preparing, X X X reviewing, approving, and verifying design documents such as system descriptions, design input and criteria, design drawings, design i' analyses, computer programs, specifications, and procedures.

3C1. Errors and deficiencies in approved design documents, including X X X design methods (such as computer codes), that could adversely t arrect structures, systems, and components [important to safetyl a re documented and action is taken to assure that all errors and i deficiencies a re corrected.

t 3C2. Deviations from specified quality standards are identified and X X X procedures are established to ensure their control. ;

3D. Internal and external design interface controls, procedures, and X X X lines or communication among participating design organizations and :

, across technical disciplines are established and described in the l i review, approva l, release, distribution, and revision or documents involving design interfaces .to assure structures, systems, and components are compatible geometrically, functionally, and with i

processes and envi ronment.

i i

3E1. Procedures are established requi ring a documented X X X check to verify the dimensional accuracy and completeness of design drawing and specifications.

'

3E2. Procedures are established requiring that design X X X drawings and specifications be reviewed by the QA organization to assure that the documents are prepared, reviewed, and approved in accordance with company procedures and that the documents contain the necessary quality assurance requirements such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results.

Editorial changes.

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3E3. Guidelines or criteria are established for determining X X X the method or design verification (design review, alternate calculations, or test).

"

3E4. Procedures are established for design verification X X X

! activities which assure the following:

1

a. The verifier is qualified and is not directly responsible for X X the design ( i .e. , neither the performer or his immediate supe rv i so r) . In excep6ional ci rcumstances, the designer's immediate supervisor can perform the verification provided:

(1) The supervisor is the only technically qualified X X individual.

(2) The need is individually documented and approved in X X advance by the supervisor's management.

(3) QA audits cover frequency and errectiveness of use of X X supervisors as design verifiers to guard against abuse.

b. Design verification, if other than by qualification testing of X X X a prototype or lead production unit, is completed prior to release for procurement, manufacturing, construction or to another organization for use in other design activities. In those cases where this timing cannot be met, the design verification may be deferred, providing that the justification for this action is documented and the unverified portion of the design output document and all design output documents, based on the unverified data, are appropriately identified and controlled. Construction site activities associated with a design or design change should not proceed without verification past the point where the installation would become irreversible (i.e., require extensive demolition and rework). In all cases, the design verification should be complete prior to fuel load for a plant under construction, or in the case or an operating plant, prior to relying upon the component, system, or structure to perform its function.

Ed i to ri a l changes.

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c. P rocedu ra l cont ro l is established for design documents that X X X reflect the commitments of the SAR; this control differentiates between documents that receive formal design verification by interdisciplina ry or multi-organizational teams and those which can be reviewed by a single individual (a signature and date is acceptable documentation for personnel certification). Design documents subject to procedura l control include, but a re not limited to, specifications, calculations, computer programs, system descriptions, SAR when used as a design document, and d rawi ng s including flow diagrams, piping and instrument diagrams, control logic diagrams, electrical single line diagrams, structura l systems for major racilities, site arrangements, and equipment locations. Specialized reviews should be used when uniqueness or special design considerations wa r ra n t .

d. The responsibilities of the verifier, the a reas and features X X X to be verified, the pertinent considerations to be verified, and the extent of documentation are identified in procedures.

3ES. The following provisions a re included if the verification method is X X X (was 3E3) only by test:

a. Procedures provide criteria that specify when verification X .X X should be by test,

b. Prototype, component or feature testing is performed as early X X X as possible prior to installation of plant equipment, or prior to the point when the installation would become irreversible.

c. Verification by test is performed under conditions that simulate X X X the most adverse design conditions as determined by analysis.

3E6. Procedures are established to assure that verified computer codes X X X

' (was 3E4) are certified for use and that their use is specified. 3F1. Design and specification changes, including fields changes, are X X X subj ect to the same design controls that were applicable to the o rig i na l design.

Editorial changes to SRP--there worn two paragraphs 3E3 and 3E4.

i Page lh 1 Min 11 Hin CUIDELINE Ref. 1 Max ll Max ill Max lli Min

3FP. The design control provisions satisfy the criteria of SRP review note Recul*; tory Guide 1.64 ,

5.2.7.2 Modirications Design activities associated with modifications of structures, ANS 3.2 X X X systems, and components important to safety shall be accomplished in accordance with NQA-1. In addition, written safety evaluations shall be prepared in accordance with 10 CFR 50.59, and these safety evaluations shall be reviewed as discussed in Section 4.3.4. 4.3.4 Sub.iects Recuirino independent Review The following subjects shall be reviewed by the independent ANS 3.2 X X X review body:

            *                       (1) Written safety evaluations of changes in the facility                                  X      X      X as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report and tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1).

This review is to verify that such changes, tests or experiments did not involve a change in the technical specifications or ~an unreviewed safety question as defined in 10 CFR SO.59(a)(2).

            *                       (2) Proposed changes in procedures, proposed changes in the                                X      X      X facility, or proposed tests or experiments, any of which involves a change in the technical specifications or an unreviewed safety question as defined in 10  CfR 50.59(c). Matters or this kind shall be referred to the independent review body by the onsite operating organization (see 4.4) following its review, or by other functional o rgan iza t iona l un i ts wi th i n the owne r o rga n i za t ion, prior to implementation.

(3) Changes in the technical specifications or license X X X amendments relating to nuclear safety prior to submittal to the Commission for approval and prior to implementation.

Editoria l changes.

p a Page lh 1 Min il Min GUIDELINE Re f. 1 Max 11 Max lil Max ill Min (4) Violations, deviations and reportable events which require X X X reporting to the NRC in writing.

Review of events covered under this subsection shall X X X include the results of any investigations made and the , recommendations resultin9 from such investigations to prevent or reduce the probability of recurrence of the event. (5) Any other matter involving safe operation of the nuclear X X X power plant which an independent reviewer deems appropriate for consideration, or which is referred to the independent reviewers by the onsite operating organization or by other functional organizational units within the owner organization. Activities related to Desion Control (SRP Section 17.2.3) are acceptable if:

X X X 1 The criteria in 17.1.3 are satisfied.

2. Measures are provided to assure that responsible plant personnel a re X X X made aware of design changes / modifications which may affect the performance of thei r duties.

Activities related to Procurement Document Cont rol (17.1.4) a re acceptable if: 4A1. Procedures are established for the review of procurement documents ). X X to determine that quality requirements are correctly stated, inspectable, and controllable; there are adequate acceptance and rejection criteria; and procurement documents have been prepared, reviewed, and approved in accordance with QA program requi rements. To the extent necessa ry, procurement documents should require contractors and subcontractors to provide an acceptable quality assurance prog ram. The review and documented concurrence of the adequacy of quality requirements stated in procurement documents is performed by independent personnel tra ined and qua li fied in QA practices and concepts. 5.2.13.1 Where changes a re made to procurement documents, they ANS 3.2 X X X shall be subject to the same degree of control as was used in the preparation of the original documents.

Editorial changes.

Page 16 i Min il Min GUIDELINE Ref. I Max il Max til Max Ill Min 4A2. Procedures are established to assure that procurement docnmcnts X X X identify applicable regulatory, technical, administrative, and reporting requ i remen ts; d rawi ng s; specifications; codes and industrial sta nda rd s; test and inspection requirements; and special process instructions that must be complied with by suppliers. 5.2.13.1 (3) Source Inseection and Audit. Provisions for access to ANS 3.2 X X X the supplier's racilities and records for source inspection and audit when the need for such inspection or audit has been determined. (4) Documenta tion 7 equi rements. Records to be prepa red, X X X maintained, submitted or made available for review or a pp rova l , such as drawings, specifications, procedures, procurement documents, inspection and test reco rd s, personnel and procedure qualifications, and material, chemical, and physical test results. Instruction on

. reco rd retentior.-and disposition shall be p rovided.

 -                         (5) Lower Tier Procurement. Provisions for extending                                  X      X     X applicable requirements to lower tier subcontractors and suppliers, including purchaser's access to racilities and reco rd s .

481. O rga n iza t iona l responsibilities are established for (1) p rocu rement X X X planning; (2) the prepa ra tion, review, approval, and control or procurement documents; (3) supplier select 6on; (4) bid evaluations; and (5) review and concurrence or supplier QA programs prior to initiation of activities arrected by the program. The involvement of the QA organization is described.
482. The procurement document control p rov i s ions listed above SRP review note satisfy the regulatory position in Regulatory Guide 1.123.

I Act ivi t ies rela ted to Procurement Document Control ( 17.2.4 ) a re acceptable if:

1. The cri teria in 17.1.4 are satisticd. X X X
Edi to ria l changes.

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Page 13 1 Min- Il Min GUIDELINE Rer. 8 Max ll Max lli Max 111 Min (5) Sequence or tests (6) Sequential actions to be rollowed (7) f requency or inspection or test (8) Pre requ i s i tes (9) App rova l requirements (10) Sultable-form for reporting data (11) Provision for identification or test equipment and date or next requi red recalibration (where requi red) for interpretation or test resu l ts (12) Inspection and test acceptance limits (13) References (14) Other pertinent items

 -                                             The abnve items shall be used as a check list and shall be marked as required or not appropriate when preparing procedures or instructions.

Activities related to Instructions. P rocedu re s. and Drawings (17.2.5) a re acceptable Jr: ,

X X X

1. The criteria in 17.1.5 a re satisfied.

Activities related to Qpcument Control (17.1.6) a re acceptable ir: l X

6A1. The scope or the document control program is established, and the X X types or controlled documents are identified. As a minimum, controlled documents include:
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e .

Page 12 1 Min il Min GUIDELINE Ref. 1 Max il Max ill Max III Min

a. Design documents (e.g., calculations, drawings, specifications, analyses) including documents related to computer codes.

b. Procurement documents.

c. Instructions and procedures for such activities as fabrication, construction, modification, installation, test, and inspection.

d. As-built documents.

' e. Quality assurance and qua s ity centrol manuals and quality-affecting procedures.

                .f. Topical reports.

9 SAR.

h. Nonconformance reports.

Procedures for the review, approval, and issuance of documents and X X X 6A2.

changes thereto are established to assure technical adequacy and inclusion of appropriate quality requirements prior to implementation. The QA organization, or an individual other than the person who X X generated the document but qua l i fied in quality assurance, reviews and concurs with these documents with regard to QA-related aspects. 6A3. Procedures are established to assure that changes to documents are X X X reviewed and approved by the same organization that performed the initial review and approval or by other qualified responsible organize.tions delegated by the applicant. 7.2 The reviewing organizations sha ll have access to pertinent ANSI X X X background data information upon which to base thei r approval. N45.2.11 However, minor changes to design documents, such as inconsequential editorial corrections or changes to commercial terms and cond i t ions, may not requi re that the revised document receive the same review and approval as the original documents. To avoid a possible omission of a required review, the type of minor changes which do not require such a review

Edi toria l changes.

Page h9 i Min il Min . CUIDELINE Rer, 1 Max 18 Max ill Max Ill Min and approval and the persons who can authorize such a decision , shall be clearly delineated in the document control p rocedu re s. 6A4. Procedures are established to assure that documents are available X X X at the location where the activity will be performed prior to commencing the work.

601. Procedures are established to assure that obsolete or superseded X X X documents.are removed and replaced by applicable revisions in work areas in a timely manner.

6B2, A master list or. equiva lent document control system is established X X X to identify the current revision or instructions, p rocedu re s , specifications, drawings, and procurement documents. When such a list is.used, it should be updated and distributed .to predetermined responsible personnet.

 '*        6C1. Procedures are established to provide for the preparation of                                                 X       X        X as-buil t drawings and related documentation in a . t imely manner to accurately reflect the actual plant design.

Activities related to Document Control (17.2.6) a re acceptable 10:

1. The criteria in 17.1.6 a re sa ti sfied. X X. X

2. Maintenance, n9dification and inspection procedures a re reviewed X X X by qualified personnel knowledgeable in QA disciplines (normally the QA organization) to determine:

a. 1r.e need for inspection, identification or inspection X X X personnel, and documentation or inspection results.

b. That the necessary inspection requirements, methods, and X X X acceptance criteria have been identified.

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Page h1 1 Min 11 Min GUIDELINE Rer. I Max 18 Max ill Max lit Min Activities related to Control of Pu rcha sed Ma te r i a l . Equipment. and Services ( 17.1. 7 ) a re acceptable ir:

               **                                 O rgan i za t i ona l responsibilities are established for the control of                               X    X     X 7A1 purchased materia l, equipment, and services including interfaces between design, p rocu rement, and QA organizations.

Verification of suppliers' activities during fabrication, inspection, X X X* 7A2. testing, and shipment of materials, equipment, and components is planned and performed with QA organization participation in accordance with written procedures to assure conformance to the purchase order requi rements. These procedures, as applicable to the method of procurement, provide for: X X X

a. Specifying the characteristics or processes to be witnessed, inspected or verified, and accepted; the method of surveillance and the extent or documentation required; and those responsible for implementing these procedures, Audits, surveillance, or inspectiont which assure that the X X X b.

supplier complies with the quality requirements. Selection of suppliers is doc?smented and filed. If an LCVIP letter X X 7A3. of confirmation or the " CASE" Register is used to establish the qualifications of the supplier, the documentation should identify the " letter" o r "aud i t" used. A documented system for reviewing and evaluating the bids and ANSI X X X 5.1 N45.2.13 awa rding of contracts sha ll be established by the Purchaser. ANSI X X X

                                                  $.2   The Purchaser shall establish measures to assure that the bid       N45.2.13 conforms to the procurement document requirements.

The bid evaluation shall be made by individuals or ANSI X X X organizations designated to evaluate the following subjects, N45.2.13 as applicable to the type of procurement:

Delete "wi th QA Organization pa rticipation" fo r i l min ill max.

               ** Ed i to ria l changes.

Pago I2 J 1 Min ll Min CUIDELINE Ref. I Max il Max 111 May lli Min

a. Technical cons ide ra t ions,

b. Qua li ty assurance requi rements.

c. Resea rch and development effort,

d. Suppliers' personnel.

e. Suppliers' production capability.

f. Suppliers' past performance,

g. A l te rna tes.

h. Exceptions.

Other considerations such as warranties, schedule, price, price adjustments, commercial terms and conditions, although not quality related, are recognized as factors affecting bid evaluation. 7A4. Procurement of spa re or replacement pa rts for structures, systems, . X X X and components important to safety is subject to present QA program controls, to codes and standa rds, and to technical requi rements equal to or better than the original technical requi rements, or as required to preclude repetition of defects. 7.3 Implementation I 7.3.1 Source Verification Activities. When planning requires ANSI X X X Purchaser source surveillance, it shall be implemented to N45.2.13 monitor, witness or observe activ'ities. Simi la rly, source inspection shall be implemented in accordance with plans to pe rfo rm inspections, examinations, or tests at predetermined points. Source surveillance and inspection may require the assignment of personnel to a Supplier's facilities. When conformance to procurement requirements is verified by X X X audit, such audits shall be conducted in accordance with established methods.

                                                       *                 '                                                             e               .

Page 3] 4 i Min il Min GUIDELINE Re r. I Max il Max ill Max fil Min 781. Receiving inspection i s pe r fo rmed to assure:

a. The material, component, or equipment is properly identified X X X and corresponds to the identification on the purchase document and the receiving documentation.

7.3.2 Receiving Inspection: When planning requi res Purchaser ANSI X X X receiving inspection, it shall be implemented and N45.2.13 coordinated with source verifications performed.

b. Ma t e r i a l , components, equipment, and acceptance records satisfy X A X the inspection instructions prior to installation or use.

c. Specified inspection, test and other records (such as X X X certificates of conformance attesting that the material, components, and equipment conform to specified requirements) are available at the nuclear power plant prior to installation or use.

7.6 Measures shall be established to provide for the ANSI X X reporting of activities performed to verify conformance N45.2.13 to requirements of procurement documents. These measures shall include reporting or source surveillances and inspections, audits, receiving inspections, nonconformances, dispositions, waivers, and corrective actions. In addition, the Purchaser shall assure that these X X reports are evaluated to determine the Supplier's quality assurance program errectivene's. 10.2 Where not precluded by other requi rements, documenta ry ANSI X X evidence may take the form of written certificates or N45.2.13 conformance which identi fy the requi rements met by the and items. Where certi ficates or conformance a re. used, the R.G. 1.123 following minimum criteria shall be met:

a. The certificate shall identi fy the purchased X X ma te ria l or equipment, such as by the purchase order number,

b. The certificate shall identify the specific X X p rocu rement requi rements met by the purchased material or equipment, such a s codes, standa rds, and other specifications. This may be accomplished by including a list of the specific requi rements or by providing, onsite, a copy of the purchase order and the procurement specifications or drawings, together with a nuitable certificate. The p rocu rement requirements identified should include any approved changes, waivers, or deviations applicable to the subject ma te ri a l or equipment.

Page h3 1 Min l* Min GUIDELINE Ref. I Max ll Max ill Max Ill Min

c. The certificate shall identify any procurement X X requirements tnat have not been met, together with an explanation and the means for resolving the nonconfo rmances.

d. The certificate shall be attested to by a person who X X is responsible for this quality assurance function

                                          . and whose functica and position are described in the Purchaser's or Supplier's quality assurance program.

e. The certification system, including the procedures X X to be followed in filling out a certificate and the administrative procedures for review and approval of the certificates, shall be described in the Purchaser's or Supplier's quality assurance program.

7B2. Items accepted and released are identified as to their inspection X X status prior to forwa rding them to a controlled storage area.

Items shall be identified prior to releasing them for installation X X X or further work. 783. The supplier furnishes the following records to the purchaser: X X X

a. Documentation that identifies the purchased item and the X X X specific procurement requi rements (e.g. , codes, standa rds, and specifications) met by the item,

b. Documentation identifying any procurement requirements that X X X have not been met.

9.2 In the case or significant conditions adverse to quality ANSI X X which may'a rise during the procurement process, the N45.2.13 Purchaser s measures shall describe the method used to:

a. Identify and document deviations and nonconformances. X X

b. Review and evaluate the conditions to determine the cause, X X extent, and measures needed to correct and prevent recurrence,

c. Report the conditions and corrective action to the X X a pp rop ria te levels.or management.

d. Assure corrective action is implemented and maintained as X X nece ssa ry.

783 c. A description or those nonconformances from the procurement X X X requi rements d isposi t ioned " accept as i s" or "repa i r."

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Page h1 l Min ll Min GUIDELINE Ref. I Max 11 Max all Max lit Min ANSI X X 9.3 The Purchaser's corrective action measures shall include N45.2.13 verification or implementhtion of Supplier corrective action system. .These measures sha ll determine that conditions adverse to quality such as deficiencies, deviations, defective items and nonconformances have had correctivc action implemented and maintained as necessary. C.3 Section 9.3 or ANSI N45.2.13-1976 states, "The Purchaser's R.G.1.123 X X corrective action measures shall include verification or The implementation of Supplier's corrective action system." Purchaser should verify the implementation of the Supplier's corrective action system when such a system is required, but this verification need not be included as part of the Purchaser's corrective action measures. While Section 9.0 of ANSI N45.2.13-1976 addresses elements or the Purchaser's corrective action system, these same elements are applicable to the Supplier's corrective action system when one is requi red.

The review and acceptance of these documents should be described in X X X 783.

the purchaser's QA program.

For commercial " ort-the-shelf" items where specific quality issurance X X X 7B4.

controls appropriate for nuclear applications cannot be imposed in a practicable manner, special qua lity verification requi rements sha l l be established to provide the necessary assurance of an acceptable item by the purchaser. X X X 7B5. Suppliers' certificates or conformance are periodically evaluated by audits, independent inspections, or tests to assure they are valid and the results documented.

The control or procurement provisions listed SRP review note 7B6.

above satisfies the regulatory position in Regulatory Guide 1.38 and Regulatory Guide 1.123. Activities related to Control of Purchased Materia l . Eauipment and Services (17.2.7) a re acceptable ir: X X X

The criteria in 17.1.7 a re sa tisfied.
Edi toria l changes.

Page h6 GulDEllNE i Min il Min Ref. I Max il Max lit Max 111 Min Activitses related Components ( 17.1.8) to identi a ref acceptableica_ tion _and if: Cont rol o f Ma te r i a l s. Parts, and 8A. Controls are established to identify and control X X X materia ls ( including consumables), pa rts, and components including partially fabricated subassemblies. O rgan i za t iona l responsibilities shall be identified. 881 Procedures are established which assure that identification is X X X ma inta ined ei ther on the item or on records traceable to the item to preclude use of incorrect or defective items. 5.2.13.3 These procedures shall be implemented to provide assurance ANS 3.2 X X X that only correct and accepted items a re used and installed and relate an item of production (batch, lot, component, pa rt ) a t any stage, from initial receipt through fabri-cation, installation, repa i r or modi fication, to an appli-cable drawing, specification, or nther pertinent technical document. Physical identification shall be used to the maximum extent possible. Where physica l identification is either imp rac t ica l or insufficient, physical sepa ra t ion, p rocedura l control or other appropriate means shall be employed. 8B2. Identification of materials and parts important to the function of X X X structures, systems, and components important to safety can be traced to the appropriate documentation such as drawings, specifications, purchase orders, manufacturing and inspection documents, deviation reports, and physical and chemical mill test repo rt s . 5.2.13.3 Whe re identification marking is employed, the marking ANS 3.2 X X X shall be clea r, unambiguous and indelible, and shall be applied in such a manner as not to affect the function of the item. Markangs shall be transferred to each part of an item when subdivided and shall not be oblitersted or hidden by surface treatment or coatings unless other means of identification are substituted. 5.2.13.3 When laws, standa rds or speci fications requi re trace- ANS 3.2 X X X abil i ty of ma teria l s, parts or components to specific inspection or test reco rd s, the p rog ram sha l l be designed to provide such traceability.

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9. Measures shall be established and documented for the N45.2 identification and control of materials, parts, and components including partially fabricated subassemblies.

These measures shall provide for assuring that only correct and accepted items are used and installed, and re la t i ng ' a n item.of production (batch, lot, component, pa rt) at any stage, from initial receipt . through fabrication, installation, repair or modification, to an applicable drawing,. specification or other. pertinent technical document. Physical identification shall be used to the maximum extent possible. Where physical identification is either impractical or - insufficient, physical sepa ra t i on, procedura l control, or other appropriate means shall be employed. Identification may be either on the item or on records traceable to. the item, . as appropria te. X X- X .- 883. Correct identi fication. of materia l, pa rts, and components is verified l and documented prior to release for- fabrication, assembling, shipping, and installation. Activities related to identification and Control of Materiais. Parts. and Components (17.2.8) a re acceptable . i r: X- X X

The criteria . in 17.1.8 a re satisfied.

Activities related to Control of Special Processes (17.1.9) a re acceptable if: X X. X

9A1. The criteria for determining those processes that are controlled as special processes' are established. As complete a listing as possible of.special processes,' which a re genera l ly those processes '

where direct inspection is impossible or disadvantageous, should be provided. Some examples a re welding, heat t rea t i ng, NDT,.and chemical cleaning. X X X**

9A2. . O rg a n i za t i ona l responsibilities including those for the QA organization are established for qualification of special processes, equipment, and personnel.

X X X*** 981. Procedures, equipment, and personnel associated with special processes are qualified and are in conformance with applicable -

Editorial changes.

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            *** Delete last sentence for 11 min./li t max.

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Page 1Q l Min il Min GUIDELINE Ref. I Max 11 Max til Max Ill Min responsible for the activity being inspected. if the individuals performing inspections are not part of the QA organization, the inspection procedures, personnel qualification criteria, and independence from undue pressure such as cost and schedule should be reviewed and round acceptable by the QA organization prior to the initiation of the activity. 2.1* Plans shall be developed for starring, indoctrination, and ANSI X X training of an adequate number of personnel to perform the M45.2.6 l required inspections. examinations, and tests and shall ; reflect the schedule of project activity so as to allow l adequate time for assignment or selection and training or l the requi red personnel . ANSI X

                  -2.1.1     Indoctrination. Provisions shall be made for the                               X indoctrination of personnel as to the technical objectives       N45.2.6 or the project; the codes and standard that are to be used; and the quality assurance elements .that are to be employed.

1082.' A qualification program for inspectors (including NDT personnel) is X X. X X established and documented, and the quallrication and certifications or inspectors are kept current. 3.1 The requirements contained within this Section define the ANSI X X minimum capabilities that qualify personnel to perform N45.2.6 inspections, examinations, and tests which are within the scope of this Standard. 3.2 There are three levels or qualification. The requi rements for ANSI X X each level a re not limiting with regard to organizational N45.2.6 position or professional status, but ra the r, a re limiting with regard to functinna t activities which are within the scope of thi s Standa rd. l 3.3 A Level l' person shall be capable or performing the ANSI X X inspections, examinations, and tests that are required to be N45.2.6 performed in accordance with documented procedures and/or industry practices. The individual shalf be familiar with the tools and equipment to be employed and shall have demonstrated l

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0 e Page il 1 Min 11 Min GUIDELINE Ref. I Max il Max ill Max til Min proficiency in their use. The individual shall also be capable of determining that. the calibration status of inspection and measuring equipment is current, that the ressuring and test equipment is in proper condition for use, and that the inspection, examination, and test procedures are approved. ANSI X X 3.4 A Level 11 person shall have all of the capabilities of a N45.2.6 Level I person for the inspection, examination or test category or class in question. Additionally, a Level li person shall have demonstrated capabilities in planning inspections, examinations, and tests; in setting up tests as including preparation and set-up of related equipment, app rop r ia te; in supervising or maintaining surveillance over the inspections, examinations, and. tests; in supervising and certifying lower level personnel; in reporting inspection, examination. and testing results; and in evaluating the validity and acceptability of inspection, examination, and test results. X X A Level 111' person shall have all of the capabilities of a Level Il person for the inspection, examination or test In addition, the individual category or class in question. shall also be capable of evaluating the adequacy of specific programs used to train and test inspection, examination, and test personnel whose qua l i fications a re covered - by this Standard. ANSI X X 3.5 The following is the recommended personnel education and N45.2.6 experience for each level. These education and experience recommendations should be treated to recognize that other factors may provide reasonable assurance that a person can competently perform a particula r task. Other factors which may demonstrato capability in a given job are previous perf ormance or satisfactory completion of capability testing. 3.5.1 Level I ANSI X X (1) Two years of related experience in equivalent inspection, N45.2.6 examination, or testing activities, or ANSI X- X (2) High school graduation and six months of related N45.2.6 expe r i ence in equivalent inspection, examination, or testing activities, or ,

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Page 15 1 Min il Min GulDLLINL Ref. 1 Max il Max Ill Max ill Min i 2.3 Pr./s i ca l ANSI X X th6 responsible organization chall identify any special N45.2.6 physical characteristics needed in the performance or each activity. Personnel requi ring these characteristics shall have them verified by examination not to exceed one yea r.

4. PERFORMANCE Personner who a re assigned the responsibility and authority to ANSI X X perform functions covered by this Standard shall have, as a N45.2.6 minimum, the level of capability shown in Table 1. When a single inspection or test requires implementation by a team or g roup, personnel not meeting the requirements of this Standard may be used in data-taking assignments or in plant or equipment operation provideo they are supervised or overseen a by a qualified individual participating in the inspection, examination, or test.

X X X X 10C1. Inspection procedures, instructions, or checklists provide for the l following: X X X X l

a. Identification or characteristics and activities to be l inspected.

X X X

0. A description or the method of inspection.

X X X

c. Identification of the individuals or groups responsible for performing the inspection operation in accordance with the provisions of item 1081.

X X X X j

d. Acceptance and rejection criteria.

X X X X

e. Identification or requi red procedures, drawings and specifications and revisions.

X X X X

f. Recording inspector or data recorder and the results or the inspection operation, X X X

g. Specifying necessary measuring and test equipment including accuracy requi rements.

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

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e ' , Page 22 1 Min li Min CUIDELINE Ref. I Max II Max Ill Max ill Min

10C2. Procedures a re established to identi fy, in pertinent X 'X X X documents, mandatory inspection hold points beyond which work may not proceed until inspected by a designated i nspec to r.

10C3. Inspection results a re documented, evaluated and their acceptability X X- X X determined by a responsible individual or group. The owner organization shall evaluate inspection results ANS 3.2 X X X 5.2.17 along.with test results ( see Section 5.2.19) to determine whether the individual inspection and test programs demon-s t ra te tha t the plant can be operated safely and as

                                                            . designed. Records sha ll be kept in sufficient detail to permit adequate confirmation of the inspection program.

The person recording the data as well as - the person approv-ing the inspection results shall be identified. Devia t ions, thei r cause, and any corrective action completed or planned as a result of the deviations shall be documented, inspec-t ion reco rd s sha l l be identified as such and shall be retrievable. Activities related to inspection (17.2.10) are acceptable if:

X X X. X

1. The criteria in 17.1.10 a re satisfied.

When inspections associated with normal operations of the plant X X X 2. ( such as routine ma intenance, surveillance, and tests) are performed by individuals other than those who performed or directly ' supervised the work, but are within the same group, the ' ro l l owi ng cont ro l s a re me t: , The quality of the work can be demonstrated through a functional X X X-s. test when the activity involves breaching a pressure retaining j item. The qualification criteria for inspection personnel are X X X l b. l' reviewed and round acceptable by the QA organization prior 1 to initiating the inspection. l l

Editorial changes.

Page h3 i Mits' !! Man GUIDELINE Pef. I Max il Max !!! Max lit Men Activities'related to Teil_fonfrol (17.1.11)'are acceptable if: 11A1. The scope of the test control program indicates X X X X an effective test program has been established for tests including proof tests prior to installation and preoperational tests. Program procedures provide criteria for determining the accuracy requi rements of test equipment and criteria for determining when a test is required or how and when testing activities are performed. 5.2.19 A test program sha ll be established to assure that testing ANS 3.2 X X X requ i red to demonstrate that the item will. perform satis factorily in service is identified and documented, and that the testing is performed in accordance with wri tten test procedures which incorpora te or reference the requi rements and acceptance limits contained in applicable design documents. The test program sha l l cover all requ i red tests including: (1) Tests during the preoperational pe ri od to demonstrate ANS 3.2 X X X that performance of plant systems is in accordance with design intent and that the coordinated operation of the plant as a whole is satisfactory, to the extent feasible. (2) Tests during the initial operation phase to demonstrate ANS 3.2 X X X the performance of systems and components that could not , be tested prior to operation and to confirm those physical pa ra me te rs, hydraulic or mechanical characteristics that need to be known, but which could not be predicted with the requi red accuracy, and to confirm that plant behavior conforms to design criteria. The initial sta rt-up test prog ram sha l l be planned to permit safe fuel loading and start-up; to increase power in safe ' increments; and to perform major testing at specified power plateaus. I f tests requi re the va ria tion of operatino parameters outside of their normal ra ng e , the limits within which such va riation is permitted shall be prescribed. Prerequisites and record keeping shall be given attention and the scope of the testing shall demon s t ra te insofar as practicable that the plant is capable of withstanding the design transients and accidents. The suitability of plant operating procedures shall be checked to the maximum extent possible during the preoperational and initial sta rt-up test prog rams.

Editorial changes.

                            ,        s                                                         *

d
e e Page 52 1 Min il Min GUIDELINL Ref. I Max 11 Max 118 Max Ill Min (3) Surveillance tests during the operational phase to ANS 3.2 X X X provide assurance that ra ilures or substanda rd performance do not remain undetected and that the required reliability of systems important to safety is maintained.

(4) Tests during design, fabrication and construction ANS 3.2 X X X activities associated with plant maintenance and modifications during the operationa l phase and the demonstration or satisfactory performance following plant maintenance and modifications or procedural changes. 11B1 Test procedures or instructions provide as required for the following: , s. The requirements and acceptance limits contained in applicable X X X X design and procurement documents,

b. Instructions for performing the test.

c. Test prerequisites such as calibrated instrumentation, adequate X X X X test equipment and instrumentation including thei r accuracy requirements, completeness or item to be tested, suitable and controlled environmental conditions, and provisions for data collection and storage.

d. Manda to ry inspection hold points for witness by owner, X X X X contractor, or inspector (as requi red),

e. Acceptance and rejection criteria. x x x x

r. Methods of documenting or recording test data and results. X X X X

g. Provisions for assuring test prerequisites have been met. X X X X 11C1. Test resul ts a re documented, evaluated, and thei r acceptabi li ty X X X determined by a responsible individual or g roup.

Page 10 1 Min it Hin GUIDELINE Ref. I Ma x 11 Max fil Max ill Min Activities related tu les_LC_ong rgj ( 17.2.11) a re acceptable if:

The criteria in 17.1.11 a re satisfied. X X X X Activi ties related to Cont rol of Measurina and Test Eauionent (17.1.12) are acceptable if:
12.1 The scope of the program for the control of measuring and test X X X X equipment is established 'and. the types of equipment to be controlled a re establ i shed. This information indicates an effective calibration program has been reestablished.
12.2 QA and other organizations' responsibilities are identified for X X X X establishing, implementing, and assuring effectiveness of the ca libration program.
12.3 Procedures are established for calibration (technique X X X X and frequency), maintenance, and control of the measuring and test equipment (instruments, tools, gages, f i x tu re s , reference and transfer standards, and nondestructive test equipment) that is used in the measurement,' inspection, and monitoring of structures, systems, and components. The review and documented concurrence of these procedures is described and the organization responsible for these functions is identified.

12.4 Measuring and test equipment is identified and traceable to the X X X X

calibration test data.

12.5 Measuring and test equipment is labeled or tagged or "otherwise X X X X controlled" to indicate due date of the next calibration. The method of "otherwisc controlled" should be described. 2.8.2 Measures shall be taken to assure proper handling, ANSI X X s to ra ge, and care of the measuring and test equipment M45.2.8 af ter ca l ibration in order to ma inta in the requi red , accuracy of such equipment. 3.5 Measuring and Test Equipment. Measuring and test equipment ANSI X X used to determine compliance with specifications shall be N45.2.4

;                                controlled in accordance with the requi rements of IEEE          (IEEE 336)

I Std 498-1975. When genera l voltage levels, flow di rections or other parameters are checked, an uncontrolled indicating ! instrument may be used.

Editorial changes.

                                                     ) e e                       .

Page 61 i Min il Min GUIDELINE Ref. I Max 11 Max ill Max ill Min i 12.6 Measuring and test equipment is calibrated at specified inte rva l s X X X X based on the requi red accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting the measurement. Calibration of this equipment should be against standards that have X X X X an accuracy of at least - rour times the .requi red accuracy of the equipment being calibrated or, when this is not possible, have an accuracy that assures the equipment being calibrated will be within required tulerance and that the basis of acceptance is documented and authorized by respcnsible management. The management authorized to perform this function is identified. 12.7 Calibrating standards have greater accuracy than standards being X X X X ca l i b ra ted. Calibrating standards with the same accuracy may be used it it can be shown to be adequate for the requirements and the basis of acceptance is documented and authorized by responsible

management. The management authorized to perform this function is identified.

12.8 Reference and transfer standards are traceable to nationally X X X X recognized standards; where national standa rds do not exi st, provisions are established to document the basis for calibration. 12.9 Measures are taken and documented to determine the validity of. X previous inspections performed and the acceptability of items inspected or tested since the last calibration when measuring and test equipment is found to be out of calibration. Inspections or tests are repeated on items determined to be suspect. Activities acceptable if: related to Control of Measurino and Test Eauipment ( 17.2.12) a re

1. The criteria in 17.1.12 a re sa ti sfied. X X X Activities related to Handlina. Sto ra ce . a nd Sh i pp i na ( 17.1.13 ) a re acceptable if:

3.1.d Although ANSI N45.2.2-1972 is entitled " Packaging, Shipping, RG.1.38 X X X Receiving, S to ra ge, and Handlin items for Nuclear Power Plants During the Construction Phase,"gthe of requi rements included in the standard are considered to be applicable during the operation phase and should be used, where applicable, consistent with the recommendations of this regulatory guide.

Editorial changes.

Page 62 1 Min li Min GUIDELINE Re f. 1 Max 11 Max Ill Max ill Min 13.1 Special handling, p re se rva t i on, storage, cleaning, packaging, and X X X shipping requi rements a re established and accomplished by suitably t ra i ned individuals in accordance with predetermined work and inspection instructions.

13.2 Procedures are established to control the cleaning, X X X handling, s to ra g e , packagirg, and shipping of materials, components, 4

and systems in accordance with design and procurement requ i rement s to preclude damage, loss, or deterioration by environmental conditions such as temperature or humidity. 3.9 Marking To maintain proper identification and instructions or both ANSI X X during shipping, receiving and storage, and to provide for N45.2.2 identification af ter the outside of the container has~ been removed, the item and ' the outside of. conta iners sha ll be marked. 13.3 The control of handl6ng, storage, and shipping SRP review note listed above satisfies the regulatory position in Regulatory Guide 1.38. Activities related to Handlina. Storaqe. and Shloping (17.2.13) a re acceptable if: o

1. The criteria in 17.1.13 a re sati sfied. X X X
2. Provisions are established for the storage of chemicals, reagents X X X (including control of shelf life), lubricants, and other consumable ma teria l s.
Editorial changes.

O

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Page 63 i Min Il Min GUIDELINE Re f. I Max 11 Max Ill Max Ill Min Activities related to inspection. Test. and Operatina Status (17.1.14) a re acceptable if: 14.1 Procedures are established to indicate the inspection, test, and X X X operating status of structures, systems, and components throughout fabrication, installation, and test.

14.2 Procedures are established to control the application X X X and removal of inspection and welding stamps and status indicators such as tags, ma rkings, labels, and stamps.
14.3 Procedures are established to control altering the X X X sequence of requi red tests, inspections, and other operations important to safety. Such actions should be subject to the same controls as the original review and approva l .

14.4 The status of nonconforming, inoperative, or malfunctioning X X X structures, systems, and components is documented and identified o to prevent inadvertent use. The organization responsible for this function is identified. 5.4 Status Indicating System I A system or method for identifying the status of items (e.g., ANSI X X an inventory system, tagging, labeling, color code) shall be N45.2.2 employed that clearly indicates whether items are acceptable or unacceptable for installation. A controlled physical sepa ra t i on is an acceptable equivalent method. The system shall indicate the date the item was placed in the acceptable or unacceptable installation status. The use of the system shall be regula ted by the Qua li ty Control p rog ra m. The system shall provide for the conditional release of items for installation pending subsequcnt correction of the nonconformance. When tags are used the stock shall be made f rom materia l which will not deteriorate during storage; tags shall be securely af fixed to the items and displayed in an a rea tha t is readily accessible. The stock used shall not be {, deleterious to the item.

Ed i to ri a l changes.

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e e o e Page 63 i Min ll Min i GulDELINE Ref. I Max 11 Max til Max ill Min l

5.5 Correction of Nonconformances items designated nonconforming or unacceptable for installation ANSI X X or use shall be enrrected using authorized to meet N45.2.2 specified requirements, or accepted "As is" procedures,

                                                                       ,  if this is not possible, the item shall be scrapped or otherwise disca rded.

5.5.1 Reinspection -- Items that have been corrected shall be ANSI X X reinspected. The area or inspection may be confined to N45.2.2 the a rea of the nonconformance. When it has been determined that the corrected item is satisfactory, the status of the item as denoted by the system shall be changed to acceptable. An appropriate entry shall be made in the documentation af ter acceptance is determined. 15.5 Nonconformance reports are periodically analyzed by the QA X X l organization to show quality trends, and the significant results are reported to upper management for review and assessment. h Activities related to Nonconformina Materials. Pa rts. or Components (17.2.15) are acceptable if: l

X X X l

1. The criteria in 17.1.15 a re satisfied. l t

! Activities related to Corrective Action (17.1.16) are acceptable if:

16.1 Procedures a re established indicating an X X X errective corrective action program has been establisheo. The QA organization reviews and documents Concurrence with the p rocedu re s.

16.2 Corrective action is documented and initiated rollowing the X X X determination of a condition adverse to quality (such as a noncon fo rma nce, railure, malfunction, deficiency, deviation, and defective material and equipment) to preclude recurrence. The QA organization is involved in the documented concurrence of the adequacy or the corrective action.

Editorial changes. ,

l

s Page 66 1 Min il Min GUIDELINE Ref. 1 Max ll Max lli Maw Ill Min 16.3 Followup action is taken by the QA organization to verify proper X X X** implementation of corrective action and to close out the corrective action in a timely manner. i 16.4 Significant conditions adverse to quality, the cause of the X X X l conditions, and the corrective action taken to preclude l repetition are documented and reported to immediate management I and upper levels of management for review and assessment. ! Activities related to Corrective ActI2D (17.2.16) a re acceptable if:

1. The criteria in 17.1.16 a re satisfied. X X X Activities related to Quality Assurance Records (17.1.17) are acceptable if:
17.1 The scope of the records program is established. QA records X X X X include results of reviews, inspections, tests, audits, and material analyses; monitoring of work performance; qualifica-tion of personnel, procedures, and equipment; and other documents, calibration procedures and reports; nonconformance reports; and corrective action reports.

18. Requirements and responsibilities for record transmittal, ANSI X X retention, and maintenance subsequent to completion of work N45.2 shall be established and documented consistent with applicable codes, standards, and procurement documents.

4.4 Status Each receipt control system shall be structured to permit a ANSI X X current and accurate assessment of the status of quality N45.2.9 assurance records during the receiving process.

18. In genera l, records which correctly identify the as-built ANSI X X conditions of items in the nuclear facility shall be N45.2 maintained for the life of the particular item while it is installed in the nuclear facility and stored for future use by or for the owner. These records should include material certification and test data for traceability and quality verification; reports of inspections,

Ed i to ria l changes.

                 **   Delete "by the QA organization"

o e O

Page 62 1 Min 11 Min GUIDELINE Ref. I Max 11 Max ill Max ill Min examinations, and test results for conformance verification; drawings; speci fica t ions, procedures, and instruction for use in control of cotifiguration; and records of nonconformances and their resolution. These records shall be indexed, filed, and maintained in facilities that provide suitable environment to minimize deterioration or damage and prevent loss.

2.1 Records System A quality assurance records system shall be established by ANSI X X the organization responsible at the earliest practicable, N45.2.9 time consistent with the schedule for accomplishing work activities and in compliance with the general requi rements of thi s standa rd. 5.2.12 Plants Records Management Provisions shall be made for preparation and ANS 3.2 X X X retention of plant reco rd s. The responsibility for maintaining records and storing them at a specified location or locations shall be assigned. Retention periods of sufficient duration to assure the ability to reconstruct significant events and satisfy any statutory requirements for Nuclear Power Plants, NQA-1 [2], shall be used for management of plant records during the operational phase. 2.2 Categories Two categories of quality assuance records are established-- ANSI X X life-time and nonpermanent. N45.2.9 2.2.1 Li fetime Qua lity Assurance Records. Lifetime records X X are those which meet one or more of the following c ri te ria : 1 Those wh'ch would be of significant value in X X demonstrating capability for safe operation.

2. Those which would be of significant value in main- X X talning, reworking, repairing, replacing, or modir/ing the item.

in - M X l l I nx i a MM 1l X X 1l i nx ia MM X X X X X X 11 1 x a X X X X X X M 1 3 6 . e g - 9 9 a . P f e I2 I2 R S5 S5 e N4 N4 AN AN t n d f : n e g e o e o n n ,g n e n l i t ag i gn ga r chi n b t e n mn t ni n o nta o a c bfa ri a iy if f eit i c n u r o o ol p ew po r nf ino dwe t i t ii a i r a l nf f te nl s ad mn t ve t p il fe ol n to ro a ece nn p a a dih No o inm ei d nb oe a . em t el t f m tt wa pm y u a r e ar ec e odt se e t l r d ien .e d mo dn n hro el r i ao uhi sh u i son rp e l v e qt dt n n, nf l c m h a t n e d r i ig il e ocd ri w . u tn i rre of . n a s tae i t q ne l ol co en ei em a e ed g s ad e efl e uo uc u b dnn hn n e o ici s r a Rl li l a l r ei ta i t t c a art l at al ao e r t w . ifc b es ea va vp vt d idu dn o . r e n a snn c r e i ueb no l n o s r oi n d dwi nt te tr tn v qm ai l o gn e ro ae np n, ne o. ers t o i n e t i a r o s re ao a ad rn rot di f t o v a s i cti um c cg ci po fn. en a i d c f u en s ie in ic i erem e v t a i fo q rat sh ff fi fc tt reme ii ff h r c f o es e e.n r c ep li e. Ac yh i ia ns g ir ni ga i a n oc apet nep ssi ri ie td n t n b e e s s p n i s o n t bu eo nel e tw ir ip ign a os daue n i e E a di ahis i sof se r s dn r w qh dhee. i a o i t d urthu dc it f o et f we uo lase its t i i N l vc o o oo h i cyr d n o e d I ue oe sr ny n, n ce et f err o h n r L oh rp somr Qh t g. e ic rieo roo c e t o e . E wt ps afeu t fi fnm fs hi vl afc p c d D I hg . hi n yriu tt t ne ol i oie ou kt a wvr tibe ntaf sdr d e s y f t o ot o r U cnm c f er eb eri ec. ee ecci ne r c G iie ie ito r na: sa so s m ss nail ohA o e s e hnt hc l yar a a op owe oee o- a l isQ c h t d r wii wi abl o msi ha heh hht hn mnpe ti e t l e m v u uf rdr Tc Trt Tti Ti r a ph al o r u t a ern er qd c ere e at zbt f s a t _ sea se eid pot pt ia t o e l a ot os ente nci naer ntd s r e d hef hn mirr oer . . . . ohho ase e n r . Tdo Ti iaao Nrc 1 2 3 4 Nttf get t o d r _ ttpt r a i n n o _ en s oel d t a oi fie re n p r

                .        . iahr                                                                       rar a i              e     t      o 3        4        Lmto                                                                       e               r t         a    t 2                                                         hss n c a m c                                .

o s d r e 2 tee oii tt it d e e f o p s 2 dii c h n n . nl v e pA T aii I I s e _ bt s g _ Aic n . . . . n - Qsa I a b c d a h - c - 2 3 _ l 7 7 a _ . 1 1 i r o t i d E

                                                                          ;    ,l

i Page 62 l I Min 11 Min GUIDELINE Ref. I Max il Max ill Max ill Min

e. Evidence as to the acceptability of the results.

f. Action taken to resolve any discrepancies noted.

17.4 Suitable facil'ities for the storage or records are established and X X satisfy the regulatory position given in Regulatory Guide 1.88 (endorses N45.2.9). Alternatives to the fire protection rated provisions are acceptable if records storage facilities conform to NFPA No. 232 Class 1 for permanent-type records and that the 2-hour f i re ra t i ng requi rement conta ined in the proposed N45.2.9 standard is met by applicants in any one of the rollowing three ways. Specifically, (1) a 2-hour vault meeting NFPA No. 232; (2) 2-hour rated file containers meeting NFPA No. 232 (Class B); or (3) a 2-hour rated fi re resistant file room meeting NFPA No. 232 if the following additional provisions are provided.

1. Ea rly wa rning fi re detection and automa tic fi re suppression X X should be provided, with electronic supervision at a constantly attended central station.

2. Records should be st ired in fully enciosed metal cabinets. X X Records should not be permitted on open steel shelving. No storage or records s! ould be permitted on the floor or the facility. Adequate access and aisle ways should be maintained at all times throughout the racility.

3. Work not directly associated with records storage or retrieval X X should be prohibited within the records storage racility.

Examples or such prohibited activities include but are not limited to: records reporduction, film developing, and fabrication or microfiche cards.

4. Smoking and eating / drinking should be prohibited throughout the X X reco rd s sto rage rac i l i ty.

5. ventilation, temperature, and humidity control equipment should X X be protected iaside with standa rd fi re-door dampers where they penetrate fire barriers bounding the storage racility.

17.5 The description of the control of records provisions listed above SRP review note sa t i si res the regula to ry. posi tion of Regulato ry Guide 1.88. Activities related to Quality Assurance Records (17.2.17) a re acceptable ir:

1. The criteria in 17.1.17 a re sa t i sfied. X X X

2. QA records include operating logs, maintenance and modification X X X procedures, and related inspection results, reportable occurrences, and other records required by Technical Specifications.

Ed i to ri a l changes.

i Page 20 i Min 11 Min GUIDELINE Ref. I Max 18 Max lit Max Ill Min Act iv i t ies rea l ted to Aur J Jas ( 17.1.18) a re acceptable i f: 18A1. Audits to assure that procedures and activities comply with the X X X ove ra l l QA prog ram a re performed by;

a. The QA organization to provide a comprehensive independent X X X*

veri fication and eva luation of qua li ty-related procedures and activities.

b. The applicant (and principal cont rac to rs ) to verify and X X X evaluate the QA programs, procedures, and activities of suppliers.

18A2. An audit plan i s prepa red identi fying audits to be performed, their X X X frequencies, and schedules. Audits should be regula rly scheduled based upon the status and safety importance of the activities being performed and a re initiated early enough to assure effective QA during design, procurement, manufacturing, construct ion, installation, inspection, and testing. 4.5 1he qua li ty assurance organization sha l l ensure that audits are ANS 3.2 X X X performed in accordance with the quality assurance program requirements. Audits of selected aspects of operational phase activities shall be performed with a f requency commensurate wi th thei r safety significance and in such a manner as to assure that an audit of all functions important to safety is completed wi thin a period of two yea rs. As a minimum, the a ud i t p rog ram sha l l provide for audit of the following elements at the increased f requencies given below: (1) The results of actions taken to correct deficiencies that ANS 3.2 X X affect nuclear safety and occur in facility equipment, structures, sys te.as, or method of opera tion--a t least once per six months. (2) The conformance of facility operation to provisions ANS 3.2 X X contained within the Technical Specifications and applicable license conditions--at least once per 12 months. (3) The performance, tra ining, and qua l i fica tions of the ANS 3.2 X X facility staff- t least once per 12 months.

Delete "The QA..." and insert "An appropriate. . " fo r l i min./Ill max.

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Page 12 1 Min Il Min GUIDrlINE Rer. 1 Max il Max ill Max ill Min should be conducted of the i nc rea sed requirements, thus starting H.G.1.144 a new trienrical period, i f, at the time of the pre-award survey, the supplier is a l ready implementing the same quality assurance program for other customers that he proposes to use on the auditing pa rty's cont ract, then the pre-award survey, if it was conducted in accordance wi us Section 4 of ANSI /ASME N34.2.12-1977, may serve as t the first triennial audit. Therefore, when such pre-awa rd surveys a re employed as the fi rst triennial audits, those surveys should satisfy the same audit elements and criteria used on other triennial audits. A documented evaluation of the supplier should be performed R.G.I.144 X X* annually. Whe re appl icable, this evaluation should take into account (1) review or supplier-f urnished documents such as certificates or conformance, nonconformance notices, and corrective act ions, (2) results of previous source verifications, audits, and receiving inspections, (3) operating experience or identical or similar products furnished by the same supplier, and (4) resul ts or audits f rom other sources, e.g., customer, ASME, or NRC audits. ] 3.$.3 Regularly scheduled audits should be supplemented by ANSI X X* , audits for one or more or the following conditions: N45.2.12 1 3.5.3.1 When it is necessary to assess the capability X X* of a contractor's quality assurance program prior to awa rd i ng a con t rac t o r pu rcha se o rde r. 3.5.3.2 When, af ter awa rd of a contract, sufficient X X* time has elapsed for implementing the quality

                                                               - assurance program and it is appropriate to determine that the organiza tion is adequately performing the functions as defined in the quality assurance program description, codes, standa rds, and other contract documents.

3.5.3.3 When significant changes are made in functional X X* areas of the quality assurance program such as significant reorganization or procedure revisions. 3.5.3.4 When it is suspected that the quality of the X X* item is in jeopardy due to deficiencies in the quality assurance prog ram.

Applies to i min. Only.

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Page 23 i Min 11 Min GUIDELINE Ref. I Max ll Max Ill Max ill Min

c. Indoctrination and training programs. X X. X

d. Interface control among the applicant and the principal X X X contractors,

e. Corrective action, calibration, and nonconformance contros X X X systems,

f. SAR and SSAR commitments. X X X

g. Activities associated with computer codes. X X X 1881. Audit data are analyzed by the QA organization and the organization X X X and the resulting reports indicating any quality-problems and the ef fectiveness of the QA program, including the need for reaudit of deficient a reas, a re reported to management for review and assess-ment.

, 4.5 Periodic review of the audit program shall be performed by the ANS 3.2 X X X independent review body or by a management representative at least semiannually to assure that audits are being accomplished in accordance with requirements of technical specifications and of this Standard. 1882. Aud i ts a re pe rfo rmed in accordance with pre-established written X X X procedures or checklists and conducted by trained personnel having no di rect responsibilities in the areas being audited. 4.1 Organiza t iona l Responsibility Tra ining of audi tors sha ll be the responsibility of the ANSI X X employer. N45.2.23 4.5 Those performing the audits may be members of the audited ANS 3.2 X X X - organization; however, they'shall not audit activities for wh i ch t hey ha ve i mmed i a te re spons i b i l i ty. While perro: ming the. audit, they shall not report to a management representative who has' immediate responsibility for the activity being audited. Appropriate and timely followup action, including reaudit of deficient areas, shall be taken, s S &

                                        '       '                                                                 o          6
                                                                                                                     . Page 12 I Min il Min GUIDELINE                                                   Ref.        I Max il Max lil' Max Ill Min 5.3    Pe rsonne l Records Records shall include documenta ry evidence of the                                         ANSI                  X qualification and training of auditors and shall be                                        N45.2.12' retrained for the same period of time as required for the audit report with which. the auditors are assnciated.

1883. The description of the conduct of audit provisions SRP review note satisfies the regulatory position in Regulatory Guides 1.144 and 1.46. Activities related to Aitjits (17.2.18) are acceptable if: X X X

1. The criteria in 17.1.18 a re sa ti sfied.

Where the "onsite" QA organization does not report to the X X X 2.

                "offsite" organization:

The "offsite" QA organization conducts audits sufficient to X X X a. verify adequacy of activities conducted by the "onsite" QA o rgan i za t ion, The "of fsite" QA organization reviews and concurs in the X X X b. schedule and scope of audits performed by the "onsite" QA ' + o rga n i za t i on. X X X

c. Results of audits pctrormed b a re provided to the "offsite"y QA theorganization "onsite" QA for organization review and assessment.

Editorial changes.

l e O l IDENTIFICATION AND QA RANKING OF NUCLEAR PLANT STRUCTURES, SYSTEMS, AND COMPONENTS i l

r O

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l ) . i IDENTIFICATION AND QA RANKING OF NUCLEAR PLANT STRUCTURES, SYSTEMS, AND COMPONENTS j The structures, systems, and components that comprise BWR, PWR, and GCd type reacto s have been listed under 13 separate groups such as Structures, Engineered Safety Features, Electrical Power, etc. The groups are' common to all lists. The breakdown within the groups becomes specific to the type of plant (BWR, PWR, or GCR). The items have been generally specified to a the system level of detail with any further breakdown being done only for clarification. O A model Safety Analysis Report (SAR), and the Standard Review Plan (SRP) for Light Water Reactors were used for generation of the BWR and PWR lists. The FSAR .or the Fort St. Vrain Reactor was used for the GCR list. Various regulations and regulatory guides were also used. For each item listed that is considered important to safety, a quality assurance level (QAL) of I, II, and III was assigned. Those items not considered important to safety were assigned NITS (Not Important To Safety). The definitions for these four categories are given in the attached notes. The further A, B, C breakdown within a level is for assistance in clarifying the level boundaries an$ to a degree giving the reason why an item was categorized as it was. It should be noted that the A, B, C breakdown is not by declining importance. It is not intended that within a level, A is more important than B, and B more important than C. For whatever reason an item is assigned a level, QAL-I A, B, or C is still a QAL-I item, for example. If an item is mentioned in the SRP, it is considered to be important to

safety. Each item listed that is in the SRP has the SRP section(s) listed also. The items in the list that have a blank in the SRP section column are those items not rpecifically mentioned in the SRP.

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                                                               -[9
                        - x-- -- ----                                _

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

Notes for Ranking Lists

1. The QA level of piping, supports, instrumentation (including annunciators and alarms) and controls, electrical distribution equipment, computer software and hardware, and associated consumables and procedures, shall be at least the same QA level as the structure, system, or compor.ent of which they are a part except that where two different QA level structures, systems, or components interface, the !

QA level of the support located at the boundary or the next support l located in the lower QA level structure, system, or component shall be the higher of the two QA levels involved. '

2. The interface between connected QAL-I and lesser QAL fluid systems shall be two closed valves or two valves capable of automatic closure and shall be categorized as QAL-I.

3. The QA level in some cases is dependent on location and, therefore, may be different than listed if a failure could initiate a transient or cause damage to a QAL-I structure, system, or component.

4. Included with each system are the fuels, chemicals, and materials that are procured over the lifetime of the plant for use in these systems.

5. If the SRP section is not given on the list, the SRP does not specifically call out that structure, system, or component.

6. Equipment used for measurement and testing, calibration, and ,

in-service inspection shall comply with the same or higher QAL listed , for the structure, system, or component that they are used on. 4

7. The data (such as geography, demography, meteorology, hydrology, geology, and seismology) obtained for site selection and design of structures, systems, and components shall be obtained with equipment having the same or higher QAL than listed for the structure, system, or component that they are used for. The data shall be controlled in accordance with that QAL also.

80

l

8. Structures are given the same QAL as the systems within the structure and may differ from this listing because of location differences for specific plants.

9. The listings provide guidance, generally, and are not intended to include detailed listings of hardware. The level specified can be deviated from for specific parts of a system or component if justified, s

10. Items have been considered important to safety even if their function during plant operation isn't important to safety if verification is needed during the design and construction phases or subsequent modification. The verification is needed to assure that the item isn't located by or connected to other items in such a way that safety can be affected.

The quality assurance levels (QAL) I, II, and III contain those structures, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public. QAL-I, Quality Assurance level I QAL-1 contains those structures, systems, and components required to assure: A. The integrity of the reactor coolant pressure boundary, B. The capability to shut down the reactor and maintain it in a safe shutdown condition, and C. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guidelines of 10 CFR 100. 81

QAL-II, Quality _ Assurance _ Level II QAL-II contains those structures, systems, and components not included in QAL-I that affect the health and safety of the public in a direct or ;

,  indirect manner:

t $ A. If their failure initiates a transient that requires measures to terminate other than those associated with normal operations, t , B. By serving as a potential backup for cooling or energy for a . l QAL-I system or component, or

1 C. By preventing long-term deterioration of the reactor coolant pressure boundary.

QAL-III, Quality Assurance Level III QAL-III contains those structures, systems, and components not included in QAL-I, or QAL-II. j ! Those structures, systems, and components that are categorized as "Not Important to Safety (NITS)" are those whose failure does not directly or indirectly pose an undue radiological risk to the health and safety of the-public. l 4 i l I l 82

DUR sil<tlCIURES/SYST[MS/C0ftPGflLliTS Af40 QA RAllKI!!G Page I OA LEVEL SRP GROUP ST RUCTU R ES/SYS T Ells /CG4P0f!EliT S (DEFINITIOff SECTI0fi SUB PART) Structures Diesel Generator Building 3.8.4 !(B,C) Turbine Building 3.8.4 I(C) Containment Enclosure Building (Reactor Duilding) 3. 8. 4 I(C) Auxiliary Building 3.8.4 I(C) Fuel Storage Building (flew and Used fuel) 3.8.4 I(C) Cooling Water Intake Structure (at ulticiate heat sink) 3.8.4 I(B C) Control Building 3.8.4 I(B.C) Shield Building 3.8.4 I(C) Radwaste Building 3.8.4 III Primary Containment 3.8.1/ 3.8.2/ I(C) 6.2.1 Service Building FLITS Ocmineralized Water Storage Tank NITS C02 Storage I(C) Class IE Electrical Systens,flanholes and Duct Runs 3.8.4 I(B.C) Emergency Response facilities 13.3 III Office building FLITS Gate House 13.6 III

DWR STRUCTURES / SYSTEMS /C0l1PONEt4TS ATID QA RAllKING Page 2 QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS SRP SECTION (DEFINI TION SUB PART) Structures (Cont.) Low Level Onsite Waste Storage 111 Concrete and Internal Structures of Steel or Concrete Containnents, such as: Refueling Pool llalls 3.8.3 !(A,B.C) Polar Crane Supporting Elements Weirwall Drywell Reactor Pedestal Reactor Shield Wall Meteorological Tower 2.3.3 I(C) Reactor Reactor Vessel S. 3.1/ 5. 3. 3 1(A,B.C) Reactor Vessel Internals: Control Rod System 3. 9. 4/ 3. 9. 5 1(A.B C) Core Support Stt uctures 3.9.5 1(B,C) Jet Pump Assemblies 1(c) _. [4oisture Separator (Operational) NITS Moisture Separator (Structural) 1(C) Steam Dryer (Operational) N115 Steam Dryer (Structural) I(C) l SBLC Sparger 1(B) I 1 l ( . AW

z' - .. e ., BWR STRilCTURES/ SYSTEMS / COMP 0HEf4TS AND QA RAliKING page 3 LE EL GROUP STRUCTURES /SYSTEllS/ COMPONENTS SRP SECTION (DEFINITION SUP PART) ! Reactor (Cont.) Feedwater Sparger NITS Incore flux fionttor flousing 3.9.5 I(A) Core Spray lines and Spargers 1(C) fuel Systen 4.2 I(B,C) Reactor Coolant Systen Reactor Recirculation System [ Pressure Boundary and Nonnal Operation (RCS) with ATWS (anticipated transient without scram)] I(A.C) Reactor Recirculation System (Normal Operation without ATWS) NITS Reactor Core Isolation Cooling (RCIC) 5.4.6 I(C) Residual !! cat Removal (RilR) System 5.4.7 I(C) (Shutdown lleat Removal /llead Spray flode) RilR System (ECCS Modes) 5.4.7 I(C) 1 RilR System (Fuel Pool Cooling) 5.4.7 I(C) flain Steam Line Isolation Valve Leatage Contrni Systen 5.4.5/6.7 I(C) Reactor Water Cleanup Systen: 5.4.8 Piping and outernost containment isolation valve 5.1.8 1(A) Other conponents outside containment (pipinq, valves, 5.4.8 II(C) denineralizers) Main Stea.a Line and feedwater Piping Pi is g nn_valumup to and including outermst containment 5. 4. 3/ 5. 4. 9 I(A,C)

UWR SiltutTUl:ES/ SYSTEMS /C0llP0illt4TS Afl0 QA RAfiKillG page 4 QA GROUP ST RUC T11R FS/SYS tells /C0HP0tlEllTS l SRP gggy jg SECTION SUB PART) RCS (Cont.) Main Steam Line and Feedwater Piping (Continued) ItSIV's 5.4.12 I(C) Main Steam Line Flow Restrictors 5.4.4 I(C) Safety / Relief Valves (Pressure Boundary and Function) 5.2.2/5.4.13 I(A)/I(C)

                 .                         Reactor Coolant Pressure Boundary Leakage Control % stem                     5. 2. 5          I(C)

Steam and Power Conversion Main Steam Supply System: Piping downstream of MSIV's up to but not including 10.3 turbine stop valves II(A) i Turbine Stop Valves (Function) 10.2/10.3 II(A) Turbine Stop Valves (Pressure Coundary) 10.2/10.3 II(A) Turbine Control Valves (Function) 10.2/10.3 II(A) Turbine Contrni Valves (Pressure Boundary) 10.2/10.3 II(A) Turbine System: Turbine disk (integrity) II(A) Turbine (Overspeed features) 10.2 li(A) Turbine (Other than overspeed features) 10.2 II(A) Moisture Separators / lleheaters 10.3 ti!TS flain Condenser System (Condenser and flotwell) 10.4.1 II(A)

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( , bur SIRUCTURES/SYSTLMS/C0llPurtEftIS AllD ()A RAfiKlflG page 5 ()A LEVEL GROUP STRUCTilRI.S/SYST Ells /C0HP0tlEllTS SRP SEC110ft (DErlfilTION SUB PART) Steam and Power Main Condenser Evacuation System 10.4.2 II(A) Conversion (Cont.) Turbine Dypass System (Steam Dump) 10.4.4 II(A) Turbine Gland Sealing System (Seals liain Turbine Shaft) 10.4.3 I!! Turbine Gland Sealing System (Seals fifu Turbine Shaft) 10.4.3 .II(D) Extraction Steam System ti!TS Injection Seal Water System (for fu and condensate booster pumps) II(B) P Injection Seal Water System (for heater drain tank pumps) III fleater Drain and Vent Systens III Auxiliary Boiler filTS Circulating llater System 10.4.5 II(C) Condensate Cleanup Systen 10.4.6 II(C) Condensate and feedwater Systens 10.4.7 II(B) Engineered Safety features Primary Containment Isolation System 6.2.4 I(C) Suppression Pool 1(C) Suppression Pool tlateup System illTS Combustible Gas Control System (In-Centainment) 6.2.5 I(C) llydrogen Reccitiner

w.

UWIt STittlCTUl!ES/SYSTIMS/00f1P0flElil5 Artt! QA RA!!KlilG page 6 QA-LEVEL S TRtlCTilRES/SYS T Ells /CG4P0tlE N T S SRP GROUP (DEFINITION ECT ON SUB PART)

Engineered Safety Combustibl Gas Control Systen (Continued) features (tont.) Purge Exhaust 6.2.5 I(C) liydrogen lionitor Energency Core Cooling Systens, such as: liigh Pressure Core Spray 6.3 I(C) Low Pressure Coolant Injection liigh Pressure Coolant Injection ADS Low Pressure Core Spray Containnent Spray Cooling ECCS Discharge 1.ine fill . System tiain Control Roon liabitability System 6.4 I(C) ESF Atmosphere Cleanup Systems: 6.5.1 Standby Gas Treatment System I(C) Containment Spray Systcn (Also used for containment 6.5.2 I(C) heat removal) i In-Containment Recirculation Systems 1(C) Protective Coating Systems (Paint) - Organic Materials '

                                                                                                                                                                       .6.1.2             III                          I

[Inside Containment] ttaterials of Construction: 6.1.1 (Covered The QA Category for the materials of construction Partially) of the structures, systems and ctmponents is the sane category as the structure, systen, and component that they are a part of.

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BWR STRUCIURES/ SYSTEMS /C0ff0NENTS Afl0 QA RAllKIfiG page 8 QA GROUP STRUCTURES /SYSTEllS/ COMP 0flENTS SRP SECTION (DEF M T DN SUB PMT) Auxiliary Water Systems Essential Service Water System 9.2.1 I(B.C) This system is generally QAC I because it serves the following QAC I components: RHR Heat Exchangers Standby Gas Treatment System Room Coolers RCIC Room Coolers Hydrogen Recombiner Coolers RHR Pump Room Coolers LPCS Pump tiotor Bearings LPCS Pump Reca Coolers Diesel Generators Fuel Pool Cooling Heat Exchangers n Closed Cooling Water HX's However, portions of this system that serve only the following types of non-QAC I components may be of lesser quality with proper isolation from the QAC I Components: Water chillets for Drywell Steam Tunnel Air Coolers Radwaste Evaporative Condenser l l g . . -

P- .. . . DWR STRUCTURES /SYSTCMS/COMPONEt4TS Af40 QA RAfiKING Page o LE EL GROUP STRUCTURES /SYSTEftS/C0HP0flENTS SRP SECTION (DEFINITION SUB PART) Auxiliary Water Systems (Cont.) Closed Cooling Uater (CCU) System 9.2.2 This system is generally QAC I because it serves these QAC I components: Recir. Pump Seal Cooler I(A) CRD Pump Coolers 1(B C) Fuel Pool Cooling liX's I(C) Drywell Control Air Compressor I(C) However, portions of this systen that serve only the 9.2.2 following types of non-QAC I components may be of lesser quality with proper isolation from the QAC I components: Waste Disposal System Conm nser RUCU Non-Regenerative HX RWCU Pump Coolers Drywell Coolers Recirc. Pump riotor Coolers Sample Coolers Exciter Air Coolers Generator Ilydr0 gen Gas Coolers Generator Stator and Rectifier Coolers Main Turbine Oil Coolers Condenser flechanical Vacuum Pump Cooler i i I

1 llI N) OT IR L TA E ) ) P _ E IN ) C, ) B C, ) L I B I I C 8 ( B I B O FU I I ( ( ! ( I ( I ES I I 1 1 ! 1 I I D ( e g a P N O PI 3 4 5 6 6 2 3 5 RT SC 2 2 2 2 2 3 3 3 E S 9 9 9 9 9 9 9 9 y se ih t s ms et t n se

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S Y o l C n e e f y r y M S C t a t t ) d yo E / s p s l s s n n rg S 5 1 o m r i r y y o a m T S F 1 o u e O o S S i oe e g e R 0 B P l s yt yn gt t Y S U o e s p r ta t w ea a s T G e e o n e u e ir io tc n y

S C M t t C i r e t l e ld s a i S E U a a b p k a i p it mCe a r R U R T

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cu ah e t Aa m. D l o r S e r e e O T C y m Fl F_ s s Qse T C u i d d r r e a y v r o t n U n c n n C P r e a t k em ee S eer o o R i e o o H F i t t s n g gf hhe C t R C C E R A a i y i ao aa g Tts l T S n W n S S rn rs n F o a o o i d R C d S r t tr tr l d i ( e e a So So p n u W z d t e f f m a q B m i n a H e e a i e l a W td td S t L t a e ae ae n s r e d t sr sr s e y y e l e a ni ni s m b S n b l m eu eu e p d i a l i dq d q c i n U m t i t ne ne o u a C e o h l oR oR r q t C D P C U C( C( P E S

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e. s BUR STRUCTURES /SYSTEftS/C0llP0llEllTS A!!D QA HAflKillG Page _ 11 i QA LEVEL-GROUP SEC Oft (D N 1 ST RUCTURES/S Y ST Ef tS/ COIIP0rlElli s Auxiliary Water Systems (Cont.) Standby Coolant Supply System I(C)

Suppression Pool Cleanup System FLITS Puxiliary Air llandling Systems ' Control Room Ventilation 9.4.1/6.5.1 I(B.C) Spent fuel Pool Area Ventilation Systen 9.4.2 I(C)

Auxiliary and Radwaste Area Ventilation System 9.4.3 Auxiliary Building Ventilation System 9.4.3 I(C)

Radwaste Building Ventilation Systen 9.4.3 III Turbine Building Ventilation System 9.4.4 III ESF Ventilation Systens 9.4.5 I(C) ! Reactor Building Ventilation Systens Containment Ventilating and Cooling System II(B) Containment Pressure Control and Porqe System I(C) Drywell Cooling System II(B) Shield Building Annulus Recirculating Exhaust System I(C) Drywell Purge System I(C) fliscellaneous Auxiliary Systems Fire Protection (Detection and Extinguishment) 9.5.1 f

p,3, 12 IluR STRUCluttES/SYSTillS/ Cot 1Por4[r1TS Afl0 QA RAfniflG QA 1EVEL SRP GROUP STRUCTURES /SYSTEllS/ COMP 0flEHIS SECTION (DEFINIlluti SUR PART)' Hiscellaneous Auxiliary Systems (Cont.) The QA Category for the fire Protection Systems is ' the same category as the structures, systems, and components they protect. __ Compressed Air System 9.3.1 Supply to ADS 9.3.1 I(C) 1 Other Service and Instrument Air 9.3.1 111 Emergency Diesel Enoine (EDE) fuel Oil Storage and Transfer System 9.5.4 I(B,C) EDE Cooling Water System 9.5.5 I(B C) EDE Starting System 9.5.6 I(8,C) 9.S.7 I(B,C) EDE Lubricating System EDE Combustion Air Intake and Exhaust Air System 9.S.8 I(B.C) Ground Water Dewatering Systems 2.4.12 I(8,C) (Required for structural integrity of QAC I structures) - Radiation, Seismic and Meteorological Instrumentation. Coninunications, and Lighting) (RSMCLS Systems Process and Effluent Radiation llonitoring Instrumentation and 11.5 1(C) Sampling Systems e e s .

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13 BUR STRUCTURES / SYSTEMS / COMPONENTS Af4D QA RANKING p,g, L EL GROUP STRUCTURES /SYSTEllS/C(MPONENTS SRP SECTION (DEFINITION SUB PART) RSMCLS (Cont.) Radiation and Airborne Monitoring Instrumentation, such as: 12.3/12.4 III Area Radiation and Airborne Radioactivity Monitoring Fixed Airborne Radioactivity Monitoring Portable Airborne Radioactivity Monitoring Seismic Instrumentation 3.7.4 I(C) Meteorological Instrumentation 2.3.3 I(C) Consnunication Systems 9.5.2 Intraplant Consuunications 9.5.2 Emer9ency Use 9.5.2 I(B.C) Normal Use 9.5.2 III Interplant and/or Offsite Conumanications 9.5.2 Emergency Use 9.5.2 I(B.C) Hormal Use 9.5.2 III Lighting Systems 9.5.3 { Hormal 9.5.3 III Standby 9.5.3 III

Emergency 9.5.3 I(B.C) l l

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BWR STRUCTUi!ES/SYS1 EMS /CGF0f4EllTS AllD QA RAllKIliG Paw u QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS SRP SECTION (DEFINITION SUB PART)

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                                        ;;eactor Coolant System (RCS)

Pressurizer Relief Valves (Pressure Boundary) 5.2.2 I(A) Pressurizer Relief Valves (Function) 5.2.2 II(A) Pressurizer Safety Valves (Pressure Boundary and 5.2.2 I(A) Function) Reactor Coolant Pump (Pressure Boundary) 5.4.1 I(A) Reactor Coolant Pump (Function) 5.4.1 II(B) Reactor Coolant Punp Flywheel Integrity 5.4.1.1 I(A) Steam Generator (SG) 5.4.2 I(A) Pressurizer (Pressure Roundary) 5.4.10 I(A) Pressurizer (RCS Pressure Source) 5.4.10 II(A) Pressurizer Relief Tank System 5.4.11 III RilR (as part of startup/ shutdown) 5.2.2/5.4.7 I(A,B)

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lHR 51RUCTURES/SYSTEt15/C0flP0tlEN1S At1D QA RAliKillG Page S 0 SRP GROUP STRUCTURES / SYSTEMS /COMPONEllTS SECTI0tl (DEFI TION Ste PART) Steam and Power Conversion (Cont.) itain Condenser Evacuation Systen 10.4.2 II(A) Turbine Gland Sealing Systen (fnr main turbine shaf ts and valve 10.4.3 III stems) Turbine Gland Sealing System (for main FU pump turbine shaf ts) 10.4.3 II(B) Turbine Bypass System (Steam Dump) 10.4.4 II(A) Circulating Water System 10.4.S II(B) Condensate Cleanup Systein 10.4.6 II(C ) Condensate and Feedwater Systens (as part of isolation and 10.4.7 I(B.C) auxiliary FW) Condensate and Feedwater Systems (not part of isolation and 10.4.7 II(B) auxiliary FW) FW Secondary Treatment II(C) Injection Water System (for heater drain tank pumps) III Injection Water System (for FW and Condensate Booster Pumps) II(B) SG Clowdown System 10.4.8 II(A.C) Auxiliary FW System 10.4.9 1(B,C) fleater Drains and Vent Systems III Engineered Safety Featiires (ESF) Haterials of Constructions

INR STRUCTURES / SYSTEMS / COMPONENTS APID QA RANKING Page 6 GROUP STRUCTURES / SYSTEMS /COMPONCitTS L SEC ON (DEFINITION SUB PART) ESF (Cont.) The QA category for these materials is the sane Covered par-category as the structure, systeri, or component tially in they are a part of. 6.1.1 Protective Coating Systens (paints) - Organic Materials 6.1.2 III (in contaliment) RHR Spray System (containment heat removal) 6.1.1/6.2.2 I(C) Containment Spray . 6.1.1/6.2.2 I(C) Ice Condenser System 616/6.2.2 I(C) Containment Isolation System 6.2.4 I(C) Combustible Gas Control (in containment), such asi 6.2.5 I(C) r, Containment Gas lionitor System Ilydrogen Recoribiner Ilydrogen Purge Exhaust System ECCS, such as 6.3 1(C) Cold Leg Accumulator System Upper llead Injection System IOIR (Lowhead Injection) Safety Injection System I liigh Head Safety Injection System Main Control Room liabitability Systems 6.4 I(C) l Emergency Gas Treatment System (ECTS) 6.5.1/6.1.1 I(C) l Auxiliary Dullding Gas Treatment System ( ABGTS) 6.5.1 I(C) e_.

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11111 STRUCIURLS/SYSif.flS/C0f1P0lltitTS Atto QA RAllKlflG p3, QA GR0tlP STRUCTURES / SYSTEMS / COMP 0fiElliS SEC 10ft (DEF i 1 ON SilB PART) Fuel Storage and Handling Overhead llandling Equipment 9.1.S I(C) Auxiliary Water Systems Station Service Uater System (Emergency Raw Cooling Water)(ERCW) 9.2.1 l(B C) This systen is generally QAC I because it serves these QAC I types of components; CCW lix Containment Spray lix Emergency Diesel Generators Emergency Makeup for C01 System Control Bldg. A/C System Aux. Bldg. Ventilation Coolers for ESF Equipment - Air Compressors Auxiliary FM (as backup to condensate storage tank) Rl!R lix (during certain flood conditions)

                                                            . Spent fuel Pool lix's (during certain flood conditions) llowever, portions of this system that serve only the following non QAC I types of components may be of lesser quality with proper isolation from the QAC I system; Containment Ventilation Coolers RCP Motor Coolers Control Rod Drive Ventilation Coolers Instrument Room Coolers

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[* * .O e lilR STRt!CiURES/SYSTLt1S/COMPollEIITS Afill 4A IIAtlKlflG page _ 9 SRP thel GROUP STRUCTURES / SYSTEMS / COMP 0t4EllTS SECT 10ft (DEFINITION SUB PART) Auxiliary tlater Systems Reactor Auxiliary Cooling Water System (Component Cooling tlater) 9.2.2 I(B C) (Cont.) (CCll) This system is generally QAC I because it serves these QAC I types of conponents CCll Pump CVCS Centrifugal Charging Pump CVCS Letdown lix CVCS Excess Letdown lix CVCS Seal Water lix - l RHR Punp RilR lix Spent Fuel Pool lix SI Pump l llowever, portions of this system that serve only the following non QAC 1 types of components may be of lesser quality with proper isolation from the QAC I system; RCP Thenaal Barrier CVCS Reciprocating Charging Puop CVCS Gas Stripper and Boric Acid Evaporator Package Sample System Sample lix Sample System llot Sample Chillers Sample System Gross failed fuel Detector Waste Disposal System (1105) llaste Evaporator Package tIDS Auxiliary llaste Evaporator Package

                                                              !!aste Gas Coupressnr

IHit STRUCTURES /SYSTEtts/ COMP 0HEtiTS Attu ilA RMitlNG page 10 SkP 0^ GROUP STRUCTURES / SYSTEMS / COMPONENTS SL CTIOil (DEf!NITION SilnPAR1 Auxiliary Hate *ttems Raw Cooling Water System (Cont.) II(A.8) This system is generally CAC 11 because it serves g these QAC II types of components 4 FU Pump Turbine Oil Hx f Condenser Vacuum Pump Coolers Condensate Booster Pumps Hx Ilowever, portions of the system that serve only the following non QAC 1 or I! types of conrsoents may be of lesser quality with proper isolation from the QAC-II system; Raw Service Water System As Hakeup for Circulating Water System As Makeup for Water Treatment Plarit Honessential A/C Equipment in the Aux. Bldg. Turtine Generator (TG) Stator Hx's TG Hydrogen fix's TG Exciter llX's TG Mein Bus Hx's TG Seal Oil Hx's 11ain Turbine Oil Hx's Turtine EHC Fluid fix's lleater Drain Tank Pump lix's Turbine Bldg. Ventilation Coolers Sample Hx's (in Turbine Bldg.) l l i O

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Auxiliary Water Systems Raw Service Water System- ' (Cont.) (Supplies water for general caintenance and clean- FLITS Ing and fill for liigh Pressure Fire' Protection , Syste:n) Deminerall ed Water Nakeup System 9.2.3 III Potable and Sanitary Water Systems ' 9.2.4 III Ulticate lleat Sink 9.2.5 I(B,C) Condensate Storage Facilities (required for safe shutdown or 9.2.6 I(B,C) accident mitigation) Condensate Storage Facilities (not required for safe shutdown or 9.2.6 II(8) accident mitigation) Process Sampling System The QA category for the components of this system 9.3.2 is the same category as the systems or components ; that they service. l Equipment and Floor Drainage System 9.3.3 III Chemical and Volume Control System (CVCS) (Portions used for RCS 9.3.4 I(A) volume control) CVCS (Portions used for RCP seal water flow) 9.3.4 I(A,C) CVCS (Portions used for chemistry control) 9.3.4 II(C) CVCS (Portions used for ECCS) 9.3.4 I(C) CVCS (Portions used for pressure control in RilR mode) 9.3.4 I(B)

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S. O ~ e PHR STRUCTURES / SYSTEMS / COMPONENTS Attu QA RANKillG page 13 OA SRP GROUP STRUCTURES / SYSTEMS / COMP 0NEllTS SECTION (MFfNfT ON SUB PART) Misc. Auxiliary Systems Groundwater Dewatering Systems (required for structural integrity 2.4.12 1(B,C) of QAC I structures) Compressed Air Systems 9.3.1 Station Control and Service Air System III Auxiliary Control Air System I (B,C) Fire Protection (Detection and Extinguishment) The QA category for the Fire Protection Systens 9.5.1 is the same category as the structure, system or component they protect. Emergency Diesel Engine (EDE) Fuel Oil Storage and Transfer System 9.5.4 1(B,C) EDE Cooling Water System 9.5.5 I(B,C) EDE Starting System 9.5.6 1(B,C) EDE Lubrication System 9.5.7 1(B,C) EDE Combustion Air Intake and Exhaust System 9.5.8 1(0.C) Radiation, Seismic, and Meteorological Instrume - tation, Comunications and Lighting Systens (RSHCLS) Heteorological Instrumentation 2.3.3 1(c) Seismic Instrumentation 3.7.4 1(C)

l let sihutitlRES/SYSIIfla/CorPu!!Li1IS Allti QA ItNIElflG page ,_ 14 SHP -4}A. GROUP S TitVLi llRE S/ S Y ST E MS/ COMPUtti tlT S SECTI0li (DE rli4!IION Still IART) CLS (Cont.) Intraplant Conenications (emergency uses) 9.5.2 I(0,C) Intraplant Cormunications (normal uses) 9.5.2 111 Interplant and/or offsite Convaunications (energency uses) 9.5.2 1(0,C) Interplant and/or offsite Cone;unications (nomal uses) 9.5.2 til

f Lighting Systems (emergency uses) 9.5.3 I(B,C) Lighting Systens (normal uses) 9. 5. 3 - III ! Process and Effluent Radiation Honitoring Instrumentation and 11.5 I(C) Sampling Systets Radiation and Airborne Monitoring Instrumentation such as; 12.3/12.4 III Area Radiation and Airborne Radioactivity flonttorin( Instrumentation Fixed Airborne Radioactivity Honitoring Systems Portable Airborne Radioactivity Monitoring Systems Radwaste Liquid Waste Management Systems 11.2 III Gaseous Waste Management Systens 11.3 III Solid Waste Management Systems 11.4 !!!

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GCR STRUCTURES / SYSTEMS / COMPONENTS AND QA RANKING Page 2 QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS (DEFillI TI0ri SUE PART) Structures (Cont. ) Service Water Cooling Towers I(B,C) Meteorological Tower I(C) Liquid Nitrogen Storaga Tank f(C) Condensate Storage Facilities (Required for safe shutdown or accident I(B C) mitigation) Condensate Storage Facilites (Not required for a safe shutdown or accident II(B) mitigation) CO 2 Storage Tank I(C) LP Gas Tank NITS Service Water Pump House I(B C) Service Water Pump Pit I(B C) Storage Basin Pump Structure I(C) Fire Water Storage Tank I(B,C) Fire Pump Pit I(B C) Fire Pump Houses I(B.C) Acid Tank III Caustic Tank III Ananonia Tank III

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G s ( s i D t S W a P r ry le Wg a l C S c m s S S r r r r r r i r n U u e t ( o o o o o R r t n m n o l e i r T t s e e w r t t t t t t a i f a S S y m t o o a a a a a x f S e s d t l l l l l l u u e R t l y t a u u u u u u A B B C r m d E S u r c c c c c c G o e o h e r r r r r r r p t R r g S n i i i i i i o p s o n e C C C C C c t u y l t i e G a S S o c c v m m m m m m l r e i r m u u u u u u u V e l t l f e a i i i i i i c R r e n f i s e l l l l l l r C o u o e r e t e e e e e le i P C F C R O R S H H H H H l C 9 t n p a l) oS oC P CR ( U r r O R t o om te G-c ct a as ey e RS R I

GCR STRUCTURES /SYSTEftS/C0llPONENTS Afin QA RANKING p3g, _4_ QA LEVEL GROUP STRUCTURES /SYSTEtiS/ COMPONENTS (DEFINITION SUB PART) RCS (Cont. ) Circulator Auxiliary Drive Supply Systen Circulator Brake and Static Seal Steam and Power Conversion Main Steam Supply System including components such as, Superheater Safet.v Valves I(B,C) Reheater Safety Valves Main Steam Electronatic Safety Valves Hot Reheat Steam Line Safety Valves Bypass Flash Tank Safety Valves Desuperheaters Bypass Valves Combined Reheat Valves Preflash Tank Bypass Flash Tank Piping from SG to flain Steam Stop Check Valves

                                                                                                               -Piping from Main Stean Stop Check Valves                     II(A)

Turbine System including components such as Turbine (overspeed features) II(A) Turbine (other than overspeed fe*tures) NITS Turbine Disk (integrity)- II(A)

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GCR STRUCTURES /SYSifMS/CullP0flLNTS Alit) QA RANKING Page 6 QA LEVEL' GROUP STRUCTURES /SYSTEriS/CCMPONENTS (DEFifilTION SUB PART) Steam and Power Conversion (Cont.) Circulating Water System II(B) Circulating Water flakeup System III Gland Seal Steam system NITS Emergency Feedwater System !(8,C) Emergency Condensate System I(B C) Engineered Safety Features (ESF) Reactor Bldg. Ventilation System (Eshaust fans and filters portion) I(C) Steam / Hater Dump System including components such as; I(C) Feedwater Isolation Valves Hat.? Steam Stop Check Valves Steam / Water Danp Valves Primary Coolant lioisture lionitoring System Primary Coolant Pressure Monitoring System Steam / Water Dump Tank Steam Generator feedwater Flow Limiters including components such as; 1(C) Feedwater Ring lleader Trin Valves Econoraizer Tube Inlet Orifice P V Penetration Flow Restriction Devices such as; I(C) Hexagonal !Iold-down Plates Shield Plug Lugs _ _ _ _ . _ _

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t o U R l o P o s n D a e i t n r P t c y o V m b c m o t T T c t e S i e n a e e C n C S d i a S t r f i t t t o U l r e e a ut iet a i o s m t C R e t h n v l b r y e n T i s e o l o p l n a P S t a d S h e r i a s u e o H s l o S R P t V I R R C t n y P R R a m n o S C r y o a i G t t o l t g e e R P a n n f u i e a l r t t P S o o c a r t A l V V t c u R R n a F g C C o e S E e P P C R R S d n a n o i) tC

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GCR STRUCTURES / SYSTEMS / COMPONENTS AtiD QA RANKING Page 8 QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS (DtFINITION S08 PART) (!&C) Cont. Instrument Systems Nuclear Instrumentation (Ileutron tionitoring Systems) I(C) Moisture Monitoring System I(C)

                                                    . Outlet Coolant Temperature 11onitors                           III Analytical Instrumentation, such as:                           III Larbon Honoxide lionitors Moisture Monitors Electrical Power Offsite Power Systems                                                             II(A,B)

A-C Power Systems (Onsite) I(B.C) D-C Power Systems (Onsite) I(B,C) Alternate Cooling flethod Power System II(B) Fuel Storage and Handling New Fuel Storage !!! Spent Fuel Storage I(C) Spent fuel Cooling System I(C) K' J ' '

rg O ~ v GCR STRUCTURES /SYSIEMS/ COMPONENTS AND QA RANKING 9 Page QA LEVEL GROUP STRUC TURES/SVSTE!!S/ COMPONENTS (DEFINITION SUB PART) Fuel Storage and Handling (Cont.) Fuel Handling System I(C) Fuel Handling 11achine Auxiliary Transfer Cask Shielded Isolation Valve Fuel Handling Purge System Overhead Handling Equipment I(C)

 ,                      Auxiliary Water Systems Reactor Plant Cooling Water Provides cooling water for the following reactor plant heat loads:

PCRV Liner Cooling Tubes I(A B.C) 1 Spent Reactor Fuel I(C) l fuel Handling flachine i I(C) fuel Handling Purge System I(C) Purification Cooling Water Systen I(B,C) l Service Water System This system is generally QAC I because it serves the following QAC I components: Reactor Plant Cooling Water llX's I(C) Purification Cooling Water ilX's 1(c) i

l r. GLR SlRUCTURES/ SYSTEMS /C0itPONENTS AkD QA RANKING Page 10 l _ QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS (DEFINITION SUB PART) l Auxiliary Water Systems (Cont.) Instrument Air Compressors I(C) Air Conditioning System Water Chiller Units 1(C) Decay lleat Removal llX's I(C) l l Helium Circulator Auxiliary System I(C) 1 "tandby Diesel Generators

                                                      ,                                                        1(B.C)

However, portions of this system that serve only the following types of non-QAC I components may t.e of lesser quality with proper isolation from the QAC I components: Hydrogen co'olers for turbine-generator set Turbine-generator lube oil coolers and reservoir o flydrogen seal oil coolers Service air compressors Boiler feed pump lube oil coole.s Steam generator tube plugging machine Radioactive gas waste and helium transfer compressors EHC systen coolers III Domestic (potable) Water System Chilled Water System I(B,C)

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CCR STRUCTURES / SYSTEMS /Cui1P0HEhls Af4D QA RANKlHG Page II QA LEVEL GROUP STRUCTURES /SYSTEllS/ COMPONENTS . (DEFINITION SUB PART) Auxiliary Air Hand-ling Systems Reactor Plant Ventilation System (Exhaust Portion) I(C) Reactor Plant Ventilation System (Non-exhaust Portions) II(A) j The non-exhaust portions of this system is generally QAC-II(A) because they provide cooling and/or ventilation to the following areas: Refueling Area

 -                                                                         PCRV Cavity Beneath the PCRV PCRV Support Ring However, portions of this system that serve only the following types of non-QAC-II areas may be of a lesser quality with proper isolation from the QAC-II areas:

Instrument Room Radio Chemistry Lab Counting Room Control Room and Auxiliary Electrical Equipment Room System I(B,C) Turbine Building Service Area S stem (Includes office and administrative NITS areas, locker, and shower areas Turbine Building Operating Area Systen NITS

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DISTRIBUTION FOR BOARD NOTIFICATI' O N 83-13 iD.o.c_umen_t_:Conthilh(50-454/455; 50-483; 50-537; 50-445/446; 50-275/323;

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50-341; 50-437; 50-329/330; 50-528/530; 50-361/362; 50-322; 50-382; 50-358) NRC PDR L PDR l PRC System NSIC AD/L Rdg S. Black T. Novak/M. Stine D. Eisenhut/R. Purple M. Williams H. Denton/E. Case PPAS J. Youngblood A. Schwencer G. Knighton E. Adensam G. Edison S. Burwell D. Hood. M. Licitra H. Rood R. Caruso J. Wilson L. Kintner L. 01shan B. Buckley R. Stark D. Lynch C. Moon R. Vollmer R. Mattson T. Speis H. Thompson j Attorney, OELD E. L. Jordan, IE J. M. Taylor, IE Regional Administrator, Region I Regional Administrator, Region II Regional Administrator, Region III Regional Administrator, Region IV Regional Administrator, Region V~ Resident Inspector W. J. Dircks, EDO (3) E. Christenbury, OELD J. Scinto, OELD (1) A. Bennette, OELD

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ML20071C668

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