Text

Rev 31 to GO-M-7, Southern Nuclear Operating Co,Farley Project Operations QA Policy Manual
	ML20086B276
Person / Time
Site:	Farley
Issue date:	12/23/1991
From:	Mcgowan J, Woodard J; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20086B270	List: ML20086B266; ML20086B276;
References
	GO-M-7, NUDOCS 9507050268
	Download: ML20086B276 (150)
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i A SNC - Farley Project - Operati:ns Go-M-7 Quality Assurance Policy Manual l U(~

Southern Nuclear Operating Company Farley Project '

Operations Quality Assurance Policy Manual GO-M-7 i

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DOCUMENT CONTROL CONTROLLED COPY COPY NO. -

O Rev.31 3887 E se" !!88834e P PDR

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O l SOUIHERN NUCLFAR OPERATING COMPANY POLICY STATEMDff l On OPERATIONS QUALITY ASSURANCE ror me JOSEPH M. FARLEY NUCLEAR PIMff he Southern Nuclear Operating Company uses a comprehensive l Operations Quality Assurance Program to assure safe and reliable operation, and to enhance performance of the rarley Nuclear Plant.

Continuing objectives of the program are: to assure that quality requirements are adequately identified for use; to verify compliance with the identified requirements; to apprise management of developing trends and problems; and to assure that the plant is operated and maintained according to established engineering criteria in keeping with plans approved by management. W e program utilizes guides from l O the U.S. Nuclear Regulatory Commission and is formulated to comply with Title 10, United States Code of Federal Regulativns, Part 50, Appendix B.

i We policies that constitute the program and associated organizational J responsibilities are described in the Operations Quality Assurance Policy Manual. Implementing instructions have been published in administrative i procedures as shown on the Operations Quality Assurance Policy Implementation List. !

l' W e program is managed by the Manager-Safety Audit and Engineering Review reporting to the Vice President. Se Vice President approves the l program content and conducts a continuing review of program effectiveness.

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J. rd - Vice President l l l

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December 23, 1991

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OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A JOSEPH M. FARLEY WCI,rAR FIAN'T chapter MFM A - Page 1 W 3 31 l I

PREFACE J i

1. Manual Control i mis operations Quality Assurance Policy Manual is a controlled document prepared and published by the rarley Project of the Southern' ,

Nuclear Operating Company (SNC). Each copy is numbered and assigned. l to a particular individual. If manuals or portions thereof are ;

reproduced, the copies shall be marked as " uncontrolled copies". :

Such uncontrolled, copies shall w t be used as policy or procedural (

guidance. ;

2. Changes to the Manual {

a. New and revised pages for the manual are issued by the Manager-Safety Audit and Engineering Review in the form of ]

Revision Notice Packages. In addition to new or revised pages, j each package has a new manual Title Page reflecting the new j O revision number and date, a new List of Effective Pages, and a new Approval sheet. Se List of Effective Pages reflects the effective rervision of each page.

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b. A proposed change to the operations Quality Assurance Policy Manual shall be reviewed and evaluated to determine if the change ;

would reduce the effectiveness of the quality assurance program. i mis review and evaluation shall be accomplished and documented i using the " Operations Qumlity Assurance Policy Manual Change Evaluation" (Preface Page 3) which shall be filed with the record copy of manual changes. Se change shall be evaluated by the. ;

person preparing the change, approved by the Manager-Safety Audit and Engineering Review, reviewed by the General Manager-Nuclear ]

Plant, and General Manager-Nuclear Support, reviewed and approved i by the vice President, and reviewed by the NORB (if required). l l If any of the evaluation questions are answered yes, NRC approval i subsequent to NORB review and approval shall be obtained prior to !

incorporation of the change. Comments obtained during reviews by )

the General Manager-Nuclear Plant and General Manager-Nuclear ;

support will be resolved by the Manager-Safety Audit and !

Engineering Review prior to approval of the change by the Vice President. ;

c. When a Revision Notice Package is received, it should be promptly incorporated on a page-by-page basis such that all superseded pages are removed and destroyed. Additionally,'upon receipt of a Revision Notice Package, each manager responsible for the j O accomplishment of quality activities under the purview of this manual shall determine which of his procedures (if any) require change to acccuplish compliance with the Revision Notice Package.

i Any necessary changes shall be initiated within ninety (90) days of receipt of the Revision Notice Package.

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OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A chapter pggg Rev.

31 Page 2 Or 3 O

3. Manual Status Verification Manual Holders will be requested concurrent with each revision and annually thereafter to verify that their copies are couplete and up to date. This is accomplished as follows:

a. Check that the revision number on the Title Page of the manual, the revision number on the List of Effective Pages, and the latest revision indicated on the Approval Sheet are all the same.

b. Within each chapter determine that the revision notation on each page agrees with that on the List of Effective Pages.

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OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A ;

Q c g 73cg m31 p.T OF 3 l r

OPERATICNS QUALITY ASSURANCE POLICY MANUAL CHANGE EVALUATICE Revision No. 31 i

YES NO

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l. Will the scope of.the program be reduced? l

2. Will the independence of the SAER group be reduced?

3. Will the staffing adequacy be reduced i (consider reductions in staff and added -

responsibilities)?

4. Will the reporting requirements be reduced?

5. Will the constituents / requirements (as referenced in the FSAR) of the program j be reduced? i Evaluation conducted By:

Date i

. Approved: -!

MSAER Date j l

Reviewed:

GelP Date Reviewed "

G 935 Date Reviewed and Approved:

VP Date l t.

NORS Review (If required):

. NORB Chairman Date Any questions answered yes for a change naast be explained fully with specific supporting docu entation that justifies the reduction created, j Additionally, if any question is answered yes, the change mist be reviewed and approved by both the NORB and the NRC.

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ASNC - Farley Project - Operations Quality Assurance Policy Manual O

Distribution List Copy Company-Department-Position Latest Holder of Position No. ,

1 i NRC - Farley - Site Resident T. R. Ross 2 ' NRC - Region 2 - U. S. NRC Library S. D. Ebneter 3 SCS - B' ham. - Manager, Quality Services R. E. Patrick 4 SNC - Adm. - Procurement & Contracts - Farley, Mgr. J. A. Ripple 5 SNC - FNP - Authorized Nuclear Inspector C. G. Ward 6 SNC - FNP - FNP Document Contro! Shelf Copy 7 SNC - FNP - Maintenance Mgr. R. M. Coleman 8 SNC - FNP - Nuclear Plant, GM R. D. Hill 9 , SNC - FNP - Operations Mgr. G. P. Crone 10 SNC - FNP - Plant Mod. & Maintenance Sup. Mgr. B. R. Yance 11 SNC - FNP - Plant Operations Assistant GM L. M. Stinson 12 , SNC - FNP - Plant Support Assistant GM C. D. Nesbitt 13 SNC - FNP - Materials Supervisor L. K. Jones 14 , SNC - FNP - Quality Control Supervisor W. G. Ware 15 l SNC - FNP - SAER Site Staff G. S. Waymire 16 I SNC - FNP - SAER Site Staff G. S. Waymire 17 SNC - FNP - SAER Site Staff G. S. Waymire 18 SNC - FNP - SAER Site Supervisor G. S. Waymire 19 SNC - FNP - Chemistry & HP Mgr. C. L. Buck 20 SNC - FNP - Plant Administration Mgr. L. W. Enfinger 21 SNC - FNP - Systems Performance Manager J. J. Thomas 22 SNC - FS - NA - Document Control Shelf Copy 23 SNC - FS - SAER Corporate Staff C. H. Mahan 24 SNC - FS - SAER Corporate Staff D. W. Daughhetee 25 SNC - HS - SAER Manager W. D. Drinkard O

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Page i et 1- l Revision 31 l 1

LIST OF EFFECTIVE PAGES l

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1 Part Page Nos./Rev. Nos.

l Title 1/31 .

Policy Statement 1/(dated 12-23-91)

Preface 1-3/31 Distribution List 1 /31 List of Effective Pages 1/31

' Approval Sheet 1/31 .

Index 1/31 Chapter Page Nos./Rev. Nos.

l 1 1-5/31 2 1-10/31 >

3 1-6/31 4 1-7/31 l 5 1-3/31 i 6 1-4/31 7 1-5/31 ,

8 1-2/31 ;

9 1-3/31 !

10 1-5/31 i 11 1-3/31 ,

12 1-2/31 ;

13 1-3/31 14 1-2/31 i 15 1-3/31 16 1-5/31 17 1-4/31 18 1-7/31 19 1-3/31 i 20 1-3/31 i 21 1-4/31 {

Glossary 1-8/31 l Appendix A 1/31 i Appendix B 1-6/31

Appendix C 1-4/31 l Appendix D 1-3/31 Appendix E 1-6/31 b

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OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A chapter m.v. p.g, anonmmi cm 11 1 nr 1 APPROVAL SHEET For Revision 31 Revision No. Revision Date Submitted Approved

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31 December 23, 1991 .

I. W. McGowan M \J.

b. Woodard L) ger-Safety Audit President

& Engineering Review i

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,n, OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A !

U chapter INDEX Rev. 31 Pa9' 1 OF 1 l

INDEX i

Chapter No. Title 1

1 OPERATICNS QUALITY ASSURANCE PROGRAM 2 ORGANIZATICH j 3 DESICN CHANGE CCtfrROL 4 PROCURDENT DOCUMDfr CONTROL j 5 INSTRUCTIONS, PROCEDURES AND DRAWINGS 6 DOCUMENT CONIROL 7 CCNIBOL OF PURCHASED MATERIAL, EQUIPMDfr, AND SERVICES 8 IDENTIFICATICN AND CONTROL OF MMERIALS, PARTS AND COMPONDirS O 9 CONTROL or SPECIAL PROCESSES 10 INSPECTICH 11 TEST CCNISOL 12 CamOL Or MEASURI!G AND TEST EQUIPMENT 13 HANDLING, $10 RAGE AND SHIPPING 14 INSPECTION, TEST, AND OPERATING STMUS 15 NCNCGGCRMING MMERIALS, PARTS OR COMPONDfrS 16 CORRECTIVE ACTION 17 QUALITY ASSURANCE RECORDS 18 AUDITS 19 TRAINING l 20 CLEANLINESS AND HOUSEKEEPING I

21 INFORMATION SYSTDtS Glossary Appendix A "Q" List q Appendix B Nuclear Operations Review Board Charter b Appendix C Plant Operations Review Conunittee Charter Appendix D Balance of Plant Quality Assurance Program Appendix E Special OQA Program Applications i

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t OPERATIONSQUAUTY ASSURANCE Southem Nuclear Operating Company A JOSEPH'M. FARLEY NUCLEAR PLANT C* 1

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OPERATIONS QUALITY ASSURANCE PROGRAM f 1.1 Purpose- {

We purpose and principle objective of the Operations Quality :

3 Assurance Program (OQAP) is to assure safe operation of the Joseph M. rarley Nuclear Plant (FNP). Se OQhP is established to cceply l with the Southern Nuclear Operating Company Policy Statement on !

Operations Quality Assurance for the Joseph M. Farley Nuclear Plant. l 1.2 Scope he OQAP is structured to encompass all activities affecting the j safety-related functions of systems, structures and components ;

which prevent or mitigate the consequences of postulated accidents !

that could cause undue risk to the health and safety of the public. .;

mese activities include: designing, purchasing, fabricating, '

handling, shipping, storing, cleaning, installing, inspecting,. ;

testing, operating, emergency planning, radiological protection, ;

training, maintaining, repairing, refueling, and'aodifying. A !

complete list of the systems, structures, and ccaponents which have safety-related functions is contained in Appendix (A). The ;

extent of control over activities will be consistent with their !

importance to safety. !

We OQAP is also structured to encompass certain non-safety related activities in'the following areas: fire protection, radiological environmental monitoring, security, and radioactive waste handling and shipping. Se C W neets the QA Program requirements of 10CFR71 i Sub Part H (formerly 10CFR71 Appendix E). Se extent to which the 1 OQAP applies to each of these areas is provided in Appendix E to :

this manual. ;

1.3 References

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a. Title 10, U. S. Code of Federal Regulations, Part 50, Appendix B.

b. Title 10, U. S. Code of Federal Regulations, Part 71, Subpart H

c. Final Safety Analysis Report for Farley Nuclear Plant.

d. Southern Nuclear Operating Company on Operations Quality l Assurance.

e. ANSI-N45.2.10 (1973).

f. NRC Facility Operating License for FNP.

g. Joseph M. Farley Nuclear Plant Construction Quality Assurance Manual. i

h. ANSI N45.2-1971

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OPERATIONS QUALITY ASSU.RANCE Southem Nudear Operating Company A Chapter y Rev.

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1.4 Documentation of the Program he OQAP is documented by the Operations Quality Assurance Policy Manual (OQAPM) and the procedures, instructions, and controls which provide guidance for the performance of all safety related activities.

The OQAPM establishes generalized quality assurance policies and requirements and assigns responsibilities for fulfilling those policies and requirements. The Operations Quality Assurance Policy Implementation List (OQAPIL) is a composite listing of administrative procedures originated by the various SNC-Farley Project organizations l assigned responsibilities in the OQAPM. The procedures describe how the organizations fulfill those requirements for which they are responsible. In support of the procedures on the OQAPIL, each organization is to have the necessary detailed work procedures and i other documents to use in performing and controlling their activities and to document all aspects of compliance with specific OQAPM and l OQAPIL procedure requirements. Sese work procedures and other ;

documents are to provide direction for activities beyond the minimum skills required for the job classification of the person performing the activity. Documentation within the Operations Quality Assurance Program will utilize definitions and terminology provided in the Glossary of this Manual. We Glossary incorporates definitions contained in ANSI-N45.2.10 (1973). ,

1.5 Program Structure The OQAP is structured as described in subsequent paragraphs to do the followings

a. to assure that quality requirements are adequately identified l for use; l

b. to verify compliance with the identified requirements; !

c. to apprise management of developing trends and problems;

d. to assure that the plant is operated and maintained according ,

to established engineering criteria in keeping with plans j approved by management (Appendix D); and 1

e. to assure that personnel are given adequate indoctrination ,

and training. i 1.5.1 Identification of Requirements Quality requirements for WP are identified in the FSAR, Policy Statement, the OQAPM, and the OQAPIL. We primary source document for the quality assurance requirements ,

contained in the OQAPM and OQAPIL is Appendix B to Title 10, )

U.S. Code of rederal Regulations, Part 50 (10 CrR 50). The ,

titles of the first eighteen chapters of the OQAPM generally l correspond to the titles of the eighteen quality assurance !

criteria described in 10 CTR 50 (Appendix B).

OPERATIONS QUAUTY ASSURANCE' Southern Nudear Operating Company A cw 1 a.ir. 3g Page 3 OF 5 These eighteen criteria are considered to be applicable to all safety-related activities. Additionally, detailed .

quality requirements for FNP are contained in codes, '

specifications, and standards made applicable by provisions of the NRC facility operating license.

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l.5.2 verification of compliance t

Formalized verification of compliance will be performed in j two ways: a corporate review group and a plant review group will systematically review designated activities; and a safety Audit and Engineering Review group will conduct a comprehensive review and audit program.

1.5.3 Apprisals to Management !

Management is to be kept informed about quality trends and probless in complying with quality assurance requirements in order that timely action can be taken at the appropriate- '

management level. Apprisals to management are accomplished' .

through frequent reports as described in Chapter 2. ,

O 1.5.4 Accomplishment of Activities l t

P All activities affecting quality are to be accomplished under -

suitably controlled conditions. " Controlled conditions" ;

include the use of appropriate equipment; suitable 4 environmental conditions for accomplishing the activity, ,

such as adequate cleanliness; and assurance that all pre-requisites for the given activity have been satisfied.

Special controls, processes test equipment, tools, and skills are to be used where required to attain the required quality. Where appropriate, quality is~to be verified by inspection and test. ,

,- 1.5.5 Training l 1

Personnel performing activities affecting quality are to be l given adequate indoctrination and training to assure that l they will achieve and maintain suitable proficiency. (See ;

Chapter 19) j i

1.6 Applicability of OQAP to Supporting Organizations The OQAP of SNC-Farley Project is the only cognizant quality l assurance program for safety-related activities performed by ;

Farley Project personnel. Safety-related activities performed l by other persons will either be performed in accordance with O the OQAP of SNC-Farley Project or in accordance with'a quality assurance program of their organizations which is under the purview of the OQAP for the activity being performed. ,

j The principal organizations providing safety-related support for l FNP will be as follows:

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OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A chapter y R*

31 Page 4 or 5 O

a. APC Construction Department This Department may provide functional construction support including that for Major Modifications or Additions (MMA).

An MMA is defined in the Glossary of this manual. Support for an MMA will be performed in accordance with provisions of the applicable Construction Department Quality Assurance program which will be similar to that utilized for design and construction. However, incidental to an MMA, the applicable QA program will be reviewed and accepted by the MSAER. After initial acceptance, the appropriate QA program will be reviewed at least annually as long as such work is being performed.

Other construction support will be performed in accordance with the provisions of the Joseph M. Farley Nuclear Plant Construction Quality Assurance Manual.

b. Southern Cenpany Services, Inc. (SCS)

Southern Coapany Services, Inc. provides certain services to support Farley Nuclear Plant. Safety-related services l ,

(including nuclear fuel activities) by SCS are to be provided j in accordance with a documented SCS Quality Assurance Program which is reviewed and accepted by SNC-Farley Project. Services provided directly within SNC-Farley Project will be under the i purview of SNC-Farley Project's Operations Quality Assurance !

Program.

services provided directly within SNC-Farley Project includes l those involving personnel support and other items as may be designated in the future.

c. Vendors Vendors who manufacture items or perform services for the FNP aust perform their safety-related activities in accordance with a quality assurance program which has been accepted by SNC-Farley l Project as described in Chapter 4. Vendors may also perform their safety-related activities through direct compliance with SNC-Farley Project's documented OQAP in lieu of a separate, vendor documented program that would require approval by SNC-Farley Project.

d. SNC-Technical Services (SNC-TS) l SNC-TS provides certain services to support FNP. Safety-related i services (including nuclear fuel activities) by SNC-TS are to be j provided in accordance with a documented SNC-Support Services i Quality Assurance Program which is reviewed and accepted by SNC-Farley Project.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company 1

~C. JOSEPH M. FARLEY NUCLEAR PLANT Cwe' 1 h 31 Pa9' 5 OF 5

e. SNC-Administrative Services (SNC-AS) l SNC-AS provides certain services to support FNP. Safety-related services by SNC-AS are to be provided in accordance with a documented SNC-Support Services Quality Atsurance Program which is reviewed and accepted by SNC-Farley Project.

1.7 Placing the OQAP in Effect he OQAP became effective upon initial approval of the OQAPM and the OQAPIL. It is also in effect for all aspects of nuclear fuel and associated core components for FNP. Since completion of final turnover, the entire plant is under the cognizance of the OQAP throughout plant operational life.

Following the coupletion of MMU s performed under the cognizance of the applicable APCo Quality Assurance Program (Design and Construction), the affected portions of the plant will be O returned to the cognizance of the OQAP in accordance with a procedure included on the then effective revision of the OQAPIL.

1.8 Program Review he status and adequacy of the OQAP will be reviewed regularly by SNC-Farley Project management as described in Chapter 2. l O

1 OPERATIONS QUAUTY ASSURANCE . Southem Nuclear Operating Company A O JOSEPH M. FARLEY NUCIKAR FIANT chapter 2 Rev.

31 Page 1 OF 10 l

ORGANIZATIG4 2.1 Purpose 1

' mis chapter describes the quality assurance related duties and responsibilities of persons and organizations which perform quality related functions for the operation of Parley Nuclear Plant. '

2.2 Scope

'Ihe principal organizational elements with responsibilities involving l operations quality assurance have functions as follows.

Responsible Executive '

f~ vice President (VP) l Flant Operations '

General Manager-Nuclear Plant (Gt4P) (with staff)

Safety Audit and Engineering Review Manager-Safety Audit and Engineering Review (MSAER) (with staff) !

Supervisor-Safety Audit and Engineering Review (SSAER) (with j staff) .j Off-site Support General Manager-Nuclear Support (G945) (with staff) i Other Support Punctions l

, APCO Construction Department Southern Company Services, Inc. l Southern Nuclear Operating Company (SNC) - Technical and l Administrative Services Review Organizations Nuclear Operations Review Board (NORB)

Plant Operations Review Constittee (PORC) -

'Ihe organizational relationships for operations quality assurance are shown in Figure 2-1. Specific responsibilities are described in subsequent paragraphs.

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OPERATIONS QUALITY ASSURANCE cnapter 2 Rev.

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2.3 References

a. 10 CFR 50, Appendix B, Criterion I

b. ANSI-N45.2 (1971), Section 3

c. ANSI-N18.7 (1972), Sections 3.3 and 6.0

d. Regulatory Guide 1.33 (1972)

e. FNP FSAR Section 17.2.1

f. Title 40, U.S. Code of Federal Regulations 2.4 Executive for Plant Operations and Operations Quality Assurance -

Vice President l We Vice President is responsible for administrative and functional l control of nuclear generation activities in a manner that adheres to provisions of the 002.

W e Vice President is the senior management authority for quality l assurance in the operation of the Farley Nuclear Plant (IHP). He approves the program content of the Operations Quality Assurance Policy Manual (OQAPM) and any subsequent modifications thereto.

He conduct' a continuing review of the program's effectiveness and will initiate any action he deems necessary for improving that effectiveness.

Annually, or more frequently as he deems necessary, he will assess the effectiveness, scope, and implementation of the OQAP.

As basis for his assessment, he will have prepared for his use an analysis of designated historical data from the following:

plant performance reports, NRC audit results, OQAP audit results, Licensee Event Reports, recommendations made by the Nuclear Operations Review Board, and/or other applicable records or reports.

We Vice President will approve Major Modifications or Additions l (MMA) for the plant. In considering a proposed MMA, a review of the proposed fem by the Nuclear Operations Review Board will be utilized.

We Vice President will resolve matters which may be referred to him by the Manager-Safety Audit and Engineering Review concerning reccamendations to stop work or to delay the initiation of work at INP due to alleged failure to meet quality assurance reg.tirements. .

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Southern Nudear Operating Company A OPERATIONS QUALITY ASSURANCE Rev. 31 Page 3 OF M O

chapter 2

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2.5 Plant Operations - General Manager-Nuclear Plant (GNP1 performed d s

@e GMNP is responsible for assuring He reports to the Vice President.

He is responsible i

that for plant activi training, l

on the OQAPIL. dio procurement, handling, storing, cleaning, installing, test ng, logical t tion, operation, maintenance, modification, fueling / refueling, illance fire ra protection, radioactive waste handling andi ities shipping, at FNP.

pro ec emergency planning, on-site environmental monitoring, surve testing, inspection, security, and quality control act vincludes His specific responsibilities involving Quality Assurance

a. Verifying that installed equipment and system requirements.

b.

Developing and maintaining, with the assistance of the Plant Staff, Administrative Procedures on the OQ the OQAPM.

c. Maintaining effective quality control over plant activities.

I Off-Site Support - General Manager-Nuclear Support (GMNS 2.6 rt for plant operation he GMNS is responsible for managing offsite su@he OQAP as set forth in PIL. Corporate and administration the FSAR, OQAPM, ard inthe a manner procedures that conforms listed on thel OQA toigt ent, and support for plant activities such as licensing, emergency p ann n ,

security, design changes, maintenance, data processing managemHe l re procurement are within this area of responsibility.

Vice President.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company d

' Chapter l 2 'Rev. Page 31 4 Or10 2.7 Operations Quality Assurance 2.7.1 Manager-safety Audit & Engineering Review (MSAER) l We MSAER the overall OQAP.is responsible for the content and effectiveness of He is assisted by an SAER staff with duties, responsibilities, on the OQAPIL. and qualifications as described in procedures We person assigned to the position of MSAER i

shall have at least a baccalaureate degree in Engineering . He or relatedoperating experience engineering operations, includin in power plant operatio

experience involving quality assurance. g two years of i

and responsibilities of the MSAER include:Se specific duties

m. Managing the OQAP.

b.

Quality Assurance Policy Manual for FNP. Preparing, mainta c.

Managing SNC rarley Project's Operations Quality Assurance Policy Implementation List, specifically l (1)

Preparing and proceduree onapproving the list. SAER staff administrative (2)

Approving administrative procedures on the list for compliance with quality assurance requirements.

(3)

Insuring that the scope of procedures included on the list is adequately comprehensive to fulfill all operations quality assurance requirements.

(4)

Promulgating, the list. maintaining up to date, and controlling

! d.

Conducting an operations quality assurance program which provides comprehensive, independent verification and evaluation of quality related procedures and activities associated with rarley nuclear Plant.

is to be in accordance with the provisions of Chapter 18We audit program He shall make reconnendations concerning deficient areas .

and verify the effectiveness of corrective actions taken.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A O

.f Chapter g Rev.

31 **8' 3 Or 10 2.5 Plant Operations - General Manager-Nuclear Plant' (GMP) he GMP is responsible for assuring that plant activities are performed i in accordance with the OQAP as set forth in the OQAPM and the procedures on the OQAPIL. He reports to the Vice President. He is responsible for l procurement, handling, storing, cleaning, installing, testing, training, operation, maintenance, modification, fueling / refueling, radiological protection, radioactive waste handling and shipping, fire protection, emergency planning, on-site environmental monitoring, surveillance testing, inspection, security, and quality control activities at FNP. ,

His specific responsibilities involving Quality Assurance include: I

a. Verifying that installed equipment and systems will perform in accordance with design and safety-related requirements.

b. Developing and maintaining, with the assistance of the l Plant Staff, Administrative Procedures on the OQAPIL.

Such procedures are to implement applicable sections of the OQhPM.

c. Maintaining effective quality control over plant activities.

2.6 Off-Site Support - General Manager-Nuclear Support (GWS) ne Gms is responsible for managing offsite support for plant operation and administration in a manner that conforms to the OQAP as set forth in the FSAR, OQhPM, and the procedures listed on the OQAPIL. Corporate support for plant activities such as licensing, emergency planning, security, design changes, maintenance, data processing management, and procurement are within this area of responsibility. He reports to the vice President. l O

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company b chapter Rev. Page 4 OF 10 2 31 2.7 Operations Quality Assurance 2.7.1 Manager-Safety Audit & Engineering Review (MSAER)

We MSAER is responsible for the content and effectiveness of the overall OQAP. He is assisted by an SAER staff with duties, responsibilities, and qualifications as described in procedures on the OQAPIL. We person assigned to the position of MSAER shall have at least a baccalaureate degree in Engineering. He shall also have at least five years of responsible administrative or operating experience in power plant operations or closely related engineering operations, including two years of experience involving quality assurance. he specific duties and responsibilities of the MSAER include:

a. Managing the OQAP.

b. Preparing, maintaining and ccatrolling APCO's Operations Quality Assurance Policy Manual for INP.

c. Managing SNC Farley Project's Operations Quality Assurance l Policy Implementation List, specifically (1) Preparing and approving SAER staff administra.tive procedures on the list.

(2) Approving administrative procedures on the list for compliance with quality assurance requirements.

(3) Insuring that the scope of procedures included on the list is adequately comprehensive to fulfill all operations quality assurance requirements.

(4) Promulgating, maintaining up to date, and controlling the list.

d. Conducting an operations quality assurance program which .

provides comprehensive, independent verification and l evaluation of quality related procedures and activities i associated with Farley Nuclear Plant. We audit program i is to be in accordance with the provisions of Chapter 18. l He shall make recommendations concerning deficient areas 1 and verify the effectiveness of cortective actions taken.

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e. Conducting audits of Supervisor-Safety Audit and Engineering Review activities.

f. Conducting audits of FNP support activities at the l Corporate Headquarters. )

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g. Reporting immediately to the Vice President any l I

deficiency, discrepancy, or problems considered I significant. This does not preclude full liaison ;

with appropriate managers to resolve such matters.

h. Obtaining prompt resolution of disputed. recommendations for stopping plant activities or stopping initiation of plant activities due to noncompliance with quality )

assurance requirements or reporting the circumstances to j to the Vice President for resolution. The MSAER shall l ;

ensure that either the premptness of resolution or the i premptness of his report to the Vice President is O

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l commensurate with the importance of the disputed action to plant safety. In any event, he shall not defer .

reporting an unresolved dispute of this type to the vice President for more than three days after its l !

initiation. ;

i. Reviewing nuclear fuel specifications and the proposals of nuclear fuel fabrication companies with respect to quality assurance requirements.

j. Ensuring the inclusion of applicable quality assurance program requirements on procurement documents, including changes, for safety-related parts, assemblies, materials and services through periodic audits.

k. Reviewing or having reviews conducted for determining i the acceptability of vendor quality. assurance programs.

1. Conducting or having conducted audits of selected vendors l and participating in selected audits of designers and l fabricators of nuclear fuel and associated cesponents.

m. Reviewing and accepting the quality assurance program !

of Southern company Services, Inc. (SCS) to be used in l 1 f

providing safety-related services and auditing those safety-related services provided.

n. Reviewing and accepting the quality assurance program of the SNC-Support Services (Administrative Services .

and Technical Services) to be used in providing safety-related services and auditing those safety-related services provided.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapter Rev. Page 6 Or 10 2 31 !

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o. Ensuring that the SAER Staff, the SSAER, and the SSAER Staff are adequately qualified, trained and knowledgeable in their areas of responsibilities.

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p. Providing OCA orientation for all SNC-Farley Project personnel below the manager level who perform activities l within the scope of the OQAP. !

q. Directing the activities of the SSAER to insure that the l on-site SAER organization functions as described in the OQAPM and in procedures on the OQAPIL.

r. Reviewing the applicable Construction Quality Assurance l program incidental to Major Modifications or Additions (MMA) to determine the adequacy of support provided to INP.

2.7.2 Supervisor-Safety Audit and Engineering Review (SSAER) ne Supervisor-Safety Audit and Engineering Review ($5AER) is responsible for all SAER functions accomplished by plant :

SAER personnel. He reports to the MSAER for functional ,

guidance. He communicates with the GNP on matters '

1 concerning quality assurance. He must be knowledge-able in nuclear plant operation, auditing, and applicable codes and regulations. He is assisted by a staff with duties, responsibilities, and qualifications as described in procedures on the OQAPIL. We specific responsibilities of the SSAER include:

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a. Supervising all assigned plant SAER personnel.

b. Conducting or having conducted by on-site SAER personnel, recurring audits of selected safety-related activities and documentation to assure that objectives of the OQAP are met. Wese are also to include audits of on-site vendor activities to assure compliance with the approved vendor's quality assurance program. j

c. Recommending to the GMNP, or his available representative, that an activity not be initiated if there is evidence of significant inadequacy in compliance with applicable quality assurance standards, procedures, or applicable codes. In the event a resolution is not reached on-site, ,

the SSAER will notify the MSAER who will take the matter for appropriate action.

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OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A 7

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d. Recommending to the GPHP, or his available representative, that an activity be stopped if there is evidence of significant inadequacy in compliance with quality ,

assurance standards, procedures or applicable codes. l In the event a resolution is not promptly reached i on-site, the SSAER is to notify the MSAER who will l take the matter for appropriate action. Such !

issues as this and that in 2.7.2c above are either to be resolved or reported to the vice President l within three days of their initiation. In those l cases, in which a resolution is not promptly I reached on-site, the SSAER and MSAER shall each '

document their respective actions taken, j

e. Filing a written report of any reccomendation made to. 4 stop or delay initiation of an evolution as previously O described. Subsequent to the resolution, the SSAER shall submit a written report of the matter to the MSAER. The report shall include. reference to the i recommendations made and a description of the j resolution. Copies are to be provided to the GWP i and Vice President. l ]

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f. Developing and maintaining procedures and instructions j to be approved by the MSAER for use by plant SAER 1 personnel in the performance of their duties. .l

g. Serving as a non-voting ===har of the Plant Operations Review Committee (PORC).

h. Providing an input to OQAP orientation for all plant personnel below the supervisor level who perform activities within the scope of the OQAP.

i. Supervising a quality assurance training program for plant SAER personnel,

j. Reviewing procedures on the OQAPIL as requested by the MSAER.

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OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A cnapter 2 Rev.

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2.7.3 Auditors Auditors carrying out duties assigned in accordance with provisions of the 00PJ shall have access to the rarley Nuclear Plant, all safety-related activities at Tarley Nuclear Plant, and all aspects of the quality assurance program for the purposes of planning and conducting audits.

Auditors are authorized to make recommendations to the SSAER, or to the MSAER if working under his direction, that an activity not be initiated or be stopped if there is evidence of significant inadequacy in compliance with provisions of the 00p@.

2.7.4 operational Evaluation Teams operational Evaluation Teams, appointed by the Vice President, conduct Operational Evaluations in l accordance with Nuclear Generation Directive NGD-D8.

2.8 other Support runctions 2.8.1 APC Construction Department l Mis APC department provides construction and operational l support in accordance with the Joseph M. Farley Nuclear

Plant Construction Department Quality Assurance Manual which fulfills applicable requirements of the 00p@. For a Major Modification or Addition (PmA) support will be provided under the applicable Construction Quality Assurance program which has been reviewed in accordance with paragraph 1.6.a.

2.8.2 SNC Administrative Services-Procurement - Farley Project l Wis department handles and executes properly approved purchase requisitions for FNP as described in Section 4.4.5.

2.8.3 Southern Nuclear Operating Coapany SNC-Technical Services serves as an agent responsible to i SNC-Farley Project for design, fabrication, procurement, and quality assurance matters involving the following:

a. Nuclear fuel, including its processing and fabrication;

b. Rod control cluster full-length assemblies;

c. Burnable poison rod, assemblies;

OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A !

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d. Primary and secondary source general assemblies, including sources.

e. Vendors of items and services that are to be procured .

for FNP.

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1 SNC-h chnical Services management will regularly review the j status and adequacy of the OQAP relating to the above.

SNC-Technical Services will also provide engineering support for other items as may.be designated by SNC-Farley Project.

1 2.8.4 Southern Company Services, Incorporated (SCS) l SCS provides engineering support for such items as may be designated by SNC-Farley Project and is responsible to SNC-Farley Project for quality assurance matters related to that support.

2.8.5 various vendors for Site Services various vendors provide, fremt time-to-time, site services 1 involving safety-related activities. A vendor's quality I assurance program is considered an integral part of the work contract and therefore its fulfillment will be a vendor management responsibility. Vendors are required to regularly review the status and adequacy of their own quality assurance programs.

2.9 Review Organizations 2.9.1 Nuclear Operations Review Board he Nuclear Operations Review Board (NOBB) conducts independent reviews of safety-related FNP matters to verify compliance with quality assurance requirements.

Se NORB functions as an advisory board reporting to the Vice President. Se Board's charter is contained l in Appendix B.

2.9.2 Plant Operations Review Committee he Plant Operations Review Constittee (PORC) reviews safety-related matters concerning plant operations to insure compliance with quality assurance requirements.

O It functions as an advisory committee reporting to the General Manager-Nuclear Plant. De Commtittee's charter is contained in Appendix C.

b OPERATIONS QUALITY ASSURANCE Southern Nudear Operating CompanyA chapt" 2

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OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A Ch * *' N- F"9' JOSEPH M. FARLEY NUCLEAR FIANT 3 31 1 OF 6 L

DESIGN CONI 140L 3.1 Purpose i me purpose of design control measures is to assure that the applicable regulatory requirements, quality standards, and the design bases for ,

FNP are correctly translated into specifications, drawings, procedures, '

and instructions. Design control measures during the operating life ;

'shall be commensurate with those applied to the original design.

3.2 Scope Design control is to be applied to all design activities involving safety related items listed in Appendix A during the operational lifetime of FNP. ' Design control of nuclear fuel activities during the design and construction phase and all design activities during the operations phase of FNP are within the purview of the OQAP.

O Design activities include those associated with design changes, field changes or modifications. Any variation from the physical design of plant equipment, systems, or structures including alterations, additions, and deletions not covered as temporary

. alterations is considered to be a design change. For purposes of the OQAP, design activities for FNP will be considered to be included in one of the following five categories: (1) nuclear fuel design; (2) design changes; (3) major modifications; (4) minor departures; or (5) computer software design.

3.3 References

a. 10CFR50, Appendix s, criterion III

b. 10CFR50.59

c. FNP FSAR Sections 17.2.3, 17.3

d. ANSI-N45.2 (1971), section 4

e. ANBI-N45.2.ll (1974)

f. ANSI-N18.7.(1972), Paragraph 5.1.6

g. Inc Regulatory Guide 1.64 (Rev. 1, Feb. 1975) 3.4 Responsibilities for Control of Nuclear Fuel Design SNC Technical Services is required to ensure that fuel suppliers l carry out documented design control QA programs which comply with requirements contained in Criterion III of Appendix B to 10CTR50, ANSI-N45.2 and ANSI-N45.2.ll. Properly qualified representatives or agents may be used to assist in such activities. It is the O responsibility of the MSAER to ensure that the programs are reviewed and audited for adequacy and compliance.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A cnacte' 3 h 31 Page 2 or 6 3.5 Responsibilities for Control of Design Changest rield Changes, and Modifications 3.5.1 General cosign changes, field changes, or other modifications (including Major Modifications or Additions) are hereafter referred to as " design changes" and may be initiated as a result of the following: unsatisfactory operational performance as found during test, operations, repair, or maintenance; failure to meet functional requirements; changes in regulatory requirements; operating experience; disposition of nonconforming items; or other efforts to improve a current design. Design control measures apply to all changes within the scope of the OQAP regardless of why or by whom originated.

Any changes to the Technical Specifications (including Technical Specification changes necessitated by design changes) as incorporated in the Operating License must be approved by the NRC prior to entering the plant mode of operation affected by the Technical Specificatim.

Any design change which constitutes an unreviewed safety question as defined in 10CTR50.59 must be approved by the NRC prior to accomplishment.

We selection of suitable materials, parts, equipment, and processes for design changes shall include the use of applicable industry standards and specifications.

Proposed design changes are to be reviewed to ensure:

design characteristics of proposed changes can be controlled, inspected and tested; and that inspection and test criteria are identified for the design change. Design change reviews are also to include consideration of the following: selection of suitable materials; compatibility of materials; maintain-ability; effect on fire protection provisions; and capability for proper functioning of the item under its full range of operating conditions.

W e following are to be accomplished and recorded for each proposed and subsequently approved design change:

a. We need for the design change, field change, or modification.

b. We input requirements (as described in Ref. 3.3.e) for the design change.

c. Determination as to whether the proposed change constitutes an unreviewed safety question by the General Manager-Nuclear Plant and/or Vice President l (with review by the PORC - and if appropriate, the lORB).

d. We approval of the change for accomplishment.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A !

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e. S e accomplishment of the change. '

f. Se accomplishment of portions of the change as may be a licable to spare parts'in storage as well as to 1 se which might have been on order or enroute to the >

plant at the time of the change.

g. Completion of drawing, technical manual, procurement ;

specifications, procedures, and other documentation i changes as applicable. ]

Se following organizational elements have functions and i responsibilities involving design change control: l 3.5.2 General Manager-Nuclear Plant (G WP) i me GesP is responsible for maintaining a design change contrc,1 system which includes the provisions of para 3.5.1 performed on-site. It shall be documented and uded on the OQhPIL as an administrative procedure.

S e Gelp shall ensure that all design changes are properly ;

identified, reviewed, and approved prior to installation. l He will utilize the PORC for reviewing the proposed design !

change to identify any possibly unreviewed safety questions. !

If an unreviewed safety question is identified, the pLoposed ;

design change mast be reviewed by the NOIB.and approved by i the Vice President prior to its being accomplished. l 1 1

If, upon advice of the PORC, the GDIP determines that a proposed design change does not involve an unreviewed safety question, he may approve the change for

, acccuplishment. He shall sutait safety evaluations for changes completed within the scope of 10CFR50.59 to the vice President for NOIS review. l 3.5.3 General Manager-Nuclear Support (Gels)

Se Gets is responsible for having a design change control system, compatible with the FNP design change control system, for design changes processed through the Nuclear Support Department. Bis control system is to be documented and l included on the 00hPIL as an administrative procedure. Se Gets is responsible for any off-site engineering support and technical support required by the GetP for the accomplishment of the items listed in Paragraphs 3.5.1 and 3.5.2 above and for extending the requirements in paragraph 3.5.6 to off-site design organizations. Additionally, the Gets is responsible for accomplishing and recording the return of developed design changes to the Nuclear Support Department from the design organization.

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i OPERATIONS QUAUTY ASSURANCE SOuthem Nudear Operating Company A f chasar 3

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!t 3.5.4 Vice President l If an unreviewed safety question is identified in a proposed design change, it must be reviewed by the NORB and approved i by the Vice President for submittal to the NRC for approval l [

prior to accomplishment.

safety evaluations of design changes completed under the ,

i provisions of 10CFR50.59 shall be reviewed by the NORS and verified by the Vice President that such changes did not l f constitute unreviewed safety questions. :

3.5.5 Manager-safety Audit and Engineering Review (MSAER) )

Se MSAER is responsibile for conducting audits of the !

j design change activities perforund by SNC-Fctley Project- l l

Nuclear Support Department personnel. Se MSAER is also !

l responsible for reviewing and accepting the applicable ;

quality assurance programs of organizations providing !

design services and for auditing these services except .

when such services are provided in accordance with the i 00hP. l 3.5.6 off-site Design organizations l

Off-site design organizations such as Southern Company- !

Services, Bechtel, and Westinghouse provide design ;

services for safety related structures, systems, and i ccuponents. S ese designers are required to maintain. !

documented design control QA programs which comply with ,

requirements contained in Criterion III of Appendix B !

to 10CPR50, ANSI-N45.2, ANSI-N45.2.ll, and applicable i portions of paragraph 3.5.1 above..

3.6 Responsibilities for control of Minor Departures j 3.6.1 General ,

A minor departure is defined as a change of very limited scope and may be classified as temporary or permanent. Se ;

following are examples of changes which might be handled as 1 departures: small change in dimension of a cogonent part; {

substitution of material for a component part; small changes i l in the run of a pipe; or valve leakage in small excess of !

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leakage specifications. No proposed design changes involving unreviewed safety questions are to be handled as minor l

departures. l I

i OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A O/ Chapt

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3.6.2 General Manager-Nuclear Plant (GSTP) !

'Ihe GelP is responsible for having a tem for controlling minor departures if he desires to han such departures :

separate from other design changes as addressed in section 3.5 above. 'Ihe system is to be documented and included in an administrative procedure on the OQAPIL. 1 h following are to be accomplished and recorded for .

each departure l 1

a. h need for the departure. l

b. Detailed description of the departure,

c. Rationale in support of the departure with respect to: I (1) sensitivity of the basic functions of the component j to the departure; and i (2) sensitivity of any other component or plant condition; ;

such as chemistry, radiological protection, or fire i protection; to the departure.

d. A Safety Evaluation reviewed by the PORC and approved by the G9fP which verifies that no unreviewed safety l questions were involved in the departure. !

e. Coupletion of satisfactory design review of the l proposed departure.

'Ihe following are to be included in such review: l l

(1) Review of the detailed description of the departure '

to insure that it fully and correctly defines the departure. .

(2) Review of information in records and doctaments held by SNC-rarley Project concerning the particular l I

aspect of design from which departure is considered. l (3) Review of the impact of the departure with respect to the functions of the component, equipment or systems for which the departure applies and with respect to the function of associated components, equipment and systems.

(4) verification that the departure does not constitute a deviation from design criteria prescribed by codes or regulations to which SNC-rarley Project l has committed.

Cancellation of the departure upon return to original O f.

design or upon approval of a design change in which the design is e mnged to that of the departure.

'Ihe Gt4P shall also insure that only those minor departures from design which are approved in accordance with the procedures above are accomplished.

OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A chaoter 3 %. 31 Page 6 OF 6 g

l 3.6.3 Manager-Safety Audit and Engineering Review (MSAER) me MSAER is responsible-for conducting audits of activities involving minor departures from design. mis is to include activities of the SNC-Farley Project-Nuclear Support Department and those organizations providing design service directly to the SNC-Farley Project.

3.7 Responsibilities for Control of Computer Software Design me General Manager Nuclear Plant (GMP) and the General Manager-Nuclear Support (GPtiS) are responsible for having systems to control Computer Software System Design changes in accordance with the provisions outlined in paragraphs 3.5 and 3.6.

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OPERATIONS'QUAUTY ASSURANCE Southem'Nudear Operating Company A JOSEPH M. FARLEY NUCLEAR P!Rrr cm 4 A 31 Page 1 OF 7 PROCUP2 MENT DOCUMDir CCNTROL 4.1 Purpose This chapter assigns responsibilities for establishing a system for procurement document control which will ensure that applicable regulatory requirements,. design bases, and applicable quality requirements are suitably included or referenced-in procurement documents.-

4.2 Scope Procurement document control measures shall be used for safety-related materials, parts, assemblies, and services purchased during the operational life of FNP by APC, SNC-Farley Project or O by its contractors or subcontractors. Procurement document control measures shall also be used for other items as designated by SNC-l Farley Project management.

4.3 References

a. 10CTR50, Appendix B, Criterion IV

b. ANSI-N45.2 (1971), Section 5

c. ANSI-N45.2.13 (Draft 2, Rev. 4, April 1974)

d. ANSI-N18.2 (1973)

e. FNP FSAR Section 17.2.4

f. Management Procedure 315-001

g. Management Procedure 315-002

h. SNC Support Services Quality Assurance Policy Manual 4.4 Responsibilities 4.4.1 General Applicable regulatory, design and other quality requirements shall be suitably included or referenced in procurement documents. To the extent necessary, such requirements shall include the provision that contractors and subcontractors shall provide for acceptance by SNC-Farley Project a @

Program which will meet the applicable provisions of ANSI-N45.2-1971. Requirements for an acceptable vendor's m program shall be based upon: the complexity of the item's

( design and fabrication; the importance of the failure of the item to plant safety; the need for special controls; the degree to which functional compliance can be demonstrated by inspection and test; and the quality history of the item.

OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A chaptw 4 Rev. 31 Page 2077 O

4.4.2 General Manager-Nuclear Plant (GMNP)

The GNP is responsible for the establishment and use of procedures for preparing, reviewing, approving and con-trolling requisitions or procurement documents and changes thereto that originate at FWP for materials, ccuponents (including spare and renewal parts) and services purchased during the operational life of the FNP, except those ordered as a result of a Major Modification or Addition. We pro-cedures shall be based upon 10CFR50, Appendix B, Criterion IV and ANSI-N45.2.13, (Draft 2, Rev. 4, April 1974) and shall provide for the followings

a. Developing, reviewing, approving and controlling requisitions or procurement documents for requisition-ing material, equipment, and services within the scope of the GWP's responsibility. We review and approval ,

of requisitions or procurement documents shall be documented and available for verification.

b. Ensuring that changes and revisions to procurement documents are subject to at least the same review and approval requirements as the original document.

c. Appropriately classifying each item or service in accordance with applicable procedures.

d. Ensuring the inclusion of the following quality and technical requirements in requisitions or procurement documents where applicables the design bases or reference to the design bases; applicable regulatory requirements; component and material ideritification l

r irements, drawings, specifications, codes, and/or i trial standards; test and inspection requirements; special process instructions; the documentation to be prepared, maintained, and submitted to SNC-Farley Project for review and approval (includes such l

documentation as inspection plans, personnel qualification requirements, and test records); and records which shall be retained, controlled, maintained,

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l or delivered to SNC-Farley Project prior to use or l l

installation of the items.

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e. Selecting appropriate @ Program provisions for parts, assemblies, materials, and services for the EWP. Such provisions shall include requirements that: J (1) ne purchaser may review and/or concur with the vendor's % Program.

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. OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A I Chapter Rey, Pay 4 31 3 OF 7

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(2) he vendor shall impose applicable quality 1 requirements on subtier vendors. I (3) SNC-Farley Project or SNC-Farley Project's Agent has l right of access to supplier's facilities and records for source inspection and audits. Right-of-access shall be afforded the purchaser and/or its agent to verify that the vendor's activities are in compliance l with the approved m provisions. 1 l

(4) ne purchaser shall have control of nonconforming i items as stated in procurement documents. l (5) Records substantiating quality shall be presented to )

the purchaser as required by procurement documents. -

(6) Procurement documents identify the m requirements j applicable to the items or services procured. mis l ma be accomplished in various ways, such as the fo lowing:

1. Invoking ANSI N45.2-1971 by reference, or

11. Invoking applicable elements or sections of I ANSI N45.2-1971, or l iii. Invoking other specific requirements which meet the intent of ANSI N45.2-1971 (such as the ,

vendors quality assurance program description). 1

f. Reviewing requisitions or procurement documents to assure that documents transmitted to the prospective suppliers i for bid or contract purposes include appropriate provisions to assure items or services meet specified requirements. Bis review shall be documented. ;

g. Reviewing and analyzing by a qualified design organization, j any vendor-supplied information requiring analysis. '

h. Evaluating reports of audits, receiving inspections, and nonconformance dispositions to determine the supplier's quality program effectiveness. Results of these evaluations shall be forwarded to SNC Corporate Quality Services for use in reviewing and evaluating supplier performance in accordance with paragraph 7.4.5.

he GPNP shall ensure that requisitions or procurement j O- documents which require vendor-supplied information for l design analyses, like seismic analyses, specify that the ;

information is to be transmitted for review and evaluation i as directed by the General Manager-Nuclear Support. l l

OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A Chapter Rev. Page 4 31 4 OF 7 he GNP shall ensure that the origination and handling of procurement documents are in accordance with SNC Corporate Guidelines.

4.4.3 General Manager-Nuclear Support (GMNS) 4.4.3.1 he GMNS is responsible for the establishment and use of procedures for preparing, reviewing, approving, and controlling requisitions.or procurement documents and changes thereto th t originate in the Nuclear Support section. Se procedures for these activities shall be compatible

! with the FNP procedures required by Paragraph 4.4.2 above and shall be based upon 10CFR50 Appndix s, criterion IV, and ANSI-N45.2.13 (Draft 2,'Rev. 4, April, 1974) and shall provide for the following:

a. Developing, reviewing, approving and controlling requisitions or procurement documents for requisitioning material, equipment, and services within the scope of the GlWS's responsibility.

We review and approval of requisitions or procurement documents shall be documented and ,

available for verification.

b. Ensuring that changes and revisions to procurement documents are subject to at least the same review and approval requirements as the original document.

I_ c. Appropriately classifying each item or service in accordance with applicable procedures,

d. Ensuring the inclusion of the follcwing quality and technical requirements in requisitions or procurement documents where applicable: the design bases or reference to component and material identification requirements, drawings, specifications, codes and/or industrial standards; test and inspection requirements; special process instructions; the source surveillance requirements; the documentation to be prepared, maintained, and submitted to SNC-Farley Project for review and approval l (includes such documentation as inspection plans, personnel qualification requirements, and test records); and records which shall be retained, controlled, maintained, or delivered to SNC-Farley Project prior to use or installation of the items.

e. Selecting appropriate OA Program provisions for parts, assemblies, materials, and services for the FNP. Such provisions shall include requirements that:

e OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A (b% Chapter Rev. Pa" 4 31 5 or 7

1) ne purchaser may review and/or concur with the vendor's % Program.

2) We vendor shall impose applicable quality t requirements on subtier vendors.

3) SNC-rarley Project or SNC-rarley Project's l ,

Agent has right of access to supplier's facilities and records for source inspection and audits. Right-of-access shall be '

afforded the purchaser and/or its agent ,

to verify that the vendor's activities are in compliance with the approved % provisions.

4) Se purchaser shall have control of non-conforming items as stated in procurement documents. )

5) Records substantiating quality shall be presented to the purchaser as required by procurement documents.

O 6) Procurement docusants identify the S V requirements applicable to the items or services procured. Bis may be accomplished in various ways, such as the following:

1. Invoking ANSI N45.2-1971 by reference, or

11. Invoking applicable elements or sections of ANSI N45.2-1971, or iii. Invoking other specific requirements which meet the intent of ANSI N45.2-1971 (such as the vendors quality assurance program description).

f. Reviewing requisitions or procurement documents to assure that documents transmitted to the prospective suppliers for bid or contract purposes include appropriate provisions to assure items or services meet specified requirements. his review shall be documented.

g. Reviewing and analyzing by a qualified design organization, any vendor-supplied information requiring analysis.

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h. Evaluating reports of source surveillances and inspections, audits, waivers, and corrective actions to determine the supplier's qualitir .

program effectiveness. Results of these evaluations shall be forwarded to SNC Corporate Quality services for use in evaluating supplier performance in accordance with paragraph 7.4.5.

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t OPERATIONS QUAUTY' ASSURANCE Southem Nuclear Operating Company A l chaow Rev. Page g gp 7 4 31 t

4.4.3.2 Upon receipt from the GNP, the Gm3 shall handle ;

requisitions for parts, assemblies, and material. >

consistent with SNC Corporate Guidelines. l.

4.4.3.3 The GWS is responsible for the establishment and use of Corporate Headquarters interface -

procedures for reviewing, approving,.and +

processing requisitions or procurement documents that originate at FNP. ,

L4.3.4 The G MS is responsible for controlling and ,

maintaining the Plant Services Approved Suppliers. l List (PSASL) which is the approved bid list for

( FNP services. ,

4.4.4 Manager-Safety Audit and Engineering Review (MSAER) f

a. The MSAER shall audit the review of S programs ;

performed by SNC Corporate Quality Services in response to the m program requirements for items and services i prescribed by FNP. -

b. The MSAER is responsible for periodic auditing of ;

procurement document control activities performed i by the SNC-Farley Project - Nuclear Administration l ;

Department, r

c. The MSAER is responsible for design control quality ;

assurance measures as prescribed in Section 3.5.5 for services involving the design analysis of vendor- ,

supplied information. j

d. The MBAER is responsible for ensuring that appropriate t ity assurance provisions are included in procurement .

ts for nuclear fuel. He shall be responsible for :

reviewing m programs that nuclear-fuel suppliers propose- '

to use in meeting those provisions..

4.4.5 SNC-Administrative Services-Procurement Department l

a. Within the scope of SNC-Farley Project's OQAP, the SNC l l Administrative Services Procurement Department will i execute all purchase orders for FNP in accordance with . j the SNC Support Services Quality Assurance Policy Manual except those handled by the Minor Purchase Order Routine. :

The SNC Administrative Services Procurement Department will execute the purchase orders for the following: [

(1) Requisitions for parts, assemblies, and material i that are reviewed and forwarded by the General Manager-Nuclear Support or the General Manager-Nuclear Plant. j

f^g OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A Chapter Rev. Page 4 31 7 OF 7 (2) Requisitions for vendor services to be performed at the FNP that are reviewed and forwarded by the General Manager-Nuclear Support or the General Manager-Nuclear Plant.

b. The approved bidders list for materials, equipment, and services will be maintained by the SNC Administrative Services Procurement Department.

4.4.6 SNC-Corporate Quality Services l SNC Corporate Quality Services shall be responsible for the l review of vendor m programs. The results of each vendor m program review shall be reflected in the SNC Qualified Suppliers List.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLFAR PIAIC chas* 5 Rer. 31 Page 1 or 3 INSTRUCTIONS, PROCEDURES AND DRAWINGS I

5.1 Purpose mis chapter assigns responsibilities for assuring that safety-related activities are prescribed in documented instructions, procedures, drawings or other guidance which shall include appropriate acceptance criteria for determining that an activity 1 has been satisfactorily performed. mis chapter also assigns responsibility for assuring that prescribed activities are performed in accordance with the documented guidance.

5.2 Scope ;

%ese requirements apply to all safety-related activities within the purview of the 00kP.

5.3 References

a. FNP FSAR Sections 17.2.5, 16.2, and 13.5

b. 10 CFR 50, Appendix B, Criterion V

c. ANSI-N18.7 (1972) Section 5

d. ANSI-N45.2 (1971) Section 6

e. NRC Regulatory Guide No. 1.33 (Safety Guide 33, Nov. 1972)

f. NRC Regulatory Guide 1.68 (Nov. 1973)

g. NRC Facility Operating License for FNP 5.4 Responsibilities 5.4.1 General Guidance for the accomplishment of safety-related activities at the FNP shall be appropriately documented and approved prior to its use and prior to initiation of the activities to which it applies. 21s guidance shall incorporate applicable quality requirements as well as necessary limits and tolerances and appropriate quantitative or qualitative criteria for determining that important activities have been satisfactorily accomplished. For activities of similar nature, the guidance documents should be as consistent as practicable.

Managers as described herein issuing guidance for safety-related activities shall utilize documented systems for preparing, reviewing, approving, controlling, distributing, changing, and determining retention times for their J instructions, procedures and drawings. Sey shall include O provisions for correcting deficiencies. Where applicable, the systems for changing guidance shall provide for both permanent and temporary changes. Managers issuing safety-related guidance shall require that their guidance be adhered te by all persons reporting to them.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapt" Re* Page 5 31 2 0F 3 hey shall specify any provisions for departing from their procedures. Where there is a direct relationship between procedural steps and physical manipulations, administrative guidance is to be provided as to how a procedure is to be used such as whether the procedure is to be used as general guidance or followed step-by-step. mis guidance shall include identification of those procedures required to be in-hand when performing the operation to which they pertain.

Specific sections of vendor manuals may be used or referenced in procedures, however, such sections shall receive the same review and approval as other procedure content. If vendor manuals are referenced in such a way as to constitute portions of procedures, those manuals so used must be identified and controlled. Changes to the identified manuals which affect portions of the manual that have been incorporated into plant .

procedures must be reviewed and approved as changes to the l parent procedures. l 5.4.2 General Manager-Nuclear Plant (Gt4P)

We GelP is responsible for the development, review, and -

approval of procedures and other guidance for the operation of the FNP which will comply with the requirements of the Code of Federal Regulations, ANSI-N18.7, and Regulatory Guide 1.33 Appendix A.

5.4.3 General Manager-Nuclear Support (GtiS) me Ge:S shall insure that adequate documented guidance is provided to his staff concerning safety-related functions ,

which they perform.

We Gets shall establish procedures which provide for the use of. support from outside the Southern Nuclear for maintaining and updating drawings.

5.4.4 Southern Company Services, Incorporated (SCS)

SCS will provide services for maintaining and updating drawings in accordance with properly approved procedures.

5.4.5 SNC-Farley Project l )

SNC-Farley Project will perform safety-related activities in accordance with properly approved instructions, procedures and drawings.

5.4.6 SNC-Administrative and Technical Services SNC Administrative and P Anical Services will perform safety-related activiti:u. In accordance with properly approved procedures.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A O chapw 5 Rev.

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5.4.7 Contractor and vendor Organizations l Contractors and vendors providing services at the FNP ]

will perform safety-related activities in accordance with !

properly approved instructions, procedures, and drawings.

5.4.8 Manager-safety Audit and Engineering Review (MSAER) l

'Ihe MSAER shall insure that adequate guidance is provided to l the SAER Group for the performance of activities required by j

, this OQhPM. i

'Ihe MSAER is responsible for the periodic auditi of- !

compliance with quality requirements for instrue ons, I procedures, and drawings from origination through use in l

. performing activities. l 5.9 Operations Quality Assurance Policy Implementation List (OQAPIL)

'Ihe OQAPIL is a ccaposite listing of administrative procedures issued by the General Manager-Nuclear Plant, General Manager-Nuclear Support, and Manager-Safety Audit and Engineering Review I to implement responsibilities assigned _ to each in the OQAPM. 'Ihe - :

Manager-safety Audit and Engineering Review is responsible for i reviewing and approving procedures to be included on the OQAPIL and J revisions thereto, prior to their issue, to confirm that provisions ,

are made to adequately and comprehensively implement all '

responsibilities assigned to managers in the OQhPM. In support of- :

the administrative guidance contained in procedures or the OQAPIL, each manager shall provide for detailed work procedures or other. ,

documents as required for use in performing and controlling activities. j l

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLEAR PLhNT CW 6 "'*

31 N' 1 OF 4 w

DOCUMNT CGf!BOL ,

6.1 Purpose ;

this chapter assigns responsibilities for controlling documents l which prescribe activities affecting quality. Such documents include instructions, procedures, drawings, and other guidance. j 6.2 Syg -l Document control measures include those ftcessary for insuring proper document review, approval, distribution, and use at the location where safety-related activities are performed. Corresponding control measures are to be applied to document changes.

l Documents subject to control measures herein include those which j will be or may be used for guidance in performing safety-related ,

activities. Such documents includes design specifications; l O- procurement documents; design, manufacturing, construction, and installation drawings; OQhPM and OQAPIL; procedures and instructions; ;

l FSAR; test procedures; Technical Specifications; and documents which !

are used by reference in guidance documents. ;

i 6.3 References :

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a. 10 CFR 50, Appendix B, Criterion VI

b. ANSI-N18.7 (1972), sections 5 and 6.2 l

c. ANSI-N45.2 (1971), Section 7 1

d. FNP FSAR 5ections 13.5, 17.2.6 and 17.3 6.4 Responsibilities 6.4.1 General Each manager as described herein responsible for the accomplishment of safety-related activities shall have one or more documented systems for controlling the guidance documents for which he is responsible. He shall be responsible for issuing guidance documents which he originates and for controlling existing guidance documents and changes thereto.

Each system shall include provisions for the following:

, review of new domanents for adequacy before approval; new document approval and release for distribution by designated personnel; distribution of documents to users; confirmation of receipts. availability of documents for use at locations O where the prescribed activity is performed prior to commencing the work; and handling of obsolete documents. Each system shall have provisions to insure that changes are reviewed and approved by the same functional group responsible for review and approval of original documents.

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- OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chap *'

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Applicable procedures shall be reviewed following a Reportable. .l.

Event or a system modification. Document control measures shall provide for confirmation of receipt by the user, prompt entry of changes, and the removal of the superseded matter to :

prevent inadvertent use.

Each manager described herein shall maintain a " master list" l identifying the latest changes and/or revisions to his !

controlled docu ents. He shall insure that such a list is f periodically distributed or is otherwise available on a timely '

basis to users, and each manager shall require periodic verification that the controlled documents are coglete azxt '

up to date. :

6.4.2 General Manager-Nuclear Plant (Gee)

The Gee shall be responsible for controlling the following l guidance documents: plant procedures and instructions; procurement documents; drawings; design specifications; !

Technical Specifications; and documents which by reference f in one of the preceding doctments becomes a guidance '.

doctament. His document control system shall include a ,

description of control for each of the document categories ;

above. His control of such documents shall begin when he ?

originates doc u ents or when he assumes control of existing !

documents. !

The Gee shall have a system for controlling procedures and instructions for plant operation complying with the provisions of section 6.4.1. This system may contain l provisions for_ making temporary changes to~ existing- ;

procedures where such changes do.not involve a change in ;

the intent of the procedure. If provided for, such changes dall be made in accordance with guidance in ANSI-N18.7, l

_ section 5. However, provisions shall also be made for_all [

l temporary changes to be subsequently reviewed for approval i I in a timely manner by the same review and approval authorities as used for the original procedure.

The Gee shall have a system for controlling vendor manuals, ,

standards, guides, or other documents which he does not issue ,

t but which he prescribes for use, in whole or in part, as l procedures, guides, or instructions for acccmplishing ,

safety-related activities. The control of such documents :

shall be similar to and parallel the control of instructions ;

and procedures which he issues. Inglementation of changes ,

to such documents shall be controlled as changes to plant ,

originated documents. !

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OPERATIONS QUAUTY ASSURANCE . Southem Nudear Operating Company A chap

6 Rw. 31 Pag' 3 Cr (

Design specifications; which include procurement specifications, site construction specifications, NSSS specifications ("E" specifications), and test specifications; shall be included in the document control system. This system may be subdivided by generic classification, and the control system for procurement doctaments ad procurement specifications may be handled as one and the same if appropriate.

The control system for safety-related design, manufacturing, construction, and installation drawings shall incorporate provisions for the services provided by Southerr. Company ,

Services, Inc. (SCS) in maintaining the Drawing Hegister. l l The Drawing Register is a comprehensive listing of both l

" domestic" and " foreign" drawings. Domestic drawings are originated by SNC-Farley Project, SCS, or Bechtel. Foreign l drawings are originated by Westinghouse or other annufacturers.

After turnover from the APC Construction Department, the GelP O shall have control of all safety-related drawings and changes thereto regardless of who initiated the drawings or changes.

l The GDIP shall utilize the PORC as required by FNP Technical l Specifications to identify any unreviwod safety questions.

If an unreviewed safety question is. identified, the proposed change must be reviewed by the NORB, approved by the Vice President, and approved by the NRC prior to implementation. l i If upon advice of the PCRC, the Gee determines that the '

proposed change does not involve an unreviewed safety ;

question, he may approve it for implementation, except i in the case of a change to the Technical Specifications. ,

'mehnical Specification changes must be forwarded to the NORB and the leC for approval. The Gee shall sutuait safety evaluations for changes implemented within the ,

scope of 10 CFR 50.59 to the vice President via prescribed l administrative channels and to the NORB for verification !

that such changes did not constitute unreviewed safety '

questions. ]

6.4.3 Vice President l )

l If an unreviewed safety question is identified in a proposed I change, it unast be reviewed by the NCRB, approved by the Vice President, and approved by the NRC prior to implementation. l Safety evaluatim s of changes implemented under the provisions of 10 CFR 50.59 shall be reviewed by the Noms and verified by i O the Vice President that such changes did not constitute unreviewed safety questions.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapter 6 Rev.

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6.4.4 General Manager-Nuclear Support (GNNS)

We GPNS shall have a system which complies with the provisions of Section 6.4.1 for controlling guidance documents originated or distributed by Nuclear Support. ,

he GMNS shall provide a control system for the FSAR which provides for distribution to all appropriate organizations / persons and which maintains duplicate copies in separate locations.

6.4.5 Manager-Safety Audit and Engineering Review (MSAER).

We MSAER shall have a system for controlling the OQAPM, OQAPIL, and other quality documents issued under his direction.

We MSAER is responsible for the periodic auditing of document control.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A chapter Rev. Page JOSEPH M. FARIKY !WCI. EAR PIANT 7 31 10F5 i

CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES l l

7.1 Purpose j l

This chapter assigns responsibilities for measures to control. l purchased materials, equipment, components, and services utilized for the FNP. j l

7.2 Scope Quality assurance requirements for the control of safety-related i purchased material, coeponents and equipment commence with the i selection of vendors and continue through installation in the j FNP and retention of quality records for the installed material, components, and equipment in FNP files. Quality assurance requirements for handling and storage are contained in Chapter 13.

Quality assurance requirements for vendor services utilized for safety-related activities at FNP commence with selection of the service vendor and continue with inspection, monitoring, and auditing of vendor services until they have been completed.

7.3 References

a. 10 CFR 50, Appendix B, Criterion VII

b. ANSI-N18.7 (1972), Section 5.3.9

c. ANSI-N45.2 (1971), Paragraph 8

d. FNP FSAR section 17.2.7

e. ANSI-N45.2.13 (Draft 2, Rev. 4, 1974)

f. ANSI-N45.2.2 (1972), section 5

g. Management Procedure 315-001

h. Imc Regulatory Guide 1.38 (Mar. 1973) which endorses ANSI-N45.2.2 (1972) 1

i. Management Procedure 315-002 !

j. SNC Support Services Quality Assurance Policy Manual 1 1

7.4 Responsibilities l i

7.4.1 General Manager-Nuclear Plant (GPNP) l

a. The GPWP shall establish measures for controlling safety-related purchased material, components and '

equipment received at FNP. These measures are to insure the following:

(1) Performance of receipt inspections in accordance with documented guidance which includes the following and applicable provisions of ANSI-N45.2.2, section 5: l

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A Chaptw 7

Rev. Page 5

O (a) Verification that the component or material is properly identified as required in the procurement document; (b) Verification that the identity of the item corresponds with, and is traceable to, received quality documentation; (c) verification that the received quality documentation completely meets all procurement document requirements; I

(d) Physical inspection of the received item for damage.

(2) Upon completion of the receipt inspection, identification of the inspected item showing the inspection status, the name of the inspector, and the date.

(3) When items meet the acceptance criteria of the receipt inspections, they are to be released for storage or use. Acceptance is to be judged as a minimum, on the following: certifications that specifically identify the purchased material or equipment and the specific quality requirements (e.g., codes, standards, specifications, etc.)

met by the iten; and certifications that identify any procurement requirements which have not been met together with a description of those non-conformances dispositioned " accept as is" or

" repair".

(4) When items do not meeti acceptance criteria of receipt inspections and are therefore in non-conformance, they shall be segregated into a controlled area for nonconforming items. If physical separation is not reasonable, the item is to be conspicuously identified as non-conforming to prevent inadvertant use.

(5) Quality documents for each item received are to be permanently retained in plant files while the item is installed in the plant or stored for future use.

(6) 'Ihe above measures shall be met by the FNP staff for all items received at the FNP either by direct procurement or through the services of a contractor.

i OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A Cd** 7- h 31 Page 3 of' 5

b. We GNP shall establish measures for verifying that r safety-related vendor services for the FNP performed on-site, off-site, or a combination of on-site and i off-site comply with the quality requirements of procurement documents. Rese shall include the following.

(1) Supervision and monitoring of on-site vendor l service for compliance with the codes, standards, I specifications and other quality requirements of procurement doctments.

(2) Receipt and retention of all quality docusents from

' the vendor which were included as r irements in the services procurement document verification of their adequacy and acceptability.

(3) on-site inspections as provided for in procurement documents. Such inspections are to be done by qualified inspectors. Records.of inspections shall be retained in plant files.

7.4.2 General Manager-Nuclear Support (GWS) me G as shall participate in the evaluation and selection of suppliers of safety-related material, components, equipment and nuclear fuel to be placed on the approved bidders list maintained by the SNC-Administrative Services Procurement l Department as requested. When requests are received, the proposed commodity is first evaluated to determine the need for addition to the approved bidders list. If such a need is identified, the Gus shall coordinate the necessary reviews ,

to determine the acceptability of the supplier. SNC Corporate !

Quality services shall evaluate the supplier, at the request of the Gus, to determine if the proposed supplier has an ac e quality assurance program for the ecemodity to be ied. Upon completion of such reviews, the Gus provides a written recommendation to the Manager Procurement-Nuclear concerning addition of the proposed supplier to the approved bidders list.

h e G MB shall maintain a Plant Services Approved Suppliers I List for FNP services. He shall maintain vendors on the.

list based on consideration of one or more of the following:

historical quality performance data; objective evaluation of identified qualitative or quantitative data; and results from I audits of the supplier's facility. l l

me GMS shall establish measures for verifying that the O safety-related vendor services consigned to Nuclear Support caugly with the requirements in paragraph 7.4.1.b above. q Se Gus shall establish measures for the performance of source surveillance at vendor facilities, as necessary, to ensure quality.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chaptw Rev. Page 7 31 4 OF 5 l l

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7.4.3 Manager-Safety Audit & Engineering Review (MSAER) ne MSAER shall review and determine the acceptability of SCS's quality assurance program to be used in providing safety-related sevices directly to Southern Nuclear operating Company for FNP. We MSAER shall subsequently .

review and approve the program annually for continued use. j me MSAER shall review and determine the acceptability of l SNC's quality assurance program to be used in providing -

safety-related services directly for FNP. Se MSAER shall !

subsequently review and approve the program annually for continued use.

We MSAER shall be responsible for measures to verify the quality of the design control and fabrication of nuclear i fuel and its associated components. We means of verification will include the use of SNC h chnical Services for the purchase and quality assurance of nuclear fuel. l he MSAER shall ensure that adequate inspections and audits are performed on the fuel, on the documentation relating to the fuel, and on the activities of the fuel design and fabricating company.

We MSAER shall be responsible for measures to ensure the quality of items and services procured for use at FNP. Se means of verification will include the use of SNC Corporate Quality Services for the evaluation and audit of vendors' l quality assurance programs and off-site services.

me MSAER shall review the quality programs utilized for safety-related FNP services performed on-site by selected vendors under the direct control of SNC-Farley Project. l Mis shall include the auditing of selectedon-site service activities.

S e MSAER is responsible for the periodic auditing of the documentation and activities of the SNC-Farley Project in the control of purchased material, equipment and services. l O'

r- OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A i chapter Rev.

7 31 Pa9' 5 0F 5 ,

7.4.4 SNC-Administrative Services-Manager Procurement l We SNC-Manager Procurement is responsible for the purchase of all materials, components, and equipment as specified in the SNC Support Services Quality Assurance Policy Manual.

He will maintain the approved bidders list and has overall-responsibility for supplier selection from this list. He obtains recommendations concerning vendor evaluations and selection from the SNC-Farley Project and makes decisions '

for changes to the approved bidders list based in part on the comments received from the SNC-Farley. Project.

7.4.5 SNC-Manager Corporate Quality Services l Se SNC-Manager Corporate Quality services is responsible for periodic reviews of suppliers' performance. his review shall incorporate comments concerning supplier performance provided O by the GPNP, the GrH5 and the SNC-Manager Procurement. l l

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OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A !

JOSEPH M. FARLEY NUCLEAR FIhrr c* 8

31 Page y g7 g IDENTIFICATICN Alt CCNTROL OF MATERIALS, PARTS Alt COMPONENTS 8.1 Purpose This chapter assigns responsibilities for establishing, maintaining, and verifying the adequacy and proper use of measures for identifying and controlling materials, parts and components having safety-related '

functions or affecting the safety-related functions of structures, systems, or components at the FNP to preclude the use of incorrect or defective items.

8.2 Scope These identification and control requirements apply to materials, parts, components, and partiall fabricated subassemblies to be used or in use in safety related app ications at the FNP. !

8.3 References

a. 10 CFR 50, Appendix B, criterion VIII

b. FNP FSAR, Section 17.2.8

c. ANSI-N18.7 (1972), Section 5.3.9 !

d. ANSI-N45.2.8 (Draft 3, Rev. 3, Apr. 1974), Section 3.0 I

e. ANSI-N45.2 (1971), Paragraph 9 8.4 Responsibilties 8.4.1 General Manager-Maclear Plant (GPNP)

Safety-related materials, parts, and components that were-initially stored or installed prior to turnover to the GMNP for preoperational testing were required to be identified by part number, serial number, assembly ntsaber or other appropriate means of identification. Identifications are made to preclude use of incorrect items, to not introduce damage to the item, and to not affect its functioning. The identifications are to be traceable to appropriate quality doctmentation such as drawings, specifications, purchase orders, manufacturing and inspection documents, deviation reports, and physical and chemical mill test reports. ,

Identifications are to either be on the items or on records i traceable to th c. The GMNP shall establish asasures for !

the continued proper identification of such items and for O new items es they are received.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A g chapter Rev. P'9' 8 31 2 or 2 Plant identification and control measures are to include the followings steps for replacement of identifying tags or marks upon discovery of their loss or inadequacy; verification of identifications incident to item replacement (quality records shall indicate the identification of both removed and replacement items); steps for maintaining traceability to quality documentation when identification must be hidden, removed, or destroyed; inclusion of identification requirements in procurement documents; and verification and documentation of identifications of purchased material during receipt inspections.

The GMNP shall ensure that identification requirements in procurement documents include the following: application of unique part numbers, serial numbers, or other appropriate means of identification; affixation of identifications such as not to damage or impair the functioning of the items purchased; and use of the unique identifications in quality documentation.

l The GMP shall ensure that, where appropriate, identification requirements are included as inputs to proposed design changes.

! 8.4.2 Manager-safety Audit & Engineering Review (MSAER)

The MSAER is responsible for the periodic auditing of the t identification and control of materials, parts, and l components.

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OPERATIONS QUAUTY ASSURANCE SOuthem Nudear Operating Company A chap

Row Page JOSEPH M. FARLEY NUCIJNt PIANT 9 31 1 OF 3 l l

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l CCNIBOL OF SPECIAL PROCESSES 9.1 Purpose h is chapter assigns responsibilities for the establishment of measures to assure that safety-related special processes are controlled and are accomplished by qualified personnel utilizing !

qualified procedures in accordance with codes, standards, f

specifications, and other applicable requirements.

9.2 Scope special processes include specific types of welding, heat treating, nondestructive testing, and other processes that require performance by certified personnel using qualified ;

O procedures and, in some cases, use of qualified equipment and/or certified material to insure quality. " Qualified" i

as used herein refers to performance or use that has been evaluated and certified acceptable for a specific special !

process. :

9.3 References

a. 10 CFR 50, Appendix B, Criterion IX

b. 10 CFR 50.55a ;

c. ANSI-N18.7 (1972), sections 5.1.6 and 5.3.5 ;

d. ANSI-N45.2 (1971), section 10

e. FNP FSAR, Section 17.2.9

f. NRC Regulatory Guide No. 1.31 (Rev. 1 of safety Guide 31, i June 1973), Control of stainless steel welding

g. ISC Regulatory Guide No. 1.34 (Dec. 1972), control of Electroeleg Neld Properties

h. Inc Regulatory Guide No.1.43 (May 1973), Control of stainless steel weld cladding of Low-Alloy steel Components

i. NRC Regulatory Guide No. 1.44 (May 1973), control of the Use of sensitized stainless steel

j. NRC Regulatory Guide No. 1.50 (May 1973), Control of ,

Preheat 'Naperature for Weld of Low-Allow Steel

k. Regulatory Guide 1.58, Revision 1 (Sept. 1980), Qualification ,

of Nuclear Power Plant Inspection, Examination and Testing ;

Personnel i

1. NRC Regulatory Guide No. 1.66 (Oct. 1973), Nondestructive )

O m.

rvamination of Tubular Products NRC Regulatory Guido No. 1.71 (Dec. 1973), Welder Qualification for Areas of Limited Accessibility j

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E OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A chapter g

9 set 31 %. 2 or 3

n. ASME Boiler and Pressure Codes (1)Section II, Material Specifications (2)Section III, Nuclear Power Plants Components, and Appendix IX, Nondestructive Examination Methods (3)Section V, Nondestructive Examination (4)Section IX, Welding Qualifications (5)Section XI, Rules for In-Service Inspection of Nuclear Reactor Coolant Systems, 1983 Edition Summer 1983 Addenda

o. SNT-TC-1A and Supplements; American Society for Non-destructive Testing Recommended Practices, 1980 Revision 9.4 Responsibilities 9.4.1 General Manager-Nuclear Plant (GleiP)

'Ihe GetP has established a program of control for those special processes which are frequently used and will make provisions to initiate control of others as the need arises. For example, some types of welding may be used frequently while other types are used very infrequently. ,

I special processes are to be controlled such_that they are accomplished by qualified personnel using qualified procedures and, as applicable, qualified equipment and/or certified material. Special processes will be performed in accordance with applicable codes, standards, specifications, and/or requirements. =ror special processes which are not adequately covered by existing codes, standards, or other requirements, the necessary qualifications and certifications :

are to be defined.

Special processes are to be performed in accordance with documented procedures and using written check lists with recorded evidence of completion. Where applicable, i procedures shall require that processes be performed under certain environmental conditions.

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(] OPERATIONS QUALITY ASSURANCE V. cnapw 9

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l Qualification records of procedures, equipment, and personnel l shall be established for those special processes for which a i program of control has been established. Se records shall l be kept complete and up to date. ,

Special process procedures to be used by FNP staff members )

may be developed by either SCS, SNC or contract personnel, but review and approval responsibility shall be maintained -l by the GWP. For cases where the performance of special '

process activities at the FNP is assigned to contractors, procurement documents shall include provisions requiring the contractor to meet quality requirements equal to those herein and that contractors performing special process activities at the FNP shall submit copies of procedures and personnel certifications for SNC-Farley Project approval prior to work initiation. We GMP shall provide for monitoring of contractor activities performed on-site to the extent necessary to verify quality performance.

We G WP shall provide for performance of Authorized Nuclear Inspector (ANI)/ Authorized Nuclear Inservice Inspector (ANII) activities in accordance with applicable codes.

9.4.2 General Manager-Nuclear Support (GES) me GES is responsible for providing engineering and technical support to the plant staff as required to support the requirements of section 9.4.1 above.

9.4.3 Manager-Safety Audit & Engineering Review (MSAER)

Se MSAER is responsibile for the periodic auditing of '

the control of special processes.

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OPERATIONS QUAUTY ASRURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLFAR FIMrr C""" 10

31 P* 1 Or 5 INSPECTICN 10.1 Purpose

'Ihis chapter assigns responsibilities for the inspection of

', safety-related activities and equipment to verify conformance with quality requirements.

10.2 Scope Inspections shall be perfonned where necessary to insure quality in each of the following categories of safety-related activities:

plant operation, plant maintenance and modifications fueling /re-fueling; and surveillance tests and inspections. These are the '

general categories of safety-related activities for which O inspection responsibilities are addressed in this section.

Additional requirements for inspections associated with the control of purchased material, equipment, and services and with the control of nondestructive testing are addressed in Chapters 7 and 9 respectively of the operations Quality Assurance Policy Manual. Plant testing, which may be considered a form of inspection, is addressed in Chapter 11.

Surveillance tests and inspections, which are widain the scope of this chapter, include in-service inspections required by 10CFR50.55a(g) and section XI of the AsME Code. i l

10.3 References j

a. 10CFR50 Appendix B, criterion X

b. 10CFR50 Appendix J

c. 10CFR50.55a(g)

d. ANSI-N18.7 (1972) sections 4.4, 4.5, 5.1, 5.3 and 6.0

e. ANSI-N45.2 (1971) Section 11

f. ANSI-N45.2.4 (1972) sections 3-6

g. ANSI-N45.2.6 (1978) ,

h. ANSI-N45.2.8 (Draft 3, Bev. 3, Apr. 1974) Sections 2-4 l

i. NRC Regulatory Guide 1.58, Rev. 1 (Sept. 1980)

j. ASME Code Section XI, 1983 Edition Summer 1983 Addenda

k. FNP FSAR Sections 17.2.2 and 17.2.13 4 3

OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A g chao* 10 %- 31 Page 2 Or 5 10.4 Responsibilities 10.4.1 General Inspections of activities shall be performed by individuals independent from the one or more individuals performing the activity being inspected. Except as provided for below in the inspection of operation activities, individuals assigned as inspectors shall be indepeMent from those who performed the activity being inspected and the inspectors shall not have positions in which they normally report to the first line supervisor responsible for the activity being inspected.

Inspectors are to be formally qualified and certified to perform inspections to which they are assigned.

In the inspection of work activities, inspections shall be performed for each work operation where necessary to assure quality. If direct inspection of the product or a work operation is impossible or disadvantageous and it is .

necessary to assure its quality, indirect control by in-process monitoring of the work shall be performed. Both inspection of work products and in-process monitoring shall be performed when control is not adequate without both. If mandatory inspection hold points are necessary, which require witnessing or inspecting by an inspector and beyond which work is not to proceed without inspector approval, the specific hold po nts shall be indicated in the work procedure. Inspectitu requirements are to be indicated in work procedures where applicable. Equipment used for inspection shall be within calibra, on limits prior to its use in inspections.

Inspections are to be performed in accordance with documented procedures, instructions aM/or checklists.

For inspections which require only a simple check or reading, the inspection provision may be delineated in work procedures, but all other inspections shall be performed in accordance with separate inspection procedures which shall be referenced in work procedures.

For each inspection the following are to be documented:

a. Identification of quality characteristics to be inspected;

b. Identification of those individuals or the organizational group responsible for performing the inspection;

c. Acceptance or rejection criterias

d. Description of method of inspection;

1 OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A l,

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e. Results of the inspection including information related i to nonconformances and acceptability of results; *

f. Date of inspection and name of the individual performing-

. the inspection; ,

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g. Identification of any instruments or special equipment '

used to conduct the inspection.

Inspection results are to be reviewed and evalueted by an l assigned, responsible person to verify the acceptability !

of results. ,

1 10.4.2 General Manager-Nuclear Plant (GNP)

The GelP is responsible for all inspections conducted at I FNP. He is responsible for the performance of inspections r ired in the FSAR and in the Technical Specifications O where he deems necessary to insure quality. Inspections shall be performed to assure substandard performance does not remain undetected for instances in which performance testing may not adequately assure a suitable level of quality and reliability. He shall provide for the develop-ment of an inspection plan which sets forth and provides for all required inspections. Such a plan may be either comprehensive for all categories of inspections or may be a ntauber of individual plans for each inspection category (i.e., operation, maintenanceAmadifications, refueling, and surveillance tests and inspections).

'Ihe GelP shall assign centralized responsibility for the direction and coordination of all plant inspection activities, except those which are done as an integral part of plant operations in'accordance with approved procedures by licensed personnel. The person designated shall be assigned the responsibility for assuring that inspection plans, inspection' schedules, and procurement documents are reviewed for comprehensiveness and fulfill-ment of gaality assurance requirements. 'Ihe GelP shall also assign centralized responsibility for certifying inspectors and reviewing their assignments to insure the independence of inspection. j i 'Ihe GetP shall insure that inspection procedures and plans, !

and changes thereto are ande available to the Supervisor- ;

Safety Audit & Engineering Review (SSAER) and that the O SSAER is also promptly provided copies of inspection schedules and changes thereto.

l The GetP shall coordinate Authorized Nuclear Inservice Inspector activities in accordance with applicable codes.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A g

chapw 10 31 **9* 4 Or 5 Below are general inspection requirements for each category of -

inspections:

10.4.2.1 Inspection of Operation Activities Personnel holding Reactor Operator or Senior Reactor Operator licenses may constitute qualified inspectors for operation activities. Each inspection is to be performed by a person other than the person who performed the activity.

10.4.2.2 Inspection of Maintenance / Modification Activities Inspection requirements for modifications or maintenance shall include the original inspection requirements or equivalent alternatives to the extent that the original requirements can be determined from available documents.

General items of importance will include the following:

visual examinations to determine material and assembly integrity; cleanliness; housekeeping; environmental conditions; compliance with work procedures; use of proper tools; use of calibrated tools and instruments; and adequacy of identification and documentation.

Inspection personnel may be selected from Plant Modifications, Technical, Systems Performance, Operations, Maintenance, Instrumentation and control (IEC) Groups, or contractor personnel; but their independence shall be as prescribed in Section 10.4.1 above. Inspectors for maintenance and modification activities shall be qualified to meet minimum applicable inspector qualification requirements in accordance with ANSI-N45.2.6.

10.4.2.3 Inspection of rueling/ Refueling Activities Inspectors may be selected from the Operations, Maintenance, I&C, Technical Groups, or contractor personnel, but they will not report to supervision responsible for accomplishing the activity being inspected for the duration of the inspecting activity.

Inspectors are to be qualified either by virtue of their Reactor Operator or Senior Reactor Operator licenses for inspecting activities of an operations nature, or by fulfilling minimum inspector qualification requirements in accordance with ANSI-N45.2.6 for inspecting other activities.

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Southem Nudear Operating Company A

( OPERATIONS QUALITY ASSURANCE Chagw Re* Page in 31 5 Or 5 l

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10.4.2.4 Surveillance Tests and Inspections i The GMNP shall provide for overall coordination and control of the surveillance program including:

(a) Planning to insure that tests and inspections are )

done at proper intervals by qualified personnel; l (b) Reviewing and evaluating individual results to '

determine their acceptability; (c) Determining the adequacy of the scope and frequency of the test or inspection, and whether any follow-up action must be takens (d) Coordinating activities between plant groups and the Authorized Nuclear Inservice Inspector (ANII).

In that Surveillance Tests and Inspections do not involve the inspection of a work activity, inspection l responsibilities are unique. Inspector assignments may i be made from any Plant group possessing appropriate skills. Inspector qualification requirements sust be O, tailored to the specific test or inspection to be conducted. If the test or inspection is within the scope of license requirements for a Reactor Operator or Senior Reactor Operator, such licenses may be the basis for qualification of inspector. In all other cases, the minimum inspector qualification requirements shall ;

be in accordance with ANSI-N45.2.6. i In-service inspections required by Section XI of the ASME Code and other surveillance inspections may be performed by contractors. Such contracted services shall be in compliance with the requirements of Chapter 9 of this manual. Inspections conducted by contractors shall be monitored by plant personnel to insure ccepliance with quality requirements.

The GPtiP shall establish criteria for determining the !

inspection requirements and shall assure that these j inspections are acconplished with consistency for !

activities of similar nature. l 1

10.4.3 General Manager-Nuclear Support (GMNS)

The Gts is responsible for providing engineering and technical support to the plant staff as required to support the requirements of section 10.4.2 above.

10.4.4 Manager-Safety Audit & Engineering Review (MSAER)

The MSAER is responsible for the auditing of all inspection procedures and selected work procedures i to verify inclusion of quality requirements for l inspections. Additionally, he is responsible for j the periodic auditing of inspection activities, i

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OPERATIONS QUAUTY ASSURANCE Southern Nuclear. Operating Company A JOSEPH M. FARLEY NUCLEAR FIJNr cw gy w 31 Page g gy 3 l

usr ccwmx.

11.1 Purpose ;

i

'this chapter assigns responsibilities for assuring that all testing, which is required to demonstrate that structures, systems, and components will perform satisfactorily in service, i is adequately identified and properly performed.

11.2 scope Test control measures are applicable to all types of testing involving safety-related structures, systems, or components.

i 11.3 References l 1

O a.

b.

c.

10CFR50 Appendix B, Criterion XI 10CFR50 Appendix J FNF FSAR, sections 14.0 and 17.2.14

d. NRC atory Guide 1.68 (Nov. 1973)

e. ANSI 8.7 (1972)_section 6

f. NRC Regulatory Guide 1.41 (Mar. 1973)

g. ANSI-N45.2 (1971) Section 12

h. ANSI-N45.2.8 (Draft 3, Rev. 3, Apr.1974)

1. ANSI-N45.2.4 (1972)

j. NRC Regulatory Guide 1.30 (Safety Guide 30 of Aug. 1972) 11.4 Responsibilities 11.4.1 General Manager-Nuclear Plant (GDIP)

'the Geir is responsible for the establishment and performance of a comprehensive test program. The program is to include all testing required to demonstrate that safety-related structures, systems, and components will

- perform satisfactorily in service. The test program is to be identified, documented, scheduled, and acccmplished in accordance with controlled procedures.

The following types of testing are to be included in the test programs: bench check of instrumentation, component testing, preoperational testing, surveillance testing as required by the h chnical specifications, testing performed O after maintenance and/cr modifications, and additional testing which may be required freut time-to-time to demonstrate the readiness or adequacy of safety-related functions of plant structures, components, or systems.

OPERATIONS QUAUTY ASSURANCE Southern Nuclear Operating Company A Chapter 11 An 31 Page 2 of 3 g

Bench checks of instrumentation are to check selected instruments for proper functioning prior to installation.

Preoperational testing shall demonstrate the capability of structures, systems, and components to meet safety-related performance requirements. Testing after maintenance and those modifications that are equivalent to repairs shall verify that the subject system or equipment has been returned to a condition capable of performing its safety-related function. Testing after modifications that involve design bases or that may affect the plant's capability of withstanding anticipated transients and postulated accidents, shall demonstrate and confirm the required capability of the particular component (s) and/or system (s) to perform their safety-related functions.

Tests within the scope of this chapter shall be documented and accomplished by trained, qualified and certified personnel using formally approved written test procedures.

Such procedures shall incorporate or reference the require-W monts and acceptance limits contained in the operating license and applicable design documents. Each written test procedure shall include provisions for the following as applicable:

a. Prerequisite preparation, condition, and completeness of the item to be tested;

b. Prerequisite completion of ather tests or inspections;

c. Calibrated test instrumentation;

d. Adequate and appropriate test equipment;

e. Use and removal of temporary installations such as jumpers, piping bypasses, and test signals or devices;

f. Initial conditions;

g. Suitable and controlled environmental conditions as applicable;

h. Procedural steps for implementing the testing method or technique;

i. Mandatory inspection hold points with descriptions of the observations to be made or witnessed by assigned personnel;

O OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A V Chapter Rev.

11 31 P89* 3 or 3

j. Acceptance criteria;

k. Collection and recording of test data and results with data storage provisions; and

1. Certifying, dated signatures of those personnel who approve the test procedures, perform the test, I perform inspections, record data, evaluate results, and who accept or approve the test results. Test results are to be evaluated and their acceptance ,

status identified by qualified personnel as -

designated by the G NP. i 11.4.2 General Manager-Nuclear Support (GWS) the Gus is responsible for providing engineering and O

j technical support to the plant staff as required to ;

support the requirements of section 11.4.1 above. j 11.4.3 Manager-Safety Audit & Engineering Review (MSAER) i The MSAER is responsible for the periodic auditing of test control.

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,. OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A ;

JOSEPH M. FARLEY NUCLEAR PWrr cw 12 Row 3g Page 1 OF 2

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CGrmOL OF MEASURING AIC TEST EQUIPMENT ;

l 12.1 Purpose l

Mis chapter assigns responsibilities for measures to assure that l sensuring and test equipment are properly controlled, calibrated, I and adjusted at specific periods to maintain accuracy within l necessary limits. I 12.2 Scope l 1

mese requirements apply to all measuring and test instnnents such as: tools, gauges, readout instruments, interlock permissive and prohibitive circuits, alarm devices, sensors, signal conditioners, ,

controls, protective circuits, laboratory equipent, reference and i transfer standards, and nondestructive test equipment which are O used in the measurement, inspection, or monitoring of safety-related components, systems, and structures.

12.3 References

a. 10 CFR 50, Appendix s, Criterion XII

b. NRC Regulatory Guide 1.33 (safety Guide 33, Nov. 1972)

c. ANSI-N18.7 (1972) Section 5.3.6

d. ANSI-N45.2 (1971) Section 13

e. FNP FSAR, Section 17.2.12

f. ANSI-N45.2.4 (1972) Sections 2 and 6 12.4 Responsibilities 12.4.1 General Manager-Nuclear Plant (GN4P)

Se Geir shall establish and maintain a system for the control and calibration of measuring and test equipent.

21s system is to include provisions for the following:

a. Identifying each piece of measuring and test equipment to be controlled.

b. Preparing and implementing procedures for the control, calibration, and adjustment of each category of measuring and test equipment requiring calibration.

1 mese procedures will include requirements for the O

control of the equipent, calibration accuracy, schedule, records, and traceability. Calibration and adjustments are to be done at specified intervals based upon accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting measurement.

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i OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A ,

chao* 12 Reit. 3g Pag' 2 or 2

c. Recording and maintaining the complete status of all controlled measurement and test instruments. Calibra-tion test data is to be identified as to the equipment to which it applies.

d. Affixing of labels or tags on each item upon completion of calibration or calibration checks which show date calibrated, person who performed calibration, and date when calibration will become overdue. Such labels or tags may be entitted where physically impractical.

e. Using calibration standards which have an uncertainty requirement of no more than one-fourth the tolerance of the equipment being calibrated. A greater uncertainty may be acceptable when limited by the commercially available " state-of-the-art".

l f. Performing an evaluation when a piece of measuring and l

test equipment is found to be out-of-calibration and documenting the results concerning the validity of inspections made using the out-of-calibration device since its last calibration. Equipment found to be out of calibration shall be clearly identified as such.

Special calibrations shall be performed whenever the accuracy of a device is in question. When an instrument will not remain in calibration, it shall be repaired or replaced.

g. Assuring that when portable instruments are not in'use, they are stored in locations and environments which do not adversely affect their performance or accuracy.

We GMP shall require the inclusion of quality provisir.ns for the control of measuring and test equipment in procure-ment specifications for FNP service contracts.

12.4.2 Manager-Safety Audit t. Engineering Review (MSAER) he MSAER is responsible for the periodic auditing of control of measuring and test equipment.

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[ OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Companyb JOSEPH M. ' FARLEY NUCLFAR PIAlff c* 13

31 P*0' 1 or 3 i

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l HANDLING, S'IDiqAGE AND SHIPPING I

1 13.1 Purpose ,

1 1his chapter. assigns responsibilities for controlling the handling, storage, shipping, cleaning, packaging, and )

l preservation of material, components, and equipment to i prevent damage, loss, or deterioration. )

13.2 scope

'Ihese requirements apply to safety-related material, !

components, and equipment which have not yet been pre- -

.j operationally tested or placed into operational use, or i which have been removed from installation in order to be processed in some manner for return to operational use. )

13.3 References ,

1 10 CFR 50, Appendix B, criterion XIII

a. '

b. NRC Regulatory Guide 1.38 (Mar. 1973), which endorses ANSI-N45.2.2 (1972) ,

c. ANSI-N18.7 (1972), section 5.3.9 !

d. ANSI-N45.2 (1971), Section 14 l

e. FNP FSAR, Section 17.2.13 13.4 Responsibilities 13.4.1 General Manager-Nuclear Plant (G9EP) l The GelP is responsible for measures to control handling, storage, shipping, cleaning, packaging, and preservation '

of materials, components, and equipment as indicated below ;

to prevent damage, loss, or deterioration by environmental I conditions such as temperature or humidity. l

a. General (1) The development and use of procedural guidance for handling, storing, shipping, cleaning, packaging, and preserving items will be based on manufacturer's I instructions or recommendations, design specifica-tions, and applicable codes and standards.

Procedural guidance shall be developed for each O generic classification of materials and equipment as described in ANSI-N45.2.2 (1972) and for individual materials and equipment having unique I characteristics requiring special treatment. NRC Regulatory Guide 1,38 shall be used in developing l the procedures. l

i OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A enapter nev.

g 13 3g Page 2 OF 3 l l

1 Procedures shall contain documentation requirements l i as necessary to provide evidence that evolutions l are performed in accordance with applicable '

procedures.

l (2) Assignment of specific responsibilities shall be made for handling, storage, shipping, packaging, cleaning and preserving items with accomplishment by qualified individuals.

(3) Tools and equipment used in handling, shipping or i storage and having critical characteristics or !

limitations shall be periodically inspected and/or tested in accordance with documented procedures to verify continued acceptability. Se results )

of such inspections and tests shall be documented.

(4) ne GelP shall include quality assurance provisions for handling, storage, and shipping in procurement documents.

b. Handling Procedures shall include prescribed handling methods from receipt to storage and from storage to installation. (Procedures for receipt of material are prescribed in Chapter 7.)

c. Storage Procedures for storage shall include the designation of storage areas and the control of access to storage areas.

d. Packaging, cicaning, and Preserving Procedures for packaging, cleaning and preserving shall incorporate guidance in Sections 3.2, 3.3, and 3.4 of ANSI-N45.2.2 (1972). (Chapter 20 addresses levels of cleanliness of reactor fluid systems and associated components.)

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Southem Nuclear Operating Company A

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' OPERATIONS QUALITY ASSURANCE Chapter Rev. Page 13 31 3g3 b

e. Shipping Where applicable, shipping procedures shall provide instructions for use of special shipping containers.

Shipping procedures for nuclear materials shall comply with applicable codes, regulations, and license provisions. ,

13.4.2 Manager-safety Audit & Engineering Review (MSAER)

The MSAER is responsible for periodic auditing of handling, storage, and shipping.

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l OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapter p.g. -

JC3EFii si. FATGi NUCTIA* *!X4 14 Rev.

n 1y) j i

INSPECTION, TEST, AND OPERATING STATUS 1

14.1 Purpose 1his chapter assigns responsibilities for the followings identifying 1 the status of required inspections and tests on individual items ;

being processed for installation in the plant; identifying installed l items which for any reason are not ready for unrestricted operational uses and identifying and controlling those temporary altarations such as bypasses, lifted leads, and blank flanges on installed items that are made in accordance with approved procedures.

14.2 S_coge these requirements apply to safety-related structures, systems, l and components that are installed or that are being processed for l

_, installation. Status control of safety-related materials and spare, twplacement, and modification parts that are being received by

~

purchase or that are in storage prior to being processed for installation is addressed in Chapter 7, " Control of Purchased Material, Equipment, and Services", and in Chapter 15, "Non-conforming Materials, Parts, or Components". Status control of measuring and test equipment is addressed in Chapter 12.

14.3 References

a. 10 CFR 50, Appendix B, criterion XIV

b. ANSI-N18.7 (1972) Section 5.1.5

c. ANSI-N45.2 (1971) Section 15

d. FNP FSAR, Section 17.2.14

e. NRC Regulatory Guide 1.47 (May 1973) 14.4 Responsibilities 14.4.1 Plant Manager the Plant Manager shall establish procedures and use one or more inspection, test and/or operating status control systems. Procedures shall include provisions for the following:

a. Measures to indicate by use of markings such as stamps, tags, labels, touting cards, or other suitable means, the status of inspections and tests performed on O individual uninstalled items that are being processed incident to maintenance modifications, fueling, refueling, or other evolutions for installation in the plant. These measures shall be designed to preclude inadvertently bypassing the successful I completion of required tests and inspections. j l

OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A Chaptw Rn g

14 31 Page 2 OF 2 he application and removal of the marking devices shall be controlled in accordance with documented guidance which includes the assignment of authorities and responsibilities.

b. (1) A directive that required inspections and tests on installed items or on items being processed for installation shall not be bypassed, or (2) measures and assignment of authorities for bypassing required inspections and tests on installed items or on items being processed for installation.

c. Measures for identifying the status of installed items that for any reason are not ready for unrestricted operational use in accordance with approved test or operating procedures. Measures shall include the assignment of authorities and responsibilities for assigning, removing, and changing status identifications. Wese measures are to be designed to preclude inadvertent unrestricted operational use. Status devices shall be placed on or adjacent to items identified and/or on their controls as applicable to preclude inadvertent unrestricted operational use,

d. Measures for identifying and controlling temporary alterations such as bypasses, lifted leads, and blank flanges that are used on installed items in accordance with approved procedures. Measures shall include the l

assignment of authorities and responsibilities for installing and removing the temporary alterations.

Se measures shall be designed to preclude inadvertent operational use of tesporary alterations,

e. Description of each statur identification device to be used for provisions a, c, and d above.

f. Periodic, frequent audit by supervisory personnel of the control records used for provisions e and d above.

We Plant Manager shall include quality assurance provisions concerning inspection, test, and operating status where applicable in procurement documents for safety-related services.

14.4.2 Manager-Safety Audit & Engine,ering Review (MSAER) h MSAER is responsible for the periodic auditing of I procedures and activities involving inspection, test, and operating status.

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-v(') OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLEAR PIA!C c* 15 Re*

31 Page 1 or 3 i NONCONFORMING MATERIALS, PARTS, OR COMPONDCS 15.1 Purpose his chapter assigns responsibilities for controlling safety-related materials, parts, components, services, or activities which do not conform with applicable codes, standards, design specifications, drawings, procurement requirements, or license provisions to preclude inadvertent use or installation.

15.2 Scope Wese control measures provide for the identification, documentation, segregation, review, disposition, and notification to appropriate personnpersonnel of nonconforming materials, parts, '

O components, services, or activities in order to prevent their inadvertent use or installation. Nonconforming items within the requirements of this chapter are those identified at FNP during receipt inspections and those identified when verifying the quality of a repaired, fabricated, or modified item prior to use or installation - this includes items which have been previously installed or in use and that have been removed for disposition.

15.3 References i

a. 10 CFR 50, Appendix B, Criterion xv

b. ANSI-N18.7 (1972) Sections 5.1.6.1 and 5.3.9

c. ANSI-N45.2 (1971) Section 16

d. FNP FSAR, Section 17.2.15 15.4 Responsibilities 15.4.1 General Manager-Nuclear Plant (CNIP) he GP94P shall be responsible for controlling non-conforming material, part, material, parts, components, services, or activities in order to prevent their inadvertent use or installation. He shall maintain such control in accordance with documented procedures which include the following:

a. Identification of nonconforming items during receipt O inspections, items removed from installation for disposition, and when verifying the quality of a repaired or modified item prior to use or installation.

Nonconformance identifications shall,be maintained on items until proper dispositioning is completed.

OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A chapte' Rn g

15 3g Page 2 OF 3

b. Segregation and marking of nonconforming items as practical. As a guideline, control of nonconforming items by tagging, marking, or other means of identification is acceptable where physical segregation is not practical, although physical segregation and marking are preferred.

c. Mechanism for dispositioning of nonconforming items and their related documentation. Personnel who have associated responsibilities or who are affected by nonconformances shall be notified of identified nonconformances. Nonconforming items shall be held, rejected, repaired, or accepted "as is" with documented justification in each case.

d. Designation of the GPEP as the approval authority for "as is" acceptance of nonconformances.

e. Designation of other personnel assigned responsibilities and authorities for dispositioning of nonconformances.

f. Handling of those nonconforming items that have been proposed for acceptance "as is" as proposed design changes in accordance with Chapter 3 when the non- ,

conformance involves design characteristics.

g. Repairing, reworking, and inspecting non-conforming items in accordance with approved procedures that incorporate design guidance where applicable.

h. Verifying acceptability of reworked or repaired items by inspection of the item, description of non-conformance, disposition, inspection requirements imposed if finally accepted, and signature approval of disposition.

i. Periodically sununarizing and analyzing nonconformance reports to show dispositioning and quality trends in a report to the Vice President with copies to the GMNS l for his review and the Manager-Safety Audit and Engineering Review for his information.

j. Including nonconformance requirements in procurement documents for materials or services for use at FNP.

Documents which show dispositioning of " accept as is" or " repair" items are to be included in the seller's documentation for SNC-Farley Project. l

t OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company d j cnapte' Rw. Page 15 31 3 or 3 i

15.4.4 Manager-safety Audit & Engineering Review (MSM:R) he MSAER shall periodically audit activities involving nonconforming materials, parts, or components.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLEAR PLANT Ch*0 16 b- 31 Page 1 OF 5 CORRECTIVE ACTION 16.1 Purpose This chapter assigns responsibilities for identifying and correcting i conditions which are adverse to quality. For conditions that are i significantly adverse to quality, this shall include determinations -

of the causes of the conditions and provisions for corrective action !

to preclude repetition.

16.2 Scope Conditions adverse to quality includes failures, malfunctions, i deficiencies, deviations, defective material and equipment; non- !

conformances and noncompliances identified in SAER or NRC audits; !

and occurrences of adverse conditions that are reportable to the :

NRC involving safety-related activities or safety-related functions l of structures, systems, or cesponents that are installed or in use.

Conditions classified as significantly adverse to quality shall 1 include those designated in FNP 14chnical Specifications to be '

reportable. Requirements concerning corrective action for non- )

J conforming asterials, parts, and components that are not installed l or placed into use are contained in Chapter 15. Reports of corrective action involving noncompliances identified in SAER and - l NRC audits are made in accordance with the provisions in Chapter 18. ) i 16.3 References

a. 10 CFR 50, Appendix B, criterion XVI l

b. ANSI-N18.7 (1972) Sections 5.1.6.1, and 6.2.4

c. ANSI-N45.2 (1971) Section 17

d. FNP 14chnical Specifications

e. FNP FSAR, Section 17.2.16 16.4 Responsibilities 16.4.1 General Manager-Nuclear Plant (CN4P)

The GelP shall assure that conditions adverse to quality l are identified and corrected in accordance with documented procedures. These procedures are to include provisions for the following:

a. A mechanism for handling and documenting conditions :

adverse to quality which includes: identification of items or activities having adverse conditions with descriptions of conditions; evaluation and determina- ;

tion of courses of corrective action; performance of J O, corrective actions; documentation of completed corrective actions and associated data in quality records of the items or activities involved in the !

adverse condition and, if applicable, changing procedures applicable to the item or activity; review and verification that proper corrective actions have

OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A Chapter Re. Pag

g ig 31 2 OF 5 The mechanism for handiing conditions which are adverse to quality shall additionally include determination of the cause and action to preclude repetition.

b. Designation of supervisory responsibilities in handling corrective action.

c. In conjunction with the evaluation of adverse conditions I and determination of appropriate courses of corrective

! action, investigation to determine whether the problem is generic and requires generic corrective action.

d. Performance of corrective action at the earliest time practicable. Until corrective action has been completed, the identified condition is to be kept under surveillance for indication that the identified adversity may be increasing therefore requiring more l

immediate corrective action.

e. Periodic review by supervisory personnel of the corrective action status of all uncorrected adverse conditions for which they are responsible,

f. Reporting conditions significantly adverse to quality to the Vice President and Manager-Safety Audit and l Engineering Review.

g. Review by the PORC and the NORB of reports of conditions significantly adverse to quality for ultimate submittal to the NRC in accordance with FNP Technical Specifications.

h. Where appropriate, placing identifications on or adjacent to cy- ents, equipment, or material and/or their controls having identified adverse conditions.

i. If a decision is made to use in repairs the identical type of material or couponent that was involved in the adverse condition, review of related historical data to verify that the material or component has not proven to be unreliable.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A chapter Rev. P8" ig 31 3 or 5 16.4.2 General Manager-Nuclear Support (GWS)

The GMNS shall assure that conditions adverse to quality are identified and corrected in accordance with documented procedures. These procedures are to include provisions for ,

the followings

a. A mechanism for handling and documenting conditions adverse to quality which includes: identification of items or activities having adverse conditions with descriptions of conditions; evaluation and determination of courses of corrective action; performance of corrective actions; documentation of completed corrective actions and associated data in ;

quality records of the items or activities involved .

in the adverse condition and, if applicable, changing O procedures applicable to the item or activity; review and verification that proper corrective actions have been completed; and documentation of closing-out action. The mechanism for handling conditions which are significantly adverse to quality shall additionally include determination of the cause and action to preclude repetition.

b. Desi tion of supervisory responsibilities in ing corrective action.

c. In conjunction with the evaluation of significantly adverse conditions and determination of appropriate courses of corrective action, investigation to determine whether the problem is generic and requires generic corrective action.

d. Performance of corrective action at the earliest time practicable. Until corrective action has been completed, the identified condition is to be kept under surveillance for indication that the identified adversity may be increasing therefore requiring more immediate corrective action. -

e. Periodic review by supervisory personnel of thG corrective action status of all uncorrected adverse conditions for which they are responsible.

f. Reporting conditions significantly adverse to quality to the vice President and Manager-Safety Audit f. l Engineering Review.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapt *'

g 16 ""- 31 Page 4 OF 5 i

16.4.3 Manager-Safety Audit and Engineering Review (MSAER)

We MSAER shall assure that conditions adverse to quality are identified and corrected in accordance with documented procedures. Wese procedures are to include provisions ;

for the following

a. A mechanism for bandling and documenting conditions adverse to quality which includes identification of items or activities having adverse conditions with descriptions of conditions; evaluation and .

determination of courses of corrective action; performance of corrective actions; documentation l of completed corrective actions and associated l data in quality records of the items or activities involved in the adverse condition and, if applicable, changing procedures applicable to the item or activity; review and verification that proper corrective actions ,

have been completed; and documentation of closir.g-out ,

action. We mechanism for handling conditions which are significantly adverse to quality shall additionally include determination of the cause and action to preclude repetition.

b. Designation of supervisory responsibilities in handling l corrective action.

c. In conjunction with the evaluation of significantly adverse conditions and determination of appropriate courses of corrective action, investigation to determine whether the problem is generic and requires generic corrective action.

d. Performance of corrective action at the earliest time practicable. Until corrective action has been completed, the identified condition is to be kept under surveillance for indication that the identified adversity may be increasing therefore requiring more immediate corrective action.

e. Periodic review by supervisory personnel of the corrective action status of all uncorrected adverse conditions for which they are responsible.

f. Reporting conditions significantly adverse to quality to the Vice President.

We MSAER is responsible for periodically auditing GNS l and GWP corrective action. l 1

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t i OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A !

cname' 16 Rev. 31 Page 5 0F 5 1

16.4.4 vice President l The Vice President is responsible for off-site reporting of l conditions significantly adverse to quality. He is also responsible for providing periodic auditing of Manager-Safety Audit and Engineering Review corrective action.

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1 OPERATIONIB QUAUTY ASSURANCE. Southem Nudear Operating Company A JOSEPH M. FARLEY NUCIJNL PLANI.

cw 17 h 31 Page 1 OF 4

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QUhLITY ASSURANCE RECORDS l 1

I 17.1- Purpose l Mis chapter assigns responsibilities for developing, identifying, maintaining, controlling and storing records that furnish evidence of the quality of items and of activities affecting quality at

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the FNP.

17.2 Scope Records shall be maintained which show compliance of safety-related items and activities with quality requirements of applicable codes, 1 standards, regulations, license commitments, and. quality assurance l O and quality control procedures.

17.3 References j

a. 10 CFR 50, Appendix s, Criterion xvii

b. ANSI-N18.7 (1972), Sections 5.2 and 6.2.3 l

c. ANSI-N45.2.9 (1974)

d. ANSI-N45.2 (1971), section 18

e. FNP FSAR, Section 17.2.17

f. NRC Regulatory Guide 1.88 (Aug. 1974) 17.4 Background APCO's Quality Assurance Program for design and construction <

included regulrements for developing, identifying, maintaining, I controlling, storing, and retaining quality assurance records during the design and construction of FNP. Se general contractor was assigned responsibility for controlling most construction related quality records. With APCO and SNC-Farley Project 'l-concurrence some records have been permanently retained by manufacturers with provisions for access by SNC-Farley Project l l when needed. Dese records accusulated by the general '

contractor, plus others which may be subsequently identified as quality records, have been or will be turned over to SNC-Farley Project in accordance with turnover procedures which are contained. ',

] on the OQhPIL and the applicable Construction QC Manual. Informa-tion concerning records retained by manufacturers is also included I O in the turnover. Turnover provisions for quality assurance records will not only apply for original design and construction but will 1 l

also be made applicable for subsequent Major Modifications or l Additions. l 1

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A enacte' 17 Rn 31 Page g

2 or 4 17.5 Responsibilities 17.5.1 General The General Manager-Nuclear Plant, General Manager-Nuclear Support, and Manager-Safety Audit & Engineering Review shall each develop, identify, maintain, control, store, and retain records in accordance with documented procedures which include assignment of responsibilities. Their records shall provide proof that the safety-related items and OQAP activities for which they are directly responsible have been in compliance with applicable quality requirements. Their record systems shall comply with the detailed guidance in ANSI-N45.2.9 (1974) with exceptions as noted in the FSAR.

Each of the above managers shall ensure that the following records are maintained, as applicable, to his activities:

plant history; operating logs; principal maintenance and modification activities; reportable occurrences; results of reviews, inspections, tests, audits, and material analyses; monitoring of work performance; qualification of personnel, procedures,and equipment; and documentation such as !

drawings, specifications, procurement documents, calibrutior procedures and reports, and documentation concerning nonconformances, and corrective action. Repetitive type records shall be maintained in accordance with approved procedures which prescribe the content of each record and how it is to be kept. All quality assurance records are to be identified, dated and signed by the person assigned direct responsibility for keeping or making the record.

The scope of records developed and their detail shall be sufficient for reconstructing significant events.

Records shall be readily identifiable and retrievable.

Those records which may be used in maintaining, reworking, repairing, replacing, or modifying items shall be stored in readily accessible locations. Other records may be stored in lesser accessible locations depending upon the urgency of their projected usage.

Records shall be stored in facilities which are constructed, located, and secured to prevent destruction of the records by fire, flooding, theft, or deterioration by environmental conditions such as temperature and humidity. An alternate to storage in such special facilities is the maintainance of duplicate records in a separate remote location.

Access to files shall be controlled and limited.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A cw.,

17 s.* 31 Pag.

3 OF 4

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'Ihe Total Plant Numbering System shall be used for filing quality records where practical. All filing systems used shall be fully described and documented. Record controls shall includs an accountability system for records that ,

are amoved from the files. l Provisions shall be made for filing supplements to records.

17.5.2 General Manager-Nuclear Plant (GefP)

In addition to the responsibilities delineated in paragraph 17.5.1 above, the G93P shall receive and be responsible for '

controlling, storing, and retaining quality records from the i design and construction of FNP when they are turned over to j him in accordance with turnover procedures. He shall have a -

receipt control system for quality assurance records received l during the life of the plant after turnover. He shall also ;

O receive and utilize, as necessary, information concerning quality records which have been retained by manufacturers.

'Ihe GetP shall ensure that those quality records which he developed for. inspections and tests contain the following as a minimum:

a. Description of the type of observation;

b. Evidence of completing the inspection or test operations;

c. 'Ihe date and results of the inspection or test;

d. Information related to nonconformances including resolutions; 7

e. Identification of test or inspection equipment;

f. Identifications of persons performing the test or inspection and identification of the recorders;

g. A statement as to the acceptability of the test or inspection based on compliance with acceptance criteria.

17.5.3 General Manager-Nuclear Support (Gels)

In accordance with paragraph 17.5.1 above, the GetS is responsible for quality records involving those off-site O SP activities for which he is responsible.

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OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A chapter N v.

g 17 31 Page 4 or 4 17.5.4 Manager-safety Audit & Engineering Review (MSAER)

In accordance with paragraph 17.5.1 above, the.MSAER is responsible for quality records involving those OQAP activities for which he is responsible.

The MSAER is also responsible for the periodic auditing ;

of activities involving quality assurance records. l l

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t OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A Chapter lg b Page JOSEPH M. . FARLEY NUCLEAR PUNT 31 yy7 l

AUDITS j l

18.1 Purpose

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'Ihis chapter assigns responsibilities for the conduct of a I comprehensive system of planned and periodic audits and for follow- l up action on the results of the audits. Such audits.are to verify :

compliance with all aspects of the quality assurance program and >

to determine the effectiveness of the program itself. Reaudits of j deficient areas are to verify follow-up action. -

18.2 Scope Audits are to be conducted on all activities affecting safety- ,

related structures, systems, or components; on compliance with !

provisions of the NRC operating license; and on provisions of the ;

O operations Quality Assurance Program for Farley Nuclear Plant. l 18.3 References 'l

a. 10 CFR 50, Appendix s, criterion XVIII

b. NRC Regulatory Guide 1.33 (Safety Guide 33, Nov. 1972)

c. NRC Regulatc:y Guide 1.64 (Rev. 1, Feb. 1975) l

d. ANSI-N18.7 (1972), Section 4 1

e. ANSI-N45.2 (1971), section 19

f. ANSI-N45.2.11 (1974), Section 11

g. ANSI-N45.2.12 (Draft 3, Rev. 4, Feb. 1974)

h. ANSI-N45.2.23 - 1978 18.4 Responsibilities for Auditing 18.4.1 General

a. Audits are to be performed in accordance with pre-established written procedures or check lists and l conducted by trained personnel not having direct ;

responsibilities in the area being audited. ,

b. Audit results are to be documented, then reviewed with ,

management having responsibility in the area audited.

c. Responsible management shall take the necessary action i to correct the deficiencies revealed by the audit.

d. When determined to be necessary by the MSAER or SSAER, {

deficient areas shall be promptly reaudited to verify :

that corrective actions have been accomplished.

OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A cnacte' Re. Page g

18 31 2 Or 7

e. Audits shall include objective evaluations of safety-related procedural guidance, safety-related activities, and quality documents. Procedural guidance shall be evaluated for conformance with -

the OQAPM and the applicable procedures on the OQAPIL. Activities and quality documents shall be evaluated for effectiveness in the iglementation of p.rocedural guidance. Work arer.s, processes, material items,.and we'rking documents shall be evaluated as integral elements of activities.

f. Audits are to be regularly scheduled on the basis of the status and safety importance of the activities being performed. Additional audits should be conducted when any of the following occur:

(1) Significant changes are made in functional areas of the quality assurance program such as significant reorganization or procedure revision; or (2) It is suspected that overall quality of a certain item or activity is in jeopardy due to identified deficiencies; or (3) It is necessary, as determined by the MSAER or SSAER, to promptly verify implementation of required corrective actions.

18.4.2 Vice President l We Vice President will provide for a periodic audit of l the SAER Staff, including both off-site and on-site activities, to verify and evaluate compliance with responsibilities as assigned in the OQAPM.

18.4.3 Manager-Safety Audit & Engineering Review (MSAER) he MSAER is responsible for the following: l

a. We conducting of an operations quality assurance auditing program which provides comprehensive, j independent verification and evaluation of safety- !

related procedures and activities associated with Tarley Nuclear Plant. l

b. We auditing of those safety-related and other selected activities for which the SNC-Tarley Project is responsible. Included in these activities are the following:

(1) Plant operation, maintenance, modification, and repair controls.

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OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A l c* 18

31 % 3 or 7 l

l (2) The preparation, review, approval, and control of '

the FSAR, design, specifications, procurement ;

documents, instructions, procedures, and drawings. j (3) Plant tests and inspections.

(4) orientation and training programs.

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(5) Health physics and security.

(6) The implementation of operating and test procedures. ,

1 (7) Activities involved in compliance with criteria in Appendix a to 10 CFR 50.-

(8) Activities involved in compliance with the '

Facility Operating License and FSAR provisions.

i (9) Results of action taken to correct deficiencies or methods of operation that affect nuclear safety.

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(10) Results of corrective action taken in response to j SAER noncompliances. j

c. Directing the conduct of audits of FNP and SNC-Farley l Project activities at the following frequencies: l NCHE: Activities may be audited piecemeal or in accordance with a functional matrix provided that all of each area listed below is audited within the prescribed frequency.

(1) The conformance of facility operation to provisions contained within the Technical Specifications and '

applicable license conditions at least once per 12 months.

(2) The performance, training and qualifications of the entire facility staff at least once per 12 months.

(3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

(4) The performance of activities required by the operational Quality Assurance Program to meet the criteria of Appendix "a", 10 CFR 50, at least once O per 24 months.

e (5) The Emergency Plan and implementing procedures at least once per 12 months.

(6) 1he Security Plan and iglementing procedures at least once per 12 months.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapter Rev. **9' g

gg 31 4 or 7 !

l (5) ne Emergency Plan and implementing procedures at least once per 12 months.

(6) he Security Plan and iglementing procedures at ]

least once per 12 months.

(7) Any other area of facility operation considered appropriate by the NORB or tw Vice President. l (8) me Facility Fire Protection Program and iglementing procedures at least once per 24 months.

(9) An independent fire protection and loss prevention '

program inspection and audit of the unit at least once per 12 months utilizing either qualified off- ,

site licensee personnel or an outside fire I protection firm.

(10) An inspection and audit of the unit fire protection and loss prevention program by a qualified outside fire consultant at least once per 36 months. :

(11) We radiological effluent and environmental i monitoring programs and results thereof at least once per 12 months. '

(12) ne OFFSITE DOSE CALCUIATION MANUAL and implementing procedures at least once per 24 months.

(13) We PROCESS CCNTROL PROGRAM and implementing ;

procedures for solidification of radioactive i wastes at least once per 24 months. j

d. he auditing of safety-related activities performed by SNC Corporate Quality Services as services provided directly to SNC-Farley Project for Farley Nuclear Plant.

Such services int.lude those involving audits of the vendors of safety-related materials, parts, assemblies and services which support plant activities and other items as may be designated in the future. Audits of vendor activities are to verify compliance with

procurewnt documents, QA programs, procedures and activities. A comprehensive audit of SNC Corporate l Quality Services' activities shall be conducted at least once per year.

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e. Se auditing of on-site vendor services as applicable l and as commensurate with their importance to plant safety. Audits shall be conducted as soon as practical after the vendor activities have begun and a representative scope of activities can be audited.

Subsequent audits shall be conducted at appropriate intervals depending upon the csplexity and safety significance of the activities being performed.

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' OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A c* 18 "'-

31 P*M 5 or 7 i

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f. 1he auditing of safety-related activities performed by Southern Company Services, Inc. (SCS) as services ,

provided directly to SNC-Farley Project for Farley Nuclear Plant. A comprehensive audit shall be conducted at least once per year. :

g. Participating in selected audits of nuclear fuel- ;

designers and fabricators when such audits are ,

conducted by SNC. '

h. 'Ihe analyzing of audits to determine quality trends !

and the effectiveness of the QA program. Arports i of the analyses are to be submitted to the Vice President. l

i. 'Ihe submitting of sumunary reports of OCA auditing i activities and auditing results to the Vice l President via the NORB at each regularly scheduled !

NORB Meeting. l 18.5 Responsibilities for Reports of Audits and Follo W Action -

APC, SNC and SC3 Reports of all audits performed under the direction of the Vice President or under the management of the MSAER shall be forwarded to the Vice President and to the management positions responsible .

responsible for the areas audited within 30 days after completion of the audit.

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'Ihe GesP, Gees, and MSAER shall each maintain a system for follow-up action to correct noncompliances identified in audits of activities for which they are directly responsible and for reporting such action to the Vice President. 'Ihey shall review l l and investigate noncompliancer to determine and schedule appropriate corrective action including action to prevent recurrence. Each identified noncompliance is to be assigned a control designator and is to be included in follow-up action reports until corrective action has been completed. Follow-up reports shall give results of the review and investigation and include action taken to prevent recurrence. Initial reports of follow-up action for specific noncosplisnees shall be submitted within 30 days of receipt of the audit report in which they are identified. In the event that corrective actions cannot be completed within 30 days, reports shall contain scheduled dates for cespletion. 'Ihe status of follow-up action shall be reported to the Vice President l at least quarterly thereafter until the noncoupliance has been corrected and so reported' .

OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A Chapter Nw g

lg 31 Page 6 OF 7 l

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I rollow-up actions to correct noncompliances identified in audits i of nuclear fuel management by SNC shall be reported by the GMNS.

Follow-up actions to correct noncompliances identified in audits of SNC's QA program for nuclear fuel shall be reported by MSAER.

4 Copies of all corrective action reports involving noncompliances identified in SAER audits or in NRC audits shall be provided to the MSAER. Copies of reports involving corrective actions at FNP shall also be provided to the SSAER. These shall provide basis for reauditing to verify accomplishment of adequate corrective action.

18.6 Responsibilities for Reports of Audits, Inspections and Follow-up Action - Vendors Reports of all audits and inspections of vendor's services relating to the FNP which are performed under the direction of the vice President or under the management of the MSAER shall be reported to the Vice President. Reports of all such audits will also be made to the SNC management responsible for the procured service and to the applicable vendor management. Such reporting shall be made within .

30 days after completion of the audit or inspection.

Audits of vendor onsite services are to verify compliance with all provisions of the purchase order including the vendor's quality assurance program. Vendors shall be required to review and investigate each cited noncompliance and take corrective action to preclude recurrence.

Responses concerning actions to correct noncompliances cited during audits of vendor services shall be reported within 30 days ,

of receipt of the audit report. Responses shall be reported to thw MSAER except in cases of audits of onsite vendor activities controlled by the G MP. For thir exception, the vendor's corrective action shall be reported to the G MP and processed in accordance with plant corrective action reporting procedures.

Responses received by the MSAER will be evaluated for acceptability with solicitation of technical evaluations as necessary from the ,

GMNP and G MS. The MSAER will then notify the vendor of the acceptance or rejection of the corrective action. Written ,

connunications, reaudit, or other appropriate means may be used '

by the MSAER as follow-up action to close-out an audit finding.

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(~) OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A Chapter ig Rn 31 Page 7 Or 7 Responses concerning actions to correct noncompliances cited during audits of non-routine services shall be reported to the MSAER or his '

representative in the course of the audit or inspection. The MSAER or his representative shall then evaluate the response and determine its acceptability prior to the completion of the audit or inspection. )

If deemed necessary, the service shall not be accepted prior to the acceptance of all vendor corrective action.

18.7 Authority of Audit Personnel Audit personnel shall have full and continuous access to facilities, documents, and personnel as required in planning and performing ,

audits or evaluations. Audit personnel shall comply with plant procedures for safety, security, and other aspects of access. This '

access is not to interfere with the timely performance of activities necessary for plant operations.

Individual Auditors or Audit Team Leaders do not have the authority to directly stop work in progress or to stop the initiation of work.

Auditor action of this nature is to be taken through the SSAER and/or MSAER as appropriate. The SSAER and MSAER will take action as described in Chapter 2.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company a+h Chapter Rev.

JOSEPH M. FARLEY NOCLEAR P!. ANT 19 31 Page 1973 TRAINING 19.1 Purpose

'Ihis chapter establishes training requirements which will insure that persons performing activities within the purview of the 000 will attain quality in job performance and will comply with SNC-Farley Project quality policies and procedures.

19.2 scope Training requirements established for activities affecting the safety of the FNP are grouped into three categories within the OQAP:

a. Operations quality assurance orientation and training;

b. Qualifications and training for specific jobs and tasks;

c. General employee training.

19.3 References

a. 10 CFR 50, Appendix B ;

b. 10 CrR 55, Appendix A

c. NRC Regulatory Guide 1.58, Rev. 1 (September 1980)

d. NRC Regulatory Guide 1.8 (March 1971) <

e. SNT 'IC-1A and supplements - 1980

f. ANSI-N45.2.23 (1978)

g. FNP FSAR Sections 13.1, 13.2, 14.0, and 17.2.2

h. ANSI-N18.1 (1971) '

1. ANSI-N45.2.6 (1978) 19.4 Responsibilities for Operations Quality Assurance Orientation and Training SNC-Farley Project esployees below manager level shall be given orientation training concerning the purpose, scope, and implementation of the Operations Quality Assurance Program (OQAP) '

as promulgated and implemented in the OQAPM and in procedures on the OQAPIL. 'Ihey shall also be individually trained in p;ocedures .

which implement those portions of the OQAP relating to their 1 t individual jobs. Such orientation and training is to be provided at recurring intervals for new and reassigned personnel and annually as a refresher for those who have received it previously.

OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A cws 19 Rev. 31 p*9* 2 or 3 Se MSAER is responsible for providing OQAP orientation to SNC-rarley Project Corporate Headquarters personnel and as requested, the SSAER shall provide input to orientation of FNP personnel. We GMNP and GMNS are responsible for the job-related quality assurance training of their respective staffs. Quality assurance orientation and job-related quality assurance training are to be given in formal courses of instruction using prepared training material and are to be in addition to on-the-job training.

19.5 Responsibilities for Qualification and Training for Specific Jobs and Tasks Personnel shall be selected, trained, and, in certain cases, formally qualified for the performance of activities affecting quality. Responsibilities are as follows:

19.5.1 General Manager-Nuclear Plant (GPt(P)

We GPfiP will ensure that the personnel performing activities affecting quality at FNP are selected, trained, and formally qualified to perform assigned duties as follows:

a. Operating and maintenance personnel are to be selected, trained, and qualified in accordance with requirements of the following: NRC Regulatory Guide 1.8, " Personnel Selection and Training"; training requirements in 10 CFR 55; and retraining requirements in 10 CFR 55, Appendix A.

b. Inspection and test personnel who are assigned the responsibility and authority to approve inspection and test procedures, to implement these procedures, and to report and evaluate the results shall be formally l qualified to requirements corresponding to those of NRC Regulatory Guide 1.58 (references ANSI-N45.2.6). ne Gre(P shall be responsible for determining the acceptance of experience qualifications for certification as out-lined in ANSI-N45.2.6. except that reevaluations will not be conducted for persons who have not annually performed inspection, examination and testing activities in their qualified area.

c. Non-destructive Examination (NDE) personnel shall be ;

formally qualified to requirements corresponding to 1 those of SNI-1C-1A (see 19.3.e for date reference) and applicable supplements,

d. Vendor personnel shall be properly qualified to perform purchased services. Personnel qualification requirements shall be included where appropriate in procurement documents, l

s n OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A chapter Rw.

JOSEPH M. FARLEY NUCLEAR PLANT 19 37 p*G* 1 OF 3 l

TRAINING 19.1 Purpose This chapter establishes training requirements which will insure that persons performing activities within the purview of the OQAP will attain quality in job performance and will comply with SNC-Farley Project quality policies and procedures.

19.2 Scope Training requirements established for activities affecting the l safety of the FNP are grouped into three categories within the j OQAP: I

a. Operations quality assurance orientation and training;

b. Qualificati:ms and training for specific jobs and tasks; l

c. General employee training.

19.3 References I i

a. 10 CFR 50, Appendix B l

b. 10 CFR 55, Appendix A l

c. NRC Regulatory Guide 1.58, Rev. 1 (September 1980)

d. NRC Regulatory Guide 1.8 (March 1971)

e. SNr-TC-1A and supplements - 1980

f. ANSI-N45.2.23 (1978)

g. FNP FSAR Sections 13.1, 13.2, 14.0, and 17.2.2

h. ANSI-N18.1 (1971) j

i. ANSI-N45.2.6 (1978) 19.4 Responsibilities for Operations Quality Assurance Orientation and Training .

SNC-Farley Project employees below manager level shall be given orientation training concerning the purpose, scope, and 1 implementation of the Operations Quality Assurance Program (OQAP) {

as promulgated and implemented in the OQAPM and in procedures on the OQAPIL. They shall also be individually trained in procedures f which implement those portions of the OQAP relating to their i

( individual jobs. Such orientation and training is to be provided )

at recurring intervals for new and reassigned personnel and I annually as a refresher for those who have received it previously. l l

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1 OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A chapter 19 R" 31 'Pa98 2 or 3 The MSAER is responsible for providing OQAP orientation to SNC-Farley Project Corporate Headquarters personnel and as requested, the SSAER shall provide input to orientation of FNP personnel. We G NP and GMS are responsible for the job-related quality assurance training of their respective staffs. Quality assurance orientation and job-related quality assurance training are to be given in formal courses of instruction using prepared training material and are to be in addition to on-the-job training.

19.5 Responsibilities for Qualification and Training for Specific Jobs and Tasks Personnel shall be selected, trained, and, in certain cases, formally qualified for the performance of activities affecting quality. Responsibilities are as follows: ,

19.5.1 General Manager-Nuclear Plant (G M P)

We GMNP will ensure that the personnel performing activities affecting quality at FNP are selected, trained, and formally qualified to perfocia assigned duties c: follows:

a. Operating and maintenance personnel are to be selected, trained, and qualified in accordance with requirements of the following: NRC Regulatory Guide 1.8, " Personnel Selection and Training"; training requirements in 10 CFR 55; and retraining requirements in 10 CFR 55, Appendix A.

b. Inspection and test personnel who are assigned the responsibility and authority to approve inspection and test procedures, to implement these procedures, and to report and evaluate the results shall be formally qualified to requirements corresponding to those of NRC Regulatory Guide 1.58 (references ANSI-N45.2.6). The G MP shall be responsible for determining the acceptance of experience qualifications for certification as out-lined in ANSI-N45.2.6. except that reevaluations will not be conducted for persons who have not annually performed inspection, examination and testing activities in their qualified area.

c. Non-destructive Examination (NDE) personnel shall be formally qualified to requirements corresponding to those of SNr-TC-1A (see 19.3.e for date reference) and applicable supplements.

d. Vendor personnel shall be properly qualified to perform purchased services. Personnel qualification requirements shall be included where appropriate in procurement documents.

i OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A f Chapter Rev. Page 19 31 3 gy 3 t

19.5.2 General Manager-Nuclear Support (GrNS)

'Ihe Gets shall ensure that members of his staff are selected and trained as necessary to assure that suitable proficiency !

is achieved and maintained in their assigned duties. !

19.5.3 Manager-Safety Audit and Engineering Deview (MSMR) ,

'Ihe MSMR shall ensure that SMR personnel are selected and trained for the performance of their duties. Personnel assigned to duties. involving auditing shall either be '

formally qualified for such duties, or (hey shall perform l under the direct supervision of other formally qualified !

personnel. ;

i 19.6 Responsibilities for General Esployee Training i O The GetP shall ensure that all plant employees are trained in those matters which are relevant to the execution of their duties and I

I which are of special significance for plant safety. Training shall ]

be conducted in the following areas: radiological health and <

safety; industrial safety; plant controlled access areas; plant security; use of protective clothing and equipment; and applicable plans and procedures concerning health, safety, and security.

Temporary plant maintenance and services employees shall also be trained in these areas to the extent necessary to assure safe execution of their duties.

19.7 Training Records Auditable records shall be maintained which identify the content of training events conducted, the participants in the training, and an evaluation of the training event, rurther, a contro1 M record shall be maintained for each person performing activities affecting quality that documents his qualifications and major training achievsments associated with his job assignment.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A chapter Rev. g Page JOSEPH M. FARLEY MJCI.FAR PIJNr 20 1W3 l l

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CLEANLINESS AND HOUSEKEEPING 20.1 Purpose

'Ihis chapter assigns responsibilities involving housekeeping requirements and responsibilities involving control of clean-liness of reactor fluid systems and associated components.

Decontamination and cleanup of radioactively contaminated systems and components are not addressed herein.

20.2 Scope

'Ihese measures apply to safety-related structures, systems, components and their environmental areas.

20.3 References

a. 10 CFR 50, Appendix B, criterion XIII

b. NRC Regulatory Guide 1.37, which endorses ANSI-N45.2.1 (1973)

c. NRC Regulatory Guide 1.39, which endorses ANSI-N45.2.3 (1973)

d. ANSI-N18.7 (1972) Section 5.3.9

e. ANSI-N45.2 (1971) Section 14

f. FNP FSAR, Section 17.2.13 20.4 Responsibilities 20.4.1 General Manager-Nuclear Plant (Gt4P) 20.4.1.1 Housekeeping

'Ihe et4F shall establish and use procedures to ensure that proper materials, equigment, and processes are utilized in the performance of housekeeping at FNP and that the quality of safety-related structures, systems, cesponents and related activities are not degraded as a result of inappropriate housekeeping practices or techniques. Housekeeping control measures shall comply with NRC Regulatory Guide 1.39, except as noted in FSAR Appendix 3A, and with applicable provisions of ANSI-N45.2.3 and j include the following:

a. Identification and maintenance of house- l keeping control zones equivalent to those described in ANSI-N45.2.3, Section 2.1.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A Chapt *'

20 Ap.

31 Page 2 or 3 g

b. Control of tools, equipnent, materials, and supplies to prevent inadvertent introduction of deleterious materials or objects into critical systems.

c. Control of cleanliness and orderliness of work areas.

d. Control of adequate light, ventilation, protection, and accessibility for work activities.

a. Compliance with NFPA National Fire Codes for prevention of, and protection from, damage by fire,

f. Training of personnel to work in house-keeping control zones.

20.4.1.2 Cleanliness of Fluid Systems and Associated Components he GNP shall establish and use procedures to ensure that cleanliness control measur** are used for the followings to preclude ent.ry of.

deleterious contaminants into fluid systems; to preclude deleterious external contamination of fluid system components; and to remove deleterious external contamination from fluid system com-ponents if such contamination occurs. Cleanliness control measures shall comply with NRC Regulatory Guide 1.37 and applicable provisions of ANSI-N45.2.1. mey are to include the following:

a. Use of cleanliness classifications equivalent to those described in ANSI-N45.2.1, Section 3.1.

b. Development of cleaning procedures for generic classifications of material which provide for use of proper cleaning materials, equipment, and processes.

c. Requirements for inclusion of cleanliness control measures in all work procedures involving reactor fluid systems.

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. OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A

.h: chaoie' 20 h 31 Pa9* 3 or 3 l l

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d. Identification of cleanliness levels for uninstalled items which have-been cleaned and are protected to maintain their level of cleanliness.

e. Adequate control of tools used in abrasive ;

work operations to prevent contamination of '

corrosion resistant alloys by previous use on materials that could contribute to intergranular or stress-corrosion cracking.

f. Training of personnel in cleanliness control.

20.4.1.3 Procurement The GWP shall require in procurement doctaments ,

for on-site services that vendors and contractors i congly with applicable housekeeping and clean-O liness quality requiraments.

20.4.2 General Manager-Nuclear Support (GWS)

The GNS shall require in procurement documents for on-site services that vendors and contractors comply with applicable housekeeping and cleanliness quality requirements.

20.4.3 Manager-Safety Audit and Engineering Review (MSAER)

The MSAER is responsible for the periodic auditing of housekeeping and cleanliness activities.

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OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A JOSEPH M. FARZ2Y NUCIrAR PIhrt chasm 21 Nv. 31 P* 1 OF 4 INFORMATICE SYSTDtS

-t 21.1 Purpose ,

l his chapter defines the requirements for verification, documentation, I and control of information systems. An Information System is defined as the total package of hardware and software used to provide l informatien processing or plant process control. _ 2e aggregate of the operating system programs, the application programs, the hardware i processor (s), the communication links and devices, and the local and remote peripheral devices will comprise an Information System. ,

Peripheral devices for plant process computers that provide external 4 process variables shall not be considered as part of an Information System. ]

21.2 Scope This chapter applies to all Information Systems used or to be I acquired for use by the SNC-Farley Project in conjunction with l l safety-related activities. ;

l 21.3 References

a. 10CFR50, Appendix B, criterion v l

b. ANSI-N413 (1974)

c. NGD-D4 Information Systems Control 21.4 Responsibilities 21.4.1 General Manager - Nuclear Plant (GFtIP) he GretP shall establish and maintain procedures which i ensure proper validation, documentation, and control of l information systems utilized in conjunction with safety-related activities at FNP. Wese procedures shall provide for the following:

21.4.1.1 validation Information systems shall be independently verified by demonstration of their ability to O produce results closely matching bench mark solutions.

OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A h enapter Rev. Page 21 31 2 gg. 4 21.4.1.2 Documentation

a. General Documentation, to assure technical quality and appropriate use of information systems shall include, as appropriate: System Hardware Configuration Descriptions, User Information, Abstract and hooretical Information, validation Information, Programming Standards, and Programming Information. Wese documents may be separate or combined and may be in the form of drawings, procedures or manuals. Plant ,

originated information and vendor manuals which constitute portions of procedures shall be approved and issued in accordance with OQAPM Chapter 5.

When a system is modified, review and approval of documentation changes shall be as appropriate to the significance of the system.

b. User Information his document shall consist of instructions or information required for effective system operation.

c. Abstract and meoretical Information System objectives, capabilities, limitations, descriptions of models, algorithms, techniques, data, and references shall be included in this document as appropriate.

d. Programming Information his document shall contain information to facilitate modification and/or enhancement of programs. Such information shall include flowcharts, listings, requirements, and constraints as applicable.

e. Validation Information mis document shall describe the validation method (s) and options utilized for system validation or verification. his may additionally include descriptions of test problems, key parameters, test data and reprints of inputs and results, bench mark solutions, and corrective actions taken as a result of errors or deficiencies identified via CC 3Drison and evaluation.

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OPERATIONS QUAUTY ASSURANCE Southern Nudear Operating Company A Chapter Rev. Page 21 31 3 gy 4 Validity of systems and components procured by SNC-Farley Project from a Vendor may be l demonstrated via a Statement of Conformance to the vendor's systen design specification and vendor's internal Quality Assurance Program. Documented evidence of system or specific program validation shall be maintained.

f. Programming Standard This doctament shall be generic information and guidance for development, modification, and maintenance of system programs.

21.4.1.3 Control

a. Change Control System changes shall be implemented only after adequate testing, review, and approval in accordance with procedures or information approved and issued under the guidance of OQAPM Chapter 5. Upon modification, validation shall be performed per Section 21.4.1.2.e. If system and/or documentation modifications may invalidate previous results,

. appropriate personnel shall be notified to assure that appropriate action is taken.

b. System Changes changes to the system hardware or software programs that may affect system results shall be demonstrated to have.no adverse effect on system operation by the initiation and documentation of pre-selected test problems or programs. Documented evidence of test problem results shall be maintained.

c. System Security Integrity Measures shall be established to ensure security to preclude purposeful or inadvertent impairment of an information system's operation.

Approved alternate system analytical techniques for system functions shall be provided in procedures and appropriate personnel shall be properly trained in their use.

OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A g Chapter 21 Rev. Page 4 op 4 31 21.4.2 General Manager-Nuclear Support (GMNS) he GMNS shall ensure that appropriate documented guidance is properly implemented by Nuclear Support personnel to achieve the same requirements that are mandated of Parley Nuclear Plant personnel in paragraph 21.4.1.

21.4.3 Manager-Safety Audit and Engineering Review (MSAER)

We MSAER is responsible for periodic auditing of information system controls.

We MSAER shall audit to verify that appropriate documented guidance is properly implemented by Nuclear Support personnel to achieve the same requirements that are mandated of rarley Nuclear Plant personnel in paragraph 21.4.1.

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i j OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY !0 CLEAR FIAIC Ch*p

MMY Rev.

31 Page 1 Or 8 4

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GLOSSARY Acceptance - De act of an authorized representative of an organization by which that organization' assumes for itself, or as an agent of another, ,

ownership of existing and identified supplies tendered, or approves specific services rendered, as partial or complete performance of a '

contract on the part of the supplier. ;

Acceptance criteria - A limit or limits placed on the variation permitted l in the characteristics of an ites expressed in definitive engineering terms !

such as dimensional tolerances,-chemical composition limits, defects, ,

temperature ranges, time limits, operating parameters, and other similar l characteristics. '

Accept as is - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse i conditions and that the item under consideration will continue to meet i all engineering functional requirements including performance, maintain- l ability, fit and safety.

Approval - An act of endorsing or adding positive authorization or both. ,

1 Appurtenance - A part that is attached to a component which has been l completed. l As-auilt Data - Documented data that describes the condition actually .l achieved in a product. '

Assembly - A combination of subassemblies or components, or both, fitted together to form a unit.

Audit - An activity to determine through investigation, the adequacy of, and adherence to, established procedures, instructions, specifications, codes, and standards or other applicable contractual and licensing requirements, and the effectiveness of implementation. An audit does not include source surveillance or inspection for the purpose of process control or acceptance of materials or items.

Auditable Record - Information which is documented and organized so as to be readily understandable and traceable to permit independent verification.

Basic component - A plant structure, system, component or part thereof necessary to assure (i) the integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (iii) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10CFR100.ll. his includes design, inspection, testing, or consulting 1

. services important to safety that are associated with the component hardware, whether these services are performed by the component supplier or others.

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A Chapter GMSSARY Rev. 31 Page 2 QT 8 g

Calibration - Adjustment of test instrumentation or equipment so that the accuracy and performance meets or exceeds the manufacturer's specifications.

Calibration Check - Verification that test instrumentation and equipment performance and accuracy meets or exceeds the manufacturer's specifications.

No major adjustments are performed as part of a calibration check.

Carrier - The transporting agency.

Certificate of conformance - A written statement, signed by a qualified party, certifying that items or services couply with specific requirements.

Certificate of Compliance - A written statement, signed by a qualified party, attesting that the items or services are in accordance with specified requirements and accompanied by additional information to substantiate the statement.

Certified Test Report - A written and signed document, approved by a qualified party, that contains sufficient data and information to verify the actual properties of items and the actual results of all required tests.

Certification - We action of determining, verifying and attesting, in writing, to the qualifications of personnel or material.

Characteristic - Any property or attribute of an item, process, or service that is distinct, describable, and measurable, as conforming or ntn-conforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings which describe the item, process, or service.

Checks - The tests, measurements, verifications or controls placed on an activity by means of investigations, comparisons, or examinations to determine satisfactory condition, accuracy, safety, or performance.

Class I Equipment - Equipment that is essential to the safe shutdown and isolation of the reactor or whose failure or damage could result in significant release of radioactive material.

Class IE Electric Systems - See Safety-Related Electrical Equipment.

Classification - he organization of items according to their susceptibility to damage during shipping, receiving and storage only. It does not relate to the function of the item in the completed system.

Cleaning - he removal of any contaminants that might have a deleterious effect on plant safety and reliable operation.

Cle mness - A state of being clean in accordance with predetermined standards, and usually implies freedom from dirt, scale, heavy rust, oil or other contaminating impurities.

Cosponent - A piece of equipment such as a vessel, piping, pump, valve, or core support structure which will be combined with other components to form an assembly.

) OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A chapter @ SSARY A*'

31 N' 3 or 8 l l

l Construction Phase - A period which commences with receipt of items at the !

construction site and ends when the cornponents and systems are ready for (

turnover to operations personnel. I contamination - Any undesirable foreign material on the surface of an item, I in the atmosphere, or in process liquids or gases. l Contaminants - Foreign materials such as mill scale, dirt, oil, chemicals, and any matter that renders a fluid, solid or surface impure and unclean according to preset standards of acceptable cleanness.

Contractor - Any organization under contract for furnishing items or l services. It includes the terms vendor, Supplier, Subcontractor, rabricator and sub-tier levels of these where appropriate. l Defective Material - A material or component which has one or more l characteristics that do not comply with specified requirements.

p Design (used as a verb) - Tect:nical and management processes which lead l Q to and include the issuance of design output documents such as drawings, specifications and other documents defining technical requirements and configurations of structures, systems and components.

Design Basis Event - See Safety-related Electrical Equipment.

Design Input - Those criteria, parameters, bases or other requirements upon which detailed final design is based.

Deviation - A nonconformance or departure of a characteristic from specified requirements.

Documentation - Any written or pictorial information describing, defining, specifying, reporting or certifying activities, requirements, procedures, or results.

Drawing - A pictorial or diagrammatical representation of a structure, system, or component which depicts quality requirements.

Electrical Equipment Inportant to Safety - All safety-related and non-safety related electrical equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in the safety-related electrical equipment definition.

Engineering Limitations - Restrictions which, if disregarded, may result in damage to the item, shortening the life of the item, or preventing the item l from functioning as intended. l

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Examination - An element of inspection consisting of investigation of materials, components, supplies or services to determine conformance to those specified requirements which can be determined by such investigation. I Examination is usually nondestructive and includes simple physical manipulation, gaging, and measurement. ;

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapter GIDSSARY A** * *9' g

31 4 or 8 External Audits - Audits of those portions of an organizations' quality assurance program not retained under its direct control and not within its organizational structure.

External Design Interface - Relationship between design groups fre.

cifferent companies. Examples are the interfaces between the plant owner and the architect-engineer or the plant owner and the NSSS (Nuclear Steam Supply System) supplier, or the architect-engineer and the NSSS supplier.

Guidelines - Particular provisions which are considered good practice but which are not mandatory. 'Ihe term "should" denotes a guideline; the term "shall" denotes a mandatory requirement.

Handling - An act of physically moving items by hand or mechanical means, but not including transport modes.

Inspection - A phase of quality control which by means of examination, observation or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.

Inspector (State or Code) - A qualified inspector employed by a legally constituted agency of a municipality or state of the United States, or Canadian Province, or regularly esployed by an Authorized Inspection Agency and having authorized jurisdiction at the site of manufacture or installation.

Inspector (owner's or Installer's) - A qualified inspector employed by the owneror Installer whose duties include the verification of quality related activities or installations or both.

Inspection Hold Point - A specified point in c work procedure which requires witnessing or inspecting by an inspec. tor, beyond which work is not to proceed without inspector approval.

l Instruction - A document which specifies areas such as conduct of business, operating ghilosophy, or management policies. An instruction may be limited in scope, period of applicability, or both.

Item - Any level of unit assembly, including structure, system, subsystem, subassembly, component, part, or material.

Internal Audits - Audits of those portions of an organization's quality assurance program retained under its direct control and within its organizational structure. ,

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Internal Design Interface - Relationship between design groups or organizations within a conpany. l Manufacturer - One who constructs any class of couponent, part, or appurtenance to meet prescribed design requirements. ,

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h Southem Nudear Operating Company A Q OPERATIONS QUALITY ASSURANCE chap'"

GLOSSARY

31 Pge 5 0F.8 ;

Major Modification or Addition - Design change, alteration and/or addition to a safety-related ites which is beyond the scope of the Plant and !

Corporate Headquarters' staffs, which involves a turnover (relinquish control) of that safety-related item from the SNC-Farley Project to Alabama Power Company Construction Department, and/or a turnover of a completed !

safety-related item from Alabama Power Company to SNC-Farley Project. l j Material - A substance or cembination of substances forming components, i parts, pieces, and equipment items. (Intended to include machinery, castings, liquids, formed steel shapes, aggregates, cement, etc.) ;

Measuring and Test Equipment - Measuring and test instruments which are used in the measurement, inspection, or monitoring of safety-related-components, systems, and structures, j Mechanical Items - Parts, components, or systems that function primarily for pressure retaining, mass moving, or heat exchange purposes. Examples !

of mechanical items are rotating equipent (motors, pumps, blowers), .

t handling equipent (crates, hoists, conveyors), coolant systems, fuel handling systems, and waste effluent systems. ;

t Modification - A planned change in plant design or operation and i accomplished in accordance with the requirements and limitations !

of applicable codes, standards, specifications, licenses and pre- ;

determined safety restrictions. j Noncompliance - A deficiency in complying with requirements l involving quality assurance. ,

Nonconformance - A deficiency in characteristic, documentation, or )

procedure which renders the quality of an item unacceptable or '

indeterminate. Examples of nonconformance include: physical or workmanshi defects; test failures; incorrect or inadequate documentat on; and deviations from prescribed processing, inspection, or test procedures.

Objective evidence - Any statement of fact, information, or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements, or tests which can be verified. ,

l owner - Alabama Power Company ;

1 Package - A wrapping or container including its contents of material or equipment.

O Packaged Unit - An assembly of iteras and parts which can be disassembled without destroying the integrity of the individual parts.

Part - An ites which has work performed on it and which is attached to TiiTbecomes a part of a component before completion of the component.

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1 OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A g Chapter G W SARY Rev. 31 Page g gy g Plant - We equipnent, piping, structures, buildings and property that !

comprise an installation or facility.

Procedure - A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used and sequence of operations.

Procurement Documents - Contractually binding documents that identify and define the requirements which items or services must meet in order to be considered acceptable by the purchaser.

Project - A planned series of activities including all actions necessa*.,f to provide, utilize, and maintain a facility or portion thereof.

Purchaser - h e organization or orge.nizations responsible for issuance and administration of a contract, subcontract, or purchase order.

Qualification (Personnel) - h e characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.

Qualified Party - A person or organization competent and recognized as knowledgeable to perform certain functions.

Qualified Procedure - A procedure which incorporates all applicable codes and standards, manufacturer's parameters, and engineering specifications and has been proven adequate for its intended purpose.

Quality Assurance - All those planned and systematic actions necessary to provide adequate confidence that an item or a facility will perform satisfactorily in service.

Quality Assurance Record - Records which are maintained to show compliance of safety-related items and activities with quality requirements of applicable codes, standards, regulations, license commitments, and quality assurance or quality control procedures.

Quality control - mose quality assurance actions which provide a means to control and measure the characteristics of an item, process, or facility to established requirements.

Receiving - Taking delivory of an item at a designated location.

Repair - he process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is uninpaired, even though that item still may not conform to the original requirement.

Report - Something (document) that gives information for record purposes.

Rework - me process by which a nonconforming item is made to conform to a prior specified requirement by coupletion, remachining, reassembling or other corrective means.

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OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A Chapter GLOSSARY Rev.

31 P89' 7 or 8 i

Safety-Related Activities - Mose activities which affect the safety- I related functions of safety-related structures, systems and components. l Wese activities include both the performing functions of attaining l quality objectives and the quality assurance functions. I l

Safety-Related - Rose plant features necessary to assure the integrity i of the reactor coolant pressure boundary, the capability to shut down l the reactor and maintain it in a safely shut down condition, or the j capability to prevent or mitigate the consequences of accidents which l could result in off-site exposures comparable to the guideline exposures !

of 10CTR Part 100. i Safety-Related Electrical Equipment - Equipment that is relied upon to remain functional during and following design basis events to ensure l (i) the integrity of the reactor coolant pressure boundary, (ii) the '

capability to shut down the reactor and maintain it in a safe shutdown condition, and (iii) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the 10 CFR Part 100 guidelines. Design basis events are defined as conditions of normal operations, including O anticipated operational occurrences, design basis accidents, external events, and natural phenomena for which the plant aust be designed to ensure functions (i) through (iii) of this paragraph.

Source - A manufacturing shop where parts are either fabricated or joined into a component; it is the last place where optinum inspection (for those items requiring in-process inspections) or other means of verifying compliance with procurement documents can be conducted.

Source Surveillance - A review, observation, or inspection for the purpose of verifying that an action has been accomplished as specified at the location of material procurement or manufacture.

Special Processes - A process the results of which are highly dependent on the control of the process or skill of the operator, or both.

Specification - A concise statement of a set of requirements to be satisfied by a product, a material or process indicating, whenever appropriate, the procedure by means of which it may be determined whether the requirements given are satisfied.

Spot Audits - Audits of a limited scope within a narrowly defined area.

Standard - he result of a particular standardization effort approved by a recognized authority.

r Storage - he act of holding items at the construction site or in an ;

t area other than its permanent location in the plant. l Storage racilities - Warehouse or yard area designated and prepared for holding of items.

Subsystem - A group of assemblies or components or both combined to perform a single function.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A g chaow GLOSSARY Rev. 31 Page g og g System - A group of subsystems united by some interaction or inter-dependence, performing many duties, but functioning as a single unit.

System Performance Test - A test performed on a completed system including electric, instrumentation, controls, fluid and mechanical subsystems under normal or sinalated normal process conditions such as temperature, flow, level, and pressure.

l Temporary Alterations - Temporary changes to components or systems made in l order to facilitate maintenance or testing.

i l Testing 'Ihe determination or verification of the capability of an item l to meet specified requirements by subjecting the item to a set of physical, l chemical, environmental or operating conditions.

l l Transit - A state of being conveyed or transported from one place to another.

l Transit carrier (open) - Trucks, trailers, railroad cars, barges, aircraf t or ships which do not afford items protection from the environment.

Transit carrier (closed) - Trucks, trailers, railroad cars, barges, aircraft, E ~ ships which provide protection of items from the environment by nature of their closed design.

Transportation Mode - A method identified by the conveyance used for transportation of items and includes any motor vehicles, ships, railroad cars, or aircraft. Each cargo carrying body (trailer, van, boxcar, etc.)

is a separate vehicle.

Trip Point - A predetermined critical level at which a bistable device changes state to indicate that the quantity under surveillance has reached the selected value.

Verification - An act of confirming, substantiating and assuring that an activity or condition has been implemented in conformance with the specified requirements.

Wrap - A flexible material, formed around the item or package to exclude dirt and to facilitate handling, marking or labeling.

( OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A JOSEPH M. FARLEY NUCIIAR Pggr chapte' APPENDIX A Rev. 31 Page 1 op i Q-LIST i

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I This O-List has been deleted and the TSAR Q-List is to be used. J l

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O o aarioa= ouau'v ^==ua^ac= 5 uthem Nudear Operating Company A Ch*8 APPENDIX B Re* 31 Pag' 1 OF-6 JOSEPH M. FARLEY NUCLEAR FIhrf i

NUCLEAR OPERATICNS REVIDi BOARD CHARTER l t

A. Introduction The Nuclear Operations Review Board (NORB) functions as an advisory board to the Vice President on safety-related matters. It conducts l independent reviews of safety-related matters and makes reports of ,

~

findings and recommendations to the Vice President. Its purposes l include the following to verify that certain aspects of plant operation are in accordance with license provisions; to review significant proposed changes to procedures, equipment, or systems; to review certain proposed tests and experiments; to verify that ,

reportable events are investigated and corrected in a manner that reduces the probability of recurrence of such events; to identify O trends indicative of decreasing plant safety; and to make recommendations for improvements both in plant operation and in effectiveness of operations quality assurance. To help it function effectively, the NORB will be kept informed on all matters for which it has review responsibilities and on the disposition of matters on which it has reported.

We NORB became functional at the first regularly scheduled meeting on August 28, 1974.

B. Background No advisory groups function to provide a system of reviews of safety-related Nuclear Plant Matters. Se Plant Operations Review.

Committee (PCRC) is an on-site review group serving as an advisory body to the General Manager-Nuclear Plant. Be Nuclear Operations Review Board (NORB) is an independent off-site review group serving as an advisory body to the Vice President. l In general the PORC conducts the initial review of all matters within the purview of the two committees. . We PORC recommendations are used by the General Manager-Nuclear Plant in making his management ,

decisions. he General Manager-Nuclear Plant forwards the minutes of PORC meetings and other reports of reviewed matters, including his actions upon PORC recommendations, to the Vice President l via the line of management and the NORB. We NORB conducts a second level review, then makes its reconnendations to the Vice President-O Nuclear who takes appropriate action to close out the matters.

For certain matters within the reviewing responsibilities of the PORC and the NORB, the General Manager-Nuclear Plant may take implementing i or approval action before the matters are reviewed by the NORB.

i av m- n wi - - _ - _ - _ _ - - _ - - - - - - - - - _ - _ _ - _ - _ _ _ . - _ . _ .

OPERATIONS QUAUTY ASSURANCE Southem Nuclear Operating Company A g ena* APPDDIX B Rev. 31 Pa9' 2 Or 6 C. Function he tops shall function to provide independent review and audit of designated activities in the areas of:

1. Nuclear power plant operations

2. Nuclear engineering

3. Chemistry and radiochemistry

4. Metallurgy

5. Instrumentation and control

6. Radiological safety

7. Mechanical and electrical engineering

8. Quality assurance practiws D. Membership

1. W e board shall consist of at least four (4) persons including:

(a) Chairman (Vice President)

(b) vice Chairman (Gereral Manager-Nuclear Support)

(c) Secretary (Manager-Safety Audit & Engineering Review)

(d) Member (General Manager-Nuclear Plant) and other appointed personnel having an academic degree in an engineering or physical science field. Each shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas listed in item C above.

2. Members in addition to those indicated by position above shall be designated in writing by the Vice President. l

3. Special consultants with expertise in specialty areas will be utilized for review of matters in those areas as assigned by the Chairman. Such special consultants shall not be considered members of the ! ORB.

4. he NCRB Chairman is responsible for assuring that these qualification requirements are met and maintained over the service life of the facility.

E. Scheduling of Meetings Meetings shall be designated as Scheduled or Unscheduled:

1. Scheduled Meetings: A written agenda will be prepared and mailed to each member prior to convening. Information on topics to be discussed will also be sent to each member for prior study before the meeting. Scheduled meetings will be held at least once per six months.

2. Unscheduled Meetings: mese meetings shall be called by the Chairman or the Vice Chairman in the Chairman's absence.

I OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A chapte' APPENDIX B Ret 31 N' 3 or 6

r. Quorum A quorum shall consist of the Chairman or Vice Chairman plus enough voting members to constitute a majority of the ! ORB, with no more than a minority of the quorum having line responsibility for operation of the nuclear plants. For the purpose of a quorum those considered to have line responsibility will include the General Manager-Nuclear Plant and personnel reporting to General Manager-Nuclear Plant.

G. Alternates Alternates, who shall be restricted to meeting legitimate and unavoidable absences of committee members, shall be appointed in writing by the Board Chairman to serve on a temporary basis; how-ever, no more than two alternates shall participate as voting members in FORB activities at any one time. They shall have an equal vote with permanent board mambers.

H. Board Action Procedure

(

(3) Recommendations will be made by the NORB on all items referred to and reviewed by the Board. A majority vote will be necessary for any recommendation. Voting of each individual member will be recorded in the minutes. In all instances the Chairman will exercise a vote only if the decision is deadlocked. If for rome reason the chairman is not present, the same rule will apply to the Vice Chairman. If the necessity arises, votes may be received by phone from Board Members.

I. Specific Matters to be Reviewed

1. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in Section 50.59, 10CrR.

2. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10CrR.

3. Violations of codes, regulations, orders, Technical

.3pecifications, license requirements, or of internal

! procedures or instructions having nuclear safety significance or abnormal degradation of systems designed to contain radio-active material.

4. Significant operating abnormalities or deviations from normal and expected performance of plant equipnent that affect nuclear p safety.

b 5. ALL REPORTABLE EV MIS as defined in the TNP Technical Specifications.

6. Recognized indications of an untnticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

I AiWh OPERATIONS QUALITY ASSURANCE Southern Nuclear Operating Company A g Chapter APPENDIX B Reo 31 Page 4 gy g

7. Reports and meeting minutes of the PORC.

8. Proposed changes to Technical Specifications or the Operating License.

9. me safety evaluations for proposed 1) procedures 2) changes to procedures, equipment, or systems and 3) tests or experiments completed under the provisions of 10CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.

J. Review of Audits

1. We following audits shall be conducted under the direction of Manager-Safety Audit and Engineering Reviews l

a. We conformance of plant operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. We performance, training, and qualifications of the entire facility staff at least once per 12 months.

c. W e results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months. ,

d. We performance of all activities required by the Operations Quality Assurance Program to meet the criteria of Appendix "B", 10CTR50 at least once per 24 months.

e. me racility Emergency Program at least once per 12 months.

f. me Facility Security Plan at least once per 12 months.

g. Any other area of facility operation considered appropriate by the NORB or the Vice President. l

h. The racility Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program i inspection and audit of the unit at least once per 12 months utilizing either qualified offsite licencee personnel or an outside fire protection firm.

A OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A V cnap* APPENDIX B

31 Pa" 5 or 6

j. An inspection and audit of the unit fire protection and loss prevention program by a qualified outside fire consultant at least once per 36 months.

. k. We radiological effluent and environmental monitoring =

programs and the results thereof at least once per 12 months.

1. We orr-SITE DOSE CALCUIATION MANUAL and iglementing procedures at least once per 24 months.

m. We PROCESS CONTROL PROGRAM and implementing procedures for solidification of ra etive wastes at least once per 24 months.

2. At each scheduled NORB meeting, the Manager-Safety Audit and Engineering Review shall make a summary report of the above audits.

K. Authority he NORB shall report to and advise the Vice President on those l areas of responsibility specified in Sections I and J above.

L. Records and Reports Minutes shall be prepared and retained for all scheduled or unscheduled meetings of the NORB. All documentary material reviewed shall be identified in the minutes. We minutes shall be approved by the Chairman and submitted to the Vice President within fourteen days following each meeting. We minutes will be acknowledged by the Vice President and returned to the Secretary for permanent retention as a record of the NORB's activities. Copies of approved minutes will be provided to all NORB members.

Se results of each review conducted by the board shall be reported via the minutes in the form of a statement to the effect that a review of a certain matter was completed, following by recommendations resulting from that review. Se document used to bring the matter before the NORB for review shall be referenced or attached.

In taking action on certain matters reviewed by the NORB, the Vice President malat ensure that reports are submitted to, or approval l

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c) reportable events must be submitted to NRC. NRC approval must be obtained before implementing any action involving an unreviewed safety question or changes to Technical Specifications or NRC licenses.

OPERATIONS QUAUTY ASSURANCE Southern Nuclear Operating Company A cwter APPDOIX B Rev.

31 Page g op g g

JOSEPH M. FARLEY NUCLEAR PLAfft i

M. Subecesittees he Chairman may appoint subecmanittees as required for designated activities which will be reported to and/or acted on by the tORB.

We Chairmen of subconnaittees will be members of the NORB.

N. Revisions of Charter his charter may be revised or amended by the Chairman on the consent of the NORB, subject to license provisions, approval of the vice President, and approval of the NRC if required. Se Chairman is l responsible for assuring that such revisions and amendments are properly documented.

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OPERATIONS QUAUTY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARLEY NUCLEAR PIANI N* APPENDIX C Re* 31 Page 1 OF 4 PLANT OPERATIONS REVIEW COMMITTEE CHARTER

1. Function he Plant Operations Review Cousaitte (PORC) shall function to advise the General Manager-Nuclear Plant on matters related to nuclear safety as described within this charter. De PORC became ,

functional on June 13, 1974. l

2. Membership me PORC shall be composed of the: l l

Chairman: General Manager-Nuclear Plant O

j vice Chairman: Assistant General Manager-Plant Operations Member: Assistant General Manager-Plant Support i Member: Operations Manager l Member Technical Manager l Member: Maintenance Manager j Member: (non-voting) Supervisor-Safety Audit and' Engineering Review l Member Performance and Planning Manager Member: Plant Modifications Manager

3. Alternates All alternate members shall be appointed in writing by the PORC 4 Chairman to serve on a temporary basis; however, no more than I one alternate shall participate as a voting member in PORC activities at any one time.

4. Meeting Frequency me PORC shall meet at least once per calendar month and as ,

convened by the PORC Chairman or Vice Chairman.

5. Quorum j A quorum shall consist of the Chairman or Vice Chairman and three l voting members including alternates. l l

6. Responsibilities he PORC shall reviews

a. All administrative procedures and changes thereto.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A $

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b. 'Ihe safety evaluations for 1) procedures; 2) changes to procedures, equipment or systems; and 3) tests or erperiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question and all programs required by Technical Specification 6.8 and changes thereto.

c. Proposed procedures and changes to procedures,' equipment, or systems which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed tests or experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

e. Proposed changes to Technical Specifications or the Operating License,

f. Reports of violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance or reports of abnormal degradation of systems designed to contain radio-active material.

g. Reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

h. All REPORTABLE EVENTS as defined in the FNP Technical Specifications.

i. All recognized indications of an unanticipated deficiency in sees aspect of design or operation of safety-related structures, systems, or components.

j. The Plant Security Plan and changes thereto.

k. 'Ibe Emergency Plan and changes thereto.

1. Facility operations to detect potential nuclear safety hazards.

m. Performance of special reviews, investigations. or analyses and reports thereon as requested by the Chairman of the Nuclear operations Review Board.

n. Every unexpected on-site release of radioactive material to the environs resulting from a lack of preplanning including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence to the General Manager-Nuclear Plant and ;

l to the Nuclear Operations Review Board.

OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A Chapt *' APPDOIX C Re* 31 **9' 3 Or 4 -

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o. Changes to the PROCESS CormtOL PROGRAM and the Orr-SITE DOSE l CALCUIATICN MANUAL.

p. The acceptance of safety-related material that has been ;

identified in nonconformance reports and that has been j accepted "as is".

7. Authority .

We PORC shall:

a. Recommend to the General Manager-Nuclear Plant written approval or disapproval of items considered under 6.0 (a) through (e),

(j), (k), (o), and (p) above.

b. Make recommendations to the General Manager-Nuclear Plant in O writing with regard to whether or not each item considered under 6.0 (a), (c), and (d) above constitutes an unreviewed l

l safety question. l

c. Make recommendations to the General Manager-Nuclear Plant in writing that actions reviewed under 6.0 (b) above did not constitute an unreviewed safety question.

d. Advise the General Manager-Nuclear Plant concerning the adequacy of items reviewed under 6.0 (a) above.

e. Make recommendations to the General Manager-Nuclear Plant in writing that the investigative actions and corrective actions have been adequate for items reviewed under 6.0 (f) through (i) and (n) above.

f. Advise the General Manager-Nuclear Plant on the recognition of any condition or activity indicative of a potential nuclear safety hasard for those items reviewed under 6.0 (1) above. l 1

8. PORC Action Procedure he Chairman or Vice Chairman is responsible for assigning PORC activities. Se PORC Secretary, Generating Plant Engineer- !

Supervising (Licensing), is responsible for preparing the meeting l agenda. Recommendations of approvals of an item under consideration 1

(~% require the agreement of a majority of the comunittee. We PORC V Chairman may appoint subconsnittees as required for assisting with matters which will be reviewed by the PORC. Se Chairman i

l of a subcommaittee will be a voting member of the PORC.

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9. Records

a. We PORC shall be responsible for maintaining a continuing record of the activities of the Committee in the form of minutes and reports.

b. We proceedings at each regular or special meeting of the PORC will be documented in written minutes. Wese minutes are an official plant record and are stored permanently in the plant files. heir content will include, but is not limited to the following: PORC meeting agenda; subcomunittees assigned; attendance; reviews performed; and connaittee evaluations and recommendations.

c. Se agenda of special meetings may be abbreviated or modified with respect to time or other considerations, and this will be reflected in the minutes.

d. We minutes will be approved by the PORC Chairman and, along O with applicable incident reports, letters, and other attached documents will be distributed to the plant file, Vice President l and NORB Secretary.

10. Revision to Charter Charter revisions or amendments may be initiated by the General Manager-Nuclear Plant. Wese revisions or amendments are subject to review by the NORB, approval by the NRC if required, and final approval by the vice President. l l

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OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A JOSEPH M. FARIEY NUCIIAR PLANT ch e er **

APPENDIX D 31 1 OF 3

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BALANCE OF PLANT QUALITY ASSURANCE PROGRAM

1. Purpose he purposes and principle objectives of the Balance of Plant Quality Assurance Program (BOPQAP) are to help ensure safe operation and to enhance the reliability and overall performance of the rarley Nuclear Plant (TNP). Implementation of the program will help to minimize transients that could damage equipment or lead to challenges of the safety systems.

2. Scope he BOPQAP includes structures, systems, and cruponents that are designated in Attachment I and that are outside the scope of the (ov) OQAP. We extent of control over activities will be consistent with their importance to plant reliability and performance.

We BOPOAP is subordinate to and supportive of the OQAP. We application and requirements of the OQAP take precedence over the BOPQAP. Accordingly, no provision of the BOPQAP shall be interpreted to allow any reduction or exception to the controls for structures, systems, components, and activities within the scope of the OQAP.

3. References

a. INPO Good Practice OA-104, October 1985. l

4. Program Structure he DOPQAP is structured to assure that the IHP is operated and maintained according to established engineering criteria in keeping with plans approved by Management.

5. Responsibilities 5.1 The General Manager-Nuclear Plant (GMNP)

We GPNP is responsible for assuring that Balance of Plant (BOP) activities are identif:.ed and performed to ensure safe f operation and to enhance the reliability and overall performance of rarley Nuclear Plant. He reports to the Vice President. l

a OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A Chapter APPENDIX D Rev. %e 2 gy 3 g j 31 i

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l He is responsible for all procurement, handling, stcrage, cleaning, testing, training, operation, maintenance, modification, radiological protection, cleanliness and housekeeping, chemistry, fire protection, document control, preventive maintenance, inspection, security, and quality control associated with the BOP at FNP. His specific responsibilities involving BOP Quality Assurance includes

a. Verifying that installed equipment and systems will perform in accordance with design and will achieve a high level of reliability.

b. Develop and maintain administrative procedures to establish and control safe operation and to achieve high reliability of the BOP.

c. Maintain effective quality control over BOP activities.

5.2 General Manager-Nuclear Support (GMNS)

The GMNS is responsible for managing off-site support for plant operation and administration to ensure safe operation and enhance reliability and overall performance of FNP activities.

Activities such as insurance inspection, personnel administration, design changes, special projects, vendor liasons, certain procurement acticns, and budget controls are within his area of responsibility. He reports to the Vice President. l 5.3 Manager-Safety Audit and Engineering Review (MSAER)

The MSAER is reLponsible for conducting an operating quality assurance audit program on the BOP which provides independent verification and evaluation of BOP accivities to ensure safety and to enhance reliability and overall performance of INP.

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Southem Nudear Operating Company d

({} OPERATIONS QUALITY ASSURANCE

.C w w APPENDIX D Rev.

31 **9' 3 or 3 Structures, Systems and Components Included in BOPCAP l ATD4HENT I Structures narbine Building Service Building Service Building Annex Utility Building Dnergency operations racility (m.3 Training Center Security Building Defensive Positions and other Security Structures Low Level Radioactive Waste Building Water Treatment Plant Fire Pump House Cooling Towers and Circulating Water Canals switchhouse Meteorological Tower and Building Warehouse ard Storage Areas River Water Structure Systems and Components All non-safety related equipnent in the Containment Buildings, Auxiliary Buildings, Service Water Structure, and Diesel Building.

All equipnent in the Turbine Building, Water Treatment Plant, Fire Pumphouse, River Water Structure, Switchhouse, and Switchyards.

Southem Nudear Operating Company A (v! OPERATIONS QUALITY ASSURANCE JOSEPH M. FARLEY NUCLEAR FIRTT Chapte' APPENDIX E Rev. 31 P89' 1 OF 6 e

SPECIAL OCA PROGRAM APPLICATICNS Forward The extent to which the Joseph M. Farley Nuclear Plant Operations Quality Assurance Program applies to the following non-safety related areas is described in this appendix:

a. Security

b. Fire Protection es c. Radiological Environmental Monitoring

d. Radioactive Waste Handling and Shipping References

1. 10CFR Part 73

2. 10CFR Part 50, Appendix R

3. Joseph M. Farley Nuclear Plant Fire Protection Program Re-evaluation

4. 10CFR Part 100

5. 10CFR Part 71, Sub-Part H l

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OPERATIONS QUALITY ASSURANCE Southem Nuclear Operating Company A Chapter APPDOIX E Rw. 31 Page 2 OT 6 g

MATRIX FOR CHAPTERS OF THE JOSEPH M. FARLEY NL, GEAR PIANT OPERATICNS QUALITY ASSURANCE PROGRAM MANUAL APPLICABLE TO FIRE PROTECTION, SECURITY, RADIOACTIVE WASTE HANDLING AND SHIPPING, AND RADIOLOGICAL DNIRCHENIAL MCHITORING.

RADIOLOGICAL RADIOACTIVE OQAPM FIRE DNIRCNENIAL NASTE HANDLING CHAPTER PROTECTICH SECURITY MONITORING AND SHIPPING 1 Yes Yes Yes Yes 2 Yes Yes Yes Yes 3 Yes Yes Yes No l 4 Yes Yes Yes Yes 5 Yes Yes Yes Yes 6 Yes Yes Yes Yes 7 Yes Yes Yes Yes 8 Yes Yes Yes Yes 9 No No No Yes 10 Yes Yes Yes Yes 11 Yes Yes Yes Yes 12 Yes Yes Yes Yes 13 No No Yes Yes 14 Yes Yes Yes Yes 15 Yes Yes Yes Yes 16 Yes Yes Yes Yes 17 Yes Yes Yes Yes 18 Yes Yes Yes Yes 19 Yes Yes Yes Yes 20 Yes Yes Yes Yes 21 Yes Yes Yes Yes O

Southem Nuclear Operating Company A v) OPERATIONS QUALITY ASSURANCE chapter APPENDIX E Rev. **9' 31 3 or 6 TIRE PROTECTICN Chapter 1 - Applicable Chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable except that vendor quality assurance programs will be appropriate to the item or service (compliance with 10CTR50 Appendix B/ ANSI N45.2 is not required).

Chapter 5 - Applicable Chapter 6 - Applicable

(] Chapter Applicable Chapter 8 - Applicable

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Chapter 9 - Not Applicable except as specified by design requirements.

Chapter 10 - Applicable Chapter 11 - Applicable Chapter 12 - Applicable e

Chapter 13 - Not Applicable Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable to documents designated as records generated in the implementation of the Fire Protection program. Records are prepared and maintained to furnish evidence that the chapters specified herein are being met for activities affecting the fire protection program as described in the Fire Protection Program Re-evaluation.

O Chapter 18 - Applicable Chapter 19 - Applicable Chapter 20 - Applicable Chapter 21 - Applicable

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m OPERATIONS QUALITY ASSURANCE Southem Nudear Operating Company A g cwer APPDOIX E A*'- 31 Page 4 OT 6 SECURITY Chapter 1 - Applicable Chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable except that vendor quality assurance programs will be appropriate to the item or service (compliance with 10CTR50 Appendix B/ ANSI N45.2 is not required).

Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable Chapter 8 - Applicable Chapter 9 - Not Applicable Chapter 10 - Applicable Chapter 11 - Applicable Chapter 12 - Applicable Chapter 13 - Not Applicable Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable to those records required by the regulatory requirements, the FNP Security Plan, or the chapters specified herein'. Safeguards Information will be stored and controlled in accordance with applicable procedures.

Chapter 18 - Applicable Chapter 19 - Applicable Chapter 20 - Applicable Chapter 21 - Applicable l

l OPERATIONS QUAUTY ASSURANCE Southern Nuclear Operating Company A Chagm gppg g gg g %. 3g p* 5 or 6 RADIOIDGICAL ENVIlO5 ENTAL MCNITORING 1

i Chapter 1 - Applicable ;

Chapter 2 - Applicable ,

Chapter 3 - Applicable i Chapter 4 - Applicable except that vendor quality assurance programs will be appropriate to the item or service (compliance with 10CFR50 Appendix B/ ANSI N45.2 is not required).

Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable -

Chapter 8 - Applicable :

Chapter 9 - Not Applicable except as specified by system design i requirements. .

Chapter 10 - Applicable Chaptsr 11 - Applicable Chapter 12 - Applicable l Chapter 13 - Applicable f r

Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable :

Chapter 17 - Applicable Chapter 18 - Applicable Chapter 19 - Applicable Chapter 20 - Applicable :

Chapter 21 - Applicable

OPERATIONS QUALITY ASSURANCE Southern Nudear Operating Company A g chapt *' APPENDIX E Rw. 31 Page 6 OF 6 RADIOACTIVE WASTE HANDLI?G AND SHIPPI?G Chapter 1 - Applicable Chapter 2 - Applicable Chapter 3 - Not Applicable to SNC-Farley Project, only to the suppliers of transportation packages. SNC-Farley Project is approved for procurement, maintenance, repair and use of transportation packages. All other activities (i.e. design, fabrication, assembly and modification) shall be satisfied by obtaining certification from package suppliers that these activities were conducted in accordance with NRC-Approved QA Programs.

Chapter 4 - Applicable Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable Chapter 8 - Applicable Chapter 9 - Applicable Chapter 10 - Applicable Chapter 11 - Applicable Chapter 12 - Applicable Chapter 13 - Applicable Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable Chapter 18 - Applicabla Chapter 19 - Applicable Chapter 20 - Applicable chapter 21 - Applicable

A SNC- Fcrisy Pr: Ject - Opercti:ns co-M-8

- Quality Assurance Policy Implementation List ,

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u Southern Nuclear Operating Company Farley Project Operations Quality Assurance Policy Implementation List GO-M-8 O

List of Effective Pagg Eagg Revision 1-7 19 Approved:

$N h&ff Vice-President (/

Mi I N(

A CREOLc;g;at T ^"" ""*" ** ~~"~

COPY NO. _

C-M -75 Date Issued O

Page 1 of 7 Gen. Rev.19

l A SNC - Fcrl y Project - Operatins Go-M 8 Quality Assurance Policy Implementation List ]

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Table of Contents Operations Quality Assurance Policy Implementation List......................................... 3 1.0 Purpose.......................................................................................................3 ;

2. 0 C o ntro l of 0 0 AP I L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Table 1 Nuclear Plant General Manager (NPGM) Administrative Procedures . .. ....4 Table 2 Nuclear Support General Manager (NSGM) Administrative Procedures.. . ....6 Table 3 Safety Audit & Engineering Review Manager (SAERM) Administrative Procedures.. .7 O

c Page 2 of 7 Gen.Rev.19

A SNC - Fcrl:y Project - Ope;Sti:ns GO-M-8 Quality Assurance Policy Implementation List O Operations Quality Assurance Policy Implementation List 1.0 Purpose I 1.1 The OQAPIL is a composite listing of administrative procedures issued by the :

. Nuclear Plant General Manager (NPGM),

. Nuclear Support General Manager (NSGM), and e Safety Audit & Engineering Review Manager (SAERM) ,

l 1.2 These procedures are approved by the Vice President to implement responsibilities ;

assigned to each manager in the Operations Quality Assurance Policy Manual (OQAPM). !

1.3 The SAERM is responsible for reviewing and approving procedures to be included in the I

OQAPIL, prior to their issuance, to confirm that provisions are made to adequately and comprehensively implement all responsibilities assigned to the managers in the OQAPM.

1.4 The SAERM is also responsible for promulgating, maintaining up to date, and controlling the list.

/ 1.5 Personnel desiring to delete procedures from the OQAPIL shall submit in writing

)

justification for this deletion to the Vice President who will review and approve / disapprove the recommendation.

2.0 Control of OQAPIL 2.1 The OQAPIL is issued as a controlled document.

2.2 The OQAPIL will be controlled in accordance with FSAER-AP-2, Development and Control of Guidance Documents.

2.3 Although the OQAPIL is not a part of the OQAPM, it is recommended that it be retained in the back of the OQAPM behind the special divider provided.

Page 3 of 7 Gen. Rev.19

A SNC- Feri y Pr ject- Operatins GO-M-8 Quality Assurance Policy Implementation List O

V Table 1 Nuclear Plant General Manager (NPGM) Administrative Procedures Procedure Title FNP-0-A?-l Development Review and Approval of Plant Procedures FNP-0-AP-2 , Plant Operations Resiew Committee FNP-0-AP-3 { Plant Organization and Responsibility FNP-0-AP-4 Control of Plant Documents and Records FNP-0-AP-5 , Surveillance Program Administrative Control ,

FNP-0-AP-6 l Procedure Adherence FNP-0-AP-7 [ Corrective Action Reporting FNP-0-AP-8 l Design Modification Control FNP-0-AP-9 [ Procurement and Procurement Document Control FNP-0-AP-10 l Conduct of Operations Security Group FNP-0-AP-11 f Control and Calibration of Test Ecjuipment and Instrumentation FNP-0-AP-12 Control of Special Processes During Operation FNP-0-AP-13 , Control of Temjorary Alterations FNP-0-AP-14 l Safety Clearance & Tagging FNP-0-AP-15 i Maintenance Conduct of 0perations FNP-0-AP-16 Conduct of Operation - Operation Group

/ FNP-0-AP-17 Conduct of Operations Chemistry and Health Physics Group FNP-0-AP-18 Conduct of Operations-Technical Group FNP-0-AP-20 , Receipt Inspections FNP-0-AP-21 Identification and Control of Materials Parts and Components FNP-0-AP-22 , Nonconformance Control / Deficiency Reporting FNP-0-AP-23 Handling Storage and Shipping of Materials Components and Fauipment FNP-0-AP-24 Test Control FNP-0-AP-25 ,_ Equipment identification FNP-0-AP-27 Conduct of Operations -Trainin6 G gp !

FNP-0-AP-28 Plant Lubrication Program FNP-0-AP-29 , Correspondence Control Procedure FNP-0-AP-30 Preparation and Processing ofincident Reports Plant Event Reports and Licensee Event

_ Reports FNP-0-AP-31 Quality Control Measures l FNP-0-AP-32 , Review of Operating Data l FNP-0-AP-35 J General Plant Housekeeping and Cleanliness Control FNP-0-AP-36 Fire Surveillance Procedures and Inspections FNP-0-AP-37 , Fire Brigade Organization FNP-0-AP-38 l Use of Open Flame FNP-0-AP-39 [ Fire Patrols and Watches FNP-0-AP-42 [* Access Control FNP-0-AP-44 Cleanliness of Fluid Systems & Associated Components FNP-0-AP-45 , Farley Nuclear Plant Training Plan Page 4 of 7 Gen. Rev.19 l

A SNC - Farley Project - Operations GO-M-8 Quality Assurance Policy Implementation List Procedure Title FNP-0-AP-51 Instrumentation and Control Group Conduct of Operations FNP-0-AP-52 Juipment Status Control and Maintenance Authorization FNP-0-AP-53 Preventive Maintenance Program FNP-0-AP-56 Insurance Administration FNP-0-AP-57 , Presenice Insenice and Eddy Current inspections FNP-0-AP-60 Oil Spill Prevention Control and Countermeaare Plan, Hazardous Waste Contin 6ency Plan FNP-0-AP-62 Evaluations of Defects and Noncompliances Potentially Reportable Under 10 CFR 21

__FNP-0-AP-63 , Conduct of Operations Systems Performance Group FNP-0-AP-64 Work Schedules for Personnel Performing Safety Related Functions FNP-0-AP45 , FNP Nuclear Experience Evaluation Program FNP-0-AP-66 Conduct of Ogerations Planning Group FNP-0-AP-69 General Plant Technical Senices Conduct of Operation FNP-0-AP-70 , Conduct of Operations Plant Modifications and Maintenance Support FNP-0-AP-72 i Protection of Safeguards Information FNP-0-AP-73 [ Computer Software Change Control FNP-0-AP-74 Development and Maintenance of Emergency Response Procedures FNP-0-AP-76 Conduct of Operations Chemistry and Environmental Group FNP-0-AP-77 Conduct of Operations Computer Senices Group O FNP-0-AP-80 ASME Section XI and Section III Code Required Authorized Nuclear Inspection b FNP-0-AP-83 Information System Change Control FNP-0-AP-85 Electrical Maintenance Group Conduct of Operations FNP-0-AP-88 Nuclear Safety Evaluations FNP-0-AP-89 Conduct of Operations Efaintenance Engineering Support Group FNP-0-AP-90 , ALARA Policy and Implementation FNP-0-AP-92 Infreguently Performed Tests or Evolutions FNP-0-AP-93 Planned Special Exposure FNP-0-AP-94 { Outage Nuclear Safety Page 5 of 7 Gen. Rev.19

A SNC - Farley Project - Operations GO-M-8 Quality Assurance Policy Implementation List tO V

Table 2 Nuclear Support General Manager (NSGM) Administrative Procedures Procedure Title GO-NG-1 Development of Farley Support Procedures

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GO-NG-2 Farley Support Organization and Responsibility GO-NG-6 Licensing Related Activities GO-NG-7 Document Control

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GO-NG-10 Corrective Action GO-NG-11 Engineering Change Process GO-NG-13 Documentation of Education Training, Experience & Qualifications for Farley Project Farley S_upport Personnel GO-NG-22 Nuclear Maintenance Support Conduct of Operations GO-NG-26 Handling Safeguards Information GO NG-29 Information Systems Change Control

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GO-NG-32 The Annual Revision to the Final Safety Analysis Report p GO-NG-34 Engineering Support Administration b ~

GO-NG-37 Nuclear Administration Conduct of Operations GO-NG-38 Acceptance of Safety Related Services by the GO-NG Staff GO-NG-39 Licensing Correspondence & Commitment Tracking GO-NG-41 Engineering and Technical Support Guidance GO-NG-42 50.59 Evaluations GO-NG-44 f Inservice Inspection GO-NG-45 ' Conduct of Operation - Nuclear Engineering & Licensing GO-NG-46 Environmental Compliance Program GO-M-1 Designer Interface Document O

Page 6 of 7 Gen.Rev.19

A SNC - Farley Project - Operations GO-M-8 Quality Assurance Policy Implementation List f)

LJ Table 3 Safety Audit & Engineering Review Manager (SAERM) Administrative Procedures Procedure Title FSAER-AP-00 (deleted)

FSAER-AP-01 SAER organization FSAER-AP-02 Development and Implementation of Procedural Guidance FSAER-AP-03 (deleted)

FSAER-AP-04 SAER Quality Assurance Records and SAER Administrative Records FSAER-AP-05 } Audit Coverage Planning FSAER-AP-06 Audit Implementation FSAER-AP-07 Qualification and Training FSAER-AP-08 Employee orientation FSAER-AP-09 Corrective Action FS AER-AP-10 Reviews and Evaluations FSAER-AP-11 Summaries and Analyses of Audit Results d FSAER-AP-13 Operational Evaluations Page 7 of 7 Gen.Rev.19

ML20086B276

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