Text

Forwards Rev 63b to Topical Rept CE-1-A, QA Program for Nuclear Generating Stations.
	ML17252A760
Person / Time
Site:	Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle
Issue date:	07/13/1993
From:	Bauer J; COMMONWEALTH EDISON CO.
To:	Murley T; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML17252A761	List: ML17252A760;
References
	NUDOCS 9307200213
	Download: ML17252A760 (211)
	v • d • e

..:__** Commo.ealth Edison

.... 1400 Op ace Downersi.. ove, Illinois 60515-July 13, 1993 Dr. Thomas E. Mtirley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comm.ision Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Commonwealth Edison Company Quality Assurance Topical Report CE-1-A, Revision 63b Byron Units 1 and 2, NRC Docket Numbers 50-454 and 50-455 .,..

Braidwood Units 1 and 2, NRC Docket Numbers 50-456 and 50-457 ~

Zion Units 1 and 2, NRC Docket Numbers 50-295 and 50-304 ~

Dresden Units 2 and .3, NRC Docket Numbers 50-237 and 50-249 '

Quad Cities Units 1 and 2, NRC Docket Numbers 50-254 and 50-265 "-*

LaSalle Units 1 and 2, I NRC Docket Numbers 50-373 and 50-374 ~

Attached please find one copy of Revision 63b of the Commonwealth Edison (CECo) Topical Report CE-1-A dated June 16, 1993. This report reflects the changes prompted by the ASME Survey conducted on June 14-16, 1993. No substantive changes were made.

Please direct any questions or comments to this office.

Sincerely, A~;t.-,6~

()"_oseph A. Bauer .

Nuclear Licensing Administrator JAB/gp l5005ti

Attachment:

CECo Topical Report CE-1-A, Revision 63b cc: J.B. Martin, Regional Administrator - Riii (2 copies)

$ii_ 1a.o&'-12 9307 l 3

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TOPICAL\REPDRT CE-1-A, REVISION 63B

. REC'D W?LTR DTD 07/13/93 .... 9307200213

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REPORTS MANAGEMENT BRANCH.

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. TION P1-22 WHITE ~LINT. PLEASE DQ.

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FEARED TO FILE PERSONNEL.

--NOTICE-

. --.... *.:..~ ..

Commonwealth Edison Company .

Topical Report CE-1-A * -

FIRST NATIONAL BANK BUILDING ONE FIRST NATIONAL PLAZA CHICAGO, IL. 60603

COMMONWEALlH EDISON COMPANY TOPICAL REPORT CE-1-A

TABLE OF CONTENTS & INDEX Pref ace & Policy (Rev. 63b) 1 page (Rev. 63b) 15 pages SECTION 1, ORGANIZATION (Rev. 63b) 26 pages

1. POLICY 1-1

.. - . . . . ******~=-=

2. RESPONSIBILITIES 1-3

3. REQUIRE:MENTS 1-3 3.1 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1-3 3.2 . Delegation * .............................. 1-3 3.3 Functional Responsibilities .................... 1-4

.3.3.1 NSSS Supplier . . . . .. . . . . . . . . . .. . . . . . . . . .' . . . . . . 1-4 3.3.2 Architect-Engineers * . . . . .. . . . . . . . . . . . . . . . . . . . . 1-4 3.3.3 Construction Contractors--.:.. . *. . . ~ ~ *. .. . . . . . . . . . . . . 1-5 3.3.4 Non-delegated Functional Requirements ........ 1-6 3.3.4.1 Program Establishment & Execu~on ........... 1-6 3.3.4.1.1 Design .............................. 1-6 3.3.4.1.2 Procurement .......................... 1-7 3.3.4.1.3 Construction ; *. . . . . . . . . . . . . . . . . . . . . . . . 1-7 3.3.4.1.4 Operations Program ................... 1-8 3.3.4.2 Verification ......................... 1-8 3.3A.2.1 Design ......................... 1-9 3.3.4.2.2 Procurement ......................... 1-10 3.3.4.2.3 Construction ......................... 1-10 3.3.4.2.4 Pre-Service~Testing ....... *-. . . . . . . . . . . . 1-12 3.3.4.2.5 Operations Verification ................... 1-12

3.4 DESCRIPTION

OF GENERAL RESPONSIBILITIES

-**.:.:t**,... ~

1-13 (3.4.) 1. Chairman and CEO . . . . . . . . . . .. . . . . . . . . 1-13 (3.4.) 1.1 President .............................. 1-14 (3.4.) I.I.I Senior Vice President (Corporate Resources) . . . 1-14 (3.4.) 1.1.1.1 *systems Material Analysis Manager 1-14 Page 1-1 REVISION 63b 6/ 16/ 93 I

~Sfe?0219 930713

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COMMONWEAL1H EDISON COMPANY TOPICAL REPORT CE-1-A (3.4.) 1.1.1.2 Director of Corporate Security . . . . . . . . 1-14 (3.4.) 1.1.1.3 Manager of Purchasing .............. . 1-15 (3.4.) 1.2 Senior Vice President (Energy Production) CNO-: . *l-15'***

(3.4.) 1.2.1 Vice President and Chief Nuclear Operating Officer ...... . 1-15 (3.4.) 1.2.1.1 Site Vice President ................... . 1-15 (3.4.) 1.2.1.1.1 Station Manager ................... . 1-16 (3.4.) 1.2.1.1.1.1 Operations Manager .............. . 1-16 (3.4.) 1.2.1.1.12 Technical Services Superintendent 1-17 (3.4.) 1.2.1.1.1.3 Maintenance--Supetintendent ....... . 1-17

- (3.4.) 1.2.1.1.1.4 Work Control Superintendent ......... . 1-17 (3.4.) 1.2.1.1.2 Site Engineering and Construction Manager . 1-17 (3.4.) 1.2.1.1.2.1 Station Support Engineering Supervisor .. . 1-18 (3.4.) 1.2.1.1.2.2 Modification Design Supervisor ...... . 1-18 (3.4.) 1.2.1.1.2.3 Site Construction Superintendent ...... *.. 1-18 (3.4.) 1.2.1.1.3 Support Services Director ... -...... . 1-18--

(3.4.) 1.2.1.1.3.1 Materials Management Supervisor .... . 1-18 (3.4.) 1.2.1.1.3.2 Training Supervisor .............. . 1-19 (3.4.) 1.2.1.1.4 Regulatory Assurance Supervisor ....... . 1-19 (3.4.) 1.2.1.2 Nuclear Operations Manager ......... . 1-19 (3.4.) 1.2.1.3 Engineering and Construction Manager 1-19 (3.4.) 1.2.1.3.1 Nuclear Fuel Services Manager ....... . 1-20 (3.4.) 1.2.1.4 Nuclear Support Manager ........ . 1-20 (3.4.) 1.2.1.5 Performance Monitoring and Improvement Manager * .............. . 1-21 (3.4.) 1.2.2 Vice President, Nuclear Oversight and Regulatory Services . . . . . . . . . . . . . . . . . . . . 1-21 (3..4.) 1.2.2.1 Nuclear Regulatory Services Manager 1-21 (3.4.) 1.2.2.1.1 Licensing Operations Director 1-22 (3.4.) 1.2.2.1.2 Regulatory Performance Director ....... . 1-22 (3.4.) 1.2.2.1.3 Emergency Preparedness and State Programs Director . . . . . . . . . . . . . . 1-22 (3.4.) 1.2.2~~*.~.; pirector of Strategic Licensing Policies and Issues ,.* . . . . . . . . . '.9 * * * * * * * *

1-22 (3.4.) 1.2.2.2 Nuclear Oversight Manager ........... . 1-22 (3.4.) 1.2.2.2.1 Director of On-Site Quality Verification ... _ 1-23

. (3.4.) 1.2.2.2.2 Director of Safety Review . . . . . . . . . . . . . . 1-24 Page 1-2 REVISION 63b 61i6/93

CO:MMONWEALlH.EDISON COMPANY TOPICAL REPORT CE-1-A (3.4.) 1.2.2.2.3 Off-Site Quality Verification Director ..... . 1-24 (3.4.) 1.2.2.2.4 Quality Assurance Policy Director ....... . 1-24 (3.4.) 1.2.3 Manager of Fuel .................. . 1-24 (3.4.) 1.3 Senior Vice President (Commercial Division Operations) 1-24 (3.4.) 1.3.1 Vice President, Transmission and Distribution Operations .............. 1-25 (3.4.) 1.3.1.1 T&D Operational Analysis Manager ....... . 1-25

4. REFERENCES 1-25 EXHIBIT 1 - Organization Charts (Rev. 63a) 4 pages EXHIBIT 2 - Organization Chart (Rev. 63a) 1 page SECTION 2, QUALITY ASSURANCE PROGRAM (Rev. 63a) 10 pages 1'

1. POLICY 2-1

2. RESPONSIBILITIES . 2-1

3. REQUIREMENTS 2"-2 3.1 General .... ..................... 2-2 3.2 Planning . ---._ :-:-:- . . . . . . . . . . . . . . . _. . . . . . . 2-5 3.2.1 General .... . . . . . . . . .. . . . . * . . . . . . . 2-5 3.2.2 Controlled Conditions .................... 2-5 3.2.3 Program Planning .... . . . . .. . . . . . . . . . . . *. . . 2-5 3.3 Program Description .... . . . . . . . . .,. . . . . . . . . . . . 2-6 3.4 Indoctrination & Training .................... 2-7

-3.5 Program Review .... . . . . . . . . . . . . . . . . .. . . . . . 2-8 3.6 Quality Assurance Manual .................... 2-8

4. REFERENCES 2-9 EXHIBIT 1 - Policy, Directive & Procedure Hierarchy (Rev. 63a) 1 page Page 1-3 REVISION 63b 6/ 16/ 93

.COMMONWEAL1H EDISON COMPANY TOPICAL REPORT CE.;.1-A SECTION 3, DESIGN CONTROL (Rev. 63a) 7 pages

1. POLICY 3-1

2. RESPONSIBILITIES 3-1

3. REQUIREMEN1S 3-1 3.1 General . . . . . . . . . . . . . . . . . .. . . . . . . . 3-1 3.2 Design Input ......................... 3-2 3.3 Design Process ......................... 3-2 3.4 Design Analyses ......................... 3-3 3.5 Design Verification ......................... 3-4 3.5.1 Extent of Design Verification ............... 3-5 3.5.2 Methods . . . .. . . . . . . . . . . . . . . . . . . . . . 3-5 3.5.2.1 Design Reviews ......................... 3-5 3.5.2.2 Alternate Calculations . . .... *. . . . . . . . . . . . . . . 3-5 3.5.2.3

Qualfffeation Tests . . . . . . . . . . . . . . . . . . . . . . . . . 3-6

3.6 Change Control . .. . . . . .. . . *. . . . . . . . . . . . . . . . 3-6 3.7 Interlace Control . . . . . . . . . . . .. . . . .. . . . . . . . . . 3-7 3.8 Documentation and Records . . . . . . . . . . . . . . . . . . . . 3-7

4. REFERENCES 3-7

~CTION. 4, PROCUREMENT DOCUI\1ENT CONTROL *. (Rev. 63a) *. s pages

1. POLICY 4-1

2. RESPONSIBILITIES 4-1 Page 1-4 REVISION 63b 6/ 16193 I

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COMMONWEAL1H. EDISON COMPANY 'TOPICAL REPORT CE-1-A

3. REQUJREMEN1S 4-1 3.1 General .................... ~ *;--: . -. 4-1 3.2 Supplier-QA Program Requirements .......... 4-2 3.3 Content of Procurement Documents .......... 4-2 3.3.1 Scope of Work . . . . . . . . . . . . . . . . . . . . . . . . .

4-2 3.3.2 Technical Requirements . . . . . . . . . . . . . . . . . . . . 4-2 3.3.3 Extension of QA Program to Subtier Suppliers . . . . . 4-3 3.3.4 Right of Access for Inspection and Audit * . . . . . . . . 4-3 3.3.5 Nonconformances . . . . . .. . . . . . . . . . . . . . . . . . . . 4-3 3.3.6 Documentation Requirements * . . . . . . . . . . . . . . . 4-3 3.3.7 Spare and Replacement Parts * . . . . . . . . . . . . . . . 4-3 3.4 Procurement Document Review . . . . . . . . . . . . . . . 4-4 3.5 Control of Procurement Document Changes . . . . . . . . 4-4

4. REFERENCES 4-5 SECTION 5, INSfRUCTIONS, PROCEDURES AND ORAWINGS (Rev. 63a) 3 pages

1. POLICY 5-1

2. RESPONSIBILITIES 5-1

3. REQUIRE:MEN1S .5-2 3.1 Preparation and Review 5-2 3.2 General . . . . . . . . . . . . . . . . . *' . . . . . . . 5-2

4. REFERENCES 5-3

Page 1-5 REVISION 63b 6/ 16/ 93

COI\fMONWEALill EDISON COMPANY TOPICAL REPORT CE-1-A SECTION 6, DOCUMENT CONTROL (Rev. 63b) 4 pages

1. POLICY 6-1

2. RESPONSIBILITIES 6-1

3. REQUIRE:MEN1S 6-2 3.1 Document Preparation, Review, Approval, Issuance and Distribution .................... 6-2 3.2 Document Changes . . . . . . . . . . . . . . . . . . .. . . . .. . . 6-2

.3.3 General ......................... 6-3

4. REFERENCES 6-4 SECTION 7, CONTROL OF PURCHASED MATERIAL, EQUIP~NT, AND SERVICES (Rev. 63b) 15 pages

1. POLICY 7-1

2. RESPONSIBILITIES 7-1

3. REQUIRE1\1EN1S _ 7-1 3.1 Supplier Selection ......................... 7-1 3.1.1 General ......................... 7-1 3.1.2 Company Responsibilities ............. *. . . . . . . 7-2 3.1.3 Methods .........._~- *~. . . . . . . . . . . . 7-2 3.2 Bid Evaluations ......................... 7-3 3.3 Supplier In-Process Control .................... 7-3 3.3.1 General ......................... 7-3 3.3.2 In-Process Control and Verification Planning ..... 7-4 3.3.3 Programmatic* Verification ........... * . . . . . . . . . 7-5 3.3.4 Quality Verification at Source ............... 7-5 Page 1-6 REVISION 63b 6/ 16/ 93 I

CO:MMONWEAL'IH EDISON COMPANY TOPICAL .REPORT CE-1-A

3.3.5 In-Process Documentation Verification 3.3.6 Documentation of Verification Activities 3.3.7 Control of Procurement Changes . . . . . . . . . . . . . . .

3.4 Acceptance of Purchased Items and Services ....... .

7-5 7-6 7-6 7-6 3.4.1 General ......................... 7-6 3.4.2 Acceptance by Receiving Inspection .......... 7-7 3.4.3 Acceptance by Source Verification ......... . 7-8 3.4.4 Acceptance by Certificate of Conformance ....... . 7-9 3.4.5 Acceptance by Post-Installation Testing ....... . 7-10 3.4.6 Acceptance of Services Only .............. . 7-10 3.4.7 Acceptance of AS:ME Code Items . . . . . . . . . . . . . . . 7-11 3.4.8 _ Commercial Grade Items .................... 7-11 3.5 Presence of Documentary Evidence ......... . 7-12 3.6 Spares ........................ . 7-13

- - 3.6.1 General ......................... 7-13

3.6.2 Equivalent Specifications and Code Requirements .. . 7-13 '

3.6.3 Procurement from Other Utilities .............. . 7-14 3.6.4 Equivalent Production/Fabrication Requirements .. . 7-14

4.

3.6.5 Maintenance or Modification .............. .

.3.6.6 Testing or Design for Eqq.iyalence .............. .

REFERENCES 7-14-..

7-14 7-15 SECTION 8, IDENTIFICATION AND -CONTROL

... *;-'-* OF MATERIALS, PARTS AND C01\1PONENTS (Rev. 63a) 3 pages

1. POLICY 8-1

2. RESPONSIBILITIES 8-1

3. REQUIREMEN1S 8-1 3.1 Identification and Traceability ............... 8-1 3.1.1 General ......................... 8-1 3.1.2 Traceability ......................... 8-2

Page 1-7

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REVISION 63b 6116/ 93 1*

\_. .

CO:MMONWEAL1H EDISON CO:MPANY TOPICAL REPORT CE-1-A 3.1.3 Identification Methods .-* . . .. . . . . . . . . . . . . . . 8-2

~

3.1.4 Transfer of Markings . . . . . . . . . . . . . . . . . . . . . . . . . 8-2 3.1.5 Limited Life Items . . . . . . . . . . . . . . . . . . . . . . .. . . . *-8-3'**

3.1.6 Stored Items . . . . . . . . . . . . . . . . . . . . . . . . . 8-3 3.1.7 Special Materials . . . . . . . . . . . . . . . . . . . . . . . . . 8-3

4. REFERENCES 8-3

. SECTION 9, CONTROL OF SPECIAL PROCESSES (Rev. 63a) 4 pages

l. ___ POLICY 9-1 2.- RESPONSIBILITIES 9-1

3. REQUIREMEN1S 9-1 3.0 General . .. . . . . . . . . . . . . . . . . . . . . . . . 9-1 3.1 Procedure Qualification and Control . . . . . . . . . . . 9-2 3.2 Personnel Qualification and Certification . . . . . . . . .

9-3.

. 3.3 Special Process Records . . . . . . . . . . . . . . . . . . . . 9-4

4. REFERENCES , 9-4 SECTION 10, INSPECTION . (Rev. 63a) .* 5 pages I*

1. POLICY 10-1

2. RESPONSIBILITIES 10-1 Page 1-8 REVISION 63b 6/ 16/ 93

COMMONWEALTH EDISON COJ\.fi>ANY TOPICAL REPORT CE-1-A

3. REQUIRE~N'IS 10-1 3.1 General 10-1 3.2 Inspection Plans .... .. ... . ... . . .. . . .. . . . . 10 .

3.3 Inspection Personnel ........................ . 10-2 3.4 Inspector Qualifi.cati*on . . . . . . . . . . . . . . . . . . . . . . . . . 10-3 3.5 Inspection Process ........................ . 10-3 3.5.1 Inspection ........................ . 10-3 3.5.2 Process Monitoring ......................... . 10-3 3.5.3 Hold Points/Witness Points .............. . 10-3 3.5.4 Re-Inspection ......................... 10-4 3.5.5 Final Inspection Review ..................... 10-4 3.5.6 Inspection Records ......................... 10-4

4. REFERENCES 10-5 SEcnON 11, TESf CONTROL * (Rev. 63a) 16 pages

1. POLICY 11-1

2. . RESPONSIBILITIES 11-1

3. REQUIRE:MEN'IS 11-1 3.1 General 11-1 3.1.1 Testing Program 11-1 3.1.2 Test Procedures 11-3 3.1.2.1 Prerequisites 11-4 3.1.2.2 Schedule 11-5 3.1.3 Test Results 11-5 3.1.4 Test Records 11-6 3.2 Initial Test Program 11-6 3.2.1 Construction Tests 11-6 3.2.1.1 Coa~gs .... .... ...... . . . ........ 11-8

Page 1-9

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REVISION 63b 6/ 16/ 93 r

COMMONWEAL1H EDISON COMPANY TOPICAL REPORT CE-1-A 3.2.1.2 Compacted Fill ......................... 11-8 3.2.1.3 Concrete ......................... 11-8 3.2.1.4 Instrumentation ......................... 11-8 3.2.1.S Electrical Tests ......................... 11-9 3.2.1.6 Mechanical Tests ......................... 11-10 3.2.1.7 Physical and Chemical Tests ............... 11-10 3.2.2 Preoperational Tests . . . . . . . . . . . . . . . . . . . . . . . . . 11-10 3.2.2.1 Cold Functional Tests* ............... 11-14 3.2.2.2 Hot Functional Tests for PWR Plants Only . . . . . . . . 11-14 3.3 Operational Tests Program ............... 11-15 3.3.1 Startup Tests ......................... 11-15 3.3.2 Surveillance Tests ......................... 11-16 3.3.3 Maintenance or Major Procedure Change ........ 11-16

4. REFERENCES 11-16 SECTION 12, CONTROL OF lVIEASURING AND TEST EQIJJPl\IBNT (Rev. 63b) 5 pages J--

1. POLICY 12-1

2. RESPONSIBILITIES 12-1

. -3. REQUIRE1\1EN1S 12-1 3.1 General 12-1 3.2 Control 12-2 3.3 Accuracy 12-2 3.4 Traceability 12-3 3.5 Interval 12-3 3.6 AS:ME Code 12-3 3.7 Certification . . . . . . . . . . . .. . . . . . . . . . . . . . 12-3 3.8 Corrective Actions 12-4 Page 1-10 REVISION 63b 6/ 16/ 93 I

4.l ...

COMMONWEALrn *EDISON CO:MPANY TOPICAL ~PORT CE-1-A 3.9 Vend or Control 12-4 3.10 Commercial Devices 12-4 3.11 Records * * :e * * * * * * * * * * * *

e 12-4

4. REFERENCES 12-5 SECTION 13, HANDLING, -* --:...... -***

STORAGE AND SHIPPING (Rev. 63a) 13 pages

1. POLICY 13-1

2. RESPONSIBILITIES 13-1

3. REQUIRE:MEN1S 13-1 3.1 General Material Control .................... 13-1 .

3.2 3.3 3.4 3.5 3.6 Special Equipment and Environments Oassification of Items ........................ .

Oeaning, Shipping, Storage -and Preservation ....... .

Handling Tools and Equipment Additional Requirements 13-2 13-2 13-2 13-2 13-3

4. REFERENCES 13-3 SECTION 14, INSPECTION, 1ESf AND OPERATING STATUS (Rev. 63a) 6 pages I 1: POLICY 14-1

2. RESPONSIBILITIES 14-1 Page 1-11

REVISION 63b 6/ 16/ 93 I

CO:MMONWEALTII EDISON COMPANY TOPICAL REPORT. CE-1-A

3. REQUIRE~NTS 14-1 3.1 General . . . . . . . . .. . . . . . . . . . . . . . . . . 14-1 3.1.1 Procedures ......................... 14-2 3.2 Operating Status ......................... 14-3 3.2.l Release for Maintenance .................... 14-3 3.2.2 Preparation for Work . . . . . . . . . . . . . . . . . . . . . . . . . 14-3 3.2.3 Temporary Modifications ........ *. . . . . . . . . . . . 14-4* * -- --:.. _-*

3.2.4 Return to Service ......................... -- 14-5

4. REFERENCES 14-6 SECTION 15, NONCONFORMING MATERIALS, PARTS OR C01\1PONENTS (Rev. 63b) 6 pages *-. J

1. POLICY 15-1 2.

3.

RESPONSIBILITIES.

REQUIREMENTS 15-1 15-1 3.1 General .............. .. . . . . . . . . . 15-1 3.2 Identification .............. .. . . . . . . . . . 15-3

3.3 Segregation * .............. .. . . . . . . . . . 15-3 3.4 Disposition .............. .. . . . . . . . . . 15-3 3.4.1 Control . .. . . . . . . . . . . . . .. . . . . . . . . . 15-3 3.4.2 Evaluation ...........* . . . .. . . . . . . . . . 15-3 3.4.3 Personnel .............. .. . . . . . . . . . *15-4 3.4.4 Documentation .............. .. . . . . . . . . . 15-4 3.4.5 Repaired, Reworked, or Scrapped Items . . . . . . . . 15-5

4. REFERENCES

15-6 Page 1-12 REVISION 63b 6/ 16/ 93

COMI\10NWEAL1H EDISON COMPANY TOPICAL REPORT CE-1-A SECTION 16, CORRECTIVE ACTION (Rev. 63a) B pages*

1. POLICY 16-1

2. RESPONSIBILITIES 16-1 .

3. REQUIRE:MEN1S 16-1 3.1 General ......................... 16-1 3.2 Significant Conditions . . . . . . . . . . . . . . . . . . . . . . . . . 16-2 3.3 Design Errors ......................... 16-4 3.4 Plant Hardware Malfunctions ............... 16-4 3.5 Documentation and Reporting ............... 16-4 3.6 Verification and Follow-up .................... 16-6

-4. -

REFERENCES 16-8 SECTION 17, QUALITY ASSURANCE RECORDS * -

(Rev. 63a) 4 pages J.

. 1. POLICY 17-1

2. RESPONSIBILITIES 17-1

3. REQUIREMEN1S 17"".2 3.1 Program . . . .. .... . ... .. . ... .. .. .. 17-2 3.2 Administration . . . . . . . . . . *- . . . . . . . . . . . . . . 17-2 3.3 Receipt * .. ......... ...... ..... ... 17-3 3.4 Transmittal .. ...... .... ............. 17-3 3.5 Storage . .... ...... .. . .... . .... .. 17-3.

3.6 Preservation . . . . . . . . . . . . . . . . . . . . . . *- .

. 17-3

Page 1-13 REVISION 63b . 61 16/ 93

CO:MMONWEALTH EDISON COMPANY TOPICAL REPORT CE-1-A 3.7 Safekeeping ...... ........ .... ...... . 17-4

.3.8 Retention * * * * * * * * * * * * * * * * * * * * * * ...! *

17-4 3.9 Disposition . . . . . . . . . . . . . . . . . . . . . . . . . *17-4

4. REFERENCES 17-4 SECTION 18, AUDITS (Rev. 63b) 4 pages

1. POLICY 18-1

2. RESPONSIBILITIES 18-1

3. REQUIRE:MENIS 18-1 3.1 Audits - General ......................... 18-1 3 .1.1 Responsibility ......................... 18-1 3.1.2 Scheduling ......................... 18-1 3.1.3 Preparation ......................... 18-2 3.1.4 Personnel ......................... 18-2 3.1.5 . Performance ......................... 18-3 3.1.6 Reporting and Follow-up .................... 18-3 3.1.7 Records ** . ; .. *. . . . . . . . . . . . . . . . . . . . . . 18-4 3.2 Independent Management Audit/ Assessment ..... *. . . 18-4

4. REFERENCES 18-4 SECTION 19, AUGMENTED QUALITY .(Rev. 63a) 3 pages l

1. POLICY 19-1

2. RESPONSIBILITIES 19-1 Page 1~14 REVISION 63b 6/ 16/ .93 I

COMMONWEAL1H EDISON COMPANY TOPICAL REPORT CE-1-A

3. REQUIRE:MEN1S 19-1 3.1 Radiation Protection, As Low As Reasonably Achievable, ALARA ........ ~ . . . . . . . . . . . . . . . . 19*<L 3.2 Emergency Planning . . . . . . . . . . . . . . . . . . . . . . . . . 19-2 3.3 Transport of Radioactive Waste . . . . . . . . . . . . . . . *19-2 3.4 Security . . . . . . . . . . . . . . . . . . . . . . . . . 19-2 3.5 Review of Class IE Equipment Qualification . . . . . . . . 19-2 3.6 Training .....................-. . . . . 19-2 3.7 Environmental Monitofihg . . . . . . . . . . . . . . . . 19-2 3.8 Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . 19-2 3.9 Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . 19-2

4. REFERENCES 19-3

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APPENDIX A, DEFINIDONS (Rev. 63b) 21 pages Approved By R. E. Querio Date Nuclear Oversight Manager Page 1 -- REVISION 63b 6/ 16/ 93

ORGANIZATION SECTION 1

1. POLICY This section identifies the Commono/~alth Edison Company (the Company) organization as it applies to the Quality Assurance Program.

This section also defines responsibility and authority for establishing, executing and verifying- the implementation of the Quality Assurance Program.

Each Officer, Manager, Superintendent, or Director identified In this

Section is responsible for implementing the quality assurance program in l their assigned areas. They may delegate the performance of their duties to qualified personnel--reporting to them. Although the individuals identified may be responsible for specific attributes, the achievement of quality in the performance of quality related activities is the responsibility of each individual involved in nuclear operations.

The Company may _delegate the performance of work to Architect- -

Engineers, NSSS Suppliers, contractors, consultants or. others, but

Commonwealth Edison Company retains responsibility. The Manager of Nuclear Oversight is responsible for corporate quality assurance policy, on-site quality audits, off-site quality audits, training standards and certification of auditors, and corporate nuclear safety policy.

The manager is assigned this responsibility by the Chairman and Chief Executive Officer of the-Company. The Manager of Nuclear Oversight _

also verifies the implementation of the quality assurance program for the design, procurement, construction, and operation of the Company's nuclear power facilities. -He.is independent-of production. -

Organizational charts, functional descriptions of departmental responsibilities or descriptions of key quality assurance positions documept lines of authority and responsibility for -the 'Quality Assurance Program. **

Page 1-1 REVISION-63b 6/ 16/ 93- J

ORGANIZATION SECl10N 1

In general, the Quality Assurance Program provides that:

a. AdiVities are verified as being correctly performed.

b. . Quality verification activities are performed independent of the individual or group directly responsible for performing the activity.

c. Quality assurance personnel have the responsibility/

authority, and organizqtiona1 freedom to:

1. identify quality problems

2. initiate, recom~end, .or provide solutions to quality problems through tj.esignated. channels.

3. verify implementation of the solutions 4;

asstire that further processing, delivery, installation, or use is controlled until prop~r disposition of a .

nonconformance, deficiency, or unsatisfactory condition has occurred.

5'. stop work on an operation or installation when a violation of tlfe applicable QA Program, procedure, specification or drawing is identified.

d.. Following a.Stop Work, work can.resume oniy*after verification of necessary corrective actions to bring the

installation or operation into conformance.

e. Only the ~dividual wh~ places a Stop Work or a person of higher authority in his or her organization may relea8e the stop work order. The~uclear Oversight Manager or his designee must concur with the release.

NOTE: The use of he" and its derivatives throughout this document is not gender *specific; all such usage refers to specified individuals regardless of gender.

Page 1-2 REVISION 63b 6/ 16/ 93

.ORGANIZATION SECilONl

2. RESPONSIBILfllES This entire section defines responsibilities for Company personnel.

3. REQUmEl\1ENTS 3.1 Organization Commonwealth Edison Company.is responsible for the assurance of quality in all phases of the design, procurement, construction, modification, testing and operation of the Stations. Management assigns areas of responsibility to Commonwealth Edison organizational elements and individuals. The Comp~y's Quality Assurance Program describes the policy and requirements to carry out this responsibility. This Quality

-:Assurance Program description documents the Program and is approved by the Nuclear Oversight Manager.

The Company may delegate certain phases of the work to contractors, Architect-Engineers, or an NSSS Supplier, who act as the Company's agents in the assigned areas. The Company also assigns the authority

required to do this, including certification and stamping in accordance with the ASME Code.

The Company delegates these responsibilities in writing. Commonwealth Edison retains responsibility for procurement, design, construction, modifications, and operation of the plant including certification and stamping in accordance with the ASME Code.

Page 1-3 REVISION 63b 6116193

ORGANIZATION SECTIONl 3.3 Functional Responsibilities 3.3.1 NSSS Supplier Responsibility for the Nuclear Steam Supply System is delegated to the NSSS Supplier. The NSSS Supplier shall:

a. Provide the mechanical, structural and electrical design of the ... ~*.* -:..... _ _....

NSSS plant to the Engineering and Construction Department or the Site Engineering and Construction Department.

b.

Review their own designs .

. c. Evaluate the Architect-Engineers' designs and perform other independent evaluations as requested.

d. Document these reviews and evaluations and supply them to the Company.

e. Establish and maintain procurement control for NSSS components.

f.. Furnish technical and quality control assistance for on-site activities relating to the NSSS. *

g. Furnish rough draft test proceauies to the Company.

h. Evaluate final draft test procedures when requested.

i. Work in accordance with a Commonwealth Edison accepted quality program. * ---* * ..

3.3.2 Architect-Engineers

Responsibility for the design of structures, systems, and components not within the scope of the NSSS supplier may be delegated to an Architect-Page 1-4 REVISION 63b 6/ 16/ 93 I

) . . .,..

ORGANIZATION . SECTION 1 Engineering firm. When delegated-, the Architect-Engineer shall:

a. Provide the mechanical, structural and electrical design of the plant to the Engineering and Construction Department or the Site Engineering and Construction Department for their scope of responsibility.

b. Review their own designs.

c. . Independently evaluate. the NSSS supplier's designs and perform other independent evaluations as requested.

d. Document these reviews and *evaluations and supply them to the Company.

e. Evaluate the NSSS Supplier procurement specifications .

f.

Provide specifications for procurement of non-NSSS *-* .*::*_

components and services.

g. Furnish rough draft test procedures to the Company.

h. Evaluate final draft test procedures when requested.

i. .Independently evaluate vendor proposals for equipment and services, designs, vendor and contractor procedures, test reports, and design reports.

J* Perform document distribution when directed.

k Work in accordance with a Commonwealth Edison accepted

quality program.

3.3.3 Construction Contractors The Company hires contractors to supply labor and service for maintenance, modification; arid new construction. These contractors shall work to a Commonwealth Edison accepted quality program. This program--may be the contractor's or the contractor may work in Page 1 REVISION 63b 6/ 16/ 93

... -~

.*. I..

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ORGANIZATION SECTION 1 accordance with the Company's program.-* These contractors shall document their organization and any delegated responsibilities necessary to establish, execute, and verify the quality program.

3.3.4 Non-delegated Functional Requirements The following description of the Company's non-delegated functional requirements are separated into two sections: establishment and execution of the quality program, and veri.fication that the program has been implemented.

3.3.4.1 Program Establishment and Execution In order to establish and exe~~e an effective Quality Assurance Program, Commonwealth Edison is organized. to provide management services and administrative controls. These controls and services provide for effective management of all aspects of quality related activities. This includes design,** procurement, construction and modification, testing, and operations. The Company administers contracts that ~feet quality.

3.3.4.1.1 IJesign Com~onwealth Edison has engineering responsibility and design authority, makes final decisions on designs and implements engineering designs. The Company has the responsibility to properly translate the applicable Safety-Analysis Report (SAR)-;*regulatory requirements, ASME Code requirements, and design bases into specifications, drawings, procedures ai:td instructions. This is accomplished by qualified personnel performing detailed design activities or reviewing and controlling the .

design work involving electrical, mechanical, structural and instrumentation and control designs of the NSSS *Supplier and Architect-Engineer.

Commonwealth Edison is responsible for design changes.

The Company performs detailed design activities and issues design documents in accordance with approved procedures.

Page 1-6 REVISION 63b 6/ 16/ 93 .

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ORGANIZATION SECTION 1 For operating plants, the Company supervises the electrical, mechanical, structural, instrumentation and control and nuclear engineering activities involved in nuclear station modificagons and maintains a configuration management program.

In addition, the Site Engineering and Construction (SEC) organization

oversees the Site Architect-Engineer field group at those locations where one is established.

Finally, the Company notifies jurisdictional authorities of the location of Code related permanent records.

3.3.4.1.2 Procurement cOmmonwealth Edison performs technical evaluations of service contractors Jor placement on the Company's Quality Approved Bidders List. The Company directly controls procurement of non-NSSS * :

components -and services based on specifications prepared by the

Company on Architect-Engineers. The Company receives and furnishes necessary storage facilities for designated items.

For operating plants, the Company prepares and processes Safety-Related and Code specifications for the award of service contracts for maintenance or modification work.

3.3.4.1.3 Construction The Company is responsible for construction quality assurance and manages all site construction activities.

The Company directs and manages contractors performing new station construction and maintenance and modification work at existing plants.

Further, the Company develops craft labor specifications and provides estimating and quality control services as required .

Page 1-7

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REVISION 63b 6116/ 93

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ORGANIZATION SECI10N 1 The Nuclear Support Department administers the Quality Control .

Inspector Qualification and Certification Program. They oversee Q.C.

certification programs and direct Inspection Agency inspection and testing activities performed for the Company. They coordinate Non-Destructive Examination certification programs with the System Material Analysis Department.

For new plant construction, the Company has AS:rvffi Section III, Division 1 and 2, constructor responsibilities and maintains Level III personnel on staff. These individuals are responsible.Jar personnel development, certification of inspectors and qualification of procedures, as required by rules established in AS:rvffi Seqion III.

Further, the Company is responsible for the Form N-3 Data Report and other Owner N-type Data Reports, including stamping responsibility for AS:ME Section III, Division 1 and Division 2. ..--

3.3.4.1.4 Operation$ -Program Commonwealth Edison controls pre-service testing (preoperational and start-up testing) and writes the final draft of pre-service tests.

For operating plants, the Company plans the modification test programs and provides modification test acceptance criteria.

For operations, the program is planned and implemented to provide the Com party with corifidence that safety related systems, structures and components perform satisfactorily in service.

For new plants, the Company performs mechanical, electrical instrumentation and structural construction tests. -

3.3.4.2 Verification In order to verify and control the effectiveness of the Quality Assurance Program, the Company is organized to provide for audit, surveillance, review, inspection and testing. These verification methods assure that Page 1-8 REVISION 63b 6/ 16/ 93 l

ORGANIZATION SECTION 1 activities performed are correct for all aspects of quality related activities which include design, procurement, construction and modification, testing, and operations.

ff conditions which are adverse to quality and which require prompt action are found by Nuclear Oversight personnel at locations where work subject to this QA program is conducted and* required corrective measures cannot be agreed upon, the Nuclear Oversight Managerwillre-*- -***

promptly notified. ff necessary, the Vice President, Nuclear Oversight and Regulatory Services will assure resolution in accordance with the ASME Code and this Program.

3.3.4.2.1 IJesign Commonwealth Edison., reviews and accepts the specifications and

. drawings for electrical, mechanical instrumentation, nuclear and

structural material, equipment and erection work, prepared by the

-Architect-Engineer and NSSS Supplier. The purpose of these reviews is to verify inclusion of inspection, testing and acceptance criteria.

-*~*-**--*

The Company reviews the .Architect-Engineer's evaluation of fabricator ~**

and erector's detailed designs, drawings and work instructions for reasonableness and completen~s.

The Company assures that personnel certifying AS:ME Section III design activities are qualified Registered-*~sional Engineers in accordance *-i- .

with ASME N626.3-1988.

Commonwealth Edison assures that Architect/Engineers and NSSS Suppliers maintain procedures to assure that their personnel certifying ASME Section III design activities are qualified Registered Professional Engineers in accordance with ASME N626.3~1988.

The Company provides qualified personnel to review and approve the resolution of nonconformances-relating to electrical, mechanical instrumentation and structural portions of the plant and to evaluate discrepant modification test results for operating plants .

Page 1-9 REVISION 63b . 6116/ 93 I

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'ORGANIZATION SECTION 1 The Company audits the design review system of Architect-Engineers, Nuclear Fuel Vend ors and NSSS Suppliers.

3.3.4.2.2 Procurement Commonwealth Edison anaJyzes bids to assure that necessary quality requirements are included in purchase orders and contracts. The Company evaluates the NSSS Supplier procurement specifications --._ -..

and audits and inspects the NSSS Supplier's control measures.

Audits of off-site contractors are performed as required to assure quality functions.

At times, the Company may assign an Independent Inspection Agency to work occurring at off-site supplier's plants. Verify that the Company's Quality Assurance and technical requirements are implemented for work occurring at off-site supplier's plants. .

3.3.4.2.3 Construction The Co~pany provides new project construction quality assurance.

Organizational elements are assigned to:

a. Oosely monitor the construction quality assurance activities of on-site contractors and others.

b. Independently evaluate site contractor quality *assurance programs. **

c. .Verify that construction activities carried out by site contractors conform to procurement document requirements.

d. Verify conformance and completeness of contractor's installation or erection to specification requirements~

Page 1-10 REVISION 63b 6/ 16/ 93

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ORGANIZATION SEcnONl

e.

f.

Review, comment, and approve on-site contractor quality instructions and procedures. . --. .

Prepare checklists for witnessing inspection notification points at vendor plants.

g. Inspect and designate status of incoming material at the site.

h. Review inspection procedures.

,.,,- - '*::!'"~

i. Monitor quality control activities of contractors at the site.

. J* Initiate those actions which are required to ensure that the assigned work is completed, in accordance with technical and design requirements.

k. Provide performance assessments of contractor work.

- 1.

Audit and survey. the compliance of the contractors to their accepted quality assurance program.

The Company has the functional responsibility to perform inspections of site construction activities but may assign these responsibilities to an Independent Inspection Agency. If assigned, these a*ctivitie5 shall include.

inspection and testing, and to determine and report whether items conform to design, test and specification requirements or to reject unsatisfactory materials, equipment or workmanship.

The Company shall take the n~essary steps to assure repair, rework or.

processing of a nonconformance report based on rejection by an Independent Inspection Agency.

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- Page l-11 REVISION 63b 6/ 16/ 93 1

-ORGANIZATION SECTION 1 For new project construction only, Nuclear Oversight will establish a site Nuclear Oversight group. They will provide independent verificatio:n_.ot the program compliance by audit and surveillance. This group will be established similar to On-Site Quality Verification Departments at operating sites. Sufficient qualified personnel are assigned to this group to assure program compliance but will average from. one to twenty. This group may employ an Independent Inspection Agency to provide inspection and testing.

3.3.4.2.4 Pre-Service Testing During new project construction, the Company assures that an acceptable

.test program is implemented. Organizational elements are assigned to:

a. Evaluate ~d indep~deritly confirm test results by internal evaluation.

b.- Manage and perform tests with technical assistance from the NSSS Supplier or the Architect-Engineer as appropriate. -

3.3.4.2.5 Operations Verification .

During operations, the Company assures that the Quality Assuran.ce Program described in this document is acceptably *established and executed. This is done by assigning organizational elements to:

a. Establish and execute quality pro~edures to be used by the station staff, or those under their direction, for operating, maintenance, modifications, in-service inspection, refueling and stores activities.

b. Assure that such procedures and instructions comply with the policies contained in this Quality Assurance Program.

Page 1-12 REVISION 63b 6/ 16/ 93 *I n

,ORGANIZATION *

SECTION 1

c. Review and approve Station Procedures and instructions and

. .. revisions thereto as provided for in the Technical Specifications.

d. Make temporary changes to station operating procedures which do not change the intent of the original procedures as described by Technical Specifications. These changes are reviewed and approved in the same manner as the original procedure..

3.4 DESCRIPTION

OF GENERAL RESPONSIBil.ITIES The Commonwealth Edison Company organization as related to Quality Assurance is shown in Exhibit 1.

Organizations which will be activated for future nuclear station construction are shown in Exhibit 2.

The Company assigns responsibilities for specific requirements through the Quality Assurance Program Database. * ;

Brief discussions of the duties and responsibilities of those p~rsonnel *'

indicated on Exhibit 1 ar~ as follows:

3.4.1 Chairman and CEO The Chairman and Orief Executive Officer (CEO) is responsible for overall corporate policy for quality and safety. The Chairman*

promulgates corporate policy through a staff which includes:

President * .. ~

Senior Vice President (Energy Production).

SemQ.{ Yice President (Commercial Division Operations)

Page 1-13

.-~'-**

REVISION 63b 6/ 16/ 93

ORGANIZATION . SECTIONl

.1.1 President The President is responsible for Purchasing, Security, Environmental *-*

Affairs, Corporate Counsel, Public Relations and physical plant, other than generating stations. The President fulfills assigned responsibilities through a staff which includes:

Senior Vice President (Corporate Resources) 1.1.1 Senior Vice President (CorpQ!'~te.Besources)

The Senior Vice President is responsible for Purchasing, Security, Systems Material Analysis Departm~t, Environmental Services, and buildings

.except for nuclear facilities. He fulfills these responsibilities through a staff which 'includes: *

1 Systems Material Analysis Manager Director, Corporate Security Manager, Purchasing 1.1.1.1 Systems Material Analysis Manager The Systems Material Analysis Manager maintains the* Company's off-site testing facilities and equipment for chemistry, metallurgy, nondestructive examination, and vibration analysis.

The Manager maintains an SNT-TC- lA qualified and certified Level ill ...

.NDE person on.staff who is responsible for personnel and p~ocedure *

development and qualification to ASJ\.IB Code requireinen:ts for

nondestructive ~ination. This person may designate deputies for certification of personnel and procedures.

~

1.1.1.2 Director of Corporate Security The Director of Corporate Security is responsible for insuring that security programs at the nuclear stations effectively meet all commitments to, and the regulations of, the Nuclear Regulatory Commission.

Page 1-14 REVISION 63b 6/ 16/ 93 I

ORGANIZATION SECTION 1

1.1.1.3 Manager of Purchasing The Manager of Purchasing purchases non-fuel goods and services to specifications and contract requirement prepared by responsible originating deparbnents.

1.2 Senior Vice President (Energy Production) CNO The Senior Vice President (Energy Production) CNO provides-strategy and policy for energy production in support of corporate needs. He provides resources and support for the operation and maintenance of the stations. He has overall responsibility for the Quality Assurance Program.

He fulfills these responsibilities through a staff which includes:

Vice President and Chief Nuclear Operating Officer Vice President, Nuclear Oversight and Regulatory Services Manager of Fuel

1.2.1 Vice President and Chief Nuclear Operating Officer .

- =--***-

The Vice President and Chief Nuclear Operating Officer provides a single executive focal point for setting policies, objectives and priorities for the Nuclear Operations organization. He brings all resources inyolved ii1

operations and direct support of operation under a single executive. He fulfills these responsibilities through a staff which includes:

Site Vice Presidents (six)

Nuclear Operations Manager Engineering and Construction Manager Nuclear Support Manager Performance Monitoring and Improvement Manager 1.2.1.1 Site Vice President Each of the six* Site Vice Presidents operates and maintains the station for which he is responsible, including operation, maintenance, modification

Page 1-15 REVISION 63b 6ti6/ 93 I --

. ORGANIZATION SECTION1 and all support functions. He has complete operational and fiscal responsibility for the assigned station.

The Site Vice President is responsible for the Station's compliance with its NRC operating license, government regulations, AS~ code requirements and the Company's Quality Assurance Program.

He fulfills these responsibilities through a staff which includes:

Station Manager Site Engineering and Construction Manager Support Services Director Regulatory .Assurance Supervisor Outage Planning Director (where established) 1.2.1.1.1 Station Manager The Station Manager-is responsible for the safe, reliable cµld ~ficient day-

to-day operation of the station for which he is responsible. He fulfills .

these responsibilities through a staff which includes:

Operations Manager .

. Technical Services Superintendent Maintenance Superintendent

~ork Control Superintendent (where established)

The Station Manager supervises the Station's on-site review function as provided in the Administrative Section 6.0 of the Technical Specifications. <

During periods when the Station Manager is unavailable, he designates this responsibility to an established alternate who satisfies -the ANS 3.1 experience requirements for plant manager.

1.2.1.1.1.1 Operations Manager The Operations Manager.is responsible for the safe, reliable and efficient operations of the station Units.

Page 1-16 REVISION 63b 6/ 16/ 93 I *

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ORGANIZAnoN* SECilONl 1.2.1.1.1.2 Technical Services Superintendent The Technical Services Superintendent provides support-for plant" --

operations in the areas of technical support, chemistry and health physics.

1.2.1.1.1.3 Maintenance Superintendent The Maintenance Superintendent manages the day-to-day repair activities

_for mechanical, electrical and instrumentation equipment. He also supervises the Quality Control activities.

1.2.1.1.1.4 Work Control Superintendent The Work Control Superintendent plans and oversees the station outages.

In this capacity he manages the current outage and plans future outages.

1.2.1.1.2 Site Engineering and Construction Manager The Site Engineering and Construction Manager provides design support engineering, modification engineering, and construction services to the station. He has responsibility and authority for all day-to-day design _

activities and is responsible for developing design policies and procedures as a member of the Nuclear Engineering Committee (NEC) as well as implementing the design po~ci~_~d procedures established by the NEC.

.He maintains plant configuration control. He provides engineering and construction subpiliport to the WhorkafCofntrhiol Superintendent. He fulfills-- _J these responsi * *ties throug a st w *ch includes:

Station Support Engineering Supervisor

_Modification Design Supervisor ---- -

Site Construction Superintendent -

Page l-17 REVISION 63b ---6116/ 93

ORGANIZATION SECilONl 1.2.1.1.2.1 Station Support Engineering Supervisor The Station Support Engineering Supervisor provides design support to Operations, Maintenance, and Systems Engineering. He maintains design cognizance in order to provide support for design changes, regulatory responses, and in order to initiate the design change process.

1.2.1.1.2.2 Modification Design Supervisor

The Modification Design Supervisor provides detailed design engineering and implementation of modifications. He oversees architect/ engineer activities. and is responsible for coordination of design with other plants.

1.2.1.1.2.3 Site Construction Superintendent The Site Construction Superintendent directs site contractors and contract management. He provides contracted craft labor and contractor

administration to Maintenance when requested ..

1.2.1.1.3 Support Services Director The Support Services Director provides Training, Materials Management, MIS Services, Security Services, and Office Support to all organizations on site.* He fulfills these: responsibilities through a staff which includes:

Materials Management Su~or---*-.-*-.::

Training Supervisor 1.2.1.1.3.1 Materials Management Supervisor The Materials Management Supervisor coordmates parts requirements, specifies and evaluates parts, procures all materials for the site, ships and receives that material and controls the on-site inventory.

Page 1-18 REVISION 63b 6/ 16/ 93 1

J. :,,

' JI ORGANIZATION SECI10N 1

1.2.1.1.3.2 Training Supervisor The Training Supervisor provides training for all site personnel as required.

1.2.1.1.4 Regulatory Assurance Supervisor The Regulatory Assurance Supervisor is the station's administrative support for regulatory matters. He assists the Site Vice President in assessing the station's regulatory performance. He assists the station in dealing with regulatory agencies and Nuclear Regulatory Services.

1.2.1.2 Nuclear Operations Manager The Nuclear Operations Manager is responsible for implementation of policy and decisions within the* Nuclear Operations Organization. He is responsible for planning and Chief Nuclear Operating Officer policy statements, procedures and instructions. The manager is responsible for all internal and external Chief Nuclear* Operating Officer communications. He is the liaison for...management training in the Nuclear Operations Organization.

1.2.1.3 Engineering and Construction Manager The Engineering and Construction Manager is the Chairman of the

-"Nuclear Engineering Committee (NEC) which is comprised of himself and the six--Site Engineering and Construction Managers. The NEC has the responsibility to establish policies and procedures to ensure that design activities are conducted in compliance with regulations and the

ASME Code in. a manner that supports safe and reliable operation. The Engineering and Construction Manager provides engineering and construction support to the nuclear stations. He is responsible for the configuration management control programs. He provides generic programs for technical and licensing issues. He provides the design for nuclear fuel and certain in-core components. The manager advises the

Chief Nuclear Operating Officer on priorities* for engineering and construction activities at the six stations. He manages the centralized Page 1-19 REVISION 63b 6116193 - I

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ORGANIZATION SECTION 1 stores facilities and services for the Nuclear Operations Division. The Manager is the designated holder of the Company's N-stamps. He notifies the Illinois Department of Nuclear Safety (the jurisdiction) of ffie location of required Code records. The Manager maintains an appointed Level ID Concrete Inspection Engineer on staff responsible for the qualification and certification- of concrete inspection and testing personnel. He fulfills these responsibilities through a staff which includes:

Nuclear Fuel Services Manager .

Electrical, Instrumentation and Control Design Supervisor Engineering Performance and Improvement Director Mechanical Structural Design Supervisor PRA and Reliability Engineering Supervisor Regulatory Assurance Supervisor Parts Stores Supervisor Nuclear Construction Supervisor 1.2.1.3.1 Nuclear Fuel Services Manager The Nuclear* Fuel Services Manager* is responsible for the design and .

monitoring of nuclear fuel. He monitors fuel reliability, provides design for reload licensing, provides the safety analysis for each reload, and provi~es support for reactor operation~

1.2.1.4 Nuclear Support Manager The Nuclear Support Manager provides support to the stations in the areas of Maintenance and Quality Control, Training, Cheni.istry, Health Physi~, Operations, Outages and Technical Support. He and his staff provide an off-site point of contact for Station Quality Control if off-site assistance is necessary for quality related matters. The Manager maintains an appointed Chief Level m Certifying Authority on staff who is responsible for qualification and certification of NQA-1 Inspection and test personnel. This person may designate deputies for certification of personnel.

Page 1-20 REVISION 63b 6/ 16/ 93

. ~*1 ORGANIZATION .SECTIONl

1.2.1.5 Performance Monitoring and Improvement Manager The Performance Monitoring and Improvement Manager provides a common resource to the Site Vice Presidents for.improvement of performance. He serves as the contact poirtt for INPO and as the coordinating point for perforinance improvement within the Nuclear Operations Department.

1.2.2 Vice President, Nuclear Oversight and Regulatory Services The Vice President, Nuclear Oversight and Regulatory Services is the principal advisor on regulatory and quality assurance matters and requirements. His departments provide all nuclear oversight activities and interactions with t}te NRC at the corporate level. He is responsible for providing reports to management concerning the status as determined by this oversight. He fulfills these responsibilities through a staff which includes:

Nuclear Regulatory Services Manager ' '

Nuclear Oversight Manager 1.2.2.1 Nuclear Regulatory Services Manager The.Nuclear Regulatory Services Manager is the administrative liaison between the Company and regulatory bodies. He coordinates division-

__wide programs that support licensing or regulatory assurance initiatives, helps in developing positions and coordinates responses to regulatory inquiries an:d notifications. He fulfills these responsibilities through a staff which includes:

Licensing Operations Director Regulatory Performance Director Emergency Preparedness and State Programs Director Director of Strategic Licensing Policies and Issues Page 1-21 REVISION 63b 6/ 16/ 93 .

. *~-*

ORGANIZATION SECTION 1 1.2.2.1.1 Licensing Operations Director __ .

The Licensing Operations Director is the liaison between the Company and the NRC staff. He is concerned with the licensing process and the

. materials issued by the NR<;:: that affect all plants.

1.2.2.1.2 Regulatory Performance Director The Regulatory Performance Director is the liaison between the Company and the NRC Region m Staff. He is concerned with inspections, SALP and Licensee Performance.

1.2.2.1.3 Emergency Preparedness and State Programs Director The Emergency Preparedness. and State Programs Director maintains the Compel!ly's readiness to respond to certain emergencies at the nuclear plants.'- He maintains the Emergency Plan and coordinates training to support the plan. ___ _

1.2.2.1.4 Director of Strategic .Licensing Policies and Issues

The Director of Strategic Licensmg Po.licies .and Issues develops and oversees implementation of CECo's policy on generic and strategic licensing issues.

1.2.2.2 __ Nuclear Oversight Manager The Nuclear Oversight Manager manages the Quality Assurance .Program and the Safety Review. He reports through the Vice President, Nuclear Oversight and Regulatory Services to the Senior Vice President, Energy Production and is independent of Nuclear Operations. The Manager must have at least four years experience in the field of quality assurance, or an equivalent number of years of nuclear power plant experience in a supervisory combination of the two. The Manager shall have at least a baccalaureate degree in Engineering or related science. The Manager may have equivalent educational qualifications in accordance with paragraph.

4.1 (items a-j) of ANSI/ ANS 3.1. He develops, maintains, and interprets Page 1-22 REVISION 63b 6/ 16/ 93 I

ORGANIZATION SECTION 1 the Company's Quality Assurance policies, procedures, and implementing directives. He conducts audits of the Company organizations re~ponsible for nuclear functions to verify that the-Quality Assurance Program is effectively implemented. The Manager verifies conformance through the Director of On-Site Quality Verification and the Off-Site Quality Verification Director and their staffs. He has the authority and responsibility to stop work when a violation of the Quality Assurance Program, procedures, specifications or drawings is identified. He *fulfills-:-.. -*

these responsibilities through a staff which includes:

,Director of On-Site Quality Verification Director of Safety Review Off-Site Quality Verification Director Quality Assurance Policy Director

1.2.2.2.l Director of On-Site Quality Verification The Director of On-Site Quality Verification provides on-site assessment of station line and support activities to ensure compliance with Quality Assurance and Nuclear Safety Requirements. He fulfills this responsibility through a staff which includes:

Independent Safety* Engineering Group Superintendent Quality Assurance Superintendent Site Quality Verification Superintendents The Director of On-Site Quality Verification and staff have direct access to the Site Vice President.for Quality Assurance and Nuclear Safety *

matters. The Director has the authority and responsibility to stop work when a violation of the Quality Assurance Program or Nuclear Safety issue is identified. The Director monitors the day-to-day station activities involving operating, modifications, maintenance, in-service inspection, refueling and. stores through on-site audits, field monitoring, and safety evaluations. *

Page 1-23 REVISION 63b 6/ 16/ 93

ORGANIZATION SECTION 1 l.2.2.2.2 Director of Safety Review The Director of Safety Review and his staff provide an independent safety review function for station activities on a routine basis. He is the contact point for industry operating experience and lessons learned information and analysis~ **

1.2.2.2.3 Off-Site Quality Verification Director The Off-Site Quality Verification Director and his staff audit internal and external organizations as required by the Quality Assurance Program.

He verifies that submitted vendors quality assurance programs comply with Company requirements. He reviews procurement documentation to assure compliance with the Quality Assurance Program. He has the authority and responsibility to stop work when a violation of the Quality Assurance Program, procedures, specifications or drawings is identified.

1.2.2.2.4 Quality Assurance. Policy Director '

The Quality Assurance *Policy Director establishes, maintains and interprets Company Quality Assurance Policy. He provides training to the Company on Quality Assurance subjects. He. and his staff control and maintain the Quality Assurance Program c:Iatabase~

1.2.3 Manager of Fuel The Manager of Fuel procures nuclear fuel and reprocessing to specifications furnished. ~y the Nuclear Fuel Services Department.

1.3 ~nior Vice President (Commercial Operations)

The Senior Vice President (Commercial Operations) is responsible for the transmission and distribution of electricity to the customers and all support activities associated with it.

Vice President, Transmission and Distribution Page 1-24 REVISION 63b 6/ 16/ 93

,, .*. ~. --

ORGANIZATION SECTION 1 1.3.1 Vice President, Transmissio!) an_d Distribution The Vice President, Transmission and Distribution is responsible for the care and maintenance of the Transmission and Distribution Systems.

T&D Operational Analysis Manager 1.3.1.1 T&D Operational Analysis Manager The T&D Operational Analysis Manager provides* specialiZed field testing services through technical specialists. He provides calibration services traceable to National Standards for measuring and testing equipment. The Manager retains supporting Quality Assurance documentation. The Manager maintains the Company's electrical testing

_ftl.c;ilities and equipment required to fulfill assigned responsibilities. His staff reviews design specifications to verify the inclusion of adequate electrical testing requirements. Also, the Manager is responsible for inspection and proof testing of electrical generation, transmission and distribution equipment. During new projects construction, the Manager directs field engineers who conduct electrical construction tests and -*-

participate in preoperational and start-up testing.

4. REFERENCES The following references were used in the generation of this section.

The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements are contained in the Q.A. Program Database. *

10CFRSO Appendix B

ANSI 18.7

ANSI/ASME NQA-1 Page 1

REVISION 63b -6/ 16/ 93

\* *,

ORGANIZATION 'SECTIONl

ASME SEC ill NCA 4000

ANSI N45.2.1 **-*

ANSI N45.2.2

ANSI N45.2.3

ANSI N45.2.4

ANSI N45.2.5 ... -*, ...-:....,._ -**"

ANSI N45.2.8

ANSI N45.2.9

ANSI N45.2.15

ANSI N45.2.20 fage 1-26 REVISION 63b 6/ 16/ 93 r

Chair11an &Chief EKecutive Officer l President I

l .3 I 1.1.1 Senior Senior Senior Vice President Vice President Vice IC011merc I a 1 Other a (Energy Production) Others President Olvlslon ) CNO (Corporate 0perat Ions) Resources I I '

I

\

I l.3. l l .2. l l .2.2 l.l.l.3 l.l.l.2 If Vice Pres ldent, Vice President Vice President, Director Transmission and Nuclear Manager of and Others Chief Nuclear Oversight and of Corporate Distribution Operating Regulatory Purchasing Security Operations Officer Services l.3. l. l T&D Operational Analysis Department, Manager

Senior

Board tlJCJear Vice President ODeratlons !Energy Production) 1.2 toniltee CNO

'----------J*: I 1.2.1 I

I 1.2.2 1.2.3 I VICI President Vice President, and Nuclear Oversight Chief Nuc Jear. and Regulatory Manager of Fuel Others Operating Off lcer Services I

1.2.t.I 1.2.2.1 1.2.2.2 Sile Nuclear Safety Nuclear Regulatory Nuclear Oversight Vice Presidents Review Board Services Manager Manager 161 Director Licensing of

_Operations Director 1.2.2.1.1 On-Site Quality* 1.2.2.2.1 Verification Regulatory Off-Site Quality Perforeance 1.2.2.1.2 Verification 1.2.2.2.3 Director Director Emergency Preparedness Director I

and 1.2.2.1.l of 1.2.2.2.2 State Programs Safety Review Director Director Of Quality Assurance Strategic licensing 1.2.2.1.* Policy 1.2.2.2.4 Policies and Issues Dlrecllor ICC sugport Staff Regulatory Services tree tor EXHJBIT I Director Page 2 of 4 REVISION 63b 6/ 16/ 93

Vice President '

and \ *' "

Chief Nuclear. ' 1.2. l Operating Officer

/1 i i" I

i i l.2.1.1 1.2.1.3 1.2.1.4 1.2.1.5 1.2.1.2 Site Engineering and Nuclear Support Performance Nuclear Operations Vice Presidents Construction Manager Monitoring and Manager (6) Manager Improvement Manager ;

i I i 1.2 ..11.3.l Nuclear Fuel I: Chief Others " Services Certifying Authority Manager Level III '

i VT Examination ASME Div 2 Level III Level III (Concrete)

EXHIBIT 1 Page 3 of 4 t'.I 1 t'.I O'l

Site Vice Presidents 1.2.1.t.

161 I

. I 1 .. ~.1.1.1 I t.2.t.t.4 I 1.2.l.l.3 I1.2.t.l.~

/i Regulatory SUpport Services Site Engineering '

l Lon~ - Range Station Mana.ger Assurance Director War Control and Construction Supervisor Superintendent Manager 1.2.l.l.l.t t.2.1.1.3. I 1.2.1.t.2.t

-- Operations Man.ger - Materials ManagHent Supervisor Others

(

\

....__ Station Support Engineering Supervisor 1.2.l.l.l.2 l.2. l.1.3.2 1.2.t.t.2.2 I~

;~

-- Technical Services superintendent ....__

Training S~pervisor

....__ Modification Design Superv lsor I

l.2.1.l.t.3. i 1.2.l.t.2.3

-- Maintenance Superintendent

-- Site Construction Superintendent 1.2.l.t.t.4

....___ Work Control Modification Superintendent '-- Ad11lnlstrator EXHIBIT I Page 4 of 4 REVISION 63b 6/ 16/ 93

senior Vice President

!Energy Productlont CNO I

I I J

VICI President, tllclear Overe 11ght end Regulatory

. ServlcH vtce President and Chief taicJear Operating Officer Ir -~*---------,

I '

I I

Engineering I tllclear and I Pro Sect Overelght Manager Conetructlon Manager *- Manager I

Site Onelte Enatneertng OualltJ and Verlflcat an Construction Manager Station Manager Startup

~ Superintendent Regulatory

- Assurance Supervisor E*hlbll 2 New Plant ..... Support Construction Services Dr,anuauan Director FUTUAEt REVISION 63b 6/ 16/ 93

~ ' ..

1o *** ' (

QUALITY ASSURANCE PROGRAM SECTION 2

1. POLICY It is the policy of the Company to have -a Quality Assurance Program that:

a. Complies with ASME Code, Federal Regulations, and other

. 'requirements.

b. Defines and documents the requirements and commitments that, when implemented, protect the health and safety of the public and .our workers.

c. Serves to protect the interests of the Company.

2. RESPONSIBILfl'IES

-An departments involved in the production of nuclear power are governed by this program and are responsible for carrying out the requirements of this section. These departments include:

a. Nuclear Operations Division

. b. Nuclear Stations c.. Site Regulatory Assurance Department d.- Site Material Management Department ..

e. - Site Engineering-and-Construction Department *

f. Engineering and Construction* Department

g. Nuclear Support Department

h. Performance Monitoring and Support Department

i. . Nuclear Operations Staff

. Nuclear Regulatory Services-Department J*

k. Nuclear Oversight Department

1. Purchasing Department

m. Corporate Security Department

n. Systems Materials-Analysis Department

o. -T&D Operational Analysis Department. .

Page 2-1 REVISION 63a 5/20/ 93

~ '~ , .. *.* ......- *- .,

QUALin' ASSURANCE PROGRAM SECTION 2

3. REQUIREMENTS 3.1 General Either regulation or the Company, independent of regulations, requires the activities of the Quality Assurance Program. As such, this program

meets the intent of the word "shall" as used in regulations and ANSI and ASME documents. * *-* --"- .. -*

This program applies without limitation to safety related or ASME Code structures, systems, components, and activities. It also applies as described in Section 19 to regulatory related structures, systems, components and activities to a degree consistent with their importance to safety.

This Quality Assurance Program is in effect during all phases of the design, fabrication,_~ection, testing, operation and decommissioning of the Company's nuclear power plants. "Operation" includes operation, maintenance, repair, modifi~tion, refueling, and in-service inspection.

The Quality Assurance Program takes into account the need for special controls, processes, test equipment, tools, and skills necessary to attain the required quality and the need for the verification of quality by inspection and test. . -. . , * *

This Quality ~µranee Program co~plies with the qqaUty. requirements of: . .. ... * * , . * . . .

a. 10CFRSO

1. paragraph 55a

2.

paragraph SS(e)

3. paragraph 59

4. Appendix A *

5. Appendix B .

6. App~dix R Page 2-2

--~-~ .. ,

. REVISION 63a 5/ 20/ 93

QUALITY ASSURANCE PROGRAM. . SECTION 2

b. 10CFR21

c. -* 10CFR71 Subpart H . --.

d. AS:ME Boiler and Pressure Vessel Code (CODE) Section ill (NCA 4000), Division 1 and Division 2, 1992

e. AS:ME Code Section XI, 1992

f. ANSI/ ANS 3.2, 1988

g. ANSI/ AS:ME NQA~ 1-r-1989 (la, lb)

h. ANSl/AS:rvIB NQA-2, 1989

i. ANSI/ ANS 3.1, 1981 This Quality Assurance Program complies with the programmatic quality requirements of the following standards. Specific work.practices

.and acceptance criteria are reflected in implementing procedures.

J*

k.

1.

ANSI N101.4, 1972 AWS Dl.1-80 IEEE Standard 323, 1974 Because of compliance with the above list of standards, this Quality Assurance Program also complies with the regulatory positions of the following Regulatory Guides:

a. 1.26 Rev 3 e. . 1.54 (6/73)

b. 1.28Rev 3 f. 1.68 Rev 2

c. 1.29 Rev 3 g. 1.143 Rev 1

d. 1.33 Rev 2 h. 4.15 Rev 1

--.:..i~*#,. ~

Page 2-3 REVISION 63a -5/ 20/ 93

QUALITY ASSURANCE PROGRAM SECTION 2 ANSI/ ASME NQA-1, 1983 and ANSI/ ASf\.IB NQA-2, 1986 were written to replace ANSI N45.2 and selected daughter standards. Among thffi.~.

the Company had previously been committed to:

a. ANSI N45.2.1, (1973) f. ANSI N45.2.8, (1975)

b. ANSI N45.2.2, (1972) g. ANSI N45.2.9, (1975)

c. ANSI N45.2.3, (1973) h. ANSI N45.2.1 l, (1974)

d. ANSI N45.2.4, (1974). 1. ANSI N45.2.13, (1976)

(IEEE STD 336)

e. ANSI/ ASME N45.2.5, (1978)

Because this program complies with NQA-1 and the programmatic requirements of NQA-2, the intent of the following Regulatory Guides is also met:

a. 1.30 Rev 0 h. 1.88 Rev 2 b.

1.37 Rev 0

1. 1.94 Rev 1

c. 1.38 Rev 2 J* 1.116 Rev 0

d. 1.39 Rev 2 k. 1.123 Rev 1

e. 1.58 Rev 1 1. 1.144 (9 /80)

f. 1.64 Rev 2 -.*--..:..:::: m. 1.146 ($/78)

-. --(

g. 1.74 (2/74)

The Company's Nuclear Units have differing effective Operating License dates. Each plant's SAR and/ or Technical Specifications documents the extent of commitments to technical requirements of Regulatory Guides, Safety Guides and/ or ANSI Standards. However, this quality assurance program applies to all operations and includes those quality requirements contained in the documents listed in this section.

Page 2-4 REVISION 63a 5/ 20/. 93

QUALITY ASSURANCE PROGRAM SECTION 2 Also, the Company requires that each of its vendors maintain a quality assurance* program which satisfies the applicable portions of:

a. ANSI/ ASME NQA-1 and ANSI N45.2 Standards not covered by ANSI/ ASME NQA-1 or the ANSI/ ASME N45.2 series of standards for previously accepted, non-ASME quality programs.

b. ANSI/ ASME N18.7 . ~- ......- ... Standards

c. ANSI/ ASME N626.3, 1988, for firms supplying ASME Code design services.

3.2 Planning 3.2.1 General Af1: quality activities are planned to achieve their *objectives. Such planning includes review of relevant requirements. Planning establishes the. systematic, sequential progression, of actions to meet the defined requirements.

The Company documents these *plans in appropriate communications, .

approvals, instructions, and procedures..

3.2.2 Controlled Conditions

.Activities described in this program are accomplished u,nder controlled

conditions. Controlled conditions include appropriate equipment, qualified personnel, suitable environment, and use of appropriate procedures.. Other sectio_ps of this program descripe these controlled conditions.

3.2.3 Program Planning An Audit Program will be planned and conducted in accordance with Section 18 of this- program .

- Page 2-5 REVISION 63a 5/ 20/ 93

.-~._,..

. *QUALITY ASSURANCE PROGRAM .SECTION 2 A Design Program will be planned and conducted iri accordance with Section 3 of this _program.

"'7 * **-...

A Procurement Program will be planned and conducted in accordance with Sections 4, 7, 8, and 13 of this program.

3.3 Program Description The Company's total program for E!Ovid.ing administrative controls and quality assurance is incorporated in many diver~e _documents. Exhibit 1 shows the relationship among the most important classes of these documents for the Quality Assurance Program. This document is the QA

-Program and serves as the company policy directive for Nuclear Quality Assurance. Nuclear Operating Policies may provide implementation of this program. At the interdepartmental level, the Special Process Procedure Manual and the QA Directives describe interdepartmental requirements to implement the QA Program. Nuclear Operating Directives may also provide implementation of the QA Program at this level. At the intra-departmental level, implementing procedures are written to the extent necessary to assure consistent results by all departments which implement the Policy and the QA Program.

Approved procedures and instructions implement the quality requirements. Line, staff, administrative, and quality oversight organizations issue these implementing procedures. All activities affecting quality are described in sufficient detail to assure *quality.

The implementation of the QA Program will be tracked by the Quality Assurance Database. In the interim, the Quality Procedtires serve as the

implementing documents for the Quality Assurance Program. Quality Procedure 2.0 provides a description of the implementation of the program and the relationship between the QA Program and the existing Quality Procedures until the Quality Assurance Database is operative for this function. - _"' . ~ ~

The Quality Assurance Program Database summarizes the sources of requirements and the relationship among them and the QA program.

- Page 2-6

REVISION 63a 5120193

QUALITY ASSURANCE PROGRAM SECTION 2 3.4 Indoctrination & Training Personnel performing activities affecting quality are oriented, indoctrinated, and trained as necessary to assure achievement and maintenance of suitable proficiency. Training programs are developed to indoctrinate, qualify and/ or certify personnel in specific activities in which they will be engaged. These training programs include:

a. Quality Assurance Program

b. Quality principles

c.

Company policies

d. Implementing pr~cedures Training is conducted in a time frame adequate to prepare personnel for their job responsibilities and is an extension of formal education or work experience. Training required for specific qualifications or certifications is conduft~ _and documented in accordance with applicable regulations and requirements including the requirements of NQA-1. Qualification documents specify functions and basis of qualification. Personnel

performing or verifying activities affecting quality are tested to det_ermine if established levels of knowledge and proficiency are attained.

Proficiency of* personnel performing and verifying activities affecting ..

quality is maintained by retraining, reexamining and/or recertifying as

determined by management* or reqttirro by Code.

\

Training and certification of personnel associated with nondestructive examination are carried out in accordance with the requirements of NQA-1 and ASME Section ill, NX~5520. A Level ill certified person administers all Code examination activities:

Training and certification of personnel associated with concrete containment inspections is in accordance with Appendix VII of ASME Section m, plvision 2. The per.fad of qualification for concrete inspectors is three years .

Page 2-7 REVISION 63a 5120193

QUALITY ASSURANCE *PROGRAM SECTION 2 Vend or personnel engaged in inspection, examination and testing activities will be trained, qualified and certified to perform their specific activity under the above requirements.

3.5 Program Review The Company regularly reviews the status and adequacy of the Quality Assurance Program. Reports to management described in Sections 1._ and 18 of this Program fulfill this requirement. Vendors are required to perform regular reviews of the status and adequacy of their quality assurance programs. The Nuclear Oversight Department defines and measures the overall effectiveness of the Quality Assurance Program.

The independence of the Nuclear Oversight Department is described in Section 1 of this program. Nuclear Oversight uses its own audits and evaluations in determining quality assurance program and corrective action effectivenes_~-~ described in Sections 16 and 18 of this program.

Independent reviews are described in Section 18 of this program.

3.6 Quality Assurance Manual The Company Quality Assurance Manual consists of this Quality Assurance Program document, and the Quality ~urance Program Database. The Quality Assurance Program Database contains: *

a. The Quality Assurance. Program

b. The pertinent parts of source documents

\

c. Cross-references among these elements

d. Cross-references to the responsible departmeI'lts and implementing procedures.

The Manual is available .to Company personnel, NRC personnel, the Authorized Nuclear *1nspector, and other regulatory authorities. The Page 2-8 REVISION 63a 5/ 20/ 93

,*-~-,.

QUALITY ASSURANCE PROGRAM SECTION 2 Company submits revisions to the Quality Assurance Program document (as the Topical Report) to the NRC for acceptance as follows:

a. Programmatic changes which reduce commitments must be accepted prior to implementation.

b. Substantive changes (Organizational, operational, etc.) will be submitted within 30 days of effective date.

c. Changes, editorial changes, reassignments which do not reduce commitments may not be submitted at the time of the change, but are submitted at least annually.

The Authorized Nuclear Inspector Supervisor accepts proposed changes before they are put into effect. Changes are distributed.

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in this section. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFR50 APPENDIX B Criteria 2

ANSI/ASME NQA-1

ANSI N18.7

ANS 3.2

ANSI N45.2

ANSI N45.2.11

ANSI N45.2.9

ASME Code Section ill NCA-4000 Page 2-9 REVISION 63a 5120/93

-QUAL11Y ASSURANCE PROGRAM SECTION 2

ANSI N45.2.3

ANSI N 101.4

LaSalle, Station P3AR 7I 83

Byron/Braidwood Stations P3AR 9 /79

ANSI N45.2.4

IEEE N45.2.l

ANSI N45.2.l

ANSI N45.2.S

ANSI N45.2.13

ANSI N45.2.8

Technical Specifications:, Byron, Braidwood, Dresden, LaSalle, Quad Cities, Zion Stations Page 2-10

REVISION 63a . 51 201 93 * \_

~.

Policy, Directive, EXHIBIT 1 1*

& Procedure '

. /i Hierarchy REVISION 63a 5/ 20/ 93 NUC.OPs CONTROLLED MEMOs IMPLEMENTING PROCEDURES

~, .. -:.*.

DESIGN SECTION 3

1. POLICY Design, de5ign interfaces, and design changes shall be defined, controlled and* verified. *

2. RESPONSIBILI'IIES The following departments are responsibl~ for carrying out ~e requirements of this section: * *

a. Nuclear Stations

b. _Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Nuclear Oversight Department

f. ~chasing Department

g. Systems Materials Analysis Department

h. T&D Operational Analysis Department

.. . \ , ,,

The Company assigns responsib~ty for specific requirements through the_ Quality Assurance Pro~ Data Base.

3. REQUIREMENTS The Engineering and Construction Department and the Site Engineering

and Construction Department are responsible for overall design and design* control of mechanical, electrical, instrumentation and control,

structural and nuclear related systems and components. The Nuclear Fuel Services Department is responsible for reactor core design analysis,

. core design specifications and design reviews, for nuclear fuel and in-core components. Specific responsibilities for these departments are stated in Section 1. * *

Page 3-1 REVISION 63a 5/ 20/ 93

.*~-*

. ~~ ;:

. DESIGN SECTION 3 Design control involves independent review and evaluation of design documents. These design evaluations or -feviews are conducted to written procedures and include consideration of quality standards, quality assurance requirements, materials suitability, process suitability, interface control, analytical or testing requirements, design basis, and configuration management.

3.2 Design Input Design inputs, such as design bases, performance requirements, regulatory requirements, codes, and standards shall be identified and documented. Their selection shall be reviewed and approved by the responsible design organization. The design input shall be specified and approved in a timely manner and* to the level of detail necessary to provide a consistent basis for making design decisions, accomplishing design-Verification~ and evaluating design changes. Changes from approved design inputs, including the reason for the changes shall be identified, approved, documented, and co:ittrolled.

3.3 Design Process

The responsible design 9rganization shall prescribe and document the design activities in a timely* manner and to the level of detail necessary to permit verification that the design meets requirements. Included in this I scope_ of activities are considerations for field engineering; physics; I seismic, stress, thermal, hydraulic, and radiation factors; the Safety I Analysis accident scenarios; and accessibility for inservice inspection, I maintenance and repairs. Design documents shall be adequate to support I facility design, construction, and operation. Selection of the appropriate quality standards shall be documented, -reviewed and approved.

Reasons for changes. from specified quality standards,. shall be identified, documented, approved and controlled. Design methods~ matetials, parts, equipment, and processes that are essential to the function of the structure, system, or component shall be selected and reviewed for suitability of application.. Applicable industry experience, as set forth in reports or other documentation, shall be made available to cognizant design personnel. The final design output documents and approved Page 3-2 REVISION 63a S/ 20/ 93

DESIGN .

SECTION 3 changes thereto shall be relatable to the design input by documentation in sufficient detail to permit design verification. The final design shall identify assemblies and/or components that are part of the item being designed. If materials, parts, equipment, or processes are different from the published vendor information, these differences shall be documented.

3.4 Design Analyses Design analyses shall be performed in a planned, controlled, and documented manner. Design analysis documents shall be legible and suitable for reproduction, filing, and retrieval. They shall be sufficiently detailed as to purpose, method, assumptions, design input, references, and units such that a person technically qualified in the subject can independently review and verify the analyses and its results.

Calculations_ shall be .identified for retrievability by subject including strUcture, system, component, originator, reviewer and date or by ~ther unique identifiers.

Computer programs may be utilized for design analysis .without .

individual verification of the program for each application provided:

a. The computer program has been verified to show that it produces correct solutions for the encoded ma~ematical

_ model within defined limits for each parameter employed;.

and

b. The encoded mathematical model has been shown to prodll:ce a valid solution to the physical problem associated with the particular application.

Computer programs shall be controlled to assure that changes are documented and approved. Verification shall be required for changes to.-

previously verified computer programs including evaluation of the effects of these changes on (a) and (b) aboye.

Page 3-3 REVISION 63a . 5/ 20/ 93

DESIGN SECTION 3 Documentation of design analyses shall include:

a. 'Statement of the objective of the -analyses,

b. List of design inputs and their sources,

c. ResWts .of_ literature searches or other applicable background data,

d. List of assumptions and indication of those that must be verified as the design proceeds, - -*-- ~-

e. List of any computer calculation and the bases for its use, and

f. Review and approval.

3.5 Design Verification Design adequacy shall be verified by one or more of the following:

p~ormance of design reviews, use of alternate calculations, or performance of qualification tests. The design verification method(s) used shall be identified and documented. The results of design '

verification shall be documented including the identification of the verifier. Design verification shall be performed by competent individual(s) other than those who performed the original design.

Cursory supervisory reviews do not satisfy the intent of design verification*.

Verification shall be performed in a timely manner. Design verification, for the stage of design activity accomplished, shall be performed prior to release for procurement, manufacture, construction, or release to another org~tion for use in other design activities provided sufficient data exists. Any unverified portion of the design shall be identified and controlled. In all cases the design verification shall be completed prior to relying upon the component, system, structure, or computer program to perform its function.

Page 3-4 REVISION 63a 5/ 20/ 93

DESIGN SECTION 3 3.5.1 Extent of Design Verification.

The extent of the design verification required is a function of the importance to safe.ty, the complexity of the design, the degree of standardization, the state of the art, and the similarity with previously proven designs. Where the design has been subjected to a verification process, the process need not be duplicated for identical designs. For each application the applicability of standardized or previously proven designs_ for design inputs shall be _verified. Known problems affecting the standard or previously proven designs and their effects on other features shall be considered. The original design and associated verification shall be adequately documented and referenced in subsequent applications. Design verification shall be required for changes to previously verified designs. This includes evaluation of the

-effects of those changes on the overall design and on any affected design analyses.

3.5.2 Methods Acceptable verification methods include one or more of the following:*

design reviews, alternate calculations, and qualification testing. ~,,

.. ~3.5.2.1 Design Reviews Critical design reviews shall provide assurance that the final design is correct and satisfactory.

3.5.2.2 Alternate Calculations Calculations or analyses shall be made with alternate methods to verify correctness of the original calculations or analyses. The appropriateness of assumptions, input data used, and the computer program or other calculation method used shall be reviewed.

Page 3 REVISION 63a 5/ 20/ 93

DESIGN SECTiON 3 3.5.2.3 Qualification Tests When design adequacy is verified by qualification tests, the tests and test"*

configuration shall be identified. Testing shall demonstrate adequacy of performance under conditions that simulate the most adverse design conditions. Where the test is intended to verify only specific design features, the other features of the design shall be verified by other means.

Test results shall be documented and evaluated by the responsible design organization to assure that test requirements have been met. . .-"'..* -****- _....

If qualification testing indicates that changes to the item are necessary to obtain acceptable performance, the change shall be documented and

verified to assure satisfactory. performance.

3.6 Change Control Changes to final designs, field changes, modifications to operating facilities, and nonconforming items dispositioned use-as-is or repair shall be justified and subject to design control measures commensurate with those applied to the original design. These measures shall include assurance that the design analyses for the structure, system, or component are still valid. Changes shall be approved by the same affected groups or organizations which reviewed and approved the original design documents. In the case where the original organization iS no longer responsible for design approval, then a new responsible design organization shall be designated. The designated organization shall have demonstrated competence in the specific design area of interest and have an adequate understanding of the requrrements and intent of the original design.

When a design change is approved other than by revision to the affected design documents, measures shall be established to incorporate, where appropriate, the change into these doQllllents.

Where a significant design change is necessary beeause of an incorrect design, the design process and verification procedure shall be reviewed and appropriate action taken.

Plant personnel will be made aware of design changes/modifications which may affect the performance of their duties. --

Page 3-6 REVISION 63a 5/ 20/ 93

DESIGN SECTION 3

3.7 .Interface Control Design interfaces shall be identified and controlled. The company shall coordinate design efforts among the participating organizations.

Interface controls shall include the assignment of responsibility and the establishment of procedures among participating design organizations.

Controls shall be for the review, approval, release, distribution and revision of documents involving design interfaces .

~--- .... *:!!!!""~

Design information transmitted across inter~aces shall be documented and controlled.

3.8 Documentation and Records Specific requirements are stated in Section 6 and Section 17.

4. REFERENCES

The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B

ANSI Nl8.7

ANSI/ ASME NQA-1

- ASME Section m; NCA4000

Page 3-7

REVISION 63a 5/ 20/ 93

PROCUREMENT DOCUMENT CON1ROL SECilON4

1. POLICY This section identifies the requiremex:.its for preparation, review and retention of procurement documents.

2. RESPONSIBILil'IES The following departments are responsible for carrying out the ... --* .......;"-, .. _ -**"

requirements of this section:

a. Nuclear Stations

b. . Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Nuclear Oversight Department

f. Purchasing Department .

g. Systems Materials Analysis Department

h. T&D Operational Analysis Department The Company assigns responsibility for specific requirements through the . Quality Assurance Program Data Base.

3. REQUIREMENTS 3.1 General The Company establishes procedures for the*preparation and review of procurement documents. Procurement documents at all tiers include or reference requirements that are deemed necessary to assure adequate quality. These requirements include reference to 10CFR21 when applicable.

. Page 4-~ REVISION 63a 5/ 20/ 93

PROCUREMENT DOCUMENT CON1ROL SECTION 4 3~2 Supplier QA Program Requirements Procurement DOeuments require:

a. Each vendor who supplies safety related items or services has and implements a quality assurance program that meets the requirements of 10CFRSO Appendix B. .

b. For purchases of ASME Code items or services, the vendor's quality assurance program,.is<onsistent with the applicable requirements of the Code.

c. Section 7 contains specific exceptions to these requirements.

3.3 Content of Procurement Documents Procurement documents at all tiers include the following as deemed necessary by the Company.

3.3.1 Scop~ of Work._.

Procurement documents describe the scope of *the items or services to be furnished by a vendor.

3.3.2 Technical Requirements The Company specifies technical requirements by reference to specific drawings, specifications,*codes, standards, regulations, procedures, or instructions (including revisions thereto) that describes the items or services to be furnished. The procurement documents identify test, inspection and acceptance requirements. The procurement document ideritifies special instructions ana requirements for such activities as designing, id~@c:.ation, fabrication, cleaning, erecting, packaging, handling, shipping, and ~tended .storage.

Page 4-2 REVISION 63a 5120/93

PROCURE:MENT DOCUMENT CONTROL SECTION 4

3.3.3 Extension of QA Program to Subtier Suppliers Procurement documents require the vendors to incorporate quality assurance program requirements in subtier procurement documents.

3.3.4 Right of Access for Inspection and Audit Procurement documents provide for access to the vendor's facilities and records for inspection or audit by_ the Company or its designated representative.

3.3.5 Nonconformances Procurement documents include requirements for reporting and

approving th~ disposition of nonconformances.

3.3.6 Documentation Requirements Procurement documents identify the documerttation_requirements including: *

a. Required quality assurance records.

b. Those records to be transmitted to the Company.

c. Time of submittal.

d.

The retention-time and..method of disposition of those records the vendor retains.

3.3.7 Spare and Replacement Parts The procurement documents require the identification of appropriate spate and replacement parts or assemblies and the appropriate delineation of the technical and quality assurance related data required for ordering these parts or assemblies.

Page 4-3 REVISION 63a 5/.20/ 93

PROCUREMENT DOCUMENT CONTROL . SECTION 4 3.4 Procurement Document Review The Company reviews procurement documents to assure that they include the necessary technical and quality requirements before release for bid and contract award. Records concerning the review and evaluation of procurement documents include, in whole or in part:

a.

Minutes of meetings, ... ~~* -.;'"-, .. _ -****

b.

Comment letters,

c. Design review records,

d. Project quality assurance audits and

e. A copy of the original design document marked with comments or latest revisions.

These records are kept in the Company department fil~s, vendor files, or both locations. Trained personnel who are qualified in QA practices and concepts review procurement documents for adequacy of the referenced quality requirements. They document concurrence in the adequacy of the specified quality requirements.

3.5 Control of Procurement Document Changes Changes to proct.Irement documents are subject to the same review and approval as the original documents. Procurement doeuments incorporate Changes made-because of bid evaluations..ar:.:Contract negotiations. The review of these changes and their effects are completed before contract award. The review of changes includes the following:

j._,'.

a. The appropriate requirements specified in paragraph 3.3 of this section. *

b. Determination of any additional or modified design criteria.

c. Analysis of exceptions or changes requested by the vendor.

d. Determination of the effects these changes may have on

1) the intent of the procurement documents or

2) quality of the procurement documents or

3) quality of the item or service to be furnished.

Page 4-4 REVISION 63a 5120193

~

PROCURE:MENT DOCUMENT CON1ROL SECilON4

Reviews required by this section are done by personnel who have:

a. Access to the pertinent information and

b. Understanding of the requirements and intent of the procurement documents.

4. REFERENCES

. The following references wer~_ µ§~Ci in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

---

10CFRSO Appendix B

ANSI N18.7

ANSI N45.2

ANSI/AS:ME NQA-1

ASME Code Section ill, NCA-4000

ANSI N45.2.13

Page 4-5 REVISION 63a 5/ 20/ 93.

INsrRUCilONS, PROCEDURES AND DRAWINGS . SECilON 5

1. POLICY Activities governed by the Common~ealth Edison Company Quality Assurance Program shall be performed as directed by documented instructions, procedures, and drawings appropriate for the activity.

The requirements for the use of these procedures shall also be prescribed in writing. These instructions, procedures, and drawings shall include acceptance criteria as applicable or appropriate for the activity. . .. -* -:.. _-*

Those participating in any activity shall be aware of and use the proper and current revision of instructions, procedures, drawings and engineering requirements for performing the activity.

2. RESPONSIBILI'IIES Nuclear Operations is responsible for the preparation and implementation of Nuclear operations Directives necessary to accomplish the Nuclear Station activities in a uniform and systematic manner.

The Nuclear Stations provide operations procedures and instruction$.

These procedures will be consistent with NRC license requirements for administering the policies, procedures, and instructions to assure safe

.operation from the time that the Operating License is issued through the

-life of the station.

Any Commonwealth Edison Company departmental group involved with nuclear plant design, procurement, maintenance, modification, construction, or operation may propose procedures, as necessary, to meet regulatory, ASME Code or other applicable code requirements. These departments include:

a. *Nuclear Operations Division

b. Nuclear Stations

c. Site Regulatory Assurance Department

d. Site Material Management Department

e. Site Engineering and Construction Department

Page 5-1~

REVISION 63a - SI 201 93

INSIRUCTIONS, PROCEDURES AND.DRAWINGS SECilON 5

f. Engineering and Construction Department

g. Nuclear Support Department

h.

Performance Monitoring and Support Department

. Nude~

1. Operations Department Nuclear Regulatory Services Department J*

k. Nuclear Oversight Department

1. Purchasing Department

m. Corporate Security Department

n. Systems Materials Analysis Department

o. T&D Operational Analysis- t>epartment P* Manager of Fuel The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUIREI\IBNTS 3.1 Preparation and Review Procedures shall be prepared, reviewed, approved, and used as prescribed in writing and shall contain sufficient detail to perform the required actions. Where appropriate, these procedures will include checklists containing the necessary attributes to *be observed or measured.

The procedures will be independently reviewed and evaluated by other involved departments with interface responsibilities and the comments forwaraed to the issuing department.

3~2 General Operation, maintenance, or modification of eqliipment s~ be preplanned and_ performed in accordance with written procedures appropriate to the circumstances and which conform to applicable codes, standards, specifications and criteria. When ASME Code work is involved, these documents shall include applicable code requirements and shall be made available to the Authorized Inspector for review and insertion of hold points as applicable.

.Page S-2

REVISION 63a S/ 20/ 93

INSIRUcnONS, PROCEDURES AND DRAWINGS SECTION 5 Temporary procedures may be issued to provide guidance in unusual "situations which are not within the scope of the normal procedures.

Temporary procedures shall be subject to review and approval, and shall include designation of the time period during which they may be used.

In the event of an emergency not covered by an approved procedure,.

authorized personnel shall provide appropriate direction to minimize ,

personnel injury and damage to the facility and to protect the health and -:,._ -*

safety of plant personnel and the general public.

4. REFERENCES .

The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2 Specific references for the requirements listed Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B Criterion V

*10CFRS0.ss

ASME B&PV Code, Section ill, NCA-4000

ANSl/ASME NQA-1

_ANSI N18.7

ANS-32 1988 --~ .... _

ANSIN452

ANSI/ ANS 32

ANSI N45.211

ANSI N452.13

Facility Operating Licenses (Technical Specifications)

Page S-3 REVISION 63a 5/ 20/ 93

DOCUMENT CON1ROL SECTION 6

1. POLICY The preparation, issue and change of documents, (e.g., instructions, procedures and drawings) shall be controlled by the Company to assure that correct documents are used. For all activities affecting quality these controls will include:

a. A review for adequacy, completeness and correctness;

b. An approval for release by authorized personnel; and

c. The distribution-to;** and use at, the location where the activity is performed.

2. RESPONSIBILl'l'IES Any Commonwealth Edison Company organization involved with--the preparation, issue, and change of documents affecting quality for nuclear plant.activities shall establish procedures necessary to implement the requirements of this section. These departments include:

a. Nuclear Operations Division

b. Nuclear Stations

c. Site Regulatory Assurance Department

d. Site Material Management Department

e. Site Engineering and Construction Department

f. Engineering and Construction Department

g. Nuclear Support Department

h. Performance Monitoring and Support Department

i. Nuclear Operations Staff J* Nuclear Regulatory Services Oepartment

k. Nuclear Oversight Department

1. Purchasing Department

m. Corporate Security Department

n. --*-"*--Systems Materials Analysis Department

o. . T&D Operational Analysis Department

Page 6-1

REVISION 63b 6/.16/ 93

DOCUMENT CONlROL SECTION6 Individuals participating in any activity shall be made aware of and use proper and current documents. . *-*

The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUIREMENTS 3.1 Document Preparatio11; Review, Approval, Issuance and Distribution Document control measures shall provide for:

a. Identifying individuals or organizations responsible for preparing,. reviewing,. approving and issuing documents including revisions.

b. Identifying and assuring that proper documents are used in performing this activity.

-~-----

c. Coordinating and controlling interface documents.

d. Establishing lists of documents required to be controlled by organizations involved with activities affecting quality.

e. Distri!Juting documents ~pp~veq_ for issuance in accordance with updated and current disfriliution lists.

3.2 *Document Changes Changes to documents shall be reviewed and apP-roved by the same organizatiol1$ that performed the original review and approval unless designated to another responsible organization. The reviewing organization shall have access to pertinent background data or

~ormation upon which to base their ~proval. Minor changes to documents, such as _editorial corrections, may not require that the._revised Page 6-2 REVISION 63b 6/ 16/ 93 . * *

':.!: *I

.DOCUMENT CONTROL SECTION 6 documents receive the same review and approval as the original documents. To avoid a possible omission of a required review, procedures will be established to control minor changes.

3.3 General Procedures developed to control documents shall meet the requirements of ANSI N18.7.

Procedures shall be -reviewooaria approved prior to initial use. The frequency of subsequent reviews shall be* specified by the Company and shall be at an interval of 24 months or less unless justification for a longer interval between reviews has been established. Based on this justification, certain classes of procedures may not require a formal review cycle. The reviews will be accomplished by individuals e:>f:h~r than the originator, knowledgeable in the area affected by the procedure.

Document controls required by AS:ME Section ill, Division 1 and Division 2 are as stated in the AS:rv.IE Code Interface.

AS:rv.IE Code documents will.be made available to the authorized Nuclear Inspector.

Document control procedures shall assure that proper documents are accessible and are being used. Obsolete documents are to be recalled or

--*identified.

The scope of the document control program is to be defined. Examples of documents to be controlled include, but are not limited to: as-built drawings, engineering calculations, design specifications, computer codes, purchase orders anQ related documents, audit and surveillance procedures, operating procedures, emergency operating procedures, technical_s,p~ications, nonconformance reports, corrective action reports, work instructions and procedures, calibration procedures, quality verification procedures, inspection and test reports, Safety Analysis Reports, and Topi~al Reports.

Page 6-3 REVISION 63b 6/ 16/ 93

.--~-'*'

\\

.DOCUMENT CONlROL . SECTION 6

4. REFERENCES The following references were used in the generation of this section. --Th~

Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B Criteria 6

ANSI/ ASN.IE NQA-1 - ----- --- ....~

ASN.IE B & PV Code, Section m, NCA-4000

ANSI Nl8.7

ANSI N45.2

ANSI N45.2.l 1

ANSI/ ANS-3.2 Page 6-4

REVISION 63b 6/ 16/ 93

-~**** _.. *-

CONlROL OF PURCHASED MATERIAL~

EQUIPMENT, 'AND SERVICES SECTION7

1. POLICY This section establishes the qualify' system elements and related policies that assure the quality of purchased material, equipment and services.

2. RESPONSIBILfllES The following departmen~ are responsible for carrying out the requirements of this section:

a. Nuclear Operations Division

b. Nuclear Stations

c. Site Material Management Department .

d. Site Engineering and Construction Department

e. Engineering and Construction Department

f. Nuclear Oversight Department

g. Purchasing Department ,.

h. --- -Corporate Security Department

i. Systems Materials Analysis Department *

j. T&D Operational Analysis Department The Company assigns responsibility for specific requirements through the Quality Assurance Program. Data Base.

3. REQUIREMENTS 3.1 Supplier Selection 3.1.1 General The Company establishes measures to assure that purchased material, equipment and services conform to the procurement documents .

Page 7-1 REVISION 63b 6/ 16/ 93 I

CONTROL OF PURCHASED-MATERIAL, EQUIPMENT, AND SERVICES SECTION7 3.1.2 Company Responsibilities The Company assigns responsibilities in the supplier selection process to the following organizations:

a. The Nuclear Oversight Department evaluates the Quality Program.

b. The following departments, as appropriate, evaluate vendors technical capabilities:

1) Engineering and Construction Department

2) Site Engineering and Construction Department

3) Nuclear Stations

4) T&D Operational Ancilysis Department

5) System Materials* Analysis Department .

3.1.3 Methods.

The Company establishes measures for evaluation and selection of procurement sources.

These measures include one or more of the following:

a. . Evaluation of the supplier's history of providing an identical or similar product that performs satisfactorily in actual use.

b.

Vendor's current quality records supported by documented qualitative and quantitative information that can be

objectively evaluated.

c. Vendor's technical and quality capability as determined by a direct evaluation of his or her facilities and personnel and the implementation of his or her quality assurance program.

The Company documentS. and files the results of these measures.

Page 7-2 REVISION 63b 6/ 16/ 93 I

.-~-*

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES. SECTION7 3.2 Bid Evaluations The Company reviews and evaluates bids and awards contracts using written procedures. The results shall be documented. The Company reviews bids to assure that they conform to the procurement document requirements .. Individuals or organizations designated to evaluate the following subjects make the bid evaluation as applicable to the type of procurement:

a. Technical considerations.

b. . Quality assurance requirements.

c. Research and development effort.

d. Supplier's personnel

e. Supplier's production capability.

f. Supplier's past performance.

g. Alternates.

h. .Exceptions.

The Company obtains commitments to resolve unacceptable conditions resulting from the bid evaluation before award of the contract.

3.3 Supplier In-Process Control 3.3.1 General The Company establishes measures to interface with vendors and to verify vendor's perforinance. The measures include the following: *

.a. Establishing an understanding between the company and

--* ' vendor.

b.

Requiring the vendor to identify planning techniques and .

processes to be used in fulfilling procurement document requirements.

Page 7-3 REVISION 63b 6/ 16/ 93

CON1ROL OF PURCHASED MATERIAL,

. EQUIPMENT, AND SERVICES SECl10N7

c.

Reviewing vendor documents that are generated or processed during activities fuHilling procurement requirements.

d. Identifying and processing necessary change information.

e. Establishing method of document information exchange between the Company and vendor.

f. Establishing the extent of source surveillance and inspection activities.

3.3.2 In-Process Control and Verification Planning.

Depending on the complexity or scope of the* item or service, the Company communicates with the supplier to establish:

a. An Wlderstanding between the Company. and the supplier of the procurement requirements.

b. The intent of the Company in monitoring and evaluating the vendor's performance.

c. The planning, manufacturing techniques, tests, inspections, and processes to be eµtp~oy~ by.the supplier in meeting procurement requirements.. _-*-._-- . * -

The Company and supplier mutually agree on notification points, including hold and witness points. They document this agreement. The Company plans and does the verification of v~dor's activities to assure conformanc~ to the purchase order requirements with QA organization participation. This verification uses written procedures or checklists.

Verification activity plans, as applicable to the method of procurement, provide for: *

a. Specifying the characteristics or processes to be witnessed, inspected, or verified, and accepted.

Page 7-4 REVISION 63b 6/ 16/ 93

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7

b. The method of surveillance and the extent of documentation required.

c. Those responsible for carrying out these procedures.

d. Audits,. surveillances, or inspections that assure that the supplier complies with the quality requirements.

3.3.3- Programmatic Verification The Company or its agents verify the effectiveness of the vendor's quality program by survey, audit or surveillance. The Company does these verifications at int~als consistent with the importance to safety, complexity and quality of the product, or services furnished. The Company witnesses or observes activities when source verification is used. The Company does audits per the requirements established in Section 18. The Company conducts verification activities as early as practicable so that subsequent activities do not prevent disclosure of deficiencies. The Company's verification activities do not relieve the vendor of his or her responsibility for verification on quality achievement.

- 3~3.4 Quality Verification at Source

-Qualified personnel do verification activities at the vendor location per approved checklists or procedures. These activities verify conformance to identified technical and quality requirements.

3.3.5 In- Process Documentation Verification The Company establishes methods to control, handle and approve vendor documents. Vendors submit these documents per procurement requirements. The Company uses acceptance criteria for the acquisition, processing, and record evaluation of technical inspection and test data.

Page 7-5 REVISION 63b 6/ 16/ 93 1

',*-~_,,.

. . .. . ~ .* ...*:.

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7 -

3.3.6 Documentation of Verification Activities The Company records activities done to verify vendor conformance to the requirements of procurement documents. The Company documents source surveillances, inspections, audits, receiving inspections, nonconformances, dispositions, waivers and corrective actions concerning vendor activities. The Company evaluates the documentation to determine the vendor's quality assurance program effectiveness.

3.3.7 Control of Procurement Changes The Company documents changes to procurement documents involving

-tedmical or quality assurance matters. These changes are subjected to the same review and. approval process as the original procurement document.

3.4 Acceptance of Purchased Items and Services 3.4.1 General The Company uses approved* procedures to accept purchased items and services. The methods used to accept an item or services from a vendor include one or more of the following:

a. Vendor Certificate of Conformance

b. -Source verification

c. Receiving lnSpection

d. Post installation testing

e. Product testing. (See section 3.4.6 for acceptance of services.)

The vendor identifies procurement requirements that have not been met. The vendor explains the disposition of all nonconformances per Section 15. - - -

Page 7-6 REVISION 63b 6/ 16/ 93

CONTROL OF PURCHASED MATERIAL, EQUIPI\iENT, AND SERVICES SECTION7 3.4.2 Acceptance by Receiving. Inspection Accept~ce solely by receiving inspection is satisfactory only when the --

item or services are: *

a. Relatively simple and standard design, manufacture and test; and

b. Adaptable to standard or automated inspection or test of th.e

.product to verify quality characteristics after delivery; and

c. Such that receiving inspection does not require -operations that could adversely affect the integrity, function, or cleanness of the item.

(Receipt inspection of an item supplied by a vendor that has been audited or surveyed and has supplied a certificate of conformance or compliance is over and above the meaning of "acceptance solely by receiving inspection.") When procureit\ent documents require

documentation to be furnished before receiving inspection, the company reviews such documentation during receiving inspection. During receiving inspection, the Company inspects as necessary to verify conformance to specified requirements, taking into accolint source

__,verification and audit activities and the demonstrated quality performance of the vendor. The Company does receiving inspections using pr()cedures and inspection instructions to verify, by objective evidence, such features as proper confi~ation; identification; dimensional, physical and other characteristics; freedom from shipping damage; and cleanliness. The Company coordinates the review of vendor documentation with receiving inspection when procurement documents require such documentation to be furnished prior to receiving inspection.

Page 7-7 REVISION 63b 6/ 16/ 93

.*~-*

.... .J

.. \ .. ,_.. . .. -

CONlROL OF PURCHASED MATERIAL, -

EQUIPI\1ENT, AND SERVICES SECTION7-3.4.3 Acceptance by Source Verification The Company considers acceptance by source verification when the item or service is:

a. Vital to plant safety; or

b. Difficult to verify quality characteristics after delivery; or

c. Complex in design, manufacture and test.

Source verification activities (for receipt inspection) include the following, as applicable:

a. The vendor has submitted -documentation as required.

b~-

- - _Documentation provides verification of approvals, material, applica~~~- inspections and tests.

c. The Company has approved fabrication procedures and processes. ,

d. The vendor has complied with fabrication procedures and processes.

e.. The applicable qualifications, process records and certifications are available.

f. The vendor has inspected, examined and tested components and assemblies as required.

g. Applicable inspection, test and certification records are

available.

h. The vendor has dispositioned nonconformances as required.

i. The vendor has cleaned, preserved, packed and identified components and assemblies per specified requirements.

Page 7-8 REVISION 63b 6/ 16/ 93

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7 Upon acceptance by source verification, the Company furnishes documented evidence of acceptance to -the receiving destinatic:>:n*of the item, to the Purchaser, and to the vendor.

3.4.4 Acceptance by Certificate of Conformance Acceptance by this method is satisfactory when the item or service is of ~--- --

simple design and involves standard materials, processes and tests. Such items may be fabricated subject to selected qualification, sample or batch testing to establish or maintain a minimum quality confidence level.

When not precluded by other requirements, documentary evidence may take the form of written certificates of conformance that identify the requirements met by the items, provided means are available to verify the validity of such claims. When used, a certificate of conformance meets the following minimum criteria:

a. The certificate identifies the purchased material and purchase order number.

b. The certificate identifies the specific procurement requirements such as codes, standards or other specifications applicable to the purchased item.

c. - The procurement requirements identified include any approved changes, waivers, or deviations that apply to the subject item. *

d. The certificate identifies any procurement requirements that have not been met with an explanation and the means for resolving the nonconformances.

e. A person who is responsible for the quality function attests to the certificate. * * * *

f. Procedures describe the certification system, including the procedures to be followed in filling out a certificate.

Page 7-9 REVISION 63b 6/ 16/ 93

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7

g. Audits, surveys, or surveillances of the supplier verify the validity of supplier certificates and the effectiveness of the certification system.

h. The Company conducts these at intervals commensurate with the supplier's past quality performance.

The procurement documents specify supplemental documentation such as material certificates or test reports when necessary.

3.4.5 Acceptance by Post-Installation Testing When post-installation testing is used, the Company and vendor mutually establish post-installation test requirements and acceptance documentation. Acceptance by this method is satisfactory when performed following the accomplishment of at least one preceding method and when:

a. It is difficult to verify the quality characteristics of the item without it being installed and in use; or

b. The item requires an integrated system checkout or test with other items to verify its quality characteristics; or _

c. The item cannot prove its ability to perform its intended

function except when in use.

3.4.6 Acceptance of Services Only In cases involving procurement of services only, the Company accepts the service by any of the following methods:

a. Technical verification of data produced;

b. .Surveillance or audit of the activity; Page 7-10 REVISION 63b 6/ 16/ 93

CONlROL OF PURCHASED MA1ERIAL, EQUIPMENT, AND SERVICES SECTION7

c. Review of objective evidence* for conformance.Jo th~-. ,..

procurement document requirements such as certifications, stress reports, etc.

The Company does a receiving inspection for items sent off site for repair, testing, or rework.

3.4.7 Acceptan_ce of ASME Code Items Personnel receiving ASME code items use a checklist. The checklist includes the foll<?wing:

a. All characteristics that the material specifications require to be reported. (Receiving personnel examine each such

--- - characteristic using accepted procedures and record the

.. -\

results.) (Characteristics included on certified material test reports or certificates of compliance need not be duplicated in the checklists.) *

b. A record that the certified material test reports and certificates of compliance have been received, reviewed and found acceptable.

c. Proper documentation of the results of the examination or test procedure conducted by the certificate holder when nec~ssary to show the compliance with material specifications or other requirements.

3.4.8 Commercial Grade Items*

Where the design utilizes commercial grade items, the 'following requirements are an acceptable alternate to other requirements* of this section:

a. An approved design document identifies the commercial grade item. (An alternate commercial grade item may be Page 7-11 REVISION 63b 6/ 16/.93

CONTROL OF PURCHASED MATERIAL, * .

EQUIPMENT, AND SERVICES SECI10N7 applied, provided the cognizant. design organizatioa provi.Qed.

verification that the alternate COµl_mercial grade item will perform the intended function and will meet design requirements applicable to both the replaced item and its application.)

b. The Company performs source evaluation and selection, where determined necessary based on complexity and importance to safety.

c. The Company identifies commercial grade items in the purchase order by the vendor's published product description.

d. After r~ceipt of a commercial grade item, the Company determines the following:

1) Damage was not sustained during shipment.

2) The item received was the item ordered.

3) Inspection and/ or testing is accomplished, as required by the purchaser, to assure conformance with the manufacturer's published requirements.

4) Documentation, as applicable to the item, was received

. __ and -is acceptable.

3.5 Presence of Documentary Evidence Documented evidence that material or equipment confo~s to .

procurement requirements is present at the site before use or installation.

This documentary evidence shall be retained at the. nuclear power plant site and shall be sufficient to identify the specific requirements such as codes, standards or specifications met by the purchased material and

. equipment.

Page 7-12 REVISION 63b 6/ 16/ 93- J *

.b CONlROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7 3.6 . Spares*

3.6.1 General Procedures control the procurement, storage and issue of materials and components including spare and replacement parts. Procurement documents for these items identify the appropriate technical and quality related requirements. The Company purchases spare parts m._ld replacement items, equipm~-and components to original or better design requirements.

3.6.2 Equivalent Specifications and Code Requirements The Company purchases materials and components associated with safety-related structures or systeins to specifications and codes eqtiivalent to those specified for the original equipment, or those specified by a properly reviewed and approved revision. When the Company cannot obtain material that has been manufactured and supplied in conformance with AS:ME Section ID, the_Company may.procure stock material and upgrade it by appropriate tests to AS:tvrn Section ID. The Company provides. certification covering such upgrading (i.e. Providing a Certified Material Test Report) for all operations performed by the Company or their vendors. Where the QA requirements of the original item cannot be determined, qualified individuals conduct an engineering evaluation to establish the requirements and controls. This evaluation insures that interfaces, interchangeability, safety, fit and function are not adversely affected or contrary to applicable regulatory or Code requirements. The evaluators document the results. Where the company procured the original item with no specifically identified quality assurance program requirements, or from an Original Equipment Manufacturer /Supplier (OEM/OES) who no longer is on the Quality Approved Bidders List, identical (like-for-like) items may be similarly procured*'from the OEM/OES. In such cases, the Company conducts a joint technical engineering and quality assurance documented evaluation to established requirements and controls to assure at least equivalent product performance. The evaluation shall assure that

Page 7-13 REVISION 63b 6/ 16/ 93

11 CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECl10N7--

interfaces, interchangeability, safety, fit and .furiction are not adversely affected or are not contrary to applicable regulatory or Code requirements.

3.6.3 Procurement from Other Utilities Purchases of Safety Related items can be made from other utilities who have had an NRC approved QA Program in effect at the time of their procurement and receipt. Such utiltty* nas maintained a Quality Systeµi Program for storage, handling and maintenance* with documented traceability to the manufacturer of the items: Certificates of Conformance to the above requirements and associated required documentation are provided.

3.6.4 Equivalent Production/ Fabrication Requirements Items associated with safety-relate4 structures or systems are produced or fabricated under requirements at least equivalent to that of the original equipment,* or those specified by a properly reviewed and approved revision. - . .-

3.6.5 Maintenance or Modification*

The Company performs maintenance-- or_ modifications that may affect

function of safety-related structures, systems, or components in a manner to ensure quality at least equivalent to that specified in _original design bases and requirements, materials specifications and inspection_

requirements.

3.6.6 Testing or Design for Equ~alence Replacement it~a. teceive adequate testing or are of a design for which experience shows a high probability of satisfactory performance. The*

Company considers phased replacement to permit in-service performance of the new component to be evaluated. When used, this minimizes the.

possibility of a hidden deficiency producing a systematic failure.

Page 7-14 REVISION 63b 6/ 16/ 93 I *

-. *';: ~ .fl;.

CON1ROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES SECTION7

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is .

contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

.._-*; ~- ... -*

10CFR50 Appendix B

ANSI N18.7 .

ANSI N45.2 -- *

ANSI/AS:ME NQA-1

AS:ME Code, Section ID

ANSI N45.2.13 Page 7-15 REVISION 63b . 6/ 16/ 93

1'

If . __ , __ --

IDENmlCATIONAND CON1ROL OF MATERIALS, PARTS AND COI\1PONENTS . SECilON 8

1. POLICY*

This section establishes the requirements for identification and control of materials, parts, and components. *

2. RESPONSIBILf IlES The ~ollowing departments are responsible for carrying out the requirements of this section:

a. Nuclear Stations

b. Site Material* Management Department

--- - c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Nuclear Oversight Department

f. Purchasing Department

g. *."' *systems Materials Analysis Department

h. T&D Operational Analysis Department The Company assigns responsibility for specific requirements through

.. _the Quality Assurance Program Data Base.

3. REQUIREMENTS * -*-._. ___

3.1 Identification and Traceability 3.1.1 General The Company establishes procedures for the identification and control of materials, parts and components, including partially fabricated assemblies. The Company establishes procedures to control welding and brazll_lg materials. The Company establishes controls to assure that only

Page 8-1 REVISION 63a S/ 20/ 93

\J IDENTIFICATION AND CON1ROL OF .

MATERIALS, PARTS AND COlv.tPONENTS SECTION 8 correct and accepted items are used or installed. The Company maintains identification on the items or in documents traceable to the items. The Company controls nonconforming items according to Section 15. The Company maintains parts, material, and equipment in storage traceable to quality assurance documents.

3.1.2 Traceability

The responsible organizations document and maintain identification and traceability of items (including partially fabricated subassemblies) .

throughout fabrication, installation and use of the item. Before use or installation of an item, the installer verifies that identification and traceability have been maintained. the Company reestablishes the

identification before installation or use, if it has been lost. Audits and surveillances assure that an identification and traceability system are provided and maintained.

3.1.3 Identification-Methods Identification is on the item where practicable. Identification is clear, unambiguous and* indelible. Identification does not* affect the function of the item. H the item* cannot be practicably marked, the Company uses records tracea~le to the item for identification. H physical identification -

is either impracti-cal or insufficient for proper- control, the Company controls an item by physical separation, procedural control or other appropriate means.

3.1.4 Transfer of Markings Before cuttirig or dividing material, the Company transfers marks or coded markings to the unmarked portions. The Company independently yerifies proper identification of each piece.

Page 8-2 REVISION 63a 5/ 20/ 93

IDENTIFICATION* ANO CONlROL OF MATERIALS, PARTS AND COMPONENTS SECTION 8 3.1.5 Limited Life Items The Company identifies and controls items having limited life to preclude use of items whose shelf life or operating life has expired.

3.1.6 Stored Items The Company uses procedures ~9=assure proper control of identification of items in storage.

__ ,,,. -** - -- _

3.1.7 Special Materials The- Company clearly identifies and mar~ special nuclear materials, radioactive sources and hazardous materials. _, **--*

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B

ANSI 18.7

ANSI N45.2

ASME Code, Section ill

ANSI/ASME NQA-1

ANSI N45.2.4

-ANSI N45.2.8

ANSI N45.2.13 Page 8-3 REVISION 63a 5/ 20/ 93

. CON'IROL OF SPECIAL-PROCESSES SECTION9

1. POLICY When the quality of a process cannot, be assured through observation of the final product, the process is referred to as a special process. The quality of such processes is assured through reliance on operator skill and in-process control. Examples of special processes include welding, brazing, heat treating, non-destructive examination (NOE), chemical cleaning, coating, and concrete placement. Special processes will be . .. --***- _.

performed in accordance with applicable requirements. These requirements are defined as codes, standards, specifications, or special instructions. *

2. RESPONSIBILI'IIES The following departments are responsible for carrying out the requirements of this section:

a. Nuclear Stations

b. Site Material Management-Department .

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Nucl~ Oversight Department

f. Purchasing Department

g. _ . Systems Materials Analysis Dep~ent The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUIREMENTS 3.0 General The Company department directing the work during construction, repair, replacement, modification, or inservice inspection (ISD activities will be Page 9-1 REVISION 63a S/ 20/ 93

.*---......-J.

CON1ROL OF SPECIAL PROCESSES . SECDON9 responsible for controlling special processes. This includes:

a. *Procedure Development and Qualification

b. Procedure Implementation

c. Personnel Qualification

d. Maintenance and Retention of Records Special process controls will be assured through audit or surveillance .

activities.

3.1 Procedure Qualification and Control Special processes will be controlled by instructions, procedures, drawings, checklists, travelers, or other appropriate means. Special process controls will specify the preparatory steps, processing details, conditions to be maintained during the process, equipment requirements~'.~

inspection and test -~uirements, acceptance criteria, and records requirements.

Special process procedures will be written ana qualified in accordance with applicable requirements.

Special process procedures will be reviewed and approved as follows:

a~ Company heat treating, welding, brazing and other non-NOE proced~es will be reviewed and approved by the Mechanical and Structural Design ISi/Materials Supervisor.

b. Company NOE, coating, and ASME Code concrete placement procedures will be reviewed and approved by the appropriate Company Level m. -

c. Contractor and subcontractor Section ID and XI and other ISl~fed NOE procedures will be reviewed and approved by the Company NOE Level ill. *

Page 9-2 REVISION 63a . S/ 20/ 93 *

~ .

4' . ,_ . '~

CON'IROL *OF SPECIAL PROCESSES SECTION 9

d. Other contractor and subcontractor special pro~ess procedures will be reviewed by the responsible Company engineering organization.

When permitted by applicable requirements, the Company may direc;t contractors or subcontractors to use Company special process procedures.

The Company will assure that qualification of Company, contractor, and ~-. __

subcontractor ASME Code NDE procedures is verified by the ANI or ANTI.

When there is a specific reason to question whether special process procedure requirements are being met, the Company, the ANI, or the ANTI may require re-evaluation of the procedure before work may proceed.

3.2 Personnel Qualification and Certification When req1Jired, Company, contractor, and subcontractor personnel.

performing special processes will be trained, tested, qualifi~, or certified in accordance with a procedure which meets applicable requirements. ~ .

When permitted by applicable requirements, the Company may qualify.

and control contractor and subcontractor personnel. **

The Company will assure -that qualifieation of Company; contractor and subcontractor ASME Code NDE personnel is verified by the ANI or ANTI.

When there is a specific reason to question the ability of an individual performing special processes, the Company; the ANI, or the ANTI may require re-evaluation before that individual will be permitted to resume __

work.

Individuals failing* any retest will be removed from applicable operations pending requalification.

Page 9-3 REVISION 63a . 51 201 93 -

CONTROL OF SPECIAL PROCESSES 'SECilON 9 3.3 *Special Process Records Special process records will provide evidence. that special processes were performed in accordance with approved procedures by qualified pers~nnel. These records will be retained by the Company, or by the contractor or subcontractor as required by procurement documents.

Records will be maintained for currently qualified personnel, processes, --.;' ..... -***

and equipment of each special process.

Completion of special process records will be verified by Station Tech Staff, Station Quality Control, or by the responsible Company engineering organization.

4. REFERENCES The following refer~ces were used in the generation of this section. The Company's commitment to particular revisions of these standards is .

contained 1n Section 2. Specific references for the requirements listed in Part 3 of this sectio~ are contained in the Q.A~, Program Database.* * * *.

10CFRSO Appendix B Criteria 9

ANSI/ ~SME NQA-1

...*-": ASME .Sec. ill Divisions 1 and 2

*-ASME Sec: xr

Page 9-4

.-~-.: ..

REVISION 63a 5/ 20/ 93

J*

INSPECilON SECilONlO

1. POLICY The company will plan and execute an inspection program to venfy that activities affecting quality conform to documented requirements. The independent inspections described in this section are not intended to dilute or replace the clear responsibility of the first line supervisors for the quality of work performed under their supervision.

2. RESPONSIBILl'I'IES .

The following departments are responsible for carrying out the requirements of this section: *

a. Nuclear Stations

b. Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Constructiqn Department.

e. Nuclear Oversight Department The Company assigns responsibility for specific reqtih-ements through the Quality Assurance Program Data Base.

3. REQUIREMENTS 3.1 General*

The Company will establish controls for coordination and execution of inspection plans. Company Quality Control or other qualified organizations are responsible for implementation of established inspection plans. If the inspection plan includes inspections. by* personnel other than the quality orgaltization, the inspection requirements, personnel qualification criteria, and inspector independence will be acceptedbyrtlle responsible quality organization prior to implementation.

Page10-r REVISION 63a 5/ 20/ -93

INSPECTION SECTIONlO 3.2

Inspection Plans The company will prepare documented inspection plans. Relatea codes,,-.

standards, specifications and design documents will be used to develop the inspection plans. The plans will identify:

a. Activities to be inspected

b. Inspection characteristics

c. Inspection techniques/ equipment (including accuracy requirements)

d. Acceptance criteria .

e. Responsible organizations

f. Qualification requirements-

g. Provisions for the record~g of inspection. results.

h. Provisions for inspection and test status The inspection plans may *be separate documents or an integral part of approved instructionS~ procedure5 or drawings. *

.. 3.3 Inspection Per8onnel Inspections will be performed by qualified personnel. Inspections for

*acceptance will be performed by inspectors with valid c~cations.

Inspectors will be independent, other than those who performed or directly supervised the activity being inspected. Inspection of operating activities may be conducted by Sec:ondline-supervisory personnel *or other qualified personnel not assigned first line supervisory responsibility for the conduct of the work. Operating activities are defined as work functions associated with normal operations of the plant, routine maintenance, and certain technical services routinely assigned to the on-site operating organization. On-the-Job-training and team inspections -shall be performed under the direct supervision of qualified personnel.

Page 10-2 REVISION 63a . SI 201 9~ .

INSPECI10N SECTIONlO

3.4 Inspector Qualification A qualification program will be established and documented to conform to applicable codes, standards, or licensing requirements. Qualifications and certifications will be kept current.

3.5 Inspection Process Inspections _will be performed ---~iD.g approved instructions, procedures, process sheets, travelers, or cllecklists and _applicable drawings.

_.

3.5.1 Inspection Inspections will be performed for each work or operating activity where necessary to verify quality. Where inspection sampling is used to_ verify acceptability of a group of items the sampling procedure shall be based on recognized standard practices.

3.5.2 Process Monitoring Process monitoring may be used when inspection of processed material or products is impossible or impractical. When necessary to ensure quality throughout the duration of the process, both inspection and process monitoring will be systematically used to verify conformance to requirements.

3S.3 Hold Points/ Witness Points When inspections must be performed before work can continue, hold points will be established in appropriate documents. Consent to waive hold points will be recorded prior to continuation of work. When inspection is desired but not mandatory before work can continue, witness points will be established. Completion of hold and witness points will be documented.

Page 10-3 REVISION 63a 5/ 20/ 93

,*-~-~.

INSPECllON SECTIONlO 3.5.4 Re-inspection When acceptance criteria are not met, corrected areas will be reihspected~,-

Changes to, or rework 'Of, an item after inspection will require re-inspection of the affected areas. -- *. -

3.5.5 Final Inspection Review A final evaluation will be perform~~_ Jpwection results will be reviewed

to confirm that required inspection$ and quality records have been completed, identified nonconformances have been resolved and the item

. conforms to specified requirements. .Final acceptance of the item will be approved by authorized personnel.

3.5.6 Inspection Records Inspection records ~ be of sufficient detail -to confirm completion and as a minimum identify:

a. Item inspected

-b. Date of inspection

c. . Inspector /Data recorder

d. Type of observation

e. MT&E \Jsed

f. Results or acceptability

g. Reference to action taken in connection with identified nonconformances

h. Authorized individual approving results When the inspection activity is performed using a separate procedure,-

the procedure and its revision will be recorded.

-*-,,~*~r ~

Page 10-4 REVISION 63a 5/ 20/ 93

...* *' _.* )

INSPECTION SECTIONlO

- 4. REFERENCES The followmg references were used in the generation of this section. The _

Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. *Program Database.

10CFRSO Appendix B Criteria 10

ANSI/ AS:ME NQA-1

ANSI/ ANS 3.2

AS:ME SEC. ill NCA 4000 Page 10-5 REVISION. 63a 5/ 20/ 93

TEST CONTROL 'SECilONll

1. POLICY This section identifies the requirements for preparation, review;-* "**

performance and documentation of testing at nuclear stations.

2. RESPONSIBILI'IIES The following departments are responsible for carrying, out the requirements of this section:

a. Nuclear Stations

b. Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. . Nuclear Oversight Department

f. Purchasing Department

g. Systems Materials Analysis Department

h. *.'"' ..T&D Operational Analysis Department The Company assigns responsibility for specific requirements through the Quality Assurance Program. Data Base.

3. REQUIREMENTS

- --~

3.1 General 3.1.1 Testing Program

~e company's overall testing program falls into two broad categories described as the initial testing phase and** the operational testing phase.

The initial testing phase ends approximately at the time of fuel load (receipt of operating license). The operational testing phase begins at this time. Tests performed after fuel load and those tests which lead directly to and support fuel loaa fall in the operational testing phase. In

*Page 11-1 REVISION 63a - - 51 201 93

TEST CON1ROL SECllONll traditional terms, start-up testing, surveillance testing, and post modification testing fall into the operational testing phase, while vendor testing, construction testing and preoperational testing fall into the material testing phase.

The Company establishes and _controls a test program to assure that design and performance criteria have been ~atisfied. The test program includes, as appropriate, procedures to ensure that structures, systems, subsystems and components will perform in service. See paragraph __

3.1.2, Test Procedures, of this Section.

The test program covers all required tests including:

a. tests during design/

b. tests during fabrication,

c. tests during construction activities associated with plant maintenance and modification during the plant operational phase

d. the -demonstration of satisfactory performance* following plant maintenance and modifications or procedural changes.

The program includes, as applicable:

a. proof tests prior to installation,

b. co~truction tests, *

c. preoperational tests,

d. start-up tests as required for a new plant

e. operational tests,

f. those tests required by plant maintenance or modifications,

g. prototype qualification tests, and .

h. production tests. * . .. : -- . .- .*.

Page 11-2 REVISION 63a . SI 201 93

TEST CONTROL . SECTIONll 3.1.2 Test Procedures The program uses written test procedures which include the requirements and acceptance limits from applicable design documents.

The Company reviews and approves test procedures. The Company reviews *and approves changes to test procedures, including changes which alter test sequence, in a similar manner to the original.

The organization responsible for the design of the item to be tested establishes the test requirements and acceptance criteria. The Company bases test requirements and acceptance criteria upon specified requirements contained in~ applicable design or other pertinent documents. Test requirements include specific characteristics to be te§!~d. The Company specifies specific test methods when they must be employed. The Company uses written procedures or checklists. It documents the status of equipment both before and after testing.

Test procedtires include provisions to assure that:

a. . proper calibrated inspection and test instruments are used,

b. equipment to be tested is properly released for testing,

c. inspections and tests are done under suitable environmental conditions, (See paragraph 3.1.2.1, Prerequisites, of this Section)

d. data documentation is in compliance with test procedures and

e. .~etention control of test data documentation is adequate.

The Company may use appropriate sections of related documents, such as ASTM methods, supplier manuals, equipment maintenance instructions, or approved drawings or travelers with acceptance criteria in lieu of specially prepared written test procedures. Such documents.

must include adequate instructions to assure the required quality of work.

Page 11-3 REVISION 63a 5/ 20/ 93

.*-~-~--

TEST CON1ROL SECTIONll Test and inspection procedures contain:

. -~. *~-: ..

a. A description of objectives;

b. responsibilities;

c. test* or inspection requirements contained in applicable design documents;

d. acceptance criteria or limits contained in applicable design or other source documents, such as vendor's literature, engineering drawings or plant specifications that will be used to evaluate results;

e. Prerequisites for or checks to be made prior to performing the

.__ tests or inspections including any special conditions to be

used to simulate normal or abnormal operating conditions;

f. limiting conditions;

g. instructions or check-lists used to verify or document that affected plant systems are arranged in their correct lineup and for restoring the system to the condition consistent with the normal plant operating status;

h. any special equipment or calibrations requireq to conduct the test or inspection;

i. Test or inspection procedure.

Where tests and inspections are to be witnessed, the procedure identifies hold points or witness points in the testing sequence to permit

witnessing. The procedure requires appropriate approval for the test to continue beyond the designated hold point.

3.1.2.1 Prerequisites Prerequisites include the following, as applicable:

a. Calibrated instrumentation, in accordance with Section 12, Control of Measuring and Test Equipment; Page 11-4 REVISION 63a 5/ 20/ 93

TEST'CONTROL SECTION11

b. Appropriate Test Equipment;

c. Trained Personnel;

d. Condition of test equipment and the item to be tested;

e. Suitable environmental conditions; and

f. provisions for data acquisition.

Procedures ensure that prerequisite steps for equipment testing, such as:

a. completion of necessary construction,

b. prior testing,

c. formal release for testing,

d. safety precautions, and

e. measures to preserve equipment status have been or will be performed.

A detailed prescribed physical inspection of equipment components and facilities is performed to ensure readiness for operation. Typical.* items to be covered include:

a. cleanliness,

b. . lubrication,

.c. setting of limit switches,

d. calibration of instruments and

e. presence of safety devices.

3'"1.2.2 Schedule The Company provides a schedule to assure that all necessary tests are performed and properly evaluated on a timely basis. It schedules testing so that the safety of the plant is never dependent on the performance of an untested system. -

3.1.3 Test Results The Company evaluates test results to assure conformance with design and performance requirements.

Page 11-5 REVISION 63a S/ 20/ 93

.-.*~-**

TEST CON1ROL SECTIONll The Company documents inspection and test r~ults in a test report or data sheet. Each report identifies the following:

a. the item to which it applies,

b. the procedures or instruction followed in performing the task,

c. the identification of the conditions encountered which were not anticipated,

d. Identity of inspector or tester

e. completion date and other significant dates and times

f. location where testing was performed or where test samples were taken. *

g. measuring and test equipment used,

h. the acceptability* of the test,

i. the deviation of test results from acceptance criteria

-- - (nonconformance),

j. the actions taken to correct the deviations noted, k as-found-..condition, and

1. as-left condition.

3.1.4 Test Records Test records include:

a. test procedures,

li test results,

c. _ documents that provide acceptance criteria, and

d. data sheets completed during the tests.

3.2 Initial Test Program 3.2.1 'cons~ction Tests The company plans, executes, documents, and evaluates tests required to collect data, such as for siting or design input.

Page 11-6 REVISION 63a 5/ 20/ 93

.. f TEST CONTROL *SECTIONll Surveillance of construction activities includes tests to verify that items being installed and the installation comply with specified quality and performance requirements. These tests* are performed at appropriate points in the construction phase as access permits or when questions arise as to the quality of components or workmanship.

A component test is a functional, operational, or performance test of an individual piece of equipment or unit system under prescribed * -* --.. -**

conditions. Typical parameters to .be examined are: *

a. direction of rotation,

b. bearing temperatures,

c. vibration,

d. time delays, and

e. ability to operate with remote and local controls.

The Company performs hydrostatic tests to verify conformance to specified requirements the reactor coolant system, including all or parts of connected systems which cannot be isolated from the test pressure.

The applicable test requirements are .contained in section III of the AS:ME code.

Where preliminary operation of equipment, during construction, is

utilized !_or a testing function, the Company clearly establishes and documents the purpose of the test, its scope, and results.

Tests are repeated if construction or associated activity affects the resul~

of the tests. The need to repeat a test is ascertained at the time of preparing for post-construction testing.

Tests and shakedown runs are made on energized systems where necessary to evaluate operations and to properly condition for service (for example, the seating of brushes or bearings, the stabilization of instrumentation and bum-in of electronic_ devices).

The Company considers providing a run-in period to mjnimize early failures during operation of the plant, where appropriate.

Page 11-7 REVISION 63a 5/ 20/ 93

TEST -CON1ROL SECDONll 3.2.1.1 Coatings The company uses the specifications of ANSI NlOl.4-1972 for test requirements for applied coatings when these tests are required during design, manufacture, and installation.

3.2.1.2 Compacted Fill The Company conducts in-process tests on compacted fill in accordance

with ANSI 45.2.5.

3.2.1.3 Concrete The Company conducts in-process tests on concrete and pre-stressing steels in accordance With ANSI 45.2.5.

3.2.1.4 Instrumentation The Company tests instrumentation and control channels to assure that they are properly calibrated. In addition, the Company performs specific tests.at critical levels such as "set points" in a manner simulating the approach toward the set point. These calibrations are made with these devices in their normal positions if the calibration is dependent . *

upon location O! attitude. The Company makes tests to determine that proper response is obtained over the operating range of *the device.

It gives particular attention to verifying independence and dependence, as appropriate, of the elements of the systems. The Company tags or labels -items after calibration indicating date of calibration* and identity of the person that performed the calibration.

The Company prepares and documents installation, inspection and test*

procedures and work instructions for instrumentation and electrical equipment. These documents are kept current and revised as necessary Page 11-8 REVISION 63a 5/ 20/ 93

TEST CON1ROL SECTIONll

to assure that installation, inspections and tests are performed in accordance with latest information. They include as appro_priat~.:..

a. installation specifications;

b. inspection and test objectives; .

c. precautions to avoid component or system damage during

testing or inspection;

d. inspection and test equipment required;

e. sequence of tests (if applicable);

f. sequential actions to be performed;

g. frequency of inspection or test;

h. prerequisites;

i. approvals;

)* data report form;

--- - k. identification of test equipment and date or required recalibration where required for interpretation of test results; and*

1. inspection and test acceptance limits.

3.2.1.5 Electrical Tests Electrical tests include:

a. continuity tests, short circuit tests, polarity and rotational tests;

b. control system tests including indicating meters, recorders, transducers, targets and lamps, annunciators and alarms, controls and interlocks;

c. voltage breakdown tests on liquid insulation;

d. overpotential (HIPOT) tests as specified; and

e. inst.Uation resistance measurements *as specified.

Overpotential tests conform to the applicable codes and standards. The manufacturer's recommendations are always considered.

Page 11-9* REVISION 63a SI -201 93

TEsr CON1ROL SECilON11*

3.2.1.6 Mechanical Tests The Company performs mechanical tests to ~certain that electri~ and/or"*

instrumentation components or systems can withstand system pressure ratings. As a minimum, the Company applies such tests to pressure sensing and transmitting devices operating in steam, hydraulic, and vacuum systems and their hydraulic or pneumatic interconnecting piping or tubing and associated instruments. Pressurized equipment which is a . ~-.*~- -****

part of electric apparatus such as heat exchangers, circulating systems,

.* actuating systems, and electric and instrumentation containment penetrations are likewise tested if -site assembled or fabricated. If

equipment is assembled at the construction site, the Company conducts tests after the assembly is complete even though the components may have been previously tested. Manufacturer' tests of fabricated items may be accepted for equipment not disturbed during the construction phase.

The Company performs these tests in accordance with the applicable codes and standards.

3.2.1.7 Physical and Chemical Tests.

Physical and chemical tests, in accordance with the applicable codes, include, as appropriate: * **

a. chemical analyzing of fluids.for *oxygen or moisture content and-purity

.b. radiation sensitivity t~ting. to* confirm. that radiation sensors and controlling devices are properly *functioning.

3.2.2 Preoperational Tests The preoperational testing, when completed, involves the operation of all items in a system to assure that the operation of that system is in accordance with the design criteria "and functional requirementS. The * * .

preoperational phase demonstrates proper coordinated operation of the plant systems, to the extent feasible. The Company demonstrates*-

Page 11-10 REVISION 63a 5/ 20/ 93.

. p TEST CONTROL SECTIONll

required independence and dependence of subsystems. The Company tests to verify that the quality of installed equipment has not deteriorated during the construction phase.

Partial systems or more than one system as defined by the test boundaries may also be tested to assure that operation is in accordance with the design criteria and. functional requirements. Where mechanical equipment's and systems' operation must coordinate with non-mechanical equipment or §Y~~s, the preoperational test*performed includes verifying the compatibility of inter.f~cing equipment and functions.

J1te Company designs preoperational tests to permit evaluation of system performance. They include,* for example:

a. the measurement of flow,

b. the measurement of temperature,

c. the measurement of pressure response time,

. d. . the measurement of vibration,

e. transfer of the power supply to emergency power* and

f. the measurement of the accuracy and response of control devices.

Preoperational tests demonstrate *' as nearly as can be practicably simulated, the overall integrated operation of the plant systems at rated conditions, including simultaneous operations of the auxiliary systems.

Preoperational tests require variation on control parameters, such as pump stops, and restarts, cycling valves and varying flows so that system performance can be evaluated.

The test procedure identifies and describes any temporary or simulated conditions or equipment. H not previously planned, the Company prepares and issu~ a documented notice with approval of the Page 11-11 REVISION 63a 5/ 20/ 93 .

TEST CONTROL SECTIONll responsible organization stating the substitu,tio~ that existed for the test.

The Company provides written verification that temporary installations have been satisfactorily replaced by the permanent installations.

Preoperational testing includes, but is not limited to the following:

a. system integrity;

b. in-line instrument installation is consistent with specified flow directions; ___ ,......,.,

c. Sensing lines are phased--correctly in ll.1-line elements and sensors;

d. Service requirements for initial operation such as flow alignments, limiting flow orificing and relief devices have been performed; e.--- - Operation of controls, valves, dampers, operators, and load limiting devices;

f. Rotating equipment (motors, pumps, blowers)~rotation, speed, vibration, noise, and no-load operation;

g. Handling equipment-load tests of cranes, hoists, conveyors, hooks, and handling adapters, and accessories; *

h. containment systems;

i. air handling systems;

_j. fuel storage and handling systems;

k. Reactor components handling systems; 1.. instrument air systems;

m. fluid service systems;

n. waste effluent systems; and

o. auxiliary building systems.

The final preoperational test includes the review of the construction tests made on assemblies and components with particular attention given to those construction tests that demoristrate functional or operational results. When these.,.tests serve as a prerequisite or a part of the final

system test, the Company reviews construction activity which may have affected the results.

. Page 11-12 REVISION 63a 5/ 20/ 93 *

'TEST 'CON'IROL SECTIONll

Where necessary, the Company demonstrates freedom from unwanted or harmful effects of conducted or induced electrical noise.

The Company checks the suitability of plant operating procedures to the --

maximum extent possible during the performance of preoperational and start-up tests and where permitted at other times prior to fuel load.

Tests, or portions thereof, are repeated if construction or asso~ated activity affects the results of the tests. The need to repeat a test is ascertained at the time of preparing for post-construction testing.

The Company rectifies--the following before final testing:

a. temporary electrical connections,

b. temporcuy piping sections,

c. abnormal chemical solutions,

d. unspecified setting of devices,

e. the fixing of a moving component, or

f. the effecting of any other abnormality.

Exceptions to this are cases where fuel loading or other critical operations prevent using the complete assembly for the test. In these instances, the Company documents the substitutions that. existed for the test. -

The Company uses normal system readout devices and installed .

transducers as far as possible to monitor the operation during the test. It uses special measuring instruments and simulating devices where the installed equipment in not adequate for the purpose of conducting tests.

Test equipment used has adequate capacity and is compatible with system under test so that the results will not be distorted.

Page 11-~3 REVISION 63a 5/ 20/ 93

TEST *CONTROL 'SECTIONll 3.2.2.1 Cold Functional Tests These tests follow preoperational testing of individual systems including reactor coolant systems. The Company performs this testing to obtain operational data of equipment with maximum allowable simultaneous operation on interfacing systems and equipment and final verification of functional performance of these systems.

The Company tests the required individual systems to demonstrate cold functional operability of individual-<:omponents, subsystems, and systems, and to demonstrate compatibility with *other systems. These tests, where appropriate, demonstrate the following:

a. system pressure drop;

b. flow rate;

c. controls and throttling- device settings;

d. function of interlocks, alarms and automatic features;

e. instrument calibration;

f. setting of meter biases;*.

g. system stability;

h. adequacy of pipe and equipment support settings;

i. heat .runs on rotating equipment; J* adequacy of ventilation, lubrication and cooling systems under sustained operating conditions; and

k. ability to meet water chemistry requirements.

3.2.2.2 *Hot Functional Tests for PWR Plants Only -

Hot functional tests for PWR plants usually follow cold functional tests and simulate plant operating conditions at elevated temperatures and pressures. All auxiliary and Sl.JJ~port systems exclusive of those required for pre-criticality testing must be available for these tests. H any of these systems are not ~va).lable, .the responsible organization specifically authorizes exclusion of these systems or subsystems from testing and document those exceptions.

Page 11-14 REVISION 63a . 51 201 93 *

.. '\."'

TEST CON1ROL SECTIONll These tests include the following asa ~um:

a. system pressure drop;

b. flow rate;

. c. controls and throttling device settings;

d.

function of interlocks, alarms and automatic features;

e. instrument calibration;

f. setting of meter biases;

g. systems stability;

h. adequacy of pipe and equipment support settings;

i. heat runs on rotating equipment; *

j. verification of heat exchanger performance;

k. verification of boron control* system performance;

1. thermal insulation effectiveness;

- - m. set points of temperature, pressure and level devices;

n. system heatup tests;

o. system cooldown tests;

p. hot flow tests;

q. **'-*setting protective devices;

r. hot clearances; and * .

s. vibration measlirements of major equipment and piping 3.3 Operational Tests Program 3.3.1 Start~up Tests .*

Start-up tests dem<?nstrate the performance of. systems that could not be tested prior to operation and to confirm those physical parameters, hydraulic or mechanical characteristics that need to be known, but which could not be predicted with the required accuracy, and to confirm that plant behavior conforms to design criteria~ The Company plans the start-up test program to permit safe fuel loading and start-up; to increase power in safe increments; and to perform major testing at specified power plateaus. If tests require the variation of operating parameters outside of their normal range, tile Company prescribes the limits within which such variation is permitted. The scope of the testing demonstrates Page *11-1s REVISION 63a 5/ 20/ 93

TEST CONTROL SECTIONll insofar as practicable that the plant is capable of withstanding the design transients and accidents.

The Company checks the suitability of plant operating procedures to the maximum*extent possible during the performance of preoperational and start-up tests and where permitted at other times prior to fuel load.

3.3.2 Surveillance Tests

The Company's test program covers surveillance testing during the operational phase to provide assurances that failures or substandard performance do not remain undetected and that the required reliability of safety related systems is maintained.

3.3.3 Maintenance or Major Procedure. Change The Company performs tests following plant modification or significant changes in operating procedures to confirm that the modification or

changes produce expected results. These tests also demonstrate that the change does not produce an unsafe operating condition.

4.0 REFERENCES

The following references were used in the generation of this section. The Company's commitment to partiCular revisiens of these standards is contained in Section 2. Specific references for the requirements listed in.

Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B

ANSI N18.7

ANSI N45.2

ANSI/ASME NQA-1

ASME Code Section ill, NCA-4000

ANSI N45.2.13 Page 11~16 REVISION 63a 5/ 20/ 93

CON'IROLOFMEASURING AND TESI' EQUIPMENT SECTION12 1 .. PQl,.ICY Measuring and test equipment (M&TE) will be calibrated and controlled to maintain its accuracy.

2. RESPONSIBILfllES The following departments ¥~ .t~ponsible for carrying out the requirements of this section:

a. Nuclear Stations

b. Site Material Management Department

- - c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. T&D Operational Analysis Depcut1nent The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUmEMENTS 3.1 General The T&D Operational Analysis Department is responsible for maintenance and calibration (traceable to National Standards) of

Company M&TE except analytical chemistry and radio-chemistry laboratory equipment.

Part or all of this respo~~ility may be delegated to the Stations.

The Stations are responsible for the control of Station analytical chemistry; ..radio-chemistry laboratory M& TE, and standard solutions.

They are also responsible for the control of the station M&TE program .

Page 12-1 REVISION 63b 6/ 16/ 93 l

CONTROL OF MEASURING AND TEST EQUIP:MENT SECTION12 -

The Engineering and Construction Department is responsible for the establishment of accuracy requirements for M&TE. Excluded are analytical chemistry and radiochemistry M&TE. Normally this will be the manufacturer's published accuracy. If such published accuracy is not required, new accuracy requirements will be establis~ed by Engineering and Construction. The Engineering and Construction Department is responsible for resolution of technical issues including when certification is required.

3.2 Control A program will specify how M& TE will be stored, handled, and used.

As a minimum the following items :will be addressed:

... -- ~

a. Environmental restrictions

b. Personnel Qualifications c~ M& TE selection

d. Usage history

e. Certification requirements

f. Status

g.

Damage or suspect M&TE

-h. Administrative controls

i. Repairs and maintenance J* Items not requiring certification 3.3 Accuracy M& TE will be calibrated against standards at least four times more accurate than the item being calibrated. Deviation from this standard will be controlled.

The accuracy ratio of M&TE to the plant equipment being calibrated will be determined by an engineering process.

Page 12-2 REVISION 63b - 6/ 16/ 93

0: . j CON1ROLOFI\1EASURING AND TEST EQUIPI\1ENT SECTION12 Standards will be calibrated against standards having a greater accuracy.

When this is not possible, equal accut~cy may be used if it is adequate.

Such deviations will be controlled.

3.4 Traceability

. M& TE will be calibrated against certified standards having valid ... -*:. --=***~- -****

relationships to nationally recognized standards.

3.5 Interval A calibration interval will be established for all M&TE. The M&TE program will specify how this interval is established. 'Upon Request",

'Not To Be Calibrated", and Before and After Use" are acceptable frequencies.

3.6 ASME Code M& TE used in Code applications will meet all requirements of the applicable Code sections.

3. 7 Certification

-Certifica!ion of M&TE is required for:

a. calibration of other M&TE

b. verification of design parameters Certification of M&TE is not required when the measurements do not require specific accuracy. -

Page 12-3. REVISION 63b 6/ 16/ 93

CONTROL OF MEASURING AND TEST EQUIPMENT .SECTION12 3.8 Corrective Actions When M& TE is found to be out of tolerance, an evaluation will be made of its previous uses to determine corrective action. Out of tolerance or suspect equipment will be identified and segregated to prevent inadvertent use.

3.9 Vendor Control

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

Vendors supplying certification services will be on-the Company Quality Approved Bidders List.

3.10 Commercial Devices Control measures are not required for rulers, tape measures, levels, .and other such commer~~ devices, if such equipment provides adequate accuracy.

3.11 Records M&TE calibration records will contain, as a minimum:

a. Last calibration date b.-- . Next calibration date

c. Standards used

d. - Serial Number

e. Calibration Data

f. As found/ As left condition g.. Repairs (H any)

h. Calibration Procedure Used

i.

lndivid ual performing calibration J* Equipment location

k. Out of'fo1erance notification

1. Established accuracy

m. Results Approval Page 12-4 REVISION 63b 6/ 16/ 93

.*~---

CONTROL OF MEASURING AND TESf EQUIPMENT SECTION12 *

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed_ in Part 3 of this section are contained in the Q.A. Program Database. _ . -** ...

10CFRSO Appendix B*Criteria 12

ANSI/ASME NQA-1

AS:ME Section III NCA 4000

--~---*-*-

Page 12..:5 REVISION 63b 6/ 16/ 93

_\ *c*

HANDLING, STORAGE AND SHIPPING SECI10N13

1. POLICY This section identifies the requirements for material control. This includes handling, storage, shipping, cleaning and preservation of material_ and equipment.

2. RESPONSIBILfl'IES The following departments cg_e_ r~onsible for carrying out the requirements of this section:

a. Nuclear Stations

b. Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Systems Materials Analysis Department The Company assigns responsibility for specific requirements through the Quality _Assµrance _Program Data Base. ,. _ -

3. REQUIREMENTS 3.1 General Material Control*

The Company uses written procedures or instructions to specify special protective conditions per the item's design and procurement requirements necessary to prevent damage or deterioration of materials -

components, and systems during handling, preservation, storage, and shipping. These procedures include proyisions for inspection, examination, testing and documentation. The vendor's Quality Program includes shipping procedures that provide for inspection and control of items leaving the vendor's plant The Company establishes instructions for marking1Uld labelling to identify, maintain, and preserve an item, including indication of the presence of special environments or the need for special controls. These requirements apply to the storage *Of chemicals, reagents, lubricants and other consumable materials.

Page 13-l REVISION 63a *SI 201 93

HANDLING, STORAGE .AND SHIPPING SEcnON13 3.2 Special Equipment and Environments When required, the Company: *. . *-*

a. Specifies special equipment (such as containers, shock absorbers and accelerometers).

b. Specifies special protective environments (such as inert gas atmosphere, specific moisture content levels and temperature levels).

c. Provides special equipment and special protective environments.

d. Verifies the maintenance of special equipment and special protective environments.

3.3 Classification of Items .

The Company,dassifies each item received into one of. four levels established in ANSI N45.2.2 This classification considers the manufacturer's requirements. The Company packages, ships, receives, stores and handles according to the established level or a higher level.

When a package or assembly contains items of different levels, the Company classifies it to the highest level designated for any of the items contained.

. *-----.. *-===

3.4 Qeaning, Shipping, Storage and Preservation .

The Company uses written procedures or instructions for cleaning, packaging, shipping, storage and preservation. These procedures specify special protective conditions necessary to prevent damage or deterioration of materialS .and equipment.

3.5 Handling Tools and Equipment The Company inspects and tests special handling tools and equipment using procedures at specified time intervals to verify adequate --

maintenance. The Company provides special handling procedures and Page 13-2 REVISION 63a 5/ 20/ ~3

HANDLING, STORAGE- AND SHIPPING SECTION13 instructions for items that are susceptible to handling damage. These procedures delineate acceptable techniques, necessary qualifications and precautions for maintenance and use. Operators of special handling and lifting equipment have experience or are trained in its use.

3.6 Additional Requirements The Company uses written procedures or instructions to specify detailed requirements for the following subjects:

. __ ,,,,..-. ; .. ~~

a. Storage records

b. Access to storage areas

c. Housekeeping

d. Fire Protection

e. Removal of items from storage.

The vendors ship special nuclear materials and sources as specified in the NRC license and other regulatory requirements.

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in

eart 3 of this section are contained in the Q.A. Program Database.

10CFRSO, Appendix B

ANSI N18.7

ANSI N45.2

ANSI/ASME NQA-1

AS:ME Code, Section ill

ANSI N4.2.2

ANSI N45.4.4

- Page 13-3 REVISION 63a 5/ 20/ 93

,*--~-'***

INSPECTION, TEST AND OPERATING STA1US SEC110N14

1. POLICY This section identifies the requirements for tracking the status of inspection and test performed on equipment at nuclear plants.

2. RESPONSIBILil'IES The following deparhnents are responsible for carrying out the requirements of this section:

a.

Nuclear Stations

b. Site Material Management Department

c. Site Engineerlrig and Construction Department

d. Engineering and Construction Department

e. Nuclear Oversight Department

f. Corporate Security Department

g. Systems Materials Analysis Department ,.

h. '"'"!&D Operational Analysis Department The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUIREMENTS 3.1 General The Company uses marking, tags, stamps, routing cards, labels, forms, or other means to identify the operating status of plant equipment. This iden~cation helps avoid inadvertent hYPassing of the inspections and tests required prior to its use. The Company provides control procedures.

which describe the use of such tags, stamps, routing cards, labels, forms, and other methods. The Company specifies the authority for application and removeµ of tags, markings--;labels and stamps.

Page 14-1 REVISION 63a 5/ 20/ 93

INSPECTION, TEST AND OPERATING STAlUS SECTION14 The Company identifies items that are acceptable or unacceptable for installation by tagging, labeling, color coding, physical separation, or using an inventory system. When tags are used:

a. the* stock is made from material which will not deteriorate during storage,

b. the stock used is not deleterious to the item, and

c. tags are securely affixed to the items and displayed in an area that is readily accessible. .

The Company indicates the date the item was placed in the acceptable or unacceptable instillation status. The program for quality control regulates this activity. The Company conditionally releases items for installation pending subsequent correction of the nonconformance.

The Company maintains records and marks equipment to indicate calibration status. The Company *clearly identifies test equipment found to be out of calibration.

The Company clearly identifies and document$ all temporary connections, such as jumpers and bypass lines, and temporary set points of .control equipment to allow restoration before placing the item in service. * * * *

The Company' tags critical valves, controls and switches to prevent inadvertent actuation during cleaning.

3.1.1 Procedures The Company uses procedures for control of equipment to maintain personnel and reactor Safety and to avoid unauthorized operation of.

equipment. These procedures require control measures such as locking or tagging to secure ari4 identify equipment in a controlle<:f status. The Page 14-2 REVISION 63a S/ 20/ 93

-.*--~-,.

INSPECTION, TEST AND OPERATING SfAlUS - SECTION14

procedures require independent verifications, where appropriate, to ensure that necessary measures, such as tagging equipment, ha:ve'been done correctly.

3.2 Operating Status 3.2.1 Release for Maintenance Operating personnel, including a senior reactor operator, as applicable grant permission to release plant systems or equipment for maintenance or surveillance tests. Prior to granting permission, such operating personnel;

a. verify that the equipment or system can be released,

b. determine how long it may be out of service,

c. .'- determine what functional testing or redundant systems are required prior to and during the out-of-service period.

The Company documents such permission. The Company uses independent verification to the extent necessary to ensure that the proper ..

system was removed from service. The Company considers the '

degraded protection avail(!ble when one subsystem of a redundant safety system has been removed for* mamfetrance or surveillance testing.

/

3.2.2 Preparation for Work After permission has been granted to take the equipment out of service, measl.,lI'es provide for protection of equipment and workers. The Company clearly identifies the status of equipment and systems at any location where the equipment can be operated. The Company enforces strict control measures for. such~uipment. The operating staff can easily identify equipment which is in other than normal conditions.

Page 14-3 REVISION 63a S/ 20/ 93

--*-~- ....

INSPECTION, TEST AND OPERATING STATUS SECI10N14 In addition to the requirements of the technical specifications conditions to be considered in preparing equipment for maintenance or surveillance testing include, for example:

a. Shutdown margin;

b. method- of emergency core cooling;

c. establishment of a path for decay heat removal;

d. temperature and pressure of the system; _

e.

valves between work and hazardous materials;

f. venting, draining and* flushing;

g. entry into closed vessels;

h. hazardous atmospheres and ALARA considerations;

i. handling hazardou5 materials; and

j. electrical hazards.

When entering a closed system, the Company prevents the entry of extraneous material and removes* foreign material before reclosing the system ** -*~ .*--- .

Appropriate personnel inform control room supervision of changes in equipment status, including temporary modifications, and the* effects of such changes~ - -

3.2.3 Temporary-;Modificati~ns ~ _* --:----*-*

The Company controls temporary modifications, such as temporary bypass lines, electrical jumpers, lifted electrical leads, and *temporary trip point settings with approved procedures. These procedures include requirements for the period of time for which the-1:emporary modification is in effect. -They also include a requirement for:

a. an independent verification by a second person of the proper installation or_ removal of the temporary modification, or

b. a functional test which conclusively proves the proper installation or removal of the temporary modification.

Page 14-4 I ' .'

REVISION 63a 5/ 20/ 93

INSPECTION, TEST AND OPERATING STATUS SECTION14

The Company maintains a log or other documented evidence for the current status of such temporary modifications. The Company reviews temporary modification periodically to assess their continued need and appropriateness.. .

3.2.4 Return to Service When equipment is ready to be returned to service, operating personnel place the equipment in operation and verify and doaiment its functional acceptability. The Company assures return to normal conditions including:

--- - a. removal of electrical jumpers,

b. . removal of signals used during testing,

c. refurning valves, breakers, or switches to proper start-up or operating positions, and

d. assuring that all alarms which are indicative of inoperative status are cleared.

A second qualified person verifies proper alignment of equipment unless:

a. all equipment, valves and switches involved in the activity

ean be proven to be in their correct alignment by functional testing without adversely affecting the safety of the plant; or

b. such verification would result in significant radiation exposure.

The person who perfo~s the independent verifications is qualified to perform such tasks. When placed into service, equipment receives additional surveillance during the run-in period. The on-duty supervisor responsible for the unit formally accepts equipment which is returned to.

service.

Page 14-~ REVISION 63a 5/ 20/ 93

~.*----=---** .

INSPECTION, TEST AND OPERATING STATUS SECTION14 -

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B

ANSI N18.7

ANSI N45.2

ANSI/AS:ME NQA-1

ASME Code Section ill, NCA-4000

ANSI N45.2.13-Page 14-6 REVISION 63a 5/ 20/ 93

. .~.

1: ~"

NONCONFORMING MATERIALS, *

PAR1S OR COI\1PONENTS SECTION15

1. POLICY This section describes the identification, documentation, segregation, ana- . '

evaluation of non-conforming items. *

2. RESPONSIBILfllES .

The following departments are responsible for carrying out the requirements of this section:

a. Nuclear Stations*

b. Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Nuclear Oversight Department

f. Purchasing Department

g. Systems Materials Analysis Department

h. T&D Operational Analysis-Department .

The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

_3. REQUIREMENTS 3~1 .General**

The Company uses written procedures to identify and control items, services or activities that do not conform to *requirements. These procedures address: *

a. Identification of nonconforming items.

b. Documentation of identified nonconformances.

c.

Segregation of nonconforming items.

d. Disposition .of nonconforming items.

e. Notification of affected organizations.

Page 15-1 REVISION 63b 6/ 16/ 93 *1

NONCONFORMING MATERIALS, PARTS OR COMPONENTS SECTION15 .

Implementation of these procedures prevents the inadvertent use or installation of nonconforming items.

The Company and its vendors establish and document measures for the identification, control and disposition of items and services that do not meet procurement document requirements. These measures provide for:

a. Review of nonconforming items.

b. The vendor submitting nonconformance notice to the Company. These submittals include vendor recommended disposition (i.e. "use-as-is" or "repair") and technical

justification. The vendor submits nonconformances to the

____ procurement document'requirements or Company approved documents to the Company for approval of the recommended disposi~~ll if: *

1) The vendor has violated a technical or material requirement, or

2) The vendor has violated a requirement in vendor.

documents, which have been approved by the

Company, or

3) **

The vendor cannot correct the nonconformance by

... continuation of the original manufacturing process or by rework, or

. 4)

the item does not conform to the original requirement even though the item can be restored to a- condition such that the capability of the item to function is unimpaired ..

c. Company disposition of vendor recommendation.

Page 15-2 REVISION 63b 6/ 16/ 93

... . J..

NONCONFORMING MATERIAL_S, PARTS OR COI\1PONENTS SECTION15

d.

e.

Verification of disposition of nonconformances.

Maintenance of records of vendor nonconformances.

3.2 Identification The Company identifies nonconforming items by marking, tagging or * ** --**- -*

other methods which do not adversely affect the end use of the item.

The identification is legible and easily recognizable.

3.3 Segregation When practical, the Company segregates nonconforming items by placing them in a hold area until properly dispositioned. When segregation is impractical or impossible due to physical conditions $Uch as size, weight or access limitations, other precautions are employed to preclude 1

inadvertent use of a nonconforming item.

3.4 Disposition 3.4.1 Control The Company uses written procedures to review and accept, reject, repair or_rework nonconforining items. The Company controls processing, delivery, installation or use of a nonconforming item pending an evaluation and an approved disposition by authorized personnel. _'.:[he Company documents ultimate disposition of nonconforming items.

3.4.2 Evaluation The Company has responsibility for resolution of Company nonconformances.

For items under a contractor's direct control, the Company may delegate to the contractor the authority to perform technical evaluation of nonconformances, if the contractor has an acceptable procedure for Page 15-3

REVISION 63b 6/ 16/ 93 I

NONCONFORMING MATERIALS, PARTS OR CO:MPONENTS SECTION15 handling nonconforming items. Where the Company delegates such authority, the contractor is responsible for establishing that:

a. all actions fall within the requirements set by the Company,

b. accepted nonconformance meets the design intent,

c. personnel performing the evaluation meet the requirements of Paragraph 3.4.3, and

d. Code items meet the requirements of the Code.

The Company remains responsible for the satisfactory resolution of vendor nonconformances.

When technical evaluation has not been delegated, the Company will make a technical evaluation of all pertinent data relating to the nonconformity, including the cause; where known, and the corrective action either taken or planned to prevent recurrence.

Where ASME Code requirements are involved, the Authorized Nuclear Inspector reViews and accepts or rejects the disposition and justification.

3.4.3 Personnel - -

Personnel having expertise in the pertinent discipline will determine whether a- nonconforming item may be accepted "as-is," may be repaired to an acceptable condition, or must be rejected. These personnel have adequate competence and knowledge necessary to make this evaluation and have access_ to_ pertinent backgroUI\d information.

3.4.4 Documentation The Company identifies, documents, and retains the disposition (such as use-as-is, reject, repair, or rework) of nonconforming items traceable to each item and technically justifies the disposition.

Page 15-4 REVISION 63b 6/ 16/ 93 *

. .t NONCONFORl\.fING MATERIALS, PARTS OR COMPONENTS SECTION15

The Company subjects items which are nonconforming to de~i_fill .,-..

requirements and dispositioned "use-as-is" or "repair" to design control measures commensurate with those applied to the original design. The Company technically dispositions and justifies acceptance "as-is," to assure that the final condition of nonconforming items will not adversely affect

a. Code requirements,

b. safety,

c. operability or

d. maintainability of the items, or of the component or system in which it is installed. The

~-.built records, if such records are required, reflect the accepted deviation.

If the nonconformance can be corrected after installation, the item may be released for installation on a conditional release basis. The Company documents the authority and technical justification for the conditional -*-

release of the item for installation and makes it part of the documentation.

3.4.5 Repaired, Reworked, or Scrapped Items The Company reexamines repaired or reworked items using procedures and the original acceptance criteria unless the disposition has established alternate acceptance criteria.

The Company reinspects items that have been corrected. The area of inspection may be confined to the area of the nonconformance. When it has been determined that the corrected item is satisfactory, the Company changes the status of the item to "acceptable." The Company makes an appropriate entry in the documentation after acceptance is determined.

The Company scraps, discards or transfers to training use*-a nonconforming item that cannot be corrected or accepted "as-is".

Page 1~5 REVISION 63b 6/16/ 93

NONCONFORMING MATERIALS, PARTS OR COI\1PONENTS SECTION15

4. REFERENCES . *-*

The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

..... ~- ....... -****

10CFRSO Appendix B

ANSI N18.7

ANS 3.2

ANSI N45.2

ANSI/ASME NQA-1

AS:ME Code Section ill, NCA-4000

ANSI N45.2.13

ANSI/ ANS 3.2

ANSI N45.2.4 *

.IEEE STD 336

ANSI N45.2.8

ANSI N45.2.2 Page 15-6 REVISION 63b 6/ 16/ 93 ..

> - .\_

*CORRECTIVE ACTION SECTION16

1. POLICY This section describes the Company program to identify and correct occurrences adverse to quality.

2. RESPONSIBILfl'IES The following departments are responsible for carrying out ~~

requirements of this section:...-- -,_ *~"" *

a. Nuclear Stations

b. Site Regulatory Assurance Department

c. Site Material Management Department

d. Site Engineering and Construction Department

e. Engineering and Construction Department

f. Nuclear Oversight Department

g. Systems Materials Analysis Department

h. T&D Operational Analysis Department The Company assigns responsibility for specific requirements through the Quality_ Assurance Program Data Base.

3. REQUIREMENTS 3.1 General The Company uses a corrective action system to promptly identify and correct items or occurrences which are adverse to quality or might adversely affect the safe operation of a nuclear generating station. Parts or all of this system may .he electronically .monitored and electronic records may be used as the sole record of such a system. These items or occurrences include failures, malfunctions, deficiencies, deviations, defective material and equipment, nonconformances and programmatic deficiencies. *

-Page 16 - REVISION 63a 5/ 20/ 93

CORRECI1VE AcnON .. SEcnON16 For the procurement process, the Company uses procedures that include methods for the identification of condition5 adverse to quality and methods for timely corrective action. The Company requires individual vendors and their contractors to include corrective action measures in their quality assurance programs.

The Company makes a thorough investigation of occurrences. It identifies corrective action to preclude the recurrence of an event. These events may .inclu~e reactor ~p, fail~~- -~uipment, pers~nnel error, and procedural infractions. Assigned personnel are responsible for determining the root cause(s) of the event and developing recommendations to preclude recurrence. These personnel report the results of this determination to appropriate station personnel and company management. The report includes a detailed description of the occurrence, the findings of the investigation, and recommended corrective measures. Any required formal reports are filed with the appropriate regulatory agency.

The Company notifies the rest of the nuclear industry of any significant event and its circumstances to help preclude a similar event. occurring at another plant.

3.2 Significant Conditions The Company takes* measures to assure that the cause of any significant condition adverse to quality is. determined and takes -corrective action to preclude repetition.

An independent* review body reviews violations, deviations and reportable events, that were required to be reported to the NRC iri writing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , such as:...

a. Violations of applicable codes, regulations, orders, technical specifications, license requirements or internal procedilres or instructions having safety significance.

Page 16-2 REVISION 63a 5/ 20/ 93

.* *: ' :.i..

CORRECTIVE ACTION SECTION16

b. Significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures, systems, or components.

c. Events, as defined in the plant technical specifications.

This independent review inclµdes the review of results of any investigations made and the recommendations resulting from such investigations.

For significant conditions adverse to quality that arise~ during the---- -

procurement process, the .Company uses procedures to describe the method used to:

a. Identify and document deviations and nonconformances.

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

c. Report the conditions and corrective action to the appropriate levels of management.

d. Implement and .maintain required corrective action.

For significant or recurring deficiencies (or errors), the Company follows written procedures to correct the deficiency (or error)'* determine the

.cause and make changes in the design process and the quality assurance program to prevent similar types of deficiencies (or errors) from recurring.

Page 16-3 REVISION 63a .51 201 93

CORRECilVE ACllON *SEcnON16 3.3

Design Errors The Company detects deficiencies or errors in design or in the design quality assurance program by:

a. Design verification measures.

b. Personnel using the design documents.

c. Audits

d. Tests Conducted

e. Actual failure during opJ?ration

f. Other means When a significant design change is necessary because of an incorrect design, the Company reviews and modifies the design process and verification procedures.

3.4 Plant Hardware Malfunctions The ca\lses of malfunction are promptly determined, evaluated recorded.

Experience with the maliunctioning equipment and similar components are reviewed and evaluated to determine whether a replacement component.of the same type can be expected to perform the function reliably. If evidence indicates that common components in safety-related systems have* performed unsatisfactorily, corrective measures are planned prior to replacement or repair of all such components.

Appropriate procedures are revised in a timely manner to prevent recurrence of equipment malfunction or abnormal operation.

3.5 Documentation and Reporting The Company documents the identification of significant conditions adverse to quality, the cause ofl:he* condition and the corrective action taken. It reports these items to appropriate levels of management. The report is made.-iffifuediately if prompt corrective action is required. If the nonconformity is not an indication of a significant failure in any portion of the Quality Assurance Program, the Company does not require reporting to management. *

page 16-4 REVISION 63a S/ 20/ 93

.CORRECTIVE ACTION SECTION16 The Company keeps records to identify:

a. Incidents (e~g., major damage, personal injury, major schedule delays.)

b.. Nonconforming items in accordance with Section 15,

Nonconforming Materials, Parts or Components."

c. . Unfavorable conditions and programmatic deficiencies identified in Audit Reports in accordance with Section 18, "Audits."

d. Significant equipment failures and malfunctions which occur during Station operation.

... --The- Company tracks the completion of corrective action for nonconformances. It maintains records of nonconformances and their resolution. Periodic reports to management inform them of the status of .

nonconformances. The Company issues reports indicating the status of _,

all corrective action in progress. These reports are routed to Company*

corporate m~agement. These periodic reports are reviewed to ensure *!':;':

prompt implementation of the corrective action. Nuclear Oversight routinely reports nonconforming items to appropriate levels of

management.

The following. items are not reported:

a. .Minor weld inclu5ioil5;* m\aercuts, or porosities, where *the

- magnitude or frequency of occurrence is not indicative of a*

significant problem in design, procedures, materials or workmanship.

- b. Minor departures, except for-Code applications, from specified physical or chemical properties of materials. that do not require extensive evaluation to determine adequacy of the materials.

_*Page 16-5 REVISION 63a 5/ 20/ 93

,CORRECTIVE ACilON SEcnON16

c. Minor structural departures from design requirements, such as low strength concrete or porosity of concrete, provided that an extensive evaluation is not required to determine adequacy of the structure or repairs. '* *

d. Minor departures from performance specifications, as demonstrated by acceptance of construction and preoperational tests, which do not require extensive evaluations of an item's performance capability or extensive redesign.

e. The occurrence of. a nonconformance that can and will be remedied through the use of established methods in applicable codes or*approved procedures.

f. The nonconforming item will have the capability of performing its intended function. The responsible department sends copies of the nonconformances to the cognizant quality* area.

For construction or modification activities under Engineering and Construction or Site Engineering and Construction control, *on-site corrective action measures consist of procedures for prompt resolution and approval of corrective actions by Engineering and Construction or Site Engineering _and Construction.. The_~~ponsible manager brings significant nonconformances to the attention of corporate management for actions where satisfactory resolution cannot be achieved by Engineering and Construction or Site Engineering and Construction.

3.6 Verification and Follow-up For construction or modification activities under.SEC control, SEC assures that the corrective action has been taken. The Company requires contractors and vendors to follow-up_Q_n corrective action commitments within their quality programs.

Page 16-6 REVISION 63a S/ 20/ 93

CORRECI1VE ACilON -SECTION16 Independent personnel follow-up and approve that nonconformances have been corrected satisfactorily.

For Operations, trend studies and audit results are evaluated to assure that corrective measures are effectively implemented and that actions to prevent recurrence are effective. The Company verifies completion of corrective actions for maintenance, repair, refueling and operation activities.

The Company performs sury.eillance of site corrective action. The Company is responsible to track and verify,.completion of corrective action taken for audit deficiencies including programmatic deficiencies identified in audits. The Company verifies and approves the completion of corrective actions by the station.

The Company regularly reviews and.analyzes records: -- -----

a. To assure that the causes of nonconformities and the corrective action have been clearly described.

b. To assure that the overall effect resulting- from the use of nonconforming items has been evaluated by authorized Commonwealth Edison Company personnel.

c. To determine whether corrective measures will preclude recurrence. _Personnel performing the evaluation function are responsible for considering the cause and the feasibility of corrective action to assure that the necessary quality of an item is not deteriorated. Where it is determined that the cause cannot be- corrected in -a timely manner, the effective date or corrective action will be determined during the review:

and evaluation. Evaluation may indicate the need for investigations to assure that corrective measures are

____", .. ~Considered complete. Evaluation may also indicate that the nature of the nonconformity is minor and does not require corrective action.

Page-1~7 REVISION 63a 5/ 201 93

CORRECTIVE . ACI'ION SECI10Nl6

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards iS contained in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendix B Criteria 16

ANSI N18.7

ANS 3.2

-* ANSI N45.2

_ANSI/ ASME ~QA-1 *

AS:ME Code Section ID, NCA-4000 *

ANSI N45.2.13

ANSI/.. ANS 3.2

ANSI N45.2. l 1 Page 16-8 REVISION 63a . S/ 20/ 93

QUALITY ASSURANCE- RECORDS ... SECilON17

1. POLICY The company establishes and implem~ts a program to ensure that sufficient records of items and activities are generated and maintained in accordance with applicable requirements.

2. RESPONSIBILfllES

- ~..... _ -***'*

The following departments are responsible for carrying out the requirements of this section:

a. Nuclear Operations Division

b. Nuclear Stations

c. Site Regulatory Assurance Department

d. Site Material Management Department

e. .Site Engineering and Construction Department

f. Engineering and Construction Department

g. . Nuclear Support Department

h. Performance Monitoring and Support. Department

i. Nuclear Operations Staff J* Nuclear Regulatory Services Department

k. Nuclear Oversight Department

1. Purchasing Department

m. Corporate Security Department

n. Systems Mat~ Analysis Department

o. T&D Operational Analysis Department The Company assigns responsibility for specific requirements through The Quality Assurance Data Base.

Page 17-1 REVISION 63a

Sl 201 93

QUALTIY ASSURANCE RECORDS SECTION17

3. REQUIREI\.1ENTS 3.1 Program The records program provides for:

a. administration

b. receipt

c. transmittal

d. storage

e. preservation

f. safekeeping

g. retention

h. . disposition 3.2 Administration The quality records _Erogram will include those record types, controls, and provisions for storage and preservation contained in NQA-1, Supplement 175-1. Authority and responsibility for record control ,

activities is delineated.* Records are administered through a system

. which inclu~es an index of record type, retention period, and storage location.

Records will be legible, accurate, complete, identifiable, and retrievable. .

Records may be maintained in electronic media. Records are complete when dated and stamped, initialed, signed or otherwise authenticated.

This may include electronic approval and authorization. Corrections, revisions, or supplements to completed records will be reviewed and approved by an authorized individual in the originating organization.

. Such changes will be dated and stamped, initialed, signed, or otherwise authenticated including the use of electronic approval and- authorization.

Procedures will be established to~as5ure that only those persons authorized to use electronic approval grant such approvals.

Measures will be established for replacement, ~toration, or substitution

of lost or damaged records.

Page 17-2

REVISION 63a 5/ 20/ 93

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

QUALfIY ASSURANCE RECORDS . SECTION17

3.3 Receipt .

A system for receipt control of records will be established. Receipt control is required for records transferred:

a.* between company locations

b. between vendors and the company

c. from company department files to final storage location5.

3.4 Transmittal Systems are established. to transfer records between company locations and between vendors and the company. Records transferred from company department files to a final storage location are also under such systems.

':fhe system includes:

a. ."'inventory of transmitted records

b. receipt acknowledgment 3.5 Storage -

Record s~orage .facilities *are established to meet reguiatory requirements, including ~ose of NQA-1,_ Supplement 175-1 and AS:ME Section ID, I

. NCA 4134.17. Storage systems proVKfe for: - I~- -

a. assignment of responsibilities

b. control and accountability of records removed 3.6 Preservation In order to prevent deterioration, records are stored:

a. in a manner to prevent damage from moisture, temperature, pressure, etc.

b. in binders, folders, envelopes, or similar systems .

Page 17-3 REVISION 63a 5/ 20/ 93

QUALITY ASSURANCE RECORDS SECflON17 Manufacturers recommendations are followed for special recording media.

3.7 Safekeeping Measures are established to prevent access to records by unauthorized personnel. These measures guard against theft and vandalism.

3.8 Retention Record retention periods are established to meet regulatory requirements.

The most sbingent retention period is implemented when multiple requirements exist.

3.9 Disposition Records will be dispositioned at the end of the prescribed retention period. A reView ofregulatory requirements will be performed prior to

disposition to assure current requirements are satisfied. *

4. REFERENCES The following references were used in the generation of this section. The Company's commitment to particular revisions of these standards is coritailied in Section 2. Specific references for the requirements listed in Part 3 of this section are contained in the Q.A. Program Database.

ANSI/ASME NQA-1

10CFR50 Appendix B, Criteria 17

AS:ME Section ID, NCA 4000

ANSI N18.7

ANS 32 Page 17-4 REVISION 63a 5/ 20/ 93

.*-~-*

.AUDITS SECI10N18

1. POLICY A documented, comprehensive system of planned and periodic performance based audits and assessments of the Company and its vendors is conducted to verify quality assurance program compliance, adequacy, and effectiveness and to assess conformance with management controls.

Audits are conducted to the requirements of NQA-1 to assist the audited organization and to assure completion of required corrective actibns, commitments, or improvements.

2. RESPONSIBILfllES The,Nuclear..Oversight Department is responsible for carrying out-the requirements of this section. The Company assigns responsibility for specific requirements through the Quality Assurance Program Data Base.

3. REQUIREMENTS 3.1 Audits - General 3.1.1 Responsibility Nuclear Oversight's responsibilities include conducting the external (offsite) audit program of Company stations, departments, and vendors involved in nuclear activities, the managemerit assessment program, and participation in joint member groups. Nuclear Oversight is also responsible for and conducts the internal (onsite) audit and surveillance

program and assessments of Company stations and departments involved in nuclear activi~es and is independent of Nuclear Operations.

3.1.2 Scheduling Audits are performed to schedules approved by the Nuclear Oversight Manager which include the minimum audit areas and frequencies.

Scheel ules are revi~wed semi~annually and revised accordingly to assure

Page-1s-1* REVISION 63b 6116/ 93

AUDITS

SECTION18 that coverage is maintained current. Audits will be initiated early to assure effective quality assurance during design, procurement, -: . . --....

manufacturing, construction, installation, inspection, testingi and operations.

Additional unscheduled audits may also be performed at various stages of activities, based on the nature and safety significance of the work being done to verify continued adherence to and effectiveness of the quality systems.

Operating activities will be audited in compliance with the Technical Specifications. Each ongoing Code activity is audited annually and r-esults are made available to the ANI.

Material Manufacturers or Material Suppliers who are qualified under the Company's ASME 'N Certificate of Authorization *and who are actively supplying Code materials will be audited/surveyed annually.

Vend_qts and their subtier suppliers are audited periodically--generally in conjunction with plant visits for witnessing inspection points. The

.. Company's activeparticipation in joint utility audit programs provides an alternative means to fulfilling its responsibility for auditing active vendors.

3.1.3 Preparation A documented plan or an agenda will id.~ntify the audit scop~, ..

requirements, audit personnel, activitie5 to be audited, organizations. to be notified, applicable documents, and schedule. An approved checklist or procedure for each audit will identify the quality and technical elements of the area or items to be evaluated. Audit plans, agendas, checklists, and procedures will be prepared inJ\.dlrallce under the direction of the Audit Team Leader.

3.1.4 Personnel Audits will be acco~plished by expeilehced personnel qualified in accordance with NQA-1 who are familiar with. written procedures~

standards and processes applicable to the area being audited. Audit Page 18-2 REVISION 63b 6/ 16/ 93.

,~,~ .* ..........

AUDITS -SECTION18 personnel shall have sufficient authority and organizational freedom to make .the. audit process meaningful* and effective and shall not have direct responsibilities in the areas to be audited. The Audit Team Leader shall organize and direct the audit and ensure the audit team collectively has the required experience or training for the activities to be audited.

The audit team may be supplemented by technical specialists to provide additional experience and competence.

3.1.5 Performance

. - - - * * **** :!/:'"~

Performance based audits are.conducted to_assess specific activities, processes, and records on the basis of their impact and importance -

relative to safety, reliability, and functionality. Audits can be focused on areas most in need of improvement. Objective evidence shall be

examined to the extent necessary to determine that a quality system is being effectively implemented.

3.1.6 Reporfu!g and Follow-up An ~udit report includes the description of the audit scope, identification of the audit team and personnel contacted *during audit activities, a summary of audit results (including a statement on effectiveness of the quality assurance program elements), and a comprehensive description of each audit concern. Audit results will be documented and distributed and shaU be reviewed by the management having responsibility in the area being audited .. Deficiencies requiring prompt corrective action

-are reported immediately to the managem~t of the audited organization.

Responsible management *shall take necessary action to correct the deficiencies identified in the audit. They will define the corrective action to be taken, actions which will prevent recurrence, and a sehed ule for implementing these actions.

These commi_tments will be evaluated by the Audit Team Leader.

Recurring deficiencies or failure to implement corrective action will be reported to appropriate Company executives.

Page 18-3 REVISION 63b 6116193

.-~-*.*

.AUDITS .SECTION18 Verification of the completion of scheduled. corrective action commitments is ..performed. to assure deficiencies or adverse conditions are corrected.. Previous deficient areas or adverse conditions are * *-*

followed. up to assure effective corrective action is effective and implementation continues.

3.1.7 Records The audit plan, report, objective evidence, written replies, and the record of completion of corrective action ~, d@ficiency follow-up will be on file. Personnel qualification records for audit team members shall be established, maintained, and reviewed.

-3.2- Independent Management Audit/ Assessment Audits of the Company are performed by the Authorized Inspection *- .*.--

Agency as required by the Code and AS:ME N626.0. A periodic review l

of the audit program will be performed by an independent organization to assure that audits are being accomplished to program requirements.

An annual report on the status, adequacy, and implementation of the Quality Assurance Program is submitted to the Chief Nuclear Officer by the Vice President Nuclear Oversight and Regulatory Services.

4.. REFERENCES The folloWing references were _used in the generation of this section. The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in Part 3 of this section are cont~ed m Q.A. Program Database.

10CFRSO Appendix B

ANSI/ ASME NQA-1

ASME Code Section ID, NCA-4000

-*...:.r*P:r ~ '

ANSI Nl8.7-1977

ANSI/ ANS 3.2-1988 Page 18-4 REVISION 63b 6/ 16/ 93

AUGMENTED QUALITY - -SEC'TIQN 1 1. POLICY It is the policy of the Company to assure a high degree of availability and reliability for our nuclear plants while ensuring the health and safety of the public and our workers. Therefore, the Quality Assurance Program is applied in a graded manner to certain areas and activities that are not clearly defined as safety related or Code related. the Company calls this application Augmented Quality.

2. RESPONSIBILl'I'IES -

The following departments are responsible for carrying out the requirements of this sectioJ:!: .

a. Nuclear Stations

b. Site Material Management Department

c. Site Engineering and Construction Department

d. Engineering and Construction Department

e. Corporate Security. Department The Company assigns responsibilities for specific requirements through the Quality Assurance Database.

3. REQUIREI\1ENTS The Company applies the Quality Assurance Program. to certain systems, structures, components, and activities which are not safety related or Code related to a degree consistent with their importance to safety.

While there may be minor interfaces with additional sections of this manual,_ the following sections apply to the-programmatic elements of the noted activities:

3.1 Radiation Protection, As Low As Reasonably Achievable, ALARA Sections 3, 4, s,- 6, 15; 16, and 18 are applicable to this area. .

Page 19-1 REVISION 63a 5/ 20/ 93

AUGMENTED QUALl'IY SECllON19 3.2 Emergency Planning Section 5, 6, 16, and 18 is applicable to this area.

3.3 TranSport of Radioactive Waste Sections 4, 5, 6, and 17 are applicable to this area.

3.4 Security Security is controlled for each station by the station security plan that is prepared per NUREG 0908. This plan describes the applicable personnel organization, the keeping of records, audits, *and the reporting of abnormal conditions. Sections 6 and 16 are applicable to this area.

3.5 Review of Class IE Equipment Qualification Sections 3, 5, 6, and 15 are applicable to this are~.

3.6 Training Sections 4, 5, 6, 15, 17, and 18 are applie_aj>le to this area.

3~7 Environmental. Monitoring

-Sections 17 and 18 are applicable to this aiea.

--3.8-* Meteorology Sections 17 and 18 are applicable to this area.

3.9 Fire Protection A quality assurance program is required for fire protection systems in Safety Related areas. Engineering and Construction is responsible for determining this need for systems on a case by case basis. The Stations are responsible for determining this need for other fire protection equipment on a case by case basis. When required by these organizations, Sections 3, 4, 5, 6, 7, 10, 11, 14, 15, 16, 17 and 18 are applicable to this area. --

Page 19-2 REVISION 63a 5/ 20/ 93

-.*-~~-

AUGMENTED QUALin' SECTION19

4. REFERENCES The following references were used in the generation of this "7secti~il: -The Company's commitment to particular revisions of these standards is contained in Section 2. Specific references for the requirements listed in _

Part 3 of this section are contained in the Q.A. Program Database.

10CFRSO Appendices A, B, R

10CFR71 Part H

10CFR73

10CFR21

ANSI/ ASJME NQA-2

Page 19-3 REVISION 63a 5/ 20/ 93

,:**** "'~

DEFINITIONS APPENDIX A

1. GENERAL This Appendix of the Quality Assurance Manual consists of definitions of words or phrases found in the Commonwealth Edison Company Quality Assurance Program. The purpose of this definition section is to provide a common basis for understanding those words or phrases that may have a different *meaning when used elsewhere.

All words and phrases are subject to review and revision as circumstances require.

-A-

~prov al Approval as used herein means by signature or initialing and date by an authorized individual.

ASME Boiler and Pressure Vessel Code, Section IIl, Division 1 and Division 2 for Concrete Containment_,

Refers to ASME Section III, Division 1 and Division 2 for Concrete 1 Containment; ASME Section III; ASME Code; ASME; or Code.

ASME Boiler and Pressure Vessel Code,Section XI

-~Refers to. ASME Section XI; Section XI; or Code.

Audit A planned and documented activity performed to determine by investigation, examination, or evaluation of objective evidence the adequacy of and compliance with established procedures, instructions, drawings, and other applicable documents, and the effectiveness of implementation. An audit should not be confused with surveillance or inspection activities performed for the sole purpose of process control or product *acceptance.

Page A-1 REVISION 63b 6/ 16/ 93 I

.*-~-**

~-* ~/

DEFINITIONS APPENDIX A Audit Team Leader An individual appointed to head an Audit Team. The Audit Team.

Leader coordinates the preparation of the audit report.

Auditor One qualified* and authorized to examine quality assurance practices and verify whether requirements are being met.

Authorized Inspector or AI or ANI As used herein is meant to mean Authorized Nuclear Inspector. An Authorized Nuclear Inspector is an employee of an Authorized Inspection Agency who has qualifications for and has been properly

.accredited for Division 1 or Division 2.

Authoiized Nuclear Inservice Inspector or ANil As used herein is meant to mean the Authorized Nuclear Inservice Inspector. An ANTI is an employee of an Authorized Inspection Agency who has qualifications for and has been properly accredited for AS:ME }* _

Section XI. *

-B-Balance of Plant Generating Station items and equipment not designed, furnished or installed as a part of the Nuclear Steam Supply System. Bcilance-of Plant items include safety-related and Code items, such as the containment as well as non safety-related and non-Code items.

Basic Component

Basic component", when applied to nuclear power _reactors means a plant structure, system, component or part thereof necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents which should result in potential offsite exposures comparable to those referred to in par 100.11 of 10CFR Chapter 1 {1-1-87), Part 21.

Page A-2 REVISION 63b 6/ 16/ 93

DEFINmONS APPENDIX A Bid Package The total of drawings, specifications, codes, standards, quality and other requirements that describes the task on which a prospective

.contractor I supplier will bid.

-C-Calibration A method of assuring accuracy of gauges and instruments used for measuring and testing by comparing with recognized standards.

Certificate of compliance A written statement, signed by a qualified person, attesting that the materials or items are in compliance with the purchasing documents. --.

Certified Personnel Personnel who have passed a formal training program and a formal proficiency test for special processes such a,s welding, plating and nondestructive testing.

Certified Standards Standards of measurement whose accuracy can be traced to standards at the National Institute of Standards and Technology or established standards.. -.

Certified Material Test Report A document attesting that material is. in accordance with specified requirements including the actual results of all reqtiired chemical*

analyses, tests examinations.

Page A-3 REVISION 63b 6/ 16/ 93

. ~::.

DEFINITIONS APPENDIX A Change Order A f9rmal award to a vendor or contractor covering revision(s) to the original Purchase _Order or Change Order, involving but not limited to quantity, technical requirements, quality assurance requirements or scope of work.

Change Order Requisition A document describing revisions to be made to the original Purchase Order or subsequent Change Order and which is converted into a Change Order.

Characteristic Any property or attribute of an item, process or service that is distinct, describable and measurable, as conforming or nonconforming to specified quality requirements. Quality characteristics are generally identified in specifications and drawings which describe the "item, process or service.

Code See AS:ME Boiler and* Pressure Vessel Code, Section ID or Section XI, whichever is applicable.*

code --* -

A recognized standard for using or processing materials, or for the skill involved in use or processing.

Cognizant Engineer The engineer assigned a specific task or area of responsibility in the design or testing of a component or system.

Company Defined as Commonwealth Edison company, and referred to variously as CECo, Edison or Company.

Page A-4 REVISION 63b 6/ 16/ 93

DEFINmONS . APPENDIXA Company Level ill Chief Level III (NOE) for the Company . **-- ....

Component ASl\IB Code items such as vessels, concrete containments, piping systems, pumps, valves, core support structures and storage tanks which will be combined with other components to form an assembly or installation of a nuclear power plant.

Component Identification Number An identification number assigned (where appropriate) to an item for use throughout its lifetime.

Construction -

Activities at the building site necessary to erect, inspect and accept a power generating station and its associated installation. This definition applies unless otherwise indicated.

Construction (AS:tv1E Section III Div.I) comprises all activities relating to materials, design fabrication, examination, testing, inspection and certification required in the manufacture and installation of items.

Construction (AS:ME Section III Div. 2) includes all those operations required to build the component and its parts in accordance with the Design Drawings and Construction Specification which have been prepared by the Designer (A-E).

Construction Tests Those tests necessary to verify that the installation of each component of a system is complete and complies with the applicable specifications, standards, codes, drawings and engineering information. *

Page A-5 REVISION 63b 6/ 16/ 93 1

DEFINITIONS APPENDIX A Contract (Including purchase order)

A binding agreement between two or more p~ons or companies.

Contractor Any organization under contract for furnishing items or services. It includes the terms Vendor, Supplier, Subcontractor, Fabricator and subtler levels of these where appropriate.

Code Contractor is a contractor holding a valid AS:ME Section ill Certificate of Authorization.

Control Point In a sequential operation, a chec15point at which certain data are taken, inspections made or approval required.

Corrective Action Measures taken to rectify conditions adverse to quality, and, where necessary, to preclude repetition.

. - D-Department When a responsibility is given a Department in this manual it is meant that the Department Head has the responsibility.

Design Change Any change in design that may affect functional requirements, operating conditions, safety-, regulatory-, reliability-, and .Code-related requirements, performance objectives, plant reliability or design life and would require that affected documentation be changed.

Page A-6 REVISION 63b 6/ 16/ 93 I

.DEFINl110NS APPENDIX A Design Controls Methods for assuring that basic design requirements are formalized and translated into design documents with proper review to assure the scheduled release of a valid design.

Design Criteria Statements of the form, function and interface requirements within well defined limitations ..

Designer (Division 2)

As used in ASME Code Division 2 construction, the Designer (A-E) is the organization responsible for the preparation and completion of the Design Report, Design Drawings, and Construction Specifications for applicable items.

Design Requirements Documents that set the functional requirements, operating conditions safety requirements, performance objectives, design margins and desigri'

life. Included are any special requirements for size, weight, ruggedness, materials, fabrications or constructions, testing, maintenance, operating environments, safety margins and derating factors.

Design Review*-

An analysis of design with respect to technical adequacy, interface control, inspectability, maintainability and conformance to applicable codes, standards, regulations and design criteria.

Design Specification A document that sets the functional requirements; design requirements; environmental conditions, including radiation; Code classification; definition of the boundaries; and material requirements. Sufficient detail shall be contained within the document to provide a complete basis for design.

Page A-7 REVISION 63b 6/.16/ 93 1

DEFINITIONS APPENDIX A For Section ID AS1\.1E Code (Division D: A document prepared by the owner or-owner's designee which provides a complete basis foe -..

construction in accordance with Section ill. -

Desk Survey An evaluation of a supplier's quality control capability made from documented procedures and records of past performance.

Destructive test A test to determine the properties of a material or the behavior of an item which results in the destruction of the sample or item.

Deviation A nonconformance. Departure of a characteristic from specified requirements.

Discrepancy A nonconformance.

Documentation Any written or pictorial information describing, defining, specifying, reporting or certifying activities, requirements, procedures or results ..

Drawing Manifest A document for trarismitting diaWings, released for construction to Engineering, Construction and Production*~

- E-Edison Defined as Commonwealth Edison Company and referred to variously as CECo, Edison or Company.*

Page A-8 REVISION 63b 6/ 16/ 93 -.

DEFIN1'110NS APPENDIX A

Erector An* organization involved in assembling and building equipment or structures at the site.

Examination ' *,.

Specific actions by qualified personnel using qualified procedures to verify that items and fabrication processes are in conformance with specified requirements. This term, when used in conjunction with qualification of personnel to*-perform quality-related activities shall mean a written examination. -

-F-Fabricator An organization involved in the manufacture of equipment.

Fabricator (ASME Section ID Div. 2)

The NPT Certificate Holder Final Safety Analysis Report (FSAR)

A finalization of the preliminary safety analysis report prepared for the Nucleat Regulatory Commission prior to issuance of an *operating license.

First Level Design Review A review conducted by the responsible project engineer within the design agency for a specific design discipline.

Flow Chart A representation of the sequence of activities such as procurement, fabrication;**processing, assembly, inspection and test, or the sequence of individual operatio.ns within one or more of those functions .

Page A-9 REVISION 63b 6/ 16/ 93 l

DEFINITIONS APPENDIX A

- H-Hold Point A designated stopping place during or following a specific activity at which inspection or examination is required before further work can be performed. *

-I -

., ----** .*. *~-~--

Incident Occurrence of major damage, serious personal injury .or significant schedule delay.

Inspec~gn A phase of qllitlity 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 ..

Inspection and Test Plan A listing, with optimum sequencing, of all the inspections and tests

required to be performed for a specific item, component, structure or service.

Interface control Consideration that components and 'structures are geometrically and functionally compatible and that materials are compatible with both process and environment.

Item Any level of unit assembly, including structure, system, subsystem, subassembly, component, part or material.

Page A-10 REVISION 63b 6/ 16/ 93

DEFINITIONS APPENDIX A When AS:ME Code items are referenced, this means products constructed under a certificate of authorization and material.

-I-Jurisdictional Boundaries The physical limits of a Code item which are identified to determine the applicability of Code rules for that item. .- -- ~--*- -***

-L-Lifetime Record A record which meet one or more of the following criteria:

a) those 'which would be of significant value in demonstrating capability for safe operation; b) those which would be of significant value in maintaining, reworking, repafuting, replacing, or modifying an item; c) those which would be of significant value in understanding-the cause of an accident or malfunction of an item;

. d) those which provide required baseline data for inservice inspections. *

.Like-for:_Like Replacement ** - ~

The replacement of *an item with an item that is identical in all physical and .performance characteristics.

Local Purchase Order A purchase order initiated through the computer by a station for the purchase of only Company Stores Coded items. '

~.

Page .A.-11 REVISION 63b 6/ 16/ 93

DEFINITIONS APPENDIX A

-M-.

Maintenance* * * *

Repair, rework, or replacement of a structure, system or component with equipment of the same design, i.e., meeting the same engineering requirements.

Maintenance/ Modification Work Package The complete set of documentation.!hat..enables the Station to fabricate, examine, test and install AS:tv.fE and safety-related .items. The work package consists of the Work Request, provisions for Station Traveler, Document Check.list and maintenance/modification procedures _and supporting information .such as, but not limited to, approved drawings, ..

Design Specifications, and Special process procedures ..

Material.

A substance or combination of subst~ces fprming components, parts,

pieces and equipment. * (Intended to ID.elude such} things as machinery, castings, liquids, formed steel shape~, ag~egates and cement.)

When AS:tv.fE Code *material is referenced, this refers to metallic materials which are manufactured to an SA, SB or SFA Specification or any other material specification permitted by Section III of the Cod.e. For Division* 2, refers to metallic materials, as well as to nonmetallic materials, conforming to the specifications permitted in Section ill of the Code.* . * -

Material Supplier

'l : * ~-.'

An organization. which supplies material produced and certified by Material Manufacturers, but does not perform any operations which affect the material except when agreed upon by the Certificate Holder who uses the material in Code construction or when so authorized by a

Quality System -Certificate (Materials). The Material Supplier may perform and certify the results of tests, examinations, repairs, or treatments required by the material specification or by this Section which were not performed by the Material Manufacturer.

Page A-12 REVISION 63b 6/ 16/ 93

-DEFINmONS APPENDIX A Modification A change to an item made necessary by, or resulting in, a change in

. design requirements. (ASME-NCA 9000)

A planned change in plant design or operation and accomplished in accordance with the requirements and limitation of applicable codes, standards, specifications, licenses and predetermined spfety restrictions .

.- N-National Standards Standards maintained at or issued by the National Institute of Standards and Technology (NISTI or other designated institutions, and the values Joi: natural physical constants and conversion factors recommended by the NIST.

Nonconformance A deficiency--in characteristic, documentation or procedure that renders--.

an item or activity unacceptable or indeterminate. Examples of nonconformance include: physical defects, test failures, incorrect or inadequate documentation and deviation or variation from prescribed

processing, inspection or test procedures.

Nonpermanent Record * ~ -*-

A record that is required to show evidence that an activity was performed in accordance with the applicable requirements but do not meet the criteria for a lifetime record.

NQA"".1 (ANSI/ ASME NQA-1-1989 Edition)

Quality Assurance Program Requirements for Nuclear Facilities. For AS:ME Section ID activities, NQA-1 is as modified by the Code.

Page A-13 REVISION 63b 6/ 16/ 93

DEFINmONS APPENDIX A Nuclear Steam Supply System (NSSS)

That portion of the nuclear generating plant which provides steam from nuclear heat. It includes reactor, its control systems, main coolant and steam generation systems, fuel handling equipment, emergency core cooling system and other safeguards, associated electrical equipment, instrumentation, spent fuel handling and radioactive waste disposal system.

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.

Off-Site Review The off-site review and approval function required by the Technical Specifications. -- *---:- -

On-Site Quality Verification Engineer or Inspector As used herein shall mean Senior Nuclear Quality Programs Engineer or Inspector or Nuclear Quality Programs Engineer or Inspector or Nuclear Quality ProgrCl!l\~ Engineer or Insp~o~Jor quality assurance .for maintenance, modifications, in-service inSpedion and Stores activities_.

On-Site Review The Station review and approval function required by the Technical Specifications.

Operational Tests Tests that are performed during the op_e_rations of the .plant to verify continued satisfactory performance of safety-related structures, systems and components.

Page A-14 REVISION 63b 6/ 16/ 93

DEFINITIONS APPENDIX A

Phased replacement

-P-.

Where several identical items are to be replaced with a new model, replace a few at a time to allow monitoring of the new items.

Preliminary Safety Analysis Report (PSAR)

The initial detailed safety evaluatiqn prepared for the U.S. Nuclear Regulatory Commission prior-to-.issuance of the site construction permit and which delineates design, n_ormal and emergency operation, potential accidents and predicted consequences of such accidents and the means proposed to prevent such accidents and/or reduce their consequences to acceptance levels.

. Preoperational Testing ,.

Preliminary testing prior to fuel loading and plant operation to assure that construction and installation are complete and to verify design and system functions.

Procedure A controlled document that specifies or describes how an activity is to be performed .. Jt may include methods to be employed, equipment or .. ,

materials *to be used, accept/ reject criteria and sequence of operations.

Projects Construction Superintendent The site Projects Construction Superintendent is the person responsible in the Engineering and Construction Department for initial plant construction. * -

Proprietary Designs * .

Designs-engmeered, produced and sold by a manufacturer in accordance with his or her criteria and warranty.

Page A-rs REVISION 63b 6/ 16/ 93 I

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DEFINmONS APPENDIX A Purchase Requisition The basic document describing a material, component or service which is converted into a purchase order for procurements.

-Q-Quality Assurance All those planned and systematic actions :necessary to provide adequate confidence that an item or a facility will perform satisfactorily in service.

For the Code, Quality Assurance comprises all those planned and systematic actions necessary to provide adequate confidence that all.

items designed and constructed are in accordance* with the applicable Code.

Quality Control Those quality .assurance examinations and actions which provide a means to contr<;>l and measure the characteristics of an item, process or facility to determine or establish conformance to acceptance standards

- and specified requirements.

Quality Receipt Inspection Report A form utilized by station Quality Control to document technical receipt inspection of Code and safety-related items received by station Stores Department. - ~ -*-

- R-Receiving Inspection Notice (RIN)

A form initiated by station Stores Supervisor upon receipt of Code or safety-related items to record inspection for damage, to record receipt of documentation and to notify station Quality Control Engineer that item(s) are available for technical receipt inspection..

Page A-16 REVISION 63b 6/ 16/ 93 1

DEFINITIONS APPENDIX A Record A completed document that:

a) furnishes evidence of the quality of items or activities b) furnishes evidence of compliance with regulations or requirements c) is required by Technical Specifications.

-** ~- ..,._ -****

Included are such related documents as drawings, specifications, procurement documents, procedures, operating logs, and reportable occurrences.

Such documents may be originals or reproduced copies.

Registered Professional Engineer (RPE)

A person co~_petent in the applicable field of design and qualified in accordance with the requirements of ANSI/ ASME 626.3-1988.

Repair The process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original

-requirements.

For ASME Section -m items, repair is the, process of an

-physically restoring a nonconformance to a condition such that item complies with Code requirements~

Request for Bid Invitation made to suppliers or contractors to bid on a specific task for materials, goods and services. -

Page A-17

.*~-**

REVISION 63b 6/ 16/ 93

DEFINTilONS APPENDIX A Request for Purchase A Generating Station's document originated by foremen, supervisors or department heads which designates the required items and services and delineates the design specifications, applicable codes and standards, as well as, any special requirements. This document is the basis of initiating a Purchase Requisition.

Rework The process by which a nonconfo@ingJtem is made to coriform to a prior specified requirement by completion, remachining, and re-assembling using previously approved procedural requirements. (For ASME Section III, rework is same as repair.)

- S-Second Level Desi~_Review Independent objective assessment of a design by qualified personnel who have no direct project responsibility for the design.

Significant Conditions (adverse to quality)

Those violations, deficiencies or events, having safety significance, that are required to be reported in writing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the NRC; severe operating abnormaliti~ or large deviations from expected plant performance of safety related structures, systems, or components; "events'~ as described in the plant Technical Specifications; pervasive breakdowns in the quality assurance program; recurring deficiencies or errors that cannot be dispositioned or brought into conformance by established corrective action systems; or. violations of the ASME Code that cannot be readily brought into compliance.

Source Acceptance

--"~ ..... ~

Acceptance made at Vend or plant prior to shipment of purchased items .

Page A-18

REVISION 63b 6/ 16/ 93 *

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DEFINITIONS . APPENDIXA

Source Inspection Inspection carried out at Vendor plant prior to shipment of purchased items.

Special. Process A process, the results of which are highly dependent on the control of the process or skill of the operator, or both.

Special Process Procedures. Manual A compilation of Commonwealth Edison company procedur.es governing nondestructive examination and special processes such as welding and I-heat treating.

Specification A concise statement of a set of requirements to be satisfied by a* product, a material or process indicating the procedure by means of which it may be determined whether the requirements given are satisfied.

Start-up Tests Tests that are performed after initial fuel loading and proceed through several power level plateaus to 1003 power.

StockMat~l

- --...... ~

Material which is or may be used for conversion to an ASME SA, SB, or SFA Specification or. allowable AS1M Specification~ As used in this program. Stock Material is that ~aterial that has not been produced in accordan~e with an NCA 3800 QA Program.

Surveillaitce Examination of supplier's manufacturing, inspection and test operations and of records of work in progress, this activity is documented.

Page A-19 REVISION 63b 6/ 16/ 93 I

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DEFINITIONS APPENDIX A

.~

Survey A documented evaluation of an organization'~ ability to perform Code activities as verified by a determination of the adequacy of the organization's quality program and by a review of the implementation of that program at the location of the work.

-T-Technical Review A determination as to whether a nonconforming item will be accepted "as is", reworked, repaired to an acceptable condition or rejected.

Technical Specification The design and performance criteria and operating. limits and principles of an operating lice~e to be observed during initial fuel loading, critical testing, start-up, power operations, refueling and maintenance operations.

Test Determination of the *physical and functional properties .of items by subjecting the item to a set of physical, chemical, environmental or opei:a~g conditions.

Test Plan An outline, narr~tive description or flow diagram indicating the tests to be performed, the methods to be used and the points in the process where they are to be executed. May be a test procedure.

Traceability The ability to verify the history, location; or application of an item by means of recorded identification.

Page A-20 REVISION 63b 6/ 16/ 93 *

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DEFINIDONS APPENDIX A

-V-variation A nonconformance. Departure of a characteristic from specified requirements.

-W-Witness Points In a sequential operation, a notification to Commonwealth Edison Company or their authorized agent that a phase of work is about to be reached and Commonwealth Edison Company may witness such phase of work at a specific time or in process witnessing either where established in the Traveler or Procedure or in the course of monitOring the work activity, to. verify acceptable performance of* such activity.

Work Instructions Instructions to personnel performing work on specific areas such as controls and identification of materials and equipment during fabrication or installation.

Workmanship **

That quality of an item expressing its skillful and artful manufacture, without apparent blemishes.

Page A-21

REVISION 63b 6/.16/ 93

ASME CODE INTERFACE TABLE OF CONTENTS (Rev. 63b) 2 pages 1.0 GENERAL (NCA 4134.1, NCA 4134.2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Statement of Authority .......... : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.2 R:s.p~nsibility - Gen:r~l. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.2.1 D1vis1on 1 - Responsibility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.2.2 Division 2 - Responsibility .................................... : 4 1.3 Organization Charts ....................*. . . . . . . . . . . . . . . . . . . . . . 4 1.4 Policy Statement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.5 General .................... *.............. *.............. *. . . 5 1.6 Training ........ *.... .- ;-:--:* :* -~":' . ........... * . . . . . . . . . . . . . . . . . . . . . 6 2.0 DRAWING AND SPEOFICATION CONTROL. . . . . . . . . . . . . . . . . . . . . . 6 2.1 Production, Maintenance and Distribution of Documents ........ ~ . . . . . 7 2.2 Drawing Revision Control/Design Change Control....... . . . . . . . . . . . . 8 2.3 Specifications and Engineering Standard Revisions Control . . . . . . . . . . . . . 8 3.0 PROCUREMENT (NCA 4134.4) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3.1 Procurement Control .................................... _.. :_._. 10 3.2 Source of Purchase Requisition Approval . . . . . . . . . . . . . . . . . . . . . . . . . 11 3.3 Source Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.0 PROCESS..CONTROL . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 12 5.0 INSTRUCTIONS AND PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.0 WELDING QUALITY ASSURANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.1 Welding Material Control ...... ; . ~-:. . . . . . . . . . . . . . . . . . . . . . . . . . . 13 6.2 Qualification of Welders. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 7.0 NONDESTRUCTIVE EXAMINATION (NB-5000 and CC-5000) and CONCRETE INSPECTION . . . . . . . . . . . . . . . . . . . . . . . . . 14 8.0 HEAT TREATING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 9.0 DOCUMEN"fATION ... *... *...................... ~- . . . . . . . . . . . 15

-9.1 System of Acquiring Final Documentation . . . . . . . . . . . . . . . . . . . . . . . . 15 9.2 List of Final Documents ................. -~ . . . . . . . . . . . . . . . . . . . . 16 9*:3 *Data Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . 16 10.0 NATIONAL BOARD REGISTRATION OF PRESSURE VESSELS .............. ~ . . . . . . . . . . . . . . . . . . . . . . . . . 17 11.0 TEST CONTROL .......* .... : ...... *. . . . . . . . . . . . . . . . . . . . . . . . . 18 12.0 CALIBRATION CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 13.0 NONCONFORMANCES~ ..................... -. . . . . . . . . . . . . . . . 19 14.0 INSPECTION AND TEST AND AUDIT PERSONNEL QUALIFICATION . 20 14.1 Qualification of Inspection and Test Personnel . . . . . . . . . . . . . . . . . . . . . 20 14.2 Qualification of Audit Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 15.0 AUDil'S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 16.0. LEVEL ill . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Page Al-1 REVISION 63b 6/ 16/ 93

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ASME CODE INTERFACE

TABLE OF CONTENTS 17.0 AUTHORIZED NUCLEAR INSPECTOR .................... *: . .. ; :-* 21 **

17.1 Relationship . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 22 17.2 Documents Available to the Authorized Nuclear Inspector . . . . . . . . . . . . 22 17.3 Choosing of Hold Points ....................... : . . . . . . . . . . . . . 23 17.4

NOE and the Authorized Nuclear Inspector . . . . . . . . . . . . . . . . . . . . . . . 23 17.5 Checklist of Final Documents and Data Reports ...... * : ..... : . . . . . . . 24 17.6 Documents in Electronic Media . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 18.0 CONTROL OF COMPUTER SOFTWARE ..................... *. . . . 24

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FIGURE I ......*............... : :- .. , ........ _,* . _.....* ., . . . . . Page 1 of 1 FIGURE Il ................*: .......... ; ........ *........ * ... ~ ..* Page 1 of 1 FIGURE ill ................ : ..- .. .' "* .. -. ........ .' ...... _. . . . . . . . Page 1 of 1 APPROVED:

R E. Querio *

Date Nuclear .Oversight Manager . *.

Page AI-2 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE The following is a supplement.which describes how this Manual complies with requirements of ASME Boiler and-Pressure Vessel Code -

Section m -Division 1 plus Division 2 for concrete containments.

1.0 GENERAL (NCA 4134.1; NCA 4134.2)

The Commonwealth Edison Company, hereafter known as the Company, has an overall Quality Assurance Program designed to accommodate the engineering and construction phases of a nuclear power plant as well as the subsequent operations of those plants including maintenance, modification, and repair. For purposes of Code activities, this program consists of four parts. The first part titled, Quality Assurance Program, which is also filed with the Nuclear Regulatory Commission as the Topical .Report, contains the requirements to which the Company has committed. This part, titled _AS:ME Code Interface, describes how the j Company's program complies with specific sections of the ASME Code~

The third part, the Station Quality Assurance Manual, covers essentially a Section XI program including In-Service Inspection activities. The last

part is titled Quality Assurance Procedures (QP's).

The Lo\\?'QP's (-1 through -50 suffix) were promulgated for administering contracts with construction contractors hired by the Company to build nuclear generating stations. These contractors had to have implemented their Company approved Quality Assurance

Programs. The focus was on those controls necessary for the achievement of quality in_ the co_~tnt~on of new stations.

The 'High" QP's (-51 through -100 suffix) were promulgated to be detailed* implementing procedures for use by the station and supporting departm~ts after the completion of the construction permit. The focus was on tl\e consistent achievement of quality in the operation, mainten~ce, modification, and repair of operating nuclear facilities.

Currently, the controls in the 'High" QP's have been essentially replicated in the stations' administrative procedure sets.

The language in both sets of QP's has evolved to acknowledge that all craft-labor c9ntraq .administration (including support of ongoing station Page 1-1.* REVISION 63b 6/ 16/ 93

(

.{,:

-ASME CODE INTERFACE operations) is by Site Engineering and Construction (SEC), and all routine maintenance and repair (as well as operations) is the responsibility of the station organization.

The Quality Procedures are invoked as detailed in QP 2.0.

The recent (1993) Nuclear Division reorganization has focused the accountability for all activitie8 in the on-site organizations during all phases in the life of a nuclear station. This includes the use of craft labor in support of the stations. This AS:ME Code Interlace is provided to--

specifically explain the Company's implementation and compliance with Quality Assurance requirements of the AS1\.1E Code Section ill as

- detailed in NCA 4134. Figure I shows the relationships among this Manual, AS:ME Code NCA 4000, and 10CFRSO, Appendix B. Figure II identifies Division 2 document responsibilities.

Other detailed quality assurance p~oced ures covering items suCh as training, the training program, review of procurement documents, personriel qualificatien and certification, maintenance and updating of AS1\.1E Code information on the computerized Quality Approved Bidders Lists, off-site audit plans, filing, trending, etc~are *documented in the Nuclear Oversight Quality Assurance Procedures. Furthermore, individual Department procedures provide detailed requirements relative to specific responsibilities involving implementation of the Company's Quality Assurance Program, AS1\.1E Code and .other National* Cddes *an:d Standards 1.1 Statement of Authority The Statement of Authority of the Nuclear Oversight organization of the Company is contained in the preface of this Manual. The Nuclear Oversight organization, which includes the Onsite and Offsite Quality Verification Departments, is empowered to assure compliance with the quality requirements of the AS1\.1E Code, other codes, Federal Regulations and the various National Standards that are applicable to an Owner's and N-type Certificate Holder's program of quality assurance for nuclear Page 1-2 REVISION 63b 6/ 16/ 93

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ASME CODE INTERFACE power. Those engaged- in qualitf verification have the independence ~d authority to stop work.

1.2 Responsibility - General In the event that the Company undertakes the construction of a new nuclear generating station or begins a project involving significant Section III construction additions, a new project organization may be established. Such an organization will follow the same program as described herein and will be managed by the Engineering and Construction Department.

Responsibility for implementation of quality assurance requirements rests with the Chief Nuclear Operating Officer, while the verification of the implementation and the-establishment of policies involving quality assurance rests with the Nuclear Oversight Manager.

for construction of new plants, the Company relies upon the utilization*

of an Architect/Engineer (AE), Nuclear Steam Supply System (NSSS) suppliers,.._and subcontractors. The Company contracts with suppliers*

who are qualified in accordance with the applicable section of the AS1vffi Code and who have the appropriate Code Certificates of Authorization or have a written quality program that has been evaluated and approved by a Company survey. The responsibility for Code compliance remains with the Company when the Company is to stamp the item .. When the Company purchases Code_it~s-~~uipng stamping, it is the responsibility. of the approved Code supplier to stamp the item.

1.2.1 Division 1 - Responsibility It is the responsibility of the Engineering__and Construction Department to assµre that stress analyses or calculations for parts and appurtenances are correctly incorporated into the drawings and Design Reports of components_ for which the Company assumes overall responsibility. The drawings used for design and construction shall be identified, described, and in agreement with the Design Report before it is certified.

Completion ~f the appli_cable Data Reports and subsequent stamping will Page 1-3 REVISION 63b 6/ 16/ 93 I

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ASME CODE INTERFACE

. be done by the Company. When authorized by the Authorized Nuclear Inspector (AN!), stamping will be witnessed by the ANI and the Onsite Quality Verification Superintendent or his designee.

1.2~2 Division 2 - Responsibility For AS:ME Section ill, Division 2 concrete containments, the Company performs construction management and does not perform the actual construction. The surveillance of the post-tensioning systems for existing concrete containments is performed under the cognizance of the Company's Division 2, Chief Level m. ,

Site Engineering and Construction has the responsibility for preparation and control of the construction procedures necessary to manage the

concrete containment work, and for preparation of the- Construction Report and the C-1 Data Report~ They will delegate to their qualified contractors the duties of preparing implementing construction procedures and shqp and field drawings, including test procedures that are needed to satisfy the requirements of the construction specification and design drawings. The .responsibility for preparation and approval of the C-2 Data Report rests with the Fabricator. The Engineering and Construction Manager will approv~ the Design and Construction Reports, and will certify the C-1 and N-3 Data Reports.

1.3 Organization Charts The organization -charts describing the company's organization are contained in Section 1.0 of the Topical Report. The basic organizational structure within the Company during operations consists of a Site Vice

President at each site with centralized support and independent overview. The engineering and construction p~rtion of the organization consists of an onsite organization supported by a. centralized support organization. The site organization is intimately and directly involved with_ the day-to-day construction and engineering activities associated with n1:1clear facility construction and modification. The Site Vice Presidents and the Engineering and Construction Manager report _to the Chief Nuclear Operating Officer~ . . Station quality assurance is provided Page 1-4 REVISION 63b 6/ 16/ 93 J

ASME CODE INTERFACE by Onsite Quality Verification Department which is independent of the Chief Nuclear Operating Officer's organizations. The station Quality Control group performs typical quality control functions such as inspections and examinations.

Quality -Control is part of the Station organization although independent of production. Station Quality Control has an offsite reporting capability to the Nuclear Support Department to insure independence. Station Quality Control personnel have sufficient organizational freedom and authority to Stop Work in order to prevent inadvertent use or installation of nonconforming materials, parts, or components.

1.4 Policy Statement The basic policy statements concerning the Company's Quality Assurance Progr_am are contained in the "Policy Statement" at the beginning of each Section of the Topical Report. Overall policy includes not only .

:f'

~.

compliance with ASf\.ffi Section ID, for Division 1 items contracted for after July 1;--1-971, and for Division 2 concrete containment items contracted for after July 1, 1977, but also the requirements contained in ---

the Code of Federal Regulations lOGFR.50, Appendix B, ANSI/ ASf\.ffi NQA-1, 1989; and ANSI N45.2 Standards not included in ANSI/ AS~.

NQA-1, and ANSI N18.7. -

1.5 General

-"The Nuclear Oversight Manager informs the individual ANI's of the ANI Supervisor_'s approval of the Quality Assurance Program by transmittal of the acceptance letter to the individual ANI's.

The Company implements revisions to the Quality Assurance Program within 60 days of issuance. Final revisions to subordinate procedures and completion of training may take longer than 60 days.

Page 1-5 REVISION 63b 6/ 16/ 93 J -

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ASME CODE INTERFACE 1.6 Training Personnel performing activities affecting qualicy are oriented, indoctrinated, and trained in their assigned duties in accordance with_(!

documented training program.

Personnel performing special processes, inspection, and tests will be subject to removal from such activities if it is determined that the individual's capabilities or performance are not in accordance with Code requirements.

I The qualification requirements for personnel performing NDE and Division 2 Concrete inspection are contained in the CECo Special Process

. Procedures Manual (SPPM) Vol. 1. This document meets the require-ments of ASME Section III, NQA-1, and SNT-TC-lA.

The qucili.fication requirements for personnel performing inspections and

. tests are contained in the CECo SPPM Vol. III. This document meets the requirements of ASN.IE Sect. III and NQA-:1.

Personnel perfoiming audit activities are qualified in accordance with ASJ\1E Sect. III and NQA-1 and the Company's qualification procedure.

These personnel will have experience and I or training commensurate with the scope, complexity, or special nature of the activity audited.

Audit Team Leaders will be qualified based on education, experience, training, testing, audit participation and evaluation of written and oral communication skills. Auditor and Audit Team Leader qualifications are evaluated annually.

2.0 DRAWING AND SPECIFICATION CONTROL (NCA 4134.3, NCA 4134.5, NCA 4134.6, NCA 3551, and NCA 3556)

Drawing and specification control is maintained by Engineering and Construction to assure that only the latest approved drawings and specifications are utilized in the procurement, fabrication, construction, maintenance, and modification of nuclear power plant facilities. The Company utilizes a centralized Drawing and Document Control Genter Page 1-6 REVISION 63b 6/ 16/ 93

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ASME CODE INTERFACE to maintain an integrated document system not only for the Company but also for their subcontractors.

2.1 Production. Maintenance and Distribution of Documents The Company contracts with qualified and Company approved Architect Engineering firms to provide design drawings, standards, certified designs, construction specifications, stress analyses, and Certified Design Reports for initial construction of the power plant. Augmenting the basic contract is the contract with the Nuclear Steam Supply System supplier who produces drawings, standards, design specifications, stress analyses, and Certified Design Reports for those portions of the plant for which he is assigned responsibility. Design Specifications will be produced that are adequate to form the basis for fabrication in accordance with the Code and are available for all items requiring an AS:ME Code symbol.

Design reports will be produced for all components, component supports, and appurtenances. Load capacity data sheets and design repo~ sum~_aries supplied by a Certificate Holder shall be reviewed and .,,;.

verified by the* Company or by its A/E's.

For modifications, a qualified Architect'/ Engineer is engaged to produce the design. drawings, standards, certified design and construction specifications, stress analyses and design reports as required and to submit them for review, approval, and acceptance by the. Engineering. ,

and Construction* Department. The Company may elect to produce the

-required drawings, standards and-specifications *and perform reqUired calculations. Applicable requirements of the design specification will be ttanslateq into specifications, drawings, procedures, and instructions. In these instances, design work .reviews and Registered Professional *

Engineer (RPE) Certification will be accomplished under the direction of the Company's own Registered Professional Engineers. The applicable Authorized Nuclear Inspector shall be made aware bf the AS:ME Section ID Code related design changes involving these modifications and all such changes will be reconciled with documents used for construction. The design package will identify the assemblies or components that are part of the.item being designed.

Page 1-7: REVISION 63b 6/ 16/ 93

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ASME CODE INTERFACE Certification of all required design documents for initial construction and modifications which are performed by ~chitect/Engineers shall be by a Registered Professional Engineer. (Design docUments, as a minimum, and include design specifications, design drawings, design reports for Division 1, Load Capacity Data Sheets and design report summaries.

For Division 2, design documents include design construction specifications and reports plus design drawings.) The Design Report shall be certified only after all design requirements of the Code have

been met. . Such Registered Professional Engineers shall be other than the individuals- certifying the Design Specifications but are not required to be independent of the organization-holding the Certificate. The Company shall assure that all Registered Professional Engineers certifying design documents on their behalf are currently certified. Such Registered Professional Engineers shall be qualified in accordance with the requireme~ts of ASME N626.3-1988 and the Company's procedures; and their rec_grds,.shall be reviewed at least once every three years to _assure that the qualifications have been maintained.

2.2 Drawing ReviSfun Control/ Design Change Control Engineering and Construction and/ or Site Engineering and Construction, or their designee, assures control of revisions to drawings produced by its Architect/Engineer or Nuclear Steam Supply System Supplier by *.

requiring submittal for documented review and comment, of changes or revisions to the originally approved design drawings prior to release.

With respect to modification of systems, structures, or components, the design revisions are submitted to the respective electrical, mechanical, or structural engin~ering disciplines of ENC or SEC, or their designee, for review prior to release. (Design change evaluation is carried out in .

accordance with Section 3.0 of the Topical Report.) An updated drawing revision status listing is available from the Centralized Drawing and .

Document Center. -

2.3 Specifications and Engineering Standard Revisions Control The Engineering and Construction Department assures control of revisions to specifications and engineering standards utilized on nuclear Page 1-8 REVISION 63b 6/ 16/ 93

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ASME CODE INTERFACE power projects in accordance with the requirements described in Section 3.0 of the Topical Report. Design Specifications will be available for all components, appurtenances, and component standard supports (unless included in the design specification for the component).-: ***-* *" ..

3.0 PROCUREMENT CNCA 41~4>

Basic procurement control, as exercised by the Company, is described in Sections 4.0 and 7.0 of the Topical Report. Overall, the engineering and --=--- -*

construction portions of the procurement for constz:uction of a new plant are conducted in such a manner that the Architect/Engineer is required to submit their design, specifications, and standards to be utilized in procurement to the Company for review and approval.

Subsequent to approval of procurement documents by the Company, the actual purchasing is performed by the General Office Ptirchasing Department or satellite purchasing organizations located at certafu sites. *if.

Procurement by such site organizations are under the control and management of the General Office Purchasing Department. Associated procurement documentation packages, when, required, are made from specifications and drawings issued and approved by the Architect/Engineer or the Company's Engineering and Construction Department. m addition, procurement packages for AS:M:E Code purchases are reviewed by a representative of Quality Verification to assure requirements are provided and the vendor is on the computerized l

CE Co Qiiality Approved Bidders List. Designated individuals using written procedilres complete and document this review prior to contract.

award. *The Company plans procurement activities prior to the start of _

procurement. These activities are documented, including the * **

procurement method and organizational responsibilities. Changes to procurement documents are incorporated into the original procurement documents.

The NSSS Supplier performs procurement within an approved quality assurance program subject to the Company's audit and surveillance of subcontractor activities.

Page 1-9 REVISION 63b 6/ 16/ 93 I --

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ASME CODE INTERFACE

':3:1 . Procurement Co.ntrol (NCA 4134.4, NCA 4134.7, NCA 4134.8, NCA 4134.13

. and. NCA 4134.15)

Procurement document control in the design and construction phases of power plant construction is exercised by the Architect/Engineer or the Nuclear Steam Supply System Supplier in the specifications prepared by them. Such documents must comply with the requirements of the rules and regulations of ASME Section III as well as other regulatory guides, codes and standards. ~--- -*

. The Company identifies and selects qualified manufacturers and suppliers of material, items and services on the Quality Approved Bidders List. These suppliers are qualified by survey, audit,~.. or on the basis of being a current ASME Nuclear Certificate holder performing work within the. scope of the Certificate. Procurement of Code material is made from a supplier or manufacturer who .either holds the appropriate Quality System Certificate (Ma~erials) or has written quality program that has been evaluated and approved by CECo survey.

When the Company qualifies a Material Supplier or a Material Manufacturer under the provisions of NCA-38_00, the audit frequency shall be commensurate with the schedule of production or procurement but shall be conducted at least *annually during the interval in which the .

Company's material is being controlled by a Material Supplier or produced by a Material Manufacturer.

Personnel receiving ASME Code material it~s, and services assure that the appropriate documentation is submitted including. Certified Material Test Reports, Certificates of Conformance, and ASME Code Data Report Forms, as applicable.

During the operational phase, either an Architect/Engineer's control is exerted and/ or the Company's own internal control* is exerted, dependent upon the assignment of the responsibility by CE Co. *In those instances when the Company controls procurement, the requirements of.

AS:ME Section III, Oasses 1, 2, 3, CS, MC and CC, as applicable, are directly included in the procurement documents. In the instances of the Pagel-10 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE utilization of an Architect/Engineer, the requirements of AS:ME Section ID, as well as other applic_(lble_ codes and standards are included in specifications by the Architect/Engirieer and subsequently .Cl§~ur.ed by the Company's engineering review. *Where provided in the scope of the Certificate of Authorization, the provisions of NCA 3820(e), whereby a Certificate of Authorization Holder may supply material or may.

manufacturer and supply material, shall apply.

3.2 Source of Purchase Requisition Approval During the engineering and construction phase of a new project, requests for proposal are prepared by Engineering and include a procurement package supplied by the Architect/Engineer to the Company or are developed internally.

__ ;preparation of*site procurement requisitions is the responsibility of Site Engineering and Construction. ASME requirements pertaining to ,*.

~ection ID, Division 1, Classes l, 2, 3, a; and MC, as applicable, and Division 2, Class CC for concrete containments are included as part of '

such purchase packages. When work is instituted by the Company for the maintenance of an existing power plant, procurement requisitions ate initiated by the Station organization.

When procurement to support operations, including modifications and

repairs, is initiated, the procedures and requirements are the_ ~e as descrihed for the engineering and construction phase for a new plant. .

3.3 Soilrce Inspection Where source inspection is required, it will be performed by Company personnel or the Company's agent, as applicable. Inspection will be by qualified personnel in accordance with preplanned inspection procedures or checklists.Source inspection and audit activities are also performed by the NSSS Supplier. The Company audits these activities to assure compliance with design requirements. When requested by the ANI, the Company shall arrange for access by the ANI to the Company's Code suppliers' facilities. *-

Page.1-11 REVISION 63b 6/ 16/ 93 I-

ASME CODE INTERFACE 4.0 PROCESS CONTROL (NCA 4134.9, NCA 4134.10, NCA 4134.11 and NCA 4134.14)

Process Control is exercised by the Company _in those activities involving the Code. In the construction phases, this process control is specified as part of the Company's contract with its AE, NSSS Supplier, or involved subcontractors. The requirements for checklists, travelers and production order systems, are also included in the procurement documents. For AS~ Section ill, Division 2 work,. the Company contracts with AS:ME approved Certificate of Authorization holders for construction activities.

Process Control sheets, travelers or checklistS are prepared, as necessary, and include:

1. document numbers and revisions to which the process, inspection or test conforms, .

_

2. space for reporting results of completion of specific operations at checkpoints of fabrication, manufacture or installation, and

3. space for a signature, initials or stamp and date -of responsible Company representatives and the_ANI for those activities*

witnessed. -

Process control documents for special processes include, ~r reference:

1. - procedure, -personnel arid equipment qualification *

- requirements, - _

2. conditions necessary for accomplishing the process, and

3. acceptance criteria, -

4. the activities that require qualified inspection and test personnel. : - *. _

The Company submits welding and brazing procedures which have been qualified under the provisions of ASME Sections ID and IX to the ANI -1 for review and acceptance prior to use. -

Page 1-12 REVISION 63b - 6/ 16/ 93

~-' *.-. ~ - :-., .. ~. --...

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ASME CODE INTERFACE 5.0 INSTRUCTIONS AND PROCEDURES <NCA 4134.5>

The Company reviews instructi.~ns, procedures and drawings for adequacy, completeness and correctness prior to approval and issue.

The Company establishes procedures to control minor changes to documents. These procedures identify the type of changes that are considered minor as well as the personnel who are authorized to review and approve ~ese changes.

Nuclear Oversight reviewspro~;dures fo:r AS:ME Section Ill (Division 1 and 2) construction.

6.0 WELDING QUALITY ASSURANCE <NB-4300, NCA 3130, NCA 4134.9, NCA 5253 and NCA 5254)

Welding quality assurance, as practiced by the Company or their agent, is a controlled plan which assures that the welding procedures and welding personnel are properly qualified in accordance with Sections Ill and IX of the ASrvffi Code. In.the construction phase, welding quality assurance is specified as part of the Company's contract requirements with their A/E, NSSS Supplier, or involved contractors. Control is assured through the Company surveillance and audit or through the use of Independent Testing Agencies.

6.1 Welding Material Control, .

The welding material control system including details of control of storage, issuance, and use, is as. outlined in the Co~pany SPPM.

6.2 Qg:alification of Welders The Company qualifies welders in accordance with the CECo SPPM.

When there-is a specific reason to question the welding procedure or the ability of welding personnel, the Authorized Nuclear Inspector may require requalification.

Page 1-13_ REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE

7.0 NONDESTRUCTIVE EXAI\11NATION <NB-5000 and cc-5000> and CONCRETE INSPECTION <cc-sooo>,

(NcA 5255, NCA 5256)

For site contractors requiring subcontracted NDE and concrete inspection services, the Company contracts for provision of such services. The administration of the contract is assigned to the Onsite Quality Verification Department where such services are established for Engineering and Construction administered contracts. In addition, the administration of such contracted sgfVic:E$. involving operating stations is

undertaken by the station Quality Control Superyisor. Nondestructive examination and concrete inspection and testing contractors are sitrveyed-and qualified by the Company, and resulting qualification documentation is supplied to the site Code contractors prior to their use of examination and inspection services. The performance of such services shall be by agreement with the inspection and testing contractor. The site Code Contractor contractors utilizing such testing and inspection services sh~ll review and accept procedures and personnel qualifications of the testing and inspection contractor. The details governing qualification of*

personnel and procedures, NDE results, and equipment are contained in the CECo SPPM. NDE Procedures shall be proven by demonstration to the satisfacti_on of the cognizant Authorized Nuclear Inspector or Authorized Nuclear Inservice Inspector, as applicable.

Concrete inspection and testing personnel shall be qualified in .

accordance with the requirements of Appendix VII of ASME Section ill, Division 2.

8.0 HEAT TREATING <NCA 5263, NB-4600>

Heat treating operations performed by or under the cognizance of, the Company are performed in a controlled and documented manner and the appropriate process parameters are monitored* and recorded as required by Section ID of the ASME Code.

Page 1-14 REVISION 63b 6/ 16/ 93 I

ASME CODE INTERFACE 9.0 DOCUMENTATION (NCA 4134.5, NCA 4134.6, NCA 4134.8, NCA 4134.9, NCA 4134.10, NCA 4134.11 and NCA 4134~17)

Records related to Code work are indexed and made available to the Company by the vendor. Records are also made available to the ANI.

The records program for classification and retention of records complies with Tables NCA 4134.17-1 and NCA 4143.17-2.

The records program provides for:

1. requirements for radiographic reprod ~ction,

2. identification of records to be maintained,

3. validation of records,

4. indexing and location of records, and

5. maintaining traceability of records.

The receipt control system includes:

1. protection from loss or damage during receipt,

2. . identification of responsible department/individual,

3. designation of required records,

-4. identification of records received,

5. inspection of incoming records using written procedures, and

6. a structure to maintain control during ~e process.

~***

A re~ords custodian inventories record's submittals, acknowledges receipt

.

and processes records.

9.1 System of Acquiring Final Documentation In those instances where the Company performs a modification involving Code, the verification and acceptance of satisfactory completion of .-

procedures, certification data, NDE documentation, etc., that were required to acceptably repair, fabricate, and install the items specified in the maintenance modification work package is the responsibility of Station Page 1-15 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE Quality Control. When the Company has contracted for the fabrication, modification, maintenance or repair, the AS:ME qualified contractor is responsible ~()r_ ~e final documentation.

Upon completion of the required testing, the complete documentation package is submitted to the station's Technical Staff Supervisor for review and acceptance. The document package shall be forwarded expeditiously to the station Central File Supervisor for filing and retention.

Quality Assurance records shall be retained, identified, indexed, protected, retrievable and accessible, plus be__classified as lifetime or nonpermanent as identified and provided in Section NCA 4134.17 of Section ill of the ASME Code. Permanent lifetime records are either maintained in

. duplicate storage or in 2-hour fire rated facility meeting NQA-1 requirements. When temporary storage of records is required, at least a 1-hour fire rated container shall. be used. Facilities use for duplicate storage are sufficiently separated to eliminate a simultaneous hazard. **-The enforcement authority is kept notified as to the location of records showing compliance to Sections ill and XI.

9.2 List of Final Documents For each contract involving ASME Code activities, a list of required final documents shall be prepared. This list shall include the requirement~ of ASME Section ill and applicable specifications, drawings, production travelers, maintenance procedures, etc. A Design Report summary may be provided in lieu of a Design Report for Standard Supports. The Final Documentation Checklist shall provide for the review and concurrence, of the Authorized Nuclear Inspector and the Quality Control Supervisor.

9.3 Data Reports The Engineering and Constructian Manager, as the chairman of the Nuclear Engineering Committee, has overall Owner's responsibility for the Form N-3, N~5, ~C-1 Data RepoJ:t and other CECo N-type Data Reports, including stamping responsibility for ASME Section III, Div. 1 .

and Div. 2. The Engirieering and Construction Manager delegates Page 1-16 REVISION 63b 6/ 16/ 93

. \ .

---~

ASME CODE INTERFACE signature authority for -Code activities to* the Site Engineering and Construction Managers, however,__ he retains the overall responsibility.

The sequence of stamping and for the completion of the Code Data Report Form shall be determined by the Authorized Nuclear Inspector and the Certificate Holder.

In any case, the Code Symbol Stamp shall not be applied until completion of the required examination and testing, and only with the authorization of the Authorized Nuclear Inspector. Before the component or appurtenance is placed in service, copies of the appropriate ASME Data Reports are filed with the enforcement authorities having jurisdiction at the location of each installation.

10.0 NATIONAL BOARD REGISTRATION OF PRESSURE VESSELS Pressure vessels constructed to ASME Section Ill rules after December 31, -~

1976 for which Commonwealth Edison Company does the stamping under its ASME N-Certificate of Authorization shall be registered with the National Board of Boiler and Pressure Vessel Inspectors. The Engineering and Construction Manager shall have the responsibility for controlling the consecutive issuance of National Board serial numbers to be affixed to these pressure vessels and shall maintain a record of the

_. serial numbers assigned to each specific item. There will be no skips, gaps or duplication of National Board serial number issued .for these

pressure vessels. The r~ord-~s;hall-mclude the date issued, description of the product to which the number is assigned, manufacturer's serial number, the Commonwealth Edison Company National Board serial number, and any additional information necessary to identify the item.

The Engineering and Construction Manager shall submit to National Board the original and one legible copy-of-the ASME Data Report for each nuclear pressure vessel required to be stamped and registered with National Board by the State of Illinois Boiler Safety Act, within 30 days of being stamped. The nameplate applied will conform to the facsimile included on Figure ID.

Page 1-17 REVISION 63b 6/ 16/ 93 I--

ASME CODE INTERFACE 11.0 TEST CONTROL <NCA 4134.n>

Test procedures identify or reference requirements and acceptance criteria contained in the AS:ME Code. The Company. uses markings, tags, stamps, routing cards, labels, forms, or other means to indicate the status of examination and tests. The required inspections and tests described in Section 10 and Section 11 of the Topical Report are performed before placing equipment in service.

12.0 CALIBRATION CONTROL <NCA 4134.12>

To maintain accuracy within necessary limits, the measuring and test equipment used in activities* affecting quality is periodically calibrated and adjusted in accordance with written procedures appropriate to the item(s) of measuring and test equipment involved. Procedures also are used to specify preoperational checks, environmental requirements, step-wise instructions for use, and instructions for storage. Suppliers and contractors to the Company are required to have and employ similar control measures which will be assured through surveillance, audit and

approval of contractor procedures.* *

The System Operational Analysis Department will be responsible for calibration and maintenance of the Company's measuring and test .

equipment. Assistance in this activity will be obtained from vendors or laboratories who .have the necessary capabilities. Calibration authority

~ay be delegated- to the sites by the -SOAD-Manager.

When measuring and test equipment is found to be out of calibration, an evaluation shall be made and documented of the validity of previous inspection or test results and of the acceptability of items previously inspected or tested. All pressure test gauges used-in ASME pressure testing shall be calibrated against a standard dead weight tester or a calibration master gauge prior to and after each test or series of tests.

Charpy V-Notch Testing Machines sha1tbe calibrated at least once each year in accordance with ASTM-E-23-72 and employing standard Page 1-18 REVISION 63b . 6/ 16/ 93

ASME CODE INTERFACE specimens obtained from the National Institute of Standards and Technology (NIST) Gaithersburg, MD. *The associated temperature instruments shall be calibrated at least once in 3-month intervals or, when utiliied With longer periods between use, such calibration shall be performed prior to being used.

Tags or labels are affixed to measuring and test equipment or its protective storage container to indicate the current calibration status.

Devices consistently found out of calibration are repaired or replaced.

13.0 NONCONFORMA*NCES <NCA 4134.16>

During the construction phase of a new plant, the Company utilizes a Nonconformance Report (NCR) to document the identification, correction and disposition of items found not in compliance with specifications (mcluding the Code). The Company's contractors may also gener~te their own internal Nonconformance Reports; however, those contractar*--

identified discrepancies which require significant engineering to resolve or involve significant rework, must be submitted to the Company for review and approval prior to placing an applicable system in service. All Code noncompliances must be corrected and result in installations which comply with the Code.

Authorized and qualified personnel approve the proposed disposition of nonconformances. Completion of all req1:rlred corrective ~ctions *. * ,.. _* _,

(including actions to prevent !ecµr:rence) is verified and* this verification is documented. Nontonfonriances are made available to the Authorized Nuclear Inspector for his review. --

During tJle operations phase, the Company utilizes an Integrated Reporting Program which results in the generation of a Discrepancy Report for hard ware or ~de. related nonconforming conditions. Review, disposition, and verification are performed in a similar manner as

. describe~ !.qr_ Nonconformance Reports. The Authorized Inspector is givep the -opportunity to review the Integrated Reporting Program documents which involved ASME Code activities.

Page 1-19 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE 14.0 INSPECTION AND TEST AND AUDIT PERSONNEL QUALIFICATION 14.1 Qualification of Inspection and Test Personnel Inspection and test personnel shall be qualified to procedures which will comply with the AS:ME Section m requirements of ANSI/ ASME NQA-1-1989, Supplement 25-1 and meet the intent of Appendix 2A-l, and shall include requirements for qualification, personnel selection, indoctrination, training, determination of initial capability and provisions for periodic evaluation of performance. The certification of qualification shall document as a minimum, the employer's name, identification of person being certified, activities certified to be performed, basis used for certification, results of periodic evaluation, results of required physical examinagqns, and the signature of the person responsible for such

certification.

14.2 _Qualification of Audit Personnel

. Auditors and Audit Team Leaders shall be qualified to procedures which

- will comply with the AS:tvm Section ID requirements of ANSI/ ASME NQA-1-1989, Supplement 25-3. Audit personnel shall have experience or training commensurate with the scope, complexity, or spe~al nature of the activities to be audited. The Audit Team Leader program shall include requirements for assessing written and oral communication skills, training, audit participation, and a qemQ!15ti:£ttion of proficiency, such as an examination. * **

The certification of qualification shall document the employer's name, Audit Team Leader's (or Auditor's) name, date of certification or recertification, basis of qualification, and signature of the Nuclear Oversight Manager, or designee. The qualifi~_tio-1) and certification records for each Auditor and Audit Team Leader shall be mair\tained and updated annually.

Page 1-20 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE 15.0 AUDITS <NCA 4134.18)

Audits are performed as required by the Audit Schedule. The audit frequency for ASME Code activities shall be commensurate with the schedule of activities and shall be such that an annual audit of all Code activities is performed at each station. Audits are performed using a preapproved checklist. The audit team is identified prior to the beginning of each audit. For audits related to Code activities, the Audit Team Leader signs the audit report. The Company provides personnel to ... -- -:,._ -****

accompany the ANI during required audits in accordanc_e with the Code and ASME N626. These personnel have responsibility for AS:ME Code I

and Quality Assurance Program compliance.

16.0 LEVEL ill The Company maintains a Chief Level III for NOE. He is qualified in accordance with the SPPM Volume I. He in turn has delegated certain specific discipline duties to Deputy Level Ill's. All such delegations and *)

their scope are documented. '

Administrative Level Ill's may be appointed for non-NDE qualification and certification activities. Such appointments will be documented and the scope of such appointments will be defined.

_J7.0 AUTHORIZED NUCLEAR INSPECTOR <NCA sooo>.

The Company 'maintains a valid, continuing agreement with an accredited

Authorized Inspection Agency to provide inspection and audit services involving Section III and XI nuclear work. The Authorized Inspection Agency is required to perform all of the functions and maintain the records required* in the applicable AS:ME N626 series of Standards and the ASME Code. The Company shall notify AS:ME and the enforcement authority whenever this written agreement is cancelled or changed to another Authorized Inspection Agency.

Page 1-21 REVISION 63b 6/ 16/ 93 I- --

ASME CODE INTERFACE 17.1 Relationship The Authorized Nuclear Inspector's primary contact is the station Quality Control Supenntendent. He also has ready access to the Onsite Quality Verification Superintendent who monitors and audits maintenance and modification work. At the construction sites, the primary contact is with the Site Engineering and Construction Manager, or designee.

17.2 *Documents Available to the Authorized Nuclear Inspector (NCA 3252)

-- - . . =:-~

. The Authorized Nuclear Inspector and any ASME survey team shall be afforded full access to procedures, procurement specifications, drawings, design specifications, construction specifications, design reports and documentation reviews of the design reports and construction reports involved in ASME Code work. De~ign Specifications shall be made available to the Authorized Inspector prior to fabrication of items requiring ASME Code stamp. The Authorized Nuclear Inspector, and Supervisor, shall have free access to the Company's and Manufacturer's and Supplier's facilities at all times while work on the item is being performed. He shall be afforded the opportunity to perform required N626 audits within the limitations of station safety, seairity and health regulations. He shall be provided adequate facilities including a drawer of a file cabinet, a desk, and a chair, plus a copy of the Company's Quality Assurance Manual.

The Authorized Nuclear Inspector shall be provided access to audit personnel qualification and training records as *wen-as audit records for ASME work. Audit records include the audit plan, report, written replies, .

and the record of completion of corrective*action.

The Authorized Nuclear Inspector.shall.also have access to proced~

developm.ent and procedure qualifications performed by a-contractor.

The Authorized Nuclear Inspector Will notify the Quality Control Supervisor or the Site Engineering and Construction Manager, as applicable, of any*]iroblem. '

Page 1-22 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE The Authorized Nuclear Inspector may request that AS:tvfE Data Reports, Certified Material Test Reports, and Certificates of Compliance be submitted to him to facilitate his monitoring of Code requirements. As a minimum, these doc;uments shall be submitted to the Authorized Nuclear Inspector prior to installation of the item(s). Also, a copy of this Quality Assurance Manual shall be filed with the Authorized Inspection Agency.

A copy. of the design report and any associated review documentation for the design report shall be made available to the regulatory and enforcement~ authorities having jurisdiction at the site of the nuclear ~-._ -**

power plant before it is placed in service.

17.3 Choosing of Hold Points The ANI/ ANTI shall be kept informed on relevant aspects of the current Maintenance/Modificati.pn work packages involving AS:ME Code work.

He shall be provided ample time during the work package approval process to insert his hold points in the work packages relating to Code ...

i work. He has ~e authority to place any item on hold if the Code is being violat.ed. Completion of ANI/ ANTI review will be indicated by signature on the work package approval documents. '*

Additional records required by the Authorized Nuclear Inspector to assure Code co~pliance will be supplied by the Company upon request.

Unlimited access to all facilities and activities shall be afforded the Authorized Inspection Agency.

17.4 NDE and the. Auth-oriz-ed-*N*udear Inspector Detailed nondestructive examination procedures are made available for review and acceptance by the Authorized Nuclear Inspector prior to their use in ASME Code work. Nondestructive examination personnel files are available to the Authorized Nuclear Inspector upon request. He may

require requalification of either procedures or personnel when there is specific reason to question the qualification of either.

Page 1-23 REVISION 63b 6/ 16/ 93

ASME CODE INTERFACE

.17.5 Checklist of Final Documents and Data Reports When the final documents and Data and Construction Reports have been prepared, the entire package shall be made available to the Authorized Nuclear Inspector. When the Authorized Nuclear Inspector is satisfied that the work is satisfactorily completed and ready to be stamped, he shall certify the Data and Construction Reports by signature. For Division 2 work, the Authorized Inspector shall assure that the Designer has signed such Data Reports and Construction Reports prior to affixing

his signature.

17.6 Documents in Electronic Media As technology advances, some or all work control and supporting documents may exist in all-electronic format. Permanent records required by the Code and by the jurisdiction will be retained in hard copy, including original pen and ink signatures, and will be afforded the same protection required for permanent records. When on-line electronic approval is utilized-,-measures will be established to assure that only those persons authorized to use and apply electronic approval giant such approval. Access control measure$ will be established to prevent unauthorized alteration or modification of documents controlling work..

The Authorized Inspector will be afforded the same opportunities to review and insert Hold Points as afforded for paper-based documents.

18.0 _,,CONTROL OF COMPUTER SOFlWARE Control- of computer software and resultant output that is. used in the performance of design is procured,. or developed, and maintained in_

accordance with the requirements of NQA-1 Suppleinents 35-1 and . *.

Supplement llS-2.' Quality Procedure QP 3-54 is the imple1llen~g .

procedure for the control of computer software.-QP 3-54 generally follows the intent of Part 2.7 to 1'JQA-2. 'Computer program outputs, .when ,

appropriately controlled, may be used as design inputs and are subject to the requirements of NQA-1, Supplement 35-1.

Page 1-24 REVISION 63b 6/ 16/ 93

/-' ... -) **~~~

-~/

FIGURE I ASME III 10CFRSO COMMONWEALTH EDISON QUALITY REQUIREMENTS NCA- APPENDIX B 1.0 Organization 4134.1 I 2.0 Quality Assurance Program 4134.2 II 3.0 Design Control 4134.3 III 4.0 Procurement Document Control 4134.4 IV 5.0 Instructions, Procedures and Drawings -- -. ~~ 4134.5 v 6.0 Document Control ..

4134.6 VI 7.0 Control of Purchased Material Equipment and Services 4134.7 VII 8.0 Identification and Control of Materials, Parts and Components 4134.8 __ .. YIII

"~

9.0 Control of Special Processes 4134.9 IX J

'f 10.0 Inspection 4134.10 x ,1

.: ~I 11.0 Test Control 4134.11 XI 12.0 Control of Measuring and Test Equipment 4134.12 XII 13.0 Handling, Storage and Shipping 4134.13 XIII 14.0 . Inspection, Test and Operating Status 4134J4 XIV 15.0 Nonconforming Materials, Parts or Components and Operations 4134.15 xv 16.0 Corrective Action 4134.16 XVI 17.0 QU_ality Assurance Records 4134.17. XVII 3280 18.0 Audits 4134.18 XVIII

--*;..:::***,.. ~

Pagel ofl. REVISION 63b 6/16/ 93

. .J.

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~-

FIGURE II ASME Section III Division 2 Responsibilities Table PREPARED REVIEWED CERTIFIED APPROVED1

PROVIDED. MADE DOCUMENT ,: BY BY BY BY BY AVAILABLE

~

, ' ONREQUE5f

~

\

Design Spectflcatlon NCA 3250) 01 0,0 .I' 01 - O,D,C,K,l,J -

~ Construction Spectflcatlon (NCA 3.340) D 0 D 0 O,C,F,M2,K l,J a

~

Design Drawtngs (NCA 3.340) D 0 D 0 O,C,F,M2 l,J,K Design Reports <NCA 3350) D D D 0 O,K,L l,J .

Comtructlon Procedures (NCA 3351) I (Note BJ C,F D,C - D,C D,O,C.L 1.J,K Certlfted Material, Test Reports or Certlftcates i of ComplJance (CB-2130, CC-2130) (Note BJ M C orD,F M \ - C,F,O J,1,D Shop and Field Drawings NCA 3452 (Shop) F D - ~ D C,F I (Field) C,F C,D - ilc,o C,F I (Note BJ

Construction Reports (NCA 3454) c j D D,I P,O D,0,J,K l,J Data Report C-1 (NCA 8410) c - D,C,1,0 ' - 0 l,J Data Report N-2 (NCA 8410) F - F,I ' - c J,J

~

Data Report N-3 (NCA 8420)

O D

C F

CECo Project Engineering (Owner or Deslgnee)

Designer (A-E)

Constructor (CECo Project Construction) .

0 Contractor to CECo Project Construction or another Constructor (Fabricator)

- K,I (1)

(2)

Owners deslgnee I

Provided when necessary to permit the Material Manufacturer to perform his duties In conformance with the Code.

M - Material Manufacturer (3) Approval Indicates an assurance that the ASME

°'tr

~

I I

K -

Authorized Inspector Jurisdictional Authority CECo Nuclear Engineering Department (Owner) requirements were carried out by the designated party.

L - CECo Construction Department P - Project Manager

~

Will be advised of the document avallabllity. I'

~

\D NCJTES: (A) CECo Project Construction Is the Construction Manager (B) Information provided to the Indicated participants when required to satisfy their designated

~ who will contract with contractors and CECo will have responsibilities under this Section. Other Information provided only by specific arrangement overall responslbllity. with the Owner. Participants are required to furnish only such Information as Is necessary to permit the recipient to perform his duties In conformance with this Section. . Othef Information may be furnished at the discretion of the responsible parties.

FIGURE Ill Facsimile of Mandatory Stamping and I or Nameplate Marking National Board Marking Area NAT'L BD.

(National Board Serial Number)

Certifie~ By (See applicable Section of ASME Code for required marking)

ASME Marking Area Approxhnateiy Sln" L X 3 *" H Page 1of1 REVISION 63b 6/ 16/ 93

.*~-*

ML17252A760

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