ML20028H709

Rev 59 to CE-1-A, Comm Ed QA Program for Nuclear Generating Stations

ML20028H709
Person / Time
Site:	Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle
Issue date:	07/23/1990
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20028H708	List: ML20028H707 ML20028H709
References
CE-1-A, NUDOCS 9101290026
Download: ML20028H709 (14)

Text

A.

CE-1-A Topical Report January 1976 Pr.

59 23-90 C3MM0NWEALTH EDIS0N C0MPANY QUALITY ASSURANCE PROGRAM F0n NUCLEAR GENERATING STATIONS COMMONWEALTH EDISON-COMPMY Post Office Box

'*7 Chicago, 1111ncis 60690

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4 LISTING COVERING REVISION Of TOPICAL REPORT CE-1-A Selow is a listing of Revision 59 changes to the Commonwealth Edison Company Quality Assurance Program Topical Report CE-1-A dated 7-23-90:

Rev. Content Pages 1-4; Pages 3-3, 3-4; 6-2; 7-3, 7-4, 7-5, 7-6.

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Approved:

Sc I N I

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H&ffager of Quality Assurance /

Nuclear Sefety v

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-t EXPLANATION OF CHANGES FOR' TOPICAL REPORT - REV.-:59-CQtt!QNHEALTH EDISON COMPANY PROGRAM TOPICAL-REPORT CE-1-A PAGE NO.

EXPLANATION Rev. Content Pages 1-4; These revisions are being made to Pages: 3-3,.3-4; 6-2;.

correct a typographical error.to, 7-3, 7-4, 7-5, 7-6 reflect ievised departmental titles, to correct a grammatical error,;and to clearly delineate Quality Controls.

r% ponsibility during receivingJas, acceptar.>.e and Nuclear Quality Programs-responst'allity as review.

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i CONTENTS TITLE EyiE REY.

DATE INTRODUCTION 1-1 56 09-13-89

1. ORGANIZATION A. Basic Organization Responsibilities 1-1 56 09-13-89 1-2 b7 12-01-89 B. Organizational Responsibilities for Major Activities 1-3 56 09-13-89 1-4 56 09-13-89 l

l-5 55 03-27-89 1-6 55 03-27-89 l-7 55 03-27-89 l-8 55 03-27-89 l-9 55 03-27-89 1-10 57 12-01-89 1-11 55 03-27-89 1-12 57 12-01-89 1-13 56 09-13-89 l-14 56 09-13-89 l-15 56 09-13-89 l-16 56 09-13-89 1-17 56 09-13-89 1-18 56 09-13-89 4

1-19 56 09-13-89 l-20 56 09-13-89 1-21 56 09-13-89 1-22 56 09-13-89 1-23~

56 09-13-89 1-24 56 09-13-89 1-25 56 09-13-89 1-26 56 09-13-89 1-27 56 09-13-89 1-28 56 09-13-89 1 56 09-13-89 l-30 56 09-13-89 1-31 56 09-13-89 l-32 56 09-13-89 1-33 56 09-13 1-34 56 09-13-89 l-35 56 09-13-89 1-36 56 09-13-89 1-37 56 09-13-99 l-38 56 09-13-89 1-39 56 09-13-89 1-40 56 09-13-89 l-41 57 12-01-89 1-42 57 12-01-89 Page 1

of _4_

Date:

07-23-9Q Rev. EE I

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CONTENTS; i

i TITLE EAGE

_ REY.

DATE ELGUhES' 1-0 Organizatlon Chart Related To Q.-A.

1-43 57 12-01 1-1 Organization' Chart - Quality Assurance-1-44 57 12-01-89 Nuclear Safety Policy and Oversight Dept.

1-1-1 Quality Programs and Assessment Department 1-45 57 12-01-89 1-2 Engineering and Construction. Department 1-46 57 12-01-89 1-3 Projects Organization and Nuclear 1-47 57 12-01-89.

I Engineering Department l

1-4 Projects Department (For Future Project -

1-48 57 12-01-89 i

Currently Inactive) 1-5 System Operational Analysis Department 1-49 57 12-01-89 and System Materials Analysis Department 1-7 Station Production Department Organization 1-50 57 12-01-89

2. QUALITY ASSURANCE PROGRAM 2-1 58 04-12-90:-

1:

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1 2

2-4 55 03-27-89 1

2-5 55 03-27-89 6-5 7 --.

12-01 l 2-7 57-12-01-89 2-8 55 03-27 !

3. DESIGN CONTROL 3-1 55 03-27 l 3-2 57 12-01-89 3-3 59 07-23-90 3-4 59 07-23-90

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4, PROCUREMENT DOCUMENT CONTROL 4-1 57' 12-01-89

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4-2 57 12-01-89' 4-3 -

09-13-89-:

. 4 57 01-89:

4-5 57 12-01-89=

5. INSTRUCTIONS, PROCEDURES AND DRAWINGS 5-1 57 12-01.5-2 55 03-27-89 5-3 0-01-76

- 6. DOCUMENT CONTROL 6-1 57 12-01-89 6-2 59 07-23-90 6 55 03-27-89' Page

_2__ of

_4._

Date: 07-23-9.0 Rev. Sii 4

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CONTENTS TITLE

--EAGE REY.

DATE'

7. CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES

'i-1 57 12-01 7-2 56 09-13-89 7-3 59 07-23-90 7-4 59 07-23-90

.7-5 59-07-23-90 7-6 59 07-23-90

8. IDENTIFICATION AND CONTR0' 0F HATERIALS,

.09-13-89 PARTS AND COMP 0NENTS' 8-1 56 8-2 55 03-27-89'

9. CONTROL OF SPECIAL PROCESSES 9-1 56 09-13-89 9-2.

57 12-01-89 9-3 55' 03-27-89

10. INSPECTION 10-1 157 12-01-89 10-2 55 03-27-89=

10-3 33 03-13-85

11. TEST CONTROL 11-1 57

.12-01-89 11-2 55

,03-27-89 11-3

'55-03-27-89' 11 55-

.03-27-89 12.-CONTROL OF MEASURING AND TEST EQUIPMENT 12-1 57 12-01-89 12-2 55~

03-27-89 12-3 57 01-89

13. HANDLING, STORAGE AND SHIPPING 13 26-10-83 13-2:

'55 03-27e89' 13 55-27 '

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14. INSPECTION, TEST AND OPERATING STATUS 14-1:

.55 03-27-89=

14 26-06-19.:

15. NOWCONFORMING-HATERIALS, PARTS OR COMPONENTS-J OPEMTIONS 15i1 57 12-01-89 15-2 55

--03-27-89 15 57-

12-01-89

16. CORRb:TIVE ACTION 1:

58 LO4-12-90. 2 58:

04-12-90:

i 16-3 58-04-12-90.

J 17, QUALITY ASSURANCE RECORDS 17.57

.12-01 17-2

'55 03i27-89 1

Page;

• of _i. Date: 07-23-90.Rev.152' j

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CONTENTS TITLE EAGE RG.

DAT1___

18. AUDITS 18-1 56 09-13-89 18-2 57 12-01-89 18-3 56 09-13-89 I

AEEEffD:X A Quality Assurance Program Manual Index A-1 59 07-23-90 Quality Assurance Procedures Manual A-2 58 04-12 90 Index (Engineering and Construction)

Quality Assurance Procedures Manual A-3 56 09-13-89 Index (Operations)

A-4 5

04-08-88 A-5 50 09-13-89 A

Approved:

If:-

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HanaprofQualityAssurance/NuclearSafety Page 4 of..4 Date: 07-23-90 Rev 59 9522H

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appropriate corrective action shall be taken.

The. Projects Erijineering Manager, chere established, prior to' plant start-up,_and~the !uclear Engineering Manager, after plant start-up for plant modifica*1ons, or by the -Nuclear fuel Services Manager for fuel or in-core relat(d matters for plant operations, or their respective agent or designee thall certifj that a review of the Design Report / Load Capacity Data Sheets has been conducted to assure that all the Design Specification and applicable Code requirements have been considered. Copies of the certification shall be attached to the copies of the Design Report, design drawings, stress calculations and Design and Construction Specifications and Reports which are made available, as applicable,-to the Authorized Nuclear Inspector for-review and certification and the enforcement authorities having jurisdiction over the nuclear power plant installation as provided by ASME Section III of the Code for Classes 1, 2, 3, CS, MC and CC.

Design information transmitted across interfaces.shall.be documented,_

controlled, and include the status of the information or documerit.

3.2 D_e.sigILChE903 Changes to drawings used for construction from the corresponding drawing used for stress analysis shall be certified, by the person or organization responsible for the stress analysis calculut ans, to have been satisfactorily reccaciled with those t

calculaF 'ns.

Oesign changes are controlled through document revisions resulting from design change requests and/or design change notices and are reviewed and evaluated in the same way as the basic design documents. Site and Station design change requests-will_be reviewed by the Station Nuclear Quality Programs Superintendent or designee, Technical Staff Supervisor, Projects Engineering personnel or_ Nuclear Engineering personnel after plant start-up _for plant modifications, and/or Architect Engineer, as applicable, and will be approved by Projects Engineering or the Nuclear Engineering Department af ter plant.

start-up for plant modifications after which the approved change will be incorporated in design documents, approved, released and distributed.

The extent of _ the evaluation will be. determined by the complexity of the change'and its safety-related. function with respect to the original design. Coordination of review and evaluation of design changes will be by Projects Engineering or the Nuclear Engine? ring-J r

Department.after plant tartup for plant modifications._ The control of documents will be maintained within the system described in Quality Requirement 6.0, " Document Control."

l Plantmodifications.willbeevaluatedinaccordancewithtbe L

requirements of 10CFR50.59'and to the requir(ments of the ASME Boller and Pressure Vessei Code Section III and will be: submitted to the Manager of Quality Assurance / Nuclear Safety, Superirtendent of Off-Site Review and the Production Superir.tendent.

Also, fcr Code-Work the modification will be reviewed with the Authorized Nuclear Inspector who will then stipulate the inspections he-Id ends to make_ prior to r

implementation of the modification work.

The Production Superintendent authorizes the modification.

The Technical Staff Surervisor reviews and 3-3 Rev. 59 7-23-90

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Commonwealth Edison

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i approves the proposed modification and is responsible for verifying

- i that operating procedure changes are_ accomplished as_to station modifications.

The station Training Supervisor is responsible ~that required training concerning plant modifications is accomplished for responsible. plant personnel where the performance.of their. duties may be affected.

Nuclear Quality Programs-assures-such training is completed.

The Superintendent of Off-Site _ Review reviews and approves proposed modifications to plant systems and; components involving a revision-to the Technical Specifications or-a previously.-

unreviewed safety question.

Evaluation and ap,yoval_of the substitution of equipment is performed by the Technical Staff Supervisor-and either the Production Superintendent, Assistant Superintendent of Operating or Assistant Superintendent of Maintensnce, Projects Engineering, Nuclear Engineering or equipment vendors provide engineering analysis as required by the design specification, Projects Management or Nuclear Engineering shall_ assign,an organization to verify installation of modifications in accordance=

with design and qualltv assurance requirements.

When modifications cannot be completed in accordance with drawings and specifications, a review for disposition will--be requested of the cognizant Engineering Department.

The verifying or checking of design features and modifications is done by qua11 fled individuals or organization other than those who prepare the original design or design modification but who may be from the same organization.

The assigned 1.nstallation department furnishes. Projects Engineering and, after plant start-up for modifications, the Nuclear Engineering Department, as-built-information to review as to.-

correctness and to issue as-built drawings.

Test data required by Projects Engineering involving-initial construction and.by the Nuclear Engineering Department in olving modification to verify the satisfactory installatiorrof components is obtained by organizations des 1gnated by them.

After completion of construction, station operating _

personn.el and station Quality. Control personnel verify the satisfactory final testing of systems required by Projects Engineering or Nuclear Engineering. Also, where-applicable, before-the component or appurtenance is placed in service,: copies of the appropriate ASME Data Reports and Certified Design and Construction Reports and Design and Construction Specifications are filed at the location of the installation and made available-to the. Authorized Nuclear Inspector and the State of--Illinois enforcement authorities hav g jurisdiction.

Completed N ta Report Form N-3, however, shall be filed by CCCo with such enforcement authority having jurisdiction.

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s.tatus reports identifying those documents currently in force.

These reports are distributed to all-involved parties.

Each document recipient is responsible _for in_suring that only the-

' latest authorized dowments are in-use and that void documents are so identified.

Requirec inspections and audits by Quality.

Assurance / Nuclear Safety end Nuclear Quality Programs are employed as a final check to assure that the latest authorized documrM s are in use.

Document distribution lists will be used and will designate recipients of document copies.- This listing-shall include document changes, distributions for comments, and/or distribution for use..Docuniit distribution reviews and approvals for key documents requireu by ASME Section III, Div._2 are as-stated in the ASME Code Interface Figure III.

Document distribution lists applicable to each projs:t i

shall be developed by the Projects Ergineering Manager or the Nuclear Engineering Manager,-as applicable, and will be coordinated with other CECO personnel as deeme Anpropriate by tLe cognizant Project Manager or Design SuperiM endent/ Supervisor, as applicable.

Each list will include an. issue dtte, revision date, and number, project identification, types of design documed s, listing of various document recipient positions and the number of copies of each position.

Each list willsbe distributed to the Architect Engineer and to all recipients identified on the list-and elli be accessible to the Authorized Nuclear Inspector for review and use.

The distribution-of documents will-be made by;the-Architect Engineer, or respective Project Manager or Design s perintendent/ Supervisor, as applicable, in accordance with the u

distribution list for each project.

Each recipient listed on-the distribution list shall, upon receipt of new documents, destroy or segregate and clearly _

mark all superseded documents.

Each receiving: office or area shall have a controlled method for checking receipt of new'or.

revised documents, and assuring that the' latest revised document-is in use.

Status reports will be issued periodically by Projects i

Engineering or Nuclear Engineering, as applicable, Architect Engineer and NSSS Supplier to all parties on.tha distribution-list stating the latest revision of documents to assist recipients in-maintaining up-to-date files.

Each document recipient on the distribution list is responsible for_ insuring that_only the latest authorized documents are in use and that-void documents are'so identified.

The responsible Projects Department Project Manager or the Nuclear Engineering Department Design

-i Superintendent / Supervisor shall periodically have the-document i

status reports. reviewed-to confirm that the latest revised docements are in use. Also, verification of compliance to this j

procedure by a physical check of document _ files, will be-periodically performed by Nuclear Quality Programs.

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1 7L3 Sun.e111ance of VendoI Doer.fLLlons Source surveillance will beccarried out through notification-points established as a condition of procurement ~of safety-related or ASME Section III ltems, Special consideration will be given for surveillance during manufacture when_one of the fcilowing is involved:-

~

a.

Determination of-conformance.of the item to purchase-9 order requirements at any other point would. require l

uneconomic disassembly or-destructive testing, 1

b.-

Special instruments, gauges, or facilities required for inspection or testLare more-readily available at source and would be uneconomic to reproduce at the_ job _ site.

c.

A receiving inspection would destroy or require replacement'of special' preservation and vaching, i

d, Quality Controls and inspections are integrated into-production methods, and inspection at the suppliers plant is necessary to economically verify test reports,_

inspection records, certifications or other evidence of r

quality.

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Source s.urveillance by Commonwealth Edison Company or its agents will not nullify the' vendor's responsibilities for. maintaining

- l a quality control organization de'livering items conforming to procurement requirerents.

Unless otherwise specified,-acceptance by-Commonwealth Edison Company wil.1 be at the nuclear generating station site in accordance with the terms of the contract

.The administration, surveillance and-inspectloi of off-site equipment and material vendors will be the responsibility of the ingineering and_

Construction Department, with final approvat _of' Inspection acceptance

_[

reports being vested in the Nuclear Qut.lity Programs. Department.

7.4 _Reteiv1na InspArdlOD j

Materials and articles received from vendors:wil_1 be; inspected upon receipt to assure physical integrity.and identity plus docmentation compliance with the procurement requirements..For71tems

-not source inspected, specific receipt iaspection measures such as mat'erial and dimensional checks against..pproved drawings'and specifications:and assurance that ASME Code Data Reports.are received will be performed by qualified personnel in-accordance with the applicable CECO or vendor-QA program and to checklists approved by appropriate Nucl_ ear Quality Programs or Quality Control _ personnel:to-

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verify conformance to procurement requirements._ Where receiving inspection requires the_use-of calibrated instruments'and tools, the identity of such eauipment shall be recorded on the applicable-receiving inspection documents. CECO purchases Code items and, turns them over to site Code vendors.._In the case where rece',pt inspection.-

is 7-3 Rev.59 7-23-90 Commonwealth Edison L

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I assigned to a site contractor, CECO provides them cith applicable i

procurement documents, such as the Purchase Order, Specification, i

etc., required to assure that the CECO purchased items meet Code requirements and to perform receipt inspection.

Also, for material supplied by non-Certificate holders, the CECO survey data covering such firms is made available to site Code contractors.

When CECO performs receipt inspeccion of such purchases or when CECO upgrades stock material for ASME Code use, CECO provides these vendors with the applicable Certified Material Test Reports and/or Data Reports plus the Material Receiving Report to provide verification that the purchased items supplied by CECO meet Code requirements.

Documented evidence that material or equipment conforms to procurement requirements including, for Code itcms, indication of their compliance to the specified quality program must be retained and available at the site prior to use or installation.

Part of this evidence shall be in the form of acceptable documentation such-as Certified Material Test Reports, Pressure Test Reports, Certificates of Conformance, etc.

Documentation requirements will be delineated in the Individual equipment specifications.

The Construction Materials Receiving Coordinator or designee will be responsible for assuring that receiving inspection is completed where the Engineering and Construction Department is responsible for the work; receipt acceptance approval will be by Nuclear Quality Programs or its designated agent.

Where ASME Section III components and safety-related materials and equipment are received by the station Stores Supervisor, station Quality Control will be responsible for receiving inspection and Nuclear Quality Programs Engineers or Inspectors for Maintenance shall assure through audit and surveillance that the receiving inspection is complete and traceability is maintained.

ASME Code material transferred from Stores or another Commonwealth Edison Company station shall meet the requirements specified for the designated installation.

Nonconforming equipment will be controlled.

L5_. _SunalteLAu.dit Vendors of safety-related and/or ASME Saction III items will be subjected to survey, audit or surveillance of their quality assurance system by CECO, or its agents, at intervals consistent with the importance to safety, complexity, and the quantity of the product or services being furnished in accordance with approved agenda and checklists to assure that the necessary manufacturing processes are belag utilized and that quality controls are being maintained.

L1_.Snuthr.isJutd_RenacenotJi Spare parts and. replacement items, equipment and components will be purchased to original or better design requirements in accordance with the controls herein.

The applicable quality assurance requirements will be included in the procurement documents.

7-4 Rev. 59 7-23-90 Commonwealth Edison

Such spare parts and replacements from vendors will require.

documentation by item, component, equipment or part number for iden-tification and traceability.

Documentation for material will-be in accordance.with procurement order requirements.

When the procurement order for ASME Section III components and safety-related spare parts, material, and equipment includes a specification or drawings, docu-mentation will be received from the vendor-which-verifies conformance 1

with those requirements.

In the case where the original part, item, component or-equipment was procured with no specifican y identified quality assur ance program requirements, or was procured from a vendor who no :

longer can ba retained on the nuclear Quality Approved Bidders 1.ist because of an inadequate Quality Assurance Program document, identical spare parts _and replacement items, components or equipment may be similarly procured from the' original equipment manufacturer (OEM), but care shall be exercised to assure at least equivalent s

performance:

that.ls, a joint technical engineering and quality H

assurance documented evaluation shall be conducted;to established.

requirements and controls by Technical Staff or Nuclear Engineering' and by Quality Assurance personnel.

The eva uation shall assure that interfaces, interchangeability, safety, fit and function are not adversely affected or are contrary to appilcable regulatory:or code requirements.

In the use of procurements of safety-related materials, e

parts and items that are a manufacturer's standard product (commercial grade l_ tem), such commercial grade items shall be inspected as part of the receipt: Inspection-fsaction to assure that:

(1) damage was_not sustained during shipment; (2) the item received-was the item ordered (i.e., it possesses the. required attributes

.p identical, as necessary, to the-item specified); and (3) documentation.as applicable to the. item,'was received and.is acceptable plus, after being received, such a commercial' grade-item.

i l-shall be tested,- where-applicable: to assure that it will perform its i

intended function (i.e., by means of bench testing and/or functional

[

testing as required)'.

A commercial grade item is one_that is not subject to i

design, specification, or-testing requirements by the supplier that-are unique _to nuclear power plants; is one that is'used in numerous 3

i applications other than nuclear' power plants; and it:is one-that can n

be ordered from the manufacturer / supplier on the. basis of I

-specifications set forth in the manufacturer's published product-l-

description _ (1.t... catalog) or on the basis of i ts manufacture to:

C

' national standards.

When an item is purchased by specifying the manufacturer's-catalog part number, when documentation:is required beyond that e

indicated-in-the catalog, and when such documentation 1s-not available:for items with the same_ part number obtained from the i

mv.ufacturer, the item does-not meet the: definition of a commercial i

grade item and shall not_be treated as a commercial grade item.

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The station Stores Supervisor and station Quality Control

, Supervisor ace responsible for assuring that docomentation for spare parts and equipment has been included as part of the shipment.

The documentation for the purchased material, equipment, and/or services, after being reviewed and accepted by the Quality Control Supervisor will be retained at the station.

When required documentation is lacking for safety-related and/or ASME Section III components or spare parts, the Technical Staff Supervisor will verify that appropriate documentation is obtained or that suitable Inspection and testing is performed to verify conformance to procurement requirements and that such items are treated as nonconformances.

Receipt inspection of spare parts and equipment purchased to ASHE Section III and safety-related requirements shall be reviewed by the Nuclear Quality Programs Engineers or Inspectors, i

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