ML20150D663

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Summary of 880628 Meeting w/C-E in Rockville,Md Re QA Program Plan for CESSAR-DC Sys 80+,request for Addl Info Re Review of Chapter 17 of Amend 12 & Engineering Plans for Revising QA Program Plan.Attendance List Encl
ML20150D663
Person / Time
Site: 05000470
Issue date: 07/01/1988
From: Vissing G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
PROJECT-675A NUDOCS 8807140097
Download: ML20150D663 (19)


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. July 1, 1988-Project No. 675

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APPLICANT: Combustion Engineering, Inc.

FACILITY:- CESSAR-DC, SYSTEM 80+ Design

SUBJECT:

SUMMARY

OF MEETING WITH COMBUSTION ENGINEERING TO DISCUSS

.THE QA PROGRAM PLAN FOR CESSAR-DC SYSTEM 80+, JUNE 28, 1988 INTRODUCTION A meeting of the staff with representatives of Combustion Engineering (CE) was held at the NRC offices in Rockville, Maryland, on June 28, 1988. The purpose of the meeting was to discuss the staff's Request For Additional Information (RAI) concerning the Quality Assurance Branch Review of Chapter 17 of Amendment No. 12 of CESSAR-DC, System 80+ and to discuss Combustion Engineering plans for revising the QA Program Plan. Enclosure 1 provides the list of attendance to the meeting. Enclosure 2 provides the RAI. Enclosure 3 provides the viewgraphs which were to be presented at the meeting.

DISCUSSION Because of travel difficulties, the lead NRC reviewer who was scheduled for this meeting _was not able to attend. Thus the meeting was postponed until a later date. However, CE representatives provided Enclosure 3 for reference during a conference call upon the return of the NRC lead reviewer.

CE irdicated that they are revising the Combustion Engineering's Quality Assurance Program as described in CENPD-210-A. The revise program will follow the guidance and requirements of NQA-1 and Regulatory Guide 1.28, Revision 3.

This revision will be submitted within a month. We indicated that we would respond to the submittal within 90 days following subt..ttal.

CE had a concern that the RAls did not seem to be correlated with the latest revision of the Standard Review Plan. This can also be resolved during the conference sall, original signed by Guy S. Vissing, Preject Manager Standardizat' ion and Non-Power 8807140097 080701 Reactor Project Directorate PDR PROJ Division of Reactor Projects - III, IV, 675A PNU V and Special Projects

Enclosure:

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UNITED STATES NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C. 20555 D

July 1, 1988 k.....

Project No. 675 APPLICANT: Combustion Engineering, Inc.

FACILITY: CESSAR-DC, SYSTEM 80+ Design

SUBJECT:

SUMMARY

OF MEETING WITH COMBUSTION ENGINEERING TO DISCUSS THE QA PROGRAM PLAN FOR CESSAR-DC SYSTEM 80+, JUNE 28, 1988 INTRODUCTION A meeting of the staff with re)resentatives of Combustion Engineering (CE) was held at the NRC offices in Roc (ville, Maryland, on June 28, 1988. The purpose of the meeting was to discuss the staff's Request For Additional Information (RAI) concerning the Quality Assurance Branch Review of Chapter 17 of Amendment No. 12 of CESSAR-DC, System 80+ and to discuss Combustion Engineering plans for revising the QA Program Plan. Enclosure 1 provides the list of attendance to the meeting. Enclosure 2 provides the RAI. Enclosure 3 provides the viewgraphs which were to be presented at the meeting.

DISCUSSION Because of travel difficulties, the lead NRC reviewer who was scheduled for this meeting was not able to attend. Thus the meeting was postponed until a later date. However, CE representatives provided Enclosure 3 for reference during a conference call upon the return of the NRC lead reviewer.

CE indicated that they are revising the Combustion Engineering's Quality Assurance Program as described in CENPD-210-A. The revise program will follow the guidance and requirements of NQA-1 and Regulatory Guide 1.28, Revision 3.

This revision will be submitted within a month. We indicated that we would respond to the submittal within 90 days following submittal.

CE had a concern that the RAls did not seem to be correlated with the latest revision of the Standard Review Plan. This can also be resolved during the conference call.

Guy S. Vissing, P oject Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III IV, Y and Special Projects

Enclosure:

As stated

.- Enclosure 1 Attendance List For Meeting with C.E. Concerning QA Program for System 80+

Name Organization Kenneth R. Hooks NRC/DLPQ/QAB Thomas L. Cameron C-E Mark W. Stewart C-E (Quality Assurance)

John P. Pasquenza C-E (Quality Assurance)

Guy S. Vissing NRC/PDSNP

4 e ENCLOSURE 2 REQUEST FOR ADDITIONAL INFORMATION

', CONCERNING OUALITY ASSURANCE BRANCH REVIEW 0F CHAPTER 17 0F AMENDMENT NO. 12 (Rev. 4 of CENPD-210-A and Letter of 12/15/87 versus NUREG-0800) 0F COMBUSTION ENGINEERING SYSTEM 80+ DESIGN, CESSAR-DC PROJECT NO. 675 260.0 Quality Assurance 260.1 Clarify the' C-E organization (s) involved in the System 80+ and under the cognizance of the QA program. Describe responsibilities of each and related interfaces. (1AS) '

260.2 Table 1 of C-E's 12/15/87 letter does not identify the organization (s) responsible for assuring design quality. That is , .

Section 17.1.3.1 of CEMPD-210-A describes the QA responsibilities of C-E's engineering organizations and the Manager of EQA, but then-responsibilities are not described in the letter. Clarify wh6 these responsibilities are since the September rearganization. (182) 260.3 Describe the qualification requirements for the following QA management positions:

Vice President, Nuclear Quality Systems Director, Quality Operations Manager, Quality Programs Manager Training and Administration. (IC2) 250.4 Section 17.2.1 states that Table 17-3 shows the "typical equipment" '

covered by C-E's QA program. For System 80+, identify in the SAR the specific equipment covered by the program. This can be done in Chapter 17 or in another chapter which is then referenced in Chapter 17. (2Ala)

Describe measures which ensure that the develoceent, control, ano 250.5

, use of computer programs will be included in C-E's QA program and describe how the QA program will be applied. (2 Ale) 260.6 Clarify that fire protection will be addressed'in the System 30-

- SAR, and de:cribe or reference C-E's QA provisions for fire protection. (2A10) 250.7 Provide a cemitment in CENPD-210-A to inform the NRC of changes :c the report in accordance with the requirefrents of 10 CFR 50.55(f)(3). (2B2, mod.)

250.8 Table 17-4 in CENPD-210-A provides C-E's connitments to QA Regulatory Guides. Update the table to address the guides and

- . - _ _ _ _ . _ _ . . _ _ - _ ~ _ _ .__ _____. _ _ _ . . _ . _ , _ . . _ _ _ _ _ _ _ _ , . - _ . . . _ _

Reculatory Guide Revision Date Coment 1.26 5 2/76 Released for Comnent 1.29 3 8/85 1.29 3 9/78 -

1.58 1 9/80 1.123 1 7/77 See also pp. 17.4-1 & 17.7-1 1.144 1 9/80 1.146 -

8/80 Clarify with the connitment to Rev. 3 of Regulatory Guide 1.28 whether C-E will meet NQA-1 or M45.2, N45.2.6, N45.2.9, etc. I Correspondingly, update Section 17.4 (first paragraph), Section 17.7 (first paragraph, Section 17.10 (first paragraph), and Section 17.18 (firstparagraph). (283) 260.9 Describe measures which ensure that the QA organization and the necessary technical organizations participate early in the QA program definition stage to determine and identify the extent QA controls are to be applied to specific structures, systems, and i components. ThiseffortinvolvesapplyingadefinedgradedapproacE to certain structures, systems, and components in accordance with their importance to safety and affects such disciplines as design, procurement, document control, inspections, tests, special processes, records, audits, and others described in 10 CFR Part 50, Appendir B.

(283) 260.10 Construction pemit holders are subject to 10 CFR 50.55. Since there is no construction pemit holder involved in the design certification of C-E's System 80+, provide a comitment that C-E will meet 50.55(e)(1)(i and 11). 50.55(e)(2, 3, and 4) and 50.55(f)(1) in confomance with the requirements of CENPD-210-A.

(284) 260.11 Section 17.2.6 of CENPD-210-A, "Management Evaluation of the QA Program " comits to an independent audit of the program at least once each two-year period. Upgrade this comitment to the performance of an annual independent, pre-planned, and documented assessment (or audit) of the QA program where corrective action is identified and tracked or justify not doing so. (2Cib) 260.12 Describe measures requiring a documented check to verify the dimensional accuracy and completeness of design drawings and '

specifications. (3E1) 260,13 Describe measures requiring that design drawings and specifications are reviewed by the QA organization to assure that the documents are prepared, reviewed, and approved in accordance with ccmpany -

procedures and that the documents contain the necessary QA requirements such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results. (3E2)

260.14 Discuss the timeliness of design verification of System 80+

including the timeliness of testing when testing is part of the des $ptverificationprocess. (3E4b and 3E5b)

Clarffy that design calculations, design analyses, topical reports, 26Q.15 and the System 80+ SAR are within the scope of CE's document control system. (6A1) 260.16 Describe measures which ensure that documents are available at the -

work location before coninencing work and that obsolete / superseded docum nts are removed and replaced in a timely manner. (6A4 and 681) 260.17 Describe measures which ensure that suppliers furnish the prehaser a description of nonconformances from the procurement requirements that have been dispositioned "accept as is" or "repair." (783) 260.18 For commercial "off-the-shelf" items where specific QA controls appropriate for nuclear applications cannot be imposed in a practicable manner, describe measures which ensure that special qualityverificationrequirementsareestablishedwhichprovidethel necessary assurance of an acceptable item by the purchaser. (784) i 260.19 Describe criteria C-E uses for detennining which processes are controlled as special processes and provide as complete a listing.of special processes as possible. (9A1) 260.20 Describe measures which ensure that inspection procedures.

instructions, or checklists provide for:

l I a. Identification of characteristics and activities to be

! inspected,

b. A description of the method of inspection.
c. Identification of the individuals or groups responsible for perfoming the inspection operation.
d. Acceptance and rejection criteria.

J e. Identification of required procedures, drawings, specifications, I

and their revisions.

f. Recciding inspector or dats recorder :nd the rasults Of tha inspection operation,
g. Specifying necessary measuring and test edluipment including accuracy requirements. (ICC1) 260.21 Describe measures which ensure proper correct *Ve action when a computer code is found to be nonc,nforming. Identify, by organi-zation or position title, C-E per:onnel authorized to review such nonconformances, disposition, and closecut. (15.1) i 260.22 Describe measures which ensure timeliness of corrective actions.

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ENCLOSURE 3 4

QUALITY ASSURANCE PROGRAM OVERVIEW MEETING WITH NRC STAFF JUNE 28, 1988 COMBUSTION ENGINEERING l

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AGENDA QUALITY ASSURANCE PROGRAM OVERVIEW MEETING WITH NRC STAFF JUNE 2,1988 INTRODUCTION T. L. CAMERON PROGRAM OVEliVIEW J. P. PASQUENZA PROGRAM DETAILS M. STEWART

SUMMARY

T. L. CAMERON DISCUSSION i

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PURPOSE o OVERVIEW COMBUSTION ENGINEERING'S QUALITY ASSURANCE PROGRAM o OVERVIEW CHANGES WHICH HAVE BEEN IMPLEMENTED AND ARE UNDERWAY o OBTAIN NRC's CONTINUED CONCURRENCE THAT OUR QA PROGRAM IS ACCEPTABLE AND THESE CHANGES DO NOT REDUCE C-E'S COMMITMENT TO QUALITY

o C-E'S CURRENT QUALITY ASSURANCE PROGRAM IS DESCRIBED BY CENPD-210-A o CHANGES TO REVISION 04 OF CENPD-210-A WERE RECENTLY SUBMITTED IDENTIFIED ORGANIZATIONAL CHANGES CONSOLIDATED NUCLEAR POWER SYSTEMS DIVISION QUALITY ASSURANCE FUNCTIONS INTO A NEW "NUCLEAR QUALITY SYSTEMS" DEPARTMENT l'

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ORGANIZATIONAL STRUCTURE

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NUCLEAR QUALITY SYSTEMS ORGANIZATION DIRECTOR QUALITY OPERATIONS MANAGER NUCLEAR QUALITY

- SYSTEMS QUALIIY PROGRAMS VICE PRESIDENT MANAGER i

. TRAINING &

MINISTRATION NUCLEAR SERVICES VICE PRESIDENT SENIOR VICE PRESIDENT NUCLEAR POWER

. SYSTEMS DIVISION NUCLEAR FUELS V*,JE PRESIDENT l

NUCLEAR SYSTEMS l

VICE PRESIDENT

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Y Comparison of Organi:ation Titles i for Quality Assurance Functions Quality Function Curren Title (s) New Title

1. a) Program resconsibility Director, Vice President, b) Approval of manuals Quality and Nuclear Quality c) Evaluation of program Administrative Systems effectiveness Services and d) Reporting to management Manager, Grouc Quality Assurance
2. a) Internal audits Group Quality Quality Programs b) Precare QA manuals Systems (GQS) and c) Interpret QA stancards Engineering Qua: 4:y Assurance (EQA) c) Coordinate cus:cmer Contract Quali:3 aucits Assurance (C0A)
3. a) Maintain training records GQS and EQA Training and b) Maintain cuality records GQS and Contrac: Administration Quality Records
) Issue M.0. numbers Coerations Piann'ng and Control
4. a) Vendor aucits/ surveys Grouc Quality Quality Coeratiens o) Accreve crocurement Control (GCC) cocuments c) Conduct source surveillence c) Maintain Accrevec Vendor Lis; e) Imolement trene analysis 4

'The term "current title" refers Oc the title accearing in CENPD-210-A.

Revision 4 r

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o MEV?aION 05 TO CENPD-210 IS BEING PREPARED o THE CHANGES REFLECT:

CONSOLIDATION OF QUALITY ASSURANCE PROGRAMS FOR ALL NUCLEAR POWER SYSTEMS FACILITIES:

NUCLEAR POWER SYSTEMS (WINDSOR, CT. & CHATTANOOGA TENN.)

NUCLEAR PRODUCTS MANUFACTURING (WINDSOR, CT. & ST. IOUIS, MO.)

C-E CONTROLS / ELECTRO-MECHANICS (NEW BRITAIN CT.)

C-E NEWINGTON (NEWINGTON, NH.)

ACKNOWLEDGEMENT OF:

4 NQA-1 i

REGULATORY GUIDE 1.28, REVISION 03 IMPROVED QUALITY ASSURANCE INTERFACES i

CENTR /.LIZED, FOCUSED QA MANAGEMENT l

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SUMMARY

OF CENPD-210 REVISION 05 CHANGES 10CFR50 APPENDIX B CENPD-210-A CENPD-210 CRITERIA REVISION 04 REVISION 05

1. ORGANIZATION o SEVERAL QA o ONE CONSOLIDATED ORGANIZATIONS QA ORGANIZATION o EACH QA ORGAN. o ONE CONSOLIDATED DEFINES METHO. METHODOLOGY FOR ADDRESSING 10CFR50 APP. B II. QA PROGRAM o QA PROGRAM o QA PROGRAM ADOPTS COMPLIES WITH NQA-1 AND REG.

SEVERAL ANSI GUIDE 1.28, REV.

STNDS & REG. REVISION 03 GUIDES i

o NUCLEAR QUALITY SYSTEMS REVIEWS, APPROVES, &

j CONTROLS MANUALS

& PROCEDURES FOR EACH NPS FACILITY l

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DETAILS OF CENPD-210 REVISION 05 CHANGES (CONT'D) 10CFR50 APPENDIX B CENPD-210 CENDP-210 CRITERIA REVISIOS 04 REVISION 05 III. DESIGN o FOCUSES ON NSSS o ADDRESSES QA CONTROL DESIGN ACTIVITIES ASSOCIATED WITH NSSS DESIGN, SERVICES, ORGAN.

& SPARE PARTS PROGRAM o ADDRESSES DESIGN CONTROL OF COMPUTER CODES IV. PROCUREMENT o SEVERAL QA o ONE QA ORGAN.

DOCUMdNT ORGAN. EACH WITH AND ONE PROGRAM CONTROL OWN PRO. FOR FOR PROCUREMENT PROCUREMENT DOCUMENT CONTROL DOCUMENT CONTROL

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V. INSTRUCTIONS, o CONTROLS DESCRIBED o CONSOLIDATED PROCEDURES & IN BODY OF REPORT DESCRIPTION OF DRAWINGS AND ATTACHMENTS CONTROLS APPLIES TO ALL NPS FACILITIES o SUPPLIERS REQ.'S o ALL SUPPLIER DESCRIBED CONTROLS UNDER CRITERIA VII.

VI. THRU XVIII. (SEE CRITERION V) l l

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NRC REVIEW OF CENPD-210 REVISION 05 o C-E CAN PROVIDE A "ROAD MAP" TO SIMPLIFY THE NRC REVIEW AND APPROVAL PROCESS

- COMPARATIVE; IDENTIFY THE IMPORTANT ISSUES FROM PREVIOUSLY APPROVED VERSION AND DEMONSTRATE HOW REVISION 05 MEETS OR EXCEEDS REVISION Of .

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SUMMARY

o THESE PROGRAM CHANGES DO NOT DECREASE OUR COMMITMENT TO QUALITY ,

o WE REQUEST NRC'S CONTINUED CONCURRENCE THAT OUR QA PROGRAM IS ACCEPTABLE s

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