ML20151H652

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Forwards Request for Addl Info Re RESAR SP/90.Resolvability of Issues During Pda Phase of Review Concluded.Meeting Between NRC & Westinghouse to Discuss & Resolve Issues Prior to Issuance of Final SER Proposed
ML20151H652
Person / Time
Site: 05000601
Issue date: 04/14/1988
From: Kenyon T
Office of Nuclear Reactor Regulation
To: Johnson W
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 8804200460
Download: ML20151H652 (7)


Text

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APR 141988 Docket No. 50-601 l

Mr. W. J. Johnson i

Nuclear Safety Department i

Westinghouse Electric Corporation 1

Water Reactor Division Box 355 Pittsburgh, Pennsylvania 15230 j

Dear Mr. Johnson:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 As a result of our ongoing review of the RESAR SP/90 application, we require additional information in order to complete our review of the quality assurance aspects of the design and design verifiestion of the plant.

Enclosed are review questions Q 260.1 - 260.33.

The basis for the review was Part 17.1 of the Standard Review Plan (NUREG-0800, Rev. 2, July 1981). Although Part 17.1 is titled, "Quality Assurance During the Design and Construction Phases," our review was limited to design and design verification, recognizing that some of the design verification could be done by test.

Thus, in addition to the control of engineering design and its related procedures, calculations, and documentation, the review addressed quality assurance activities such as y

procurement control, control of special processes, inspection, test control, nonconformance control, and M&TE control for test articles.

The staff has concluded that these issues should be resolvable during the PDA i

phase of the review. We propose a meeting be set up between the NRC and Westinghouse to discuss these issues in order to resolve them prior to issuance of the final SER.

If you have any questions concerning this matter, l

call me at (301) 492-1120.

9 Sincerely,

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Originni Sigzad av s Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects J

Office of Nuclear Reactor Regulation 1

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Mr. W. J. Johnson

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Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburgh, Pennsylvania 15230

Dear Mr. Johnson:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 l

As a result of our ongoing review of the RESAR SP/90 application, we require additional information in order to complete our review of the quality asw-:r.a aspects of the design and design verification of the plant.

Enclosed are review questions Q 260.1 - 260.33.

j The basis for the review was Part 17.1 of the Standard Review Plan (NUREG-0800, Rev. 2, July 1981). Although Part 17.1 is titled, "Quality Assurance During the Design and Construction Phases," our review was limited to design and design verification, recognizing that some of the design verification eculd be done by test. Thus, in addition to the control of engineering design and its related procedures, calculations, and documentation, the review addressed quality assurance activities such as procurement control, control of special processes, inspection, test control, nonconformance control, and M&TE control for test articles.

The staff has concluded that these issues should be resolvable during the PDA phase of the review. We 3ropose a meeting be set up between the NRC and Westinghouse to discuss t1ese issues in order to resolve them prior to issuance of the final SER.

If you have any questions concerning this matter, call me at (301) 492-1120.

Sincerely, u[

Thomas J.14nyon, Project Manager Standardifation and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated l

REQUEST FOR ADDITIONAL IIFORMATION RESAR SP/90 260.1 Describe measures which ensure that Westinghouse retains and exercises responsibility for the overall quality assurance program for th design and design-related activities for RESAR SP/90.

j (1A1) 260.2 Identify and describe the criteria for determining the size of the organization (s) responsible for design verification and other quality assurance activities of the RESAR SP/90.

(1A5) 260.3 Describe provisions for resolving disputes involving quality which result from a difference of opinion between quality assurance personnel.and personnel from other departments / divisions.

(185) 260.4 Describe measures which ensure that designated quality assurance individuals are involved in day-to-day SP/90 activities important to safety (that is, the quality assurance organization routinely attends and sarticipates in work schedule and status meetings to assure they are (ept abreast of work assignments and that there is adequate quality assurance coverage relative to procedural and inspection controls, acceptance criteria, and quality assurance staffing and qualification of personnel to carry out quality assurance assignments).

(186) 260.5 Describe the scope of the Westinghcuse quality assurance program.

(2A1) 260.6 Provide a commitment in the RESAR SP/90 SAR that Westinghouse will meet the latest NRC-accepted version of WCAP-8370. Also, update the commitnent in Table 17.1 to the latest revision of Regulatory Guide 1.28.

(2B3) 260.7 Identify Westinghouse procedures reflecting that quality assurance regulatory guides, general design criterion 1 of Appendix A to 10 CFR Part 50, 10 CFR Part 50 Subsection 50.55(a), and each criterion of 10 CFR Part 50, Appendix B will be met by documented procedures.

260.8 Provide a summary description of how responsibilities and control of quality-related activities will be transferred from Westinghouse to the licensee during the phasecut of design.

(2C3) 1/

Alpha-numeric indicators refer to acceptance criteria from Section 17.1 of the Standard Review Plan, NUREG-0800, July 1981.

~

2 260.9 In the area of personnel training and qualification, clarify that:

a.

Proficiency tests are given to those personnel performing activities affecting quality, and acceptance criteria are developed to determine if individuals are properly trained and qualified; b.

Certificates of qualification clearly delineate (a) the specific functions personnel are qualified to perform and (b) the criteria used to qualify personnel in each function; c.

Proficiency of personnel performing activities affecting quality is maintained by retraining, reexamining, and/or recertifying.

(20) 260.10 Describe internal and external design interface controls, procedures, and lines of comunication among participating design organizations and across technical disci)1ines to assure that structures, systems, and components are compati)1e geometrically, functionally, and with processes and environment.

(3D)

Describe measures which ensure a documented check to verify (the 260.11 dimensional accuracy and completeness of design drawings.

3E1) 260,12 Describe measures which ensure that design drawings are reviewed by the quality assurance organization to assure that they are prepared, reviewed, and approved in accordance with company procedures and that j

they contain the necessary quality assurance requirements such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results.

(3E2) 260,13 Describe measures which ensure that procedural control is established for design documents that reflect the commitments of the SAR; this control differentiates between documents that receive formal design verification by interdisciplinary or multi-organizational teams and those which can be reviewed by a single individual (a signature and date is acceptable documentation for personnel certification).

Design documents subject to procedural control include, but are not limited to, specifications, calculations, computer programs, system descriptions, SAR when used as a design document, and drawings including flow diagrams, piping and instrument diagrams, control logic diagrams, electrical single line diagrams, structural systems for major facilities, site arrangements, and equipment locations.

Specialized reviews should be used when uniqueness or special design considerations warrant.

(3E4c) 260,14 When design verification is by test, describe measures which ensure that such testing is performed as early as possible prior to installation of plant equipment, or prior to the point when the installation would become irreversible.

(3ES)

3 260.15 The first paragraph of Section 17.1.3 of WCAP 8370/7800 uses the term "quality standards." Clarify if this term includes such things as codes and industrial standards, test and inspection requirements, and special process instructions.

(4A2) 260.16 The second paragraph of Section 17.1.6 of WCAP 8370/7800 indicates that Westinghouse may use master lists to identify the current versions of documents. Clarify how such a list is updated and distributed.

(6B2) 260.17 Clarify whether procedures for supplier verification specify the characteristics or processes to be witnessed, inspected or verified, and accepted; the method of surveillance and the extent of documentation required; and those responsible for implementing these procedures.

(7A2) 260.18 Position 3 on Regulatory Guide 1.123 clarifies controls on Westinghouse procurement of standard hardware and catalog items.

Describe measures which ensure that, for such procurements, special quality verification requirements shall be established and described to provide the necessary assurance of an acceptable item.

(784) 260.19 Describe measures which ensure that the Westinghouse quality assurance organization is involved in the qualification activities of special process procedures, equipment, and personnel to assure they are performed satisfretorily.

(9B1).

260.20 Describe measures which ensure that the acceptability of inspection results is deten,ined by a responsible individual or group.

(1003) 260.21 The second paragraph of Section 7.1.11 of WCAP 8370/7800 lists some test prerequisites. Describe measures which ensure that test prerequisites have been met before doing the test.

(1181) 260.22 Describe quality assurance and other organizations responsibilities i

for the Westinghouse calibration program.

(12.2) 260.23 Describe the review and r.oncurrence of calibration procedures and identify the organization responsible for these activities.

(12.3) 260.24 Clarify whether measuring and test equipment is labeled or tagged to indicate due date of the next calibration.

If not, describe the method of control.

(12.5) 260.25 Identify the Westinghouse management (by position title, for example) authorized to:

a.

allow calibration with less than four-to-one accuracy ratios.

l (12.6) i b.

allow calibrating standards to have the same accuracy as i

standards being calibrated.

(12.7) 1

4 260.26 Describe measures which ensure that procedures for altering the j

sequence of required tests, inspections, and other operations require the same controls as the original review and approval.

(14.3) i Identify the organization (s) responsible for documenting (and 260.27 preventing the inadvertent use of nonconforming items.

14.4) 260.28 Describe quality assurance and othat organizational responsibilities for the definition and inplementation of activities related to nonconformance control.

This includes identifying those individuals l

or gr ups with authority for the disposition of nonconforming items.

(15.2 260.29 Describe quality assurance and other organizational responsibilities for the definition and implementation of activities related to quality assurance records,.

(17.2) 260.30 Describe measures which ensure that audit data are analyzed by the quality assurance organization and the resulting reports indicating i

any quality problems and the effectiveness of the quality assurance program, including the need for reaudit of deficient areas, are reported to management for review and as:;2ssment.

(18B1) 260.31 WCAP 8370/7800 should be revised to reflect the current Westinghouse organization and related quality / quality assurance responsibilities (see Wes';inghouse letter NS-NRC-87-3220, PA-87-519, dated April 29, 1987 for latest information received by the NRC).

260.32 The second paragraoh of SAR Section 17.1 refers to a WAPWR Integrated PDA submittal. We understand there has not been and will not be an integrated PDA for RESAR SP/90; therefore this paragraph should be revised or deleted from the SAR.

260.33 SAR Table 3.2-1, "Classification of structures, Systems, and Components for the Reactor System," has a column headed "Quality Assurance." This column shows either "WQCS-1" or "WQCS-2" for the systems / components in the table, and it references a footnote which states:

"WQCS 1 and WQCS-2 satisfy the requirements of 10 CFR 50 Appendix B7" Clarification is needed since neither SAR Section 17 nor WCAP-8370 address the WQCS documents.

i i

TABLE 17.1-1 Regulatory Guidance Applicable to Quality Assurance Program 1.

Regulatory Guide 1.26, "Quality Group Classifications, and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants" (2/76).

2.

Regulatory Guide 1.28, "Quality Assurance Program Requirements (Design and 1

Construction)" (8/85).

3.

Regulatory Guide 1.29, "Seismic Design Classification" (9/78).

4.

Regulatory Guide 1.30, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment" (8/11/72).

5.

Rt.gulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid ',ystems and Associated Components of Water-Cooled Nuclear Power Plants" (3/16/73).

6.

Regulatory Guide 1.38 - Revision 2, "Quality Assurance Requirements for Packaging Shipping, Receiving, Storage, and Handling of Items for i

Water-Cooled Nuclear Power Plants" (5/77).

7.

Regulatory Guide 1.39 - Revision 2 "Housekeeping Requirements for Water-Cooled Nuclear Power Plants" (9/77).

8.

Regulatory Guide 1.58 - Revision 1, "Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel" (9/80).

9.

Regulatory Guide 1.64 - Revision 2 "Quality Assuranco Requirements for the Design of Nuclear Power flants" (6/76).

10. Regulatory Guide 1.74, "Quality Assurance Terms and Definitions" (2/74)
11. Regulatory Guide 1.88 - Revision 2. "Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records" (10/76).
12. Regulatory Guide 1.123 - Revision 1. "Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants" j

(7/77).

13. Reg 11atory Guide 1.144. Revision 1, "Auditing of Quality Assurance Programs for Nuclear Power Plants" (8/80).
14. Regulatory Guide 1.146, "Qualification of Quality Assurance Program Audit i

Personnel for Nuclear Power Plants" (8/80).

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