ML20246A663
| ML20246A663 | |
| Person / Time | |
|---|---|
| Issue date: | 02/23/1989 |
| From: | Hooks K, Spraul J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), Office of Nuclear Reactor Regulation |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20245F414 | List: |
| References | |
| NUDOCS 8905080302 | |
| Download: ML20246A663 (5) | |
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MEMORAHDUli FOR: John A. Zwo11nski, Deputy Director Division of Licensee Performance and Quality Evaluation J
Office of Nuclear Reactor Regulation FROM:
K. R. Hooks, Senior Quality Assurance Engineer QA Section, HLPD Divisicn d High Level Waste Management Office of 6xlear Material Safety-and Safeguards J. G. Spraul, Quality Operations Engineer QA Section, PQEB-1 Division of Licensee Performance i
I and Quality Evaluation Office of Nuclear Reactor Regulation j
SUBJECT:
During the week of February 6,1989, the writers, accompanied by Dino Scaletti i
I (the ABWR Project Manager) and Shogo Hara of MITI (Japan) ) audited the quality program applied to the General Electric (GE Advanced Boiling assurance (QA)(ABWR)designprocess.
Water Reactor This audit, at GE's San Jose,' California, offices, was preceded by fact-finding visits to these offices during the weeks of February 03 and June 6,.1988.
I During this audit we completed our review of the QA program applied to the design of the ABWR and reached conclusions concerning the effectiveness and acceptability of the design QA program. We did not make any judgment concern-ing i. adequacy of the ABWR design as this is being done by other NRR techniul reviewers during their review of the ABWR Standard Safety Analysis l
Report. Based on the sample of design activities audited as' discussed below, I
we found that the design QA programs implemented by GE, Hitachi, and Toshiba meet the applicable requirements of Appendix B to 10 CFR 50 and are acceptable for designing the ABWR.
The principal GE personnel with whom we met were:
Jack Fox, ABWR Certification Program Manager l
Phil Novak, ABWR QA flanager Darrel Stickler, Senior Engineer Mr. Stickler is GE's responsible engineer for the standby gas treatment system and the spent fuel pool cooling and cleanup system for the ABWR.
An exit meeting was held February 9,1989 at which we presented our conclusions regarding the ABWR design QA arogram. This meeting was attended by i
Mr. Scaletti, Mr. Hara, and tie'following'GE personael-C
j 4
l John A. Zwolinski Jack Fox, ABWR Certification Program Manager
]
Steve Hucik, ABWR Project Manager i
Joe Quirk, Domestic ABWR Program Manager Phil Smith, ABWR Project Support Manager Dan Wilkins, ABWR General Manager The major activities that we needed to do prior to reaching our conclusions regarding the ABWR design QA program were given in our memorandum to you dated l
' January 19, 1989. The activities and the results of our audit in each of the areas are:
j 1.
Activity. Determine the extent to which GE has independently verified that the' Japanese-designed portions of the ABWR were controlled by a l
quality system equivalent to that required by the NRC. We were looking for evidence that GE verified implementation and effectiveness of the Japanese quality system rather than simply auditing the Japanese program procedures.
l Audit Results. Phil Novak (GE) and Y. Kezuka'(GETSCO) reviewed implemen-tation of the QA programs at Toshiba on August 28-29, 1988 and at Hitachi.
on September 1-2, 1988. We reviewed the plans for these reviews and the 1
resulting reports. The plans were based on Toshiba' and Hitachi's QA-Program descriptions, were detailed, and emphasized design control.
I l
The reports were discussed in detail with Mr. Novak.
We also reviewed reports of Hitachi and Toshiba reviews of the GE QA program, conducted July 5-7, 1988 and September 12-14, 1988, respectively.
Hitachi had no findings; Toshiba had one finding related-to lack of l
objective evidence of independent design review.
Overall, the NRC auditors were satisfied that GE had verified the 1
l effectiveness of Hitachi and Toshiba design QA programs. We believe that I
l the next GE review should be more in depth, including discussion with the designers of how the design controls were implemented, and GE agreed to consider this request.
We also noted that the Japanese QA programs do not require an independent third party design verification: t'ut. allow design verification by the designer's supervisor as a routine matter.
2.
Activity. Audit design files for one or more ABWR systems designed by.
the Japanese to independently verify the implementation and effectiveness of the Japanese design QA program.
Audit Results. We reviewed the ilitachi design record file for the standby gas treatment system and the Toshiba design record file for the spent fuel pool cooling and cleanup system. These files.had been sent to GE for review by the NRC. The majority of the documents in these. files had been
I John A. Zwolinski <
translated into English. Mr. Hara translated other portions of the. files as required.
The contents of the design record files were generally consistent with the requirements of the Hitachi and Toshiba QA Programs and the results of GE's review.
3.
Activity. Audit the design control process which GE is using while revising portions of the ABWR designed by the Japanese to make the design i
compatible with US requirements.
4 Audit Results. GE has, to date, not been required to make specific changes to the design for the Japanese ABWR' ( A-6/7) to meet US licensing requirements or codes and standards.
In general, the design has been adjusted through the three-party ' review process (between GE, Hitachi and Toshiba) to envelope US requirements. GE is keeping a Design Action List (DAL) of items which may require further consideration when a specific plant is presented for licensing in the US.. A copy of the it' ' and updated by GE to 2/8/88, is enclosed.
We reviewed backup documents for the DAL which indicate that GE is tracking the items that may require changes. We suggested to GE that i
they include auditing this process in a future internal audit of their design activities. GE agreed to consider this suggestion.
To reiterate, based on the sample of the design activities audited, we found j
that the design QA programs implemented by GE, Hitachi, and Toshiba meet the applicable requirements of Appendix B to 10 CFR 50 and are acceptable for designing the ABWR.
W K. R. Hooks, Senior Quality Assurance Engineer QA Section, HLPD Division of High Level Waste: Management Office.of Nuclear Material Safety and Safeguards I
J. G. Spraul, Quality Operations Engineer' QA Section, PQEB Division of Licensee Performance and Quality Evaluation-Office of Nuclear Reactor Regulation-
Enclosure:
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Design Action List (DAL) Activity /St2tus as of 11/22 DISPOSITION PAL #
SUBJECT Disapproved 1501 Post Accident Monitoring 1502 Delegation of Switchgear Common to Two Appv'd Section I.
Unit J. ABWR Cancelled 1503 Split BUS Power Distribution 1504 Remote Shutdown System Redundancy Disapproved 1505 Automatad Rod Block Monitor Protection Disapproved 1506 Electrical Separation, R.C. 1.75 and Disapproved IEEE Std. 384 1507 Control Room Air Intake System Disapproved 1508 Codes and Standards RPV & Internals Appy'd Section I s
Implementation Deferred Disapproved 1509 Triple-sleeve Feedwater Sparger Disapproved 1510 Type of MNS Tip Detector 1511 Reactor Shield Wall Stabilizers Disapproved 1512 U.S. ABJR Codes & Standards Pending
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Appv'd Section I 1513 U.S. ABWR Product Structure Appy'd Section I 1514 Single Unit ABWR f
Pending 1515 0.3g SSE all Soil Envelope 1516 Sixty Year Plant Life Appy'd Section I Implementation Deferred I
1517 U.S. ABWR Turbine Orientation Appv'd Section I L
1518 60 Hertz Electrical Design Appv'd Section I Implementation Deferred 1519 Automated Rod Block Monitor, Rod Pending Block Functions I
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Design Action List (DAL) Activity / Status as of 11/22/88 DISPOS 57 ION DAL #
SUBJECT 1520 Steam & Power Conversion System Appy'd Section I Appv'd Section I 1521 ABWR Plot Plan 1522 ABWR Control Building Appv'd Section I Pending 1523 FMCRD Leak Detection 1524 Recire System Reactor Internal Appy'd Section I Pump Operation Coahg Co d S Pew diw c) 152.F MECW C.ow d A.w s gle Po b shs w)
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