NRC-94-4225, Forwards Info to Support Draft SER for AP600
| ML20072D023 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 08/05/1994 |
| From: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NTD-NRC-94-4225, NUDOCS 9408180192 | |
| Download: ML20072D023 (4) | |
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Westinghouse Energy Systems Box 355 Pittsburgh Pennsylvania 15230-0355 Electric Corporation NTD-NRC-94-4225 DCP/NRC0179 Docket No.:STN-52-003 August 5, 1994 Document Control Desk Nuclear Regulatory Commission Washington DC 20555 ATTN:
Mr. Dennis M.
Crutchfield
SUBJECT:
DRAFT SAFETY EVALUATION REPORT FOR THE AP600 REFERENCE 1)
Letter, Taylor to the Commission, July 14, 1994 2)
Letter, Crutchfield to Liparulo, July 22, 1994 In reference 1, the staff provided the Commission with an expedited review schedule for the AP600 that would result in the final design approval being issued in September, 1996.
This schedule included issuing a draft safety evaluation report (DSER) in November, 1994.
Reference 2 expressed a concern that information not submitted by June 30, 1994 might not be considered in the DSER and would be designated as open issues for later resolution.
Issuance of the AP600 DSER in November, 1994 is an important milestone in the AP600 design certification review process.
Westinghouse has made significant achievements in the areas of testing programs, submitting information to the NRC for their review and responding to staff questions and comments.
The Information Westinghouse has provided to the staff allows a l
meaningful DSER to be prepared.
The attachment presents the status of the outstanding design material mentioned in reference 2.
In addition, the attachment presents additional material that has been provided to the staff since May to assist the review of the AP600.
As mentioned in reference 2, revision 2 of the AP600 SSAR was delayed to allow Westinghouse to complete RAI responses.
To
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assist the staff in their review of the RAI responses, the RAI responses provided have included in-context SSAR text updates where appropriate.
To further assist the staff in preparation of the DSER, a table will be provided that cross references the SSAR sm
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NTD-NRC-94-4225 DCP/NRC0179 ' August 5, 1994 sections to the RAI's.
This table will be provided by August 12, 1994.
The AP600 DSER will allow both the staff and Westinghouse to focus their efforts on an identified specific set of open items.
The significant progress made in the review and the information provided to the staff makes the AP600 DSER in November an achievable objective.
Please contact Brian A. McIntyre if you have any questions concerning the P600 design certification review.
hYrY N. J.
Liparulo, Manager Nuclear Safety Regulatory And Licensing Activities
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9 Attachment to NTD-NRC-94-4255 DCP/NRC0179 AP600 INFORMATION SUBMITTED TO SUPPORT DSER PREPARATION REQUESTS FOR ADDITIONAL INFORMATION A total of 1995 requests for additional information have been received from the staff.
Westinghouse has provided over 1860 responses to these RAIs.
HUMAN FACTORS Two WCAP reports requested by the Human Factors Branch reviewers have been completed and submitted to the NRC.
These two reports cover the incorporation of operating experience in the AP600 design.
RELIABILITY ASSURANCE PROGRAM The reliability assurance program example submittal is currently i
in technical review.
Following a management review, the report will be submitted by September 9, 1994. This item is not critical for the DSER since it serves to illustrate execution of the DRAP process.
PROBABILISTIC RISK ASSESSMENT The revision to the AP600 probabilistic risk assessment report has been submitted to the NRC.
This revision included the addition of decomposition event trees, incorporation of responses to RAIs, containment event trees, conditional containment failure probability distributions and requantification of the level 2 and level 3 PRA.
In addition, the seismic margins assessment requested by the staff was added.
Many of the items in this submittal were previously discussed with the staff.
The report was therefore documentation that Westinghouse had completed the activities.
OTHER DSER SUPPORTING INFORMATION PROVIDED IN JUNE AND JULY Thirty test and analysis reports were provided to the NRC for their information. This included 20 quick look data reports covering the tests performed at the Oregon State University, SPES-2, CMT and critical heat flux test facilities.
Facility description reports were submitted on the Oregon State University test facility, SPES-2 test facility, and the CMT test facility.
1 Final data reports were submitted for the PCCS test and the wind tunnel phase IVB test. Reports were submitted on the PCCS preliminary scaling analysis, PCCS shell water coverage and the sensitivity of small break LOCA results to containment pressure.
Meetings were held with the staff to review responses to RAIs and audit work performed in the areas of piping design (4 days), soil structure interactions (7 days), reactor internals design (2 days) and containment design (3 days).
Meetings were also held on the AP600 approach to technical specifications, passive system reliability, PRA and the passive containment cooling test and analysis program.
TESTING STATUS (8/5/94)
OSU All matrix testing completed NRC staff witnessed 9 tests 6 months ahead of schedule SPES-2 8 of 11 matrix tests completed NRC staff or ANPA has witnessed 8 tests j
1 month ahead of schedule PCCS All matrix testing completed NRC witnessed 2 tests CMT 19 of 40 matrix tests completed NRC staff has witnessed 1 test Testing matrix revised in response to NRC comments 1 month behind schedule CMT testing is not critical path item ADS 6 of 25 matrix tests completed On schedule I