ML20215F549
| ML20215F549 | |
| Person / Time | |
|---|---|
| Issue date: | 06/16/1987 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-675A NUDOCS 8706220437 | |
| Download: ML20215F549 (19) | |
Text
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June 16, 1987 Project No. 675 MEMORANDUM FOR:
The Record FROM:
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
SUBJECT:
SUMMARY
OF MEETING WITH COMBUSTION ENGINEERING CONCERNING THE SCOPE OF PROPOSED PRA PROGRAM FOR THE ADVANCED CESSAR DESIGN j
INTRODUCTION l
A meeting of the staff with representatives of Combustion Engineering (CE) was held at the request of CE at the NRC offices in Bethesda on June 2, 1987. The purpose of the meeting was to hear and discuss the plans of CE for developing a PRA for the Advanced CESSAR Design. Enclosure 1 provides the list of the attendees of the meeting.
DISCUSSION CE's main objective was to initiate a dialog with the staff on the CE approach q
to a PRA for the Advanced CESSAR design.
The initial discussion centered around the Advanced CESSAR design certification program.
CE intends to implement the EPRI Requirements Document, which establishes the top-level i
i criteria.
In general, the CE submittals will follow the Standard Review Plan (SRP). However, the EPRI document will be followed where the EPRI Document establishes criteria in areas which are not covered by the SRP, such as Unresolved Safety Issues and Generic Issues.
CE submittals will be in groupings and will follow and be coordinated with the complementary EPRI submittals. The Advanced CESSAR is viewed by CE as a revision of the current CESSAR 80 design and submittals of the SAR chapters will be the same as the current CESSAR 80 design SAR except in areas w1ere there are revisions. The Advanced CESSAR SAR will clearly note the areas of revisions from the current CESSAR 80 SAR. Most revisions will be in those areas which reflect the EPRI Requirements Document.
The CE submittal schedule is as indicated in the CE presentation material.
The guidelines document (formerly " licensing basis agreement") is scheduled for submittal in late June 1987. The first SAR chapters are not expected until the end of August. The major submittals are scheduled for the end of September 1987.
CE anticipates that the scope of the Advanced CESSAR design will include the containment, the control room, cooling water systems and the Emergency
[c'()
4y&
Feedwater System. CE and DOE are currently discussing these additions to the M
scope of the design.
8706220437 870616
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s 2-The development of the PRA includes a baseline PRA early in the design program. The baseline PRA will serve as a design verification tool.- It will establish the reliability requirements of the interface requirements.of the balance of plant (B0P).. The interface requirements will be both reliability and deterministic requirements.
The staff indicated that the most important interface requirements are the operating characteristics of the plant including the operating procedures, the Technical Specifications and the training of the operators.
i The baseline PRA will be submitted to the staff for information. The Advanced CESSAR will address the sabotage issue on a deterministic basis.
The NRC/RES Probabilistic Risk Assessment Branch will have the lead review-I effort for the Advanced CESSAR PRA. The NRR Risk Application Branch-will provide coordination of the PRA review.
Prior'to completion of the baseline PRA, CE wants to meet with the staff to-discuss their approach. This meeting is tentatively scheduled for August 1987. When the baseline PRA is completed, CE will meet with the staff to discuss the results. CE expressed a desire to have frequent meetings with the staff during the development of the PRA to keep the staff informed on the progress of the program.
i bTgInni Signed By:
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV j
V and Special Projects i
Enclosures:
As stated
]
DISTRIBUTION xDocket File, E. Hylton PDNSP Reading NRC 'PDR==:
H. Berkow OGC-Bethesda G. Vissing NRC Participants A. E. Scherer-CE
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-7 The development of the PRA includes a baseline PRA early in the design'
)
program. The baseline PRA will serve as a design verification tool.
It will establish the reliability requirements of the interface requirements of the balance of plant (B0P).
The interface requirements will be both reliability and deterministic requirements.
The staff indicated that the most important interface requirements are the operating characteristics of the plant including the operating procedures, the Technical Specifications and the training of the operators.
The baseline PRA will be submitted to the staff for information. The Advanced CESSAR will address the sabotage issue on a deterministic basis.-
The NRC/RES Probabilistic Risk Assessment Branch will have the lead review effort for the Advanced CESSAR PRA..The NRR Risk Application Branch'will
-l provide coordination of the PRA review.
Prior to completion of the baseline PRA, CE wants to meet with.the staff to discuss their approach. This meeting is tentatively. scheduled for August 1987. When the baseline PRA is completed, CE will meet with the staff to discuss the results.
CE expressed a desire to have frequent meetings with the staff during the development of the PRA to keep the staff informed on the progress of the program.
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV V and Special Projects-
Enclosures:
As stated
-_ 7 _
M' o,
Attendance List for Meeting With Combustion Engineering Concerning PRA Sco3ing for Advanced C ESSAR - 80 June 2, 1987 I
Names Organization Frank Rose DOE Dan Gessing DOE Rick Summitt IT Corporation 1
Mark Beaumont Westinghouse, Bethseda 1
Charles Brinkman Combustion Engineering Steve Long NRC/NRR/DRPEP j
Dean Houston NRC/ACRS Harold.Vandermolen NRC/RES/PRAB Richard Barrett NRC/NRR/RAB Brad Hardin NRC/RES/PRAB Kaz Campe NRR/RAB E. Che111ah.
NRC/0NRR I
Guy Vissing NRC/NRR/PDSPN i
George A. Davis
-C-E Bob Jaquith C-E Regis Matzie C-E Herb Berkow NRC/NRR/PDSNP i
4 i
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AGENDA 9:30 INTRODUCTION PURPOSE OF MEETING 9:40 REVIEW 0F DESIGN VERIFICATION G.
A.
DAVIS PROGRAM OBJECTIVES 10:00 USE OF PRA IN DESIGN VERIFICA-BOB JAQUITH TION PROGRAM BASE CASE S-80 MODEL RELIABILITY ASSURANCE PROGRAM BOP CONSIDERATIONS FINAL PRA AND DOCUMENTATION I
11:30 DISCUSSION AND FUTURE MEETING PLANS w seassusTION)ENGINEEMNG
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