ML20045D097
| ML20045D097 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 11/20/1992 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2855, NUDOCS 9306250322 | |
| Download: ML20045D097 (8) | |
Text
.
CERTIFIED BY:
DATE ISSUED:
11/18/92
,Carlyle Michelson 11/20/92 g
SUMMARY
/ MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE ADVANCED BOILING WATER REACTORS (GE)
OCTOBER 21, 1992 BETHESDA, MARYLAND PURPOSE The purpose of this meeting was to begin the review of the draft final safety evaluation report (DFSER) for the GE/ABWR design. The meeting began at 8:30 a.m.,
adjourned at 5:00 p.m.
and was held entirely in open session. No written comments or requests for time to make oral statements were received from members of the public.
The principal attendees were as follows:
ATTENDEES:
ACRS HEC C. Michelson, Chairman R. Nease, NRR J.
Carroll, Member J. Wilson, NRR I.
Catton, Member C.
Poslusny, NRR P. Davis, imminent Member D. Terao, NRR R.
Costner, Consultant G. Georgiev, NRR M.
El-Zeftawy, Cognizant Staff Engineer H. Richings, NRR M. Hum, NRR G_.E H. Pastis, NRR M. Rubin, NRR J.
Fox J.
Sharkey, NRR J.
Chambers B. Mendelsohn, NRR S.
Boynton, NRR Others J.
Lee, NRR W.
Burton, NRR Y. Kim, NUS A. Mendiola, NRR V.
San Angel, Bechtel J. Lyons J.
Raval, NRR F. Young, RGI CHAIRMAN'S OPENING REMARKS In his opening remarks, Mr. Michelson stated that the purpose of this meeting is to examine the resolution of open items and to discuss with the NRC staff and GE representatives the approach been taken to close these open items.
Items that are still open need to be discussed.
Mr. Michelson solicited any feedback from the subcommittee members and reminded them that the inspections, tests, analyses, and acceptance criteria (ITAAC) associated with certain chapters will not be part of the discussion for this meeting.
This is due to the incompleteness of the ITAAC and,was based on the staff's request to postpone such discussion at a later meeting.
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Summary / Minutes ABWR October 21, 1992
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1 NRC Staff Presentation Mr.
C.
Poslusny, NRR, stated that the staff is reviewing GE's application for design certification in accordance with the applicable regulatory standards of NUREG-0800, " Standard Review Plan" (SRP),
and in accordance with Regulatory Guide 1.70,
" Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)."
The staff is also using the guidance from the staff requirements memoranda (SRM) for each of the Commission's policy papers listed in Chapter 1 of the DFSER.
In these Commission papers, the staff addressed the policy issues that, for evolutionary light water reactors, modify SRP review criteria or address issues, such as severe accidents, that are beyond the scope of the SRP.
In each section of the DFSER in which the staff found the ABWR to be acceptable, according to the review criteria and guidance, the staff indicates that, except as stated otherwise, GE has submitted a sufficient amounc of design detail for the NRC to make its safety finding.
In areas such as radiation protection and airborne concentrations, digital computer instrumentation and control systems, detailed piping design, and control room human factors.
engineering, the staff has made its finding by reviewing the design acceptance criteria (DAC) for acceptance, as described.in SECY 196, " Development of Design Acceptance Criteria for the Advanced Boiling Water Reactor ( ABWR), " and SECY-92-299, " Development of Design Acceptance criteria for the Advanced Boiling Water Reactor (ABWR) in the Areas of Instrumentation and Controls -(I&C) and Control Room Design."
The staff concludes that the DFSER contains no new policy issues.
The staff will issue the DFSER to GE to inform it of the staff's current findings, including outstanding technical issues that should be resolved.
In the FSER for the.ABWR, the staff will indicate the resolutions of issues included in the DFSER.
Desian Control Document Mr.
J.
Wilson, NRR, described the form and content of the design control document (DCD) in the design certification rule. He stated that the DCD is a two-tiered document (Tier 1 and Tier 2).
Tier 1 consisting of scope, design descriptions, ITAAC, site parameters, and interface requirements, and Tier 2 consisting of supporting information.
For Tier,1, the applicant for design certification will extract the information from its application, the SSAR and submit it to NRR for review.
The staff will provide an evaluation of the proposed DCD in a final safety evaluation report (FSER), and the applicant would then prepare a revised DCD.
This later version of the DCD will be 1
I Summary / Minutes ABWR October 21, 1992 referred to as the Master DCD in the proposed standard design certification rulemaking.
The Master DCD, without the proprietary information or secondary references, will be referenced in the rule that is published in the Federal Register.
The legal details for withholding the proprietary portions are still under development by the staff.
After the rulemaking hearings, the Commission will direct the staff to make any required changes to the Master DCD for publication in the final standard design certification-rule.
Mr. Wilson discussed the change process for Tier 1 and Tier 2 information.
For Tier 1,
the changes are limited to rulemaking, plant-specific order, or exemptions as given in various sections of 10 CFR 52.63.
These changes must be necessary either to bring the certification into compliance with the Commission's regulations applicable at the time tla certification was issued, or to assure adequate protection of the public health and safety.
For Tier 2, a lower threshold for change is proposed in order to accommodate changes in technology, to incorporate lessons learned from construction and operating experience, and to accommodate necessary changes to a facility or application for a facility. These changes are to be governed by the backfit standard of 10 CFR 50.109.
- Also, the staff proposes a change process for Tier 2 based on 10 CFR 50.59 for processing of changes for plants currently in operation.
Mr.
Wilson pointed out that the staff proposal differed with Commission guidance in two aspects.
One difference was in. regard to the change standard for Tier 2 information.
The Commission indicated that this standard should be based on adequate protection while the staff proposed that the standard be based on substantial increase in protection.
The other difference was in regard to when the 10 CFR 50.59 process could be used.
The Commission indicated that this process could only take effect after the issuance of a combined operating license (COL) while the staff proposes that the process can be used either before or after the COL.
Mrs. R. Nease, NRR, stated that the DFSER has approximately 80 new open items in addition to the original 300 open items in the DSER.
The new open items are related to ITAAC, completed review, and updating the SSAR.
There are approximately 100 open items.that were resolved from the DSER.
Mr. Michelson agreed to the staff's request of just answering questions, without specific presentation, regarding the open items associated with the subject chapters of the meeting.
Chapter 4 - Reactor Mr. Carroll stated that the ABWR design (as initially designed) did not include a loose-parts monitoring system (LPMS).
However, in response to the staff's position that an LPMS is required, GE has provided an LPMS general description.
Mr. Carroll asked the staff
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i Summary / Minutes ABWR October 21, 1992 j
to provide discussion of LPMS requirements and the basis for such requirements at the November '92 subcommittee meeting.
Mr. Carroll requested from GE representatives to clarify operation with less than 10 reactor internal pumps (RIP).
In addition, the staff requested GE to provide existing flow test results for operation with fewer than 10 RIPS.
The staff has not received such information.
Mr. Carroll asked the staff and GE to provide information on the potential for electrical faults in RIP motors, and what clears faults and how long it takes to clear such faults for pumps with M/G sets and without M/G sets.
Chapter 5 - Reactor Coolant System and Connected Systems Mr. Poslusny, NRR, stated that the staff reviewed the measures.used to provide and maintain the integrity of the reactor coolant pressure boundary (RCPB) and other pressure-retaining components and their supports that are important to safety for the plant design lifetime.
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According to 10 CFR 50.55a components important to safety are subject to the following:
e RCPB components must meet the requirements for Class 1 (Quality Group A) components in American Society of Mechanical Engineer (ASME) Code,Section III, except for those components that meet the exclusion requirements.of 10 CFR 50.55a(c) (2).
- Components classified as Quality Groups B and C must' meet the requirements for Class 2 and 3 components, respectively, in ASME Code,Section III.
s Mr. Michelson asked the staff to clarify the discussion in the DFSER section 5.2, regarding the overpressure protection and also to. add discussion of RCIC.
Mr. Michelson expressed concern regarding the statement made.by the staff regarding the intersystem leakage to be " highly unlikely" because it would have to occur through closed check valves and/or
. closed containment isolation valves.
OPEN ITEMS Per the staff's reque'st and agreement with the subcommittee members, no presentation was requested regarding Chapter 10, " Steam and Power Conversion System," Chapter 11,
" Radioactive Waste Management,"
Chapter 12,
" Radiation Protection,"
Chapter 13,
" Conduct of Operations," Chapter 15,
" Transient and Accident b
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1 Summary / Minutes ABWR October 21, 1992 Analysis " and Chapter 17, " Quality Assurance." However, review of the resolution of selective open items regarding these chapters was discussed.
Mr. Poslusny stated that GE has submitted ITAAC for the RCIC system.
The staff will review the GE submittal and provide an-evaluation in the FSER.
FOLLOW-UP ITEMS As a result of the subcommittee discussion, the following items were discussed, with the staff and GE representatives agreeing to provide the necessary information at a later ABWR subcommittee meeting:
1.
Loose Parts Monitoring Clear up historical discussion in DFSER Section 4.4, page 4-9.
(staff)
Clarify operation with <10 reactor internal pumps operable, page 4-9.
(GE)
Revise FSER writeup. (staff)
Provide discussion of LPMS requirements at November meeting.
(staff) 2.
Electrical Faults in RIP's Provide information on the potential for faulting in RIP motors, what clears faults, and how long it takes for pumps with M/G sets and w/o MG sets.
(staff, GE) 3.
Add reference to Chapter 14 in Chapter 5 discussion of Code editions, page 5-3.
(staff) 4.
Over pressure protection - Clarify operation of system in discussion on page 5-6 DFSER Section 5.2, and add discussion of RCIC. (staff) 5.
RCP Boundary Leakage Detection, DFSER page 5-19 Delete sentence on intersystem leakage. (staff) 6.
RCIC - Clarification of COL Action Item 5.4.6 RCIC valve closure verification ITAAC vs COL Action Item. (staff) 7.
RCPB Materials - Clarify why materials selection is not Tier I.
(staff, GE)
t y
4 Summary / Minutes ABWR October 21, 1992 8.
Revise DFSER as requested ' to address SSAR Sections 5.4.3, 5.4.4, 5.4.5, 5.4.9, 5.4.12, 5.4.13, 5.4.14 (staff) 9.
Discuss basis for post LOCA valve operability and leakage for feedwater, RWCU, RCIC steam. (GE) 10.
Discussion of uninterruptable power source for protected-lighting area. (GE) 12.
Decrease in core coolant temperature, DFSER Section 15.1, page 15-4.
Remove redundant sentence. (staff) 13.
Clarification of credit for nonsafety equipment, DFSER Section Address basis for conclusion and include 15.1 page 15-7 extent of redundancy in power and water supplies.
Include table in the SSAR. (staff) i Describe basis for and better define 14.
Trip of all RIPS "special case" on page 15-9 of the DFSER.
(staff) 15.
Verify that CRAC weather input error identified in Chapter 19 was not used in Chapter 154 analysis. (staff) 16.
DFSER Section 15.4.3, MSL - On page 15-12 of the DFSER, include cross reference to Chapter 3 discussion of environment effects.
Provide discussion about steamline break being limiting accident for offsite doses. (staff, GE) 17.
DFSER Section 15.4.4.1, Containment Leakage Contribution -
Discuss why sizing of SATS is adequate to address. potential ex-leakage with extremely low outside pressure.
Add discussion to page 15-15 of the DFSER. (staff) 18.
Discuss contribution to offsite release from gland seal system leakage via steam packing exhauster. (GE, staff)
Discuss post LOCA radiological 19.
DFSER Section 15.4.4.3 analysis to address the assumption of 25 gpm identified leakage versus 1 gpm. (staff) 20.
Discuss why the design does not include continuous drywell to wetwell leakage monitoring system. (GE) 21.
Discuss details of heavy object drop accident and control rod damage in accident scenario. (staff) 22.
Reconsider writeup u DFSER Section 10.2.2, page 10-4,.to better describe staff position regarding SRP.
Revise writeup for COL Action Item 10.2.2-1 on turbine orientation. (staff) i
O 8
Summary / Minutes ABWR October 21, 1992 23.
Verify 2 second closure time for MSL MOV gate shutoff valves, page 10-6.
(GE) 24.
DFSER, page 10-9, Section 10. 4.1 - Discussion of circulating water system and power heat sink as an interface.
SSAR and SAR revisions required. (GE, staff) 25.
DFSER Sections 10.4.2 and 10.4.5, Main Condenser Evacuation Provide cross reference to turbine building System compartment exhaust system page 10-10, and defined medium efficiency filter.
Clarify Statement about intercondenser.
(staff) 26.
Turbine Gland Scaling System, DFSER Section 10.4.3 - Better define " fairly clean" steam on DFSER pages 10-11 and 10-13.
(staff)
Identify industry 27.
DFSER section 10.4.4, Turbine Bypass standards on page 10-13. (staff)
Discuss staff evaluation of GE 28.
DFSER Section 10.4.5, CWS calculators of complete rupture of single expansion of joint on CWS and provide additional discussion in DFSER. (staff) 29.
SSAR Section 10.4.5 - Discuss flooding protection for at-grade loads.
(GE) 30.
Discuss whether strainers in RW, CWS and condensate cleanup system are designed to full shut off head of pumps.
(GE) 31.
SSAR Section 10.4.7, Condensate and Feedwater - Discuss ABWR resolution the generic issue related to Reactor Vessel Overfill Protection. (GE) 32.
DFSER Section 11.2.1, Liquid Waste Management System - Reword passage on page 11-2 concerning demineralizers and resin cleaning. (staff) 33.
DFSER Table 11.1, page 11-3, Discuss meaning of steam / water concentration, reactor vessel data.
Are these partition valves? (staff) 34.
Section 12.2.2 of the DCM - Clarify use of the word 'DAC' and include cross references to ger.eric ITAAC.
Include in FSER pertinent references to GE's specific ITAAC documents (GE, staff) 35.
DFSER Chapter 17 - Section 17.1 needs to address role of COL applicant during design and construction. Need to reflect how a
QA program comparable to GE's and which meets NRC requirements will be implemented. (staff)
Y Summary / Minutes ABWR October 21, 1992 36.
Add RG titles to DFSER Table 17.1 (staff) 37.
Provide the data of the audit of GE's QA program in text in DFSER and provide details of review of GE's audit of Japanese QA programs.
Add appropriate information in conclusion in i
DFSER 17.1 (staff) 38.
Discuss means to prevent interconnections between floor drains systems.
39.
Discuss the need for vent and fill system design features.
(GE, staff) 40.
Provide to ACRS a set of submittals concerning PRA which will support FSER development by staff. (GE)
FUTURE ACTIONS The ABWR subcommittee will meet on November 19 and 20, 1992 to continue its review and discussion of the DFSER.
Pending the results of such discussion the Subcommittee Chairman may recommend certain ecurse of action to the full Committee.
BACKGROUND MATERIAL PROVIDED TO THE SUBCOMMITTEE FOR THIS MEETING 1.
DFSER - dated October 5, 1992 (Predecisional) 2.
Note from C.
Michelson to Igne -
" Items to include in future SSAR revision" - dated August 28, 1992 NOTE:
Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 2120 L Street, NW, Washington, DC 20006, (202) 634-3273, or can be purchased from Ann Riley and.
Associates, Ltd.,
1612 K
- Street, NW, Suite
- 300, Washington, DC 20006, (202) 293-3950.
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