ML20059C973
| ML20059C973 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/08/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| REF-GTECI-057, REF-GTECI-NI, TASK-057, TASK-57, TASK-OR ACRS-2894, NUDOCS 9311020078 | |
| Download: ML20059C973 (42) | |
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C' 09/08/93 TABLE OF CONTENTS MINUTES OF THE 400TH ACRS MEETING ,
August 5-6, 1993 Pace :
I. Chairman's Report . . .............1 II. Proposed Resolution of Generic Safety Issue 57, " Effects of Fire Protection System Actuation on Safety-Related Equipment,"
and Lessons Learned from the LaSalle Fire PRA . . . . . . . . . . ............. 2 III. Report on the Advanced Boiling Water Reactor (ABWR) Fire Safety Issues . . .....6 IV. Remaining Policy Issues for Passive Plant ,
Designs . . . . . . . . ............. 6 V. Proposed Approach for Addressing Emergency Planning Under 10 CFR Part 52 . . . . . . . . . . 8 VI. Prioritization of Generic Issues . . . . . . . . . 10 ,
VII. Proposed Resolution of Generic Issue 143, ,
" Availability of Chilled Water Systems and Room Cooling" . . . . . . . . . . . . . . . . . 10 VIII. Report on the Meeting of the Thermal Hydraulic Phenomena Subcommittee Held on July 22-23, 1993 . 12 IX. Report on the Meeting of the Computers in Nuclear Power Plant Operation Subcommittee Held on July 21, 1993 . . . . . . . . . . . . . . 13 1 l
X. Report on the Meeting of the Planning and Procedures Subcommittee Held on August-4, 1993 . . 14 XI. Reconciliation of ACRS Comments and Recommendations . . . . . . . . . . . . . . . . . 16 XII. Executive Session . . . . . . . . . . . . . . . . 17 1
A. Reports, Memorandum and Letter
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020021 C. Future Meeting Agenda (
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MINUTES OF THE 400TH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS t u' ,
AUGUST 5-6, 1993 BETHESDA, MARYLAND The 400th meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Maryland, on '
August 5-6, 1993. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. ;
The meeting was open to public attendance, except for a portion that dealt with matters of a personal nature. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W., Washington, D.C. [ Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd., 1612 K Street, N.W., Washington, D.C. 20006.]
ATTENDEES i
ACRS Members: Dr. J. Ernest Wilkins, Jr. (Chairman), Mr. James I Carroll (Vice-Chairman), Mr. William Lindblad (Member-at-Large),
Dr. Ivan Catton, Mr. Peter Davis, Dr. Thomas Kress, Mr. Carlyle Michelson, Dr. Robert Seale, Dr. William J. Shack, and Mr. Charles !
l Wylie. [For a list of other attendees, see Appendix III.] l i
I. CHAIRMAN'S REPORT (Open)
[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.]
Dr. J. Ernest Wilkins, Jr., Committee Chairman, opened the meeting at 8:30 a.m. and reviewed the schedule for the meeting. Dr.
Wilkins identified a number of items that he believed to be of interest to the Committee, including:
e As of this meeting, Dr. William J. Shack is a member of the Committee.
e Several members and staf f expressed interest in visiting the Naval Museum and Exhibit Center in Crystal City, Vir-ginia. The ACRS staff was asked to schedule the visit consistent with the availability of the interested members and staff.
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9 400th ACRS Meeting 2 August 5-6, 1993 ,
II. PROPOSED RESOLUTION OF GENERIC SAFETY-ISSUE 57, " EFFECTS OF TIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EOUIPMENT," ,
AND LESSONS LEARNED FROM THE LASALLE FIRE PRA (Open)
[ Note: Mr. Herman Alderman was the Designated Federal Official for '
this portion of the meeting.]
LaSalle Fire PRA Dr. Ivan Catton pointed out some of the results of the LaSalle Fire PRA reports. He noted that inadvertent fire protection system !
(FPS) actuations were 0.15 actuations per reactor year. Advertent !
FPS actuations were 0.02 per reactor year. Thirty percent of all actuations resulted in damage to some equipment. Twenty percent of all actuations resulted in a plant transient and a reactor trip. )
He observed that the means of evaluating the fire issue through :
modeling seems to be state-of-the-art within the fire arena, but the state-of-the-art in fire hazard assessment is far behind modern l technologies. The end result is that there is a potential for a I wide range of uncertainty in fire risk analysis.
Methodoloav '
Dr. John Lambright, Sandia National Laboratories, said that the ,
first step in the methodology is to look at fire initiators, l frequencies of fires, types of fires, and fire sources in critical !
plant areas. The second step is to look at a comprehensive list of l initiating events and determine which initiating events have~a potential to be fire induced. The third step in the methodology involves assessment of fault trees and event trees. For the next-step, a screening methodology is employed to obtain signific' ant sequences and cutsets, which are combinations that lead to core damage. For the next step, a quantification of these dominant scenarios is performed. An uncertainty analysis is the final step.
Dr. Lambright discussed the vital area analysis. He noted that vital area analysis used the fault trees and event trees that were already developed for internal events. The accident sequences were expressed in terms of fire zones and random failures. He listed three basic combinations. The first implies damage to safety-related equipment in a fire area and subsequent core damage. The second combination is a barrier failure resulting in all the !
safety-related equipment in two zones failing and resulting core l damage. The third combination is fire related failures in one zone '
with random failures in other areas of the plant. leading to core damage.
Dr. Lambright talked about the screening techniques. He said that there were several levels of screening performed prior to quantifi-cation. He noted that there were three basic screening steps. The i
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400th ACRS Meeting 3 August 5-6, 1993 first is identification of the relevant fire zones. These are the zones that contain safety-related equipment or cabling. All_the l other fire zones do not require detailed analysis. This screening reduced the fire zones under consideration by about half.
The second screening step is to screen the fire zones based upon '
the vital area analysis that was previously mentioned. In the case of LaSalle, the amount of fire zones under consideration was i reduced to 14. J The final screening step, is to have a plant visit to look at ,
specific locations of equipment and cabling within the zones.
Besults of the LaSalle fire risk assessment !
Dr. Lambright noted that, for the LaSalle nuclear power plant, two types of sequences were identified. These were short-term and ;
long-term core damage sequences. The short-term core damage I sequences involved loss of coolant injection. The long-term core damage sequences involved successful injection, but containment heat removal failed. The mean calculated core damage frequency (CDF) at LaSalle was found to be 1.2E-5 per reactor year. The dominant contributors to this CDF are fires in the control room followed by fires in the electrical switchgear room. The design of control room cabinets (open at the top, thus producing a chimney effect) is a unique feature of the LaSalle design and contributes specifically to this CDF. Most plant areas had a negligible contribution to core damage frequency. In all zones additional random failures were required to lead to core damage, either operator errors or test and maintenance and random equipment failures.
Generic Issue 57, the Effects of Fire Protection System Actuation on Safety Related Eauipment Mr. Roy Woods, Office of Nuclear Regulatory Research (RES),
presented the background for Generic Issue 57. He noted that the '
issue was identified in 1982 by the occurrence of precursor events.
These events typically involved testing, maintenance errors, we.'. ding, or dust near fire protection system detectors. The proolem is that safety-related equipment could be subjected to the suppressant from a fire protection system and could then be
- rendered inoperable. An Information Notice was issued in 1983 l requesting licensees to take corrective measures. Since an Information Notice is a request and is not enforceable, it was .
decided to pursue this concern further.
Four_PRA-type analyses of operating plants were performed. These analyses, plus information from other operating plants, were used ,
to construct a generic analysis. The mean core damage frequency, determined from the generic plant analysis, is 1E-5, which is
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400th ACRS Meeting 4 August 5-6, 1993 reasonably low. The mean core damage frequency will vary from plant to plant. The staff is proposing as the resolution for I Generic Issue 57, to let the individual plant examination of externally initiated events (IPEEE) Program find these plant '
specific vulnerabilities and if they are significant enough, correct them.
Methodoloov of Fire Study Dr. Lambright mentioned that they had developed a methodology for the evaluation of potential accident scenarios caused by fire protection system actuation. This methodology was used to determine core damage risk for four individual nuclear power plant examinations. A generic analysis was then performed based on the results of these plant-specific analyses and a survey of fire protection designs at other nuclear plants. A cost-benefit analysis was performed on proposed modifications to reduce core 1 damage frequency due to the fire protection system actuation issues. The last step was to provide technical insights from the results of this study.
Technical Insichts Dr. Lambright said that in all the individual plants that were studied, there was a high potential for fire protection system diversion. He pointed out that some combined fire protection systemc could protect from 10 to 20 nuclear power plant areas. As a result, fire protection system diversion could affect as many as i 10 to 20 nuclear power plant areas.
He observed that some CO 2 tanks were on skids with inadequate mounting. In a seismic event there was the potential for these tanks or the associated piping to rupture and to create damage or become ineffectual when needed.
In some cases, batteries that are vital, for instance, to open a co 2 utlet emission valve were not anchored. In a seismic event, ;
the battery could be lost. Necessary pumps, in some cases, were found on non-vital power supplies. If off-site power is lost, then these pumps are also lost.
Mercury wetted contact type relays in fire protection system controllers were discussed. These relays are very susceptible to vibration and would be vulnerable to actuation in a seismic event.
Dr. Lambright pointed out three different mechanisms for failure of diesel generators that are protected by carbon dioxide systems.
The first was failure of the relays in the fire protection system can lock out or trip the diesel generator if it has started.
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400th ACRS Meeting 5 August 5-6,.1993 Some diesels have air intakes within'the room in which they are located. Actuation of the CO 2 system could deprive the diesel of j the air necessary to operate. :
Some. systems isolate room cooling to maintain CO 2 concentration when it is used. The diesel's generator has a high' heat load and could overheat. ,
Root Cause Scenarios !
Dr. Lambright identified 13 root cause scenarios resulting from fire protection actuations. These are:
Root Cause 1 - FPS actuation due to fire in an adja- ,
cent area.
Root Cause 2 - FPS actuation (due to fire in an adja-cent area) preventing random failure recovery actions.
Root Cause 3 - FPS actuation (due to fire in adjacent i area) preventing access for manual fire i suppression. _
l Root Cause 4 - FPS actuation caused by human error.
Root Cause 5 - FPS actuation caused by steam release.
Root Cause 6 - FPS actuation caused by hardware fail-ures.
Root Cause 7 - Seismic-induced FPS actuation caused by dust. i Root Cause 8 - Seismic-induced' FPS actuation caused by i relay chatter Root Cause 9 - Seismic-induced FPS agent release due i to mechanical damage !
Root Cause 10 - FPS actuation due to external plant fires Root Cause 11 - Advertent FPS actuation Root Cause 12 - Seismic / Fire interactions J Root Cause 13 - FPS actuation caused by unknown mechanisms :
Dr. Lambright noted that the more important contributors of core damage frequency were the seismic root causes, and the areas of highest potential contribution to core damage frequency are diesel generator room, cable spreading room, and the emergency switchgear room.
Conclusion The Committee provided a report on this matter dated August 11, 1993, to James M. Taylor, Executive Director for Operations.
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400th ACRS Meeting 6 August 5-6, 1993 III. REPORT ON THE ADVANCED BOILING WATER REACTOR (ABWR) FIRE SAFETY ISSUES (Open) '
[ Note: Mr. Dean Houston was the Designated Federal Official for this portion of the meeting.]
Mr. Michelson, Chairman of the Advanced Boiling Water Reactor (ABWR) Subcommittee, summarized the discussions that took place during the meeting of the ABWR Subcommittee held on July 28, 1993, to review the fire protection aspects of the General Electric ABWR design.
As background, Mr. Michelson indicated that the ABWR design is a three-divisional arrangement that uses three-hour fire barriers between divisions and provides a separate safe shutdown compartment for the loss of control room case. The fire protection piping'in the safe shutdown areas is seismically designed. Nearly all of the fire protection is manually activated. .Further, he indicated that
- GE is using the Fire Induced Vulnerability Evaluation (FIVE) methodology for performing the fire risk study.
During the Subcommittee meeting, the following concerns were discussed and are still under review: (1) diesel generator compartment fire, (2) performance of the foam system provided for DC compartment fire protection, and (3) accidents associated with i battery room that is directly under the control room. l Conclusion Mr. Michelson noted that the responses to the concerns discussed at the Subcommittee meeting will be reviewed later and appropriately incorporated into the ACRS report on the ABWR tentatively scheduled I for January 1994. He observed that there are no major concerns that would warrant Committee action at this time.
IV. REMAINING POLICY ISSUES FOR PASSIVE PLANT DESIGNS (Open)
[ Note: Dr. Madhat M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.]
The Committee discussed the NRC staff's positions and recommenda-tions delineated in the draft Commission paper concerning policy and technical issues associated with the regulatory treatment of non-safety systems (RTNSS) in passive plant designs. !
l In the draft SECY paper, the staff identified eight issues specific !
to the RTNSS as follows:
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- RTNSS !
e Definition of passive failure ;
e Safe shutdown requirements e Control room habitability e Station blackout e Electrical distribution e Inservice testing of pumps and valves i e Reliability Assurance Plan (rap)
As part of the resolution of the eight issues, the staff is 4 proposing the following:
o PRAs will be used explicitly in the RTNSS process to determine the risk significance of active systems.
e Individual plant designs will be held to standards that are surrogates for the safety goals, e Reliability missions for active systems will be developed that can be interpreted as reliability target values.
The Committee agreed with the staff's proposed positions for '
resolving the above eight issues, but had some concerns regarding specific aspects of the proposed approach that include:
e The use of an (as yet unspecified) large release criteri-on that is likely to be well beyond what is required by the Commission's quantitative health objectives in the Safety Goal Policy statement.
e The difficulty of establishing reliability values for passive systems and the rationale in using these values to establish the risk-significance of the active systems.
e The difficulty of establishing the reliability of active systems and components.
- The lack of a firm position on how the results of the uncertainty analysis will be used in the process.
. The need to clarify the technical basis for allowing' 420*
F to be the definition of a safe shutdown condition.
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August 5-6, 1993 !
The staff stated that the draft SECY will be placed in the Public.
Document Room and the public will be given an opportunity to submit comments.
Conclusion The Committee decided to defer issuance of its report until the resolution of the public comments are completed by the staff and a revised SECY is made available to the Committee.
V. PROPOSED APPROACH FOR ADDRESSING EMERGENCY PLANNING UNDER 10 CFR PART 52 (Open) '
[ Note: Mr. Elpidio Igne was the Designated Federal Official for k this portion of the meeting.] '
Dr. Wilkins, Chairman of the Occupational and Environmental i Protection Systems Subcommittee, introduced this topic to the Committee.
He noted that the NRC staff has prepared a draft paper o that addresses emergency planning requirements for early site ;
permits, standard design certification, and combined licenses under 10 CFR Part 52. The paper specifically does not address proposed simplified emergency plans for advanced LWRs of passive designs. ,
The staff plans to discuss simplified emergency plans in a separate i Commission paper.
Mr. Robert Erickson, NRR, briefed the Committee on the staff plans dealing with emergency preparedness for future reactors licensed under 10 CFR Part 52. He noted that Part 52 contains three !
subparts dealing with, 1) early site permits, 2) standard designs l and 3) combined license. Part 52 was, in part, designed.to provide i opportunity for licensing issues, including emergency preparedness, to be identified and addressed in the licensing process before large investments are made in future nuclear power plants. Mr.
Erickson described how the emergency preparedness aspects are being addressed under each subpart of the rule. He stated that the emergency preparedness plans submitted by the applicant are reviewed by the NRC and the Federal Emergency Management Agency (FEMA). The acceptance criteria for the review of these plans are delineated in NUREG-0654/ FEMA-REP-1, Revision 1, Supplement 2.
Mr. Erickson noted that the subpart of the rule dealing with combined license is probably the most important with regard to emergency preparedness. He mentioned that this subpart was modified when Congress passed the Energy Policy Act of 1992. The Act requires that the inspection, test, analysis, and acceptance l criteria (ITAAC or Tier 1) for combined license include those applicable to emergency planning. Prior to nuclear power plant operation, the NRC must find that the acceptance criteria are met.
In reply to a question from Dr. Wilkins, Mr. Erickson stated that
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400th ACRS Meeting 9 August 5-6, 1993 there is a memorandum of understanding (MOU) between the NRC and the FEMA delineating on-site and off-site responsibilities. It was also mentioned that a new amendment to the MOU has been agreed ,
upon and will be published in the Federal Register in about a week.
This amendment addresses events such as natural disasters, e.g., '
flooding. -
Mr. Erickson noted that the matter of hearings and proceedings-is i central to the question of Part 52. It has loosely been called a '
one-step licensing process, whereby a holder of a combined license ;
may be able to not only construct but also operate the plant. Mr. '
Erickson noted that for a Part 52 combine license, NRC's assurance i of quality in emergency preparedness will be based upon the ;
inspection, test, analysis, and acceptance criteria (ITAAC) . These ITAAC may call for various drills, exercises and demonstration that the emergency planning standards have been met. In reply to a -;
question from Dr. Kress, Mr. Erickson stated that the emergency-plans are applicable during plant shutdown condition.
Mr. Erickson discussed the work that remains to be completed, including the joint issuance (NRC and FEMA) of NUREG-0654 supple-ment 2 and the continued coordinating with FEMA to develop standard i emergency planning ITAAC guidance for applicants. In reply to a question from Mr. Lindblad regarding an early site permit applica- i tion, Mr. Erickson stated that no formal commitment for an early i site permit has been received. Further, the staff believes no uncertainties exist in Part 52 and that other matters, - e.g. ,
political or financial, may be more important than the matter of ,
emergency planning. On the matter of using an existing nuclear power plant site for building another plant, Mr. Erickson mentioned that Part 52 would be bypassed and the existing emergency planning site plan would be in effect -- multiple units at the same site are covered by the existing site plan.
Mr. Erickson, noted that the Electric Power Research Institute "
(EPRI) has submitted to the NRC a modification of the EPRI utility Requirements Document for passive plants that will consider the nuclear plant like any other major industrial facility dealing with j hazardous substance subject to enforcement by EPA-type regulations.
Mr. Richard Borchardt, NRR, added that neither GE nor Westinghouse, i the vendors for the two passive designs, is requesting simplifica- i tion of present emergency planning. Their design certification ;
application is consistent with the present rules on emergency i planning and preparedness. If details of a simplified emergency planning and preparedness submittal are received by the staff, the Committee will have an opportunity to discuss it with the staff.
Conclusion This briefing was for information only. The Committee decided not to comment on this matter, at this time.
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August 5-6, 1993 VI. PRIORITIZATION OF GENERIC ISSUES (Open)
[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for ;
this portion of the meeting.] ;
The members discussed the Subcommittee Chairmen's assignments for.
reviewing the NRC staff's priority rankings to 31 generic issues (eighth group) . Pricr to the September Full Committee meeting, the Subcommittee Chairmen are expected to review and comment on the rankings and, if necessary, consult with the other members of the :
Subcommittee and/or the NRC staff. Comments are expected to be submitted in writing to Sam Duraiswamy on or about August 25, 1993. i VII. PROPOSED RESOLUTION OF GENERIC ISSUE 143, " AVAILABILITY OF CHILLED WATER SYSTEMS AND ROOM COOLING" (Open) ;
[ Note: Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.] l Dr. Ivan Catton, cognizant ACRS Member, introduced this topic-to-the Committee. He noted that the relevant documents supporting ;
this matter are in the meeting notebook. Dr. Catton noted that the Committee raised this issue following a joint Subcommittee Meeting .i on June 27, 1993. The Committee formally communicated its concern '
in a report to Victor Stello, Executive Director for Operations on October 15, 1987.
FRC-RES Presentation Mr. Vincent Leung, RES, provided introductory remarks concerning the staff's proposed resolution of Generic Issue 143, " Availability of Chilled Water Systems and Room Cooling." He repeated the above I information concerning ACRS's initiation of concern and said that RES began work on GI-143 in April 1991, following the assignment of l a "high" priority. Pacific Northwest Laboratories (PNL) was 1 engaged as the principal investigator.
The objectives of the regulatory analysis conducted on this Generic Issue were: (1) to evaluate the design of HVAC and chilled water system at operating plants and to determine the impact of their failure on plant safety and, (2) to obtain realistic risk and risk-reduction potential for possible modifications designed to improve the availability of said systems.
The results (CDFs in 10 10-6 range, potential CDF reductions of l approximately 10-6) do not justify any modifications, pursuant to the Backfit Rule. In response to Dr. Seale, Mr. Robert Baer, RES, j noted that, following initiation of this work, Commission guidance was provided concerning what risk reduction is deemed " substantial
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l 400th ACRS Meeting 11 August 5-6, 1993 for public health and safety" that would have deemed it prudent to terminate their efforts here a:ter the above-CDF values were i determined. It was decided to complete the Regulatory Analysis, I nevertheless. l The discussion centered on the issue of resolution of the GIs vis- ,
a-vis their incorporation into the integrated plant evaluation ;
(IPE) process. It was noted by Mr. Baer that most licensees seen !
to be considering the potential safety impact of the various GIs in their IPEs, however, there is no mechanism in place to ensure that this is the case nor is the staff currently planning to check into this matter via its review of the IPE submittals.
Mr. Philip Daling, PNL, provided a presentation detailing the '
results of its value-impact assessment associated with GI-143. The ,
key points noted include:
e Discussing the objectives, scope and approach taken, Mr.
Daling noted that an assessment of existing information showed that there was little material on temperature
" fragility" of equipment, and that EQ tests seldom tested ;
the equipment tc failure conditions. '
e Four nuclear power plants were selected as representative of the majority of the operating plant population: t Sequoyah (H), Grand Gulf (GE) , Palo Verde (CE), and ;
Oconee-3 (B&W). These plants were examined in detail. ;
i Loss of room cooling was examined as both an initiator '
and as a contributing event. An external events analysis was also performed.
e The external events analysis evaluated the CDF contribu-tor due to fire, seismic events, floods and tornadoes.
The results for the four nuclear power plants show that ;
the affected CDFs to all are in the range of 10-5 _ in-6
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e Mr. Michelson raised several questions regarding the '
ability of large chiller units to be rapidly restarted ;
following the loss of power. The staff confirmed his understanding that restart must be delayed 10-20 minutes to allow decay of the compressor loading pressure, unless
' the unit is equipped with a " pressure dump." He also asked if there are problems associated with the start of a cold compressor unit. The staff said that one must i wait approximately 30 minutes in order to allow for l timing considerations. Mr. Michelson further observed '
that the compressor lube oil must be warmed up in order to ensure it does not froth in the presence of freon and
- result in failure of the compressor due to the lack of proper lubrication.
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1 400th ACRS Meeting 12 August 5-6, 1993 e As noted above, none of the proposed resolution alterna- ,
tives evaluated are cost ef fective (cost _ > $1000/ man-rem) .
except the "do nothing" Alternative.
Dr. Catton indicated that he has drafted a letter to the EDO that supports the staff's proposal to resolve this GI, absent issuance of any regulatory requirements by NRC. He also indicated to the staff that the Committee intends to look into the issue of how the -
staff is evaluating the IPEs submittals vis-a-vis resolution of various generic issues.
Conclusion i The Committee provided a report on this matter dated August 11, 1993, to James M. Taylor, Executive Director for Operations. The- 1 Committee also intends to address its concern that there appears to be no process in place tt. ansure that licensees give appropriate attention to this issue as part of their IPEs.
VIII. REPORT ON THE MEETING OF THE THERMAL HYDRAULIC PHENOMENA i SUBCOMMITTEE HELD ON JULY 22-23. 1993 (Open)
[ Note: Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr. Catton reported on the results of the meeting of the Thermal Hydraulic Phenomena Subcommittee, held on July 22-23, 1993, to ,
review the status of the H analytical and experimental program being conducted in support of the AP600 design certification effort. He noted the following points:
e H is conducting its test programs in support of develop-ment of the following major codes: COBRA / TRAC and NOTRUMP. The H strategy is to use the data obtained from the separate effects and integral tests for verification and validation (V & V) of the above codes. The codes, in I turn, will be used for modeling of the nominal plant design. l e Th2 following concerns were identified by the Subcommit-tee during the raeting:
A great amount of data are lacking on the design, scaling, instrumentation and test conduct for the various H test programs.
Scaling analyses are, in some cases, being conducted "after the fact" (subsequent to facility design and construction). The Subcommittee received a, scaling report on SPES-II, but it appears to be inadequate.
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400th ACRS Meeting 13 August 5-6, 1993 The scaling report for the OSU facility was just received, although the facility construction is essentially complete.
4 For the CMT. separate effects test facility, the tank >
design is not prototypical, and there may not be sufficient instrumentation to obtain the needed ',
data.
The ADS Phase B tests of the nominal blowdown valves do not appear to give sufficient emphasis to the t thermal hydraulic phenomena that these valves will see in an actual plant.
The full-height, full-pressure SPES-II facility noted above, only mocks up two RCPs-(versus four on the nominal plant). A flow splitter was inserted on 4 the pump discharges; there is concern that use of the splitter will result in inadequate simulation of thermal hydraulic phenomena.for some transients.
Dr. Catton noted that the codes will need to be vigorously exercised to ensure their fidelity. He noted that the Subcommittee >
l has planned a meeting at the site of OSU in September. j i
Mr. Davis observed that he finds it ironic that a so-called j
" passive" plant design evaluation necessitates such extensive l analytical and experimental programs on the part of both H and the NRC. Dr. Catton indicated that, although he finds the design of AP600 appealing from a safety standpoint, H needs to demonstrate an ability to predict its thermal hydraulic behavior for transient /-
accident scenarios. One problem he noted is that both H and the staff are not using simple fast running codes for analysis of this design, rather than the currently available complex codes.
Conclusion This briefing was for information only. No Committee action was taken.
IX. REPORT ON THE MEETING OF THE COMPUTERS IN NUCLEAR POWER PLANT OPERATIONS SUBCOMMITTEE HELD ON JULY 21. 1993 (Open)
[ Note: Mr. Douglas Coe was the Designated Federal Official for this portion of the meeting.)
Dr. Thomas Kress reported on the Computers in Nuclear Power Plant Operations meeting on July 21, 1993, in lieu of the Subcommittee Chairman, Dr. Lewis, who was not present. Dr. Kress noted that the principal issues discussed at tr.is subcommittee meeting were the
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s 400th ACRS Meeting 14 August 5-6, 1993 industry's efforts at writing a guidance document to ' assist licensees during 10 CFR 50.59 evaluai. ions to detarmine when NRC staff review is required for a digital upgrade and what guidelines should be used by either the staff or licensee in aetermining that such an upgrade is safe. Two licensees were represented, from D.C.
Cook and Zion nuclear power plants, who have been or are involved in digital upgrades being reviewed by the staff. '
Dr. Kress stated that Mr. William Russell had agreed to brief the '
Committee in closed session regarding the staff's insights gained i from foreign trips and from the U.S. military on digital instrumen- '
tation and control (I & C) issues. He noted that Dr. Lewis had indicated an intent to draft a letter for Committee review. A short presentation from the staff would be scheduled at the next ACRS meeting for this purpose. Mr. Carroll expressed concern that not enough Committee attention was being given to the ABWR I & C review, and that thic could become a problem toward the end of the :
year.
X. REPORT ON THE MEETING OF THE PLANNING AND PROCEDURES SUBCOM-MITTEE HELD ON Aucust 4, 1993 (Open)
[ Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.]
As a result of the Planning and Procedures Subcommittee meeting held on August 4, 1993, the following items were brought to the attention of the Committee:
e Dr. Wilkins reported on his meeting with Chairman Selin on August 4, 1993. Items discussed during the meeting included the interaction between the Committee and the NRC staff, the Quadripartite Advisory Committees meeting in France, the impact of FTE reductions on the ACRS, and the ACRS/ACNW Fellowship program.
e The Committee discussed a draf t letter regarding certain comments made by Dr. Murley during a staff briefing of the Commission on the afternoon of May 14, 1993. These comments concerned the conduct and motives of ACRS in dealing with the NRR staff on the issue of digital instrumentation and control. The Committee agreed not to issue a letter at this time.
- Several options for the future operation of the Fellow-ship Program was discussed. The Committee endorsed a proposed plan to appoint three Senior Fellows for two-year terms with optional reappointments to second two-year terms and to award stipends to postgraduates
_ _ ~_ __ - ___
G 400th ACRS Meeting 15 August 5-6, 1993 attending universities where individual Committee members can provide guidance and oversight.
The Committee discussed the status of a draft Manual Chapter that defines the objectives, responsibilities, requirements, and procedures to implement and operate a Fellowship Program. A draft Manual Chapter will be reviewed by the ad hoc Fellowship Subcommittee and the full Committee during the next meeting.
Dr. Wilkins reminded the members that he would like more possible topics to be placed on the Committee retreat agenda.
- Mr. Carroll suggested that the Committee members might like to read the Inspector General's audit report on Frequent Flyer Benefits. -
e The members discussed a proposed amendment to the Bylaws submitted by Mr. Carroll during the 399th ACRS meeting.
Several revisions were discussed and agreed upon. A motion was passed to table discussion of the proposed amendment (as revised) until the 401st ACRS meeting.
e The members discussed the preparation of technical papers for the Second Quadripartite Meeting of the Advisory Committees on October 11-15, 1993. The Committee agreed that each paper should include a disclaimer that states that the contents of the paper are not necessarily the vie.. a or recommendations of the Advisory Committee on Reactor Safeguards. Tae members also discussed the merits of placing the nanas of collaborators on the paper as coauthors or as footno*;n. The ACRS staff was asked to place the papers in ile <,oper format, if required, and forward to the Fre uh uljanizers.
e The Committee discussed ue implications of a memorandum to William Parler from Samuel Chilk, dated July 30, 1993, regarding SECY-93-157, Supplemental Ethics Regulations and Implementing Management Directives.
e The Committee endorsed a request from Dr. Catton to retain Dr. Quintiere, University of Maryland, to review the adequacy of existing standards for fire barriers for nuclear power plant application and to determine ' industry practice for oil fire barriers. It is expected that the work can be completed by the end of September 1993.
? .
J 400th ACRS Meeting 16 August 5-6, 1993 e The Committee discussed the relative accuracy of the meeting transcripts and the possibility of adding 'a disclaimer similar to that found in the Commission meeting transcripts. l e The Committee discussed a recent memorandum that requires members to sign up for direct deposit of compensation payments. The staff was asked to contact the Office of the General Counsel to learn more about the legal basis for this requirement.
e The Committee endorsed Dr. Lewis's request to attend and participate in the following meetings: ;
International Society for Bayesian Analysis, August ,
6-7, 1993, in San Francisco, CA American Statistical Society meeting, August 8-10, i 1993, in San Francisco, CA Nuclear Utilities Software Management Group meeting, l October 21, 1993, in Annapolis, MD [
L During discussion on this matter, Mr. Lindblad recom- .
mended that the Planning and Procedures Subcommittee consider establishing a policy on supporting member's '
attendance at professional meetings.
i XI. RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS (Open) !
[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.) ;
The responses of the Executive Director for Operations (EDO) to l previous ACRS reports were discussed as follows:
- EDO letter, dated July 22, 1993, responding to the ACRS report dated June 18, 1993, concerning policy statement on technical specifications improvements for nuclear :
power plants Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments.
- EDO letter, dated July 23, 1993, responding to the ACRS report dated July 15, 1993, concerning the regulatory review group report
400th ACRS Meeting 17 August 5-6, 1993 Conclusion The Committee did not raise any objections to the EDO's response. However, Mr. Carroll believes that there are some questions that still remain to be discus. sed with Dr.
Murley regarding NRR's response to the report.
e EDO letter, dated July 27, 1993, responding to the ACRS report dated July 15 20, 1993, concerning proposed draft Regulatory Guides, DG-1023 and DG-1025. ,
Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments. As stated in the response, the Committee expects to schedule another meeting for review of the proposed final versions of the draft guides.
XII. EXECUTIVE SESSION (Open) I
[ Note: Dr. John Larkins was the Designated Federal Official for this portion of the meeting.) -
A. Reports and Memoranda Proposed Resolution of Generic Issue 57, " Effects of Fire !
Protection System Actuation on Safetv-Related Eauipment" I (Report to James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated August 11, I 1993) I Proposed Resolution of Generic Issue 143, " Availability of Chilled Water System and Room Coolina" (Report to James M.
Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated August 11, 1993)
Proposed Amendments to 10 CFR Parts 19 and 20: Controlled Area, Occupational Dose, and Training Criteria (Memorandum for C. J. Heltemes, Jr., Deputy Director for Generic Issues and Rulemaking, RES, from John T. Larkins, Executive Director, ACRS, dated August 12, 1993.) Consistent with the Committee's decision, Dr. Larkins informed Mr. Heltemes that the Committee had decided not to review the subject proposed rule changes.
Proposed NRC Generic Letter " Removal of Accelerated Testing i and Soecial Reportina Reauirements for Emercency Diesel I Generators from Plant Technical Specifications" (Memorandum j to Brian K. Grimes, Director, Division of Operating, Reactor i Support, NRR, from John T. Larkins, Executive Director, ACRS,
J .
J l
400th ACRS Meeting 18 August 5-6, 1993 dated August 13, 1993.) Consistent with the Committee's decision, Dr. Larkins informed Mr. Grimes that the Committee '
had decided to review the subject proposed Generic- Letter during its 401st meeting, September 9-11, 1993. The committee has no objection to the staff's proposal for issuing the proposed Generic Letter for public comment prior to this review.
Proposed NRC Sucolement 1 to Generic Letter 92-08. " Fire Endurance Test Acceptance Criteria for Fire-Barrier Systems Used to Seoarate Redundant Safe Shutdown Trains within the Same Fire Area" (Memorandum to Brian K. Grimes, Director, Division of Operating Reactor Support, NRR, from John T.
Larkins, Executive Director, ACRS, dated August 26; 1993.)
Consistent with the Committee's decision, Dr. Larkins informed i Mr. Grimes that the Committee had decided to postpone its review of the Supplement 1 to Generic Letter 92-08 until af ter the public comments have been reconciled by the staff.
B. Future ACRS Activities-1
.Several members and staff expressed interest in visiting the Naval Museum and Exhibit Center in Crystal City, Virginia. ,
The ACRS staff will schedule the visit consistent with the availability of the interested members and staff.
C. Future Meeting Agenda Appendix IV summarizes the proposed items endorsed by the ,
Con uittee for the 401st ACRS Meeting, September 9-11, 1993, ,
and future Subcommittee meetings. !
The 400th ACRS meeting was adjourned at 3:10 P.M. on Friday, August !
6, 1993.
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_ . - . . , , . - . , , n - e n-,- -- -~ - - - - - - -'
I .
APPENDICES i MINUTES OF THE 400TH ACRS MEETING l AUGUST 5-6, 1993 i
I. Federal Register Notice II. Meeting Schedule and Outline III. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee
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APPEt0IX I Fed:rcl Regist:r / Vol. 58, No.139 / Thursday, July 22, 1993 / Notices 39251 pressure locking and thermal binding of . RiiR suppression pool suction valves With respect to a particular question gate valves within the scope of GL 89- . Containment isolation valves (sample on the consideration of external heat line, letdown heat exchanger inlet loads, licensees may evaluate the effects tok. Document an evaluation of theheader) gate
- of these loads in a bounding manner to valves within the scope of GL 89-10 as . Condensate discharge valves mmimize the need for detailed having creretional configurations with a . Reactor feedwater pump discharge potential for pressure locking or thermal valves measurements and analyses in the plant.
From the evaluation of licensee binding, including the basis for A recent event at a plant involving activities during CL 89-10 inspections, determining whether the valves (a) are possible pressure locking of a ROC the staff will determine whether susceptible to pressure locking or valve indicates that MOVs in steam regulatory action is necessary with thormal binding or (b) can be removed lines also are susceptible to pressure respect to other types of power-operated from further consideration. For locking. valves (such as air-operated valves) in example, solid wedge disc gate valves 2. Document an analysis of the safety- regard to the potential for pressure mir'at not be susceptible to pressure related gate valves (identified in 1 locking and thermal binding.
ate valves are not above) with the potential for either locking.
likely to beDouble susceptibdirc fe to thermal pressure locking or thermal binding to Miscellaneous i binding. ensure all such valves can be opened to The NRC staff received miscellaneous i
The evaluation would include perform their safety function under all new questions on plans for a generic j consideration of the potential for an modes of plant operation. Credit for letter on air operated valves (AOVs), the MOV to undergo presure locking or bonnet pressure decay within the valve need for on-line continuous monitoring thermal binding during surveillance response time might not be acceptable of MOVs, the plans for a proposed NRC testing. Fer example, the inboard unless operation of the actuator rnotor at staff meeting with MOV experts from containment isolation MOV in the locked. rotor conditions would not other countries, the role of vendors in reactor core isolation cooling (ROC) de;;;rade motor iorque capability; resolving the MOVissue, and the status system steam line at a plant recently Specific acceptable modifications and of NRC staff comments on the EPRI failed in the closed position following actions to prevent pressure locking or MOV Performance Prediction Program.
closure for routine surveillance testing. thermal bm, dmg are listed on page 7 of The cause was believed to be pressure NUREG/CR-1275. Sta esponse The NRC regulations require an The staff has been considering the lockinhvaluation The also wouldvalve include analysis under 10 CFR 50.59 for any modifications and the issue of performance of AOVs and review of generic studies for site. currently does not believe that a generic i
specific applicability, such as in the establishment of adequate post- letter is necessary.
areas of thermal effects and designesis m dification and inservice testing of Use of on-line continuous monitoring d ressurization any valves installed as part of the would be a licensee decision.
$xamples of unacceptable reasons for m dification. For example, the licensee The staff has requested the eliminating valves from consideration of w uld evaluate the effects of drilling the International Atomic Energy Agency pressure loc 3dng or thermal binding are hole m the disk if used to resolve a (IAEA) to set up a meeting under the (1)leckage rate. (2) engineering pressm lqcking concern. One aging program to discuss problems with judgment without justification, and (3) consideration m this evaluation is the the performance of MOVs in other lack of event occurrence at the specific fact that the MOV will be leaktight in countries and the resolution of those
>lant nly one direction. problems.
ne AEOD study indicated that As required through appendix B to 10 The staff encourages licensees to work ~
' CFR part 50, the licensee would safety related gate valves involved in closely with the vendors to resolve pressure locking events were: establish training for plant personnel to MOV performance concerns.
. Low pressure coolant m, iection (LPC) perform any necessary actions and The staff sent a letter in December and low pm incorporate specific procedural 1992 to EPRI discussing issues wgarding g g cQspray M
, precautions / revisions into the existing the EPRI MOV program.
. Core s (CS) valves plant operstmg procedures. For {
example, plant personnel might Dated at Rociville, Maryland. this 15th day
. Residua eat removal (RHR) , ]f luf y 1993.
shutdown cooling (SDC) isolation "d s erta val st t
valves kdu g g, {g g For the Nuclear Regulatory Comtrission.
DI ding Gail 11. Marcus.
. RHR hot leg crossover isolation valves
= RHR contamment sump and h m end M sup ression pool suction valves to pressure locking or thermal bir ding M n fOpemungReadorSupport. Office and the licensee relies on the capabihty
- hie, Pressure coolant inlection (FR Doc. 93-17468 riled 7-21-93; 8.45 aml of the MOV to overcome pressure
. R beat c ger outle va ves I cking or tl ermal 3
binding, the staff will ***o coot m-ow
. Emergency feedwater isolation valves review the hcensue justification during The AEOD study indicated that safety. inspections in consideration of the related gate valves involved in uncertainties surrounding the Advloory Committee on Reactor thermal binding events were Prediction of the required thrust t Sa%uwds (ACRS) and Advisory
. Reactor deprest,urization system overcome these phenomena. If the staff Committee on Nuclear Waste (ACNW);
isolation valves Proposed Meetings finds that a licensee has not adequately
. RHRinboard suction isolation valves addressed the potential for pressure la order to provide advanm
. HPCI steam admission valves locking and thermal binding of gate. information mgardingproposed public,y .
M = Power operated relief valve (PORV)
~
valves, enforcement actions and O meetingsof the ACRSSubmmmittees s a .'
block valves schedules for response will depend on and meetings of the ACRS full . s
. . Reactor coolant system letdown the safety significance of the issue at the Committee,of the ACNW,and the i isolation valves plant. ACNW Working Groups the following 1; '
a .
I d 39252 Federal Register / Vol. 58, No.139 / Thursday, July 22, 1993 / Notices associated with the CE ABWR design preliminary schedule is published to proposed ACRS
' reflect the current situation, taking into matters. Portions of activities this meeting and mayrelated be . certification review.
account additional meetings that have closed pursuant to 5 U.S.C. 552b(c)(2) Planning and Procedures, October 6, been scheduled and meetings that have and (6) to discuss organizational end 1993, Bethesda, MD (2 p.m.-4:30 p.m ).
been postponed or cancelled since the personnel matters that relate solely to The Subcommittee will discuss last list of proposed maetings was internal personnel rules and practices of proposed ACRS activities and related matters. Portions of this meeting may im published June 23,1993 (58 FR 34067) ACKS and matters the release of which Those meetings that are firmly would represent a clearly unwarranted closed pursuant to 5 U.S.C. 552b(c)(2) scheduled have had, or will have, an invasion of personal privacy. and (6) to discuss organizational and individual notn e published in the Materials and Metallurgy, August 16, personnel matters that relate solely to Federal Register approximately 15 days 1993 Bethesda, MD (12 noon). The intemal personnel rules and practices of f or more) prior to the meeting. It is Subcommittee will review proposed ACRS and matters the release of which expected that sessions of ACRS and rulemaking on fracture toughness would represent a clearly unwarranted ACNW full Committee meetings requirements for reactor pressure invasion of personal privacy.
designated by an asterisk (*) will be vessels-revisions to 10 CFR 50 61. Ther rralHydraulic Phenomena, closed in w he!o or in part to the public.
October 20-21,1993 (tentative),
Fracture Toughness Requirements for The ACRS and ACNW full Committee Protection Against Pressurized Thermal Bethesda. MD. The Subcommittee will Shock Events, Appendix C, Fracture review selected aspects of the NRC-meetings b S ni at 8:30 a.m. and ACRS Subcommittee and ACNW Working Toughness Requirements, Appendix H. "#S-Sponsored ROSA-V confirmatory Group meet ngs usually begin at 8:30 Reactor Vessel Material Surveillance test program being conducted in support a.m. The time when items listed on the Program Requirements, and a new rule of the Westinghouse AP600 passive agenda willbe discussed during ACRS on reactor vessel thermal annealing (to Pl ant design certification effort. Specific and ACNW full Committee meetings. CFR 50.66). review topics will include: facility and when ACKS, Subcommittee nnd Mechamca! Components. August 17, design modifications and additions, the ACNW Woriing Group meetings will 1993, Bethesda, MD. T he Subcomn.ittee test matrix, and instrumentation and start will be published prior to each will discuss the status of the ongoing controls. Also the Subcommittee will meeting. Information as to whether a NRC and industry activities associated continue its review of the NRC RELAPSI meeting has been firml y scheduled, with motor-operated valves, check MOD 3 code.
cancelled, or rescheduled, or whether Advanced Boiling Water Reactors, ulves, butterfly valves :nd other Octobar 26-27,1933, Bethesda, MD.
changes have been made in the agenda related matters.
for the August 1993 ACRS and ACNW The Subcommittee will begin its review Advanced Boiling Water Reactors. f the NRC staffs Final Safety tell Commatee meetings can be September 8,1993. Bethesda, MD. The chtamed by a prepaid telephone call t Subcommittee will discuss the status of Evaluation Report for the GE ADWR the Office of the Executive Director of resolution of the remaining open iuues design.
the Committees (telephone: 301/492- Advanced Boiling Water Reactors, in the ABWR Standard Safety Anahsis November 16-17,1933, Bethesda, MD.
4600 (recoramg) or 301/492-7288, Attn: Report and the resolution of'USIs and The Subcommittee will contmue its Barbara Jo White) between 7.30 a.m. and GSIs. Also,it will discuss the NRC review f the NRC staffs Fmal Safety i 4:15 p m., (EDT). staffs schedule for submittal of tl.e Evaluatmn Report for the GE ABWR ACRS Subcommittee Meetings Final Safety Evaluation Report.
A uxiliary and Seconda:y Systems.
Planning and Procedures, September 0*)i "Q g h g 1
8,1993, Bethesda, MD (2 p m.-4 30 january 25-26,1994. Bethesda, MD. The I
July 27 (8.30 a.m. until close of business) and 28,1993 (8.30 a.rn.-10:30 P m.). The Subcommittee will discuss Subcommittee will review any residu'il a m.), Bethesda, MD. The Subcomm.ittee proposed ACRS activities and related issues associated with the ABWR design will review the La Salle Fire PRA and matters. Portions of this meeting may be and prepare a proposed ACRS report on the preposed resolution of GenericIssue ci sed pursuant to 5 U.S C. 552b(c)(2) the ABWR issues for consideration by and (G) to discuss organizational end the full Committee.
57," Effects of Fire Protection System Actuation on Safety.Related Personnel matters that relate solely to internal personnel rules and practices of ACRS Full Conunittee Meetings Equipment." ACRS and matters the release of which Advanced Boiling Water Reactors, 400th ACRS Meeting, August S-7, 1 July 28.1993, Bethesda, MD (11 a.m.). would represent a clearly unwarranted 1993 Bethesda, MD. During this The 56 committee will discuss fire invasion of personal pnvacy. meeting, the Committee plans to PRA, fire hazards analysis, and fire Computers in Nuclear Peu er Plant consider the following:
barrier design associated with the Operations September 15,1993. A. Remaining PolicyIssues for Pcssiv Advanced Boiling Water Reactor design. Bethesda, MD-POSTPONED. Plant Designs-Review and comment on improved Light Water Reacton, Thermal Hydraulic Phenomena, the draft Commission paper on the August 4,1993, Bethesda, MD. The September 21,1993 (tentative), Oregon remaining policy issues related to the Subcommittee will discuss the NRC State University (OSU), Corvallis, OR. passive plant designs. Representatives staffs response to ACRS comments and The Subcommittee will continue its of the NRC staff will participate.
recommendations related to certain review of the Westinghouse and NRC B. Proposed Resolution of Generic policy, technical, and licensing issues integral systems and separate effects test Safety Issue 57, Effects of Fire pertaining to evolutionary and advanced programs supporting the AP600 design Protection System Actuation on Sofery-light. water reactor designs. Also, the certification effort. The meeting Related Equipment," and Lessons Subcommittee will discuss the staff discussion will focus on the OSU frorned from the lo Salle Fire FRA-integral systems test facility program. Review and comment on the proposed positions on certain remaining policy issues for passive plant designs. Severe Accidents, September 22-24. resolution of Generic Safety issue 57 Planning and Procedures, August 4, 1993. Los Angeles, CA or Portland, OR. and the Lessons Leamed from the La 1993 Bethesda, MD (2 p.m.--4:30 p.m ). The Subcommittee will continue its Salle Fire PRA, Representatives of the The Subcommittee will discuss review of the severe accident issues NRC staff will participate.
I
. . Federzl Register / Vol. f.6, No.139 / Thursday, July 22, 1993 / Notices 3925'l Representetivos of the industry will 402st ACRS Meeting. September 9-11, also focus on the recharge ten ..
participate, as approprints. 1993. Dethesda, MD Agenda to be hy drogeologic models, alternt sve C. Proposed Resolution of Generic cnnounced. conceptual models for how and where ,
Issue 143. "Availchility cf Chilled Water 402nd ACRS Meeting. October 7-9. regior,al rocharge occurs, and the effect l Sysums and Ronm Cochng"-Review 1993. Bethesda, MD. Agenda to be of assumptions about recharpe on model l di commnnt on the NRC staffs anncunced results. i pronesed resolution of Generic Issue scJrd ACRS Meefirg, Nosen,ber 4-A Smh AOIWMratirig. October 27-28, i 1431 Represantauves of the NRC staff 1993 Bethesde, MD. Agendo to be 19M. Las Wges. NV. Agenda to be l wiH psr'ic:p?t+ ann unced. anr.otacad. ,
.. 4utth ACBS Moeting. f Mcember 9-11 5% ACNW Mating, November 22~ '
bcn Fan -
He . abb a W. Nthesda, MD. Agenda to be l Tc r r Rev+w and comment on e draft "N"M,3 Wn edn@ amber 15-Ccrtmission peer related to emargency ACNW Full Committn and Wod ing .
ethesda, MD Agenda to be piennir.c ic Mvenred Ught Water ~ Group Meetings INac to, sentatives of the NRC 56th ACMVMeeting. Au3ust 25-26 .
staff w apMe. . N, 'I "
1993, Holiday Inn, BetMsdi, MD.
EM x mth Chairman Sehn- Durir.g this meeting the Cammittee W C D '-
Hold du us; ions with NRC Chairman plans to consider the followinr Advisry Co m tree Managernent Officer.
S-!in on items of mutual interest.
- A. The Committee will meet in IFR Doc. 93-17341 Filed 7-2 t43; 8.45 aml F. Resolution of ACBS Comments cnd executive senion to d scuss a strat5y su,*c. cooe rmw Recommendatiens-Discuss responses for implementing recent directmn from __
fmm the NRC Executive Director for the Commission on the ACNW charter (Dccket No. $>318]
Operations to recer t ACKS comments and renewal of appointment fcr and recommendations members. Methods for ACNW Baltimore Gas & Electric Co.;
G Prioritizatien of Generic Issues- operation, candidates for appointment Considerstion of lasuance of D:scuss proposed assignments for to the Committee, and topycal areas for Amendment to Facility Operating reviewing the priority rankings ACNW review will form tne central License, Proposed No Significant prcposed by the NRC staff for a group focus of this meeting. Hazards Consh$eration Determlnation, of wneric issues.
- B. Cnmmittee Activities-Da. cuss and Opportunity for a Hearing i ll. ACES Subcomrrartee Activities-- anticipated and proposed Commiuee Hear reports and hold discussions acuvaies, future meeting ager.da. and 1,he U S. Nuclear Regulatory ,
regarding the status of ACRS organizptional and personnel matters Commission (the Commission)is C. Miscellaneous-Discuss considering issuance of an amendment subcommittee activities, including to Facihty Operating License No. DRP-reports from the Subcommittees on misceHaneous rnatters related to the Thermal Hydraulic Phenomena and conduct of Committee activities ar.d 69 issued to Baltimore Gas & Electnc Ads anced heiling Water Reactors. c mplete discussion of topics that were Company (the licensoel, for operation of Pcrtions of this session may be closed ntc pleted during previous meetirgs the Calvert Cliffs Nuclear Power Plant, as time and availability of information Unit No. 2 located in Calvert County, to discuss information deeined meeting will be closed to the xised emendment would bectri Cr ta o r S extent it discusses organizational and revise Tec mical Specifications (TS) 3/
552b(c)(4)' 4.2," Power Distribution Limits," and 3/
personnel matters that relate solely to
- !. Planning and Procedures the intemal personnel rules and 4.3, " Instrumentation." to relax the Subcommittee Repon-liear a report-of practices of this advisory committee and requirements for the number and the Planning and Procedures the release of which would represent a distribution of operable incore Subcommittee mvolving matters related clearly unwarranted invasion of detectors. The incore detectors are to the status of appointment of new personal privacy per 5 U.S C. 552b(c)(2) required to verify that the core power members and organizationel and distribution is consistent with the safety and (6).
personnel matters relating to ACRS staff 57th ACMV Meeting, September 29- assumptions used in the safety analyses members. A portion of this session may 30,1993, Bethesda. MD. Agenda to be and to protect the current power be closed to public attendance pursuant ennounced. distribution TS limits. The proposed to 5 U.S.C. 552b(c)(2) and (6) to discuss ACMV Worbng Group on changes would elso apply penalties to organizetional and personnel matters Characteritation of the Unsatureted the values measured by the incore that relate solely to mternal personnel Sne Flc,w and Tmnspon Propenses detectors prior to their comparison with rules and practaces of ACRS and matters cacture vs. Mattir Flow, October 26 TS limits to assure that the TS limits ,
the release of which would represent a .993,las Vegas, NV.The Working monitored by the intere detectors will l clearly unwarranted mvasion of Group will examine the relationships continue to be valid. I personal pn.vecy. betweea precipitation, recharge, and Specif;cally, footnotes will be added. !
). Future ACRS Activitics-Discuss flut through the unsaturated zone at the to the following TS and will be topics proposed for consideration by the proposed Yucca Mountain site, and the applicable for only the remainder of the full Committee during future meetings. edequacy of ongoing field studies to Calvert Cliffs Nuclear Power Plant Unit K. Miscellaneous-Discuss ascertain these relationships. Emphasis 1. Operating Cycle 11, as follows:
miscellaneous matters related to the will be placed on the modeling cf flew TS 3.2.2.1. Total Plancr Radial conduct of Committee activities and in the unsaturated zone, alternative Peaking Factor, Limiting Condition for complete discussion of matters and conceptual models of fracture versus Operation (LCO), 3.2.3. Total Integrated specific issues that were not completed matrix flow, and conditions under Radial Peaking Factor LCO; and '
during previous meetings as time and which fracture flow can be shown to 4.2.1.4.b.1, Surveillar ce Requirements availability of information permit. predominate. The Working Group will for Incore Detector Monitoring System
- APPENDIX Il
,[ga uc%%, UNITED STATES y " ) y,7 ; NUCLEAR REGULATORY COMMISSION 5 t l
- ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o, 'f WASHINGTON, D. C 20555
~
Revised: July 28, 1993 SCHEDULE AND OUTLINE FOR DISCUSSION 400TH ACRS MEETING AUGUST 5-7, 1993 Thursday, August 5, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, KD 2
- 1) 8:30 - 8:45 A.M. #
0Denina Remarks by ACRS Chairman (Open)
! 1.1) Opening statement (JEW /SD) 1.2) Items of Current Interest (JEW /JTL) 1.3) Priorities for preparation of ACRS reports (JEW /SD)
- 2) 8:45 - 10:45 A.M. ,
Proposed Resolution of Generic Safety i Issue 57. " Effects of Fire ProtectiED System Actuation on Safety-Related Eauipment." and Lessons Learned from the LaSalle Fire PRA (Open) (IC/HA) 2.1) Remarks by the Subcommittee Chairman 2.2) Briefing by and discussions with rep-resentatives of the NRC staff regard-ing the proposed resolution of Gener-ic Safety Issue 57, and lessons learned from the LaSalle Fire PRA.
Representatives of the industry will
, participate, as appropriate.
II: CO IT M+4 5- - 11:00 A.M. BREAK G
- 3) 11:00 - 11:30 A.M. / Report on the Advanced Boilina Water Egactor (ABWR) Fire Safety Issues (Open)
(CM/HA/MDH) 3.1) Report of the ACRS Subcommittee on Advanced Boiling Water Reactors re-garding fire safety issues associated with the GE ABWR design. Representa-tives of the NRC staff will partici-
. . . ,s pate, as appropriate.
- 4) 11:30 - 1steS Noon Reconciliation of ACRS Comments and Recom-mendations (Open) (JEW, et al./SD) 4.1) Discussion of the responses from the NRC Executive Director for Operations i to comments and recommendations made !
in recent ACRS reports !
( = Te u:A ced padlon O Medung
t ,.
)
.a -
/
2 i 12:00 -
1:00 P.M. LUNCH 40 i
- 5) 1:00 -
2:}e P.M. Remainina Policy Issues for Passive-Plant:
Desians (Open) (CJW/MME) 5.1) Remarks by the Subcommittee Chairman 5.2) Briefing by and discussions.with j representatives of-the NRC. staff i regarding-the remaining policy issues-related to the passive plant designs.
Representatives of the industry will ;
participate, as appropriate. '
40
- 6) 2:}e -
3:30 P.M. Advanced Licht Water Reactor Policy Issue on ,
Emeroency Plannina (Open) (JEW / EGI) - .
6.1)
Remarks by the Subcommittee Chairman 6.2) Briefing by and discussions with. 1 representatives of the NRC staff ;
regarding the proposed policy-issue -i on emergency planning for Advanced Light Water Reactors 3:30 -
3:45 P.M. BREAK
- 7) 3:45 -
4:00 P.M. Prioritization of Generic Issues (Open)
(JEW /SD/DC) 7.1) Discussion of the proposed assign- ,
ments for reviewing the priority :
rankings proposed by the NRC staff for a group of generic issues.
5':50
- 8) 4:00 -
6tOO P.M. Precaration of ACRS ReDorts (Open) 3.1) Discussion of proposed ACRS reports on: ,
8.1-1) . Proposed resolution of Generic Safety Issue 57 (IC/HA) 8.1-2) Remaining Policy Issues on Passive Plant Designs !
(CJW/MME) t 8.1-3) Advanced Light Water Reactor "
Policy Issue on Emergency '
Planning (JEW /EGI) i 1
8 3
Friday, Aucust 6, 1993. Room P-110, 7920 Norfolk Avenue, Bethesda, MD
- 9) 8:30 -
8:35 A.M. 0penino Statement by ACRS Chairman (Open)
(JEW /SD)
Io
- 10) 8:35 - 10:44 A.M. ProDosed Resolution of Generic Issue 143, _
" Availability of Chilled Water Systems and Room Coolina" (Open) (IC/HA/PAB) 10.1) Remarks by Subcommittee Chairman 10.2) Briefing by and discussions with representatives of the NRC staff on the proposed resolution of Generic
,, Issue 143 10 L5 10:90 -
1 0 : 1-5 A . M . BREAK 25 2 S'
- 11) 10 : F5 -
11:&O A.M. Reoort of the Plannino and Procedurgg Subcommittee (Open/ Closed) (JEW /JTL) 11.1) Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, in-cluding matters related to the status of appointment of new members, and organizational and personnel matters relating to ACRS staff members gNote: A portion of this session may be closed to public attendance pursuant to 5 U.S.C. 552b(c)(2) and (6) to discuss organi-zational and personnel matters that relate solely to the personnel rules and practices of this advisory Committee and matters the
' release of which would represent a clearly unwarranted invasion of personal privacy.)
15- i 2. o s
- 12) 11:00 - LL&+& A.M. ACRS Subcommittee Activities (Open/ Closed) 12.1) Report on the Thermal Hydraulic Phe-nomena Subcommittee Meeting of July 22-23, 1993 (IC/PAB)
(Note: Portions of this session may be closed to discuss Proprietary Information related to this subject.)
12.2) Report on the Computers in Nuclear Power Plant Operations Meeting on July 21, 1993 (TSK/DC) 11.05- 1: 00 14++5 - 1+t45 P . M . LUNCH I: 00 5e
- 13) Eft 45 -
1:}U P.M. Future ACRS Activities (Open) (JEW /RPS) 13.1) Discussion of the recommendations of the Planning and Procedures Subcom-mittee regarding items proposed for
l 4 l consideration by the full Committee during future meetings
- 14) 1:}O -
Eres P.M. Precaration of ACRS Recorts (Open)
(3:00-3:15: Break) 14.1) Continue discussion of proposed ACRS Reports regarding matters considered during this meeting 14.1-1) Proposed resolution of Generic Safety Issue 57 (IC/HA) 14.1-2) Remaining Policy Issues on Passive Plant Designs (CJW/MME) 14.1-3) Advanced Light Water Reactor Policy Issue on Emergency Planning (JEW /EGI) 14.1-4) Proposed resolution of Generic Issue 143 (IC/HA/PAB)
- 15) 5tes -
4tes p.m. Miscellaneous (Open) 15.1) Discussion of matters considered during this meeting and matters con-sidered but not completed at previous meetings as time and availability of information permit.
n s enedsrq on Cca, u rds]
Saturday, August 7, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, MD
- 16) 8:30 - Close of Precaration of ACRS Reoorts (Open)
Business 16.1) Discussion of proposed ACRS reports regarding matters considered during this meeting NOTE: o Presentation time should not exceed 50 percent of the total time allocated for a specific item. The remaining 50 percent of the time is reserved for discussion.
e Number of copies of the presentation materials to be provided to the ACRS - 35.
,e
R. Borchardt NRR S. Boynton NRR Earl Brown AEOD Frank Brush RIII M. Case NRR T. Y. Chang RES F. Congel NRR D. Crutchfield NRR .
Mark Cunningham RES A. El-Bassioni NRR R. Erickson NRR John Flack RES E. F. Fox NRR Yi Gene Hsii NRR Wayne Johnson NRR R. Jones NRR F. Kantor NRR Janet Kennedy NRR !
William LeFave NRR e V. T. Leung RES Les R. Lupida AEOD N. Markisohn NRR Jerry Mazetis RES Conrad McCracken NRR J. Murphy RES Paul Norian RES J. OBrien NRR H. Pastis NRR E. Reis OGC Mark Rubin NRR '
Kris Shembarger OCM Mat Taylor EDO A. Thadani NRR ,
Roy Woods RES B. Zalcman NRR l
e
-, ,e-
- - ,. ,-- -- w..
7 Appendix III 2 400th ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIQ Alan Beard GE/NE Greg Brown Stone & Webster Philip Darling PNL Megs Hepler FEMA John Lambright SNL Chong Lewe NUS Jan MacGregor Winston & Strawn Candace Miller Stone & Webster Mike Neff GSA Alan Nelson NUMARC Anthony Pfeffer Serch Licensing Vern Wingeif FEMA Bob Youngblood BNL
'i i
1
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t .
APPENDIX IV ACRS FULL COMMITTEE AND SUBCOMMITTEE MEETINGS August 13, 1993 Advanced Boilina Water Reactors, September 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will discuss the status of resolution of the remain-ing open issuen in the ABWR Standard Safety Analysis Report and the resolution of USIs and GSIs. Also, it will discuss-the NRC staff's schedule for submittal of the Final Safety Evaluation Report. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of September 7:
Michelson HYATT Kress RESIDENCE Carroll HOLIDAY INN Lindblad HYATT Catton HYATT Scale HYATT Davis NONE Wylie HYATT Plannina and Procedures, September 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would repre-sent a clearly unwarranted invasion of personal privacy. Atten-dance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of September 7:
Wilkins HOLIDAY INN Carroll HOLIDAY INN Lindblad HYATT 401st ACRS Meeting, September 9-11, 1993, 7920 Norfolk Avenue, Bethesda, MD. During this meeting, the Committee plans to consider the following:
A. Proposed Rulemakina on the Fracture Touchness Recuirements for Reactor Pressure Vessel (RPV) - Revisions to 10 CFR 50.61. Appendix G and Accendix H. and a New Rule on Thermal Annealina (10 CFR 50.66) - Review and comment on the proposed rulemaking on the fracture toughness requirements for RPV for protection against pressurized thermal shock events. Also, review and comment on a new rule on thermal annealing of the RPV. Representatives of the NRC staff will participate. Representatives of the industry will participate, as appropriate. ,
^*
2 B. Proposed Priority Ranking of Generic Issues - Review and comment on the priority rankings proposed by the NRC staff for a number of generic issues. Representatives of the NRC staff will participate.
C. Proposed Generic Letter on Removal of Accelerated Testinc and Special Reportina Recuirements for Emercency Diesel Generators from Plant Technical Specifications - Review '
and comment on the proposed generic letter on removal of accelerated testing and special reporting requirements for emergency diesel generators from plant technical specifica-tions. Representatives of the NRC staff will participate.
Representatives of the industry will participate, as appropriate.
D. Proposed Guidelines for Dicital Instrumentation and Control '
(I&C) Systems Unarades - Review and comment on the guide-lines proposed by NUMARC for 10 CFR 50.59 evaluations of digital I&C systems upgrades. Representatives of the NRC staff and the industry will participate.
E. SECY-93-143, "NRC Staff Actions to Address the Recom-
- rendations in the Report on the Reassessment of the NRC Fire Protection Procram" - Hear a briefing by and hold -
discussions with representatives of the NRC staff regarding SECY-93-143. Representatives of the industry will partic-ipate, as appropriate.
F. Status of Individual Plant Examination (IPE) Procram - Hear a briefing by and hold discussions with representatives of the NRC staff on the status of the IPE Program, including how generic issues are addressed in the IPE program.
Representatives of the industry will participate, as appropriate.
G. Periodic Meetina Between the ACRS and the Commissioners - ]
Meet with the Commissioners to discuss matters of mutual interest.
- H . Insichts Gained frota Foreion Trios and U.S. Military Sources reaardina Diaital I&C Issues - Hear a briefing by and hold discussions with representatives of the NRC staff regarding insights gained by the staff from its interactions with i foreign regulatory authorities and nuclear utilities as
]
well as U.S. military sources on digital I&C issues. This session will be closed to discuss foreign proprietary information per 5 U.S.C. 552b(c) (4) and classified national .
security information per 5 U.S.C. 552b(c) (1) . !
- Open/ Closed i
g ,. , . - , - - y ,_ w --.
7
3 I. Resolution of ACRS Comments and Recommendations - Discuss responses from the'NRC Executive Director for Operations to recent ACRS comments and recommendations.
- J. Report of the Plannina and Procedures Subcommittee - Hear a report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business. A portion '
of this session may be closed to public attendance pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel-matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would represent a clearly unwarranted invasion of personal privacy.
K. ACRS Subcommittee Activities - Hear reports and hold discus-sions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Materials and Metallurgy, Mechanical Components, and Advanced Boiling Water Reactors.
L. Future Activities - Discuss anticipated and proposed Com-mittee activities, and organizational matters, as appro-priate. Also, discuss matters and specific issues that.
were not completed during previous meetings as time and availability of information permit.
Thermal Hydraulic Phenomena, September 20, 1993, Orecon State University (OSU). Corvallis. OR (Boehnert). The Subcommittee will tour the OSU test facility and observe an NRC/W meeting to discuss details of the OSU test program. Attendance by the following is anticipated, and reservations have been made at the Ramada Inn (telephone: 503-753-9151), 1550 N. West 9th Street, Corvallis, OR for the night of September 19:
Catton Dhir Davis Wulff Kress Zuber Lindblad !
Wilkins l
- Open/ Closed l
l l
1
i l
i l
4 Thermal Hydraulic Phenomena, September 21, 1993, Orecon State University (OSU), LaSalle Stewart Center. Corvallis, OR (Boehnert), 8:15 a.m. The Subcommittee will continue its review of the Westinghouse integral systems test programs supporting the AP600 design certification effort. The meeting discussion will focus on the OSU integral systems test facility program.
Attendance by_the following is anticipated, and reservations have been made at the Ramada Inn (telephone: 503-753-9151),
1550 N. West 9th Street, Corvallis, OR for the night of September 20:
5 Catton Dhir Davis Nulff Kress Zuber Lindblad Wilkins .
Severe Accidents, September 22-24, 1993, Sheraton Portland Airport Hotel, 8235 N.E. Airport Way, Portland, OR (Houston),
8:30 a.m., Room Columbian-D. The Subcommittee will continue its i review of the severe accident and PRA issues associated with the GE ABWR design certification effort. Attendance by the following is anticipated, and reservations have been made at the Sheraton Portland Airport Hotel (telephone: 503-281-2500) for the nights of September 21, 22, 23:
Kress Seale Catton Corradini (9/22 only)
Davis Dhir l Lindblad Kerr Miche' son Zuber Decay Heat Removal Systems, October 5, 1993, 7920 Norfolk Avenue, Bethesda. MD (Boehnert), time and location to be determined. The l Subcommittee will review the proposed rule to address resolution i of GSI-23 " Reactor Coolant Pump Seal Failure." Attendance by the following is anticipated, and reservations have been made at i F
the hotels as indicated for the night of October 4: j i
Catton HYATT Shack NONE Davis NONE Wilkins HYATT Kress RESIDENCE INN Ward NONE l i
4
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4 5
Mechanical Components, October 5, 1993, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. The Subcommittee will discuss the status of the ongoing NRC and industry activities associated with motor-operated valves, check valves, butterfly valves, and other related matters. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of October 4:
Michelson HYATT Carroll HOLIDAY INN
- Lindblad HYATT Wylie HYATT Improved Licht Water Reactors, October 6, 1993, 7920 Norfolk Avenue, Bethesda. MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will begin its review of the NRC staff's Safety Evaluation Report for the EPRI passive LWR Utility Requirements document. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of October 5:
Wylie HYATT Kress RESIDENCE INN Carroll HOLIDAY INN Lindblad HYATT Catton HYATT Michelson HYATT Davis NONE Seale HYATT Plannino and Procedures, October 6, 1993, 7920 Norfolk Avenue, Bethesda. MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6)'to discuss organizational and person-nel matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would repre-sent a clearly unwarranted invasion of personal privacy. Atten-dance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of October 5:
Wilkins HYATT Carroll HOLIDAY INN Lindblad HYATT 402nd ACRS Meetina, October 7-9, 1993, 7920 Norfolk Avenue, i Bethesda, MD , Room P-110.
{
t
.u . - . . . . . . - . . - . . . - .
- - ~..
. j 6 !
Advanced Boilina Water Reactors, October 2 -27, 1993, 7920 '
Norfolk Avenue, Bethesda. MD (El-Zeftawy), u:30 a.m., Room P-110.
The Subcommittee will begin its review of the NRC staff's Final Safety Evaluation Report for the GE ABWR design. Attendance by the following is anticipated, and reservations have been made at ,
the hotels as indicated for the nights of October 25 and 26: '
Michelson HYATT Kress HYATT Carroll HOLIDAY INN Lindblad HYATT Catton HYATT Scale HYATT Davis NONE Wylie HYATT Thernal Hydraulic Phenomena, October 28-29, 1993, 7920 Norfolk ,
Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room P-110. The-Subcommittee will review selected aspects of the NRC-RES-spon-sored ROSA-V confirmatory test program being conducted in support of the Westinghouse AP600 passive plant design certification effort. Specific review topics will include: - facility design ;
modifications and additions, the test matrix, and instrumentation and controls. Also, the Subcommittee will continue its review of the NRC RELAPS/ MOD 3 code. Attendance by the following is i anticipated, and reservations have been made at the hotels as ~
indicated for the nights of October 27 and 28:
Catton HYATT Dhir NONE Davis NONE Schrock NONE Kress RESIDENCE INN Wulff NONE Scale HYATT Zuber NONE Wilkins HOLIDAY INN ,
Ad Hoc Subcommittee on Desian Acceptance Criteria / Computers in Nuclear Power Plant Operations, November 2, 1993, 7920 Norfolk Avenue, Bethesda, MD (Coe/El-Zeftawy), 8:30 a.m., Room P-110.
The Subcommittees will review Chapter 7, "
Instrumentation and Control Systems" of the Standard Safety Analysis Report for l the ABWR design and associated Design Acceptance Criteria /
Inspections, Tests, Analyses, and Acceptance Criteria. ,
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of November 1:
Carroll HOLIDAY INN Wylie HYATT Lewis RESIDENCE INN Kemmerer NONE Catton HYATT Kerr NONE Davis NONE Place (SEI) NONE
. Michelson HYATT Wilkins HOLIDAY INN t-m*.e " - + e ersi------+w--e -e.-.pi.= e-+ cwa--m- w-=4 w- e- ++ g.er T-r-- T 1-- er *- r
s
. l 7
Safecuards and Security, November 3, 1993, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. .The Subcommittee will review the proposed SECY paper on Internal Threat ~and the Rulemaking Associated with Staff Recommendation for Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
Portions of this meeting may be closed to discuss safeguards information per 5 U.S.C. 552b(c) (3) . httendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of November 2:
Lewis RESIDENCE INN Lindblad HYATT Carroll HOLIDAY INN Micholson HYATT ,
Catton HYATT Wilkins HOLIDAY INN Davis NONE Wylie- HYATT Planninc and Procedures, November 3, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. .The Subcommittee will discuss proposed ACRS activities and'related matters. Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and person-nel matters <that relate solely to internal personnel rules and -
practices of ACRS and matters the release of which would repre-sent a clearly unwarranted invasion of personal privacy. Atten-dance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of November 2:
Wilkins HOLIDAY INN Carroll HOLIDAY INN ,
Lindblad HYATT t
403rd ACRS Meetina, November 4-6, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110.
Advanced Boilina Water Reactots, November 16-17, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will continue its review of the NRC staff's Final Safety Evaluation Report for the GE ABWR design.~
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the nights of November 15 and 16:
Michelson HYATT Kress RESIDENCE INN Carroll HOLIDAY INN Lindblad HYATT 4
Catton HYATT Seale HYATT Davis NONE Wylie HYATT h
-, - + . - .m.--- ,,, ,~.
P
- 8 ABB-CE Standard Plant Desians, December 8, 1993, 7920 Norfolk-Avenue, Bethesda, MD (Coe), 8:30 a.m., Room P-110. The Subcommittee will begin its review of the Standard Safety Analysis Report for the ABB-CE System 80+ design. Attendance by_the following is anticipated, and reservations have been made at the hotels as indicated for the night of December 7:
Carroll HOLIDAY INN Lindblad HYATT s Catton HYATT Michelson HYATT Davis NONE Seale HYATT Kress RESIDENCE INN Wylie HYATT Planninc and Procedures, December 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 4:00 p.m. - 6:00 p.m., Room P-422. The Subcommittee will discuss proposed ACRS' activities and related raatters . Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel matters that relate solely.to internal personnel-rules and practices of ACRS and matters the release of which '
would represent a clearly unwarranted invasion of personal !
privacy. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of December 7:
Wilkins HOLIDAY INN Carroll HOLIDAY INN Lindblad HYATT 404th ACRS Meetina, December 9-11, 1993, 7920 Norfolk Avenue, '
Bethesda, MD, Room P-110.
i Advanced Boilina Water Reactors, January 25-26, 1994, 7920-Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will review any residual issues a associated with the ABWR design and prepare a proposed ACRS report on ABWR issues for consideration by the full Committee. .
Lodging will be announced later. Attendance by the following is anticipated:
Michelson Kress Carroll Lindblad Catton Seale i Davis Wylie i
-r---- - . . - - -, , , - , -, .- , - - - , , ,--..,.-----.m.--- , - , - , . . . - - - - -
, i s
4 9
Joint Individual Plant Examinations / Severe bccidents (tentative), .
Date to be determined (October / November), Bethesda, MD (Houston).
.The Subcommittees will review the status and insights gained in regard to the Individual Plant Examination Program and Accident Management Guidelines. Attendance by the following is anticipat-ed:
Davis Michelson Kress Scale Catton Kerr Lindblad Ward !
paval Reactors, Date to be determined (November / December),
Crystal City, VA (Boehnert). Members of the ACRS will-tour.
the facility housing the exhibits /models related to the Naval ,
Reactors Programs. Attendance by the following is anticipated: i Lewis Michelson Catton'(tent) Scale >
Carroll Shack Davis Wilkins Kress Wylie
- Lindblad l
Severe Accidents, Date to be determined (November / December),
Bethesda, MD (Houston). The Subcommittee will discuss the ;
methodology developed and applied for assessing the effects of direct containment heating (DCH) at the Zion Nuclear Power Plant (NUREG/CR-6075). Attendance by the following '
is anticipated:
i Kress Lindblad -
Catton Michelson Davis Seale
- Consultants (TBD)
- Thermal Hydraulic Phenomena, Date to be determined (2-day meet-ing), San Jose, CA (Boehnert). The Subcommittee will continue ;
its review of both the GE analytical program (TRACG code) and I the experimental program supporting the certification effort j for the Simplified Boiling Water Reactor design. Attendance ,
by the following is anticipated: l l'
Catton Dhir Carroll Wulff Davis Zuber Kress l Seale Wi.1 kins
F e * .
6 APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE i
MEETING HANDOUTS AGENDA DOCUMENTS '
ITEM NO.
2 Proposed Resolution of Generic Safety Issue 57. " Effects of Fire Protection System Actuation on Safety-Related Eauipment."
and Lessons Learned from the LaSalle Fire PRA
- 1. Evaluation of Generic Issue 57: " Effects of Fire Protection System Actuation on Safety-Related Equipment,"
Presented by John A. Lambright, Sandia National Laboratories, dated August 5, 1993 [Viewgraphs]
- 2. Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk ;
Methods Integration and Evaluation Program (RMIEP),
Presented by John A. Lambright, dated August 5, 1993 ,
[Viewgraphs]
- 3. Proposed Resolution of Generic Issue 57, " Effects of Fire <
Protection System Actuation on Safety Related Equipment,"
Prepared by Roy Woods, RES, dated August 5, 1993
[Viewgraphs) 4 Reconciliation of ACRS Comments and Recommendations
- 4. Reconciliation of ACRS Comments and Recommendations
[ Handout No. 4.1]
i 5 Remainina Policy Issues for Passive Plant Desians
- 5. Regulatory Treatment of Non-Safety Systems in Passive ALWR Designs, dated August 5, 1993, prepared by Mark Rubin [Viewgraphs]
- 6. Regulatory Treatment of Non-Safety Systems for Passive LWRs, dated August 5, 1993, prepared by Nancy Markisohn, PDST [Viewgraphs]
6 Advanced Licht Water Reactor Policy Issue on Enercency Plannina
- 7. Emergency Planning Considerations in Licensing Under 10 CFR Part 52, dated August 5, 1993, prepared by Robert Erickson [Viewgraphs]
8 Preparation of ACRS Reports
- 8. Papers for the Quadripartite Meeting [ Handout No. 13.1]
- 9. Summary of ACRS Planning and Procedure Subcommittee Meeting on August 4, 1993 [ Official Use Only] :
10 Proposed Resolut;jpn of Generic Issue 143. " Availability of 1 Chilled Water Systems and Room Coolina" l
- 10. Generic Issue 143, " Availability of Chilled Water System l and Room Cooling," prepared by Vincent T. Leung,.RES, I undated [Viewgraphs) l l
i
e 1
' Appendix V 2 400th ACRS Meeting 11 Report of the Plannina and Procedures Subcommittee
- 11. Minutes of Planning and Procedures Subcommittee Meeting -
August 4, 1993 [ Handout No. 13.3]
12 ACRS Subcommittee Activities
- 12. Draft Minutes of the Thermal Hydraulic Phenomena Subcommittee meeting held on July 22-23, 1993
[ Proprietary Information]
13 Future ACRS Activities
- 13. Memorandum for ACRS Members from Richard Savio,-dated August 5, 1993, regarding future ACRS activities - 401st ACRS Meeting September 9-11, 1993, with enclosure
[ Handout No. 13.2]
MEETING NOTEBOOK CONTENTS TAB DOCUMENTS 2 Pronosed Resolution of Generic Safety Issue 57, " Effects of Fire Protection System Actuation on Safetv-Related Ecuipment,"
and Lessons Learned from the LaSalle Fire PRA
- 1. Status Report
- 2. Evaluation of Generic Issue 57: " Effects of Fire Protection System Actuation on Safety-Related Equipment,"
Presented by John A. Lambright, Sandia National Laboratories, dated July 28, 1993 [Viewgraphs]
- 3. Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP),
Presented by John A. Lambright, dated July 27, 1993 '
[Viewgraphs] :
3 Report on the Advanced Boilina Water Reactor (ABWR) Fire Safety Issues
- 4. Status Report
- 5. Fire Hazards Analysis, Prepared by Mohsen Nik-Ahd, GE Nuclear Energy, dated July 28, 1993 [Viewgraphs) 5 Remainina Policy Issues for Passive Plant Desians
- 6. Status Report-
- 7. SECY-90-016, dated January 12, 1990. regarding Evolutionary Light Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements
- 8. SECY-93-087, dated April 2, 1993, regarding Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs ,
- 9. Draft SECY, dated July 1993, regarding Policy and l l
l
I .-
4 Appendix V 3 400th ACRS Heeting Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs
- 10. ACRS Report to Chairman Carr, dated April 26, 1990, regarding Evolutionary Light Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements
- 11. Staff Requirements Memorandum, dated June 26, 1990, regarding SECY-90-016
- 12. ACRS Report to James Taylor, dated May 13, 1992, regarding Issues Pertaining to Evolutionary and Passivo Light Water Reactors and Their Relationship to Current Regulatory Requirements
- 13. ACRS Report to James Taylor, dated August 17, 1992, regarding Issues Pertaining to Evolutionary and Passive Light Water Reactors and Their Relationship to current Regulatory Requirements
- 14. ACRS Report to James Taylor, dated September 16, 1992, regarding Draft Commission Paper, " Design Certification and Licensing Policy Issues Pertaining to Passive and Evolutionary Advanced Light Water Reactor Designs"
- 15. ACRS Report to Chairman Selin, dated April 26, 1993, regarding SECY-93-087, " Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs"
- 16. Letter to Paul Shewmon from James Taylor, EDO, dated May 19, 1993, regarding SECY-93-087, with enclosures 6 Advanced Licht Water Reactor Policy Issue on Emeroenc_y Planning
- 17. Status Report
- 18. Memorandum for John Larkins from Frank Congel, NRR, dated June 14,1993, regarding Proposed Approach for Addressing Emergency Planning Under 10 CFR Part 52 (Draf t Commission Paper), with enclosures
- 19. SECY-93-087, dated April 2, 1993, regarding Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs
[pages 76-77]
7 Prioritization of Generic Issues
- 20. Memorandum for J. Ernest Wilkins, Jr. from Sam Duraiswamy, dated July 20, 1993, regarding Assignments for Reviewing Proposed Priority Rankings for Generic Safety Issues - Eighth Group, with attachments l 21. ACRS Letter to James M. Taylor, dated November 12, 1992, regarding Revised Guidelines for Prioritization of Generic Safety Issues l
J 4
.s (
)
g . - -
o Appendix V 4 400th ACRS Meeting 10 Proposed Resolution of Generic Issue 143. " Availability of Chilled Water Systems and Room Coolina"
- 22. Status Report
- 23. ACRS Letter to Victor Stello, dated October 15, 1987, regarding ACRS Comments on Nuclear Power Plant Air Cooling Systems
- 24. Memorandum for John Larkins from Warren Minners, dated July 8, 1993, regarding Resolution of GI-143,
" Availability of Chilled Water System and Room Cooling,"
with enclosures i