ML17310B142
| ML17310B142 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/02/1993 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| REF-GTECI-023, REF-GTECI-NI, TASK-023, TASK-23, TASK-OR ACRS-2905, NUDOCS 9403300125 | |
| Download: ML17310B142 (35) | |
Text
ACCELERATED I+TRIBUTION DEMONSATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR-94033'00125 DOC.DATE-93/12/02 NOTARIZED: NO FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi AUTH.NAME AUTHOR AFFILIATION ACRS Advisory Committee on Reactor Safeguards RECIP.NAME RECIPIENT AFFILIATION ACRS Advisory Committee on Reactor Safeguards DOCKET g
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05000529 NOTES:Standardized plant.
SUBJECT:
Summary of 402nd ACRS meeting on 931007-08 in Bethesda,MD re EPRI passive LWR requirements document, proposed resolution of GI-23, "RCP Seal Failure," severe accident/PRA issues for ABWR design 6
SG tube rupture event at PVNGS,Unit 2.
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11 I
I
TABLE OF CONTENTS MINUTES OF THE 402ND ACRS MEETING October 7-8, 1993 Pacae XI.
Chairman's Report EPRI Passive Light Water Reactor Requirements Document (Open)
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2 III.
Proposed Resolution of Generic Issue 23, "Reactor Coolant Pump Seal Failure" (Open) 3 IV.
Severe Accident/PRA Issues for the ABWR Design (Open}
6 V.
Steam Generator Tube Rupture (SGTR) Event at Palo Verde Nuclear Power Plant, Unit 2 (Open) 7 VI.
VII.
VIII.
X.
XX.
Proposed Final Amendments to 10 CFR Part 55 (Open)
Report of the Thermal Hydraulic Phenomena Subcommittee (Open)
Report on the NRC Digital Systems Reliability and Nuclear Safety Workshop, September 13-14, 1993, at Crown Plaza Hotel, Rockville, MD (Open}
Report on the Meeting of the Planning and Procedures Subcommittee Held on October 6,
1993 (Open}
Reconciliation of ACRS Comments and Recommendations (Open)
Executive Session (Open) 10 10 12 13 14 15 A.
B.
C.
- Reports, Memorandum and Letter Future ACRS Activities Future Meeting Agenda QQf) p
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APPENDICES I.
II.
III.
IV.
V.
Federal Register Notice Meeting Schedule and Outline Attendees Future Agenda and Subcommittee Activities List of Documents Provided to the Committee
Certified:
December 2,
1993 M NUTES OF THE 402ND MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS OCTOBER 7-8, 1993
- BETHESDA, MARYLAND The 402nd meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Maryland, on October 7-8, 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 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 ACRS Members:
Dr. J.
Ernest Wilkins, Jr.
(Chairman),
Mr. James Carroll (Vice-Chairman),
Mr. William Lindblad (Member-at-Large),
Dr. Ivan Catton, Mr. Peter Davis, Dr.
Thomas Kress, Mr. Carlyle Michelson, Dr. Robert Scale, Dr. William J.
- Shack, and Mr. Charles Wylie.
[For a list of other attendees, see Appendix III.]
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:
Region V of the Nuclear Regulatory Commission, located in Walnut Creek, California, will be closed.
Region V activities and resources will be transferred to Region IV in Arlington, Texas.
Mr. Mark Stella, Senior ACRS Fellow, will be leaving the NRC on October 15, 1993.
Dr. Wilkins acknowledged Mr.
Stella's very excellent counsel and reports to the members during his term.
On behalf of all the members, Dr. Wilkins expressed his appreciation for Mr. Stella's contributions.
The Committee agreed to provide a letter of appreciation to Mr. Stella.
402nd ACRS Meeting October 7-8, 1993
~
Professor Goren Dahlen, Chairman of the advisory commit-tee
- RSN, Swedish Nuclear Power Inspectorate, is sched-uled to meet with Dr. Wilkins in the ACRS office on November 3, 1993, to discuss generic issues, programma-ble equipment, and other issues of mutual interest.
II.
EPRI PASSIVE LIGHT WATER REACTOR RE UIREMENTS DOCUMENT (Open)
[Note:
Dr. Medhat El-Zeftawy was the Designated Federal Official for this portion of the meeting.]
Mr. Charlie Wylie, Chairman of the Improved Light Water Reactor (ILWR) Subcommittee, indicated that the subcommittee had met with the NRC staff and EPRI on October 6,
1993, to discuss the EPRI Utility Requirement Document (URD) for Passive LWRs and the associated NRC Safety Evaluation Report with emphasis on how the policy issues related to the passive nuclear power plant designs have been dealt with in the EPRI document.
He noted that the staff concludes that the EPRI URD does not conflict with the regulations, and that it should result in a nuclear plant which willhave all of the attributes required to ensure that there is no undue risk in the health or safety of the public or to the environment.
Mr. Wylie pointed out to the committee members similarities of the passive Utility. Requirement Document against the evolutionary plant.
He noted that 80 percent of it was covered, as identical with the requirements in the evolutionary'plant.
He further noted that the ACRS spent considerable time reviewing the evolutionary plant in preparation for its final report in August of last year, and so the passive document only contained those additional requirements for the passive features and thereby making this review much simpler.
Mr. Wylie stated that the IWLR Subcommittee agreed to prepare a
draft letter on the Volume 3 for consideration during the Novem-ber/December meetings and requested the members to send recommenda-tions to the ACRS staff engineer for inclusion in a proposed draft letter.
Conclusion The Committee agreed to provide input to the ACRS draft letter for discussion during the November/December full committee meeting.
402nd ACRS Meeting October 7-8, 1993 III. PROPOSED RESOLUTION OF GENERIC ISSUE 23 nREACTOR COOLANT PUMP SEAL FAILURE" (Open)
[Note:
Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr. Ivan Catton, Chairman of the Decay Heat Removal Systems (DHRS)
Subcommittee, introduced this matter to the Committee.
He noted that the NRC staff developed a proposed rule and draft regulatory guide for the resolution of Generic Issue 23 dealing with reactor coolant pump (RCP) seal failure.
Dr. Catton said that this is a long standing (was elevated to generic issue status in 1983) issue.
He said that presentations will be made by representatives of the NRC Office of Nuclear Regulatory Research (RES}
and Northeast Utilities.
He also directed the Committee's attention to a report from Mr. David Ward, ACRS consultant, on the DHRS Subcommittee meeting on October 5, 1993, to review this matter.
NRC Staff Presentation Mr. Robert Baer,
- RES, noted the following points:
RES has crafted a proposed rule and draft regulatory guide for resolution of GI-23.
The rule will apply to PWR licensees only and is performanced-based in approach in order to allow the affected licensees flexibilityin implementation of the rule's strictures.
The NRC staff's key safety concern is common cause loss of seal cooling (LOSC) coincident with loss of core cooling capability.
As such, the rule requires that affected licensees ensure RCP seal integrity during postulated events (station blackout, loss of component cooling water, service water} or, ensure emergency core cooling capability if seal integrity is loss.
Seal integrity can be demonstrated by either providing an alternate seal cooling capability or verification by test that seal integrity is maintained.
In response to Mr. Carroll, Mr. Baer said that the rule addresses LOSC for off-normal events only and that consideration of this issue for BWR nuclear power plants will be addressed via the generic issue priority process.
Mr. Jerry
- Jackson, RES, discussed the history and background~~,
associated with this issue.
He noted that'there are two types of seal systems used in PWR nuclear power plants, hydrostatic (used on W pumps) and hydrodynamic (used on the other PWR vendor pumps).
In addition, 0-ring elastomer material is used in the seal cartridges that is susceptible to failure upon exposure to high-temperature RCS water.
W is supposed to have developed elastomer material that
402nd ACRS Meeting October 7-8, 1993 is resistant to high temperatures; all affected licensees have not yet, however, made use of this new elastomer material.
For both seal types noted above, there exists the potential for the seal to pop open, with a subsequently large leak rate if the seal does not reseat.
This is the central concern of the RES staff regarding this issue.
During the discussion, it was noted that W
maintains that a pop-open event is incredible, but has not provided data to substantiate this claim.
Mr. Baer noted that such an event is of low-probability.
The staff discussed an event tree that was originally developed by W and used by the staff in the development of its estimation of the seal leakage rate given a LOSC event. It was noted that the worse-case leakage rate specified was 480 GPM/RCP.
The staff specified in the draft Regulatory Guide that licensees are to assume in their coping analyses the above worse-case leakage rate, for all four RCPs.
Mr. Prasad
- Kadambi, RES, noted the following points during his presentation:
In discussing some of the specific criteria cited in the draft Regulatory
- Guide, the staff indicated that it.
would be amenable to negotiation, subject to licensees providing information to justify their respective positions.
The staff's CDF estimate for a LOSC event (approximately 2.4 E-05) is fairly consistent with the mean CDF value for same seen in the IPE submittals received to date.
The staff estimates the cost for this fix at approxi-mately
$72.4M, or about
$1M/affected plant.
Dr. Catton opined that based on the Northeast Utilities presenta-tion on October 5, 1993, this estimate is probably low by a factor of 3 or 4.
Mr. Baer replied that the staff figure is based on the best information available to them and noted that some plants have already installed a backup RCP seal cooling system.
Mr. Carroll said that no licensee is going to elect the "seal test option" detailed in the draft Regulatory Guide, as the acceptance criteria are pegged to absolute worse-case conditions.
Mr. Kadambi said that this program is designed to ensure seal pop-open if its occurrence is possible.
Northeast Utilities Presentation Dr. Donald Dube, Northeast Utilities (NU), provided the following comments on the NRC staff's proposed rule for resolution of GI-23:
402nd ACRS Meeting October 7-8, 1993 I
Two major points:
many plant-specific design and opera-tional considerations are available to licensees to decrease the perceived risk significance of RCP seal failures; and, PWR licensee seal failure experience has been improving.
LOSC events have not resulted in multiple catastrophic seal failures as postulated in PRAs or NRC regulatory analyses.
NU has incorporated many hardware and procedural features into its PWR plants, largely in'response to the strictures of the station blackout (SBO) rule that effectively mitigate the LOSC event.
Of concern is the so-called "10-minute rule,"
specified in the draft Regulatory Guide, that requires that seal cooling be restored within 10 minutes of its loss.
Dr. Dube said that NU would need to make additional hardware modifica-tions to comply with this provision.
NU's LOSC experiences (three events) have not resulted in any gross leakage
- events, though for two of these events seal cooling was lost for a number of hours (5
and 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, respectively).
For CE plants, there have been a
number of LOSC events, some lasting hours with no observed gross leakage.
During discussion of this matter, Dr. Dube referenced a
CE Owners Group Topical Report (CEN-408) that he said contains a compilation of LOSC experience for all CE plants.
This report was submitted to the staff in September 1991.
In response to a Committee inquirer, Mr. Bear said that they had not seen this report.
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Estimates of costs for addressing resolution of GI-23 range in the order of
$3-5+M/plant is considerably higher than the staff cost estimate of approximately
$1M/plant.
The test option in the proposed rule is not viable because the industry is being asked to "prove the negative."
Likewise, the "10-minute rule" cited above will severely impact almost all the coping analyses'erformed in accordance with the SBO Rule.
Comments b
the Nuclear Mana ement and Resources Council NUMARC Re resentative Mr. A. Marion, NUMARC, noted the following points:
~
Based on the discussion, Mr. Marion plans to contact the affected Owners Groups and ensure that all information relevant to this issue has been made available to the NRC staff.
402nd ACRS Meeting October 7-8, 1993 Conclusion The SBO Rule was resolved based on a deterministic approach.
Resolution of B-56 ('ZDG Reliability) is being pursued on a performance-based approach.
NUMARC hopes that resolution of GI-23 can be handled in the same manner as was that for B-56.
However, the current rule version seems to, in effect, mandate a hardware fix (installation of backup seal cooling).
Adoption of the RCP seal leakage rate suggested in the draft Regulatory Guide (480 GPM/RCP) will result in licensees having to reevaluate their coping analyses performed to resolve station blackout.
The Committee indicated that it was dissatisfied with the proposed rule package, in part, given the need for additional dialogue between the NRC and industry on this matter.
A report to the EDO was issued that recommends that the proposed rule and draft regulatory guide not. be issued for public comment in their present form IV.
SEVERE ACCIDENT PRA ISSUES FOR THE ABWR DESIGN (Open)
[Note:
Mr. Dean Houston was the Designated Federal Official for this portion of the meeting.]
Dr.
Thomas Kress, Chairman of the Severe Accidents Subcommittee/
indicated that the subcommittee met with General Electric Nuclear Energy (GE) on September 22-24,
- 1993, in Portland,
- Oregon, to discuss severe accident and PRA issues associated with the GE ABWR design certification review.
He noted that these matters would be discussed with the NRC staff at an ABWR Subcommittee meeting on October 26-27,
- 1993, when the Supplemental Safety Evaluation Reports (SSER) on Chapter 19 of the ABWR SSAR are available.
Ms. Carol Buchholz, GE, discussed the ABWR PRA and severe accident analysis.
In regard to the ABWR PRA, she discussed the following topics:
Probabilistic Methodology Level 1/ core damage frequency (CDF) analysis including internal initiators, internal floods, fires and seismic events Shutdown assessment Level 2/ severe accident analysis Ms. Buchholz indicated that the CDF from internal initiators was calculated to be 1.6E-07/RY and that the main contributor was station blackout (71%).
402nd ACRS Meeting October 7-8, 1993 Ms. Buchholz also discussed the ABWR design features important for accident mitigation. These are as follows:
Pressure suppression containment Containment isolation Drywell-wetwell vacuum breakers Reliable vessel depressurization Containment inerted with nitrogen Lower drywell (cavity) configuration and flooder Fire water addition system Containment overpressure protection system (COPS)
She described the layout and functioning of the AC independent water addition (fire water),
the lower drywell flooder, and the COPS in detail.
In regard to severe accident
- issues, Ms.
Buchholz discussed how specific severe accident issues are modelled in the Modular Accident Analysis Program (MAAP) code and how various codes (TRACG, SAFER and MAAP) are used in the analysis.
The following MAAP models were discussed:
thermal-hydraulic, HEATUP for core melting, core relocation, hydrogen generation, core-concrete interactions, fuel coolant interaction (FCI),
fission product release and transport, and direct containment heating (DCH).
During this discussion, the NRC staff agreed to provide a copy of an analysis performed for the ABWR ex-vessel FCI using the TEXAS-II code.
Ms. Buchholz concluded her presentation with a discussion of how the ABWR satisfies all of the containment performance goals (CCFP, Large
- Release, Individual Risk, and Societal Risk) by a large margin.
She also showed how the ABWR compared to the NUREG-1150 plants in respect to CDF and Individual Risks.
Conclusion This was an information briefing only.
The Committee did not take any action on this matter at this meeting.
The Committee will take the information under consideration for action after hearing the NRC staff's presentation on the SSERs later in October or November.
V.
STEAM GENERATOR TUBE RUPTURE SGTR EVENT AT PALO VERDE NUCLEAR POWER PLANT UNIT 2 (Open)
[Note:
Mr. Douglas Coe was the Designated""-Federal Official for this portion of the meeting.]
Mr. James Carroll, Chairman of the Plant Operations Subcommittee, introduced this topic by noting that the Committee was interested in both the operator response to this event as well as the causes behind the steam generator tube degradation that caused the event.
402nd ACRS Meeting October 7-8, 1993 NRC Staff Presentation Mr. Alfred Chaffee,
- Chief, Events Assessment
- Branch, NRR, intro-duced the three presenters for this briefing:
Mr. Dennis Kirsch, Augmented Inspection Team (AIT) Team Leader, Region V; Mr. James
- Reese, Chief, Facilities Radiological Protection Branch, Region V; Mr. Ken Karwoski, Materials and Chemical Engineering Branch, NRR; and Mr. Jim Wiggins, Director, Division of Engineering, NRR.
Mr. Kirsch described the sequence of events that occurred on March 14, 1993 at Palo Verde Nuclear Power
- Plant, Unit 2,
and the findings of the AIT.
He made the following major points:
The AIT concluded that the Emergency Operating Procedures (EOPs) were flawed in that they required a radiation monitor to be in alarm at the time a specific EOP step was performed in order to begin the portion of the EOPs designed for a SGTR.
Although one of these monitors had previously alarmed and was continuing to read abnormally high, the alarm had cleared and this led operators to remain in the more general section of the EOPs.
Ultimately, this had the effect of delaying the cooldown and depressurization of the plant, which was needed to stop the primary-to-secondary leakage.
- However, the AIT concluded that the licensee at no time was in danger of releasing activity off-site or of causing a danger to the public.
The radiation monitor alarm setpoints associated with the most likely alarms following a SGTR were set inappropriately high, resulting in no alarms present at the time the EOP step to check for radiation alarms was performed, further resulting in the above described problem.
The evaluation of two NRC Information Notices should have led the licensee to reset the alarm setpoints, but did not.
In addition, simulator training for STGRs led operators to expect that any radiation alarms would remain in alarm throughout the event.
The licensee declared an Alert following this event.
- However, the licensee should have declared a Site Area Emergency (SAE) per their Emergency Plan Implementing Procedures (EPIP), based on the magnitude of the initial primary leak rate.
Therefore, the AIT considered an Alert declaration as the most appropriate classification, even though it was less conservative than the licensee's EPIPs.
Mr.
Reese discussed the licensee's leak rate determination methodologies and related problems.
He made the following major points:
402nd ACRS Meeting October 7-8, 1993 The licensee's reactor coolant system activity was extremely low, relative to the values assumed in the FSAR for a SGTR.
This results in minimal offsite radiological consequences, but made leak rate determinations based on radionuclide analysis of the secondary coolant very difficult.
The licensee's method of choice for leak rate determination was to sample for tritium in the secondary coolant because tritium was the only radionuclide they were detecting.
The problem with this method was that the equation used to compute leak rate assumed a constant buildup of tritium into the steam generator.
When equilibrium was reached (accounting for tritium losses equal to gains), the equation would give false results.
The next method of choice, analysis of the secondary coolant for radioactive iodine, did not account for dilution or hideout of iodine due to the steam generator flow and chemistry characteristics.
- Finally, the third method of
- choice, condenser off-gas radiation monitor readings, was found to be incorrectly low by a factor of six due to monitor deficiencies.
The licensee's procedures did not specify a
hierarchy of methods or any requirement to verify one method with another.
Mr. Karwoski discussed the root cause of failure for the Palo Verde Unit 2 STGR.
He made the following major points:
The ruptured tube had a 2.5 inch fishmouth axial opening and was the result of intergranular attack or intergranular stress corrosion cracking (IGA/IGSCC).
The conditions for IGA/IGSCC were enhanced by bowing of tubes that narrowed the tube-to-tube
- gap, the presence of film boiling and an alkaline environment in the upper tube bundle region, and the presence of reduced sulfur from condensate demineralizers.
These conditions allowed the formation of chemical contamination deposits which in some cases bridged the narrow gap between tubes.
The staff has allowed continued operation of Palo Verde Unit 2 for six months based upon its evaluation of the risk associated with operating with degraded tubes and taking account of licensee actions such as improved primary-to-secondary leakage detection, lower leak rate limits, improved EOPs and training, reduced overpower reactor trip setpoint, and a reduced primary coolant iodine limit.
- However, the staff did not agree with the license'e"'that Regulatory Guide'.121 margins for tube leakage under design basis accident conditions (maximum analyzed pressure differential) would be met at the end of six months.
The licensee will perform additional eddy current examinations of steam generator tubes following this six month operating period.
402nd ACRS Meeting October 7-8, 1993 10 Mr. Wiggins stated that the licensee is currently in an outage at Unit 1 and is performing extensive steam generator tube inspec-
- tions, as well as re-evaluating the eddy current testing'esults from the most recent Unit 3
outage.
The staff hopes to gain additional insights from these efforts.
He also discussed the history of steam generator tube inspection criteria (voltage-based interim plugging criteria) and the staff's ongoing evaluation of possible alternate methods of specifying tube degradation limits, including defect-specific
- limits, and performance based limits which would depend on the extent of compensatory actions.
He stated that rulemaking is anticipated in this area.
Mr. Carroll noted that the EOPs had been significantly revised only a few months prior to this event and that the NRC's review of the new EOPs had missed the above weakness.
Mr. Carroll asked if the licensee had considered the impact of the ratio of various chemical species in the steam generator which may be below the individual concentration limits.
Mr. Karwoski replied that the licensee had instituted a multi-ratio chemistry control program to maintain specified chemical ratios within limits.
Mr.
Davis asked if there were any indications of tube-to-tube physical contact or interaction.
Mr. Karwoski replied that there were none.
Dr.
Shack asked if the wearing of steam generator tubes due to fretting with tube supports is generic to all Palo Verde units.
Mr. Wiggins stated that it was generic to all CE steam generators but that it did not play any role in the Palo Verde SGTR.
Conclusion No Committee actions were taken as a result of this information briefing.
VI.
PROPOSED FINAL AMENDMENTS TO 10 CFR PART 55 (Open)
[Note:
Mr. Herman Alderman was the Designated Federal Official for this portion of the meeting.]
Dr. Sher Bahadur, Chief, Regulation Development Branch, Office of Nuclear Regulatory Research (RES),
discussed the status of the proposed final Amendments to 10 CFR Part 55.
The review package has received concurrence from the RES and the Office of Nuclear Reactor Regulation (NRR).
The projected plan is to have the Committee To Review Generic Requirements (CRGR) review the proposed final rule during the first week in November.
402nd ACRS Meeting October 7-8, 1993 Public Comments Dr.
Bahadur said that the first amendment is to delete the requirement that the NRC should administer a comprehensive written examination for any qualification test.
Of the 42 public comments
- received, 36 comments were in favor of deleting this requirement.
Most of the comments came from the nuclear power plant licensees.
Those in favor of the deletion thought that it would reduce the regulatory burden and would improve the operational safety at the facilities.
Those in opposition thought that the facilities would not be able to monitor whether their programs were satisfactory.
Dr. Wilkins asked if the NRC staff reserved the right to look at the licensees'xamination procedures and examinations and to judge whether they are likely to be satisfactory?
Dr. Bahadur said that the answer was yes, and he would discuss this when he talked about the second proposed amendment.
Dr. Bahadur pointed out that the NRC staff had been duplicating the testing efforts of the nuclear reactor facilities.
He noted that the pass rates for operator licenses had increased from 80 percent to 90 percent.
For these
- reasons, the staff suggested to the Commission that rulemaking should be initiated to relieve the NRC staff of the responsibility for overseeing the operator testing.
Mr. Carroll expressed his concern regarding his belief that the staff had changed its position regarding supervision of operator requalification subsequent to the October 1992 ACRS presentation, and did not inform the ACRS of this change.
Dr. Bahadur said the early proposals specified that the NRC staff would conduct periodic requalification examinations, but the current. proposed amendments have eliminated that requirement.
Dr. Bahadur said that the second proposed amendment would require the NRC licensees to submit examination materials to the NRC 30 days prior to the administration of the examination.
The supposi-tion was that, with the examination in hand, the NRC inspectors would be better prepared to conduct their inspection.
Following resolution of the public comments, it was decided to change the amendment to read that the examinations would be submitted upon request.
Ins ection Pro rams Mr. Robert Gallo, NRR, said that they have"'completed nine pilot'nspections, and several more inspections have been accomplished on regional initiatives.
He noted that the inspections will coincide with the facility annual operating test. If there are programmatic deficiencies, a more detailed evaluation may be conducted.
Under the Part 55 Rule, the NRC can still conduct requalification exams for cause.
In general, a "for cause" examination will be conducted
402nd ACRS Meeting October 7-8, 1993 12 based upon poor SALP ratings or a general belief that the requalif-ication program has become ineffective.
Im lementation Schedule The current schedule calls for a CRGR review and submittal to the EDO by the end of October.
If the CRGR review is late, then the schedule willslip.
The staff plans to publish these amendments in mid-or late December depending on the Commission review.
Conclusion The Committee provided a report on this matter dated September 16, 1993, to James M. Taylor, Executive Director for Operations.
VII. REPORT OF THE THERMAL HYDRAULIC PHENOMENA SUBCOMMITTEE (Open)
[Note:
Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr.
- Catton, Chairman of the Thermal Hydraulic Phenomena Sub-committee, reported on the results of the meeting held on September 21, 1993.
The meeting was held on the campus of Oregon State University (OSU), located in Corvallis, Oregon.
The Subcommittee met to continue its review of the Westinghouse-sponsored AP600 integral facility test program that is being conducted at OSU.
On September'20, 1993, members of the Subcommittee and representatives of the NRC staff toured the OSU facility.
Dr. Catton indicated that the Subcommittee was'impressed with both the test facility and the supporting analyses conducted largely by OSU faculty members (Dr. J. Reyes, et. al.).
Overall, the program appears to be sound.
Dr. Catton also indicated that the Committee is scheduled to be briefed during its November meeting on the entire W test program being conducted in support of design certification effort for the AP600 passive plant.
Conclusion This briefing was for information only.
No action was taken by the Committee.
VIII.
REPORT ON THE NRC DIGITAL SYSTEMS RELIABILITYAND NUCLEAR SAFETY WORKSHOP SEPTEMBER 13-14 1993 AT CROWN PLAZA HOTEL ROCKVILLE MD (Open)
[Note:
Mr. Douglas Coe was the Designated.
Federal Official for this portion of the meeting.]
402nd ACRS Meeting October 7-8, 1993 13 Mr. Bill Lindblad, member of ACRS Subcommittee on Computers in Nuclear Power Plant Operations, reported to the Committee on the subject workshop in lieu of the cognizant Subcommittee chairman who was not present.
Mr. Lindblad stated that the workshop was orga-nized more like a professional society topical session than an actual working level workshop.
He observed that the speakers were knowledgeable in areas related to software design and reliability, but in most cases they did not provide direct insights into the issues that confront the NRC and the nuclear industry.
This point was also noted by some audience members at the end of the workshop.
One of the two objectives of the workshop was to provide expert feedback to the NRC staff on their proposed digital systems review guidelines.
Additionally, the staff hoped to receive feedback on whether it was addressing the correct issues in the correct manner.
Mr. Lindblad noted that neither of these objectives were fulfilled by the presentations given.
Other ACRS members who attended the workshop and were present for Mr. Lindblad's report were Mr. Wylie, and Mr. Michelson, who concurred with Mr. Lindblad's assessment.
Conclusion This briefing was for information only.
No action was taken by the Committee.
IX.
REPORT ON THE MEETING OF THE PLANNING AND PROCEDURES SUBCOM-MITTEE HELD ON OCTOBER 6
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 October 6,
- 1993, the following items were brought to the attention of the Committee:
The Committee discussed the need to establish a policy for sponsoring members and consultants to attend meet-ings other than ACRS meetings.
Mr. Lindblad reported that there have been no abuses of this policy.
The number of sponsored meetings attended by different members varied greatly.
The Committee concluded that a detailed written policy does not need to be developed,
- however, members should advise the staff as to whaQ, outside meetings they plan to "attend so that this information can be approved by the Planning and Proce-dures Subcommittee and by the full Committee.
A list of future meetings to be attended by members will be included in a monthly "future meeting report" to provide a paper trail.
402nd ACRS Meeting October 7-8, 1993 14 The Committee discussed a draft Manual Chapter that defines the policy, objectives, and responsibilities to implement and operate the ACRS/ACNW Fellowship Program.
Dr.
Larkins recommended that members submit their comments to him during the next few weeks.
Dr. Wilkins expects to brief Chairman Selin on the status of the Fellowship Program in the near future.
The Committee discussed a memorandum to Ivan Catton from Brian Sheron, Director, Division of Systems
- Research, dated September 27, 1993, regarding a planned meeting of the Thermal Hydraulic Phenomena Subcommittee.
The Committee deferred to Ivan Catton for the formulation of a response, if deemed necessary.
Dr. Larkins briefed the members on the ACRS staff's meeting with the Technical Assistants from the Chairman's office and others to discuss the ACRS/ACNW budget.
Dr. Wilkins noted that election of new officers (Chair-man, Vice-Chairman, and Member-at-Large to the Planning and Procedures Subcommittee) will be scheduled during the December meeting.
He requested that members advise Dr.
- Larkins, in writing, of their inclination (or disinclination) to be considered for nomination.
Dr. Wilkins recommended that the staff begin soliciting candidates for Committee membership in 1994.
Specifi-cally, he requested that a press release be submitted to professional publications.
The members discussed a
suggestion by Dr.
Scale to consider the level of safety oversight being provided to university training and research reactors as compared to power reactors.
The Committee agreed that it was not an issue that needed attention by ACRS now.
X.
RECONCILlATION 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 previous ACRS reports were discussed as follows:
EDO letter, dated September 11, 1993, responding to the ACRS report dated August 11, 1993, concerning ACRS Com-ments on the Proposed Resolution of Generic Issue 57,
402nd ACRS Meeting October 7-8, 1993 15 "Effects of Fire Protection System Actuation on Safety-Related Equipment" Conclusion The above EDO letter satisfactorily addressed the Committee's comments.
EDO letter, dated September 22, 1993, responding to the ACRS report dated August 11,
- 1993, concerning ACRS Comments on Proposed Resolution of Generic Issue
- 143, "Availabilityof Chilled Water System and Room Cooling" Conclusion The Committee agreed that any further outstanding questions on its part should be submitted to the NRC staff (in detail) during the Individual Plant Exami-nations Subcommittee meeting scheduled for November 18, 1993.
XI. EXECUTIVE SESSION 'Open)
[Note:
Dr. John Larkins was the Designated Federal Official for this portion of, the meeting.]
A.
Reports and Memorandum Pro osed Rule and Draft Re ulator Guide to Address Resolution of Generic Issue 23
>>Reactor Coolant Pum Seal Failure" (Re-port to James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr.,
ACRS Chairman, dated October 14, 1993)
Pro osed Final Amendments to 10 CFR Part 55 on Renewal of Licenses and Re alification Re irements for Licensed 2!
Jr.,
ACRS Chairman, dated October 14, 1993)
Pro osed Final Rule on Modifications to Fitness-for-Dut Pro ram Re uirements (Memorandum to Frank J.
Congel, Direc-tor, Division of Radiation Safety and Safeguards, NRR, from John T. Larkins, Executive Director, ACRS, dated October 15,,
1993.)
Consistent with the Committee 's'decision, Dr. Larkins informed Mr. Congel that the Committee decided not to review the proposed final rule on modifications to the Fitness-for-Duty Program requirements concerning the random drug testing rate.
The Committee has no objection to the staff's proposal for issuing these modifications to the rule.
402nd ACRS Meeting October 7-8, 1993 16 B.
Future ACRS Activities The Committee agreed to postpone the review of the proposed supplement to Generic Letter 86-10 on Fire Endurance Testing until the 404th ACRS meeting.
The members requested that the background material on this issue be re-sent to them.
During the discussion on the planned briefing on the NRC technical training program, Mr. Michelson requested that all AEOD reports be sent to the Committee members.
Mr.
Peter Davis requested a copy of an in-house AEOD report on the Diesel Generator Testing Program.
Dr.
Wilkins requested that the members review the proposed schedule for ACRS full committee meetings in CY 1994.
Comments should be given to Dr.
Savio or Mr.
Duraiswamy.
The 1994 meeting schedule willbe completed during the November meeting.
The Committee agreed to schedule the 405th ACRS meeting on January 6-8, 1994.
The OECD/NEA and the NRC are sponsoring a conference on the results of the TMI-2 Vessel Investigation Project on October 20-22, 1993.
The Committee endorsed Dr. Lind-blad's request to attend and participate in this confer-ence.
Dr.
Catton suggested that the Committee explore the details of the analyses required according to the stric-tures of the PTS Rule, in light of the actions surround-ing the shutdown of'the Yankee Rowe Nuclear Power Plant.
The focus of these discussions should be on the specif-ics of the thermal hydraulic phenomena analyses.
It was suggested that a joint meeting of the Thermal Hydraulics Phenomena, Materials and Metallurgy, and PRA Subcommit-tees be
- held, subject to availability of time and resources.
C.
Future Meeting Agenda Appendix IV summarizes the proposed items endorsed by the Committee for the 403rd ACRS Meeting, November 4-6,
- 1993, and future Subcommittee meetings.
The 402nd October 8, ACRS meeting was adjourned at 3:25 p.m.
on Friday, 1993.
'APPENDIX I J
~
Federal Register / Vol. 58,'No.;183 / "thursday, September 23, 1993 /'Notices
'"'9531 ADDRESSES: Setid comments to Mr.
Steve Semenuk, Office ofManagement and Budget, New Executive Office Building, 726 Jackson Place. NW.. room 3002, Washington, DC 20503; (202-395-7316). In addition, copies ofsuch comments may be sent to Ms. Judith E.
O'rien, National Endowment for the Arts, Administrative Services Division, room 203, 1100 Pennsylvania Avenue.
NW., IVashington, DC 20506; (202-682-5401).
FOR FURTHER INFORMATIONCONTACT: Ms.
, Judith E. O'rien. National Endowment for the Arts, Administrative Services Division, room 203, 1100 Pennsylvania Avenue, NW., Washington, DC 20506; (202-682-5401).
SUPPLEMENTARY INFORMATION:The Endowment requests the review of a revision ofa currently approved collection of information. This entry is issued by the Endowment and contains the followinginformation:
(1) The title ofthe form; (2) how often the required information must be reported; (3) who willbo required or asked to report; (4) what the form will be used for; (5) an estimate ofthe number ofresponses; (6) the average burden hours per response; (7) an estimate of the total number ofhours needed to prepare the form. This entry is not subject to 44 U.S.C. 3504(h).
Title:
FY 95/96 Expansion Arts Program Application Guidelines.
Frequency ofCollection One-time.
Respondents: Non-profit organizations and state and local governments.
Use: Guideline instructions and applications elicit relevant information from non-profit organizations and state and local arts agencies that apply in the Expansion Arts Program. This information is necessary for the accurate, fair and thorough consideration ofcompeting proposals in the review process.
Estimated Number ofRespondents:
566.
Average Burden Hours Per Response:
17.
Total Estimated Burdent 9,622.
Judith F O'rien, Management Analyst, Administrative Services Division, National Endowment for the Arts.
(FR Doc. 93-23279 Filed 9-22-93; 8:45 aml tui.usa coos Tsorwim Agency Information Collection Activities Under OMB Review AGENCY:National Endowment for the Arts, NFAH.
ACTION:Notice.
SUMMARY
- The National Endowment for the Arts (NEA) has sent to the Oflice of Management and Budget (OMB) a request for expedited clearance, by October 19, 1993, ofthe following proposal for the'collection of information under the provisions of the Paperwork Reduction Act (44 U.S.C.
chapter 35).
DATES: Comments on this information collection must be submitted by October 13, 1993.
ADDRESSES: Send comments to Mr.
Steve Semenuk. Office ofManagement and Budget, New Executive Oflice Building, 726 Jackson Place, NW.;room 3002, Washington, DC 20503;(2020395-7316). In addition, copies of such comments may be sent to Ms. Judith E.
O'rien. National Endowment for the Arts. Administrative Services Division, room 203, 1100 Pennsylvania Avenue, NW., Washington DC 20506; (202) 682-5401).
FOR FURTHER INFORMATIONCONTACT:
Ms. Judith E. O'rien, National Endowment for the Arts, Administrative Services Division. room 203, 1100 Pennsylvania Avenue, hW., IVashington DC 20506'(202-682-5401).
SUPPLEMENTARY INFORMATION:The Endowment requests the review of a revision ofa currently approved collection ofinformation. This envy is issued by the Endowment and contains the followinginformation:
(1) The title ofthe form; (2) how often the required information must be reported: (3) who willbe required or asked to report; (4) what the form will be used for; (5) an estiniate of the number ofresponses; (6) the average burden hours per response; (7) an estimate ofthe total number of hours needed to prepare the form. This entry is not subject to 44 U.S.C. 3504(h).
Title:
FY 95 Design Arts Program Application Guidelines.
Frequency ofCollection: One-time.
Respondents: Individuals, state or local governments, non-proflt organizations.
Use: Guideline instructions and applications elicit relevant information from individual design artists, non-profitorganizations and state and local arts agencies that apply in the Design Arts Program. This information is necessary for the accurate. fair and thorough consideration ofcompeting proposals in the review process.
Estimated Number ofRespondents:
650.
Average Burden Hours Per Response:
20.
Total Estimated Burden: 12,737.
'udith E. O'rien, Management Analyst, Administrative Services Division, National Endawmeri%r the A'its.
lFR Doc. 93-23280 Filed 9-22-93; 8:45 aml iuLUNO coos TSSMI1M NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) and Advisory Committee on Nuclear Waste (ACNW);
Proposed Meetings In order to provide advance information regarding proposed public meetings of the ACRS Subcommittees and meetings of the ACRS full Committee, of the ACNW, and the ACNWWorking Groups the following preliminary schedule is published to tefle'ct the current situation. taldng into account additional meetings that have been scheduled and meetings that have been postponed or cancelled since the last list ofproposed meetings was published August 18, 1993 (58 FR 43918). Those meetings that are firmly scheduled have had, or willhave, an individual notice published in the Federal Register approximately 15 days (or more) prior to the meeting. It is expected that sessions ofACRS and ACNWfullCommittee meetings designated by an asterisk ( ) willbe closed in whole or in 'part to the public.
The ACRS and ACNW fullCommittee meetings begin at 8:30 a.m. and the ACRS Subcommittee and ACNW Working Group meetings usually begin at 8:30 a.m. the time when items listed on the agenda willbe discussed during ACRS and ACNWfullCommittee meetings, and when ACRS Subcommittee and ACNW Working Group meetings willstart willbe published prior to each meeting.
Information as to whether a meeting has been firmly,scheduled. cancelled, or rescheduled, or whether changes have been made in the agenda for the October 1993 ACRS and ACNWfullCommittee meetings can be obtained by a prepaid telephone call to the Office of the Executive Director of the Committees (telephone: 301/492M600'(recording) or 301/492-7288, AttnBarbara Jo White) between 7:30 a.m. and 4:15 p.m.. (EDT).
ACRS Subcommittee Meetings Mechanical Components,'ctober 5.
1993, Bethesda, MD.The Subcommittee willdiscuss the status of the ongoing NRC and industry activities associated with moto~perated valves, check
. 49532 Feckral Register / Uo,.No-183 / Thursday,'September 23,
/ Notices valves. butterfly valves. and other related matters.
~yHeal Removal Systems, October 3, BeQiesda. MD(1260 p~). The
.ommittee will.review the proposed rule to address resolution ofGeneric Safety Issue-23, "Reactor Coolant Pump Seal Failure."
Improved Light Water Reactors, October 6. 1993, Bethesda, MD. The Subcommittee willbegin its review of the NRC staffs Safety Evaluation Report for the Electric Power Research Institute (EPRI) passive LWRUtility Requirements document.
Planning and Procedures, October 6, 1993, Bethesda, MD (2 p.m.-4:30 p.m.).
The Subcommittee willdiscuss proposed ACRS activities and related matters. Portions ofthis 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 rolease ofwhich would represent a clearly unwarranted invasion ofpersonal privacy.
Advanced Bailing Water Beactors, October 26-27, 1993, Bethesda, MD.
The Subcommittee willbegin its review ofthe NRC staffs Final Safety Evaluation Report for the GE ABWR design.
Yhenna/ Hydmulic Phenomena, ber 28, 1993. Bethesda, MD. The ommittee willreview selected
~.~acts ofthe NRC-IuS-sponsored ROSA-V confirmatory test program being conducted in support ofthe Westinghouse AP600 passive plant design certification effort. Specific review topics willinclude: Facility design modifications and additions, the test matrix, and instrumentation and controls. Also. the Subcommittee will discuss the status ofthe RES contract with Purdue University to perform integral thermal-hydraulic testing in support ofthe GE SBWR passive plant des igll.
Ad Hoc Subcommittee on Design Acceptance Critena/Compu terin Nuclear Power Plant Operations, November 2, 1993, Bethesda, MD.The Subcommittees willreview Chapter 7, "Instrumentation and Control Systems" ofthe Standard Safety Analysis Report for the ABWRdesign and associated Design Acceptance Criteria/Inspection, Tests, Analyses, and Acceptance Criteria.
Safeguards and Security, November 3.
1993, Bethesda, MD.The Subconunittee willreview the proposed SECY pa r
'nternal Threat and the Rul ciated with Staff Recommendation rotection Against Malevolent Use of Vehicles at Nudear Power Plants and Safeguards requirements forthe Advanced Boiling%Voter Reactors.-
Portions ofthis meeting may be closed to discusssafeguards information pursuant to 5 US.C. 552b(c)(3).
~
Planning amf Procedures, November
- 3. 1993, Bethesda, MD(2 P.m;4:30 p.m.). The Subcommittee willdiscuss proposed ACRS activities and related matters. Portions ofthis 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 ofwhich would represent a dearly unwananted invasion ofpersonal privacy.
Advanced Boiling Water Reactors; November 16-17, 1993, Bethesda, MD.
The Subcommittee willcontinue its review ofthe NRC stafFs Final Safety Evaluation Report for the GE ABWR design.
Individual Plant Examinations, November 18, 1993, (tentative),
Bethesda. MD.Tho Subcommittee will review the status ofand insights gained with regard to tho Individual Plant Examination Program and how generic issues are resolved by use oftho results ofthis Program.
ABB-CEStandard Plant Designs, December 8, 1993, Bethesda, MD. The Subcoinmittee willbegin Its review of the Standard Safety Analysis Report for the ABB-CE System 80+ design.
Planning and Procedures, December 8, 1993, Bethesda, MD(4 pm;6 p.m.).
The Subcommittee willdiscuss proposed ACRS activities and related matters. Portions ofthis 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 ofwhich would represent a dearly unwananted invasion ofpersonal privacy.
Advanced Boiling Water Reactors, January 25-26. 1994, Bethesda, MD.The Subcommittee willreview any residual issues associated with the ABWRdesign and prepare a proposed ACRS report on ABWR issues forconsideration by the fullCommittee.
ACRS Full Committee Meetings 402nd ACBS Meeting, October 7-8, 1993, Bethesda, MD.During this meeting, the Committee plans to consider the following:
A. Proposed Resolution ofGeneric Issue-28, "Reactor Coolant Pump Seal Failure"Review and comment on the proposed rule to address the resolution ofGeneric Issue-23. Representatives of the NRC staff willparticipate.
Representatives ofthe industry will participate, as appropriate.
B. EPRI Passive I.WRRequirements DocumentReview and comment on the NRC staffs Safety Evaluation Report forthe EPRI UtilityRequirements Document forpassive I.WRs.
Representatives o'fthe NRC staff and industry willparticipate.
C. Resolution.of Generic Issue 67.5.1,
Reassessment ofSGTR Radiological Conseguences" Review and comment on the proposed resolution ofGeneric
~
Issue 67.5.1 that addresses the validity ofpresent techniques to calculate offsite radioactive dose releases from a design basis steam generator tube rupture.
Representatives ofthe NRC staff will participate.
D. Proposed Final Amendments to 10 CFB Part 55Review and comment on the proposed final amendments to 10 CFR part 55 regarding renewal of license and requdification requirements for licensed operators. Representatives of the NRC staff willparticipate.
Representatives of the industry will participate, as appropriate.
E Seizure Accident/PRA Issues forthe ABWBDesignHear presentations by and hold discussions with representatives ofthe NRC staff and GE on the severe accident/PRA issues for the ABNR design. Develop comments and recommendations for inclusion in the find ACRS report on the final design approval for tho ABWR F. Ins.'ghts Gained from the NRC Staff Reassessment ofthe Fire Protection Program (tentative)Hear a briefing by and hold discussions with representatives ofthe NRC staff on the lessons learned from the stafFs recent reassesanent ofthe fire protection program.
G. St~ Generator Tube Bupture Event at Palo Verde Unit2Hoar a briefing by and hold discussions with representatives ofthe NRC staff regarding the issues arising from the steain generator tube rupture event that occuned at Palo Verde Unit 2 on March
- 14. 1993. Representatives ofthe industry willparticipate, as appropriate.
H. Resolution ofACRS Comments and Recommendations Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and reautunendations.
- i. Report ofthe Planning and Procedures Subcommittee Hear a report ofthe Planning and Procedures Subcommittee on matters related to the conduct ofACRS business.
J. ACBS Subcommittee Activities Hear reports and hold discussions regarding the status ofACRS subcommittee activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena, and
Bedew'egister Z Val. 58. No. II83 X..VhttzsdaySeptember
'23, 4'993 4 W06oes Computers inNuclear Power'Plant Operations.
K.kuture ActivitiesDiscuss anticipated,and imposed Committoe activities, and organizational matters. as appropriate.
L Miscellaneous
'Discuss matters and speciflc issues that moro ziot completed during pzev'ious meetings as time and availability ofinformation permit.
403rd ACRSMeeting, November 4-6, 1993, Bethesda, MD.Agenda to ba announced.
404th ACRS Meeting, December 9-11, 1993. Bethesda, MD.Agenda to'be aiiil0ullca cL 405th ACRS Meeting,.January 6-8, 1994, Bethesda, MD. Agenda to be announced.
ACÃWFu11 Committee Meetings 57th ACNWMeeting,.September 29-
- 30. 1993, Bethesda, MD. During this meeting, the Committee plans to consider the following:
A. ConGnue discussions ofmatters related to implementation plans. for futum ACNWactivities, including preparation ofreports on ACNE protocols, topics forreview, and zesource zequiz'emcnts.
B. Continue discussion ofmatters mlated to the appointment ofnew niembers, and organizational and personnel matters zalatcd to the ACNW Members and ACNWstaff. Portions 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 mlate solely to internal personnel zuics and practices of ACNWand matters the release ofwhich would represent a clearly unwarranted invasion of personal privacy.
C. Discuss topics proposed for consideration during future ACNW meetings.
58th ACNWMeeting, October 27-28, 1993, Residence Inn,Ias Vegas, KV.
During this meeting, the Committee plans to consider the following:
A. Continuo discussions ofmatters rolated to implementation plans for future ACNWactivities, including preparation ofzeports on ACNW protocols, topics for1aview, and resource requirements.
B. Pa&cipate 1n a technical exchange withtepzescntatives ofthe Department ofEnergy's Yucca Mountain.Site Characterization Pmject Office.
C. Continue discussion af matters related tothe appointment afziew members. anB ogganizational and pezsonnel mattczs zelated to&e ACNW Members and ACNWstaK 4'ortions of this session znay be closed to pubTic attendance pursuant to 5 US.C. 552b(d)
(2) and t(6}to discuss organizational.and pcrsozmci matters that relate solely to internal personnel cules and practices of ACNWainB znatters gabe zelease ofwhich would represent a c)carly unwarranted invasion efpersonal privacy.
D. Discuss topics proposed for consideration during future ACNW meetings.
59th ACNWMeeling.I4ovembcr 15-
~16, 1993, Holiday Inn. Bethesda, MD.
Agenda to be announced.
40th ACNWMeeting, December 15-16, 1993, Bethesda, MD.Agenda to.be anno uncocL ACNWWorking Group Meetings Characterizati on ofthe Unsaturated Zone Flow and Transpor Properties, November 18, 1993. One White Flint North, Bethesda, MD. The Working Group willexanune the relationships between precipitation, <<echarge, and fluxthrough the unsaturated zone at the proposed Yucca Mountain site, and the adequacy ofongoing Geld studies to ascoztain these relationships. Emphasis willbe placed on the modeling of flow in the unsaturated zone, alternative conceptual modelsof tincture versus matrix flow,and condidons under which fractuze flowcan be shown to predominate. The Working Group will also focus on the recharge term in hydrogeologic models, alternative conceptual models forhow and where zegional recharge occurs. and the effect ofassumptions about recharge on model zesli its.
Low-Level Radioacth v Waste Performance Assessmen.'. December 14.
1993,3ethesda, MD.The Working Group willreview the overall low-level waste performance assessment program.
with emphasis on the s'atus of the draft Branch Technical Position. and staff s performance assessment capability.
Issues tobe exammed mclude ongoing and planned activities. milestones and schedules, results ofongoing test case analyses. and tale ofglRC staff in evaluating Agreement States'erformance aissessment programs.
NRC StaffCapabilitiesin Perfonnance Assessment and Computer Modeling of High-Level Waste Disposal Facilities, December %7. 1993. Bethesda, MD.The ACNWwillrevisit this subject, which was discussed in an October 17,'1991 WorkingGroup Meeting. Progress inthe NRC9%tezative Performance Assessment (PA) Pmgram, &e NRC staffs compIetion ofan~ elicitation exercise,mzB made in the execution of e NRCsmodular computer model willbe subjects of interest to tho Committee. This review wfllbe yerIonneB qedncBcally to determine the degree ofin-house and contractor-supported PAcapabilzty, the coordination and integration'between data analyst and computer modelers, revisions to the High-Level Radioactive Waste Management PA Strategy Plan',
and'future plans forPAdevelopment.
'Dated: September 17. 1993.
John C. Hoyle, AdvisoryCommittee ManagementOffiaar.
lFR Doc. 93-23297 Filed 9-'22-93; a:45 aml POSTAL RATECO@MISSION (Dockot No. A93-17J Notice and Orders,ccepting Appeal and Establishing Procedural Schedule Under 39 UD.C.404(b)(5)
Before Commissioners: George IV. Haley.
Chairman; John W. Crutcher: W.H."Trey-LeBlanc.1II; H. Edward Quick, Jr.: Wayne A.
Schley.
In the Moner ofMorrison, Iowa 50657 Oessie Cooley, at al., Petltlonezs).
Issued: Scptemher17,1993.
Docket Number: A93-17.
Name ofAffected Post Ogglcei Morrison. Iowa 50657.
Name(s) of'etitioner(s): jessie Cooley and othe'.
Type ofDeterminationi Consolidation.
Dateof FilingofAppeal Papers:
September 8, 1993.
Categories ofIssues Apparentl>
Raised:
- 1. Effect on postal services (39 U.S.C.
404(b)(2)(C)).
- 2. Effect on the community (39 U.S.C.
404(b)(2)(A)).
- 3. Economic savmgs (39 U.S.C.
404(b)(2)(D)).
Other legal issues may be disclosed by the record when itis filed; or, conversely, the determination made by the Postal Service may be. found to dispose ofone or more ofthes issues.
In the interest ofexpedition. in light of the 1204ay decision schedule (39 U.S.C. 404(b)(5)), the. Commission reserves. the right to request ofthe Posiai Service memoranda oflaw on any appropriate Issue. Jfrequested. such memoranda willbe Bue 20 Bays I'mm the issuance ofthe request;a copy. shall bo served on the. petitioners. Ina brief or motion to dismiss. oraffirm, the Postal Service may incorporate by reference any such memoranda previously Iliad.
The Caznzzassian ozzfers:.
'(A)Xbeaicordinthisappeal shall be filed onarbefoze September 23, 1993.
(B) The Seczetaryshall publish this Notioe anBChderand Procedural Schedule in the Federal Register.
gp R 4ECy~
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APPENDIX II UNITEDSTATES NUCLEAR REGULATORY COMMlSSION ADVISORYCOMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 Revised:
October 6,
1993 SCHEDULE AND OUTLXNE FOR DXSCUSSXON 402ND ACRS MEETING October 7-8, 1993 Thursda October 7
1993 Room P-110 7920 Norfo1k Avenue Bethesda MD.
1) 8-30 8:45 A-M.
0 enin
- 1. 1) 1.2) 1.3)
Remarks b
ACRS Chairman (Open)
Opening statement (JEW/SD)
Xtems of Current Interest (JEW/JTL)
Priorities for preparation of ACRS reports (JEW/SD) 25')
8:45 9:34 A.M.
TAB 2 EPRX Passive LWR Re uirements Document (Open)
(CJW/MME/JM) 2.1)
Remarks by the Subcommittee Chairman 1S 6) 9:~
9: 30 A.M.
5) 9: 30 M".~ A. M.
4 II '. O0 12) 10:00
~~i A.M.
lo:oo M".~
M~ A.M.
Reconciliation of ACRS Comments and Recom-mendations (Open)
(JEW, et al./SD) 6.1}
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations made in recent ACRS reports Arran ements for Multilateral Meetin (Open)
(JEW/JTL) 5.1)
Discussion of arrangements for multilateral meeting Future ACRS Activities (Open}
(JEW/RPS) 12.1)
Discussion of the recommendations of the Planning and Procedures Subcom-mittee regarding items proposed for consideration by the full Committee during future meetings Break (Note:
Numbering out of order to coordinate with tabs in Meeting Books)
Io 3) ll:00 12:66 Neea TAB 3----------
Io 12:88 1:00 P M.
lZ 3) 1:00 2:S9 P M.
Pro osed Resolution of Generic Issue 23 "Reactor Coolant Pum Seal Failure" (Open)
(IC/PAB) 3.1)
Remarks by the Subcommittee Chairman 3.2)
Briefing by and discussions with representatives of the NRC staff.
regarding the proposed rule to address the resolution of Generic Issue 23.
Representatives of the industry will participate, as appropriate.
LUNCH Continue Discussion of the Pro osed Resolution of Generic Issue 23 "Reactor 4) l5 30 2: &6 5:6& P.M.
(~-~: Break) 2.:9s -3: td g 30 -g)STAB Coolant Pum Seal Failure" (Open)
(IC/PAB)
Severe Accident PRA Issues for the ABWR Desicen (Open)
(TSK/MDH) 4.1)
Remarks by the Subcommittee Chairman 4.2)
Briefing by and discussions with representatives of GE on the severe accident/PRA issues for the ABWR design.
Representatives of the NRC staff will participate, as appropriate.
45 l5 7) 598
6 &&P M.
Proposed resolution of Generic Issue 23 (IC/PAB)
Pre aration of ACRS re orts (Open) 7.1)
Discussion of Proposed ACRS report on:
- 7. 1-1)
Frida October 8
1993 Room P-110 7920 Norfolk Avenue Bethesda MD 8) 8:30
8 35 A.M.
2.$
9) 8:35 10: M A.M.
TAB 9----------
0 enin Remarks b
'the'CRS Chairman (Open)
(JEW/SD)
Steam Generator Tube Ru ture Event at, Palo Verde Unit 2 (Open)
(JCC/DC) 9.1)
Remarks by the Subcommittee Chairman 9.2)
Briefing by and discussions with representatives of the NRC staff regarding the issues arising from the steam generator tube rupture event that occurred at Palo Verde, Unit 2 on March 14, 1993 Representatives of the industry will participate, as appropriate
Break 10) 10:B6 ll:30 A.M.
TAB 10-----------
pro osed Final Amendments to 10 CFR Part 55 (Open)
(JCC/HA) 10.1)
Remarks by the Subcommittee Chairman 10.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed final amend-ments to 10 CFR Part 55 related to renewal of license and requalifica-tion requirements for licensed operators.
Representatives of the industry will participate, as appro-priate 11) 11:30 12:30 P.M.
Re ort of the Plannin and Procedures Sub-committee (Open/Closed)
(JEW/JTL) 11.1)
Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business and organizational and personnel matters relating to ACRS staff members (Note:
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 internal personnel rule" and practices of this advisory Committee and matters the release of which would represent a clearly unwarranted invasion of personal privacy.)
12: 30 1 30 PM.
LUNCH 3:25 13) 1:30
~ P.M.
(3: 00-3: 15: Break)
Pre aration of ACRS Re orts (Open) 13.1)
Discussion of proposed ACRS reports on:
13.1-1)
Proposed resolution of Generic Issue 23 (IC/PAB) 13.1-2)
Proposed Final Amendments to'. 10 CFR Part 55 (JCC/HA)
ACRS Subcommittee Activities (Open/Closed) 14.1)
Report on Thermal Hydraulic Phenomena (Open/Closed)(IC/PAB)
(Note:
Portions of this session may be closed to discuss Proprietary Information related to Westinghouse AP600 test programs.)
14.2)
Computers in Nuclear Power Plant Operations (WJL/DC) 15) 5:00 6:00 P.M.
Miscellaneous (Open) 15.1)
Discussion of matters considered during this meeting and matters considered but not completed at previous meetings as time and availability of information permit.
NOTE:
~
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.
~
Number of copies of the presentation materials to be provided to the ACRS - 35.
APPENDIX III MEETING ATTENDEES 402ND ACRS MEETING OCTOBER 7-8, 1993 NRC STAFF Raj Auluck Robert Baer Sher Bahadur Rich Barrett R. Borchardt Tom Boyce Rex Brown Al Chaffee J. L. Coldwell J.
F. Collins Joe Donoghue G. Galletti R.
M. Gallo E. Goodwin Herman Graves Francis Grubelich Brad Hardin Brian Holian Jerry Jackson Robert Jones N. P.
Kadambi K. Karwoski D. F. Kirsch T. Koshy Bill LaFave Seung Lee Chu-yu Liang John Manninger Bob Palla H. Pastis Gennard Pisanti Chet Poslusny Jim Reese M. Rubin Will Swenson Mat Taylor A. Thadani Cecil Thomas Linh Tran J.
T. Wiggins Jerry Wilson RES RES RES NRR/DSSA/SCSB NRR/ADAR NRR/ADAR/PDST NRR NRR/D NRR NRR NRR/SRXB NRR/DRCH NRR NRR/DORS RES NRR/DIE/EMEB RES NRR/PD5 RES/DSIR/EIB NRR/SRXR RES/DSIR/EIB NRR/DE RV/IV NRR/DORS NRR/DSSA/SPLB NRR/DE/EGGB NRR/DSSA/SPLB NRR/DSSA/SCSB NRR/DSSA/SPSB NRR/ADAR/PDST NRR/ADAR/PDST RV NRR/SPSB NRR OEDO NRR NRR NRR/PD5 NRR/DE NRR/ADAR/PDST
Appendix III 402nd ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC Hector Barbeito Margo Barron Michael Bausler J. Alan Beard Richard A. Bernier Charles B. Brinkman Carol Buchholz Mike Chesk Donald Dube Robert C. Evans Norman Fletcher Sterling Franks Stephen Madaras A. Marion Everett P. Perkins Anthony Pfeffer Jim Raleigh C. Ruger Morris Schrem Hiroaki Yasui Bechtel SERCH Licensing NUS LIS N&H GE Nuclear Energy Arizona Public Service Co.
ABB-CE GE Nuclear Energy NUS Northeast Utilities NUMARC DOE/ALWR DOE SERCH Licensing Bechtel NUMARC Northeast Utilities SERCH Licensing Bechtel Southern Technical Services, BNL NUMARC Tokyo Electric Power Co.
APPENDIX IV:
FUTURE AGENDA A.
- B
- C ~
D.
E.
F.
G'.
- H.
PRA Workin Grou Final Re ort Review and comment on the proposed PRA Working Group Final Report and an associated Commission paper.
Representatives of the NRC staff will participate.
Revised Securit Re uirements Review and comment on the proposed Commission paper on Internal Threat, SECY-93-270, "Proposed Amendments to 10 CFR Part 73 to Protect Against Malevolent Use of Vehicles at Nuclear Power Plants,"
and safeguards and security requirements for the GE ABWR design.
A portion of this session may be closed to discuss safeguards and security information
[5 U.S.C 552b(c)(3)].
Repre-sentatives of the NRC staff will participate.
NRC-RES ROSA AP600 Confirmator Test Pro ram
Review and comment on the adequacy of the proposed text matrix and modifications and additions to the ROSA test facilityprior to initiation of the RES test program in support of the AP600 design certification review.
A portion of this session may be closed to discuss material deemed proprietary by the Westinghouse Electric Corporation
[5 U.S.C.
552b(c)(4)].
Representatives of the NRC staff will participate.
Prea lication Safet Evaluation Re ort PSER for the PRISM Desicen Review and comment on the NRC staff's draft PSER for the PRISM liquid-metal-cooled reactor design.
Representatives of the NRC staff will participate.
Instrumentation and Control S stems and Certified Desi n
Material for the ABWR Desi n
Review and comment on Chapter 7,
"Instrumentation and Control Systems,"
of the Standard Safety Analysis Report for the ABWR design and Certified Design Material (Tier 1) for the Instrumentation and Control
- Systems, Human
- Factors, Radiation Protection, and Piping Design.
Representatives of the NRC staff and GE will participate.
Re ulator Treatment of Non-Safet S stems Review and comment on the draft Commission paper that includes proposed NRC staff positions on issues related to the regulatory treatment of non-safety systems.
Representatives of the NRC staff will participate.
Technical Trainin Pro rams
Hear a briefing by and hold discussions with representatives of the NRC's Office for Analysis and Evaluation of Operational Data (AEOD) on the technical training programs being developed by AEOD for the Technical Training Center in Chattanooga, Tennessee.
Westin house Anal tical and E
erimental Pro rams Related to the AP600 Passive Plant Desi n Certification Hear briefings by and hold discussions with representatives of the Westinghouse Electric Corporation and the NRC staff regarding the Westinghouse analytical and experimental programs related to the AP600 passive plant design certification effort.
A portion of this session may be closed to discuss information deemed proprietary by the Westinghouse Electric Corporation [5 U.S.C. 552b(c)(4)).
Appendix IV 402nd ACRS Meeting K.
L.
M.
Resolution of ACRS Comments and Recommendations
Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
Re ort of the Plannin 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 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.
ACRS Subcommittee Activities
Hear a report and hold a
discussion regarding the activities of the Advanced Boiling Water Reactors Subcommittee.
Future Activities
Discuss topics proposed for consideration by the full Committee during future meetings.
Miscellaneous Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of matters and specific issues that were not completed during previous
- meetings, as time and availability of information permit.
APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE MEETING HANDOUTS AGENDA ITEM NO.
DOCUMENTS 1
0 enin Remarks b
ACRS Chairman 1.
Memorandum for ACRS members from Dean
- Houston, dated October 5, 1993, regarding Paper by David Ward, "Stories,
- Rules, and Reg Guides,"
September 28,
- 1993, with enclosure 2
EPRI Passive LWR Re uirements Document 2
~
EPRI Passive LWR UtilityRequirements
- Document, (URD) by J. Wilson,
- NRR, and J.
Devine, Jr.,
EPRI [Handout g2-1)
Final Safety Evaluation Report for EPRI ALWR Requirements Document for Passive Plant Designs Passive Plant Utility Requirements Document Overview ALWR Policy Issues for Passive Plant Designs 3
Pro osed Resolution of Generic Issue 23 "Reactor Coolant Pum Seal Failure" 4
5.
6.
7.
Report to Ivan Catton, Chairman of DHRS Subcommittee, from David Ward, ACRS Consultant, dated October 6, 1993, regarding GI-23, "RCP Seal Failure"
[Handout g3-1]
Presentation Schedule:
Resolution of GI-23, RCP Seal Failure by Paul Boehnert
[Handout g3-2]
Predecisional draft for 10 CFR 50.66, undated [Official Use Only]
Generic Issue 23 "Reactor Coolant Pump Seal Failure" Presentation to the ACRS by Engineering Issues
- Branch, dated October 7, 1993
[Viewgraphs]
A Utility Perspective on GI-23, "Reactor Coolant Pump Seal Failures,"
by Donald A. Dube, Northeast Utilities, dated October 7, 1993
[Viewgraphs]
Severe Accident PRA Issues for the ABWR Desi n
8.
Member and Consultant Reports from the Severe Accident Subcommittee Meeting held in Portland, OR, September 22-24, 1993
[Handout g4-1]
[Official Use Only]
9.
Review of ABWR PRA and Severe Accident Analysis by C.E.
- Buchholz, dated October 7,
1993
[Viewgraphs]
Appendix V 402nd ACRS Meeting 6
Reconciliation of ACRS Comments and Recommendations 10.
Reconciliation of ACRS Comments and Recommendations by S.
Duraiswamy
[Handout k6-1]
9 Steam Generator Tube Ru ture Event at Palo Verde Unit 2 11.
ACRS Presentation on Steam Generator Tube Rupture at Palo Verde Unit 2, dated October 8, 1993 10 Pro osed Final Amendments to 10 CFR Part 55 12.
Proposed Final Amendments to 10 CFR Part 55 [Handout g10-1]
11 Re ort of the Plannin and Procedures Subcommittee 13 14.
15.
Minutes of Planning and Procedures Subcommittee Meeting, October 6, 1993, Prepared by Michael MacWilliams [Handout Ill-1]
Draft ACRS/ACNW Fellowship Program Directive, dated October 7, 1993 Memorandum for Ivan Catton from Brian W.
- Sheron, RES, dated September 27,
- 1993, regarding Forthcoming Subcommittee Meeting, with enclosure 12 Future ACRS Activities 16.
17.
18.
Future ACRS Activities by R.
P. Savio
[Handout f12-1]
Letter to Steven C. Sholly, MHB Technical Associates, from Edward L. Jordan, AEOD, regarding Insights from Common-Cause Failure Events Advanced Information Management System for the Advisory Committee on Reactor Safeguards and Advisory Committee on Nuclear
- Waste, dated October 7,
- 1993, Presentation to Commissioner Rogers and Remick [Viewgraphs]
14 ACRS Subcommittee Activities 19.
Report on Digital Workshop, September 13-14, 1993, by Dr.
- Kerr, Chad Little, and Douglas Coe
[Handout gl4-1]
Appendix V 402nd ACRS Meeting MEETING NOTEBOOK CONTENTS TAB DOCUMENTS 2
EPRI Passive LWR Re uirements Document 1 ~
2.
3.
4 5.
Table of Contents Tentative Agenda Status
- Report, dated October 7, 1993 SECY-93-087, dated April 2,
- 1993, regarding
- Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR)
Designs Draft
- SECY, undated, regarding Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs Pro osed Resolution of Generic Issue 23 "Reactor Coolant Pum Seal Failure" 6.
7.
8.
9.
Table of Contents Project Status
- Report, dated October 7,
1993 [Official Use Only]
Memorandum for ACRS members from Steve
- Mays, dated September 14, 1993, regarding Generic Issue 23, Reactor Coolant Pump Seal Failure Memorandum for J.
Ernest Wilkins, Jr.
from C.
J.
- Heltemes, Jr.,
dated August 3,
- 1993, transmitting Proposed Rule for GI-23, Reactor Coolant Pump Seal
- Failure, with enclosures (Official Use Only Predecisional) 4 Severe Accident PRA Issues for the ABWR Desi n
10.
11.
12.
13.
14.
15.
16.
17.
Table of Contents Tentative Agenda Status
- Report, dated October 7-8, 1993 Selected Sections of Chapter 19, ABWR SSAR, Amendment,31 Handout on ABWR Severe Accident Review from the Severe Accidents Subcommittee Meeting on September 22-24, 1993 Handout on ABWR Containment Performance from the Severe Accidents Subcommittee Meeting on September 22-24, 1993 Handout on ABWR PRA Methodology from the Severe Accidents Subcommittee Meeting on September 24, 1993 GE ABWR Response to USI A-45, Shutdown Decay Heat Removal Requirements
Appendix V 402nd ACRS Meeting 9
Steam Generator Tube Ru ture Event at Palo Verde Unit 2 18 19
'0.
21.
Table of Contents Agenda Project Status
- Report, dated October 8, 1993 Letter to Mr.
W.
F.
- Conway, Arizona Public Service
- Company, from J.
B. Martin, NRC Regional Administrator, dated April 16, 1993, regarding NRC Xnspection Report 50-529/93-14, with enclosure 10 Pro osed Final Amendments to 10 CFR Part 55 22
'3.
24.
25.
26.
Table of Contents Tentative Agenda Status
- Report, dated October 8, 1993 Draft 10 CFR Part 55, RZN-AE 39, Operators'icenses, undated ACRS report to James M. Taylor, dated October 19,
- 1992, regarding Proposed Amendments to 10 CFR Part 55 on Renewal of Nuclear Power Plant Operator Licenses and Requalification