ML20059C832

Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3

ML20059C832
Person / Time
Site:	Salem, Indian Point
Issue date:	07/21/1993
From:	Wilkins J Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2882, NUDOCS 9311020030
Download: ML20059C832 (41)

Text

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[. W h D/L lo/Afh.3 Certified By: $ 'J l f j .p te Issued: 06/29/93 J. Ernest Wilkins, 07/21/93 g

TABLE OF CONTENTS MINUTES OF THE 398TH ACRS MEETING June 10-11, 1993 I. Chairman's Report . . . . . . . . . . . . . . . . 1 II. SECY-93-113, Additional Implementation Information for 10 CFR Part 54, " Requirements for Renewal of Operating Licenses for Nuclear Power Plants" (Open) . . . . . . . . . . . . . . 2 III. Public Comments on Advanced Light-Water Reactor Severe Accident Plant Performance (Open) 3 IV. SECY-93-067, " Final Policy Statement on Technical Specifications Improvements" (open) . . . 4 V. Reactor Operating Experience (Open) . . . . . . . 6 VI. Risk-Based Regulation (Open) . . . . . . . . . . . 9 VII. Unauthorized Forced Entry at Three Mile Island Nuclear Power Plant Unit 1 (Open) . . , . . . . . . 10 VIII. Reliability of BWR Vessel Water Level Instrumentation (Open) . . . . . . . . . . . . . . 12 IX. Report on the Planning and Procedures Subcommittee Meeting (Open/ Closed) . . . . . . . . 13 X. Reconciliation of ACRS Comments and Recommendations (Open) . . . . . . . . . . . . . 14 XI. Miscellaneous . . . . . . . . . . . . . . . . . . 15 XII. Executive Session . . . . . . . . . . . . . . . 16 A. Reports and Memorandum SECY-93-113. Additional Implementation Information for 10 CFR Part 54. "Reauirements for Renewal of Operatina Licenses for Nuclear Power Plants" Public Comments on Proposed Rule on ALWR Severe Accident Performance

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-Briefing by the NRR Staff on Fhy 14, 1993 D. Future ACRS Activities Supplement - Official Use Only

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CERTIED l MINUTES OF THE 398TH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS JUNE 10-11, 1993 BETHESDA, MARYLAND  !

The 398th meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Maryland, on June 10-11, 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 the election of a new Committee Officer and other 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, Dr. Harold Lewis, Mr. Carlyle Michelson, Dr. Robert Seale, and Mr. Charles Wylie. [For a list of other attendees, see Appendix III.]

I. CHAIRMAN'S REPORT (Open)

[ Note: Mr. San 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 briefly reviewed the schedule for the meeting.

Dr. Wilkins identified a number of items that he believed to be of i interest to the Committee, including:

e Mr. Douglas Coe, ACRS staff, was welcomed back from his recent rotational assignment to the Division of Reactor Inspection and Licensee Performance, Office of Nuclear Reactor Regulation (NRR).

• As part of the NRR Joint Coordinating Committee on Civilian Nuclear Reactor Safety Direct Assistance Program, the Senior ACRS staff and Dr. Wilkins led a training session for a Russian team of mid-level techni-cal specialists on June 3, 1993. The subject of the i meeting was the role of the ACRS in reviewing license applications and other issues. ,

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I 398th ACRS Meeting 2 June 10-11, 1993 II. SECY-93-113. ADDITIONAL IMPLEMENTATION INFORMATION FOR 10 CFR PART 54. " REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLANTS" (Open)

[ Note: Mr. El Igne was the Designated Federal Official for this portion of the meeting.]

Mr. William Lindblad noted that the NRC staff recommends in SECY-93-113 Additional Implementation Information'for 10 CFR Part 54,

" Requirements for Renewal of Operating Licenses for Nuclear Power Plants," that' the Commission directs the staff to publish for public comment, the staff's approach to the implementation of the license renewal rule as described in SECY-93-049, SECY-93-113 and the proposed rulemaking or policy statement. Mr. Lindblad also noted that NUMARC was not present at this meeting.

Presentation by the NRR Staff Mr. William Travers, NRR, stated that this briefing is a continua-tion of the staff's updating of the Committee on the proposed guidance of implementing the license renewal rule. Mr. Travers noted that the license renewal rule is a process rule and that the staff needs the experience of a lead plant application in order to provide the practical experience needed for the staff to conduct an effective review. Mr. Travers believes that the present rule need not be revised in order for the staff to provide an effective technical review. Mr. Travers stated that, in addition to SECY 113 that the staff provided to the Commission, the Office of General Counsel (OGC) has provided two rulemaking options for the Commission to consider in revising Part 54, in order to resolve key differences between the staff's position stated in SECY-93-094 and the statement of considerations for 10 CFR Part 54.

Mr. Travers mentioned that SECY-93-113 clarifies. the approach described in SECY-93-049 and describes the integrated plant assessment with conceptual examples using selected structures and componentL. He mentioned that the staff has identified additional flexibility in determining that equipment need not be identified as subject to age-related degradation unique to license renewal.

Further, existing programs (e.g., Technical Specifications and maintenance programs) are expected to be effective for renewal. In addition, Mr. Travers stated that equipment of relatively less safety significance will allow for less rigorous. treatment. .The result will be fewer effective program justifications required in the renewal application. Mr. Carroll asked the staff to define safety significance. Mr. Newberry, NRR, did not have a specific '

definition f or safety significance but mentioned that quantitative approach is not implied in SECY-93-113. In reply to a question by Mr. Peter Davis, Mr. Travers stated that the license renewal process does not address requirements for accommodating severe accidents. '

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t 398th ACRS Meeting 3 June 10-11, 1993-Mr. Travers mentioned that SECY-93-049, SECY-93-113 and the proposed OGC rulemaking package is being released to the public for comments. In the meantime, the staff is working'with the Babcock

& Wilcox and Westinghouse owners group on license renewal matters.  !

Mr. Travers noted that he will keep the Committee informed on the Commission's SRM that will be forthcoming.

Conclusion The Committee expressed interest in reviewing the public comments and the staff's resolution of these comments. The Committee prepared and issued a report on SECY-93-113 to Chairman Selin.  !

III. PUBLIC COMMENTS ON ADVANCED LIGHT-WATER REACTOR SEVERE ACCIDENT PLANT PERFORMANCE (Open)

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[ Note: Mr. Dean Houston was the Designated Federal Official for this portion of the meeting.]

Mr. Peter Davis, Chairman of the Containment Systems Subcommittee, ,

indicated that the Advance Notice of Proposed Rulemaking (ANPR).was

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focused on challenges to the containment from severe accidents-and '

was aimed at future LWR plants, not the current evolutionary ones under review. He indicated that the Committee had written two reports that addressed these matters. He noted that the ANPR provided three alternatives to accommodate the challenges and that the Committee, in one of its reports, had endorsed Alternative No. l 3 (an approach based, in part, on changes to General Design Crite- l ria).

Mr. Brad Hardin, Office of Nuclear Regulatory Research (RES), -

discussed the background information for the ANPR on ALWR Severei ,

Accident Design Criteria and the three options included in the ,

notice. He indicated that eleven responses to the ANPR had been-received of which three favored generic rulemaking and seven opposed it. He further indicated that although there was no I consensus regarding the value or structure cf a generic rule, the NRC staff believes that development of a draft generic rule should proceed.

Mr. Hardin discussed the following NRC staff recommendations: I

1. Continue discussions with ACRS concerning a potential t generic rule for severe accident issues in ALWRs. .

2. Delay final decision regarding implementation of a rule until at least after FSERs for the ABWR and CE Systems 80+ are completed.

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3. Staff involved in draf ting a generic rule and design certification rules for ABWR and CE System 80+ to coordinate efforts to ensure consistency. ,

4. Staff to follow the reviews of the two evolutionary and passive reactor designs to ensure consistency of draft rules with these reviews.

Conclusions The Committee issued a report to Mr. James M. Taylor agreeing with the staff's proposed approach and making some' specific recommenda-tions for the NRC staff's consideration. The Committee also indicated that it continues to recommend Alternative 3 of the ANPR.

IV. SECY-93-067, " FINAL POLICY STATEMENT ON TECHNICAL SPECIFICA-TIONS IMPROVEMENTS" (Open)

[ Note: Mr. Douglas Coe was the Designated Federal Official for this portion of the meeting.]

Mr. James C. Carroll, Chairman of the Plant Operations Subcommit-tee, introduced this topic to the Committee by noting that SECY 067, " Final Policy Statement on Technical Specifications Improve-ments" had been sent to the Commission with the NRC staff's recommendation that the Final Policy Statement on Technical Specifications Improvements be issued for public _ comment. The Committee expected to wait until resolution of public comments before being briefed by the staff prior to issuance of the Policy Statement. However, the Commission directed the NRC staff to issue the Policy Statement without further public comment, but to initiate rulemaking to codify the four criteria that define the intended scope of requirements in Technical Specifications. Also, the Commission directed the NRC staff to. include in the Policy ,

Statement a clarification of how it intends to utilize the -

probabilistic safety assessment (PSA) in its review of Technical i Specification change requests.

NRC Staff Presentation Mr. Christopher Grimes, Chief, Technical Specifications Branch, NRR, stated that revision zero of the Standard Technical Specifica-tions (STS) was issued in September 1992 following an extensive period of development since 1987 and resolution of 27,302 public comments received during 1991. Implementation of the STS began in October 1992 with the Crystal River Nuclear Power Plant Unit 3, ,

which is the first of five lead plants (one plant for each of the i three PWR vendors and one each for BWR/4 and BWR/6). In addition, the Watts Bar Nuclear Power Plant will use STS upon receipt of its operating license, which is expected in early 1994.

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l 398th ACRS Meeting 5 June 10-11, 1993 Mr. Carroll asked if adoption of the STS would resolve the problem of widely different emergency diesel generator (EDG) testing requirements. Mr. Grimes responded that, following resolution of the Unresolved Safety Issue B-56 on EDG reliability, development of STSs will be based on that resolution. In addition, a generic letter is being developed to allow relocation of accelerated testing requirements for EDGs from Technical Specifications into the maintenance program. Finally, adoption of the STS is volun- .

tary, so licensees who choose not to use STS will continue with their existing requirements. He added that the major inhibitor for. ]

licensees to revise their Technical Specifications for EDG testing i is priority, i.e., more pressing revisions are being prepared. i Mr. Carroll pointed out that the Policy Statement appears- to suggest that NRC and NUMARC had not reached agreement on very specific issues regarding NSAC-125 guidance for 10 CFR 50.59 evaluations. Mr. Brian Grimes, NRR, explained that the NRC did not endorse NSAC-125 as regulatory guidance because it proposed a methodology beyond what is required by 10 CFR 50.59. Also, agreement could not be reached on issues such as the correct way to assess " margin-of-safety," but that those differences were not significant enough to warrant concern over the adequacy of the safety evaluations.

Mr. Carroll believes that there was insufficient guidance for I either the NRC staff or a licensee to determine whether a system 3~

was of high enough " safety-significance," based on PRA, to warrant inclusion in the STS.

Ms. Nanette Gilles, NRR, described the directions given to the NRC staff by the Commission, including clarification on the uses of PSA, issuance of the Policy Statement, codification via rulemaking of the four scoping criteria, and exploration of possible stream-  ;

lining of the Technical Specification change process. She described the objectives of the Policy Statement, including encouragement of complete conversion, providing criteria for future additions, providing a generic basis for developing line-item improvements, and enhancing standardization and consistency among plants.

Mr. Michelson asked how plant specific differences were dealt with by STS implementation. Mr. Grimes stated that the requirements in the existing Technical Specifications for a plant would be reviewed -l for such plant specific requirements and that the STS' incorporates i reserved requirements intended to be filled in with plant specific details. Mr. Michelson also asked how manual valves -and other components needed to function per the safety analysis, were being dealt with in STS. Mr. Grimes answered that the STS, like the existing Technical Specifications, will not specify the full range of surveillance needed to demonstrate all aspects of equipment i

a 398th ACRS Meeting 6 June 10-11,.1993 operability. Programs such as the maintenance program are relied-upon to support operability as well.

Mr. Grimes suggested that the NRC staff would find any Committee comments helpful in the context of its preparation of the rulemak-ing package directed by the Commission. Dr. Wilkins reiterated that there was need for a senior NRC staff decision -on how to utilize PRA results and that the Policy Statement was another example of why this need exists.

Conci'icign  ;

The Committee prepared and issued a report on this matter to Chairman Selin.

V. REACTOR OPERATING EXPERIENCE (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 to the Committee by noting that.it involves several recent and significant problems with digital control and protection systems.

NRC Staff Presentation Mr. Alfred Chaffee, Chief, Events Assessment Branch, NRR, intro-duced Mr. John Calvert, Reactor Engineer, Region I, who described the Salem Nuclear Power Plant Unit 2 loss of control room annuncia-tors event and the Indian Point Nuclear Power Plant Unit 3 inoperable ATWS mitigating system actuation circuitry ( AMSAC) event ,

and the findings of the staff's inspection of these events. Mr.

Calvert emphasized the following points:

Salem Unit 2 The Salem main overhead annunciator system.was converted to a computer-based system in the summer of 1992 to resolve control room human interface deficiencies. The vendor has indicated that Kewaunee, Sequoyah, Three-Mile Island, and Susquehanna Nuclear Power Plants have received similar systems.

Although the main overhead annunciator indications were not functioning for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during this event, an independent set of alarms located on the lower control boards were available. These were not identical with the overhead alarms, but provided a subset of functionally similar alarm indica-l tions. Salem is believed to be the only nuclear power plant '

with such an arrangement.

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An operator was interacting with the annunciator computer at

, a keyboard, trying to obtain status data, when he incorrectly typed <contro1> L instead of < alt > L. Normally this would not have mattered, i.e. , nothing would have been changed. In this case, a switch position was also wrong, sending this command to a sensitive location in the computer that recognized it as a command to stop processing and await further high-speed data entry. Unknown to the operators, the computer remained in this state for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The software was supplied by the vendor, but there were no detailed specifications or a software design review from -

either the vendor or the licensee. Thus, there' was no specification that required the computer to alert the operator that an abnormal data processing condition had been detected, or to provide continuous system status,. or to determine processing priorities under abnormal conditions.

Dr. Lewis pointed out that the review of software may not need to be performed locally (i.e., by a licensee) as long as the licensee i accurately defines the specifications. He further commented that the definition of " root cause of failure" as stated in the Augmented Inspection Team report is inappropriate -- by combining and confusing the determination of information with how it will be used.

Dr. Catton questioned why this system was not reviewed for these kinds of problems prior to being installed. Mr. Jared Wormiel, Chief, I&C Branch, NRR, responded that the installation was made under 10 CFR 50.59 by the licensee, and that the licensee's evaluation did not require a software review.

Indian Point Unit 3 '

The ATWS mitigating system actuation circuitry (AMSAC) is intended to meet the requirements of 10 CPR 50.62 (the "ATWS Rule"), but is not required to be safety-related or to be treated under the Quality Assurance guidelines of 10 CFR'50 Appendix B. The AMSAC uses a software-based computer system ~

that stores the software on a hard-disk and must load the stored program into computer memory each; time the system is turned on. In May 1992, during a refueling, the AMSAC hard-drive f ailed and was returned to the vendor for repair. After the repair, a vendor technician reinstalled the AMSAC hard-drive, but he incorrectly used uncontrolled (lacking quality control) software to restore the system to operation. A subsequent problem with system operation led the technician to -

make an unauthorized change in the software. Although this "fix" was effective for the specific problem, it introduced another error that went undetected because the subsequent retests did not completely check the software. This error

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June 10-11, 1993 rendered the system not fully functional (auxiliary feedwater initiation was defeated).

Following the failure of a subsequent surveillance test, the licensee identified the above error. Further NRC review revealed that system testing since installation in May 1989 had not been complete, i.e., portions of the software logic were not being tested. Finally,.the NRC review also revealed that a design requirement related to a time delay function had not been correctly translated into software. Dynamic accep-tance testing.might have identified this error, however only-static testing was performed.

Mr. Carroll noted that both these examples were.for non-safety-related systems (performed by the licensee under 10 CFR 50.'59 without NRC staff review) and asked if the staff believes. any better about its review of analog-to-digital retrofits being made to safety-related systems. Mr. Wermiel expressed confidence that these type of problems are identified through the NRC staff's ,

review of specifications, testing, and verification and validation processes.

Mr. Lindblad commented that the problems identified are similar-to basic problems more generally associated with test procedures, calibrations, and maintenance procedures, and appear _to be related to a breakdown in engineering communication. Mr. Wermiel agreed,  ;

but noted that one factor unique to lhe newer computer related  !

problems is the weaker knowledge base of the I&C technicians who- a previously worked solely on analog systems. '

Mr. Mark Benner, Events Assessment Branch, NRR, discussed the staff's preparation of Information Notices (IN) on recent industry events involving computer problems, including yet to be issued ins on two research reactor digital control system problems, and software problems with the Maine Yankee ATWS system land the Fitzpatrick torus temperature monitoring system. He also.noted that Region I is developing an inspection procedure for assessing .I l

the adequacy of software integr'ation at nuclear power plants. .Mr.

'Wermiel- added that guidance on performing' analog-to-digital retrofits under 10 CFR 50.59 is being discussed with NUMARC with the expectation that the staf f and NUMARC will come to an agreement 1 on such guidance before the end of this year.

Mr. Davis asked if the Salem or Indian Point events were given an Accident. Sequence Precursor analysis. Mr. Chaffee stated that a .I core damage frequency figure had been computed by the Risk Applications Branch at NRR. Mr. Davis requested this analysis, if it were available.

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398th ACRS Meeting 9 June 10-11, 1993 Conclusion This briefing was for information only. No Committee action was taken.

VI. RISK-BASED REGULATION (Open)

[ Note: Dr. Medhat El-Zeftawy was the Designated' Federal Official for this portion of the meeting.)

Dr. Vojin Joksimovich presented his views on risk-based regulation before the Committee. He stated that "for all of us who have dedicated our professional careers to nuclear electricity genera-tion, recent revelations that nuclear utilities are experiencing-difficulties m ompeting economically with fossil fuel plants and~

other sources of electricity are of grave concern."

Dr. Joksimovich indicated that rising operations and maintenance (O.

& M) costs are largely attributable to regulatory requirements and how the utilities have responded to them are driving the industry right into the ground. The crisis boils down to an issue of how to maintain or enhance nuclear safety at substantially reduced costs in an acceptable regulatory framework. There is a direct correla-tion between risk-based regulation and the survival of the nuclear ,

option.

Dr. Joksimovich stated that significant reduction in O & M costs should be realized by reducing too frequent and manpower intensive i inspections and audits conducted by the NRC and Institute of Nuclear Power Operations. Examples of some European and Japanese

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j nuclear utilities were discussed to corroborate this belief. 1 l

Dr. Joksimovich described a concept of an integrated risk manage- U ment program (IRMP). He stated that operation of a nuclear power I plant (NPP) with an appropriate safety culture, assured via an IRMP will be efficient, reliable and optimal-cost plant. Through review of catastrophic accidents (such as the Chernobyl event), the Accident Prevention Group (APG) concluded that accidents may be characterized by four broad categories as follows:

e Man (operating crew response) e Machine (design with its basic flaws) e Milieu (natural phenomena, political environment, etc.) l

. Management (organizational safety culture flaws)

A strong management can minimize contribution of man, machine, and j milieu to the risk arising from operation of hazardous facilities.

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398th ACRS. Meeting 10 June 10-11, 1993 One way management can have this powerful, positive influence is through establishment of a proper safety culture. Central to the concept of IRMP is the existence of a nuclear power plant risk model that is sensitive to changes. The NRC research could provide a scientific basis for the key elements and sub-elements of IRMPs.

Dr. Joksimovich outlined ten assertions that could be incorporate ,

into the IRMPs.

Conclusion This briefing was for information only. No action was taken by the Committee.

VII. UNAUTHORIZED FORCED ENTRY AT THREE MILE ISLAND NUCLEAR POWEB PLANT UNIT 1 (Open)

[ Note: Mr. Herman Alderman was the Designated Federal Of ficial for this portion of the meeting.]

Mr. Sam Collins, Director, Division of Reactor Safety, Region IV, was the principal speaker. Mr. Collins was the team leader for the Incident Investigation Team that investigated the unauthorized forced entry at Three Mile Island Nuclear Power Plant Unit 1 that occurred on February 7, 1993. Also present were, Mr. Lee Miller, Technical Training Center, and Mr. Charles Gaskin, Office of Nuclear Material Safety and Safeguards (NMSS); both of whom were part of the Incident Investigation Team. Mr. Edward Jordan and Mr.

R. Lee Spessard represented the Office of Analysis and Evaluation- '

of Operational Data (AEOD) during this discussion.

Mr. Collins described the basis for the NRC incident investigation process. The guiding document for NRC investigations is NUREG- ,

1303, " Incident Investigation Manual," Revision 2. AEOD sponsors {

the incident investigation process. The NUREG publication  !

identifies the categories of incidents that qualify for an incident l investigation team (IIT) review, which is the highest level of NRC l incident review. The IIT is formed " om a roster of qualified individuals including those qualified as team leaders. Upon completion of the investigation, the conclusions are published in a NUREG that recommends follow-on activities by both the NRC and the industry.

In response to a question by Dr. Lewis, Mr. Collins said that the difference between an Augmented Inspection Team (AIT) and an Incident Investigation Team was that an IIT deals with more serious incidents. He noted that an IIT is an independent review in that it is independent of the regional office. He pointed out that an AIT is sponsored by the regional Of fice that oversees the f acility.

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398th ACRS Meeting 11 .i June 10-11, 1993 Mr. Lindblad remarked that he understood that the Commission could j sponsor team investigations. Mr. Jordan said that the staff had proposed this option in a Commission paper, and the staff is preparing procedures to achieve this. It will be called an Incident Investigation Group, and will provide for people outside-of the NRC as potential team leaders.

Mr. Collins presented a video that shows a reenactment of the intruders ride from the main highway to the nuclear power plant boundary, through the entry gates, and into the turbine building.

The video helped the members to visualize the sequence of events in-the intrusion. In response to a question from Dr. Lewis, Mr'.

Collins replied that there was no indication that the intruder was familiar with the site or had a planned destination.

Dr. Lewis asked who has the on-site authorization to use firearms?

Mr. Collins said that the use of deadly force is controlled by Pennsylvania law. If an individual believes his or her life is threatened, or is a third party to another individual's life being threatened, then he or she is authorized to use deadly force.

There was a brief discussion regarding concrete barriers for potential truck bombs. Mr. Collins stated that there was a contin-gency requirement to be prepared against potential truck bombs.

Mr. Jordan said that if there was intelligence of a potential truck bomb with respect to a specific plant, then that plant would have 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to erect a concrete barrier against the truck bomb. '

i Mr. Collins described the intruder. He is a native of Pennsylvania with a previous history of hospital admissions for depression. The individual has no military background, has no history of violence l or record of previous arrests and no known association with any anti-nuclear groups. An interview with the intruder revealed that he believed he was being pursued. He was fleeing from perceived individuals who wanted to harm him. He indicated that he thought the Three Mile Island facility would be a safe haven.

The licensee has procedures in the event of a protected area intrusion. One provision requires that the control room doors be locked. This presented a problem both for operator movement and access to the shift supervisors office where the emergency notification phones are located.

Mr. Collins discussed the findings and conclusions of the ' IIT i review.  !

e The intruder challenged the Three Mile Island security barriers and disrupted normal site operations.  ;

e The intruder did not reach the vital area.

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4 398th ACRS Meeting 12 June 10-11, 1993 e The primary plant was not challenged.

e There was no indication that the intruder intended to commit radiological sabotage, e Maintaining power operations was appropriate.

e The site security response was appropriate.

Conclusion This briefing was for information only. No action was taken by the Committee.

VIII. RELIABILITY OF BWR VESSEL WATER LEVEL INSTRUMENTAT_JOJ{

(Open)

[ Note: Mr. Paul Boehnert was the Designated Federal Official for-this portion of the meeting.)

Dr. Catton provided a brief report on the status of the issue of the reliability of BWR vessel water level indication. This issue was discussed during the Joint Core Performance / Thermal Hydraulic Phenomena Subcommittee Meeting of May 12, 1993. Specifically, Dr.

Catton noted that Mr. Paul Blanch, who had requested time to make a presentation to the Committee on the subject, had changed hic mind and withdrew his request. [ Note: Mr. Blanch, a former employee of Northeast Utilities, is credited with identification of the susceptibility of the BWR vessel level indication to under certain conditions provide a false-high level reading due to the presence of dissolved noncondensable . gas _ in the instrument's reference leg. The licensee was subsequently cited for a Severity Level II violation as a result of harassment / discrimination charges filed by Mr. Blanch.)

Dr. Catton noted that the NRR staff has issued an Emergency Bulletin that orders the af fected licensees to institute a hardware fix; as such, the problem has been resolved.

In response to questions, Mr. Boehnert provided some details on the NRC staff's Bulletin Order. All af fected licensees are to fix this problem when their plant (s) effect a cold shutdown after July 30, 1993. During the discussion, Dr. Catton noted that, given the above action by the NRC staff, Mr. Blanch is apparently satisfied that his concerns have been addressed. Dr. Wilkins said that Committee Members could pursue any questions that they have regarding Mr. Blanch's concerns with him on an individual basis.

In response to questions from Mr. Michelson on the details of the I so-called Millstone fix (continuous backflow of the level instru-

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e 398th ACRS Meeting 13 June 10-11, 1993 ment's reference leg using CRD cooling water), Mr. Davis' referred ,

him to the Committee notebook that contains two letters from Mr.

Blanch. Mr. Boehnert offered to provide the Memberc-additional information on this fix, upon request.

q Copelusion  !

This was an informational briefing only. No Committee action was _t taken. t IX. REPORT ON THE PLANNING AND PROCEDURES SUBCOMMITTEE MEETING (Open/ Closed)

[ Note: Dr. John T. Larkins was the Designated Federal Of ficial-for ,

this portion of the meeting.) >

As a result of the Planning and Procedures Subcommittee meeting held on June 9, 1993, the following items were brought to the attention of the Committee:

e The members were informed on the current status of Dr. '

Shack's appointment as a new Committee member. Dr. Shack will not be able to attend the 399th ACRS meeting in June. However, he expects to attend the Materials and Metallurgy Subcommittee meeting to be held on June 29, 1993.

e The Committee discussed the logistics, itinerary, and passport requirements for the trip to the Quadripartite Meeting of the Advisory Committees on October 11-15, 1993, e Dr. Larkins and Ms. Lee advised the Committee that a New Member's Guidance Manual will be prepared. A Statement of Work has been sent to the Division of Contracts. The members were also advised that Dr. Kress volunteered to serve as a mentor to Dr. Shack.

• The members discussed plans for an ACRS retreat and agreed that it would be difficult to schedule in 1993 because of the expected workload. It was agreed that a retreat should be planned for early 1994. Dr. Wilkins requested members to provide a list of possible topics _. to be placed on the retreat agenda.

• Dr. Larkins discussed the status of a draft SECY paper prepared by the Office of the General Counsel regarding stock ownership that also covers exemptions on stock ownership for new Committee members. The members will be kept current on this matter.

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398th ACRS Meeting 14 j June 10-11, 1993 '

e Dr. Larkins and Mr. Boehnert met with representatives of the Division of Naval Reactors, DOE, to discuss a Committee review of a new nuclear power plant for the next generation of nuclear submarines. A schedule will be developed with anticipated completion in late summer 1994.

• Dr. Larkins noted that he issued a memorandum requesting the Office of Information Resource Management to estab-lish Internet access through the office. SUN workstations.

Internet accounts for Committee members and staff who are not already on Internet will be requested. Dr. Lewis observed that NRC is already on Internet and requested a list of the NRC staff Internet addresses.

e The following recommendations for changing the Subcom-mittee Structure and Assignments was discussed and approved:

Abolish the Subcommittee on Advanced Pressurized Water Reactors that has the responsibility for reviewing Westinghouse AP600, SP/90, ABB-CE System ,

80+, and Safe Integral Reactor designs.

]

Establish three new Subcommittees: Westinghouse Standard Plant Designs (Mr. Lindblad, Chairman),

ABB-CE Standard Plant Designs (Mr. Carroll, Chair-man), and Simplified Boiling Water Reactor (Mr. ,

l Carroll, Chairman).

[A portion of this session was closed to discuss the status of a new member, issues raised as a result of Commission briefing by the NRR staff on May 14, 1993, the Committee's FY 1993 budget, and i ACRS/ACNW Fellowship program. Supplemental Minutes are Official j Use Only.]

I X. RECONCILIATION OF ACRS COMMENTS AND RECOM,tiENDATIONS (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:

e EDO letter, dated June 3, 1993, responding to the ACRS report dated April 22, 1993, concerning Definition of a Large Release.for Use with Safety Goal Policy.

The above EDO letter satisfactorily addressed the Committee's comments.

I

e 398th ACRS Meeting 15 June 10-11, 1993 '

e EDO letter, dated May 28, 1993, responding to the ACRS report dated April 30, 1993, concerning Staff Initiatives . l to Revise the Systematic Assessment of Licensee Perfor-mance Program.

The above EDO letter addressed the Committee's comments.

However, the Committee expressed.' interest in discussing the-formal appeal process in more detail with Dr. Thomas Murley during his next visit to a Full Committee meeting.

• EDO letter, dated May 28, 1993, responding to the ACRS +

report dated April 27, 1993, concerning Review of_Orga-nizational_ Factors Research Program.

The above EDO letter satisfactorily addressed the Committee's comments. i e EDO letter, dated May 25, 1993, responding to the ACRS report dated April 23, 1993, concerning SECY-93-049, Implementation of 10 CFR Part 54, Requirements for '

Renewal of Operating Licenses for Nuclear Power Plants.

The above EDO letter satisfactorily addressed the Committee's-comments.

1 e EDO letter, dated May 19, 1993, responding to the ACRS report dated April 26, 1993, concerning SECY-93-087, ,

" Policy, Technical, and Licensing Issues Pertaining to

• Evolutionary and Advanced Light-Water Reactor (ALWR)

Designs." '

Tne Committee noted that there were several unresolved issues that needed further discussion with the NRC staff. It_was agreed that these issues would be itemized and addressed during the Improved LWRs Subcommittee meeting on August 4, ,

1993. <

e EDO letter, dated June 8, 1993, responding to the ACRS report dated April 23, 1993, concerning Prioritization of Generic Issue 152, " Design Basis for Valves That Might be Subjected to Significant Blowdown Loads." i The above EDO letter satisfactorily addressed the Committee's 'i comments. I I

XI. MISCELLANEOUS (open)

(Note: Dr. John Larkins was the Designated Federal Official for this portion of the meeting.]

. . - . _~ ._ ~ _ _ _. __

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-b 398th ACRS Meeting 16 ~l' June 10-11, 1993 Dr. Lewis observed that the ACRS report entitled, " Staff Approach for Assessing - the Consistency of the Present Regulations with

-Respect to the Commission's Safety Goals " dated' .May 26, 1993, contains an'aversight in the last paragraph that may cause some confusion. The Committee agreed to change the phrase ". . . the level of safety . . . " to read ". . . the level of risk . . ." and reissue the report. ,

XII. EXECUTIVE SESSIOJI (Open)  !

[ Note: Dr. John Larkins was the Designated Federal Official,for this portion of the neeting.]

A. Reports and Memorandum l

t SECY-93-113, Additional Implementation Information for 10 CFR Part 54, "Recuirements for Renewal of Operatina Licenses for Nuclear Power Plants" (Report to the Honorable Ivan Selin, NRC i Chairman, from Dr. J. Ernest Wilkins, Jr., ACRS Chairman, dated June 18, 1993)

Public Comments on Proposed Rule on ALWR Severe Accident Performance (Report to Mr. James M. Taylor, Executive Director for Operations, from Dr. J. Ernest Wilkins, Jr., ACRS Chair-man, dated June 18, 1993)

Policy Statement on Technical Specifications Improvements for '

Nuclear Power Plants (Report to the Honorable Ivan Selin, NRC Chairman, from Dr. J. Ernest Wilkins, Jr., ACRS Chairman, '

dated June 18, 1993)

Information from International Meetinos on Diaital ' Instru-mentation and Control Systems (Memorandum for Mr. James M. ,

Taylor, Executive Director for Operations, from J. Ernest. '

Wilkins, Jr., ACRS Chairman, dated June 18, 1993)

B. ACRS Operations. Member's Frince Benefits and Fellowshio -j Procram  ;

The Committee discussed the perception of NRC staff generated ~

constraints on Committee operations and management of Com-mittee resources, particularly as it has effected the ACRS/-

ACNW Fellowship Program. The discussion centered on maintain-ing the Committee's level of intellectual independence and how NRC personnel policies may be infringing on that independence.

A draft letter prepared by Dr. Lewis on ACRS staffing and NRC personnel practices was deferred indefinitely. The Committee agreed to discuss this issue further during future meetings.

. ~

. 1 398th ACRS Meeting 17 l June 10-11, 1993 The members discussed the feasibility of contracting out for ACRS members so that members would no longer be counted as FTEs. The members asked Dr. Larkins to look into this possi- i bility.

Dr. Larkins discussed the use of " frequent flyer" benefits by '

ACRS members. The members asked whether special government employees are entitled to any fringe benefits, 'such as  ;

accident or disability insurance. The members requested that the ACRS staff investigate this matter.

C. Issues Raised as a Result of the Commission Briefina by the_JJRR Staff on May 14, 1993 During the Chairman's opening report on the first day, Dr.

Lewis expressed interest in discussing a recent article in Inside NRC and the events that led up the article. The Chairman postponed the discussion until the scheduled Planning and Procedures Subcommittee Report session when it could be ,

discussed in more detail. [The supplemental minutes of the  ;

closed portion of the meeting contain the related discussion.-]

During the Chairman's opening report on the second day, a '

motion to discuss matters involving certain members of the NRC staff and the management of the Committee be deferred until ,

the July regular meeting was passed. Dr. Wilkins stated that further remarks on this subject were out of order. Dr.

Lewis's motion to appeal this decision of the Chairman was defeated.

D. Future ACRS Activities i

The members discussed the issue of hydrogen control, the effectiveness of igniters and catalytic converters. Dr. .

Catton noted that the NRC staff position was inadequate and  !

recommended that further investigation on stratification is needed. The members agreed to take up these issues during the Improved LWRs Subcommittee meeting on August 4, 1993. Mr.

Charles Wylie issued a memorandum that assigns lead responsi- l bility for SECY-90-016 issues, policy and technical issues 4

associated with the regulatory treatment of nonsafety systems  !

ir passive plant designs, and other evolutionary and passive i design issues. The memorandum requests lead members to provide a list of what the NRC should discuss and what specific questions should be answered.

The Committee agreed to discuss the IPE Program and the Severe Accident Management Program at a near-future meeting.

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398th ACRS Meeting 18 il June 10-11, 1993 E. Future Meetino Acenda l I

Appendix IV summarizes the proposed items endorsed by,the Committee for the 399th'ACRS. Meeting, July 8-10, 1993, and future Subcommittee meetings.'

The 398th ACRS meeting was adjourned at 5:40 P.M. .on Friday, June 11, 1993. '

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APPENDICES MINUTES OF THE 398TH ACRS MEETING JUNE 10-11, 1993

1. Federal Register Notice II. Meeting Schedule and Outline III. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee 5

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{M Feder:I Register / Vol. 58, No.103 / Tuesday, June 1,1993 / Notices 31221 i'

• telephone number. The category which ADontssts: Address requests for single 4. Department of the Treasury, Office

1. the candidate would represent should copies of schedules identified in this of Thrift Supervision (N1-483 2).

be specified and a resuma of the notice to the Records Appraisal and Comprehensive schedule for regional l offices.

nommeo's background, experience, and Disposition Division (NIR), National qualifications included. In addition, the Archives and Records Administration, 5. General Services Administration. {

Washington, DC 20408. Requesters must Public Buildings Service (N1-121-et- f nomination should state that the

! nominee is aware of the nommation and cite the cetrol number assigned to each 1). Records of the Office of Real is wilhng to serve as a committee schedule when requesting a copy. The Proper y Managemont and Safety; momber for a two year term. control number appears in the comprehensive.

Darts: Nominations must be submitted pamntheses immediately after the name 6. National Foundation on the Arts of the requesting agency. and Humanities, Institute of Museum no later than June 30,1993.

. Nominations received after this date EUPPLF'MENTARY INFORMATON: Each year Services (N1-288-93-1). Grant case

' will not be considered. U.S. Government agencies create files.

7. President's Committee on

.' ADDREssts: Nominations should be billions of rocords oo paper, film, submitted to Tom liall, Division of magnetic tape, and other media. In order Manpower W1-220-934. Trau, u,ng Consumer Affairs, Office ofinfonnation to control this accumulation, agency "en a '

l g s and Consumer Affa!rs Occupational records managers prepare records

Commission (N1-266-03-2). Postcards Safety and H9alth Administration, room schedules specifying when the agency u'E in8 8Pproval of the pubh.c sale of N-3647. U.S. Department of Labor,200 no longer needs the records and what Tuh wporatim stock,1947.

i Constitution Avenue, NW., Washington, happens to the records after this period.

DC 20210. Some schedules are comprehensive and Dated. May 19,1993.

Epod at Wastungton. DC this 2 5 day of cover all the records of an agency or one Trudy liulamp Peterson, M y; 1993. of its major subdivisions. These Admg Archivist of the United States.

Desid C. 7sialer, compmhensive sdwdules provide for IFR Duc. 93-12813 Filed 5-28-93; 8 45 am!

the eventual transfer to the National saa.o coor ms.*.a Actmg Auhront secretary.

• I ** * ""

• WR N. 9F12832 Filed 5-28-93. 8 45 eml and authorize the disposal of all other

• * * * * " rncords. Most schedules, howes er, cover NUCLEAR REGULATORY

_ . _ . - records of only one office or pmgram er OMMISSION a few series of mcords, and many are NATIONAL ARCHIVES AND RECORDS updates of previously approved Advisory Committee on Reactor ACMMSTRATION s,chedules. Such sdiedules also may Safeguards; Meeting Agenda Records Schedules; Availabil;ty and include records that are designated for In accordance with the purposes of Request for Commenta permanent retention- sections 29 and 182b. of the Atomic Destruction of records requires the Enusy Act (42 U.S.C. 2039,2232b), the AcDecv: Office of Records approval of the Archivist of the United Advisory Committee on Reactor Admmistration, National Ardmes and States. This approval is granted after a Safeguards will hold a meeting on Jane Records Administration. thorough study of the records that takes 10-12,1993, in room P-110,7920 ACT10m Notice of availability of into account their administrative use by Norfolk Avenue, Bethesda, Maryland.

proposed roccrds schedules; request for the agency of origin, the rights of the Notice of this meeting was published in r om ments. Government and of private persons the Federal Register on April 28,1993.

directly affected by the Govemment's suuARY: The National Archis es and activities, and historical or other value. Thursday, June 10,1993

, Rm ords Administration (NARA) This public notice identifies the 8.30 a.m.--B.45 a.m.: Opening pubbshes notice at least onm monthly Federal agencies and their subdivisions RemarAs by ACRS Chairman (Open}-

of(emin Federal egency requests for requesting disposition authority. The ACRS Chairman will make opening rm ords disposition authority (records includes the control number assigned to remarks regarding conduct of the i

wheduhm). Records schedules identify each r.chedule, and briefly describes the meeting and comment briefly regarding l records of sufficient value to warrant records proposed for disposal. The items of carrent interest. During this preservation in the National Archives of records schedule contains additional session, the Committee will discuss the United States. Schedules also information about the records and their eutho.nu agencies after a specified priorities for preparatica of ACRS i disposition. Further information about reports.

period to dispase of records lacking the disposition process will be 8:45 a.m -10:15 a.m.: SECY-93-!!J, administrative legal, researth, or other furnisbad to each requester.

value. Notice is published for records Additionallmplementation Information Schedules Pendm.g for 10 CFR Part 54, "Requirementsfor schedules that (1) propose the l Renewal of Operating Ucenses for I destruction of records not previously 1. Department of State, Dureau of Nuclear Power Plants"(Open}-The authorized for disposal, or 12) reduce the evtention period for records already Oceans and International Environmental Committee will review and comment on l and Scientific Affairs (N1-59-93-32). SECY-93-113 regarding additional authorized for disposal NARA invites Routine and facilitative remrds relating implementation information for 10 CFR public comments on such schedules, as to oceans and fisheries affairs. part 54. Representatives of the NRC staff i

required by 44 U.S.C. 3303ala). 2. Dspartment of State, All foreign and the industry will participate, as 4 DATES: Request for copies must be Service Posts fN1-84-93-10). Records appropriata. '

received in writing on or before July 16, relating to construction security. 10:30 a.m.-f 1:30 a.in.:Public 1993. Once the appraisal of the records 3. Department of State, All Foreign Comments on ALWR Severe Aecident is mmpleted. NARA will send a copy of Service Posts (N1-84-93-11). Reports Performance (Open}-The Committee the schedule. The requester will be generate.d by the Immigrant Visa will hear a briefing by and hold given 30 days to submit comments. Applicant Control System, discussions with representatives of the l

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F 31221 Fedird Regiser / Vol. 58, No.103 L Tuesday, June 1,1993 / Notices -

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NRC staff on a draft Commission peper 9:25 a.m.-J1:15 a.m.: Unauthorized selected portions of the meeting as .

regarding public comments on the to forced Entry at Three Mile Island, Ur.it determined by the Chairman.

) CFR part 50 Advance Notice af f (Open)-The Committee will heer a Information regarding the time t@, set Proposed Rulemaking on Severe briormg by and hold discussions with aside for this purpose may be obtataed

• f Accidents for Future LWRs as well as the staffs recommendation regarding reprewntatives of the NRC staff by a prepaid telephone call to the ACRS regardin8 the unauthorized forced entry Executive Dimctor prior to the meeting.

' major policy issues resulting from the into the pmtected area at Three Mile in view of the possibility that the .

resolution of public comments. Island, Unit 1 that occurred on February schedule for ACRS meetings may be Representatives of the industry will 7,1993. Representatives of the licensee adjusted by the Chairman as necessary participate, as appropriate. will participate, as appropriate. to facilitate the conduct of the meeting.

11:30 a.m.-12 Noon: Resolution of 21:25 a.m.-22 noon:Prepantion of persons planning 1o attend should check ACRS Recommendations (Open)-The ACRSReports (Open)-The Committee with the ACRS Executive Directorif Committee will discuss responses from will discuss pmposed ACRS reports f: the NRC Executive Director for regarding items considered during this such rescheduling would result in msjor inconvenience.

Operations to recent ACRS comments meeting. I have determined in accordance with and recommendations. 2 p.m.-2 p.m.: Future ACRS subsection 10(d) Public Law 92-463 I p.m.-2 p.m.: SECY-93-067, " Final Activities (Open)-The Committee will that it is necessary to close po,rtions of -

Policy Statement on Technical discuss topics proposed for this meeting noted above to discuss information that involves the intemal

[S. ificofionsImprovements"(Open)-

i 11 d consideration during future ACRS meetings, personnel rules and practices of the cornme t or t e aff a op sed final 2 P.m-2:30 p.m.: Reliability of BWR agency per 5 U.S.C. 552b(c)(2) and to policy statement on tec nical Reoct r Vessel Waterlevel discuss information the release of which specifications improvements. Instmmentadon (Open)-The would represent a clear invasion of personal pn,1y per 5 unwarranted Re resentatives of the NRC staff and Committee will hear a briefing by and vocy in ustry will partici ate, P as appropriate. hold discussions with Mr. Paul Blanch U.S.C. 552b(c)(6).

2 p.m -J:30 p.m.:-Reactor regarding his concerns associated with Further information regarding topics Operating Experience (Open)-The = the reliability of BWR reactor Vessel to be discussed, whether the meeting Committee will hear a briefmg by and water level instrumentation. has been cancelled or rescheduled, the hold discussions with representatives of 2:45 p.m.-f p.m.: Preparation of Chairman's ruling on requests for the the NRC staff regardmg recent operating ACRS Reports (Open)-The Committee opportunity to present oral statements events involving computer will discuss proposed ACRS reports and the time allotted can be obtained by malfunctiores. Representatives of the regarding items considered during this a prepaid telephone call to the ACRS industry will participate. as appropriate. meeting. Executive Director. Dr. John T. Larkins 4 p m-5 p.m.: Miscellaneous (telephone 301-492--45161, hetween 8 J:45 p.m.-4:30 p.m.:-Report of the (Open)-The Committee will discuss Plannm, g and Procedures Subcornmittee a m. and 4:30 p.m. EST.

(Open/ Closed)-The Committee will miscellaneous matters related to the conduct of Committee activities and D*t*d'Ma# 2 hear a report of the Planning and **

complete discussion of topics that wers '

Procedures Subcommittee on matters myCanaemanwinumffwer not completed during previous meetings related to the conduct of ACRS IFR Doc. 93-128t6 Filed 5-28 -93, B 45 aml business, including matters related to as time and availab3ity ofinformation permit. seem em 7sem the status of appointment of new members, and organizational and Saturday, June 12,1993 personnel matters relating to ACRS staff Biweekly Notice; Appilcations and members.

8:JO o.m.-Close o/Rusiness:

Prepamtion of ACRS Reports (Open)- Amendments to Facility Operating A portion of this session may be The Committee will discuss proposed Licenses involving No Slynificant ,

closed to public attendance pursuant to ACRS reports regarding items Hazards Consideration; Correction b U.S.C. 552b(c)(2) to discuss matters considered during this meeting.

that relate solely to intemal personnel AGENCY: Nuclear Regulatory 1 Procedures for the conduct of and Commission. i rules and practices of this Advisory participation in ACRS meetings were Committee and, pursuant to 5 U.S.C. ACTION: Biweekly notice: correction.

published in the Federal Register on l

552b(c)(6), to discuss matters the release October 16,1992 (57 FR 47494). In

SUMMARY

This document corrects a of which would represent a clearly *i accordance with these procedures, oral notice document appearing in the unwarranted invasion of personal [l or written statements may be presented Federal Register on May 12.1993 (58 i privacy, by members of the public, recordings FR 28050), that revises the Technical 4:30 p.m.-5:30 p.m.wPreparation of will be permitted only during those Specifications to conform to the ACRS Reports (Open)-The Committee open portions of the meeting when c wording of the revised to CFR part 20 will discuss proposed ACRS reports l!

transcript is being kept, and questions and to reflect a separation of Chemistry [,

regarding items considered during this may be asked only by members of the and Radiation Protection ,

meeting. Committee,its consultants, and staff, i responsibilities. This action is necessary Friday. june 11,1993 #8 "8 ** 8 * * * ' a me s M ch an enes dah '

should notify the ACRS Executive .

FOR FURTHER INFORMATION CONTACT:

8:30 o.m.-10 a.m>-Risk. Based Director, Dr. John T. Larkins, as far in M'chael T. Lesar Chief, Rules Review Regulation (Open)-The Committee will advance as practicable so that Section Rules Review and Directives hear a briefing by and hold discussions appropriate arrangements can be made Branch, Division of Freedom of with Dr. Vojin Joksimovich on risk- to allow the necessary time during the Information and Publications Services, based regulation. Rapresentatives of the meeting for such statements. Use of still. Office of Administration U.S. Nuclear ,

NRC staff will participate, as motion icture. and television cameras Regulatory Commission Washington.

{

appropriate. during i is meeting may be limited to DC 20555, telephone (301) 492-7758.

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i APPENDIX II

, - a,Do UNITED STATES

!" n NUCLEAR REGULATORY COMMISSION j 3  :. E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o, of WASHINGTON, D C. 20555 I

'%4. .. . J June 2, 1993 SCHEDULE AND OUTLINE FOR DISCUSSION 398TH ACRS MEETING JUNE 10-12, 1993 Thursday, June 10, 1991, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.

1) 8:30 - 8:45 A.M. /Openina Remarks by ACRS Chairman (Open) 1.1) Opening statement (JEW /SD) l 1.0) Items of Current Interest (JEW /JTL) 1.3) Priorities for preparation of ACRS reports (JEW /SD)

L: AE  ;

2) 8:45 - LO&4G A.M. SECY-93-113. Additional Imolementation l Information for 10 CFR Part 54. "Recuire-

{ ments for Renewal of Operatina Licenses for Nuclear Power Plants" (Open) (WJL/EGI) l' 2.1) Remarks by the Subcommittee Chair-

! man l 2.2) Briefing by and discussions with representatives of the NRC staff l regarding SECY-93-113. Representa-l tives of the industry will partici-pate, as appropriate k

_0 10:15 - 10:30 A.M. BREAK s

3) 10:30 - 11:30 A.M. Public Comments on ALWR Severe Accident Performance (Open) (PRD/TSK/MDH) 3.1) Remarks by the Subcommittee Chairmen 3.2) Briefing by and discussions with representatives of the NRC staff regarding public comments on the 10 CFR Part 50 Advance Notice of-Proposed Rulemaking on Severe ,

Accidents for Future LWRs as well l 4

as the staff's recommendations j regarding policy issues resulting l from the resolution of public l comments Ls

[ - w e cr k cd p r b J m d !2 c e

2

4) 11:30 - 12:00 Noon Reconciliation of ACRS Comments and Recom-

' , g _ g;g,oa,,m.)

mendations (Open) (JEW, et al./SD) 4.1) Discussion'of the responses from the NRC Executive Director.for Operations to comments and recommendations made in ACRS reports 12:00 -

1:00 P.M. LUNCH

5) 1:00 - 2: hhp.M. / SECY-93-067. " Final Policy Statement on-l Technical Snecifications Imorovements" '

(Open) (JCC/DC)  ;

5.1) Remarks by the Subcommittee Chair-man 5.2) Briefing by and discussions with representatives of the NRC staff l regarding the staff's proposed l final policy statement on techni-cal specifications improvements.

! Representatives of the industry will l participate,'as appropriate.

05

6) 2:00 -

3:30 P.M. f' Reactor Operatina Experience-(Open)' ,

(JCC/DC) 6.1) Remarks by the Subcommittee Chairman L%

6.2) Briefing by and discussions with representatives of the URC staff '

on recent operating events involving computer malfunctions 3:30 -

3:45 P.M. BREAK

7) 3:45 -

4:~0 P.M. Report of the Plannina and Procedures Subcommittee (Open/ Closed) (JEW /JTL) 7.1) Report of the Planning and Procedures Subcommittee on matters related to

} the conduct of ACRS business, in-cluding matters related to the status (3:4 7 - 5 '. 00 P m B TE^ /

of appointment of new members, and organizational and personnel matters relating to ACRS staff members I (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 personnel rules and practices of this advisory Committee and matters.the l release of which would represent a clearly unwarranted invasion of personal privacy.) j i

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8) 4:30 - 5739 P.M. Preparation of ACRS Reports (Open) 8.1) Discussion of proposed ACRS reports regarding:

8.1-1) SECY-93-113, Additional Requirements for License Renewal (WJL/EGI) 8.1-2) SECY-93-067, Final Policy Statement on Technical Specifications Improve-ments (JCC/DC) 8.1-3) ALWR Severe Accident Performance (Tentative)

(PRD/TSK/MDH)

Friday, June 11, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.

9) 8:30 -

8:35 A.M. Openina Statement by ACRS Chairman (JEW /SD)

(Open) 9.45

10) 8:35 - F&tGO A.M. Risk-Based Reaulation (Open) (HWL/MDH) 10.1) Remarks by the Subcommittee Chairman 10.2) Briefing by and discussions with Mr.

3 Joksimovich on risk-based regulation 10:00 - 10:15 A.M. BREAK

11) 10:15 - 11:15 A.M. "' Unauthorized Forced Entry at Three Mile Island Unit 1 (Open) (HWL/HA) 11.1) Remarks by the Subcommittee Chairman 11.2) Briefing by and discussions with representatives of the NRC staff regarding the unauthorized forced entry into the protected area at

.s Three Mile Island, Unit 1 that occurred on February 7, 1993

12) 11:15 - 12:00 Noon Preparation of ACRS Recorts (Open)

(9 4r. f o: co a.m.)

~

12.1) Discussion of proposed ACRS reports regarding matters considered during this meeting 12:00 -

1:00 P.M. LUNCH

13) 1:00 -

2:00 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 consideration by the full Committee during future meetings

a-e 4

06 s

14) 2:00 -

2:30 P.M. Reliability of BWR Reactor Vessel Water ,

Level Instrumentation (Open) _ (IC/PAB) 14.1) Remarks by the Subcommittee Chairman 14.2) Briefing-by and discussions with Paul Blanch regarding his concerns associated'with the reliability of

.BWR reactor vessel. water level

_s instrumentation. >

2:30 -

2:45 P.M. BREAK

15) 2:45 -

4:00 P.M. Preparation of ACRS Reports (Open) 15.1) Discussion of proposed ACRS reports regarding matters considered during this meeting 40

16) 4:00 -

5:GO P.M. Miscellaneous (Open) 16.1) Discussion of matters considered' during this meeting and matters considered but not completed at pre-vious meetings as time and availabil-ity of information permit Saturday, June 12, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda,'Md.

17) 8:30 - Close of Preparation of ACRS Reports (Open)

Business 17.1) Discussion of proposed ACRS reports

'e- r . . . .a ,s " sr, s h regarding matters considered during

, this meeting HOTE: o Presentation time should not exceed 50 percent of the total time allocated for a specific item. Tho' remaining 50 percent of the time is reserved for discussions.

e Number of copies of the presentation materials to be provided to the ACRS - 35.

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APPENDIX III: MEETING ATTENDEES u 398TH ACRS MEETING l l

JUNE 10-12, 1993-NRC STAFF Charles Ader RES Eric Benner NRR Bruce Boger NRR Tom Boyce NRR Rex Brown NRR J. A. Calvert NRR Robert Capra NRR Al Chaffee NRR Frank Cherry RES Franklin Coffman RES Sam Collins RIV >

Commissioner de Planque OCM  :

Mary Drouin RES .

P. L. Eng NRR Morton Fleishman OCM _!

Charles Gaskin NMSS Nanette Gilles NRR Ed Goodwin NRR L. Robert Greger EDO Brian Grimes NRR Brad Hardin RES Chuck Hendren NRR Tom Hiltz NRR

• E. Jordan AEOD  !

Kerri Kavanagh NRR .I Stephen Koenick NRR 1 Joel Kramer RES '!

A. Kugler NRR Eileen McKenna OCM l Lee Miller AEOD {

John Moulton NRR I J. A. Murphy RES Scott Newberry NRR Helen Pastis NRR l Roger Pedersen NRR l John Ridgely RES  !

D. Ross AEOD Philip Rush NRR l Kristine Shembarger RGN-III '

Len Soffer RES  !

L. Spessard AEOD Joelle Starefos NRR M. Taylor EDO I William Travers NRR '

Milton Vagins RES J. Wermiel NRR l

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Appendix III, 2

'398th ACRS Meeting HRC STAFF Duke Wheeler EDO' James Wing -NRR Suzie Wittenberg NRR ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC Hector Barbetio Serch - Bechtel Val Barnes PSHA Lynn Connor STS ,

Joseph DeBor SEA Jim Eaton NUMARC Duane Fitzgerald GAO Roger Huston TVA Vojin Jorsimovicm APG ,

Kathryn Kalowsky Winston & Strawn Elizabeth Len' Winston & Strawn Chong Lewe NUS Charles'Mallon 'Newman & Holtzinger Ronya McMillen Embassy of Australia Anthony Pfeffer Serch Licensing - Bechtel Jim Raleigh STS, Inc Judith Sikorski Serch - Bechtel J. N. Sorensen Grove Eng Karen Unnerstall Newman & Holtzinger Bob Whiter. 1 NUMARC 1

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APPENDIX IV-ACRS FULL COMMITTEE AND SUBCOMMITTEE MEETINGS '

June 24, 1993 Materials and Metallurav, June 29, 1993, 7920 Norfolk Avenue, Bethesda, MD (Igne), 8:30 a.m., Room P-110. The Subcommittee will~

review draft Regulatory Guides, DG-1023, " Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 ft-lb",

and DG-1025, " Calculational and Dosimetry Methods for Determining -

Pressure Vessel Neutron Fluence." Attendance by the the following is anticipated, and reservations have been made at the hotels as indicat-ed for the night of June 2ti:

Scale HYATT Shewmon NONE Kress RESIDENCE INN Shack HYATT Michelson HYATT Reculatory Policies and Practices, July 7, 1993, 7920 Norfolk Avenue, Bethesda t _MQ (Houston), 1:00 p.m. - 5:00 p.m., Room P-110. The Subcommittee will review the report of the NRC Regulatory Review Group. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of July 6:

Lewis RESIDENCE INN Wylie HYATT Davis NONE Kerr NONE Michelson HYATT Ward NONE Plannina and Procedures, July 7, 1993, 7920 Norfolk Avenue, Bethesda.

HQ (Larkins), 1:30 p.m. - 4:00 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 ta 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 July 6:

Wilkins HOLIDAY INN Catton HYATT Carroll HOLIDAY INN Lindblad HYATT

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2 399th ACRS Meetina, July 8-10, 1993, Bethesda, MD. During this meeting, the Committee plans to consider the following:

A. Draft Reculatory Guide, DG-1025, Calculational and Dosimetry i Methods for Determinina Pressure Vessel Neutron Fluence - Review and comment on a draft regulatory guide on the methodology for determining pressure vessel neutron fluence. Representatives of the NRC staff will participate.

B. Draft Regulatorv Guide, DG-1023. Evaluation of Reactor Pressure Y3ssels with Charny Uoper-Shelf Enerav Less Than 50 ft-lb -

Review and comment on a draft regulatory guide on the evaluation of reactor pressure vessels with Charpy upper-shelf energy less

, than 50 ft-lb. Representatives of the NRC staff will partici-pate.

C. NRC Reculatory Review Group Report - Review and comment on the report of the NRC Regulatory Review Group. Representatives of the NRC staff will participate.

D. Plans for Completina the ACRS Review of the Advanced Boilina Water Reactor (ABWR) Standard S- .ity Analysis Report (SSAR) -

Discuss the schedule for complo n of the ACRS review of the SSAR for the ABWR design. Rep- -.tatives of the NRC. staff will  ;

participate, as appropriate.

E. Debris Pluacina of E.neraency Core Coolina Suction Line Strainers Hear a briefing by and hold discussions with representatives of the NRC staff on the potential for debris plugging of emergen-cy core cooling suction line strainers. In addition, hear an update on the NRC staff activities to evaluate the need for actions by U.S. licensees to address this issue as a result of the lessons learned from the Barseback event in Sweden. Repre-F.

sentatives of the industry will participate, as appropriate.

Application of Probabilistic Risk Assessment Methods for Ranking Motor-Operated Valves (MOV) - Hear a briefing by and hold discus-sions with representatives of the NRC staff on the preliminary results from a research program to prioritize the risk importance of MOVs. Representatives of the industry will participate, as appropriate.

G. Orcanizational Behavior and Factors (Tentative) - Hear a briefing by and held discussions with Dr. Leamon, ACRS consultant, on the subject of organizational behavior and organizational factors.

Representatives of the NRC staff will participate, as appropri-ate. [ NOTE: This item has been postponed to a future ACRS meeting.)

H. Reactor Operatina Experience - Hear a briefing by and hold discussions with representatives of the NRC staff on a recent event at Sequoyah Nuclear Power Plant Unit 2 that involved a rupture of an extraction steam header line.

I.

Imolementation Guidance for the Maintenance Rule - Discuss the NRC staff's response to ACRS comments and recommendations includ-ed in the April 26, 1993 ACRS report regarding implementation guidance for the Maintenance Rule. Representatives of the NRC staff will participate.

_ . . . _. _ ~ _

3 J. Resolution of ACRS Comments and Recommendations - Discuss re-sponses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.

• K. ACRS Subcommittee Activities - Hear reports and hold discussions.

regarding the status of ACRS subccmmittee activities, including a report of the Planning and Procedures Subcommittee involving matters related to the status of appointment of new members and organizational and personnel matters relating to ACRS staff members. 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 this Committee and matters the release of which would represent a clearly unwar-ranted invasion of personal privacy.

L. Future ACRS Activities - Discuss topics proposed for consid-eration by the full Committee during future meetings.

M. 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.

Computers in Nuclear Power Plant Operations, July 21, 1993, 7920 Norfolk Avenue, Bethesda, MD (Coe), 8:30 a.m., Room P-422. The Subcommittee will review the progress in developing requirements for Analog to Digital retrofits and the Environmental Qualification research on digital instrumentation and control systems. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of July 20:

Lewis HYATT Michelson HYATT Carroll HOLIDAY INN Wilkins HOLIDAY INN Catton HYATT Wylie HYATT Davis NONE Kerr HYATT Thermal Hydraulic Phenomena, July 22-23, 1993, 7920 Norfolk Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room P-422. The Subcommittee will begin its review of both the Westinghouse analytical and separate effects programs being conducted in support of the AP600 design certification effort. Portions of this meeting will be closed to discuss material deemed proprietary by the Westinghouse Electric Corporation. Attendance by the following is anticipated, and I reservations have been made at the hotels as indicated for the nights of July 21 and 22:

Catton HYATT Dhir NONE Davis NONE Schrock NONE Kress HYATT Wulff NONE Seale HYATT Zuber NONE Wilkins HOLIDAY INN

• Portion Closed l

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i buxiliary and Secondary Systems, July 27-28,.1993, 7920 Norfolk Avenue, Bethesda, MD (Alderman), 8:30 a.m., Room P-110. .The Sub-committee will review the LaSalle Fire PRA and the proposed resolution of Generic Issue-57, " Effects of Fire Protection System Actuation on Safety-Related Equipment." Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the nights of July 26 and 27:

Catton HYATT Karidas NONE Carroll HOLIDAY INN Quintiere NONE Davis NONE Michelson HYATT Wylie HYATT Materials and Metallurav, August 4, 1993 (tentative), 7920 Norfolk Avenue, Bethesda, MQ - POSTPONED.

Improved Licht Water Reactors, August 4, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will discuss NRC staff's response to ACRS comments and recommendations related to certain policy, technical, and licensing issues pertaining to evolutionary and advanced reactor designs. Also, the Subcommittee will discuss the staff positions on certain remaining policy issues for passive plant designs. Attendance by the following is anticipat-ed, and reservations have been made at the hotels as indicated for the ,

night of August 3:

Wylie HYATT Lewis l RESIDENCE INN Carroll HOLIDAY INN Lindblad HYATT Catton HYATT Michelson HYATT Davis NONE Scale HYATT Kress RESIDENCE INN 1

Plannina and Procedures, August 4, 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 mat-ters. 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 antici-pated, and reservations have been made at the hotels as indicated for the night of August 3:

Wilkins HOLIDAY INN Catton(tent.) HYATT Carroll HOLIDAY INN Lindblad HYATT

)1

5 400th ACRS Meeting, August 5-7, 1993, 7920 Norfolk Avenue, Bethesda.

MQ, Room P-110. ,

Advanced Boilina Water Reactors, September 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcom-mittee will discuss the status of resolution of the remaining open issues 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. Lodging will be announced later. Attendance by the following is anticipated:

Michelson Kress Carroll Lindblad Catton Seale Davis Wylie 401st ACRS Meeting, September 9-11, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110.

Thermal Hydraulic Phenomena, September 21, 1993, Orecon State Univer-sity (OSU). Corvallis. OR (Boehnert). The Subcommittee will visit the OSU test facility. Lodging will be announced later. Attendance by the following is anticipated:

Catton Dhir Davis Schrock Kress Wulff ,

Lindblad Zuber Seale Wilkins Thermal Hydraulic Phenomena, September 22, 1993, Orecon State Univer-pity (OSU). Corvallis. OR (Boehnert). The Subcommittee will continue its review of the Westinghouse and NRC integral systems and separate effects test programs supporting the AP600 design certification effort. The meeting discussion will focus on the OSU integral systems test facility. Lodging will be announced later. Attendance by the  !

fol;.owing is anticipated:

Catton Dhir Davis Schrock Kress Wulff I Lindblad Zuber Seale Wilkins i

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6 402nd ACRS Meetino, October 7-9, 1993, 7920 Norfolk Avenue, Bethesda.

MQ, Room P-110.

Advanced Boilina Water Reactors, October 26 (Room P-110) and 27 (Room P-422), 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m. The Subcommittee will continue its review of the GE ABWR Stan-dard Safety Analysis Report and the associated NRC staff's Final' Safety Evaluation Report. Lodging will be announced later. .Atten-dance by the following is anticipated:

Michelson Kress Carroll Lindblad Catton Seale Davis Wylie 403rd ACRS Meeting, November 4-6, 1993, 7920 Norfolk Avenue, Rethesda, MD, Room P-110.

Advanced Boilina Water Reactors, November 16-17, 1993, 7920 Norfolk Avenue,. Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcom-mittee will continue its review of the GE AEWR Standard Safety Analy-sis Report and the associated NRC staff's Final Safety Evaluation Report. Lodging will be announced later. Attendance by the following is anticipated:

Michelson Kress Carroll Lindblad Catton Seale Davis Wylie 404th ACRS Meetina, December 9-11, 1993, 7920 Norfolk Avenue, Bethesda, MD. Room P-110.

Joint Individual Plant Examinations / Severe Accidents (tentative), Date to be determined (August / September), 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 anticipated:

Davis Michelson Kress Seale Catton Kerr Lindblad Ward

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'7 Decay Heat Removal Systems, Date to be determined (August), Bethesda, liq (Boehnert).

The Subcommittee will continue its review of the.NRC 4 staff's proposed final resolution of Generic Safety-Issue 23, " Reactor Coolant Pump Seal Failures." Attendance by the following'is antici-pated:

Catton Michelson Davis Wylie Lindblad Ward Improved Licht Water Reactors, Date to be determined (October),

Bethesda, MD (El-Zeftawy). The Subcommittee will continue its review of the NRC staff's Safety Evaluation Repcrt for the'EPRI passive LWR Utility Requirements document. Attendance by the following is antici-pated:

Wylie Kress Carroll Lindblad Catton Michelson Davis Scale Thermal Hydraulic Phenomena, Date to be determined (2-day meeting),

San Jose. CA (Boehnert). The Subcommittee will continue its. review of both the GE analytical program (TRACG code) and the experimental program supporting the certification-effort for the Simplified Boiling Water Reactor design. Attendance by the following is anticipated:

Catton Dhir Carroll Kerr Davis Ward Kress Wulff Seale Zuber Wilkins Materials and Metallurov, Date to be determined, Bethesda, MD (Igne).

The Subcommittee will review proposed rulemaking on fracture toughness requirements for reactor pressure vessels - revisions to 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Appendix G, Fracture Toughness Requirements, i Appendix H, Reactor Vessel Material Surveillance Program Requirements, '

and a new rule on thermal annealing (10 CFR 50.66). Attendance by the following is anticipated:

Scale Michelson Kress Shack Lewis Shewmon

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i Thermal Hydraulic Phenomena, Date to be determined, Bethesda. MD (Boehnert). The Subcommittee will review selected aspects of the NRC-RES-sponsored ROSA-V confirmatory test program being conducted in support of the Westinghouse AP600 passive plant design certifica-tion effort. Specific review topics will include: facility design modifications and additions, the test matrix, and instrumentation and controls. Attendance by the following is anticipated:

Catton Dhir Davis Zuber Kress Seale Wilkins E

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APPENDIX V '

LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE MEETING HANDOUTS - I AGENDA DOCUMENTS ITEM NO. ,

1 Chairman's Report O. Memorandum for the Record .from Dr. Harold W. Lewis, ~ Draf t ,

1 2 SECY-93-113. Additional Implementation Information- for 10 CFR Part 54. " Reauirements for Renewal of Oneratina Licenses for Euclear Power Plants"

1. Viewgraphs on ACRS Bri~efing on License Renewal, dated June 10, 1993, prepared by William D. Travers

2. Memorandum from James M. Taylor to the Commission, dated May 14, 1993, regarding License Renewal, with enclosures

[ACRS Meeting Handout 2-1]

3 Public Comments on ALWR Severe Accident Performance

3. Copies of Public Comments on ALWR Severe Accident Performance i

4. Viewgraphs on RES Presentation on Summary of Comments on Proposed Rule on ALWR Severe Accident Performance, by Brad Hardin, dated June 10, 1993 .;

4 Reconciliation of ACRS Comments and Recommendations i

5. Five ACRS Letter Reports and the EDO Response Letters

[ACRS Meeting Handout 4.1]

6. Additional set of ACRS Letter Reports and the EDO Response Letters 5 SECY-93-067. " Final Policy Statement on Technical Specifications Improvements"

7. Viewgraphs on Final Policy Statement on Technical Specifications Improvements, dated June 10, 1993,  !

prepared by Christopher I. Grimes 6 ReAg_t;or Ooeratina Experience

8. Viewgraphs on Software Issues at Nuclear Power Plants:

Introductions, Recent Plant Events, and NRC Generic Actions, dated June 10, 1993 7 Renort of the Plannina and Procedurec Subcommittee

9. Minutes of the Planning and Procedures Subcommittee -;

Meeting Held on June 9, 1993, with enclosures 10 Risk-Based Reculation 'I

10. Viewgraphs on Where Do We Go from Here in U.S. Nuclear )

Safety Regulation? A Personal Perspective, dated June 1

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Appendix V 2 398th ACRS Meeting 11, 1993, presented by Dr. Vojin Joksimovich 10a. Where Do We Go From Here In U.S. -Nuclear Safety zRegulation? A Personal l Perspective, dated June 7, 1993 (Revision 3) 11 Unauthorized Forced Entry at Three' Mile Island, Unit 1

11. Viewgraphs on Incident Investigation of Unauthorized Forced Encry into the Protected Area at Three Mile Island-Unit 1 on February 7, 1993, undated, prepared by Samuel Collins 13 Future ACRS Activities

12. Future ACRS Activities - 399th ACRS Meeting, July 8-10, 1993 [ Meeting Handout 13-1]

16 Miscellaneous

13. Memorandum for ACRS Members from Charles Wylie, dated June 11,1993, regarding Policy, Technical, and Licensing Issues Pertaining - to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs" MEETING NOTEBOOK CONTENTS TAB DOCUMENTS 2 SECY-93-113, Additional Implementation Information for 10 CFR Part 54. "Reauirements for Renewal of Operatina Licenses for Nuclear Power Plants"

1. Project Status Report

2. SECY-93-113, Additional information for10 CFR Part 54,

" Requirements for Renewal of Operating Licenses for Nuclear Power Plants," dated April 30, 1993

3. ACRS Report, dated April 23, 1993, regarding SECY-93-049,

" Implementation of 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants"

4. Letter from James Taylor, EDO, for Paul Shewmon, dated May 25, 1993, in response to ACRS report dated April 23, 1993 3 Public Comments on ALWR Severe Accident Performance

5. Status Report

6. ACRS Report, dated May 14, 1992, regarding Advance Notice of Proposed Rulemaking On Severe Accident Plant Performance Criteria For Future LWRS

. 7. ACRS Report, dated May 17, 1991, regarding Proposed Criteria to Accommodate Severe Accidents in. Containment Design

j . ..

4 q Appendix V 3

)

398th ACRS Meeting i I

8. Memorandum for John Larkins, ACRS Executive Director, from Warren.Minners, RES, dated May 14, 1993, regarding Summary of Public Comments on Proposed Rule on ALWR Severe Accident Performance - 57 FR 44513 (Summary l Sections Only) NOTE: PORTIONS DRAFT PREDECJSIONAL  !

5 SECY-93-067, " Final Policy Statement on Technical l Specifications Improvements" i

9. Project Status Report  !

10. Draft Final Policy Statement on Technical Specifications Improvements for Nuclear Power Plants (Redline / Strikeout -l-version incorporating Commission directives) [ Pre-decisional Information)

11. Staff Requirements Memorandum, dated May 25, 1993, and Commissioner vote sheets for SECY-93-067 1

12. SECY-93-067, " Final Policy Statement on Technical Specifications Improvements," dated March 17, 1993, with enclosures 6 Reactor Operatina Experience

13. Project Status Report

14. Salem Unit 2 Augmented Inspection Team (AIT) Report 50-311/92-81, dated February 4, 1993, with enclosures 10 Risk-Based Reculation

15. Status Report

16. ACRS Report, dated November 16, 1992, regarding Risk-Based Regulation

17. Documents provided by Dr. Vojin Joksimovich

a. Where Do We Go From Here In U.S. Nuclear Safety Regulation? A Personal Perspective, dated May 8, 1993 (Revision 2)

b. Letter from Vojin Joksimovich for Paul Shewmon,

, dated February 19, 1993, regarding Risk-Based Regulation

c. Safety Culture in Nuclear Utility Operations, undated

d. Safety culture Assurance Via Integrated Risk Management Programs, undated 11 Unauthorized Forced Entry at Three Mile Island. Unit 1

18. Status Report

19. List of TMI Intrusion Questions Raised by ACRS Member Mr.

W. J. Lindblad, dated February 7, 1993 4

14 Reliability of BWR Reactor Vessel Water Level Instrumentation

20. Project Status Report [ official Use Only)

21. Memorandum from Sam Duraiswamy to ACRS Members, dated May 25, 1993, regarding Mr. Paul M. Blanch's Concerns on BWR Vessel Level Instrumentation, with enclosures [ official I

1

.o Appendix y 4 398th ACRS Meeting i

Use Only]  !

22. Excerpted draft copy of Minutes from the Joint Core Performance / Thermal Hydraulics Phenomena Subcommittee Meeting, held on May 12, 1993 [ Proprietary Information)

23. Memorandum from Paul Boehnert to Ivan Catton, regarding Commission Meeting on Reliability of BWR Vessel Level Instrumentation, held on June 1, 1993 I

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