ML20056C526
| ML20056C526 | |
| Person / Time | |
|---|---|
| Issue date: | 04/14/1993 |
| From: | Shewmon P Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0404, ACRS-SL-404, NUDOCS 9306240418 | |
| Download: ML20056C526 (8) | |
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UNITED STATES SL-0404 i
NUCLEAR REGULATORY COMMISSION
{
- ,E PDR 4/A//95 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGT ON, D. C. 20555
+...+
April 14, 1993 The Honorable Ivan Selin Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED AND NINETY FIFTH HEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MARCH 11-12, 1993, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 395th meeting, March 11-12, 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memorandums as noted.
Reports Computers in Nuclear Power Plant Operations (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 18, 1993)
Advanced Boilina Water Reactor (ABWR) Review Schedule (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 18,1993)
Human Performance in Ooeratina Events (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 19,1993)
Memorandums Generic letter on Emeraency Response _Qata System Test Proaram (Memorandum to James M.
Taylor, Executive Director for Operations, from John T.
Larkins, Executive Director of the ACRS, dated March 17,1993)
Procosed NRC Generic Letter "Line-Item Technical Specification Imorovements to Reduce Surveillance Reauirements for Testina Durina Power Operation" (Memorandum to Gail H.
Marcus, Chief of the Generic Communications Branch in the Division of Operating Reactor Support Office, from John T. Larkins, Executive Director of the ACRS, dated March 17, 1993)
HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1.
Current License Renewal Issues The staff discussed the results of its senior management review on the harmonization of the maintenance and license renewal rules and its q g 62 g s 930414 pg3;cgg7g3 onic13AL NR M
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recommendations on how the license renewal rule is envisioned to be implemented.
Following the Committee meeting with the Commissioners in l
December 1992, an SRM was issued requesting that the Committee consider I
how the maintenance rule might be used to address the requirements of the license renewal rule. The Committee will discuss its response during the April 15-17, 1993 ACRS meeting.
License Renewal Representatives of the staff discussed the status of their efforts to examine a number of key license renewal issues focused on implementing the license renewal rule. The outcome of the staff's senior management review and the staff's proposal for implementing 10 CFR Part 54, " Requirements i
j for Renewal of Operating Licenses for Nuclear Power Plants," are l
delineated in SECY-93-049, dated March 1, 1993. The staff discussed this SECY at a public meeting on March 12, 1993 and met with the Commission to discuss this matter on March 15, 1993.
Intearated Plant Assessment (IPA)
Representatives of the staff discussed the IPA Program and how it relates to the activities conducted under the maintenance and license renewal rules. All plant equipment within the scope of the license renewal rule will be considered, but the scope will be reduced based on definition of SSCs important to license renewal.
NUMARC was in attendance but not prepared to comment or provide a presentation.
l Conclusions l
l This was an information briefing only.
The Committee did not comment on this matter as a result of this briefing.
The Committee expects to respond to the Commission's December 24, 1992 SRM concerning this matter after it hears from industry, i.e., NUMARC, at the April 15-17, 1993 mee(ing.
2.
Computer Issues Dr. Hal Lewis, Chairman of the Computers in Nuclear Power Plant Operations Subcommittee, introduced this topic to the Committee by noting that there l
are two separate levels of discussion that must be undertaken. One is at the level of detail associated with conversions from analog to digital instrumentation and control (I&C) systems in existing plants. The other is a higher level at which the criteria is established for decisionmaking at the first level.
He emphasized the need to keep the two discussions separate.
3 ERC Staff Presentation Mr. William Russell, Associate Director of the Office of Inspection and Technical Assessment in the Office of NRR, noted the following:
Digital I&C systems can provide enhanced capabilities and improved safety.
The technology is changing rapidly and staff recruiting is ongoing to bring special expertise in digital system applications to the NRC, even in the face of impending budget cuts.
Logical deficiencies embedded in software create a systemic failure mode to which probability of failure cannot be assigned.
The staff's approach to this has been to require diversity within the design of the control and protection systems. Based on earlier ACRS comments, the staff will consider diversity achieved by a second dedicated simple digital
- system, and also under certain circumstances give credit to n'on-safety systems and/or manual operator actions. The adequacy of such systems will be evaluated on a case-by-case basis.
Based on discussions with other regulatory authorities, the staff has identified the importance of writing specifications on hardware / software performance that is precise and unambiguous.
The question of analog to digital retrofit is being worked via staff dialogue with EPRI and NUMARC working groups.
Severe accident mitigation normally involves manual actions, and will be treated under the staff position to require manual system level actuation.
Digital I&C issues will be discussed as a portion of the May 3-4, 1993 Regulatory Information Conference and at a Research Workshop on digital and software issues planned for September 1993.
Conclusions The Committee did issue a report to Chairman Selin on the use of computers in nuclear power plants, as noted above.
3.
Reactor Ooeratino Experience - Fort Calhoun Station loss-of-Coolant Event of July 3-4. 1992 Mr. J. Carroll, Chairman of the Plant Operations Subcommittee, introduced this topic to the Committee by noting the similarity of this event to the Three Mile Island 2 accident, most notably a temporarily stuck open valve.
He emphasized the effectiveness of the operators response and emergency procedures.
i
4 NRC Staff Presentation Representatives of the staff concluded that the Augmented Inspection Team (AIT) looked at all aspects of the event and arrived at a valid conclusion that the operators performed correctly.
It was noted that this event was one of the few opportunities for the NRC to evaluate human and hardware interaction during a "THI-like" event and it did demonstrate the successful implementation of many of the post-THI requirements.
Conclusions This was a briefing for information. No specific action was taken at this meeting as a result of this briefing.
4.
ISO Ouality Standards Mr. Rob Cerzosimo, ACRS Consultant, briefed the Committee on the ISO 9000 standards for quality management and quality assurance that were issued in 1987.
These standards were developed by the International Standards Organization (IS0) to promote harmonization of standards within and outside the European community.
He presented the following conclusions:
a.
The certification of a company's quality system by an accredited certifying body cannot, by itself, provide the necessary confidence that a specific product or service will exhibit the degree of quality required for the specific safety-related application, b.
A company that has established measures for quality and documented' adequate and suitable provisions, as required by an ISO 9001 and/or 9002 standard (as applicable), for achieving and improving quality may have a quality system that satisfies the intent of the current
- nuclear regulatory requirements.
c.
Some companies that are expected to achieve certification of their ISO 9000 quality system do intend to provide items and services to the nuclear industry.
Conclusions This was a briefing only.
No Committee action was taken at this meeting as a result of this briefing.
5.
Accointment of New Members The Committee intends to send a slate of nominees to the Commission to fill the vacancy that will be created when Dr. Shewmon retires.
This slate is expected to be sent following the May 1993 meeting.
5 6.
Voorade of Conference Roqm A representative of the NRC's Office of Consolidation nade a presentation covering the design concept, furniture and furnishings for the ACP.S meeting room and subcommittee rooms.
Mr. Stan Schofer, ACRS staff, demonstrated the use of the Zy Index, that is available for use at this time on the Network.
The Index has all of the ACRS letters that have been issued since 1985.
He demonstrated the word / phrase search capability of the presently available Zy Index program.
7.
ACRS Subcommittee Activities Report of the Materials and Metalluray Subcommittee Meetina Held on March.
10, 1993 Dr. Paul Shewmon briefed the Committee on the outcome of the Joint ACRS Subcommittees on Materials and Metallurgy / Structural Engineering meeting of March 10, 1993.
Steam Generator Interim Criteria Dr. Shewmon discussed the status of the development of interim steam generator tube plugging criteria applicable to outside diameter steam generator tube degradation of short and deep cracks at the tube support plant.
This briefing was for information only. The subcommittee will meet again when the development of the staff's final plugging criteria is complete.
ALWR Pioina Desian Criteria Dr. Shewmon noted that the industry presented a briefing on first-of-a-kind engineering on piping design criteria for advanced LWRs.
Based on recent tests and analyses, it was found that current piping systems are rig (d and very robust.
In addition, tests indicate that the current ASME Code failure criteria are incorrect and should be corrected. Based on the industry proposed piping criteria, redesigned piping systems should be more flexible and have less supports, restraints and snubbers.
These improvements should reduce piping loads; be easier to inspect and fabricate; and reduce overall cost.
The industry stated that they are working with the ASME Code Committees (in which the staff is represented) to modify existing codes to reflect current knowledge.
This briefing was for information only.
Egoort of Thermal Hydraulic (T/H) Phenomena Subcommittee Meetina. March 4-
- 5. 1993 - Idaho Falls. Idaho Dr. Ivan Catton, T/H Phenomena Subcommittee Chairman, reported on the subject meeting.
The meeting was held to discuss the status of the PWR version of the RELAPS/ MOD 3 (R/5) code, sponsored by the Office of
6 Research.
The emphasis of the discussions was on the use of R/5 to support RES's confirmatory research programs associated with NRR's certification review for the Westinghouse AP600 passive plant design.
Members of the Subcommittee said they were surprised to discover that the so-called " passive" plant designs, e.g.,
AP600, required more complex modeling than that of the current reactor designs. The Subcommittee will meet to discuss this matter after receipt of additional information is available.
This briefing was for information only.
8.
Reconciliation of ACRS Comments and Recommendations The Executive Director for Operations' (ED0's) responses to previous ACRS reports were discussed as follows:
ED0 letter, dated February 24, 1993, responding to the ACRS report dated December 17, 1992, "NRC Response to the Petition Submitted by Richard Grill for Rulemaking on Electrical transients, PRM-50-56."
The EDO letter did address the Committee's comments.
EDO letter, dated February 19, 1993, responding to the ACRS report dated November 12,1992, " Revised Regulatory Analysis Guidelines."
The ED0 letter did address the Committee's comments.
ED0 letter, dated February 11, 1993, responding to the ACRS report dated January 13, 1993, concerning Proposed Resolution of Generic Safety Issue 120, "On-Line Testability of Protection Systems."
The ED0 letter did address the Committee's comments.
9.
Miscellaneous Gene'ric letter on Emeroency Response Data System Test Proaram The Committee directed Dr. John Larkins to send a memorandum to James M.
Taylor, Executive Director for Operations, as noted above, indicating that the Committee decided not to review the, proposed generic letter.
Proposed NRC Generic letter "Line-Item Technical Specification Imorovements to Reduce Surveillance Reauirements for Testina Durina Power Operation" The Committee directed Dr. John Larkins to send a memorandum to Gail H.
Marcus, Chief of the Generic Communications Branch, as noted above, indicating that the Committee decided not to review the proposed generic letter.
4
l 7
Revision of ACRS Subcommittee Assianments The members were given a revised list of proposed subcommittee assignments.
The members were asked to provide their comments on the.
proposed assignments to the ACRS staff before the April 1993 ACRS meeting.
10.
Subcommittee Meetinas During the period between the February and the March 11-12,-
11-13,1993* tings were held:
1993, ACRS meetings, the following Subcommittee mee Thermal Hydraulic Phenomena - March 4-5, 1993 The Subcommittee discussed the status of the PWR Version of the RELAP5/M00-3 code with emphasis on analytical and test programs in support of the AP600 design certification effort.
Joint Meetina of the Subcommittees on Materials and Metallurav and Structural Enaineerina - March 10, 1993 l
The Subcommittees discussed (1) the status of the NRC staff's concerns regarding steam generator tube degradation, and (2) the industry proposal on piping design improvements for ALWR plants to reflect current technical knowledge.
Plannina and Procedures - March:10,1993 The Subcommittee discussed proposed ACRS_ activities, practices, and-e procedures for conducting Committee business, and related matters.
Qualifications of candidates nominated for appointment to the ACRS were also discussed.
11.
Future ACRS Activities The following activities were scheduled for the 396th ACRS Meeting,' April 15-N,1993, Bethesda, Maryland:
The SALP Proaram - The Committee will review and comment on the-overall SALP process and the changes made or proposed since the 1
Regulatory Impact
' Survey that was conducted in 1989.
Representatives of the industry and NRC staff will participate.
Commission Pacer on Safety Goals /Larae Release - The Committee will review and comment on a revised Commission paper on the definition of a large release within the context of the implementation of the Safety-Coal Policy.
Representatives
.of the : NRC staff will participate.
Maintenance Guidance Documents - The Committee will review. and comment on the guidance documents for Implementation of the Maintenance Rule.
Representatives of _ the NRC staff and industry will participate.
Current license Renewal Issues - The Committee will discuss and comment on how the Maintenance Rule might be used as a means to
8 address the activities required of licensees by the License Renewal Rule.
Representatives of the industry and NRC staff will partici-pate.
Proposed Final Commission Paper on Resolved SECY-90-016 Follow-on Issues - The Committee will review and comment on.the status of the NRC staff's work on resolution of SECY-90-016 follow-on issues.
Representatives of the NRC staff will participate.
Reaulatory Guide for Implementation of Revised 10 CFR Part 20 - The Committee will discuss and comment on the proposed final regulatory guide, DG-8006, " Control of Access to High and Very High Radiation Areas in Nuclear Power Plants." Representatives of the NRC staff will participate, as appropriate.
Prioritization of Generic Issue 152. "Desian Basis for Valves that Might be Sub.iected to Sianificant Blowdown loads" - The Committee will discuss proposed ACRS report on the proposed priority ranking of this generic issue.
Representatives of the NRC staff will participate, as appropriate.
Oraanizational Factors Research - The Committee will discuss proposed ACRS report on the Organi2ational Factors Research Program.
Representatives of the NRC staff and industry will participate, as appropriate.
Effects of Hurricane Andrew on the Turkey Point Plant - The NRC staff will brief the Committee on the effects of Hurricane Andrew on the Turkey Point Nuclear Plant.
Representatives of the industry will participate, as appropriate.
Meetina with the Director of the Office of Policy Plannina (Tenta-tive) - Meet with the Director of the Office of Policy Planning to discuss matters of mutual interest.
Future ACRS Activities - The Committee will discuss topics proposed for consideration by the full Committee.
Resolution of ACRS Recommendations - The Committee will discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS comments and recommendations.
ECRS Subcommittee Activities - The Committee will hear reports on and hold discussions of the status of ACRS subcommittee assignments, including activities of the NRC Region II Office, Severe Accident issues for the GE ABWR, ABB-CE System 80+ control room mockup, and procedures for the conduct of ACRS business. Representatives of the NRC staff will participate, as appropriate.
Apoointment of ACRS Members The Committee will discuss qual-ifications of candidates proposed.for appointment as ACRS members.
Sincerely, Ce Paul Shewmon Chairman