ML20217A991
| ML20217A991 | |
| Person / Time | |
|---|---|
| Issue date: | 12/23/1997 |
| From: | Seale R Advisory Committee on Reactor Safeguards |
| To: | Shirley Ann Jackson, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0456, ACRS-SL-456, GL-97-04, GL-97-4, SECY-97-231-C, NUDOCS 9803250317 | |
| Download: ML20217A991 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION' SL-0456 l
ADVISORY COMMITTEE oN REACTOR SAFEGUARDS '
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g, wassmarow. o. c.rosos December 23,1997 The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Dear Chairman Jackson:
SUBJECT:
SUMMARY
REPORT-FOUR HUNDRED FORTY-SEVENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, DECEMBER 3-6,1997, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 447th meeting, December 3 6, 1997, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and letter. In addition, the Committee authorized Dr. Larkins, Executive Director, to transmit the memoranda noted below:
REPORTS Proposed Final Reaulatorv Guide 1.174 and Standard Review Plan Chaoter 19 for Risk-Informed. Performance-Based Reaulation (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 11,1997.)
Prooosed Revisions to 10 CFR 50.59 (Chanoes. Tests and Fwneriments (Report to
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Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated 4
December 12,1997.)
Credit for Containment Overora==ure to Provide Assurance of Sufficient Net
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Positive Suction Head for Emeroenev Core Coolina and Containment Heat Removal Pumos (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 12,1997.)
Treatment of Uncertainties Versus Point Values in the PRA-Relatart Deri=hnmaking Process (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 16,1997.)
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LETTER e'
Pisscd Final Revision 1 to NUREG-1022. " Event Reoorting Guidelines 10 CFR 50.72 and 50.73 (Letter to L. Joseph Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated December 10,1997)
MEMORANDA Pronosed Generic Letter. " Augmented Inspection of Pressurized-Water Reactor Class 1 Hioh-Pressure Safstv Inlaction Pining"(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 9,1997)
Draft Regulatorv Guide DG-1071. " Standard Format and Content for Post-Shutdown Decommissioning Activities Report"(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 9,1997)
Year 2000 Comouter lasue (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 10,1997)
Proposed Generic Letter on Interim Guidance for Uodating Final Safety Analvsis Reports (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 10,1997)
- HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1.
Emeroency Core Coolina System Strainer Blockaoe The Committee heard presentations by and held discussions with representatives of the NRC sta# regarding the staff's Safety Evaluation Report on the BWR Owners Group (BWROG) Utility Resolution Guidance (URG) for Emergency Core Cooling System Suction Strainer Blockage, and related matters. The staff performed an independent assessment of the BWROG URG report and concluded that the BWROG URG report, overall, provides good guidance that the staff considers acceptable.
Further, the staff stated that, where it has identified concems, licensees should address those concerns when applying the URG. The staff is expected to issue a final Safety Evaluation Report (SER) by February 1998.
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. The, Honorable Shirley Jackson 3
Conclusion The Committee decided not to issue a letter until the final SER has been issued.
The Committee also requested a briefing from the staff after the issuance of the final SER.
2.
A=-orance of Sufficiant Net Padive Sur*ian Haarl for Emeroency Core Coolina and Containment Heat Removal Pumps The Committee heard presentations by and held discussions with representatives of the staff regarding the status of issues pertaining to assurance of adequate net positive suction head (NPSH) for emergency core cooling and containment heat removal pumps. This discussion was held at the request of the ACRS to address some continuing concems that arose during the Committee's review of Generic Letter (GL) 97-04,'" Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps." In response to the ACRS concerns, the staff noted that licensees are not granted credit for containment overpressure due to accidents that occur during shutdown. For the case of containment bypass events, the staff has selectively granted credit for use of small amounts of containment overpressure. The staff also noted that licensee responses to the GL-97-04 information requests will be used as the basis for identifying the need for corrective actions with regard to NPSH requirements.
Conclusion The Committee issued a report to Chairman Jackson dated December 12,1997, on this matter.
3.
NRC Performance Plan The Committee heard presentations and held discussions with Mr. Jesse L.
Funches, Chief Financial Officer for the NRC, and Mr. James L. Blaha, Executive Secretary of the Executive Council, regarding the NRC's Planning and Performance Management System and the Operating Plan. Mr. Funches stated that the Performance Plan was prepared in accordance with the Govemment Performance and Results Act. He stated that,in implementing the Performance Plan, NRC will:
(1) precede budget decisions with strategic, policy and planning decisions; (2) use results from assessments to inform planning and budgeting decisions; (3) identify the activities that no longer add value to the NRC's goals and mission; and (4)
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i The Honorable Shirley Jackson 4
monitor progress toward achieving NRC's goals throughout the year. The plan is scheduled to be implemented by FY 2000. Mr. Blaha stated that the Operating Plan is organized by program and not by office. The Operating Plan includes the significant components of the Performance Plan and corresponds to the budget cycle which will be updated quarterly.
Conclusion This briefing was for information only. No Committee action was required.
4.
ACRS Reoort to Conaress on the NRC Safety Research Proaram The Committee discussed the content of a draft report to the Congress regarding the NRC Safety Research Program. The Committee plans to issue its report in final
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form in February 1998.
1 Conclusion This session was for discussion only.
5.
Prooosed Revisions to 10 CFR 50.59 (Chanaes. Tests and Exoeriments)
The Committee heard briefings by and held discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEI) regarding the proposed revisions to 10 CFR 50.59 (Changes, Tests and Experiments). The Committee discussed the i
staff's proposed changes to clarify the rule. The Committee also discussed the proposed attemate rulemaking language proposed by NEl and guidance contained in NEl 96-07, Revision OA, " Guidelines for 10 CFR 50.59 Safety Evaluations."
Conclusion The Committee issued a report to Chairman Jackson, datedoecember 12,1997, on this matter.
6.
Prooosed Generic Letter on Interim Guidance for Uodatino Final Safety Analysis Reoorts The Committee heard briefings by and held discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEI) regarding the proposed NRC l
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The Honorable Shirley Jackson 5
Generic Letter 97-XX, " Interim Guidance Regarding Updating Final Safety Analysis Reporting in Accordance with 10 CFR 50.71(e)." The Committee also discussed the NEl document entitled, " Draft Industry Guidelines for Final Safety Analysis Reports."
Conclusion The Committee decided to review this matter following reconciliation of public comments. The ACRS Executive Director issued a memorandum to the Executive Director for Operations, dated December 10,1997, on this matter.
7.
Meetina with Commissioner Diggs Commissioner Greta J. Dicus offered her views on how the NRC could operate more efficiently and effectively and discussed a number of technical and regulatory issues. These included the NRC Safety Research Program, the Senior Manage-ment Meeting process, the proposed rule on shutdown risk, the proposed revision to 10 CFR 50.59 and related matters, the use of probabilistic risk assessment in the regulatory decisionmaking pro::ess, plant license renewal, the health effects of low levels of ionizing radiation and the linear non-threshold model, and the timeliness and utility of ACRS letters.
Conclusion The Committee meets occasionally with individual NRC Commissioners. No Committee action was required.
8.
Prooosed Revision 1 to NUREG-1022.
- Event Reoortina Guidelines.10 CFR 50.72 and 50.73" The Committee heard presentations by and held discussions with representatives of the NRC staff and the nuclear industry regarding the issuance of a proposed final Revision 1 to NUREG-1022, " Event Reporting Guidelines,10 CFR 50.72 and 50.73." The Revision to NUREG-1022 consolidates NRC reporting guidance, which presently exists in several documents dating from 1983, into a single reference document. Discussions concerned the specific changes to NUREG-1022, the voluntary reporting guidance added to Revision 1, and the necessity for proceeding with rulemaking.
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- The Honorable Shirley Jackson 6
Conclusion The Committee issued _a letter to the Executive Director for Operations, dated December 10,1997, on this matter.
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Emoosed Final SRP Chanter 19 (General Guidance) and Reaulatorv GMe DG-
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1061 for Risk-Informed Performance-Basad Reaulation. Includina Use of Uncertainty Versus Point Values in the PRA-Related Decis!cnmakina Prar*ss The Committee heard briefings by and held discussions with representatives of the NRC staff regarding the propnaad final Regulatory Guide 1.174 (formerly DG-1061) and Standard Review Plan (SRP) Chapter 19 (General Guidance) for risk-informed,
- performance-based regulation, including the use of uncertainty versus point values in the PRA-related decisionmaking process as discussed in the Staff Requirements j
Memorandum dated May 27,1997. The Committee previously met in August, September, and November 1997 to review this matter. The Subcommittee on Reliability and PRA also met with representatives of the NRC staff and of the industry on July 7, August 28-29, October 21-22, and November 12-13,1997.
Conclusion The Committee issued a report to Chairman Jackson, dated December 11,1997, on the proposed final Regulatory Guide 1.174 and SRP Chapter 19.
The Committee also issued a report to Chairman Jackson, dated December 16,1997, on the use of uncertainties versus point values in the PRA-related decisionmaking process.
10.
Ooeratina Events at Oconee Nuclear Power Plant Units 1 and 2 The Committee heard presentations by and held discussions with representatives of the NRC staff and the Oconee licensee regarding recent events at the Oconee Nuclear Power Plant. The NRC conducted augmented or specialinspections of two emergency power system failures, an unisolable primary coolant system leak, and an event that resulted in damage to high pressure injection pumps. Discussions concerned the procedures and training programs at power stations that provide emergency electrical power to Oconee, the inspection program for primary piping welds, and organizational deficiencies.
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The Honorable Shirley Jackson 7
Conclusion This briefing was for information only. No Committee action was required.
11.
Canability and Anolication of the EPRI CHECWORKS Cade (Open)
The Committee was briefed by representatives of the NRC staff and the Electric Power Research Institute (EPRI) on the issue of flow-accelerated corrosion (FAC) and the capability and application of the EPRI CHECWORKS code, used to predict the potential for FAC damage in the secondary-side steam systems of nuclear power plants. The staff discussed the characteristics of FAC, plant systems susceptible to FAC, the history of component failures, and regulatory efforts to address this issue. The staff considers FAC a safety issue and is relying, in part, on the strictures of the Maintenance Rule for NRC enforcement actions. The EPRI representative provided information relative to the Chexal-Horowitz empirical model used in CHECWORKS to predict FAC, the data base used to develop and qualify this model, and its implementation. It was noted that, to date, every instance of FAC-induced failure seen by a licensee who was using CHECWORKS has been found to be the result of a mis-application of the code; i.e., EPRI believes that the code itself is a robust tool, when properly applied.
Conclusion This briefing was for information only. No Committee action was required.
RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The Committee discussed the response from the NRC Executive Director for Operations dated November 26, 1997, responding to ACRS comments and recommendations included in the ACRS report dated October 8,1997, concerning the Human Performance and Reliability implementation Plan.
The Committee decided that it was satisfied with the EDO's response.
The Committee discussed the response from the NRC Executive Director for
. Operations dated November 12, 1997, responding to ACRS comments and recommendations included in the ACRS report dated October 9,1997, conceming proposed changes to 10 CFR 50.59 and proposed Revision 1 to Generic Letter 91-18.-
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The Honorable Shirley Jackson 8
The Committee plans to continue its discussion with the staff daring future ACRS meetings. A briefing is planned for the February 1998 ACRS mwting.
The Committee discussed the response from the NRC Executive Director for Operations dated November 10, 1997, responding to ACRS comments and recommendations included in the ACRS report dated October 10,1997, conceming the staff response to ACRS comments on the Differing Professional Opinion pertaining to steam generator tube integrity.
The Committee decided that it was satisfied with the EDO's response.
OTHER RFI ATED ACTMTIES OF THE COMMITTFF During the period from November 6 through December 3,1997, the following Subcommit-tee meetings were held:
Reliability and Probabilistic Risk Assansment - November 12-13,1997 The Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) met with the NRC staff to review the proposed final Standard Review Plan Chapter 19 (General Guidance) and associated Regulatory Guide 1.174 (formerly DG-1061) for risk-informed, performance-based regulation. The Subcommittee continued its review of the matter included in the Staff Requirements Memorandum dated May 27,1997, regarding the use of uncertainty versus point values in the PRA-related regulatory decisionmaking ' process. The Subcommittee also discussed policy issues related to performance-based regulation, including industry initiatives in this area.
Plant Ooarations - December 2,1997 The Subcommittee on Plant Operations met with representatives of the NRC staff to review the staff's Safety Evaluation Report on the BWR Owners' Group Utility Resolution Guidance to address emergency core cooling system suction strainer blockage and related matters.
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i The Honorable Shirley Jackson 9-Plannina and Procedures - December 3,1997 The Planning and Procedures Subcommittee discussed proposed ACRS activities, practices, and procedures for conducting Committee business and organizational and personnel matters relating to ACRS and its staff.
LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS The Chief Financial Officer has agreed to review the Strategic Plan and identify those areas where the ACRS or ACNW should be listed as support offices.
The Committee decided not to review the proposed Generic Letter, " Augmented Inspection of Pressurized-Water Reactor Class 1 High-Pressure Safety injection Piping." The Committee would like the opportunity to review the document that summarizes the responses to the Generic Letter.
The Committee decided not to review draft Regulatory Guide DG-1071, " Standard Format and Content for Post-Shutdown Decommissioning Activities Report."
The Committee decided to consider reviewing the " Year 2000 Computer lasue" following the reconciliation of public comments.
The Committee decided to review the proposed NRC Generic Letter 97-XX, " Interim Guidance Regarding Updating Final Safety Analysis Reporting in Accordance with j
10 CFR 50.71(e)," following the reconciliation of public comments.
j The Committee considered the response from the NRC Executive Director for Operations (EDO) dated November 12,1997, responding to ACRS comments and recommendations concerning proposed changes to 10 CFR 50.59 and Proposed NRC Revision 1 to Generic Letter 91-18. The Committee plans to continue its discussion with the staff during future meetings. A briefing is planned for the February 1998 ACRS meeting.
The Executive Director for Operations has agreed that there is a need to highlight the connection between public safety and the requirements in the Operating Plans associated with the Strategic Plan.
The Honorable Shirley Jackson 10 The ACRS Subcommittee on Human Factors plans to continue its review of the Human Performance and Reliability implementation Plan and the status of related activities during its January 21,1998 meeting.
The ACRS Subcommittee on Fire Protection plans to review the staffs revised approach to amending fire protection regulations during its January 22,1998 meeting.
The ACRS Subcommittee on Plant License Renewal plans to discuss license renewal implementation issues and proposed industry guidelines during its January 23,1998 meeting.
The ACRS Subcommittee on Plant Operations plans to continue its review of proposed changes to the Senior Management Meeting process during its February 3,1998 meeting.
The ACRS Subcommittee on Advanced Reactor Designs plans to continue its review of the AP600 design during its February 3-4,1998 meeting.
I PROPOSED SCHEDULE FOR THE 448TH ACRS MEETING The Committee agreed to consider the following during the 448th ACRS Meeting, February 5-7,1998:
Proposed Rulemakina Related to 10 CFR 50,59 (Chanaes. Tests and Exoeriments)
The Committee will hear presentations by and hold discussions with representatives of the NRC sta# and the Nuclear Energy Institute regarding the proposed changes to 10 CFR 50.59.
AP600 Thermal Hydraulic Codes and Standard Safety Analysis Reoort The Committee will hear presentations by and hold discussions with representatives of the NRC staff and Westinghouse regarding the thermal hydraulic codes used in the AP600 design and the AP600 Standard Safety Analysis Report, Chapters 1,4,.
5,7, 8,9,10,11,13,17, and 18.
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o The Honorable Shirley Jackson 11 Westinahouse Sonnt Fuel Rack Crkiram Analysis Methodalaav v
The Committee will hear presentations by and hold discussions with representatives of the NRC staff and Westinghouse regarding Westinghouse's spent fuel rack criticality analysis methodology.
Meetina with Chairman Jackson The Committee will meet with Chairman Jackson to discuss dems.of mutual interest.
Imorovements to the Senior Mannamment Meetina Pranans The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding proposed improvements to the Senior Management Meeting process. Representatives of the nuclear industry will provide their views, as appropriate.
Draft Commission Paoer on Modified Anoroach for Fire Protection The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding fire protection issues. Representatives of the industry and the public will provide their views, as appropriate.
SECY-97-231: Performance-Bamad Insnaction Guidance and Related Matters The. Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding performance-based inspection guidance and related matters.
Representatives of the nuclear industry will provide their views as appropriate.
Draft NUREG-1555. "SRP for Environmental Reviews for Nuciaar Power Plants" The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding draft NUREG-1555 and related matters. Representa-tives of the nuclear industry will provide their views as appropriate.
The Honorable Shirley Jackson 12 Human Performance and Reliability lmolementation Plan The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the Human Performance and Reliability implementation Plan.
Sincerely,
. -, A R.L.Seale Chairman
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