ML20210A393
| ML20210A393 | |
| Person / Time | |
|---|---|
| Issue date: | 07/15/1999 |
| From: | Bergman T NRC (Affiliation Not Assigned) |
| To: | Carpenter C NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-689 NUDOCS 9907220091 | |
| Download: ML20210A393 (16) | |
Text
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1 UNITED STATES y
j NUCLEAR REGULATORY COMMISSION i
t WASHINGTON, D.C. 20665-0001
\\*****/
July 15,1999 MEMORANDUM TO: Cynthia A. Carpenter, Branch Chief Generic issues, Environmental, Financial and Rulemaking Branch Division of Reactorimprovement Programs FROM:
Thomas A. Bergman, Senior Project Manager-b Generic issues, Environmental, Financial f
and Rulemaking Branch Division of Reactor improvement Programs
SUBJECT:
SUMMARY
OF MEETING HELD ON JULY 8,1999, WITH THE PUBLIC TO DISCUSS EFFORTS TO RISK-lNFORM 10 CFR PART 50 (RIP 50)
On July 8,1909, the staff held a public meeting at NRC headquarters in Rockville, Maryland. At the beginning of the meeting, the staff notified attendees that the meeting would be an open forum on the subject of risk-informed Part 50, and that participation was encouraged from all present, and not only from NEl. Attachment 1 is a list of the attendees at the meeting.
Attachrnent 2 is a copy of NEl's slides presented at the meing.
NEl Risk-Informed. Performance-Based Acoroach:
After opening remarks by the NRC, representatives from NEl, Steve Floyd and Adrian Heymer, presented NEl's view on Risk-informed, Performance-Based Regulation. NEl believes that the effort should proceed in four parallel phases. Phase 1 involves the Oversight and Enforcement P;ocess with industry wide implementation in April 2000. Phase 2 involves Regulatory Structures, Systems, and Components (SSCs) (Option 2) with ongoing pilot projects and issuance of the final rule by March 2001. Phase 3 involves Technical Regulatory Scope (Option
- 3) with preliminary reviews and plan completed by December 1999. Phase 4 involves other administrative regulations that would proceed parallel to the other phases. Under Option 2, NEl foresees 26 rule changes associated with a transition in scope from the definitions of safety-related and important to safety to safety-significant. NEl believes that possible areas for risk-informed rulemaking include: equipment qualification, maintenance rule, technical specifications, quality assurance, license conditions, fire protection, codes and standards, reporting requirements, fire protection, final safety analysis report, Appendices A, B, J, K, and S, Appendix A to 10 CFR Part 100; 10 CFR part 21, and license renewal.
SSC Classification:
NEl proposed a revised classification scheme using a blended approach of risk information and other criteria, such as defense-in-depth, to reciassify SSCs into " Safety-Significant SSCs" and "Other SSCs." For " Safety-Significant SSCs," NRC oversight would be implemented in accordance with the NRC's revised inspectian and oversight program. For "Other SSCs", no regulatory requirements would apply. The licensees would use normal commercial practices i
- 7) Q P () Q Q (9f 9907220091 990715 SQ
%Q$:
ALL
Cynthia barpenter
--2 July 15,1999 with plant monitoring consistent with business oversight plans. NRC regulatory involvement with "Other SSCs" could occur, but this would occur only as a result of plant events. NEl representatives stated that the industry would address risk-informing 10 CFR Part 50 by submitting a petition for rulemaking, a guidance document, and several packaged exemptions from four nuclear power plants which will serve as pilot plants for the regulatory scope changes.
Industry currently anticipates that the pilot plants will test out scope changes for the existing special treatment rules. However, it is not clear whether the full range of Part 50 special treatment rule will be tested by the pilot plants. This issue wi!! he further explored in future meetings.
l NEl indicated that the development of a single "O-list" with determination of the attribute of significance and an understanding of why the item is O-listed is a major focus. Several members of the NRC staff expressed concerns for gradations of classification and for the j
process that would facilitate transition from the current safety-related and important to safety classification scheme to the " safety-significant" classification scheme. NEl responded that individual licensees may choose to have gradations within the scheme that was established at their facilities, but the NEl position was to use two classifications. With respect to the transition j
process, NEl indicated that the planned guideline for NRC endorsement would establish the i
process for transition. This guideline would define the attributes, range, and reasons for SSCs to be important.
Optional and Flexible implementation:
NEl representatives have indicated that licensees desire the ability to select which risk-informed regulations that they would choose to implement. In essence, the NRC would promulgate all necessary changes to risk-inform regulations and licensees would then select which of the risk-
)
informed rules to implement at their facilities. Gary Holahan, Director, Division of Systems l
Safety and Analysis, specifically expressed concern that given selectivity, that a licensee could do a partialimplementation of Option 2 changes and not implement Option 3 thus never get to I
the end state of the given risk-informed regulation. NEl acknowledged that this had not been foreseen and would consider this concern. The staff noted that selectivity will also significantly increase the complexity of the rulemaking effort involved in implementing risk-informed regulations.
Specific Points:
NEl indicated a desire to risk-inform 10 CFR 50.59, but they are unsure how to address 50.59 at this time. Likewise, NEl indicated that they were struggling with a definition for " safety-significant."
Attachments: As stated cc w/atts: See next page
List of Attendees Name Oraanization P. Balmain NRC/NRR G. Bagchi -
NRC/NRR R. Barrett NRC/NRR W. Beckner NRC/NRR f
T. Bergman -
NRC/NRR B. Bradley NEl J
W. Burchill Commonwealth Edison N. Chapman SERCH/Bechtel M.Cheok NRC/NRR B. Christie Performance Technology M. Cunningham NRC/RES M. Drouin NRC/RES D. Fischer NRC/NRR S. Floyd NEl N. Gilles NRC/NRR H. Hamzehee NRC/RES
' W. Harrison STPNOC A. Heymer NEl -
G. Holahan NRC/NRR T. King NRC/RES J. Knox NRC/NRR A. Markley NRC/NRR l
M. Markley NRC/ACRS Staff J. Mitchell NRC/OEDO S. Newberry NRC/NRR G. Parry NRC/NRR l
T. Reed NRC/NRR M. Rubin
' NRC/NRR M. Schoppman FP&L - Washington M. Shuaibi NRC/NRR D. Stellfox McGraw-Hill J. Williams NRC/NRR S. Wong NRC/NRR ATTACHMENT 1 m
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Nuclear Energy Institute Project No. 689 t
cc: Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suite 400 1776 l Street, NW 1776 l Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charles B. Brinkman, Director Programs Washington Operations Nuclear Energy Institute ABB-Combustion Engineering, Inc.
Suite 400 12300 Twinbrook Parkway, Suite 330 1776 i Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Mr. Kurt Cozens, Director Engineering Materials Reliability Project Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suite 400 1776 i Street, NW 1776 i Street, NW Washington, DC 2000G-3708 Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jim Davis, Director Operations Nuclear Energy institute l
Suite 400 1776 i Street, NW Washington, DC 20006-3708
.o i
DISTRIBUTION:
SUMMARY
OF PUBLIC MEETING HELD ON JULY 8,1999 l
HARD COPY tPropect File * -
TBergman E-Mall SCollins RZimmerman BSheron BKane DMatthews SNewberry 4
CCarpenter FAkstulewicz GBagchi PBaranowsky, RES RBarrett CBarlett WBeckner MCheok MCunningham, RES NGilles GHolahan TKing, RES PLewis, RES AMarkley BPalla Treed MRubin MShuaibi JWilliams 1
i 4
I t
b J
Cynthia Carpenter July 15,1999 with plant monitoring consistent with business oversight plans. NRC regulatory involvement with "Other SSCs" could occur, but this would occur only as a result of plant events. NEl representatives stated that the industry would address risk-informing 10 CFR Part 50 by submitting a petition for rulemaking, a guidance document, and several packaged exemptions from four nuclear power plants which will serve as pilot plants for the regulatory scope changes.
Industry currently anticipates that the pilot plants will test out scope changes for the existing special treatment rules. However, it is not clear whether the full range of Part 50 special treatment rule will be tested by the pilot plants. This issue will be further explored in future meetings.
NEl indicated that the development of a single "Q-list" with determination of the attribute of significance and an understanding of why the item is O-listed is a major focus. Several members of the NRC staff expressed concerns for gradations of classification and for the process that would facilitate transition from the current safety-related and important to safety classification scheme to the " safety-significant" classification scheme. NEl responded that individual licensees may choose to have gradations within the scheme that was established at their facilities, but the NEl position was to use two classifications. With respect to the transition process, NEl indicated that the planned guideline for NRC endorsement would establish the process for transition. This guideline would define the attributes, range, and reasons for SSCs to be important.
Optional and Flexible implementation:
NEl representatives have indicated that licensees desire the ability to select which risk-informed regulations that they would choose to implement. In essence, the NRC would promulgate all necessary changes to risk-inform regulations and licensees would then select which of the risk-informed rules to implement at their facilities. Gary Holahan, Director, Division of Systems Safety and Analysis, specifically expressed concern that given selectivity, that a licensee could do a partial implementation of Option 2 changes and not implement Option 3 thus never get to the end state of the given risk-informed regulation. NEl acknowledged that this had not been foreseen and would consider this concern. The staff noted that selectivity will also significantly increase the complexity of the rulemaking effort involved in implementing risk-informed regulations.
Specific Points:
NEl indicated a desire to risk-inform 10 CFR 50.59, but they are unsure how to address 50.59 at this time. Likewise, NEl indicated that they were struggling with a definition for " safety-significant."
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