ML20134L768: Difference between revisions
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Monroe County, Michigan. The plant is owned Cooper Nuclear Station and operated by the Detroit Edison Company The Cooper Nuclear Station is a single-unit, (the h,censee). 778-megawatt (electrirl GE BWR facili y, t k>cated in Nemaha County, kuraska. The plant is owned On December 23,1993, the Ferm.i 2 plant suffered and operated by the Nebraska Public Power a catastrophic failure of the turbine generator District (the licensee). | Monroe County, Michigan. The plant is owned Cooper Nuclear Station and operated by the Detroit Edison Company The Cooper Nuclear Station is a single-unit, (the h,censee). 778-megawatt (electrirl GE BWR facili y, t k>cated in Nemaha County, kuraska. The plant is owned On December 23,1993, the Ferm.i 2 plant suffered and operated by the Nebraska Public Power a catastrophic failure of the turbine generator District (the licensee). | ||
while the plant was at 93 percent reactor power. | while the plant was at 93 percent reactor power. | ||
The Region III Administrator issued a In May 1994, the Cooper Nuclear Station entered confirmatory action letter (CAL) on December 28, a forced, unplanned outage, which continued until 1993, documenting actions required of the licensee the restart in February 1995. The plant was shut before restart. In addition, with the concurrence down because of deficiencies identified by the of NRR, the Regional Administrator formed a NRC in the surveillance testing of the electrical restart panel, in accordance with NRC Manual distribution system, the control room emergency Chapter (MC) 0350, " Staff Guidelines for Restart filter system, and the primary containment Approval," to evaluate and track the licensee's penetrations. Several confirmatory action letters investigative and recovery actions before restart. (CALs) sent out from May through August of The panel developed a formal restart action plan 1994 required the licensee to address these issues with over 33 action items to be resolved before and to evaluate its operational experience review restart. By letter dated December 14,1994,the and testing programs. | The Region III Administrator issued a In May 1994, the Cooper Nuclear Station entered confirmatory action letter (CAL) on December 28, a forced, unplanned outage, which continued until 1993, documenting actions required of the licensee the restart in February 1995. The plant was shut before restart. In addition, with the concurrence down because of deficiencies identified by the of NRR, the Regional Administrator formed a NRC in the surveillance testing of the electrical restart panel, in accordance with NRC Manual distribution system, the control room emergency Chapter (MC) 0350, " Staff Guidelines for Restart filter system, and the primary containment Approval," to evaluate and track the licensee's penetrations. Several confirmatory action letters investigative and recovery actions before restart. (CALs) sent out from May through August of The panel developed a formal restart action plan 1994 required the licensee to address these issues with over 33 action items to be resolved before and to evaluate its operational experience review restart. By {{letter dated|date=December 14, 1994|text=letter dated December 14,1994}},the and testing programs. | ||
licensee notified the NRC of its resolution of the action items. As a result, by letter also dated The licensee's independent diagnostic self-December 14,1994, the region notified the assessment (DSA) report, released in September 1 licensee that the CAL was rescinded, and that the 1994, concluded that corporate and station ; | licensee notified the NRC of its resolution of the action items. As a result, by letter also dated The licensee's independent diagnostic self-December 14,1994, the region notified the assessment (DSA) report, released in September 1 licensee that the CAL was rescinded, and that the 1994, concluded that corporate and station ; | ||
licensee was free to restart the Fermi 2 plant. On management did not foster high standards of December 19,1994, nearly 1 year after the performance, and that management and quality catastrophic turbine failure, the licensee restarted assurance oversight were not effective. In the Fermi 2 plant. addition, the DSA stated that significant weaknesses existed in the licensee's long-range l After restart, the Fermi 2 plant began an planning efforts, and that its testing, configuration l aggressive campaign of startup testing, power control, and corrective a: tion programs were ascension, and turbine balancing. However, deficient. The NRC subsequently conducted a during the outage, the licensee had decided to special evaluation, finding that the DSA was an | licensee was free to restart the Fermi 2 plant. On management did not foster high standards of December 19,1994, nearly 1 year after the performance, and that management and quality catastrophic turbine failure, the licensee restarted assurance oversight were not effective. In the Fermi 2 plant. addition, the DSA stated that significant weaknesses existed in the licensee's long-range l After restart, the Fermi 2 plant began an planning efforts, and that its testing, configuration l aggressive campaign of startup testing, power control, and corrective a: tion programs were ascension, and turbine balancing. However, deficient. The NRC subsequently conducted a during the outage, the licensee had decided to special evaluation, finding that the DSA was an | ||
| Line 745: | Line 745: | ||
application in 1996 to increase the authorized resolve NRC concerns regarding TVA's ability to ' | application in 1996 to increase the authorized resolve NRC concerns regarding TVA's ability to ' | ||
thermal power of hionticello by about 6.3 percent, safely operate the BFN facility. | thermal power of hionticello by about 6.3 percent, safely operate the BFN facility. | ||
'I\vo GE-designed BWRs in Switzerland have Following extensive NRC review and inspection of completed extended power uprate licensing TVA corrective actions, BFN Unit 2 was restarted actions. The Kernkraftwerk hiuehlberg plant on hiay 24,1991, and is currently in its third fuel (BWR-4) started operating at 15 percent above cycle after restart. In a letter dated June 30,1992, original power in 1994. The Kernkraftwerk the NRC notified TVA that Unit 2 had Liebstadt (BWR-6) plant expects to receive demonstrated excellent plant performance, and approval for a 20-percent uprate in early 1996. would therefore be removed from the list of plants The Swiss nuclear regulatory authority and the warranting close NRC monitoring. However, the NRC have been actively involved in a program to NRC informed TVA that Units 1 and 3, would exchange information, including information remain in the close monitoring category and about the extended pmver uprates. would require explicit NRC cuthorization to be operated. | 'I\vo GE-designed BWRs in Switzerland have Following extensive NRC review and inspection of completed extended power uprate licensing TVA corrective actions, BFN Unit 2 was restarted actions. The Kernkraftwerk hiuehlberg plant on hiay 24,1991, and is currently in its third fuel (BWR-4) started operating at 15 percent above cycle after restart. In a {{letter dated|date=June 30, 1992|text=letter dated June 30,1992}}, original power in 1994. The Kernkraftwerk the NRC notified TVA that Unit 2 had Liebstadt (BWR-6) plant expects to receive demonstrated excellent plant performance, and approval for a 20-percent uprate in early 1996. would therefore be removed from the list of plants The Swiss nuclear regulatory authority and the warranting close NRC monitoring. However, the NRC have been actively involved in a program to NRC informed TVA that Units 1 and 3, would exchange information, including information remain in the close monitoring category and about the extended pmver uprates. would require explicit NRC cuthorization to be operated. | ||
The NRC is developing a staff position paper on extended power uprating for BWRs, based in part After restarting Browns Ferry Unit 2, TVA on the NRC review of the GE licensing topical focused attention on Unit 3 restart. In general, report. This staff position paper will provide TVA adopted the approved Unit 2 methods, industiy guidance for developing license criteria, and technical positions for restoring Unit amendment applications for extended power 3 to service, and corrective actions were uprate, as well as NRC staff guidance for completed in 1995. However, TVA revised some reviewing those applications. Programs based primarily on lesson learned from Unit 2. The NRC staff ro,bwed and approved the proposed changes, and TVA completed the corrective actions in 1995. | The NRC is developing a staff position paper on extended power uprating for BWRs, based in part After restarting Browns Ferry Unit 2, TVA on the NRC review of the GE licensing topical focused attention on Unit 3 restart. In general, report. This staff position paper will provide TVA adopted the approved Unit 2 methods, industiy guidance for developing license criteria, and technical positions for restoring Unit amendment applications for extended power 3 to service, and corrective actions were uprate, as well as NRC staff guidance for completed in 1995. However, TVA revised some reviewing those applications. Programs based primarily on lesson learned from Unit 2. The NRC staff ro,bwed and approved the proposed changes, and TVA completed the corrective actions in 1995. | ||
TVA PROJECTS A restart panel, consisting of NRC managers and the Senior Resident Inspector, was established in In September 1985, the NRC star fissued a letter February 1995 to coordinate NRC staff activities, to the Chairman of the Board of Directors of the monitor Browns Ferry activities, and keep the Tennessee Valley Authority (TVA), discussing Regional Administrator informed regarding the significant continuing weaknesses in TVA restart of Unit 3. The NRC staff conducted performance, and stating that management of the numerous inspections of licensee activities, TVA nuclear program was ineffective. including verifying licensee corrective actions identified from the TVA Nuclear Performance Plan, Thil action items, generic letters, bulletins, and operational readiness reviews. TVA Browns Ferry successfully completed the BFN Unit 3 fuel load on October 29,1995; and, on November 19,1995, The Browns Ferry Nuclear (BFN) Plant the NRC authorized TVA to restart the unit. BFN (Alabama) consists of three boiling-water reactor 3 reached criticality and has completed a power units, which are owned and operated by the ascension test program enroute to full power Tennessee Valley Authority (TVA). BFN Unit 2 operation. TVA remains ahead of their schedule was shut down for a planned refueling outage in to return BFN Unit 3 to full power by February September 1984. BFN Units 1 and 3 were 1996. | TVA PROJECTS A restart panel, consisting of NRC managers and the Senior Resident Inspector, was established in In September 1985, the NRC star fissued a letter February 1995 to coordinate NRC staff activities, to the Chairman of the Board of Directors of the monitor Browns Ferry activities, and keep the Tennessee Valley Authority (TVA), discussing Regional Administrator informed regarding the significant continuing weaknesses in TVA restart of Unit 3. The NRC staff conducted performance, and stating that management of the numerous inspections of licensee activities, TVA nuclear program was ineffective. including verifying licensee corrective actions identified from the TVA Nuclear Performance Plan, Thil action items, generic letters, bulletins, and operational readiness reviews. TVA Browns Ferry successfully completed the BFN Unit 3 fuel load on October 29,1995; and, on November 19,1995, The Browns Ferry Nuclear (BFN) Plant the NRC authorized TVA to restart the unit. BFN (Alabama) consists of three boiling-water reactor 3 reached criticality and has completed a power units, which are owned and operated by the ascension test program enroute to full power Tennessee Valley Authority (TVA). BFN Unit 2 operation. TVA remains ahead of their schedule was shut down for a planned refueling outage in to return BFN Unit 3 to full power by February September 1984. BFN Units 1 and 3 were 1996. | ||
| Line 2,259: | Line 2,259: | ||
: national security. This rule applies only to the prevention, accident analysis, and fire protection, GDPs operated by the USEC. among others. | : national security. This rule applies only to the prevention, accident analysis, and fire protection, GDPs operated by the USEC. among others. | ||
The USEC submitted its initial application for . | The USEC submitted its initial application for . | ||
certification on April 18,1995. However, the NRC On September 15,1995, the USEC submitted a determined that USEC's April 1995 submittal did revised application, which the NRC accepted for I not include adequate information for the NRC to review by letter dated September 21,1995. | certification on April 18,1995. However, the NRC On September 15,1995, the USEC submitted a determined that USEC's April 1995 submittal did revised application, which the NRC accepted for I not include adequate information for the NRC to review by {{letter dated|date=September 21, 1995|text=letter dated September 21,1995}}. | ||
, assess compliance with the standards established Subsequently, the NRC issued its first request for , , | , assess compliance with the standards established Subsequently, the NRC issued its first request for , , | ||
l for the GDPs. Therefore, the NRC rejected the additional information (RAI) in October 1995. l i application on May 5,1995. The NRC's decision Public meetings to receive pubh,c comments on i j to reject the application did not constitute a the USEC s application were held in late 1995 at determination that the plants were unsafe. the Kentucky and Ohio plant sites. | l for the GDPs. Therefore, the NRC rejected the additional information (RAI) in October 1995. l i application on May 5,1995. The NRC's decision Public meetings to receive pubh,c comments on i j to reject the application did not constitute a the USEC s application were held in late 1995 at determination that the plants were unsafe. the Kentucky and Ohio plant sites. | ||
Latest revision as of 13:39, 14 December 2021
| ML20134L768 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1996 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-1145, NUREG-1145-V12, NUDOCS 9611210208 | |
| Download: ML20134L768 (337) | |
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This Annual Report for 1995 of the United States Nuclear Regulatory Commission is forwarded for your transmittal to the Congress, as required by 1 Section 307(c) of the Energy Reorganization Act of1974. The report is devoted mainly to coverage of events and activities occurring in fiscal year 1995, with additional treatment of events after that period where circumstances warranted. Respectfully, Shirley Ann Jackson Chairman
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ii PREVIOUS REPORTS IN TIIIS SERIES 1975 NRC Annual Repon, published April 1976 1976 NRC Annual &pon, published April 1977 NUREG-0400,1977NRC Annual Ryon, published April 1978 NUREG-0516,1978 NRC Annual Repon, published February 1979 NUREG-0690,1979 NRC Annual Repon, published March 1980 NUREG-0774,1980 NRC Annual Repon, published June 1981 NUREG-0920,1981 NRC Annual Repon, published June 1982 NUF ' r i 0998,1982 NRC Annual Repon, published June 1983 NURIiG-1090,1983 NRC Annual Repon, published June 1984 NUREG-1145, Vol 1,1984 NRC Annual Repon, published June 1985 NUREG-1145, Vol. 2,1985 NRC Annual Repon, published June 1986 NUREG-1145, Vol. 3,1986 NRC Annual Repon, published June 1987 NUREG-1145, Vol 4,1987NRC Annual Repon, published July 1988 NUREG-1145, Vol. 5,1988 NRC Annual Repon, published July 1989 NUREG-1145, Vol. 6,1989 NRC Annual Repon, published July 1990 NUREG-1145, Vol. 7,1990 NRC Annual Repon, published July 1991 ; NUREG-1145, Vol. 8,1991 NRC Annual Repon, published July 1992 ) NUREG-1145, Voi. 9,1992 NRC Annual Repon, published July 1993 NUREG-1145, Vol.10,1993 NRC Annual Repon, published August 1994 NUREG-1145, Vol.11,1994 NRC Annual Repon, published June 1995 l i l l l The 1995 NRC Annual Repon, NUREG-1145, Vol.12, is available from U.S. Government Printing Office j P.O. I3ox 37082 l Washington, D.C. 20402-9328 i i _ - - _ - _ - _ _ _ _ - _ _ _ . - _ _ m e
1 l lii )1 j 1 CONTENTS Previous Reports in th.is Series ............................................................ in NRC Annual Report Statutory Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xi Chapter 1: Highlights for Fiscal Year 1995 Changes in the Commission and NRC's Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Strategic Assessment and Rebaselining Initiative . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Power Reactor Regulation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Nuclear Materials Regulation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 International Coope ration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Table 1. Fuel Cycle Licensing Actions (Safety / Safeguards) Completed in FY 95 . . . . . . . . . . . . . . . 6 NRC License and Annual Fees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Administrative Accom plish ments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Chapter 2: Nuclear Reactor Regulation Lice nsing the Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Pa rt 50 Licensing Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Part 52 Licensi ng Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 License Applications. Issuances, and Decommissioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 S p eci al Ca s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 TVA Proj ec ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Plan t Li ce nse Ren ewal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 R ulem aki n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Regulatory Guidance Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 In dustry Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .............. 23 Improving the Licensing Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 Ongoing Regulatory Improvement Initiatives . . . . . . . . . . . . . . . . .... .. .................. 23 Standardization of Reactor Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Next-Generation Reactor Designs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Pre-application Review of the MHTGR Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... 26 Testing for Passive Designs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ... .. 26 Early S i te Pe rm i ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 Improved Standard Technical Specifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 Inspection Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ ........... ..... 28 Reactor Inspection Program . . . . . . ...... ......... . ...... .... . ............... 29 Special Team Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 30 Vendor Inspection Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Performance Evaluation ............................................. ......... ......... 32 Systematic Assessment of Licensee Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
.= . . . . - . .
c IV 2 1 . 1 Inspecting the Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 j H u m a n Fa c t o r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Instrumentation and Control System Upgr' des a .......................................... 35 Maintenance . . . . . . . . . . . . . .................................................. ...... 36 Operator Lice ns i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 Plant Performance Reviews . ......................................................... 38 Senior Management M eetings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 Em ergen cy Prep a re d a es s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 l S a fe ty Revi ews . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 l Probabilistic Risk Assessment Policy Statement and Implementation Plan . . . . . . . . . . . . . . . . . . 41 Reactor Vessel M aterials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 I High. Performance Computing in NRR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 i Performance of Motor-Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 i l Evaluation of Shutdown and Low-Power Risk Issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 S team Generator Issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... 45 Primary Water Stress Corrosion Cracking . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 Radiation Protection at Nuclear Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 Environmental Radioactivity Near Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 Occupational Exposure Data and Dose Reduction Studies . . . . . . . . . . . . . . . . . ............. 49 Age-Related Degradation of BWR Internals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 Environmental Qualification of Electric Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 i ECCS Strainer Blockage in BWRs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 ! Cleanu o at Three Mile Islan d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 Loss o / Spent Fuel Pool Cooling Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 Reactor Engineer Intern Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 Antitrust Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ 54 Indemnity, Financial Protection, and Property Insurance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 1995 Insurance Premium Refunds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 Property Ins u ra n ce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Advisory Committee on Reactor Safeguards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Chapter 3: Operational Information and Investigations and Enforcement Actions Analysis and Evaluation of Operational Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 , Analysis of Reactor Operational Experience . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60
'Pable 1. AEOD Reactor Reports Issued During FY 95 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 Allegations .. .......... .................. ........................................ 66 Analysis of Nuclear Materials Experience . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66 Radiation Exposures from Reactors and Nonreactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69 Abn o rm al Occu rren ces . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 Risk an d Reliability Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 Table 2. Abnormal Occurrences Reported During FY 1995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71
'Pable 3.1994 Accident Sequence Precursors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 74 Incident Response Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......................... 79 Incident Investigation Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 Diagnostic Evaluation Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... 83 International Support Activities . . . . . . .............. ...... ..................... . 84 Limited Participation in the International Nuclear Event Scale . . . . . . . . . . . . . . . . . ........ 84 Lisbon Initiative Activities ........................ ............. ... ........ ....... 84 Table 4. U.S. Events Reported on the International Scale 1995. . . . ... . .......... ...... 85
Techni cal Raini ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 Committee to Review Generic Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 O ffice of Investigations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 Department of J ustice Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 88 En force m ent Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 88 O ffice o f En forc e m e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 90 Overview of NRC Enforcement Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 Chapter 4: Nuclear Materials Regulation Storage and Transportation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 Interim S pent Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 Certificates of Compliance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 Creation of Spent Fuel Project Office . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 Development of the D y Cask Storage Action Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 Revision of 10 CFP L% 71 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 T ansportation and Storage Inspection Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 Materials Licensing and Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96
'Ihble 1. Distribution of NRC-Administered Nuclear Materials Licenses . . . . . . . . . . . . . . . . . . . . 96 Materials Licensing Business Process Reengineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96 H u m a n Fac to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 Regulatory Impact Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 Integrated Materials Performance Evaluation Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Ind us trial Us es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 Me d i c al Us es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 Chapter 5: Fuel Cycle Safety and Safeguards Fuel Cycle Licensing and Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 Fuel Cycle Action Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 Fuel Cycle Licensing Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104 Table 1. Fuel Cycle Licensing Actions (Safety / Safeguards) Completed in FY 95 . . . . . . . . . . . . . 1M Fuel Cycl e Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 Fuel Cycle Safety Licensing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105 Fuel Cycle Safety Ins pections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 Facilities and Transportation Safeguards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 Fuel Cycle Safeguards Licensing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 Fuel Cycle Safeguards Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 Reactor Safeguar ds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 Transportation Safeguards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............. 114 Inte rn ati o n al Activi ti es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114 International Safeguards Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 114 Former Soviet Union Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 115 International Physical Protection Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 116 Nuclear Materials Management and Safeguards System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 Safety and Safeguards Event Evaluation and Response . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 Reporting of Nuclear Criticality Safety Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 Threat Assessment and Liaison / Design-Basis Threat / Incident Response Activities . . . . . . . . . . 117 Safeguards Summary Event List . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 118
V] Safety and Safeguards Regulatory Activities and Issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 118 Proposed Rules and Studies
..... ... ......................................... 118 G uid an ce Doc u m en ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... ..... .120 Chapter 6: Waste Management High-Level Was t e Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 Regulatory Development Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 Technical Assessment Capability for Repository Licensing Reviews . . . . . . . . .............. 124 Yucca Mountain Site Characterization Reviews and Interactions . . . . . . . . . . . . . . . . . . . . . . . .124 Interactions With Affected Governmental Units and Indian Tribes . . . . . . . . . . . 125 Quality Assurance Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............. . . . . . . . . . . . 125 Center for Nuclear Waste Regulatory Analyses ....................................... 125 Low-Level Waste Management Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126 Regulations an d G uidance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126
'Itchnical Assistance to the States . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .128 Cooperation With Other Federal Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 128 Intern ational Cooperation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 129 Decommissioning of Nuclear Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 130 i Regulations an d G uidance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 130 Materials Decommissioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ...... 130 Reactor Decom missioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 132 '
Management of Uranium Recovery and Mill Tailings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 133 Regulatory Development and Guidance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134 Licensing and Inspection Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134 Remedial Action at Inactive Sites . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 135 i Advisory Committee on Nuclear Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 135 Chapter 7: Communicating With the Public and the Government Communication With the Public . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .139 Public Responsiveness Initiatives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139 Com mission Meetings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139 A dvi s ory Com m i t tees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 140 Public Meeting Notice Sys tem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 141 Headquarters Public Document Room . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 141 Local Public Document Room Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... ....... 142 Commission History Program . . . . . . . . . . . . .............. .. .... ......... ........ 142 Public Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .................. ..... .... ... 143 News Confe re nc es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143 Enforcement Conferences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143 School Vol unteers Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 144 Communication With the Congress . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 146 Cooperation With States, Indian Tribes, and Other Federal Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . 146 Agreement States Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 146 State, Local and Indian Relations Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 151 Fede ral Liaison . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............................ 153 . e i
Yli Chapter 8: International Cooperation Fiscal Year 1995 Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 155 l Bilateral Safety Information Exchange . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 156 i Safety Cooperation Arrangements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 156 l Foreign Assignees Working at the NRC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157 Bilateral Nuclear Safety Cooperation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157 Forme r Soviet Union . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157 Central an d Eastern Europe . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 159 i Pa ci fi c Ri m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 161 i l Western Eu rope an d Canada . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 Latin Am e ric a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 165 So ut h Afri c a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 166 Multilateral Nuclear Safety Cooperation . . . . . . . . . . . . . . . . . . . . . .............................. 167 International Atomic Energy Agency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 167 N u clear Ene rgy Age n cy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 168 Cooperative Nuclear Safety Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 170 Export and Import Licensing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 170 NRC's Export / Import Role . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 170 NRC Export Licensing Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 171 Nuclear Suppliers G roup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 171 Subgroup on Nuclear Export Coordination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 171 Department of Energy Technology Transfers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 172 International Safeguards and Physical Protection Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 172 Assistance to FSU in Nuclear Materials Safeguards and Physical Protection . . . . . . . . . . . . . . . 172 Other Physical Protection Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 172 Nuclear Nonproliferation Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 173 U.S. Nonp roliferation Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 173 NPT Extension and Review Conference . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 173-Chapter 9: Nuclear Regulatory Research Reacto r Regul ati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 175 1 Reactor Aging and License Renewal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 175 Engineering Standards Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 187 I Reactor Safety Assessment and Reg 21ation Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 188 Table 1. Issues Prioritized in FY M95 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 209 i Table 2. Generic Safety Issue Resolved in FY 1995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 209
'Ihble 3. Generic Safety Issues Scheduled for Resolution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 210 Standard Reactor Designs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 216 M ateri als Us e rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 219 Nuclear Materials Research and Regulation Development . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 219 Low-Level Waste and Decommissioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 222 Development of Low-Level Waste Regulation and Guidance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 222 M aterials and Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 222 Hydrology and Geochemistry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 225 Compliance, Assessment, and Modeling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 225 Decommissioning and Environmental Protection Regulation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 225 H igh -Level Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 227 High-Level Waste Rulemaking . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 227
..e High-Level Waste Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 227 Engineered Systems Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 227 i Geologic Systems Research . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 228 1 Performance Assessment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 229 Chapter 10: Proceedings and Litigation O ffice of th e Sec retary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 231 l Atomic Safety and Licensing Boards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 231 l
Responsibilities of Licensing Boards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 232 Technology and Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 232 Pers onnel C hanges . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 233 Pan el Cas eloa d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 233 Significant Commission Decisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 236 l J u di ci al Revi ew . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 239 I Pe n din g Cas es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 239 l Significant Judicial Decisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 240 l 1 4 1 Chapter 11: Management and Administrative Services ) Personnel M anage m e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 243 1995 NRC Staff-Years Expended . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 243 Rec rui tm e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 243 Award s an d Recogniti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 243 Benefits............................................................................. 244 Labor Re l ati ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 244 National Performance Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 244 Training and Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 244 Employee Assistance and Health Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 245 Information Resources Management . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 245 NRC Technical Lib rary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 245 The Washington National Records Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 246 NRC Document Control Desk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 247 Network Software Upgra de . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248 Com p ute r Vi ruses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248
- Administrative Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248 Fa cili ti es Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248 Property M anagement Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 249 Freedom of Information Act Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 249 Sec u ri ty Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 249 Con tract Man age me nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 250 Office of the Inspector G eneral . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 250 OIG Fiscal Year 1995 Au dits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 251 OIG Fiscal Year 1995 Investigations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 254 Office of Small Business and Civil Rights . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 256 Small and Disadvantaged Business Utilization Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 256 Civil Rights Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 257 Affirmative Action and Federal Women's Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 259
ix Appendices Appendix 1-NRC Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 263 Appendix 2-Atomic Safety and Licensing Board Panel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 269 Appendix 3-NRC Federal Advisory Committees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 271 Appendix 4-Local Public Document Rooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 275 Appendix 5-Regulations and Amendments-Fiscal Year 1995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 283 Appendix 6-Regulatory Guides-Fiscal Year 1995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 291 Appendix 7-Civil Penalties and Orders-Fiscal Year 1995 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 293 Appendix 8-Nuclear Electric Generating Units in Operation or ' Un de r Construction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 311 i i Index .............................................................. 321 i
=_
xi 3 NRC Annual Report Statutory Reporting Requirements ENERGY REORGANIZATION ACT OF Section 205 requires development of "a long 1974, AS AMENDED term plan for projects for the development of new or improved safety systems for nuclear power plants" and an annual updating of that plan. (See Section 307(c) directs the Commission to Chapter 9.) include in its Annual Report statements and descriptions concerning: Section 209 requires the Commission to include in each Annual Report a chapter describing the
" the short-range and long-range goals, status of the NRC's domestic safeguards program.
priorities, and plans of the Commission as they (See Chapter 5.) are related to tl1e benefits, costs, and risks of Section 210 requires the Commission to submit "a n clear power.,(See Chapters 1,2,3,4,6,9,and plan providing for the specification and analysis ' -) of unresolved safety issues relating to nuclear reactors," and to include progress reports in the
"...the Commission's activities and findings in Annual Report thereafter concerning corrective l the following areas- actions. (See Chapter 9.)
"(1) insuring the safe design of nuclear power plants and other licensed facilities.. ." (For reactor design, see Chapters 2 and 9; for materials NUCLEAR NONPROLIFERATION ACT OF facilities, devices, and transportation packaging, 1978 see Chapters 4 and 5; for waste disposal facilities, ,
see Chapters 6 and 9.) Section 602 requires annual report; by the Commission and the Departmera of Energy to
"(2) investigating abnormal occurrences and " include views and recommendations regarding I defects in nuclear power plants and other licensed the policies and actions of the United States to facilities...."(See Chapters 2,3, and 4.) prevent proliferation which are the statutory responsibilities of those agencies.. "(See
"(3) safeguarding special nuclear materials at all Chapter 8.)
stages of the nuclear fuel cycle.. ."(See Chapters 5,8, and 9.)
"(4) investigating suspected, attempted, or ATOMIC ENERGY ACT OF 1954, AS actual thefts of special nuclear materials in the AMENDED licensed sector and developing contingency plans for dealing with such incidents.. ."(See Chapters 5 Section 170(i) directs the Commission to report and 9.) annually on indemnity action implementing the Price Anderson Act which provides a system to
"(5) insuring the safe, permanent disposal of pay public indemnity claims in the event of a high-level radioactive wastes through the licensing nuclear accident. (See Chapter 2.)
of nuclear activities and facilities.. ."(See Chapters 6 and 9.)
"(6) protecting the public against the hazards of PUBLIC LAW 96-295 low-level radioactive emissions from licensed nuclear activities and facilities.. ."(See Chapters Section 303 directs the Commission to report 2,4, and 6.) annually a statement of-
xii
' (1) the direct and indirect costs to the (2) the fees paid to the Commission for the Commission for the issuance of any license or issuance of any license and for the inspection of 4
permit and for the inspection of any facility; and any facility."(See Chapter 1.) i I < l . 1 i ' 1 t 1 l l
- y y ,
, a l \fE.
F} P CHAPTER 1 i A 4 l -. ! a ! .A ! HIGHLIGHTS FOR FISCAL YEAR 1995 ~ t l This 21st annual report of the U.S. Nuclear nuclear materials and facilities from theft and/or l Regulatory Commission (NRC) covers sabotage; by the issuance of rules and standards; i accomplishments, activities, and planning for and by inspection and enforcement actions. l fiscal year 1995 (FY 95)-October 1,1994, i through September 30,1995. It notes activities Appendices 1 through 8 provide additional detail. that occurred early in the next fiscal year if they l are significant, including changes in the j l Commission and the organization of NRC. ' CHANGES IN THE Its issuance complies with Section 307(c) of th Energy Reorgam,zat,on i Act of 1974, as amended, COMMISSION AND NRC'S which requires that an annual report be submitted ORGANIZATION to the President for transmittal to the Congress. On April 6,1995, the Senate confirmed President The NRC was created by enactment in the Clinton's nomination of Dr. Shirley Ann Jackson Congress of the Energy Reorganization Act of as NRC Commissioner. Dr. Jackson was sworn in 1974. It is an independent agency of the Federal as Commissioner on May 2,1995. A ceremonial
, Government. The five NRC Commissioners are swearing-in ceremony for Commissioner Jackson i nominated by the President and confirmed by the was performed by Vice President Gore on
- United States Senate.The Chairman of the May 26,1995,in the Indian Treaty Room of the
! Commission is appointed by the President from Old Executive Office Building. President Clinton i among the Commissioners confirmed by the signed an order on June 14,1995, naming j Senate. Commissioner Jackson as Chair of the Naclear Regulatory Commission effective July 2,1995.
- The mission of the NRC is to ensure that civilian Chairman Ivan Selin resigned on July 1,1995, one l i
uses of nuclear materials in the United States-in year prior to the expiration of his five-year term. l
- the operation of nuclear power plants and fuel On December 22,1995, the Senate confirmed l cycle plants, and in medical, industrial, and Greta J. Dieus as NRC Commissioner. She was j research applications-are carried out with sworn in as Commissioner by Chairman Jackson j adequate protection of public health and safety, on February 15,1996, and her term will expire j the environment, and national security. The June 30,1998.
. agency also has a role in combating the i proliferation of nuclear weapons material Between July 1,1995, and February 15,1996, the
{ worldwide. The NRC accomplishes its purposes Commission lacked the three members needed for j by the licensing and regulatory oversight of a quorum. During that period, the Commission
; nuclear reactor operations and other activities operated under a delegation of authority to the j involving the possession and use of nuclear Chairman, as authorized by Section 1 of NRC 1 materials and wastes; by the safeguarding of Reorganization Plan No.1 of 1980.
1 l i
2 m In addition to changes in the Commission during Development of a Strategic Plan, and Phase IV: FY 95, several office directors and a regional Implementation, administrator retired: Robert M. Bernero, Director of Nuclear hiaterial Safety and Safeguards, was succeeded by Carl J. Paperiello; PHASE I: STRATEGIC ASSESSMENT Eric S. Beckjord, Director of Nuclear Regulatory Research, was succeeded by David L. hforrison; The first phase, the Strategic Assessment phase, Ben B. Hayes, Director of Investigations, was began in August 1995 and is expected to be succeeded by Guy P. Caputo; and, finally, John B. completed in the Spring of 1996. The Steering h1artin, Administrator for Region llI, was Committee began with a bottom-up approach for succeeded by Hubert J. hiiller. assessing where the agency is today, with an examination of current NRC functions and In other organizational changes, John C. Hoyle activities. This assessment included approximately succeeded Samuel J. Chilk as Secretary of the 4,500 activities that the Steering Committee Commission. hir. Chilk was appointed as reviewed to thoroughly understand what the Director, Commission Decision Tracking System. agency is doing, why the agency is doing it, and Leo Norton was designated as Acting Inspector what factors most need to be considered in General when David Williams resigned to take the providing options for change. Starting with this position of Inspector General at the Social information, the Steering Committee applied Security Administration. top-down strategic thinking to define strategic and l direction-setting issues whose resolution will The NRC organization as of December 31,1995, influence the future direction of the agency. Each is shown in Appendix 1. of these direction-setting issues is being developed into an options paper for Commission consideration. STRATEGIC ASSESSMENT AND REBASELINING PHASE II: REBASELINING AND ISSUE PAI,ERS INITIATIVE The second phase builds on the issues identified in Phase I. Two parallel and interrelated actions The environment in which the NRC conducts its activities is rapidly changing as a result of many are planned for Phase II. They are development l and resolution of issue papers and providmg the I influences. These include resource restraints, Commission appropriate Steering Committee changes in the industry that NRC regulates, and insight for the FY 1998 budget. The Commission's the potential for new and revised mission decisions will result in a rebaselining or a requirements. Against this backdrop of change in resetting of the agency's goals. our regulatory and fiscal erwironment, the Chairman established the Strategic Assessment and Rebaselining Initiative. To oversee this PHASE III: DEVELOPMENT OF A activity, a Strategic Assessment and Rebaselining STRATEGIC PLAN Steering Committee (Steering Committee) was formed of senior agency managers. The Steering In Phase III, the Strategic Plan will be developed : Committee is assessing where the NRC is today from the agency's mission statement, its strategic 1 and developing options which the Commission vision, general goals, and the Commission's can consider in determining the agency's future decisions on the issue papers. The development of { path. His effort was initiated in August 1995, and the Strategic Plan will be guided by the l is being completed in four phases. The effort is requirements contained in the Government I divided into four broad phases that will be carried Performance and Results Act. The Strategic Plan out sequentially, with each phase building on the will be the agency's tool for setting priorities and preceding phase. As described below, they are alk)cating resources consistent with the vision and Phase I: Strategic Assessment, Phase II: goals of the agency. It is anticipated that the Rebaselinicg and Issue Papers, Phase III: Strategic Plan will be completed early in 1997.
3 PHASE IV: IMPLEMENTATION IMPLEMENTATION STATUS OF 5 SAFETY ISSUES Phase IV, the implementation phase, may begin as The NRC tracks the status of the implementation soon as the Commissioners make final decisions and verification of actions involving major safety on the issue papers. The implementation phase
, issues that affect multiple facilities, including the includes implementing the Commission s .
Three-Mile Island (TMI) Action Plan decisio,ns based on the issue papers, generating
, requirements, unresolved safety issues (USIs),
Commission papers to resolve related strategic generic safety issues (GSIs), and all other issues, and complymg with Comnu,ssion guidance
, multiplant actions (MPAs). More than 99 percent based on the Strategic Plan. The implementation of the TMI Action Plan Requirements, about 96 phase will also melude developing a framework
, percent of the USIs, about 99 percent of the GSIs, that allows for updatmg the Strategic Plan and for
, and about 92 percent of the other MPAs had been '
< integratmg the Strategic Plan with the budget implemented at the 107 operating plants as of process, performance monitoring and reporting September 30,1995. processes, and the process for development of i future Commission decisions. IMPROVED STANDARD TECHNICAL SPECIFICATIONS
; The NRC places its highest priority on license POWER REACTOR amendment applications to fully implement the ~
Improved Standard Technical Specifications REGULATION (STS), and more than 70 percent of power reactor plants are planning to convert. In a related effort, ! the NRC continues to work with the industry to develop ongoing improvements to technical specifications and license amendment practices. These activities are supported by the August 1995 POWER REACTOR LICENSING amendment to NRC regulations, regarding the ACTIONS content of technical specificatic .s. i No new licenses were issued during fiscal year RENEWAL OF OPERATING 1995 (FY 95). LICENSES Either routine activity or unexpected events at a The first operating license of a currently act.ive nuclear facility can result in a need for the NRC , to take licensing actions. Routine actions Pl ant-Big Rock Point-will expire in the year 2000, and the operating licenses of nearly 20 occurring after license issuance include license Percent of these plants will expire by the end of amendment requests, possibly involving public the year 2010. Preparation for expected b,eense hearings; requests for exemption from regulations; new regulations requiring "backfit" modifications renewal appli; cations contmues to be a high Priority. Durmg FY 95, the NRC staff issued a to operating reactors; and orders for modification revised rule to simplify license renewal, and of a license. During FY 95, the NRC's Office of c ntm, ued to develop ,mplementat, i ion guidance. Nuclear Reactor Regulation (NRR) completed about 1871 licensing actions. About 98 percent of these actions were directed at specific plants and licensees. The balance were multiplant actions IMPROVING THE LICENSING deriving from the imposition of NRC PROCESS requirements. During FY 95, total inventory of licensing actions under review decreased from The Commission strongly encouraged the nuclear about 1293 to 1000. (See Chapter 2.) industry to standardize the next generation of
i 4 l reactor designs, and to resolve design- and training to the resident and region-based site-related issues early in the licensing process. inspectors. The training will be completed before The NRC plans to realize the benefits of the rule takes effect on July 10,1996. standardization with the new licensing process in the Code of Fedem! Regulations, Title 10, Part 52 (10 CFR Part 52), which includes provisions for design certification, early site permits, and SPECIAL REACTOR PLANT combined licenses. In addition, the NRC is INSPECTIONS preparing final standard design certification rules for two evolutionary light-water reactor (LWR) designs, these rules should be published in During FY 95, the NRC headquarters and mid-1996. regional staffs continued to perform special team inspections involving 4 to 10 inspectors and l requiring 1 to 2 weeks of onsite inspection. The i objective of these special inspections was to determine whether, when called upon to do so in POWER PLANT MAINTENANCE an emergency, the nuclear plant's systems and l personnel would perform their safety functions in From September.1994 to March 1995, the NRC the manner set forth in the facility's safety staff performed a series of nine pilot site visits to analysis report. verify the adequaev of a draft version of inspection procedure (IP) 62706. The NRC will use this procedure to verify each licensee's implementation of the mamtenance rule,10 CFR GRADED QUALITY ASSURANCE 50.65, " Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power One activity associated with the probabilistic risk Plants." The NRC performed these pilot visits at assessment (PRA) implementation plan is the sites that had volunteered to have the staff review development of a graded quality assurance (QA) their maintenance rule implementation before the methodology. The purpose of graded QA is to effective date of the rule, July 10,1996. adjust the application of licensee QA controls (such as reviews, inspections, audits, and other The staff documented the results of these site verifications) so that they are conducted with an visits in NUREG-1526, " Lessons Learned from intensity proportional to the relative safety Early Implementation of the Maintenance Rule at significance of plant equipment. Thus, graded QA Nine Nuclear Power Plants." On June 27,1995, allows both licensee and staff resources to be the staff held a public workshop in St. Louis, focused on more safety-significant plant Missouri, to review the lessons learned from the equipment. Similarly, graded QA reduces the pilot site visits. On July 17,1995, the staff issued a resources that must be allocated for QA activities Commission Paper, SECY 95-179, to apprise the involving equipment of less safety significance. Commission of the status of recent and planned The staff envisions a process, similar to the maintenance rule activities. On August 31,1995, maintenance rule implementation, whereby a the staff issued the final version of IP 62706, licensee evaluation of both PRA input and which incorporated appropriate comments and deterministic considerations by an expert panel suggestions received from the public and industry would result in the categorization of plant representatives. equipment by safety significance. Beginning on July 10,1996, the staff will perform Initially, the staff focused on interacting with the baseline inspections of each licensee's Nuclear Energy Institute (NEI) during the implementation of the maintenance rule. These development of a document that could provide inspections > vill be conducted by resident and generic industry guidance on how to adjust region-based inspectors, and will be completed quality practices commensurate with equipment within 2 years. Tb ensure uniform implementation, safety significance. A Commission Paper, SECY the NRR maintenance section staff will 95-059, describes the initial stages of the project. participate in these inspections, and will provide During FY 95, three volunteer licensees indicated
5 a desire to work with the staff to develop graded information among individuals and computer QA implementation practices. In general, the systems during a routine license review. On current licensee QA controls would continue to average, the NRC took 84 days to complete a apply to safety-significant equipment, while less licensing action, although only 2 days were rigorous licensee QA controls would apply to actually needed to complete the technical safety equipment of less safety significance. The review of a typical licensing request. During the program would be subject to periodic assessments remaining 82 days, paper was either in transit or of plant and industry information to adjust both in the queue.The staff proposed to reduce the QA controls and safety significance licensing process to an average of four days. . Therefore, consistent with the goals of the National Performance Review and the Paperwork Reduction Act of 1995, the staff initiated an IIUMAN FACTORS COORDINATION innovative approach to improve management of inf rmation collections. As directed by the COMMITTEE Commission, the staff held various meetings and workshops to gather input from Agreement A task force established by the Deputy Executive States, licensees, and the public. The selected Director for Nuclear Reactor Regulation, Regional approach, called Business Process Reengineering
- Operations, and Research, recommended the (BPR), fundamentally changes the way work is formation of an interoffice committee to performed, to achieve significant improvements in coordinate the agency's human factors programs. speed, cost, and quality. This new process, BPR, As a result, the Human Factors Coordination will also most likely lead to more clear, consistent, Committee was established with representatives and timely regulatory guidance, ensuring that its l from NRR, the Office for Analysis and implementation will not have any adverse effect !
Evaluation of Operational Data (AEOD), the on public health and safety. In fact, many I Office of Nuclear Regulatory Research (RES), the licensees believe that fewer operational problems Office of Nuclear Material Safety and Safeguards will occur if the NRC is able to significantly (NMSS), and the regions. As required by its reduce the time necessary to process licensing charter, they began by developing a Human actions. Performance Program Plan that reflects the goals, objectives, and activities associated with the In the first BPR phase a core team of people who agency's human factors programs. The Committee work in licensing, administration, and information issued this program plan in August 1995, technology developed a generalized design for a new materials licensing process. Specifically the core team proposed using a graded licensing approach that matches the safety hazards associated with a license application. A more NUCLEAR MATERIALS streamiined workfiow for materiais licensing REGULATION 'ti "S iS "P*Ft*d * 'fsuh fr m the Business Process Reengmeermg imtiative. MATERIALS ACTIVITIES MATERIALS LICENSING BUSINESS PROCESS REENGINEERING During fiscal year 1995 (FY 95), the NMSS completed the following activities related to In October 1994, the staff began to examine the nuclear materials regulation: process used to issue materials licenses, in order to identify ways to improve the process. During e nearly 90 reviews of transportation and spent this examination, the staff found that licensing fuel storage packages, and 6 route approvals was being accomplished using a complex process for transporting special nuclear material and involving anywhere from 54 to 94 exchanges of spent fuel.
6
- cafety inspections of 7 transportation e Suppoit for meetings of the U.S.-Russia Joint packaging and dry spent fuel storage system Comtrission on Technological Cooperation in suppliers, and observations of 3 Department Energy and Space, chaired by Vice President of Energy (DOE) audits of multipurpose Gore and RLesian Prime hiinister canister (hfPC) contractors Chernomyrdin. NRC activities with Russia regarding nuclear safety and security issues e more than 4600 licensing actions on continued to play an important part.
applications for new byproduct materials licenses, as well as amendments and renewals e Nuclear safety cooperation with the New of existing licenses, and reviews of sealed Independent States of the former Soviet sources and devices Union and countries of Central and Eastern Europe. These activities included strength-e approximately 2109 materials licensee ening their regulatory organizations, training inspections foreign inspectors, and working together in the areas of operational safety and risk reduction. FUEL CYCLE LICENSING
- Efforts to help countries of the former Soviet ACTIVITIES Uni n-p rticul fly Russia, Ukraine, and Kazakstan-to improve their systems for protecting, controlling, and accounting for By the end of FY 95, the NRC had completed 121 nuclear materials. These efforts focused on fuel cycle licensing actions. Table 1 shows these improving regulatery programs and licensing actions by category. enhancing facility safeguards within the framework of agreements signed by the United States with these countries in the fall of 1993.
INTERNATIONAL
- Contmued efforts to work (m. conjunction COOPERATION with other U.S. Government and related entities) with countries of the former Soviet Union-specifically Russia, Ukraine, and During the fiscal year 1995 (FY 95) reporting Belarus-to study the health effects of period, the NRC continued its involvement in the exposure to ionizing radiation resulting from international arena, including the following the Chornobyl accident and from Russian noteworthy activities: defense-related activities.
Table 1. Fuel Cycle Licensing Actions (Safety / Safeguards) Completed in FY 95 Category No. of Actions Fuel Fabrication and Conversion 73 Critical Mass hiaterials 6 Fuel Research, Development, Pilot, and Fresh Fuel Storage 6 Other Source Materials 3 Material Control and Accounting 24-Physical Security 4 West Valley Demonstration 4 Department of Energy Waste Processing 1
f 7 l o Raising the priority of regulatory cooperation budget was appropriated from the Nuclear Waste with several Pacific Rim areas (Indonesia, Fund. Of the remaining $501.9 million,100 China, Korea, and Taiwan) that are percent was collected through fees and annual embarking on, or are considering, new or charges. A detailed account of NRC financial expanded nuclear power programs, management, with an audited financial report, is provided in the Fiscal Year 1995 Accountability o Maintaining an active information exchange Report (NUREG-1542), which will be available with coutries that have substantial nuclear April 1996. power programs, and with multilateral organizations promoting international nuclear safety as well as assuming a proactive role in support of significant international initiatives m the mterest of nuclear safety. ADMINISTRATIVE ACCOMPLISHMENTS o Playing a leading role in resolving implemen-tation issues for the international Convention on Nuclear Safety resolutions, which were submitted to the Congress in May 1995 for its advice and consent and ratification. If LABOR RELATIONS ratified, these resolutions could become effective during 1996. Implementation of U.S. On October 1,1993, the President signed obligations under the Convention will be Executive Order 12871 dealing with Labor-ceried out primarily by the NRC. A separate Management Partnerships in the Federal Convention on the Safety of Radioactive Government. The order expands the scope of Waste Management is now in active bargaining and calls for a more cooperative and ir ternational negotiation, with the NRC less confrontational relationship between labor p aying an active role in its development, and management. Pursuant to the order, the agency, and the union, have established an o Cantinuation of active, cooperative nuclear " agency partnership committee," as well as office safety research with other nations having and regional partnership committees, to foster a major nuclear power programs, including cooperative relationship and to identify problems France, Germany, Japan, and the United and propose solutions. The agency has also Kingdom. provided training in methods of dispute resolution, helping parties in a dispute to work together in framing possible resolutions. NRC LICENSE AND NATIONAL PERFORMANCE ANNUAL FEES REVIEW The Omnibus Reconciliation Act of 1990 (Public The Office of Personnel (OP) has been carefully Law 101-508) requires that in FY 95, the NRC reviewing the human resources management collect fees (under 10 CFR Part 170) and annual recommendations in the National Performance fees (under 10 CFR Part 171) that approximate Review (NPR) report, published in September 100 percent of the agency's budget authority, less 1993 and the follow-on report, Reinventing Human the amount appropriated to the NRC from the Resources Management. While many NPR Nuclear Waste Fund. Public Law 103-316 recommendations require changes in the law or in appropriated approximately $525.6 million to the OPM regulations, others may be implemented NRC for FY 95, and Public Law 104-19 without delay. The OP has already begun to (Emergency Supplemental) enacted a recision of implement some of the suggested changes. Two of
$1.7 million for a net FY 95 appropriation of the changes that will have an impact on the $523.9 million. Approximately $22.0 million of the agency are (1) the reduction in staff size and the l
I
8 ratio of supervisors and managers to employees, opened a " Snack 'N Go" store, specifically to sell and (2) the elimination or reduction of personnel sundries such as cards, chips, and sod >.s. directives and processes. While the former change will affect the nature of supervisory relationships, To enhance the safety and comfort of employees I the latter will provide management with more walking from one building to the other, the White flexibility and fewer procedural barriers in Flint Limited Partnership, Inc. awarded contracts managing the NRC's human resources. During to design and construct an enclosed link between FY 95, the ratio of supervisors and managers to Two White Flint and One White Flint. employees was decreased from 1:4.8 to 1:5.4 (a Construction is expected to be completed by the decrease of 12.5 percent), and seven Management end of September 1996. Directives were eliminated. In March 1995, the NRC's Office of Adminis-tration (ADM) published its policy concerning FACILITIES PROGRAM " " "' '" '" T "' "
$" ort During fiscal year 1995 (FY 95), several special Executive Order 12821, " Improving Mathematics facilities were completed on the plaza level of the and Science Education in Support of the National Two White Flint North (TWFN) complex in Education Goals," directs Federal agencies to the Rockville, Maryland. First, a newly renovated maximum extent possible to identify and transfer Health Unit opened in May 1995 in the One excess education-related equipment to elementary White Flint Nerth building for use of employees and secondary schools. Under these guidelines, within the complex. Second, an 8000-square foot, the NRC has established an aggressive program 300-seat, full-service cafeteria capable of serving for donating computer equipment to school approximately 1500 people daily, opened in June systems nationwide. In FY 95, the NRC donated 1995. A fitness center, opened in September 1995, more than 4700 pieces of computer equipment, offering a comprehensive wellness and fitness including color monitors, system units, and program to accommodate individual needs. Also, printers with an acquisition value of about $5.4 in September 1995, the Maryland Blind Industries million. I i
i
L p9 - p a CHAPTER 2 L + q IJ - s [" 7 s - wm . . . _ , , a NUCLEAR REACTOR REGULATION The NRC's Office of Nuclear Reactor Regulation e facility security and safeguards (including (NRR) is responsible for overseeing all aspects of fitness for duty) licensing and inspection of the Nation's nuclear , , power and research reactors. The NRC does not e mspection of nuclear component supph,er regulate reactors operated by the Department of facilities Energy (DOE) to furnish fissionable materials for use in nuclear weapons. NRR develops policy and inspection guidance for LICENSING THE NUCLEAR prog:ams assigned to the regional offices, and assesses the effectiveness and umformity of each POMR PLANT region's implementation of those programs. Responsibilities of NRR also include technical All nuclear power plants licensed to date have review, certification, and licensing of advanced followed a "two-step" licensing process as nuclear reactor facilities, as well as renewal of required by 10 CFR Part 50 (see Appendix 8). current power reactor operating licenses. In the First, the NRC issues a construction permit after course of these activities, NRR identifies reviewing the siting issues and preliminary design conditions and licensee performance that may issues. Second, the NRC issues an operating adversely affect public health and safety, the license after the detailed design is completed, the environment, or the safeguarding of nuclear Pl ant is built, and the NRC has reviewed and facilities. When such conditions arise, NRR takes inspected the plant. Owing to many factors, action in coordination with the responsible including the political and regulatory regional offices and licensees. NRR also assesses environment, the process sometimes generates and recommends or takes action in response to uncertainty as to whether a facility will be allowed incidents or accidents. In addition, NRR is to operate after billions of dollars have been spent responsible for licensing issues and regulatory on its construction. policy concerning the following areas: The issuance of 10 CFR Part 52 in 1989 established a streamlined licensing approach that o reactor operators (including the initial resolves many issues before construction of a licensing examination and requalification facility begins. The new licensing approach allows exammations) for the following distinct siting and design issues: o emergency preparedness (including e ppr v 1 f an e rly site permit for the siting f a nuclear power plant participation in emergency drills with Federal, State, and kwal agencies) e design certification of a final standard nuclear power plant design that could be used at e radiation protection multiple sites
10
- issuance of a combinedlicense-before (" docketing") the application, the staff publishes a construction-for a facility that references a notice of the fact in the Fedeml Register, and certified standard design to be built and furnishes copies of the application to the operated at a site appropriate State and local authorities, to a public document room established by the NRC o authorization for fuel load following facility near the proposed plant site, and to the NRC construction, upon successful demonstration public document room in Washington, DC. The .
that the stringent inspection, testing, analysis, NRC also publishes a notice of a public hearing i and acceptance criteria (ITAAC)in the in the Fedend Register and in local newspapers, l combined license are met giving 30 days for members of the public to l petition to intervene in the proceeding. Such Part 52 relies heavily on the existing 10 CFR petitions are entertained and adjudicated by the Part 50 technical requirements and regulations for NRC Atomic Safety and Licensing B' oard (ASLB) the reviews of reactor designs. Several applica- appointed to the case, allowing the petitioner the tions for design certification of advanced reactor right to appeal to the Commission. designs are already nearing completion. Next, the NRC staff reviews various safety, Before applications are submitted to initiate environmental, safeguards (from theft or either licensing process, considerable consultation sabotage), and antitrust issues. The safety review takes place between the applicant and the NRC is performed in accordance with the " Standard staff. This can involve many volumes of pre. Review Plans (SRPs) for Light-Water-Cooled liminary data, covering both safety and Reactors" (NUREG-0800), initially published in environmenta! aspects of construction and 1975 and periodically revised since then. The operation. The consultation may also involve plans set forth the acceptance criteria used in discussion of the major safety issues for new cvaluating the various systems, components, and designs, wh:ch may be resolvable under existing structures related to safety and in appraising the regulations or Commission policy, by requiring suitability of the proposed site; they also describe new Commission policy guidance to the staff, or the procedures to be used m performmg the by requiring confirmatory research and/or safety review, during which the NRC staff development. examines the applicant's PSAR. Through the safety review, the staff determines whether the plant design is safe and consistent whh NRC rules and regulations, whether the PART 50 LICENSING PROCESS apph,eant used valid methods of calculatmn, and whether the applicant conducted its analysis and According to 10 CFR Part 50, the nuclear power evaluation in sufficient depth and breadth to plant licensing process begins when an entity, ensure adequate safety. Upon verifying that the traditionally a utility, files an application for a applicant's PSAR meets the acceptance criteria of construction permit with the NRC. The the SRPs, the staff prepares a safety evaluation construction permit application includes a report (SER) describing the expected effect of the preliminary safety analysis report (PSAR), which construction and operation of the proposed describes the proposed nuclear plant design and facility on public health and safety. Following site safety issues, as well as an environmental publication of the SER, the independent Advisory report (ER), which addresses environmental Committee on Reactor Safeguards (ACRS) protection issues. Regulatmy Guides 1.70 and 4.2, completes its assessment ar.J meets with the staff respectively, provide guidance to prospective and the applicant. The ACRS then prepares a applicants concerning the standard format and report, under letter to the Chairman of the .NRC, content of these reports, presenting the results of its independent evaluation and its recommendations as to whether The NRC subjects each construction permit a construction permit should be issued. The staff application to an acceptance review to determine then issues a supplement to the SER, whether it contains sufficient information to incorporating any changes or actions adopted as a satisfy NRC requirements. Upon accepting result of ACRS recommendations. A public
11 hearing can then be held, generally in a decision is available by recourse to the Federal community near the proposed facility site, on the courts. safety aspects of the licensing decision. Where appropriate, the NRC may grant a limited work authorization to an applicant before a final In a similar manner, the NRC staff evaluates the decision is reached concerning the construction applicant's ER to assess the environmental permit, in order to allow work to begin at the site; consequences of construction and operation of the such a step can save months in construction time. l proposed facility. The staff performs this This authorization will not be given until the NRC environmental review in accordance with the staff has completed its reviews of environmental " Environmental Standard Review Plans for the impact and site suitability, and until the ASLB Environmental Review of Construction Permit has conducted the environmental impact and site Applications for Nuclear Power Plants" suitability hearing and has reached a favorable (NUREG-0555), published in 1979 and currently finding. To realize the desired savings in under revision. The plans establish the criteria construction time, the applicant must submit the used in benefits assessment in conformance with environmental portion of the application early in the National Environmental Policy Act (NEPA) the process. and NRC environmental protection regulations. Upon completion of the analysis, the staff The subsequent operating license review publishes and distributes a draft environmental reconsiders many of the issues evaluated during statement with specific requests for evaluation the construction permit review, and is also c f> ject and comment by Federal, State, and local to ACRS and ASLB review and agencies; other interested parties; and members of recommendations. the general public. Comments received are taken into account as the staff prepares the final environmental statement for the facility. Both th draft and the final statements are made available PART 52 LICENSING PROCESS to the public at the time of their publication. During the environmental review, the NRC staff Under 10 CFR Part 52, a number of licensing also conducts analyses and prepares a report act!ons can be initiated that do not immediately concerning the site suitability concerns of the lead to the construction of a nuclear power plant. proposed licensing action. A public hearing, The early sitepermit is considered a partial presided over by the appointed ASLB, may then construction permit, with many of the elements of be held to discuss the environmental and site the 10 CFR Part 50 construction permit suitability issues related to the proposed licensing previously described. An early site permit may be action (or a single hearing on both safety and incorporated by reference in a combined license environmental matters may be held). application, but is not required. Early site permit provisions allow early resolution of site safety, environmental protection, and emergency Antitrust reviews are carried out by the NRC and preparedness issues, independent of a specific the U.S. Attorney General before or during other design. The early site permit application must bcensmg reviews. If an antitrust hearmg is address the safety and environmental required, it is held separately from hearings on characteristics of the site, and must evaluate safety and the environment. Thereafter, as potential physical impediments to the required by law, the independent ACRS assesses development of an emergency plan. Additionally, the proposed project and the results of the earlier the application may address more detailed reviews, and makes its recommendations. The emergency preparedness issues. next phase is a mandatory public hean,ng conducted by a three-member ASLB, which Upon accepting the application, the staff makes an initial decision as to whether a publishes a notice of the fact in the same manner construction permit should bc grar.ted. This described for 10 CFR Part 50. The staff prepares decision is subject to appeal to the Commission SERs to document its findings on site safety by any person or youp with standing in the characteristics and emergency planning, as well as proceeding. Appeal beyond the final NRC draft, "for comment", and final environmental
12 statements to document findings related to an early site permit in the application for a environmental protection issues. The early site combined license. The advantage of this approach permit also has provisions for a limited work is that the issues resolved during the early site authorization to perform non-safety site permit hearing process and the design preparation activities, subject to redress, before a certification rulemaking process are precluded combined license application is processed. After from reconsideration at the combined license the NRC completes its review and the ACRS stage. An application for a combined license must completes its safety review, the NRC issues a contain allinformation required of applicants for notice for mandatory public hearing. The early both construction permits and operating licenses. site permit is valid for no less than 10 and no This includes the site-specific design features and more than 20 years, but can be renewed for 10 to acceptance criteria that were not approved in the 20 years. standard design certification, as well as portions of the emergency plan that were not approved for The design review process can involve up to three the early site permit. If an application does not stages of staff review, including preliminary incorporate by reference either a certified design design approval (PDA), final design approval or an early site permit, the applicant must include (FDA), and design certification through all relevant informa, tion to make the application rulemaking. The PDA is an optional, preliminary complete, and this mformation is subject to approval of a standard plant design. The FDA is hearings. Upon accepting application, the staff a final design approval, issued by the staff, publishes a notice of the fact in the same manner deeming a standard design acceptable for described for Part 50. The NRC staff and ACRS incorporation by reference in individual facility then review the combined license application for license applications. The FDA can be referenced those issues not resolved in the early site permit in construction permit and operating license or the design certification. Following this review applications under Part 50, or in combined and before the license is issued, the NRC holds a construction permit and operating license mandatory hearing. Additionally, the combined applications under Part 52. The FDA is followed hcense review meludes an antitrust review, which by certification of the standard plant design is carried out by the NRC and the U.S. Attorney through a rulemaking by the Commission, which General;if an antitrust heanng is required,it is also identifies the ITAAC for the design. The held separately from hearings on safety and the ITAAC specify the criteria for those inspections, environment. The issuance of a combmed beense tests, and analyses that are necessary and Permits an entity to construct and operate the sufficient for a licensee to perform in order to Pl ant. For this reason, the combmed beense under provide a reasonable assurance that a facility 10 CFR Part 52 is sometimes referred to as a referencing the standard design, has been built "one-step" licensing process. and will operate in accordance with the design When the NRC issues a combined license to an certification and applicable regulations. The entity, the recipient is permitted to construct the design certification rule is valid for 15 years, and plant in accordance with the approved design on can be renewed for 10 to 15 years. The resolution the specified site. Within the combined license, of issues for a certified design is considered final. the Commission also specifies the inspections, That is, the design cannot be modified unless the tests, and analyses that the licensee shall perform, change is necessary to meet applicable NRC as well as the acceptance criteria that are regulations in effect at the time of the design necessary to provide reasonable assurance that certification, or to ensure adequate protection of the facility has been constructed and will operate the public health and safety. A rulemaking must in conformance with the license. After issuing a be conducted for these changes. An applicant or combined license, the Commission shall ensure licensee may request an exemption to portions of that the licensee performs these required the rule, and may make changes to a facility that inspections, tests, and analyses, and that the do not affect the design certification. acceptance criteria are met. At periodic intervals during construction, the NRC staff publishes An entity intending to construct and operate a notices of the successful completion of the nuclear power plant under Part 52 can inspections, tests, and analyses in the Fedeml incorporate by reference a design certification or Register. In addition, not less than 180 days before
13 1 the date scheduled for initial loading of fuel, the 1995, and the staff is scheduled to issue a final ' NRC publishes a notice of intended operation of rule in summer 1996, the plant. An opportunity for a hearing exists following construction, but petitions for a hearing These rulemakings represent a collaborative effort will only be considered if the petitioner between the Offices of Nuclear Reactor demonstrates that the acceptance criteria have not Regulation (NRR), Nuclear Regulatory Research been met. Before operation of the facility begins, (RES), Nuclear Material Safety and Safeguards the Commission shall find that the acceptance (NMSS), and the Ge ieral Counsel (OGC). To criteria in the combined license are met. further clarify responsibilities between the two technical program offices, NRR and NMSS reached agreement on March 15,1995 to realign certain responsibilities for power reactor decommissioning. In the future, NRR will LICENSE APPLICATIONS, maintain project management responsibility for ISSUANCES, AND Power reactor facilities until NMSS assumes that responsibility when the fuel is permanently DECOMMISSIONING transferred from the spent fuel pool to either an authorized licensee (onsite or offsite) or to the Department of Energy (DOE). During fiscal year 1995 (FY 95), the NRC staff continued revising regulations to clarify their . On January 10,1995, the Citizens Awareness applicability and to change the decommissiomng Network (CAN), an activist group based in Rowe, pohey regardmg permanently shutdown reactors. Massachusetts, petitioned the U.S. Court of On July 20,1995, the Commission issued a Appeals for the First Circuit (Boston) for a review
" Notice of Proposed Rulemakmg on Decom-
, of the NRC decision not to ;; rant a hearing to missiomng of Nuclear Power Plants." The CAN regarding the component removal program proposed rule redefines the decommissioning
, conducted at Yankee Nuclear Power Station. (This process, defines termmology related t
, program was discussed in the 1993 and 1994 decommissiomng, requires beensees to give the arinual reports.) In its decision of July 20,1995, NRC, early notification of planned decom- the Court held that CAN was entitled to a missiomng activities at their facilities, and. hearing, and remanded the case to the explicitly defines the applicability of certam NRC Commission for further action. In the Fedeml requirements to permanently shutdown reactors. Register, on September 6,1995, the Commission The Commission beheves that the proposed rule notified the public of the Court's decision, will enhance efficiency and um,formity m the
, solicited public comment regarding the process of decomnussionmg nuclear power. Commission's legal authority to allow or forbid reactors. In addition, the proposed rule will allow
, , further decommissioning activity at Yankee, and greater pubhc participation m the decommission- stated the Commission's intention to issue a ing process, and will afford both the licensed future Fedeml Register notice that would offer an commumty and the pubhc a better understandm.g
, opportunity for a hearing on the Yankee of the process as the operatmg personnel at a decommissioning plan. On October 12,1995, the 4 nuclear power reactor facility undergo the Commission issued an order forbidding, Yankee l transition from an operatmg orgamzation to a Atomic Electric Company, the licensee for decommissiomng orgamzation. The staff plans to Yankee, from conducting further " major" issue a final rule m, summer 1996.
decommissioning activities at the facility until the hearing is completed. On October 27,1995, the On August 18,1995, the Commission published a Commi .sion provided public notice of the proposed rule that addresses physical protection opportunity for a henring regarding reapproval of requirements for the storage of spent fuel and the Yankee decommissioning plan. high-level radioactive waste in a permanently shutdown reactor, an independent spent fuel In November 1994, Portland General Electric storage installation, a monitored retrievable (PGE), the licensee for the Trojan Nuclear Plant storage installatien, and a geologic repository. The (Oregon), commenced its large component public comment period expired on November 13, removal project (LCRP). The project included the
14 removal and shipment of the Trojan steam Cyclical performance of Comed plants has generators and pressurizer to the U.S. Ecology concerned the Commission and the NRC staff for low-level waste repository at Hanford, some time. The NRC placed Dresden on the Washington. (This program was discussed in the Watch List from June 1987 until December 1988 1994 annual report.) On September 6,1995, in a and again in January 1992. Zion was on the Watch Federal Register notice separate from, but similar List from January 1991 until January 1993. In ! to, the Yankee Nuclear notice previously 1992, the NRC staff found several probable root ' discussed, the Commission announced its causes for the utility's difficulties. The staff ; intention to issue a Federtd Register notice offering discussed these probable causes with the utility's ' an opportunity for a hearing on whether to senior managers. In response, Comed developed , approve the Trojan decommissioning plan. In and began to implement an Integrated l addition, the notice solicited public comment on Management Action Plan to improve l the decommissioning activity at Trojan. Following organizational and management effectiveness, l publication of the Federal Register notice, the business planning and issue management. ! 4 Don't Waste Oregon Council filed lawsuits in the Despite these initiatives, in January and June Oregon State Supreme Court and the U.S. Court 1994, the NRC issued letters to Comed expressing of Appeals for the Ninth Circuit requesting concerns about adverse performance trends at i suspension of the LCRP activities. In response to both the LaSalle and Quad Cities stations. ; the injunctions, the two courts imposed stays that Comed then developed and implemented a series they subsequently lifted after determining that the of more focused and much more effective courts lacked jurisdiction over the matter. initiatives. In 1993, the NRC staff issued its safety evaluation In 1995, the NRC instituted site focus teams to ! and environmental assessment of the proposed closely monitor the performance at all six Comed decommissioning plan for the Rancho Seco facilities. The NRC also conducted periodic and Nuclear Generating Station in California. How- integrated plant performance assessments through ever, NRC approval of the decommissioning plan semiannual plant performance reviews, semi-was delayed because of hearing contentions raised annual senior management meetings, and the by the Environmental and Resources Conser. systematic assessment of licensee performance vation Organization (ECO). During FY 94, (SALP) program. The NRC used these however, the ECO reached a settlement with the assessments to adjust the application of Sacramento Municipal Utility District, the inspection resources. licensee for Rancho Seco, and withdrew from the proceeding on August 1,1994. Following the court Throughout 1995, performance of activities at the decision, the staff reviewed and updated its Byron plant was generally excellent. Similarly, previous safety evaluation and, on March 20,1995, because of positive steps taken by the new issued the order authorizing decommissioning of management teams, LaSalle and Quad Cities were the Rancho Seco facility. removed (in January and June 1995, respectively) from the list of plants with adverse performance trends. Performance at Braidwood and Zion was acceptable, but inconsistent. SPECIAL CASES Dresden also performed adequately, but the pace of improvement continued to be slow, and Commomvculth Edison Company. The Dresden remained on the NRC's Watch List. In Commonwealth Edison Company (Comed) owns 1995, both Dresden units conducted extensive and operates 12 nuclear power plants at each of 6 outages to correct several long-standing material sites in Illinois, including Braidwood, Byron, condition problems. Comed continued to make Dresden, LaSalle, Quad Cities, and Zion. These substantial changes in the station's management plants range in time of operation from 8 years for and organizational structure. The licensee also Braidwood to 25 years for Dresden. Two operating developed an overall improvement plan and reactors are located at each site, giving the utility executed other initiatives to improve performance a total nuclear generating capacity of about 11,500 at the station. In addition, station management megawatts (electric). identified seven focus areas to be improved in 2
l l 15 l l 1995, including (1) work management, (2) material remove the seventh- and eighth stage blades from l condition, (3) outage preparation. (4) training, all three low-pressure (LP) turbines, and to (5) procedural adherence, (6) corrective action replace the blades with pressure plates, even l
- programs, and (7) radiation protection. though this would result in a net 200-230 MWe i derating. As a result, the licensee experienced l Each of these focus areas has been assigned to a numerous power reductions and reactor trips senior plant manager, and specific objectives and during the startup testing program, and did not corresponding actions have been identified, complete the turbine balancing until June 1995.
! assigned, and scheduled for each focus area. The licensee's turbine vibration subsequently ran These efforts have begun to show some positive slightly higher on the highest bearing (no. 8) than results; however, the NRC has determined that the goal of 6 mils (8-9 mils). continued close monitoring is warranted until a period of sustained performance improvement is The licensee also planned to replace all three LP observed. turbine rotors during the next refueling outage, scheduled for March 1996. Because of delays in fabricating and shipping the replacement rotors, as well as a lower-than-anticipated fuel burnup, Fermi the licensee postponed the refueling outage until fall 1996. The Fermi 2 Nuclear Plant is a single-unit, 1139-megawatt (electric) General Electric (GE) boiling-water reactor (BWR) facility, located in . Monroe County, Michigan. The plant is owned Cooper Nuclear Station and operated by the Detroit Edison Company The Cooper Nuclear Station is a single-unit, (the h,censee). 778-megawatt (electrirl GE BWR facili y, t k>cated in Nemaha County, kuraska. The plant is owned On December 23,1993, the Ferm.i 2 plant suffered and operated by the Nebraska Public Power a catastrophic failure of the turbine generator District (the licensee). while the plant was at 93 percent reactor power. The Region III Administrator issued a In May 1994, the Cooper Nuclear Station entered confirmatory action letter (CAL) on December 28, a forced, unplanned outage, which continued until 1993, documenting actions required of the licensee the restart in February 1995. The plant was shut before restart. In addition, with the concurrence down because of deficiencies identified by the of NRR, the Regional Administrator formed a NRC in the surveillance testing of the electrical restart panel, in accordance with NRC Manual distribution system, the control room emergency Chapter (MC) 0350, " Staff Guidelines for Restart filter system, and the primary containment Approval," to evaluate and track the licensee's penetrations. Several confirmatory action letters investigative and recovery actions before restart. (CALs) sent out from May through August of The panel developed a formal restart action plan 1994 required the licensee to address these issues with over 33 action items to be resolved before and to evaluate its operational experience review restart. By letter dated December 14,1994,the and testing programs. licensee notified the NRC of its resolution of the action items. As a result, by letter also dated The licensee's independent diagnostic self-December 14,1994, the region notified the assessment (DSA) report, released in September 1 licensee that the CAL was rescinded, and that the 1994, concluded that corporate and station ; licensee was free to restart the Fermi 2 plant. On management did not foster high standards of December 19,1994, nearly 1 year after the performance, and that management and quality catastrophic turbine failure, the licensee restarted assurance oversight were not effective. In the Fermi 2 plant. addition, the DSA stated that significant weaknesses existed in the licensee's long-range l After restart, the Fermi 2 plant began an planning efforts, and that its testing, configuration l aggressive campaign of startup testing, power control, and corrective a: tion programs were ascension, and turbine balancing. However, deficient. The NRC subsequently conducted a during the outage, the licensee had decided to special evaluation, finding that the DSA was an
16 effective and comprehensive assessment that demonstrated its ability to operate the plant reached substantive conclusions, which were safely, but a number of challenges remain to supported by the NRC's independent assessment. further improve the overall level of performance. In November 1994, because of the nature and extent of the managerial and programmatic weaknesses observed at the Cooper plant, the Palisades Dry Cask Storage , NRC staff established a formal restart panel, to ; review in accordance with NRC Manual In 1993, the NRC amended 10 CFR Part 72 by Chapter 0350, plant readiness for restart and to adding the VSC-24 model to the list of approved coordinate the inspection efforts necessary to spent fuel storage casks. Consumers Power identify any outstanding restart issues. In Company (CPCo) became the first utility to store addressing the identified problems, the licensee spent fuel under the generallicense when it began made extensive management changes and initiated using the VSC-24 cask for storage at its Palisades a three-phased performance improvement plan Nuclear Power Plant in Michigan. During FY 94, (PIP) to define and address actions needed to a number of issues were raised regarding dry-cask prepare for (1) plant restart, (2) the short-term storage at Palisades. In July 1994, while reviewing period following restart, and (3)long-term plant radiographs, a CPCo inspector found two . operation. The restart panel determined that the crack-like indications in the vertical weld of PIP included all significant issues, and that it storage cask 4, which had already been loaded I provided an acceptable process for resolving those with spent fuel. Although the cask was adequate issues. The panel subsequently concluded that the for containing the fuel, CPCo intends to offload licensee had successfully completed the first the fuel from cask 4 after the NRC staff reviews (restart) phase of the PIP by addressing the CAL the unloading procedure submitted by Palisades issues and the fundamental managerial in June 1995. 'Ile offloading of cask 4 has been l weaknesses identified by both the DSA and the delayed until 1996.
~
special evaluation. In reaching its conclusion, the panel reviewed the results of extensive NRC In early 1995, CPCo discovered that the shield lid inspections, including the findings of the January material used in the VSC-24 cask storage system 1995 restart team inspection. In addition, the (the multiassembly sealed baskets (MSBs)) for panel held five public meetings at the site to casks 1 through 4 had not undergone Charpy examine the licensee's progress in implementing V-notch impact tests as required by the safety the PIP. Based on the recommendations of the evaluation report. CPCo submitted its restart panel, and in consultation with the Office interpretation of Section 1.2.13 of Certificate of of the EDO and NRR, the regional administrator Compliance 1007 for the VSC-24 spent fuel granted plant restart approval on February 6, storage cask. Specifically, CPCo's interprptation is 1995. that future movement of MSBs 1 through 4 is permissible, but should be restricted to ambient The licensee began the process of startup and temperatures of at least 10'F to maintain the power ascension on February 9,1995. Throughout specified safety margin to brittle fracture. The this process, the NRC resident inspection staff NRC staff reviewed CPCo's interpretation and was augmented by Region IV and NRR personnel found it consistent with the vendor's safety to provide 24-hour-a-day oversight. The plant analysis report, as well as the NRC's safety reached 100-percent power on February 27,1995, evaluation report on protection against MSB and operated at or near full power until it was brittleness. shut down for the 16th refueling outage on October 13,1995. In early 1995, the U.S. 6th Circuit Court of Appeals upheld the NRC's position on Kelley v. In June 1995, the NRC staff concluded that the Sclin. Filed in May 1993 by the Attorney General licensee's corrective actions had been effective, of the State of Michigan and petitioners against that both hardware and personnel performance the NRC and CPCo, this lawsuit challenged the had improved, and that the downward trend in use of dry fuel storage casks at Palisades. In a performance had been arrested. The SALP report similar ruling in June 1995, the Supreme Court (dated August 2,1995) stated that the licensee had denied to hear a petition for certiomii filed on
17 April 11,1995, by the Attorney General of the zones, each of which will have two independent State of Michigan and petitioners. burners located outside containment. Ductwork and exhaust ventilation will be routed through the equipment hatch and/or the escape hatch. CPCo
, currently plans to use a controlled thermal profile Palisades Reactor Vessel Annealing during heatup and cooldown with a 7-day soak at ppt ximately 850 *E The pressurized thermal shock (PTS) screening criteria provided in 10 CFR 50.61 require that a CPCo predicts that the Palisades reactor vessel licensee submit updated information to the NRC materials will recover 80 percent or more of the whenever there is a significant change in the original material properties. CPCo also estimates projected valu,es used to calculate the reference that only 40-percent recovery is required to reach temperature (i.e., the value compared to the the target license expiration date of 2011(which screening criteria). During fall 1994, CPCo includes a recapture of the construction period).
performed material properties tests and chemistiy analyses of samples of weld material acquired An annealing demonstration project (ADP) using from the shells of Palisades' retired steam the indirect gas heating method is scheduled for generators. These tests and analyses were spring 1996 at Marble Hill, a four-loop important because the newly acquired material Westinghouse plant. This demonstration project is samples had been fabricated using the same independent of the Palisades annealing program, procedures and weld wire heat number as the but is expected to yield information useful to the limiting weld in the reactor pressure vessel (RPV). Palisades project. On the basis of these tests and analyses, CPCo concluded that the degree of embrittlement of the In October 1995, CPCo submitted for staff review Palisades RPV could be higher than previously the first section of the Palisades Thermal calculated. Consequently, with the new data Annealing Report. Additional sections of the included in the evaluation used in PTS screening report are expected during the next few months, and analyses performed in accordance with 10 with the final sections to be submitted following CFR 50.61, the PTS rule indicated that the the Marble Hill ADP. In addition to material Palisades RPV will satisfy the requirements of issues, the NRC staff will review the structural this rule until the end of the plant's 14th refueling integrity of the bioshield during elevated outage, scheduled for late 1999. annealing temperatures, as well as radiological shielding issues during the dry lift of reactor In reviewing the PTS analyses, the staff noted a vessel internals, and fire protection issues large variability in the reported copper and nickel associated with the indirect gas heating chemistry data for the limiting RPV weld. To equipment. assess this concern, the NRC staff employed the Palisades plant-specific chemistry and fluence data to perform RPV failure frequency
, , . Callaway and Grand Gulf'IYansfers calculations similar to those m a Comm.ission Paper, SECY-82-465, " Pressurized Thermal On October 1,1995, the NRC transferred regional Shock" (November 23,1982), which established oversight responsibility for the Grand Gulf the basis for the PTS screening criteria. These Nuclear Station and the Callaway Plant, to the analyses confirmed that the Palisades RPV will Region IV office in Arlington, Texas. Grand Gulf satisfy the safety margins intended by the PTS (located in Clairborne County, Mississippi) had rule through the 14th refueling outage, even with previously been overseen by the Region II office I the variability observed in the Palisades chemistry in Atlanta, Georgia. Callaway (located in data. Callaway County, Missouri) had been overseen by the Region III office in Lisle, Illinois. Grand Gulf Under a contract awarded to Westinghouse, was transferred to place all nuclear plants CPCo currently plans to anneal the Palisades operated by Entergy Operations, Inc. (EOI), in RPV in 1998, using an indirect gas heating Region IV. The Callaway Plant, a standardized system. Inside the reactor vessel, Westinghouw nuclear power plant system (SNUPPS) design will use a compartment 91ized heating can wh tae plant, was transferred to Region IV because the
18 only other SNUPPS plant in operation (Wolf The NRR staff is closely monitoring licensee Creek)is located in Region IV. Placing all of the activities associated with the ISFSIs at these sites, EOI and SNUPPS plants in Region IV enhances in cooperation with staff from the regions and day-to-day oversight activities and makes the from NMSS. In addition, NRR and NMSS have reactor inspection program more efficient. jointly developed a Dry Cask Storage Action Plan to address issues and problems associated with fabricating, installing, and licensing IS FSIs. The NRR is actively resolving some of the technical I Dry Cask Storage of Spent Reactor issues (such as heavy-load crane control and cask Fuel loading and unloading), as well as some of the programmatic issues (such as public In November 1980, the NRC published a final rule responsiveness and inspections of site activities). adding Part 72 to its regulations in Title 10. Part 72 defines the regulatory requirements for licensing and operating independent spent fuel storage installations (ISFSIs). In J uly 1990, the BWR Power Uprates NRC amended 10 CFR Part 72 to simplify the In the 1960s and early 1970s plants were licensing process for storing spent fuelin commonly licensed to operate at a powe rating NRC-approved storage casks at power reactor below the' plant design rating while licensees sites. This amendment was developed in response gained experience with new plant design: . As they to Section 133 of the Nuclear Waste Policy Act of gained this operating experience, many li:ensees 1982. for both boiling-water reactors (BWRs) a nd To date, seven reactor sites have constructed pressurized-water reactors (PWRs) have sought power uprating to make the authorized n:aximum ISFSIs and placed them into operation: power level closer or equal to the plant dasign rating. Thus far, the NRC has issued moi e than e Calvert Cliffs, Calvert County, Maryland 30 such power uprating license amendme lts. e Fort St. Vrain (permanently shut down), Weld In February 1995, the General Electric Company County, Colorado (GE), the vendor for BWRs, submitted tc the NRC a licensing topical report proposing generic e H.B. Robinson, Darling County, South review guidelines for extended power upr iting of Carolina BWRs. This GE report gives generic criteria, methods, assumptions, and scope-of-wori e Oconee, Oconee County, South Carolina estimates required for power uprates to nominally 20 percent over the original licensed thermal e Palisades, Van Buren, Michigan power. Benefiting from the previous power uprate program, GE's proposed extended power uprate e Prairie Island, Goodhue County, Michigan is based on analytical techniques using more realistic assumptions and models (computer e Surry, Surry County, Virginia codes), plant performance feedback, and new fuel designs. These factors have significantly increased
. . the difference between calculated safety analysis Four additiona1 reactor sites plan to place ISFSIs
, , results and licensing limits. GE stated in the mto operation m FY 9& report that this available difference, combined with the as-built equipment, system, and e Arkansas Nuclear One, Pope County, component capability, would allow most BWRs to Arkansas increase their thermal power rating by between 5 and 15 percent without making major hardware e Davis Besse, Ottawa County, Oh. modifications to the nuclear steam supply system.
e Oyster Creek, Ocean County, New Jersey GE plans to submit additional licensing topical l reports containing generic bounding analyses for e Point Beach, Manitowoc County, Wisconsin specific aspects of BWRs. Currently, GE and the
i 19 Northern States Power Company are completing hiarch 1985, TVA volunteered to maintain all extended power uprating studies for hionticello. three BFN units in a cold shutdown condition J The NRC expects to receive a license amendment until corrective actions could be implemented to ; application in 1996 to increase the authorized resolve NRC concerns regarding TVA's ability to ' thermal power of hionticello by about 6.3 percent, safely operate the BFN facility. 'I\vo GE-designed BWRs in Switzerland have Following extensive NRC review and inspection of completed extended power uprate licensing TVA corrective actions, BFN Unit 2 was restarted actions. The Kernkraftwerk hiuehlberg plant on hiay 24,1991, and is currently in its third fuel (BWR-4) started operating at 15 percent above cycle after restart. In a letter dated June 30,1992, original power in 1994. The Kernkraftwerk the NRC notified TVA that Unit 2 had Liebstadt (BWR-6) plant expects to receive demonstrated excellent plant performance, and approval for a 20-percent uprate in early 1996. would therefore be removed from the list of plants The Swiss nuclear regulatory authority and the warranting close NRC monitoring. However, the NRC have been actively involved in a program to NRC informed TVA that Units 1 and 3, would exchange information, including information remain in the close monitoring category and about the extended pmver uprates. would require explicit NRC cuthorization to be operated. The NRC is developing a staff position paper on extended power uprating for BWRs, based in part After restarting Browns Ferry Unit 2, TVA on the NRC review of the GE licensing topical focused attention on Unit 3 restart. In general, report. This staff position paper will provide TVA adopted the approved Unit 2 methods, industiy guidance for developing license criteria, and technical positions for restoring Unit amendment applications for extended power 3 to service, and corrective actions were uprate, as well as NRC staff guidance for completed in 1995. However, TVA revised some reviewing those applications. Programs based primarily on lesson learned from Unit 2. The NRC staff ro,bwed and approved the proposed changes, and TVA completed the corrective actions in 1995. TVA PROJECTS A restart panel, consisting of NRC managers and the Senior Resident Inspector, was established in In September 1985, the NRC star fissued a letter February 1995 to coordinate NRC staff activities, to the Chairman of the Board of Directors of the monitor Browns Ferry activities, and keep the Tennessee Valley Authority (TVA), discussing Regional Administrator informed regarding the significant continuing weaknesses in TVA restart of Unit 3. The NRC staff conducted performance, and stating that management of the numerous inspections of licensee activities, TVA nuclear program was ineffective. including verifying licensee corrective actions identified from the TVA Nuclear Performance Plan, Thil action items, generic letters, bulletins, and operational readiness reviews. TVA Browns Ferry successfully completed the BFN Unit 3 fuel load on October 29,1995; and, on November 19,1995, The Browns Ferry Nuclear (BFN) Plant the NRC authorized TVA to restart the unit. BFN (Alabama) consists of three boiling-water reactor 3 reached criticality and has completed a power units, which are owned and operated by the ascension test program enroute to full power Tennessee Valley Authority (TVA). BFN Unit 2 operation. TVA remains ahead of their schedule was shut down for a planned refueling outage in to return BFN Unit 3 to full power by February September 1984. BFN Units 1 and 3 were 1996. voluntarily shut down in hiarch 1985 because of poor performance, including signi5 cant A decision on whether to pursue restart of enforcement actions, several operational events, Browns Ferry Unit 1 is part of TVA's Integrated equipment failures, and the inability of Resource Plan, which is expected at the end of management to identify and correct problems. In 1995. To restart Unit 1, TVA expects to require a
20 license amendment to " recover" a portion of the opportunity for the NRC staff to observe plant extended shutdown time. operators under simulated operating conditions. On September 1995, representatives of NRR and Region II held a public meeting near the Watts Bar site, in order to allow members of the public Watts Bar to ask questions. The meeting was transcribed, and written answers were provided to those members of the public who asked questions and During FY 95, TVA continued its activities to provided addresses. Also in September, the complete Watts Bar Unit 1, including work on Commission was briefed on the status of Watts corrective action programs (CAPS) and special Bar by both TVA and the NRC staff. The projects (SPs), as well as other construction and following photographs are of Chairman Jackson's modification activities. As systems were tested, visit to Watts Bar Unit 1 before startup. they were turned over to the plant's operating staff. In October 1995, the staff published NUREG-1528, assessing the completion of the construction inspection program at Watts Bar. In support of the Watts Bar licensing process, the Later in October, the staff published Supplement staff prepared a supplement to NUREG-0498, 17 to the Watts Bar Safety Evaluation Report
" Final Environmental Statement Related to the (NUREG-0847). Supplement 17 dealt with the Operation of Watts Bar Nuclear Plant, Units 1 history of Watts Bar, and identified the reasons and 2" (FES), during FY 95. The document was that the NRC could conclude that the plant was prepared to supplement the NRC's 1978 FES in now adequately built and ready to operate.
the interest of furthering the National Environ-merital Policy Act. The supplement evaluated changes ,m the environment, as well as changes in On November 3,1995, NRC inspection confirmed that TVA had successfully implemented all of the the plant design, procedures, and proposed . CAPS and SPs. On that same day, TVA certified methods of operation, smce the staff's previous environmental evaluation in 1978. The staff that Unit 1 was completed, and requested a low power operating license, transmitted the draft supplement for pubhc comment via a Fedeml Register notice and held a public meeting near the site to solicit further The NRC issued the requested license on comments. The staff considered and responded to November 9,1995. This hcense authon, zed TVA to the comments in the final supplement. The staff load fuel and operate Unit 1 up to five percent of concluded that there are no changes in the design, rated power. Fuel loadmg commenced on . operation, population, demographics, land use, November 11,1995, and was completed on water use, regional climatology, meteorology, November 13,1995. Initial criticality is targeted terrestrial environment, aquatic environment, or for January 1996. background radiological characteristics that will result in a significant change in the environmental impact. In July-August 1995, TVA performed a series of PLANT LICENSE RENEWAL integrated tests, called " hot functional tests," at normal operating pressure and temperature. These hot functional tests demonstrated the The U.S. Department of Energy has projected an performance of significant plant safety systems increase in national demand for electricity of and equipment. Moreover, TVA conducted the 100,000 megawatts in the next decade. In light of plant heatup and pressurization as if a reactor the anticipated demand, the electric utility startup was being conducted in accordance with industry has urged the NRC to expedite its technical specifications. This provided a unique rulemaking and development of regulatory
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- plants has long been a top priority for the NRC interaction with the industry. Consequently, the and the nuclear mdustry. Within the next 20 years, NRC published an amendment to the license many commercial nuclear power plants will have renewal rule on May 8,1995. The revised rule
, reached the standard 40-year term of their emphasizes managing the effects of aging (rather i
operating licenses, a figure adopted by Congress than managing the aging mechanism): focuses the l in the Atomic Energy Act of 1954, as amended. review on passive,long-lived structures and j The Act permitted the NRC staff to renew components; and allows greater credit for existing
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j , l lf x . b * ,?; l - j 4 ep# CT' y if , l / aLagggg "%f Jf-l l l 1 l Chairman Jackson talking with TVA officials at the remote shutdown panel at Watts !!ar Unit I before startup. i licensee programs in the license renewal process. effort to openly discuss the commenters' concerns Further, the revised rule tesolves ambiguities and to formulate resolution of these policy issues, , between the rule and the statements of the staff conducted three public workshops in ! consideration, and establishes a more efficient, February 1994. On July 25,1994, the staff stable, and predictable license renewal process. published a supplement to the rule, which contained the staff's proposal to resolve the policy The NRC is also putting forth environmental issues. The staff expects to complete the initiatives to improve the efficiency of license environmental protection rulemaking in early renewal,in the context of National Environmental 1996. , Policy Act (NEPA) requirements. The NRC has l proposed amendments to the " Environmental l Protection Regulations for Domestic Licensing Regulatory Guidance Development and Related Regulatory Functions"(10 CFR Part 51), and a generic environmental impact Since publication of the amended license renewal statement (GEIS), in support of the proposed rule, the staff has been preparing implementation amendment. Public comments on the draft GEIS guidance for the rule, including development of a and proposed rule have raised concerns related to draft regulatory guide. By letter dated August 3, NRC policy for treatment of "need for power" 1995, the Nuclear Energy Institute (NEI) informed and " alternative energy source" issues. In an the NRC of its activities related to developing an
23 1 1 industry guideline for implementing the demo stration to obtain information that should requirements of the amended license renewal rule. assist in the development of other regulatory he NEI proposed that the NRC staff review the implementation guidance, such as the inspection guideline and endorse it in a regulatory guide, program. rather than preparing its own separate regulatory guide. After carefully considering the benefits of The Babcock & Wilcox Owners' Group the industry's proposal and performing a cursory (B&WOG) submitted a topical report on review of the draft industry guideline, the staff managing aging effects for reactor coolant system determined that endorsement of an appropriate piping. The staff reviewed the report and issued a industry guideline would be equivalent to an draft safety evaluation report dated October 18, NRC-generated regulatory guide and would meet 1995. The staff will issue a final safety evaluation the requirements of the license renewal rule. after the open items are resolved. The staff is developing a draft regulatory guide Industry owners' groups are continuing to develop for the format and content of a license renewal topical reports and related documents on i application. The draft regulatory guide proposes managing agmg of plant structures and to endorse an implementation guideline prepared components for renewal. For example, the , by the Nticlear Energy Institute (NEI) as an Westinghouse 0wners' Group submitted a' topical . acceptable method of implementing the license report on the ag,mg of reactor coolant system i renewal rule. A notice of availability and request supports, the B&WOG submitted a topical report for public comments is scheduled to be published n the pressurizer, and Baltimore Gas and in the Fedeml Register in August 1996 ior the draft Electric Company (BG&E) submitted an , regulatory guide and NEI guideline. In addition, integrated plant assessment methodology it plans to use to meet the h, cense renev al rule. The staff the staff is also participating in an NEI-sponsored demonstration program that is assessing the s currently reviewing all of these reports. . cffectiveness of guidance contained in the NEl guideline. A workshop is planned for October i 1996, and the final regulatory guide and NEI ; guideline incorporating lessons learned are IMPROVING THFs expected to be issued in final form in August l 1997. LICENSING PROCESS The staff also expects to publish a draft standard review plan (SRP) for license renewal. However, the staff will not publish the SRP untilit gains expenence with implementmg the final rule ONGOING REGULATORY amendment, based on the review of a few license IMPROVEMENT INITIATIVES renewal applications. On September 30,1993, President Clinton issued Executive Order D66," Regulatory Planning and Industry Activities Review," requiring all Federal Government agencies to perform a periodic review of their Several industry efforts are currently underway to existing regulations, and te eliminate unnecessary implement the license renewal process and and unproductive requirements. At that time, the conduct initial reviews for preparing applications. NRC already had several initiatives under way to One such activity is a pilot demonstration identify and eliminate requirements that were program to implement portions of the industry considered to provide only marginal safety guideline. His demonstration will involve a mix of benefits. These initiatives have since been 3 volunteer plants that have participated in consolidated within the " Continuing Program for developing the industry guidelines, as well as Regulatory Improvement," which is based on the others that have not. The pilot demonstration will fundamental principle that all regulatory burdens be conducted between March and August 1996. must be justified, and that the NRC's regulatory he NRC staffis considering onsite audits of the process must be efficient.
24 l The Commission's Continuing Program for requirements that are most cost-effective. To Regulatory Improvement incorporates three NRC expedite processing of petitions that include a initiatives: comprehensive regulatory analysis of the basis for the petitioned rulemaking, the NRC revised
- 1. the " Marginal to Safety" Program 10 CFR 2.802, " Petition for Rulemaking," and published the revision for public comment on
- 2. the Regulatory Review Group (RRG) March 28,1995. Public comments generally Implementation Plan supported the concept behind the proposed revision, but indicated that rulemaking was not
- 3. the Cost Beneficial Licensing Action (CBLA) the most appropriate regulatory vehicle for Program expediting the NRC's handling of petitions for i rulemaking. Consequently, the rtaff reevaluated l In 1994, NRR created the RRG/CBLA Program its approach and determined that alternative Group to oversee and facilitate the implementa- regulatory vehicles could be used to provide tion of these initiatives. Since its creation, the guidance on the scope and level of detail of RRG/CBLA Program Group has served as a focal information that should be submitted with point for the NRC staff, industry, and public on petitions for rulemaking so that they can receive issues and initiatives associated with CBLAs. The expeditious processing.
RRG/CBLA group has not replaced the normal process for reviewing and approving licensee . I requests. Nonetheless, the RRG/CBLA group has Regulatory Review Group tracked and trended CBLA submittals and Implementation Plan approvals, as well as NRC responsiveness related to CBLA activities. The group has also provided The NRC's Regulatory Review Group (RRG) general CBLA poh,ey guidance to hcensee staffs, Implementation Plan, issued in early 1994, and worked with the staff and industry to identify resulted from a review by senior-level staff in the CBLAs with generic implications. In addition, the RRG of selected power reactor regulations and RRG/CBLA group has focu. sed management related processes, programs, and practices. The attention on implementing the CBLA process RRG recommended specialized areas within within the staff. As a result, processing bcense which the NRC's regulations might be changed, in i amendment requests as CBLAs has become a order to reduce the regulatory burden with little I part of the NRC's normal work planmng process. or no adverse safety impact. The implementation I Based on successful implementation or closure of plan included 71 recommendations covering a i many of the actions under these imtiatives during wide spectrum of issues and topics related to 1994 and 1995, the functions of this group will be power reactor licensing activities. In its December folded back into the NRR organization by the end 1995 report to the Commission, the staff of 1995. However, the NRR staff will contmue t identified 42 recommendations that have been ensure resolution of remaining RRG implemented or closed. Work on the 29 remaining recommendations has progressed to a point where Implementation Plan and Margmal to Safety Program actions, which will be carried out as part they can be resolved under other ongoing of ongomg agency programs. programs and no longer require special attention by the CBLA group.
" Marginal to Safety" Program Cost Beneficial Licensing Actions Through the " Marginal to Safety" Program, the The Cost Beneficial Licensing Action (CBLA)
NRC focuses on petitions for rulemaking and program was created to increase the staff's regulatory guidance identified by industry that receptiveness to licensee requests that would might be costly to implement and only marginally reduce or eliminate license requirements that have l effective in enhancing safety. The staff recognizes an incrementally small effect on safety, but carry that the industry is in the best position to identify a heavy economic burden. This new receptiveness which regulations impose a heavy economic differs from the past when the NRC staff gave the burden with little commensurate safety benefit, lowest priority to requests for approval of license and the methods used to meet existing amendments that might have marginal safety
25 sigtificance, but might result in large cost savings. NEXT-GENERATION REACTOR After a successful pilot program in mid-1993, the
, DESIGNS program was made available to all licwnsees in 1994.
The staff is currently reviewing five applications , for design certification under Subpart B of 10 CFR Part 52. Two of these applications are for On February 23,1995, the staff issued Administrative Letter 95-02, " Cost Beneficial the evolutionary LWR designs known as the dvanced boilmg water reactor (ABWR) and Licensing Actions," to all licensees to proside System 80+, two are for passive LWR designs additional information on the CBLA program, known as the simplified boih,ng water reactor including questions and answers based on past (SBWR) and AP600, and one is for a heavy-water meetings between licensees and the staff. The re ctor design known as CANDU 3. The status of CBLA group conducted a public workshop on , these reviews, is as follows. April 13,1995, and has also participated in a , number of industry forums to further com-municate the advantages of the program. Through ABWR December 5,1995, the staff received 271 CBLA submittals, and approved 166 submittals, resulting The staff issued its final safety evaluation report in an estimated lifetime savings (based on (NUREG-1503)in July 1994, followed by the final industry estimates) of approximately $588 million. design approval on July 13,1994. The Commission then issued a notice of proposed rulemaking for . certification of the ABWR design on April 7, 1995. The staff will address public comments, and plans to issue a final rulemaking by late 1996. System 80+ STANDARDIZATION OF REACTOR The staff issued the final safety evaluation report RESIGN (NUREG-1462) and final design approval in July 1994. The Commission then issued a notice of proposed rulemaking for certification of the Combustion Engineering (CE) System 80+ standard plant design on April 7,1995. The , staff The Commission strongly endorses regulatory ' policies that, encourage the industry to pursue a na ru ma b a e 19 ki. standardization of next-generation reactor designs. Standard designs are expected to benefit public health and safety by (1) concentrating SBWR industry resources on common approaches to solving design problems that have wide On August 27,1992, GE Nuclear Energy application, (2) stimulating adoption of sound submitted an application for final approval and construction practices and quality assurance, certification of its SBWR design. GE (3) fostering constantly improving maintenance subsequently furnished supplements to its and operating procedures, and (4) permitting a application on February 25, February 28, and more effective licensing and inspection process. May 7,1993. The SBWR is a 600-megawatt The NRC plans to achieve these benefits with the (electric) advanced reactor design that employs i design certification process. Together, design passive features (such as gravity flow and natural I certification, early site permits, and combined convection) to perform essential safety functions. licenses constitute the major provisions of the new The staff docketed GE's application for design licensing process in 10 CFR Part 52. The NRC is certification in May 1993. Howeve:, problems in currently preparing proposed standard design resolving staff concerns led GE to reassess its certification rules for two light-water reactor SBWR testing and analysis program, and to (LWR) designs. request a realignment of the SBWR design
26 certification. In response, the staff suspended all Expeditious completion of the review is consistent review activities not related either to testing and with the Commission's " Statement of Policy for analysis, or to the TRACG thermal-hydraulic the Regulation of Advanced Nuclear Power I code. In November 1994, the NRC issued a DSER Plants," which called for early Commission review on the GE's SBWR Test and Analysis Program and interaction with potential applicants for the Description (TAPD). GE-sponsored testing is licensing of advanced designs. expected to continue into early 1996. Following GE's announcement to redirect the focus of its SBWR programs from plants of the 670 MWe size CANDU 3 to plants of 1,000 MWe or larger, the staff's The CANDU 3 is a 450-megawatt (electric), ! efforts have been directed to orderly closure of natural uranium-fueled, heavy-water-moderated ; the SBWR review. These activities should ' ' and -cooled, pressure tube reactor developed by completed toward the latter portion of 19! Atomic Energy of Canada, Ltd. (AECL). In its letter of September 30,1994, AECL Technologies AP600 (AECLT) applied for design certification under 10 CFR Part 52, and submitted the safety analysis In June 1992, Westinghouse Electric Corporation report for the CANDU 3 design. The staff submitted an application for final approval and completed the certification acceptance review for certification of its AP600 design. The AP600 is a the CANDU 3 design, and notified AECLT of the ! 600-megawatt (electric) pressurized-water reactor review findings on December 15,1994. By letter incorporating passive safety systems and features. dated March 9,1995, AECL requested that the On November 30,1994, the staff issued a draft NRC discontmue all work on CANDU 3 because safety evaluation report (DSER) identifying 1145 of the anticipated high cost of NRC's review and open items,63 confirmatory items, and 165 the lack of any near-term market in the United combined operating license action items. To date, States. the staff has also issued approximately 2800 i requests for additional information (RAls), as MHTGR well as follow-on questions in support of its evaluation of the application. Westinghouse has DOE submitted the MHTGR design to the NRC responded to most of the questions raised by the in 1986. The design is a helium-cooled, graphite-staff. In support of the passive design, Westing. moderated thermal reactor with multicoated fuel house established an AP600 test program that particles, which uses fuel and core similar to those includes separate-effects (SE) experiments on the used in Fort St. Vrain. The NRC issued a draft passive approach, as well as two integral systems PSER for the MHTGR (NUREG-1338)in March test (IST) programs. See " Testing for Passive 1989. Since then, the NRC conducted meetings Designs," later in this chapter. At the request of with DOE, and issued RAls on the design. DOE Westinghouse, the staff reprioritized portions of responded to the RAIs, and submitted three the AP600 review. As a result, Westinghouse and amendments to the preliminary safety information the staff are in the process of reevaluating the document for the MHTGR. The staff is scheduled review schedule for the AP600; however, the staff to complete the final PSER in 1996. expects to issue a DSER supplement in 1996 to report the results ofits review of the Westinghouse passive design testing program. TESTING FOR PASSIVE DESIGNS The requirements for certification of advanced PRE-APPLICATION REVIEW OF reactor designs, under 10 CFR Part 52.47(b)(2), include dem nstration that the reliability of each THE MHTGR DESIGN design safety feature has been confirmed through analysis, testing, experience, or a combination During FY 95, the staff continued its thereof, and that sufficient data exist to confirm pre-application review of the modular high- the accuracy of the analytical tools used in safety temperature gas-cooled reactor (MHTGR) design. analyses. Both the AP600 and the SBWR designs
i 27 rely on passive systems for reactor safety. Institute (PSI) in Wuerentingen, Switzerland. The Accordingly, the vendors for both designs have staff has also identified several other tests that developed testing programs to provide data to must be included in the GE test program, and satisfy the requirements of 10 CFR testing activities are scheduled to be completed by Part 52.47(b)(2). The NRC is monitoring the early 1996. The staff is actively evaluating the GE vendors' test programs using the procedure test data. described in SECY-91-273, and is reviewing these . test programs to determine whether they will yield The NRC is conductmg confirmatory research for the necessary data. The staff is also examining the both the AP600 and SBWR designs. The research experimental data, as it becomes available, to Will Provide valuable data to aid in validating the ensure that the codes are adequate. NRC's analytical codes used to audit the vendors' calculations, and will provide experimental knowledge to improve the staff's understanding of Westinghouse's AP600 test Program includes the umque behavior of the safety systems separate-effects (SE) experiments on several of th designed for the passive ALWR. (The need and key systems and components myolved in the planning for confirmatory research are discussed passive safety approach. These tests examine the
, in SECY-92-037 and SECY-92-219 for the performance of the passive residual heat removal AP600, and in SECY-92-211 for the SBWR.)
(PRIIR) system, the core makeup tanks (CMTs), AP600-related testing began in early 1994 in the the automatic depressurization system (ADS), and modified ROSA-V/LSFT facility in Japan, and is the passive containment cooling system (PCCS). providing insights into passive system behavior. In add,i tion, Westinghouse has conducted tw The NRC will perform SBWR confirmatory mtegral systems test (IST) programs. For the first testing at PUMA, a reduced-height, low-pressure program, a low-pressure IST facility was integral systems SBWR loop, located at Purdue constructed at Oregon State Umversity to study University. the behavior and interactions of the safety systems and important nonsafety systems at low pressures corresponding to the later stages of several accident sequences. For the second EARLY SITE PERMITS program, a high-pressure, full-height IST facility was built at the Societas' Informazione Esperienze On April 18,1989, the Commission issued, in Termoidrauliche (SIET) laboratories in Piacenza, 10 CFR Part 52, the regulatory framework for Italy, to examine the behavior of the passive safety obtaining early resolution of site-related issues. In systems during the high-pressure phase of 1995, he NRC continued upgrading its capabili-accidents. Testing in both integral facilities was ties for managing and conducting environmental completed in 1994. The staff is evaluating the data and site-licensing reviews, developing regulatory from all of Westinghouse's design certification test guidance, and accessing and analyzing requisite programs. geographical and land use information. GE Nuclear Energy developed a broad testing program to support SBWR design certification. IMPROVED STANDARD GE has completed much of the planned testing, TFCIINICAL SPECIFICATIONS including SE experiments on the unique squib-type, explosive-actuated depressurization The NRC continues to place the highest priority valves used in the SBWR ADS, and SE heat on license amendment applications related to full transfer tests related to the operation of the conversion to the improved Standard Technical SBWR PCCS. Tests related to operation of the Specifications (STS). During 1995, the NRC gravity-dnven coohng system have been run m the issued license amendments implementing the GIST facility at GE's San Jose site, and an IST improved STS for an additional six units at four program has been carried out at Toshiba's plant sites. GIRAFFE facility in Japan to study the behavior of the PCCS. Further SE tests are in progress in The NRC is presently reviewing license l ! the new PANTHERS facility at SIET, and the new amendment applications to implement the PANDA integral test facility at the Paul Scherrer improved STS for another five units.
28 l As of November 1995, about 70 percent of all amendment practices. In April 1995, as a result of commercial nuclear units have converted, are NRC and industry efforts, revisions to the converting, or plan to convert to the improved improved STS for each reactor design were STS. An additional 10 percent of the units are issued. These revisions incorporate the numerous undecided about converting to the improved STS, generic improvements made in various and about 20 percent of the units are not specifications since the original improved STS presently planning to convert. Compared to those were issued in September 1992. Future revisions i of a year ago, these estimates represent a to the improved STS will be issued as additional i substantial shift toward the adoption of the enhancements evolve and performance-based improved STS in the commercial nuclear power regulatory reforms are instituted. industry. As the process required to complete a conversion to the improved STS continues to :' become more efficient, the NRC anticipates that additional licensees will decide to convert to the improved STS. INSPECTION PROGRAMS 1 In August 1995, an amendment to the regulations A basic element in the NRC reactor regulation I (in 10 CFR 60.36) pertaining to the content of the program is the inspection of licensed reactor I technical specifications became final. Specifically, facilities to ensure reactor safety by confirming ' the amendment codifies the criteria for that the operations comply with the Regulations, I determining the content of technical specifications provisions of the license, and to look for other that were first published in the July 1993 final conditions that have safety implications serious policy statement on technical specifications. These enough to warrant corrective action. criteria were developed in recognition of the need to concentrate the technical specifications on NRR is responsible for developing, maintaining , those requirements of immediate importance to and assessing the effectiveness of the reactor l public health and safety. Under the rule change, inspection program, which applies to all applicant licensees may voluntarily propose to relocate and licensee activity carried out in connection existing technical specification requirements from with the construction and operation of nuclear the facility license to the appropriate facilities. Most of the inspection effort is licensee-controlled program or document, when dedicated to operations at the 109 plants where the requirements do not meet the criteria for operating licenses are in effect (as of inclusion in the technical specifications. September 30,1995), with added coverage of the five facilities with construction permits. The NRC places a high priority on improvi,ng the existmg techmcal specifications, usmg the process The NRR inspection program has the following codified by the change to 10 CFR Part 50.36 and four objectives:(1) to provide one of several bases the process of adoptmg im, e item, generic STS for conclusions on both individual licensee and improvements. In the latter process, licensees may industry-wide performance for allocating NRC voluntarily request h,eense amendments to resources, (2) to ensure that the licensee's systems selectively adopt improvements to the S'IS as and techniques for conducting internal "hne item, changes to their existing heenses. inspections and maintaining control result in safe Ilowever, the impact of future resource reductions operations, (3) to find and resolve plant-specific may eventually limit the NRC,s ability to focus on safety concerns that have generic significance, and "h,ne item, amendments, which are less efficient (4) to identify declining trends in licensee than full conversion as a way to improve techmcal performance and perform inspections to verify specifications. that the licensee has resolved the issue before performance declines below an acceptable level. The NRC continues to work with the Nuclear The inspection staff seeks through direct Energy Institute standing task force established to obseivation and verification of licensee activities coordinate industry initiatives for improvements determines whether the facility is being operated to technical specifications and related license safely, whether the licensee's program is effective,
29 and whether regulatory requirements are being systems important to safe operation; and frequent satisfied, plant tours to assess radiation control, physical security, equipment condition, and housekeeping. The NRC conducts a program of routine inspec- The resident inspectors are the primary onsite tions at each reactor licensee. This includes a evaluators with respect to licensee event reports,
" minimum" program conducted at every site events and incidents, and other general ,
(core), plus initiative inspections based on inspections of licensee activities. licensee performance, and reactive inspections as required. Reactive inspections are performed to The inspection program allows headquarters and determine the root cause of safety-related events regional inspections to focus on those plant or conditions; evaluate the licensee management's 'Perations hat contribute most to ensuring response to it, including action to prevent reactor safety, as well as on the identification of recurrence; and decide whether a similar problem existing or potential safety problems. The NRC could occur at other facilities. The NRC, through continued to revise the program during FY 95, this inspection program, is committed to dealing based on knowledge gained from experience with aggressively with unsafe or potentially unsafe the current program. conditions occurring at individual plant sites. The m.spection program comprises the following The four NRC Regional Offices conduct most of three elements: the NRC inspection programs, while the NRC (1) Core Inspections. As " regular" inspections Headquarters directly conducts only a lirnited conducted at every plant, core inspections number. NRR is responsible for developmg provide a minimum examination of licensee inspection poh,cies and procedures and for activities in order to confirm the adequacy of momtormg and assessmg the effectiveness and licensee performance and identify potential umformity of the programs carried out by the problems in the early stages. Core inspections NRC Headquarters and Regional Offices. are performed by resident and region-based inspectors. (2) Plant-SpecVic RegionalInitiative Inspections. REACTOR INSPECTION PROGRAM This program element consists of three parts: j 1
. (a) RegionalInitiative Inspections address The operatm.g reactor mspection program is specific areas decided by several factors, implemented by mspectors located in NRC
, particularly the results of other Headquarters and Regional Offices, as well as at inspections, licensee performance, and the heensees, sites. Headquarters inspectors are
, , the results of interactions with the
- pamanly m, yolved with conductmg team licensee' inspections. The Regional Offices conduct most of the required inspections, utilizing both (b) Reactive Inspections are generally
, region-based and resident inspectors, as conducted in response to events or appropriate. Region-based inspectors perform issues, but may also be conducted to technically detailed inspections in such areas as follow up on findings from other engineering, system modifications, inservice inspections that require immediate inspection, fire protection, physics testing, attention. radiation protection, physical security and safeguards, maintenance, and licensee (c) Team Inspections provide an management systems. The resident inspectors independent, indepth, and balanced provide the major onsite NRC presence for direct assessment of one or more aspects of observation and verification of licensee activities. licensee performance. They are often This involvement includes indepth inspections of multidisciplined in both the scope of the control room operations; maintenance and inspection and the composition of the surveillance testing carried out by the licensee; team. Team members include NRR periodic " walk-down" inspections to verify the personnel, resident and region-based correctness of system lineups for those nuclear inspectors, and contractors.
30 1 (3) Generic Safety Issue Inspections. This and the maintenance and engineering inspection program element consists of two parts: at Watts Bar. Headquarters also led two operational readiness assessment team (ORAT) (a) Generic Area Team Inspections address inspections at Watts Bar and one at Millstone. An one or more generic areas selected for ORAT is an independent review of licensee specific team inspection emphasis. The readiness to begin initial plant operation or to
- selection is based on the identification of resume plant operation after an extended outage.
, an emergmg safety concern, or an area requiring increased emphasis because of Some types of team inspections are performed "as recurring problems. needed" at particular plants, while others are designated " area-of-emphasis" inspections and (b) Safety Issues Inspections address specific are performed at a designated population of safety issue concerns. If a concern is of plants. Established types of special team appropriate safety significance, it may be inspections cover emergency operations, 3 necessary to initiate a one-time maintenance, ability of systems to perform safety i inspection effort under the safety issues functions as designed, motor-operated valves, 4 program element. modification of safety systems during reactor ; outages, operational safety, operational readiness, and plant designs. SPECIAL TEAM INSPECTIONS Ongoing Initiatives During FY 95, NRC headquarters and regional In 1991, the staff developed a team inspection, staffs continued to perform special team known as the Semce Water System Operational inspections. Such inspections usually involve a Performance Inspection (SWSOPI), which team of 4 to 10 individuals, with several ddressed a new area of concern to the NRC. The engineering disciplines represented, and require 1 staff conducted pilot SWSOPIs m each region to to 2 weeks of onsite inspection. The team test the methodology and scope of each. In examines in detail various aspects of selected accordance with TI 2515/118, Revision 1, the NRC systems and components that are critical to safe pr cg,eded with the SWSOPI, as a "genene safety shutdown of a plant or that are required to ssue mspection, at sites beensed before 1979 and maintain the plant in a safe condition after at other sites having service water system shutdown. The team may inspect design, pr blems, or more general maintenance, installation, testing, maintenance, and operation engmeering, or techrucal support problems. As a of the selected systems. The overall objective of result of a SWSOPI performance effectiveness such inspections is to determine whether, when review m 1995, the staff ehmmated the beens, mg called on to do so in an emergency, plant systems date criterion for selectmg plants for SWSOPIs. and personnel will perform their safety functions In the future, all plants will be selected based on as set forth in the safety analysis report. senice water or more general problems. The staff issued a Commission Paper (SECY-95-(M1, dated Headquarters staff members develop the method February 17,1995) and TI 2515/118, Revision 2, to for each new type of team inspection, test the effect these changes. At the end of FY 95, the method during a limited number of pilot NRC had completed 37 SWSOPIs, meluding the inspections, and incorporates the developed Pilot m, spections. The NRC mamtains an inspection methodology into the NRC Inspection electronic database of SWSOPI findings. In addition, IN 94-03 discusses deficiencies and Manual. Responsibility for most of the special team inspections is assigned to the Regional weaknesses identified during the mitial seven Offices. Headquarters may also lead a team SWSOPIs. inspection in some circumstances. Examples of headquarters-led special team inspections during New Initiatives 1995 were the engineering inspection at South Texas, the configuration management inspection In 1994 and 1995, the NRC developed a new at Washington Nuclear Plant Unit 2 (WNP-2), process to improve the periodic, long-term
31 integration of objective information (e.g., well as allegations from members of the public inspection reports, licensee self-assessments, concerning potentially defective and sometimes SALPs, etc.) to arrive at conclusions regarding misrepresented parts, components, and materials. licensee performance and provide site-specific The program determines and prioritizes actions to recommendations for future inspections. This identify and resolve issues according to their process, known as the Integrated Performance safety significance and generic applicability. Assessment Process (IPAP), supplements existing processes that provide ongoing integration, and it provides direct feedback on the effectiveness of Inspections during FY 95 addressed public the inspection program and its implementation. allegations and reports from industrial After piloting the IPAP at five plants, the staff organizations. According to the provisions of 10 CFR Part 21, licensees and vendors are held a public meeting on the process, obtained Commission approval to implement the process, required to report the NRC problems and defects issued the final inspection procedure (IP 93808), in safety-related equipment, materials, and and began planning IPAPs to be conducted at 16 services. In FY 95, the vendor inspection staff had plants during FY 96. the responsibility for screening, tracking, and ensuring the closecut of approximately 80 Inspection Procedure 40501, " Licensee Self- notifications required in 10 CFR Part 21. The Assessments Related t'o Team Inspections," allows staff determined the validity, extent, and safety reduced NRC inspections at facilities that significance of each reported and alleged demonstrate good performance over time. Under deficiency, and determined the need for this pilot effort, the NRC would evaluate a inspection. Further, as appropriate, the staff licensee's self-assessmem effort as an alternative ensured that licensees were apprised of potential to a full-scope NRC " area-of-emphasis" problems so that they could take appropriate inspection. The NRC would sample areas covered action to prevent the use of defective components by a licensee's self-assessment, as well as in nuclear plant safety systems. The NRC vendor significant areas not covered. The goals of this inspection staff also frequently corresponded with approach are to more effectively apportion NRC vendors and licensees, both orally and in writing, inspection resources, and to reduce the impact of to explain the NRC's position on specific NRC inspection activities on licensee operations interpretations and applications of 10 CFR (e.g., licensees are required to respond to a Part 21 and other Federal regulations. smaller NRC team). At the end of FY 95, licensees had either completed or initiated 27 SWSOPI self-assessments, and the staff had In FY 95, the NRC vendor inspection staff conducted 34 vendor mspections,4 inspections of completed and overviewed most self-assessments. licensecs, and 3 information gathering trips to NRC experience has shown that reduced-scope vendors. Of the inspections,13 m, yolved SWSOPIs use about 25 percent of the direct , allegations. The vendor mspections covered those inspection resources of a full-scope SWSOFI. who provide commercial grade dedication or Based on the staff's positive impressions of licensee self-assessments through the end of FY equipment qualification services, as well as those who manufacture or supply instrumentation and 95, the NRC has expanded IP 40501 to cover all control systems and components, switchgear and team inspections. distribution equipment, transmitters, switches, fasteners, pumps, valves, digital systems, fire barrier material and testing, rupture discs, or snubbers. Two major inspection activities were VENDOR INSPECTION PROGRAM undertaken durmg the year. The first involved three large team inspections of fuel i The Vendor Inspection Program centered in NRC manufacturers, including sub-tier material ! Headquarters is principally a reactive program suppliers. The second was the continuing i I structured to respond to vendor and licensee involvement of the inspection staff in the review reports of deviations and defects in and inspection of the GE and Westinghouse vendor-supplied parts, components, materials, advanced water reactor quality assurance and services provided to nuclear power plants, as program.
32 As a result of inspection findings and other overlay these processes and give agency senior information in the vendor program area, the NRC managers an opportunity to review observations issued 13 information notices informing the and findings and plan a coordinated course of nuclear industry of problems. These information action for those plants where past performance notices dealt with concerns involving circuit gives the NRC the greatest concern. These various breakers, including contaminated lubricants, processes rely on the results of NRC inspections problems with contact blocks, and material and other objective information collected on plant lodged in the trip mechanism: Thermal lag fire performance. barriers, including test results and legal actions; fasteners; pressure transmitters; problems with relay latching mechanisms; failure of pump shafts; air regulator problems with pilot-operated relief valves (PORVs); inadequate heat treatment of SYSTEMATIC ASSESSMENT OF i material; and degradation of scram solenoid pilot LICENSEE PERFORMANCE valve pressure and exhaust diaphragms. The vendor inspection staff continued to supply The SALP program is a principal and regular information to other government agencies through method for assessing licensee safety performance. participation in the Government-Industry Data Under the SALP program, the performance of Exchange Program (GIDEP). All NRC each licensee with a nuclear power facility in information notices and bulletins are published in operation or under construction in the United the GIDEP Failure Experience Database. In States is evaluated through the periodic, addition, the vendor inspection staff provided comprehensive examination of available technical support to assist the NRC Office of data-including inspection findings, event review Investigations and various U.S. Attorneys in results, and similar licensing and inspection-criminal cases, related information. The SALP program is designed to arrive at an overall assessment of how well licensee management at a given plant is directing and guiding operations for the requisite assurance of PERFORMANCE plant safety. The purpose of the SALP review is to EVALUATION focus both NRC and licensee attention on, and to direct NRC resources to, those areas that could most likely affect nuclear safety and that need The NRC evaluates the performance of nuclear improvement. power plant licensees through various coordinated processes. Performance evaluation involves The SALP includes a review of reported events, integrating information from various sources and inspection findings, enforcement history, and NRC activities such as conducting inspections, licensing issues for the previous 1 to 2 years. Also imposing enforcement actions, tracking per. important are evaluations by resident and region-formance indicators, analyzing trends, evaluating based inspectors, licensing project managers, and events, and examining licensed operators. senior managers-all of whom are familiar with Ongoing evaluations of licensee performance are the facility's performance. New data are not made by NRC inspectors during each plant necessarily generated in conducting a SALP inspection and documented in the associated assessment, which consists of performance inspection reports. Short-term assessments of evaluations in specific functional areas. performance are made at least twice each year through the plant performance review process. In 1995, the Commission solicited feedback from Senior NRC regional managers assess licensees' licensees and the public on the effectiveness of long term performance through the systematic changes made to the program in 1993. The NRC assessment of licensee performance (SALP) is currently reviewing the responses, and the process. Senior management meetings (SMMs) results of the feedback will be issued in FY 96.
33 INSPECTING THE NUCLEAR POWER PLANT ne primary safety consideration in the operation of any nuclear have been met and to confirm the consistency of tests that are reactor is the control and containment of radioactive material, planned and conducted. Inspectors also review the qualifications of under both normal and accident conditions. Numerous controls operating personnel and verify that operating procedures and QA and barriers are installed in reactor plants to protect workers and plans are properly developed and implemented. the pubhe from the effects of radiation. About 6 months before the operating license is issued, the licensee j lloth the industry and the NRC have roles in providing these begins a startup phase to prepare for fuel k>ading and "ptmer l projections and in ensuring that they are maintained. The NRC ascension." Af ter issuance of the operating license, fuel is loaded l establishes regulations and guides for the construction and into the reactor, and the startup test program begins. As in operation of nuclear reactors. Organizations licensed by the NRC pre-operational testing, NRC inspections emphasize test procedures must abide by these regulations and are directly responsible for and results. Inspectors appraise the licensee's management system designing, comtructing, testing, and operating their facilities in a for startup testmg, analyze test procedures, witness tests, and safe manner, review licensee evaluations of test results. Dereafter, the NRC continues its inspection program for the remainder of the operating nrough selective examinations, the NRC inspection program life of the plant. ensures that licensees meet their responsibilities. The NRC l inspection program is audit-oriented to verify, through scrutiny of ne staff is developing a new construction inspection program for l carefully selected samples, that relevant activitics are properly reactors to be built under combined construction and operating I conducted and equipment properly maintained to ensure safe licenses issued under 10 CFR Part 52. He new inspection program operations. He staff determines which items to sample, as well as wdl continue to verify the safety aspects of a plant's construction ; the sample sizes and inspection frequencies, based on the and testing, as previously described for the current program and ' i importance of the activity or system to overall safety and on will allow for more systematic inspection planning and , available resources. De mspection process monitors the licensee's documentation of mspection results. The new construction activities and gives feedback to the licensee's management for inspection program will be structured to verify a licensee's appropriate corrective action. Ilowever, the NRC inspection satisfactory completion of the inspections, tests, analyses, and program does not supplant the licensce's programs or attenuate its acceptance criteria (ITAAC) as specified in the combined license responsibilities. Drough the inspection program, the NRC seeks to and required by 10 CFR Part 52. independently verify the effectiveness of the licensee's implementation of its programs, to ensure that operations are being De NRC verifies that the licensee is operating safely through carried out safely and m accordance with applicable NRC selective inspections. An onsite resident inspector provides a requirements. Inspections are performed on power reactors under continual inspection and regulatory presence, as well as a direct construction, in test conditions, and in operation. He inspections contact between NRC management and the licensee.De activity are conducted primarily by region-based and resident inspectors. of the resident inspector is supplemented by the work of engineers Resident inspectors are stationed at each reactor under and specialists from the Regional Office who perform inspections construction and in operation. Region-based inspectors operate out in a wide variety of engineering and scientific disciplines, ranging of the four Regional Offices located in or near Philadelphia, from civil and structural engineering to health physics and reactor Atlanta, Chicago, and Dallas. Dese programs are supplemented by core physics. personnel from NRC lleadquarters. The NRC Inspection Manual defines the frequency, scope, and Inspections are a vital part of the NRC's review of applications for depth of the inspection program for operating reactors, and licenses, as well as the process leading to issuance of construction detailed inspection procedures provide instructit and guidance permits and operating licenses. Inspections continue throughout for NRC inspectors. %c program consists of thi a major elements: the operating life of a nuclear facility. e core inspections-the minimum required at all plants Before construction, the inspection program concentrates on the . Pg applicant's establishment and implementation of a quahty
, PCg S'g g;g ;, peg assurance (QA) program. Inspections cover OA activities related to P'ff [*2"C' design, procurement, and planning for fabrication and construction . Seneric safety issnes inspections-focus on a safety significant of the facility, problem of a generic nature ne program is structured to ensure that the resources available for During, construction, samples taken across the spectrum of licensee activities are examined to confirm that the licensee is following the mspection are used efficiently and effectively, with particular requirements of the construction permit issued by the NRC, and attention accorded to,those plants where past performance indicates the need to improve the levels of protection and that the plant is being built according to the approved design and safety-consciousness.
applicable codca and standards. Cons!ruction mspectors look for qualified personnel, quality material, conformance to approved design, and a well-formulated and well-implemented quality The inspection program is designed to ensure that nuclear power assurance program. As construction nears completion, plants are constructed and operated safely and in compliance with l regulatory requirements. The NRC considers the results of the pre-operational testing begins in order to demonstrate the I operational readiness of the plant and its staft Inspections during inspection program when making its overall evaluation of licensee this phase seek to determine whether the licensee has developed performance for the SALP program. When a safety problem or adequate test plans-both to verify that tests are consistent with failure to comply with requirements is discovered, the NRC NRC requirements, and to ascertain whether the plant and its staff requires prompt corrective action by the licensee, confirmed, if are thoroup,hly prepared for safe operation. Inspections during the necessary, by appropriate enforcement action. pre operational phase involve reviewing overall test procedures, exammmg selected test procedures for technical adequacy, and he NRC periodically assesses the inspection program to evaluate witnessing and assessing selected tests to verify that test objectives its effectiveness in achieving its regulatory objectives.
34 During FY 95, the NRC issued 44 SALP reports. performance. Specifically, the modules include the Among the 44 reports,7 plant sites (with a total Detailed Control Room Design Review (DCRDR) of 11 reactors) received SALP Category 1 ratings, and Safety Parameter Display System (SPDS), indicating superior safety performance in all four Licensee Event Reports (LERs), Emergency functional areas. Because of their superior level of Operating Procedures (EOPs), training, inspection performance, the SALP evaluation frequency for reports, and HPIP. During FY 95, the staff these plants was extended to 24 months. In continued to use HFIS information to determine addition, they will receive an appropriate the need for, and focus of, plant-specific and reduction in NRC inspections. Another 6 plant generic inspections and other reviews, such as sites (with 10 reactors) received at least one SALP event investigations, relating to human Category 3 rating, indicating acceptable safety performance. In addition, HFIS information is performance, but still of concern to the NRC. The used to monitor plant-specific and national trends ; NRC will focus an appropriate level of increased of issues related to human performance. LER ! inspection at these plant sites and on the plant information in HFIS is used to develop insights functional areas that were rated SALP Category 3. on the contribution of human performance to operational events. Inspection report information from HFIS is also used to gain insights into human performance that is not necessarily related HUMAN FACTORS to significant operational events. During FY 95, several improvements were made to HFIS, and Human performance is a crucial element of the HFIS database was made available agency-wide in November 1995. nuclear power plant safety. More than half of the incidents reported by commercial nuclear power One of the most important ways the staff plant licensees have human performance as a root evaluates the effectiveness of licensee training cause. Humans perform multiple functions, and efforts is by monitoring the Institute of Nuclear while accomplishing these functions, they can Power Operations (INPO) training program cause, prevent, mitigate, recover from, or be accreditation process. During FY 95, NRC affected by events. During FY 95, the Human personnel observed National Nuclear Accrediting Factors Assessment Branch (HFAB) staff Board meetings, during which utility training participated in 1 augmented inspection team programs are evaluated for initial accreditation or (AIT),3 operational readiness assessment team accreditation renewal. NRC staff members also (ORAT) inspections,2 restart assessment team observed two INPO accreditation team site visits. inspections (RATIs), and 14 special inspections at The staff concluded that the industry continues to operating plants. The objectives in each of these conduct effective training in accordance with 20 inspections were to help determine the root NRC requirements. The Commission continues to causes and contributing factors of events involvin8 endorse the INPO accreditation program as an human performance, and to identify and analyze effective means of ensuring proper nuclear plant those conditions that contribute to human errors. personnel training. The human performance investigation process (HPIP)is often used in such inspections. The When a significant training program weakness is NRC developed HPIP specifically to consider identified at a specific plant through, for example, . issues related to human performance-the design an event investigation or operator requalification of human-systems interfaces, plant procedures, inspection, the staff may conduct a training training, and communications, as well as the inspection. During FY 95, the staff conducted effects of supervision, management, and inspections of accredited training programs at two organization. sites. On June 13,1995, the staff updated Inspection Procedure 41500, " Training and The HFAB staff developed the Human Factors Qualification Effectiveness," to include training Information System (HFIS) to evaluate, track, inspection selection criteria. trend, and manage various types of information on human performance at nuclear power plants. During FY 95, the staff continued to perform HFIS comprises a database of six modules for follow-up inspections of emergency operating storing and analyzing data on human procedures (EOPs). The objective of the
35 i region-led EOP inspe.Jons was to follow up on activities; research programs and integration of I items previously ider tified by event investigations findings; operational performance reviews and ! or previous EOP inspections. During FY 95, the followup activities; and the collection, evaluation, staff supported all four regions by providing compilation, and dissemination of human onsite human factors specialists and systems performance information. experts for 10 EOP inspections. During FY 95, the staff revised Inspection Procedure 42700, As required by its charter, the committee began
" Plant Procedures," to focus the inspection effort by developing a Human Performance Program on areas where procedure problems have been Plan that reflects the goals, objectives, and identified. In particular, the inspection procedure activities associated with the agency's human was revised to provide additional guidance on factors programs. The committee issued this inspecting the usability of the procedures by program plan in August 1995.
assesung the degree to which accepted human factors principles have been incorporated. Also in accordance with its charter, and to enhance communication and coordination among On October 10,1995, the staff issued Information the offices, the committee will meet approximately Notice (IN) 95-48, "Results of Shift Staffing every 6 months in order to monitor agency human Study," to inform licensees of the results of the Performance activities and update the program NRC study that addressed the adequacy of Pl an. The committee will also review new minimum shift staffing levels at nuclear power developments in the area of human factors, both j plants. The IN gave licensees several insights into within the nuclear arena and in other related : problems that could result from inadequate fields. In addition, the committee will review controls to ensure that shift staffing is sufficient trends of human performance data identified in to accomplish all functions required by n event. various information systems, and will communicate related initiatives and activities to l In July 1994, the staff published the " Human each of the involved offices. ' Factors Engineering Program Review Model," NUREG-0711, which describes review criteria for the human factors engineering program elements necessary to develop an acceptable advanced INSTRUMENTATION AND control room design specification and an CONTROL SYSTEM UPGRADES acceptable implemented design. During FY 95, the staff completed two supplements t Through the years, the industry became aware NUREG-0711, supporting the program review that some earlier analog electronic modelin the areas of human factors engmeermg instrumentation and control (I&C) systems are msights based upon operating experience and
, subject to age-related degradation, and it has review criteria for group-view displays. become increasingly difficult to obtain qualified replacement components for those systems.
Licensees have also come to desire enhanced Human Factors Coord. mat. ion features such as automatic self-test and Committee diagnostics, greater flexibility, and increased data availability. Together, these factors have prompted A task force established by the Deputy Executive some operating reactor licensees to replace Director for Nuclear Reactor Regulation, Regional existing analog systems with digital systems. Operations and Research, recommended the formation of an interoffice committee to The Nuclear Management and Resources Council coordinate the agency's human factors programs. (NUMARC) and the Electric Power Research As a result, the lluman Factors Coordination Institute (EPRI) took the initiative to develop Committee, was established with representatives guidance for implementing digital system from NRR, AEOD, RES, NMSS, and the regions. modifications. 'Ibgether, NUMARC and EPRI wrote a topical report to address the issue of The overall responsibilities of this committee are evaluating such upgrades in accordance with the to coordinate human factors program review requirements of 10 CFR Part 50.59. The staff
36 commented on this report while it was in draft provide a consistent process that will assist form, and the resulting final report, licensees in reaching a proper conclusion NUM ARC /EPRI 'Iopical Report TR-102348, regarding the existence of an unreviewed safety
" Guideline on Licensing Digital Upgrades," dated question when undertaking a digital system December 1993, reflects a coordinated effort replacement. The introduction to TR-102348 between industry and the staff. states that the guidance is supplemental to and consistem with that provided in NSAC-125, The staff reviewed the final report and " Guidelines for 10 CFR 50.59 Safety Evaluations."
determined that, with certain clarifications, it can GL 95-02 reminded licensees that NSAC-125 has be used as guidance by licensees for both properly not been endorsed by the staff; therefore, any use designing analog-to-digital replacements and of those guidelines is advisory only, and nothing making proper unreviewed safety question in NSAC-125 should be construed as a substitute determinations under 10 CFR Part 50.59. The for the requirements of 10 CFR Part 50.59. The staff issued the related draft generic letter for actual determination of whether or not an public comment in the Fedeml Register on unreviewed safety question exists must be made in October 18,1994. After reviewing the public accordance with 10 CFR Part 50.59. The generic comments, the staff issued NRC Generic Letter letter also cautioned licensees that if while making (GL) 95-02, "Use of NUMARC/EPRI Report the 10 CFR Part 50.59 unreviewed safety question TR-102348,' Guideline on Licensing Digital determination there is uncertainty about whether Upgrades,' In Determining the Acceptability of the probability or consequences of an accident Performing Analog-to-Digital Replacements under may increase, or whether the possibility of a 10 CFR 50.59," on April 26,1995, endorsing different type of accident or malfunction may be report TR-102348 with clarifications. created, the uncertainty should lead the licensee to conclude that the probability or consequences Specifically, the staff included in GL 95-02 two may increase or a new type of malfunction may be clarifications to TR-102348. The first concerns the created, and therefore, an unreviewed safety system level to be used when licensees make the question is involved. 10 CFR Part 50.59 unreviewed safety question determination, since 10 CFR Part 50.59 does not The staff is confident that issuance of GL 95-02 use this term. The staff stated that the system created a consistent regulatory basis upon which level to be considered in this regard should be the licensees may proceed to implement digital I&C digital system being installed. The staff believed system upgrades. The staff will continue to that this clarification was necessary because the inspect digital modifications, including the EPRI report used the term " system" both to refer accompanying 10 CFR Part 50.59 evaluations. to the digital system being installed, and to the Lessons learned from the staff inspections and larger trip or fluid system of which the digital from implementing the guidelines in TR-102348 system is a part. This led to the possibility that will assist in maintaining a consistent approach to the unreviewed safety question evaluation would digital I&C system modifications in accordance focus on the entire fluid system, rather than the with 10 CFR 50.59. system being changed. The second clarification concerned the use of engineering judgment when making a 10 CFR Part 50.59 unreviewed safety question evaluation. Since this judgment is not MAINTENANCE readily quantifiable, such j,udgment may be difficult to duplicate and understand at a later time. Therefore, the staff stated that the basis for On July 10,1991, the Commission published in the engineering judgment and the logic used in the Fedeml Register (56 FR 31306) a new the determination should be documented to the maintenance rule 10 CFR Part 50.65, extent practicable. " Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." This The intent of the report and the staff was not to rule takes effect on July 10,1996, and will require predispose the outcome of the 10 CFR Part 50.59 commercial nuclear power plant licensees to process for determining whether an unreviewed monitor the effectiveness of maintenance activities safety question exists. Rather, the intent was to for safety-significant plant equipment in order to
37 minimize the likelihood of failure and of events The operator licensing process at power reactors caused by the lack of effective maintenance. includes a generic fundamentals examination (GFE), which covers the theoretical knowledge During the period from September 1994 to March required to operate a nuclear power plant, and a 1995, the NRC staff performed a series of nine site-specific examination, which consists of a pilot site visits to ensure the adequacy of a draft written examination and an operating test that version of inspection procedure (IP) 62706, which includes a plant walk-through and a dynamic 4 will be used to verify implementation of the rule. performance demonstration on a simulation These pilot visits were performed at sites that facility. License applicants must pass the GFE volunteered to have the staff review their before they can take the site-specific examination. maintenance rule implementation before the effective date of the rule. The results of these site The operator licensing examinations at nonpower visits were documented in NUREG-1526, reactors are similar to those at power reactors,
" Lessons Learned from Early Implementation of with two major exceptions. Specifically, the the Maintenance Rule at Nine Nuclear Power theoretical knowledge is included on the Plants." On June 27,1995, the staff held a public site-specific written examination, and the dynamic workshop in St. Louis, Missouri, to review the performance demonstration is conducted on the lessons learned from the pilot site visits. On actual reactor instead of a simulation facility.
July 17,1995, the staff issued a Commission Paper, SECY-95-179, to give the Commission a During FY 95, the NRC administered status report on the recent and planned approximately 500 site-specific initial licensing maintenance rule activities. On August 31,1995, examinations to RO and SRO applicants at power the staff issued the final version of IP 62706, and nonpower reactor facilities. In addition, the which incorporated appropriate comments and NRC administered approximately 325 GFEs to suggestions received from the pubhc and industry prospective license applicants at power reactor representatives. facilities. Beginning on July 10,1996, the staff will perform During FY 95, the NRC also evaluated the baseline inspections of each h,eensee,s
, licensed operator requalification programs at implementatam of the mamtenance rule.These
, , approximately 60 power reactor facilities to verify inspections will be conducted by resident and capacity of the programs to ensure the continued region-based mspectors, and will be completed
, competence of their individual licensed operators.
within two years, To ensure umform All of the programs were evaluated using the implementation, NRR maintenance section staff process described in Inspection Procedure (IP) will participate in these inspections, and will
, 71001, " Licensed Operator Requalification provide traimng to the resident and region-based Program Evaluation." The FRC uses this IP to mspectors. This trammg wdl be completed before periodically evaluate each licensed operator the rule takes effect on July 10,1996. requalification program at each power reactor facility. The NRC also conducts requalification examinations, as needed, when the staff loses c nnden e in a f cycensee's awhy to OPERATOR IICENSING conduct its own exammations, or beh, eves that the inspection process will not provide the needed The NRC is continuing to administer initial insight. The staff did not conduct any examinations to applicants for reactor operator requalification examinations during FY 95.
(RO) and senior reactor operator (SRO) licenses at power and nonpower reactor facilities. The On August 14,1991, the NRC amended 10 CFR responsibility for administering the examinations Part 55 to make the licensee's fitness-for-duty at power reactors rests with the four NRC requirements a condition of each operator's Regional Offices, while the NRC Headquarters is license. Through September 1995, the NRC responsible for managing the program and received 41 reports of licensed individuals administering the examinations at nonpower exceeding their facility licensee's cutoff levels for reactors. drugs or alcohol. One additional operator at a
j 38 i non-power facility voluntarily sought treatment for and grade the operating tests, and they will alcohol abuse. review the written examinations after they are graded by the facility licensee. In addition, The NRC is continuing to monitor the the NRC will continue to issue or deny performance of the utilities' certified and operator licenses based upon the approved simulation facilities to ensure that they qualifications and competence of the license remain acceptable for conducting operating tests applicants. in accordance with 10 CFR Part 55. In observing the conduct of NRC licensing examinations and Before formally implementing the revised requalification inspections, and in evahiating process in the next revision of NUREG-1021, licensees' quadrennial simulator performance test NRR will evaluate the results of the pilot reports through September 1995, the staff did not examinations, refine the examination identify any deficiencies that would result in procedures, solicit public comments, and invalid operating tests. obtain Commission approval. In continuing to improve the operator licensing (2) The NRC issued Revision 1 of the program during FY 95, the NRC staff " Knowledge and Abilities Catalog for l implemented or is considering a number of Nuclear Power Plant Operators" for both l initiatives that will enhance the initial licensing pressurized water reactors and boiling water i and requalification examination processes: reactors (NUREG-1122 and NUREG-1123), which were originally published in 1985 and (1) The NRC is considering a change that will 1986, respectively. The revised catalogs give beensees the option to prepare draft incorporate evolutionary changes in licensed written examinations and operating tests for operators' tasks and the operator licensing review and administration by the NRC. This program. pioposed change is consistent with Administration initiatives and the NRC's (3) In an effort to conserve resources, the NRC ongoing efforts to streamline the functions of the Federal Government, and to changed the frequency of the requalification program inspections (IP 71001) from once per accommodate anticipated resource SALP cycle to once every 24 months (i.e., the reductions including the elimination of
, maximum requalification cycle permitted by contractor support in the operator licensing 10 CFR Part 55). This change is not expected area.
to have a significant effect on the staff's ability to oversee the facility licensees' From October 1995 through March 1996, the - requalification programs. staff will conduct a voluntary pilot program to evaluate the effectiveness of the proposed examination process: 21 facility licensees are expected to participate. These 2 licensees will prepare the pilot examinations in accordance PLANT PERFORMANCE REVIEWS with the existing procedures in NUREG-1021. " Operator Licensing The Plant Performance Review (PPR)is a Examiner Standards," with supplemental semiannual process conducted by the regional instructions provided by NRR. The NRC will offices to provide a short-term evaluation of remain actively engaged in the examination objective information and insights to arrive at a process to ensure that acceptable levels of current summary of overall plant performance. effectiveness, objectivity, and independence The PPRs are used to adjust a region's plant are maintained. NRC examiners will review inspection plan (increasing or decreasing the the proposed examinations in detail to verify number and scope of inspections), and to that they conform with the applicable distribute inspection resources among the plants guidelines, and they will ensure that changes over the upcoming 6 months. The PPRs also are made (as necessary) to bring the provide a primary source of input to the senior examinations into conformance. NRC management meeting (SMM) process, described examiners will also continue to administer below.
39 The SMM is conducted under the direction of the ; For each power reactor licensee within the ' region's responsibility, regional staff and Executive Director for Operations (EDO), with managers integrate and assess objective each regional administrator leading the senior information in the areas of plant operations, managers in discussing the plants in the maintenance, engineering, and plant support. This respective region. During these discussions, the information includes insights regarding the managers determine which plants, if any, to place licensee's ability to identify, resolve, and prevent in one of the three problem plant categories: issues that degrade the quality of plant safety. Following each PPR, the staff issues to the e category 1, plants removed from the problem heensee a revised master mspection plan, plant list reflecting any observed trends or changes in licensee performance. Inspections are then conducted in accordance with the plan, unless
- category 2, plants that are authorized to reactive events cause the staff to redirect Operate, but will be closely monitored by the
, resources. NRC e category 3, shutdown plants that require NRC authorization to start up, and that will be closely monitored by the NRC SENIOR MANAGEMENT MEETINGS In addition to the three problem plant categories, senior managers identify plants that are exhibiting adverse performance trends that could cause the NRC to place the plants on the problem plant list The SMM process is a semiannual review and in the future. Strong evidence exists that most l integration of the agency's observations and licensees take robust actions to remediate poor findings regarding nuclear reactors, which culminates in a meeting of senior NRC managers Performance if they believe their plants are close during which operating nuclear power plant safety to being placed on the problem plant list. performance is reviewed. This SMM process gives senior agency managers an opportunity to review The senior managers also review the performance . of plants that have received SALP Category 1 l the staff's observations and findings on operating nuclear reactors, and to plan a coordinated course ratings in all four functional areas since the last of action for plants at which performance is of SMM. This review enables the senior managers to I significant concern to the NRC. Since the first identify those plants at which sustained superior SMM v:as held in 1986, the scope of the meetings performance warrants formal recognition by the has been expanded to include major fuel facilities EDO. and materials licensees, nuclear power plants that have demonstrated superior performance, and As a result of SMM discussions, the EDO issues plants at which performance is dechmng. letters to the licensees of the plants placed on the problem plant list, plants exhibiting adverse Performance trends (known as trending letters), Preparations for the SMM occur over several 4 months leading up to the meeting. During this and s,uperior performers.The results of the SMM are discussed with the Comm,ission at a pubh,c time, NRC regional and headquarters staff meeting twice cach year. integrate licensing, inspection, and operating experience to evaluate the safety performance of operating facilities. They also determine whether During the two SMMs that were held in 1995, five the licensees are finding and effectively correcting plants remained on the problem plant list, two problems, or if they are experiencing adverse were removed from the list, and three were issued performance trends. The review emphasizes the trending letters. No new plants were placed on the effectiveness of lic:nsee self-assessment and problem plant list. In addition, eight plants at five corrective actions. Plants that are of greatest sites were recognized by the EDO for superior concern are slated for discussion at the SMM. performance.
40 l EMERGENCY imp lementation of the guidance in NUhfARC/NESP-007, "hiethodology for PREPAREDNESS Development of Emergency Action Levels." As a result of this effort, the staff issued 12 safety evaluation reports. Durm.g FY 95, the emergency preparedness (EP) staff focused its attention on three major areas, In response to a staff requirements memorandum, including onsite EP inspections, EP licensing the staff worked closely with the Office of Nuclear activities, and coordination with the Federal Regulatory Research (RES) to develop j Emergency hianagement Agency (FEh!A). Onsite recommendations to simplify EP requirements for EP inspections continued to be a major activity in reactor designs with greater safety margins. This the regions. The regional staff observed and process includes conducting a study to reevaluate evaluated full and partial participation exercises the existing technical bases for EP using the at more than 32 nuclear ~ power plant sites around following input: the country, and performed routine EP inspections at more than 36 sites. In support of e insights from a plant-specific severe accident the inspection effect, the staff prepared technical risk study conducted by the staff (published guidance in the form of three emergency preparedness positions (EPPOS), which were as NUREG-1150) issued and placed in the NRC's public document e revised severe accident source term I room. Subjects covered in the EPPOS included information (published as NUREG-1465) timely classification of emergency conditions, i on-shift dose assessment capability, and e available plant design and probabilistic risk additional guidance for emergency action level assessment information for passive and scheme modifications. Additionally, in response evolutionary reactor designs to lessons learned from the effect of Hurricane Andrew on the 'Ibrkey Point (Florida) nuclear During FY 95, the staff also supported several l power plant in 1993, the staff prepared a rulemaking activities related to emergency temporary inspection (TI) to evaluate licensees' planning. These included climinating the annual offsite communication systems. "off-year" exercise, and establishing regulations for independent spent fuel storage installations. hiajor EP licensing activities in FY 95 included the following: The staff also participated in two working groups involved in developing EP-related industrial o completing the final steps in issuing a standards for nuclear power plants. One new low-power operating license for Watts Bar standard, ANSUANS-3.8.7, " Criteria for (Tennessee) Planning Development, Conduct, and Evaluation of Drills and Exercises for Emergency o preparing a Commission Paper on the use of Preparedness," was issued for comment in 1995. the corporate emergency operations facility The other standard, ANSUANS-3.8.9, " Criteria (EOF) as an interim EOF for Commonwealth for Radiologica! Emergency Response Plans and Edison nuclear facilities Implementing Procedures for Permanently Defueled Commercial Nuclear Power Plants,"is o relocating the backup EOF for the Wolf currently under development. Creek Generating Station (Kansas) The staff continued to work closely with FEhfA to o continuing the review and assessment of address issues related to offsite emergency licensee-submitted changes to emergency preparedness (at and around nuclear power plants plans and implementing procedures for in the United States). For this cooperative activity, nuclear power plants, as well as research and the NRC has statutory responsibility for the test reactors radiological health and safety of the public, while FEhiA has been designated as the lead Federal The staff reviewed 18 proposed emergency agency for offsite planning and response. As such, classification schemes representing industry FEhfA assesses the adequacy of State and local
41 emergency preparedness, and provides its findings and determinations to the NRC for use m, SAFETY REVIEWS licensing decisions. The NRC and FEh1A staffs worked closely together in FY 95 to develop and l assess emergency planning for the Watts Bar plant in Tennessee. In that process, FEhfA reviewed the PROBABILISTIC RISK offsite plans, assessed the adequacy of the alert ASSESSMENT POLICY STATEMENT and notification system in the emergency planning AND IMPLEMENTATION PLAN zone, and observed the full participation exercises preceding the licensing of the facility.
. In August 1994, the staff fonvarded to the Commission the proposed Probabilistic Risk Assessment (PRA) Policy Statement, which was The NRC and FEh!A staffs also coordinated closely in monitoring the potential impact on subsequently published in the Fedeml Register on December 8,1994, m order to solicit pubhc emergency planning of hurricanes that threatened c mment. After addressmg the pubh,c comments, nuclear power plants on the Atlantic and Gulf coasts during the rather active 1995 hurricane the Commission published the Final PRA Pohey Statement in the Fedeml Register on August 16, season. In particular, Hurricane Opal impeded evacuation routes and damaged the alert and 1995. According to that pohey of PRA technology should be m, ereased statement, m all the notification system in the Farley (Alabama) emergency planning zone. In that instance, FEMA regulatory matters to the extent supported by state-of-the-art PRA methods and data, and m, a was able to determine that despite communication difficulties, emergency preparedness remained manner that complements the NRC's adequate as a result of the efforts of State of determmistic approach and supports the NRC's Alabama and local emergency response officials traditional defense-m, -depth philosophy. In with the support of the licens'ee. NRC and FEhiA addition, the final pohey stated that PRA should staffs are currently reviewing the lessons learned be used to reduce unnecessary conservatism from the 1995 hurricane season, with the objective associated with current regulatory requirements, of improving coordination procedures between the and that PRA evaluations m support of regulatory two agencies.
decisions should be as realistic as practicable. In late 1995, the staff fonvarded the Commission Paper entitled " Framework for Applying In addition, the NRC and FEhfA staffs Probabilistic Risk Analysis in Reactor coordinated closely on the following EP-related Regulation," which described a process to ensure program matters during FY 95: c nsistent and appropriate application of PRA msights m regulatory decisions. In order to manage the expanded use of PRA o imtiation of efforts to improve the agencies,
, methods and techniques in a manner consistent responsiveness to pubh,c inquiries concernmg with the Commission's policy statement, the NRC offsite EP issues staff developed a PRA Implementation Plan, which was submitted to the Commission in August 1994. On December 2,1994, the staff c reexamination of the guidance for conducting conducted a workshop to inform the public of and evaluating emergency preparedness NRC activities related to the implementation plan, exercises and to receive public comments. In hfarch 1995, the staff briefed the Commission on the status of the activities described in the PRA e development of a standardized exercise Implementation Plan. The NRC staff then report format performed a preliminary review, and provided comments to the industry on the EPRI "Probabilistic Safety Assessment (PSA) o consolidation of program policies and Applications Guide," the draft NEI " Guideline guidance in a planning manual for Risk-Based Inservice Testing (IST)," and the
42 mumium 1 draft American Society of Mechanical Engiacers material surveillance program for the RPV (ASME) " Risk-Based IST Gudeline." materials that are subject to neutron irradiation. In addition,10 CFR Part 50.61 sets limits on the i Also in 1995, NRC. NEl. and industry reference temperature for pressurized thermal l representatives initiated a number of pilot shock, RTm, which is related to an increase in ' programs to test several PRA applications. The brittle-to-ductile transition temperature. l purpose of these pilots was to develop, test, and validate risk-informed rnethodologies for specific j On the basis of the currently docketed , regulatory applications, and to finalize the information, the staff has concluded that Beaver i guideline documents. The Commission has Valley Unit 1 (Pennsylvania) and Palisades assigned a high priority to these pilot (Michigan) are the only two plants likely to exceed applications. Several PRA pilot applications the pressurized thermal shock (PTS) screening started in 1995 included graded quality assurance, limits before their current operating licenses risk-informed inservice testing, risk-informed expire, unless mitigative actions are taken. As a inservice inspection, and risk-informed technical result of information recently obtained by testing specification improvements. The staff expects to material from Palisades' retired steam generatois, continue interaction with industry representatives it was determined that the Palisades RPV will and licensees, with the objective of completing all exceed the PTS screening criteria in late 1999, , pilot programs during the next 2 years. before the end of its operating license in 2007. I Similarly, Beaver Valley Unit 1 is projected to ! The staff is currently completing the individual exceed the PTS screening limits in 2012, before plant examination (IPE) review, and is continuing the end of its operating license in 2016. the individual plant examination external events (IPEEE) review. The staff also initiated a The NRC expects that additional information and program to summarize insights gained from the analyses and licensee programs to reduce neutron l IPE reviews. This effort is expected to continue flux will result in changes to the currently l during 1996. In addition, PRA Training Focus predicted RTm and USE values. The NRC staff l Group was formed to review current PRA training will continue to assess new information as it for NRC staff, and to provide recommendations becomes available, and plans to provide periodic to senior NRC managers regarding a PRA updates of the NUREG report on the basis of this training program for NRC technical managers information. This effort will be facilitated through and staff members. As a result, several existing the use of a computerized reactor vesselintegrity PRA courses were improved a.M new ones were database (RVID) developed by the NRC. This added in 1995. database includes summary tables containing necessary input for evaluating RPV structural integrity in accordance with the requirements of 10 CFR Part 50, Appendix G, and 10 CFR REACTOR VESSEL MATERIALS Part 50.61. The RVID was made available for public access in early 1995, and will be updated periodically on the basis of NRC assessments of Reactor pressure vessel (RPV) integrity is new information from the industry and licensees. essential to ensuring reactor safety. During operation, a reactor vessel is subject to neutron In order to continue operation of the Palisades irradiation and, as a result, the fracture resistance RPV beyond 1999, the licensee is evaluating of its materials is reduced. The decrease in annealing the reactor vessel during its refueling fracture resistance is measured by an increase in outage in 1998. Annealing is a thermal treatment the brittle-to-ductile transition temperature and a to mitigate the effects of neutron irradiation by reduction in the Charpy upper-shelf energy increasing the fracture resistance of the RPV (USE). materials. To demonstrate the feasibility of annealing, the licensee will rely on the results of in 10 CFR Part 50.60(a), the NRC requires that the Marble Hill Demonstration Anneal, which is licensees for all light-water nuclear power plants scheduled for 1996. In preparation, the staff began meet fracture toughness requirements and have a processing an annealing rule and regulatory guide,
43 which are expected to be published in December determinations for advanced light-water reactors l 1995. (ALWRs). These determinations enabled the staff i to understand the behavior of operating reactor steam generator internal deflections during main steam line break accidents. Specifically, the staff IIIGH-PERFORMANCE was able to analyze test data from ALWR COMPUTING IN NRR experimental facilities, to calculate soil-structure mteractions under a turbm, e buildmg caused by earthquakes, and to calculate heat losses and In FY 95, NRR's high-performance computing gains through electrical insulation during a fire. capability continued to grow providing NRR The staff also used the available communications technical staff with improved analytical capability to exchange electronic mail with code capabilities and advanced electronic users and developers at the Nationallaboratories communications. NRR staff members use and at regulatory organizations in foreign high-performance UNIX workstations to perform countries. In addition, the staff transferred large analyses involving complex calculations: amounts of data from experimental test facilities o the thermal-hydraulic performance of reactor coolant systems and reactor containment With the establishment of this internal analytical systems during normal operation, transients, capability, the staff significantly enhanced its and accidents ability to judge the quality of technical work performed by licensees and agency contractors, o reactor core and fission ptod.ict behavior Immediate access to analytical tools has also during severe accidents brought a more timely response to incidents and l events, as well as reduced dependence on I o structural and mechanical analyses of reactor contractors. The visualization tools that are now structures and components during normal being built into the analytical tools improve operations, accidents, and seismic events analytical quality, as well as access to the l l analytical results by non-experts. As the agency l c radiat,on i shieldm, g moves toward increased use of PRA-based regulation, this improved analytical capability will l o electrical network stability form a strong foundation for risk-informed
" "E' To perform these calculations, the staff uses computer programs (codes) that have been developed internally (such as RELAP5, TRAC, MELCOR, CONTAIN, SCALE and CAERES), PERFORMANCE OF i as well as commercially available programs (such as ALGOR and ANSYS). At one time, these MOTOR-OPERATED VAINES codes ran on large supercomputers, but now they run on powerful UNIX workstations that are the On June 28,1989, the NRC staff issued Generic i
size of a normal personal computer. The 25 Letter (GL) 89-10 " Safety-Related
! workstations distributed within 7 different Motor-Operated Valve Testing and Surveillance,"
branches in 4 divisions of NRR are tied together as a result of problems with the performance of in a network that allows each user to share motor-operated valves (MOVs)in nuclear power networked resources for the analysis of plants. In GL 89-10, the staff requested that engineering problems. In addition, the licensees ensure the capability of MOVs in high-performance computer network is also safety-related systems by reviewing MOV connected to the agency's office automation designbases, verifying MOV switch settings network, so that engineers with less-frequent initially and periodically, and testing MOVs under needs for analyses can use them. design basis conditions where practicable. GL 89-10 also requested that licensees improve In FY 95, the staff used this capability to support evaluations of MOV failures, necessary corrective probabilistic risk assessment (PRA) success path actions, and trends regarding MOV problems. In l l l
44 addition the staff requested that licensees programs. The staff also provides information to complete the GL 89-10 program within licensees on MOV issues through NRC-sponsored , approximately 3 refueling outages or 5 years from public meetings, participation in industry l 4 the issuance of the generic letter. Since 1989, the meetings, and issuance of NRC information , staff issued Supplements 1 through 6 to GL 89-10 notices. to provide additional information and clarify l GL 89-10 recommendations. The industry has issued several event reports l describing opera: . nal failures of safety-related ) On July 26,1995, the staff issued for public gate valves as a result of pressure locking or l comment a proposal for Supplement 7 to thermal binding of the valve disks. Such pressure l GL 89-10, which would climinate the locking or thermal binding can be caused by valve recommendation that licensees of pressurized- design characteristics (wedge and valve body water reactor nuclear plants address the configuration, flexibility, and material thermal inadvertent mispositioning of MOVs as part of coefficients) when the valve is subjected to their GL 89-10 programs. (This is similar to specific pressures and temperatures during Supplement 4 to GL 89-10, issued in 1992, which various modes of plant operation. Operating applied to boiling-water reactor licensees.) The experience indicates that these situations are not staff plans to issue Supplement 7 to GL 89-10 in always considered as part of the design basis for a rly 1996. valves in many plants. Despite industry awareness I of the problem, pressure locking and thermal Many nuclear power plant licensees have notified binding events continue to occur, the staff of the completion of their programs to verify the design-basis capability of safety-related On August 17,1995, the NRC issued Generic MOVs as requested in GL 89-10, and the staff Letter (GL) 95-07, " Pressure Locking and has completed its review for about 25 percent of Thermal Binding of Safety-Related the licensees. Mo',t licensees will have completed Power-Operated Gate Valves."In that letter, the MOV design-basis capability verification under staff requested chat licensees take the necessary GL 89-10 by the end of 1995. actions to ensure that safety-related, power-operated gate valves susceptible to The staff is preparing a proposed generic letter to pressure locking or thermal binding are capable address the need for periodic verification of the of performing their safety functions within the design-basis capability of safety-related MOVs. current licensing bases of the facilities. The staff The staff is also working with the American also requested that licensees perform a screening Society of Mechanical Engineers (ASME) to evaluation, within 90 days from the issuance of revise ASME code requirements by including the generic letter (to ensure that no immediate long-term provisions for monitoring and safety concerns exist), and complete the GL 95-07 maintaining the capability of MOVs to perform program within 180 days from the issuance of the their design-basis safety functions. In addition, generic letter. However, GL 95-07 states that the staffis completing a safety evaluation of the schedules for corrective action (if corrective MOV Performance Prediction Program developed actions are needed) may be based on risk by the Electric Power Research Institute (EPRI) significance, including consideration of common to predict thrust and torque requirements to cause failure of multiple valves. Plant operation operate gate, globe, and butterfly valves. The new and outage schedules may also be considered in generic letter willinclude discussion of the ASME developing corrective action schedules. A and EPRI efforts. The staff also intends to licensee's schedule for completing corrective discuss other attributes of an effective, periodic action in response to GL 95-07 is considered MOV verification program in the new generic independent from GL 89-10. letter. The staff anticipates receiving summary The staff continues to monitor the industry's information regarding licensee actions in response efforts toward resolving concerns about the to GL 95-07 by February 1996. The staff will performance of MOVs at nuclear plants by review these submittals and provide a safety inspecting the implementation of GL 89-10 evaluation for each facility. The staff also
l 45 l I anticipates the need to perform limited follow-up received, and many identified significant inspections on an as-needed basis. operational and cost implications. The NRC has worked with commenters via announced public meetings to understand the comments and to l discuss the implications of possible changes to the j EVALUATION OF SIIUTDOWN AND proposed rule. The objective was to ensure the l LOW-POWER RISK ISSUES ppropriate safety benefit while minimizing or ehmmatmg the regulatory burden. As a result, the stafr has drafted a revised rule and corresponding After investigating the March 1990 loss of ac regu!atory guide, and has developed a new power at the Vogtle (Georgia) plant, an NRC regulatory analysis to fully address the comments. incident investigation team reported the need for The NRC plans to publish this revised rulemaking improvement and risk management of shutdown package, along with a statement of considerations, operations (NUREG-1410). As discussed in the during 1996 in order to solicit public comment. 1991-1994 NRC Annual Reports, the staff subsequently conducted an evaluation of shutdown and low-power issues. In February 1992, the NRC published a draft report, " Shutdown and
, , STEAM GENERATOR ISSUES Low-Power Operations at Nuclear Power Plants m the United States"(NUREG-1449), documenting the evaluation and its findings. Comments on the Steam generator tube integrity continues to be a draft report were addressed in the final significant issue for the nuclear industry.
NUREG-1449, which was issued in September Degradation of mill-annealed alloy 600 steam 1993. generator tubes has resulted in the development l of improved inspection techniques, alternative The staff also prepared a regulatory analysis of tube repair criteria, and improved i potential requirements for shutdown and primary-to-secondary leak rate monitoring low-power operations, and documented its programs. preliminary findings in SECY-93-190,
" Regulatory Approach to Shutdown and As discussed in the 1994 Anmeal Report, an Low-Power Operations," dated July 1993. The increasing number of plants have reported the regulatory analysis supported the staff's occurrence of circumferential cracking at the preliminary findings, in NUREG-1449, that expansien-transition location. Such circum-public health and safety have been adequately ferential cracking of steam generator tubes was protected during shutdown operation, but safety the subject of Generic Letter 95-03, which was levels could be substantially improved and such issued on April 28,1995. In GL 95-03, the staff improvement is warranted. alerted the industry to recent steam generator tube inspection findings at Maine Yankee Atomic The staff proposed rulemaking to resolve Power Station (Maine) and requested licenseo to concerns regarding shutdown and low-power take the following actions:
operations, and prepared a rulemaking package
- consisting of a draft regulatory analysis, a Federal (1) Evaluate recent operating experience with Register notice with a statement of considerations, respect to the detection and sizing of and a regulatory guide. This package was circumferential indications to determine the approved by the Commission on September 12, applicability to their plant.
1994, and was published for public comment in the Federal Register (59 FR 53707-52714) on (2) Develop a safety assessment justifying October 19,1994. continued operation until the next scheduled steam generator tube inspections are The proposed rule would have required that performed. licensees conduct analyses, establish administrative controls, and implement design (3) Develop plans for the next steam generator modifications to :mprove safety during shutdown tube inspections as they pertain to the operations. Hoy ever, numerous comments were . detection of circumferential cracking.
46 In addition, GL 95-03 alerted licensees to the Currently, on an interim basis, nine nuclear power importance of performing comprehensive plants have implemented voltage-based limits for examinations of steam generator tubes using ODSCC at the tube support plates. It is expected techniques and equipment capable of reliably that these and other plants will implement the detecting the degradation to which the steam criteria on a permanent basis. With respect to generator tubes may be susceptible. The staff also voltage-based limits, the staff recently reviewed issued Information Notice (lN) 95-40, which and approved an amendment that defines a provided information supplemental to GL 95-03. methodology similar to that documented in GL The staff is currently reviewing the responses to 95-05. However, this methodology explicitly takes GL 95-03, and has issued requests for additional credit for the tube support plates minimizing the information on a plant-specific basis, as likelihood of tube burst and tube leakage under necessary. postulated accident conditions. This amendment permits the use of higher voltage limits, and was During outages conducted in fall 1995, a number approved on an interim basis for two plants of plants have detected circumferential cracks at perated by the same utility. the expansion-transition region and at dented To more broadly address steam generator tube tube support plate locations. At one plant, several integrity issues, the staff issued an advanced thousand circumferential indications were notice for proposed rulemaking in August 1994. In detected at the expansion-transition region of the general, public comments on the proposed rule tubes. At several plants, the circumferential extent were supportive of the staff's efforts. The of the indications were large. These tubes were objective of the steam generator rule is to provide removed from service, and the severity and safety continued assurance that steam generator tubes significance of these indications is being assessed. will remain capable of performing their intended These inspection findings may be attributed, in
, safety functions while considering changing forms part, to improved mspection techmques and of degradation and providing incentives for using heightened data analyst sensitivity to state-of-the-art inspection and repair methods.
circumferential cracks. The NRC intends that licensees will accomplish this objective by developing and implementing Circumferential cracking has also historically steam generator programs that contain the j been observed in the U-bend portion of tubes appropnate elements important to ensunng 4 with small bend radii. In addition to defense-m-depth. Such programs must maintain a { circumferential cracking at these locations, balance of preventive, mspection/ repair, and , l cracking continues to occur in parent tubes in stigative measures that reflect current operatmg which sleeves have been installed. Tube sleeving experience and risk considerations. It is also was discussed in the 1994 Anmmt & port. intended that the steam generator rule will provide the broad performance objectives, while an associated regulatory guide wquid provide l Various flaw-specific tube repair criteria have more detailed performance criteria with guidance, been proposed by the industry for axially oriented as necessary, to ensure that these performance outside diameter stress corrosion cracking goals are met. The NRC expects to issue a draft 1 (ODSCC) confined to within the thickness of the steam generator rule and regulatory guide for I tube support plate. In support of these criteria, public comment in early 1997. I the staff issued GL 95-05, " Voltage-Based Repair 1 Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Crackm, g, on August 3,1995. The methodology PRIMARY WATER STRESS I described in this generic letter is intended to CORROSION CRACKING ! ensure adequate structural and leakage integrity ' of the steam generator tubing throughout the In 1989, primary water stress corrosion cracking operating cycle, without taking credit for tube (PWSCC)was identified to the Commission as an support plates minimizing the likelihood of tube emerging issue after leakage was reported from an burst or tube leakage under postulated accident Alloy 600 pressurizer heater sleeve penetration at conditions. Calvert Cliffs Unit 2 (Maryland). Since 1986, other
47 1 leaks have occurred in several Alloy 600 CRDM inspections. Currently, the model predicts pressurizer instrument nozzles at both domestic that Virginia Power Company plants, North Anna j and foreign reactors from several different nuclear 1 and 2 and Surry 1 and 2, have the most steam supplier vendors. In 1991, a leak was susceptible CRDM penetrations. Virginia Power discovered in a control rod drive mechanism Company is planning to conduct a CRDM (CRDM) penetration at the Bugey-3 plant in penetration inspection at North Anna 1 in spring l France. Since the discovery at Bugey-3, many 1996, and is considering inspecting North Anna 2 . European plants have conducted inspections and and the Surry units later. identified more cracked nozzles. The NRC staff is continuing to interact with the In 1992, the NRC staff conducted meetings with industry on this issue. The industry, in turn, is the owners' groups to discuss the significance of continuing its proactive approach to this problem, the CRDM leak at Bugey-3, with respect to updating the susceptibility model, developing an l domestic plants. Evaluations of CRDM nozzles in inspection plan, and determinmg the required U.S. reactor vessels showed that they are not inspection frequencies and repair techniques. inherently less susceptible to PWSCC than European CRDM nozzles. However, the NRC concluded that the cracking was not safety significant. The basis for this conclusion was that, RADIATION PROTECTION AT with perhaps one exception, the cracks were short NUCLEAR REACTORS and axial, leakage would occur before catastrophic failure, and visual examination would Daily monitoring of licensee and region reports to find leaks. Degradation of the vessel head by the NRC Operations Center alerts the staff to borated water m a crevice area was predicted t potential problems developing in radiation safety, occur very slowly; consequently, an event such as i ranging from major repair problems (involving ejection of a CRDM would be unlikely. highly radioactive components inside the facility) to contamination from small leaks of liquid and To address PWSCC of CRDMs at U.S. plants, the gaseous materials. These initial reports are industry responded by developmg a compre-
, , evaluated and discussed with regional NRC hensive mspection, repair, and mitigation inspection staff. Significant health physics program. Qualification test results demonstrated problems result in subsequent reactive regional that the vendors' mspection procedures and inspections. One example of NRR involvement personnel would be highly likely to find any and close coordination with regional counterparts PWSCC in the CRDM nozzles. in a event was the onsite airborne release from the radioactive waste system at the Hope Creek In FY 95, Palisades conducted a limited plant in New Jersey.
examination of eight in-core instrumentation penetrations and found no cracking. These During FY 95, the NRC staff provided radiation penetrations were selected because they could be protection support in licensing activities at most inspected from the top of the reactor head with of the operating nuclear power reactors, as well as relatively low radiation dose. Inspection of all reviews of design criteria and conceptual designs CRDM penetrations would require inspection for the Westinghouse AP600 advanced reactors. from underneath the reactor head and would Such support included detailed evaluations of result in a much higher radiation dose. Results occupational radiation protection design features, were consistent with those from earlier systems, equipment, and public dose controls and , evaluations, and the NRC's view of the safety projections for normal operations. The staff was , significance remains unchanged. However, the also active in the accident source term evaluation I fact that crac' king was found in two of four U.S. for the AP600. In addition, the staff's licensing vessels indicates that the problem is generic. support activities for operating plants included assessments of the postulated dose consequences Westinghouse has developed a model to establish for design-basis accidents, including quick- l a susceptibility rating for all U.S. PWRs. The turnaround evaluations of plant-specific steam model is continually updated as more plants have generator interim tube plugging criteria.
48 An important staff function has been to provide the boundaries of the plant site for indications of radiation protection evaluation of low level waste radioactivity originating from the plant. This handling and disposal activities at power reactors. environm:ntal monitoring program is to verify In this area, the staff has evaluated proposals that measurable concentrations of radioactive from several plants for the onsite disposal of material and levels of radiation are not higher wastes contaminated with very low fevels of than allowed or expected. In turn, the studies radioactivity. Another important staff function certify that the plant is in compliance with falls in the area of generic cominunications on regulations, and that the releases measured do not radiation protection matters. During FY 95, an exceed the amounts defined in the final Information Notice (IN) was issued to warn environmental statements as representing very licensees of a serious, continuing material small risks to members of the public. problem with certain self-contained breathing . . . . . apparatus used for emergency escape and rescue, Extensive monitonng is required for each plant. firefighting, and in other hazardous environments. The radiological environmental momtormg Another IN was written to alert licensees of a program regords when, if ever, radioactive, shielding deficiency at an operating boiling water contammation above natural background is reactor. detected outside the plant boundaries. Samples come from sources that range from lake, river, The staff continued to closely monitor the and well water for water-borne contaminants; to implementation of the major revision to 10 CFR radioiodine and particulate dusts for airborne Part 20, " Standards For Protection Against contaminants; to milk, fish, shellfish, and Radiation." The staff provided Regional vegetables for contaminants that might be inspection guidance and answered the licensees' ingested as foods. Direct radiation from each of implementation questions on the revised rule. up to 16 specific sectors of land surrounding the Previously developed guidance (NUREG/ Pl ant is also measured, by special radiation , CR--6204," Questions and Answers Based on dosimeters that gauge the cumulative radiation Revised 10 CFR Part 20," and NUREG/CR-5569, dose for each calendar quarter. Rev.1, " Health Physics Positions Data Base"))vas Results of licensees' radiological environmental placed on the pubh,e-accessible NRC Electronic
, monitoring programs are recorded in an annual Bulletin Board in early 1993. radiological environ nental report, which is
. . . submitted each May for the preceding calendar I To ensure consistent regional implementation and year. These reports for each year of operation of a 1 inspection of the revised rule, the staff ciosely power reactor are available for public inspection momtored the regional mspection activit,es i in local public document rooms (LPDRs; see governed by Temporary Instruction (TI) 2512/123, Appendix 4 for listing)-
" Implementation of the Revised 10 CFR Part 20."
This TI focuses the inspectors on the major The NRC conducts two programs that are aspects of the new rule, and provides specific independent from, but supplemental to, these inspection guidance for each area. Based on the licensee monitoring programs. In one, the NRC TI feedback to date, the power plant licensees are independently measures the direct radiation in the effectively implementing the rule. Finally, the staff sectors surrounding each plant using dosimeters continues oversight and review of significant at locations similar to those measured by the - proposed escalated enforcement actions as a licensee. The results of measurements for each I result of inspector findings. power reactor site from this "NRC Direct I Radiation Monitoring Network" are published ! quarterly in NRC documents, which are also available in the LPDRs. ENVIRONMENTAL RADIOACTIVITY i NEAR NUCLEAR POWER PLANTS ["onduct ni nmenta[sa$p i. a t vit e . rhe l purpose of these contracts is to have the States Under Federal regulations, all licensed U.S. mdependently collect and analyze samples from ! nuclear power plants are required to periodically the environs of the NRC-licensed facilities. The measure samples from the environment outside sample collections duplicate, as closely as
l 49 possible, certain parts of the licensee's 1993. The activities that most frequently environmental monitoring efforts, but they are contributed to PWR doses in 1994 were steam executed independent of the licensee. The results generator related work, area and system of State monitoring are compared to the results of decontamination, refueling activities, inservice licensee monitoring programs. inspections, and valve-related maintenance and repair work. In 1994, the average dose per unit for BWRs was OCCUPATIONAL EXPOSURE DATA 327 person-rem, down slightly from the average l AND DOSE REDUCTION STUDIES d se per unit of 330 person-rem in 1993. Major contributors to BWR doses m 1994 included valve maintenance work, inservice inspections, pump Since 1969, the NRC staff has been collating the maintenance, repair and refurbishment of control annual occupational doses at light-water reactors rod drive mechanisms, and refueling activities. (LWRs). Although the annual dose averages for both pressurized water reactors (PWRs) and In FY 95, the NRC continued its ongoing boiling water reactors (BWRs) have fluctuated contracts with Brookhaven National Laboratory over the years, the overall trend between the early (BNL) in the area of occupational dose reduction 1970s and 1980s was increasing, and annual plant at LWRs. The NRC-sponsored program monitors dose averages peaked in the early 1980s. These U.S. and foreign nuclear power plant efforts to high doses primarily resulted from NRC- reduce occupational dose. Under the contract, mandated plant upgrades imposed on all LWRs BNL publishes a periodical entitled "ALARA shortly after the 1979 accident at Three Mile Notes," which contains ALARA-related Island (Pennsylvania). Since 1983, the annual information submitted by U.S. and foreign average doses for both PWRs and BWRs have nuclear power plants. (ALARA is an acronym for steadily declined. "as low as reasonably achievable," the criterion characterizing the dose-reduction objective.) As The 1994 dose compilation includes data from 72 part of this contract, BNL is also involved on a PWRs and 37 BWRs, for a total of 109 LWRs. regular basis in compiling an ongoing annotated Plants that have not been in commercial bibliography of selected readings in radiation operation for a full year are not included in this protection and ALARA. In another continuing compilation. One new PWR, Comanche Peak 2 radiation protection-related contract with the (Texas), has been added to the plant dose NRC, BNL performed a study in FY 95 to assess compilation for 1994. Another PWR, San Onofre hot particle production, mitigation, and 1(California), has been dropped from the 1994 dosimetry. Another NRC-sponsored BNL study annuallisting because the plant has been on the impact of reduced dose limits was permanently shut down. Other plants that are no completed during FY 95. longer included in the dose compilation are Dresden 1 (Illinois), Fort St. Vrain (Colorado), Humboldt Bay (California), Indian Point 1 (New York), Lacrosse (Wisconsin), Rancho Seco AGE-RELATED DEGRADATION OF (California), Three Mile Island 1 (Pennsylvania), BWR INTERNALS
,I'rojan (Oregon), and Yankee Rowe (Massachusetts).
Many BW' vesselinternals are made of materials l In 1994, the average dose per unit for all LWRs susceptible w intergranular stress corrosion ! was 197 person-rem. This is 18 percent lower than cracking (IGSCC), including stainless steel, alloy l the 1993 average of 240 person-rem, and is the 600, alloy X750, and alloy 182 weld metal. lowest LWR average dose since 1969 (when only Background on IGSCC and the construction and seven LWRs were operating). functions of the core shroud were provided in the 1993 and 1994 Annual Reports. Since 1988, the In 1994, the average dose per unit for PWRs was NRC staff has been meeting every year with the 131 person-rem, down more than 32 percent from Boiling Water Reactor Owners' Group (BWROG) the average dose per unit of 194 person-rem in and the General Electric Company (GE), and i u -_
l 50 l later with the Boiling Water Reactor Vessel and ligaments would remain in the shroud such Internals Project (BWRVIP), to review the generic that structural integrity of the shroud would safety implications of reactor internals that are be ensured for the remainder of the plant's considered to be susceptible to IGSCC. operating cycle. i l Significant circumferential cracking of the core (3) No U.S. BWR has exhibited any of the ' shroud was discovered at the Brunswick Unit 1 symptoms (power-to-flow ratio mismatch) (North Carolina), Dresden Unit 3 (Illinois), Quad that would indicate significant leakage Cities Unit 1 (Illinois), Oyster Creek (New Jersey) through a 360*, through-wall shroud crack. and Vermont Yankee (Vermont) nuclear stations. . . In light of the extent of cracking observed at these (4) Mam. steam im.e or recirculation line breaks plants, the staff evaluated potential safety are both considered to be low probability events. concerns associated with the possibility of a 360 circumferential separation of the shroud following (5) Only short durations remained until core a postulated loss-of-coolant accident (LOCA). shroud inspections or repairs would be The staff's evaluation considered the potential for implemented by the individual BWR separation of the shroud during postulated licensees. accidents either to prennt full insertion of the control rods, or to open a gap large enough to To date, all licensees owning BWRs with shrouds preclude the emergency core cooling systems that are highly or moderately susceptible to (ECCS) frcm fulfilling their intended safety IGSCC have performed comprehensive functions. inspections or have implemented modifications (repairs) of their core shrouds. To date, core In order to verify compliance with the structural shroud modifications have been made in integrity requirements of 10 CFR Part 50.55a and Brunswick Unit 1 (North Carolina), Hatch Units 1 to ensure that the risk associated with core & 2 (Georgia), FitzPatrick (New Jersey), Oyster shroud cracking remains low, the staff concluded Creek (New Jersey), Quad Cities Unit 2 (Illinois), that it is appropriate for BWR licensees to Nine Mile Point Unit 1 (New Jersey), Dresden implement timely inspections and/or repairs, as Unit 2 (Illinois), and Pilgrim (Massachusetts). appropriate, at their BWR facilities. On July 25, Shroud modifications will be made in additional 1994, the NRC issued GL 94-03, which requested plants if inspection results and flaw evaluations BWR licensees to inspect their core shrouds by indicate that such modifications are necessary, or the next outage, and to justify continued safe at the discretion of the licensee. These operation until inspections could be completed. modifications are designed to ensure the structuralintegrity of the core shrouds based on The NRC staff received all of the BWR licensee an assumption that the shroud circumferential submittals in response to GL 94-03 by September welds are completely cracked, and are being 1994. The staff completed its evaluations of these reviewed by the NRC staff on a case-by-case licensee responses, and transmitted the safety basis. evaluation reports (SERs) to the appropriate BWR licensees. The staff concluded that, for all In spring 1994, the industry formed a new cases, BWR licensees provided sufficient organization, known as the BWR Vessel and l justification to operate their facilities until core Internals Project (BWRVIP), to address the issue l shroud inspections or repairs could be of age-related degradation of BWR internals. The implemented. The staff's conclusions were based BWRVIP is headed by several high-level utility on the following factors: executives to ensure that top executives in the I industry are aware of its function, purpose, and , . (1) No 360* through-wall core shroud cracking efforts. Since its founding, the BWRVIP has ) l has been observed to date in any U.S. BWR provided submittals addressing an integrated l that has performed a shroud inspection. safety assessment of the issue, guidelines on performing non-destructive examinations (NDE) (2) All analyses performed by U.S. licensees to of core shroud welds, guidelines on inspection date indicate that, even if cracking did exist scopes for reactor internals, and generic in a particular BWR core shroud. sufficient guidelines and acceptance criteria in regard to
51 l performing flaw evaluations and repairs of BWR review of the adequacy of the requirements and ' core shrouds. The NRC staff has approved the their implementation. During the program review, BWRVIP generic repair criteria document, the the staff also conducted surveys, met with latest revision to the BWRVIP guidelines industry representatives, and conducted an rcgarding core shroud inspection scopes and flaw extensive document research effort. The staff is evaluations, and the BWRVIP guidelines currently preparing a final report to categorize the regarding core shroud NDE methods. The issues, set priorities for staff action, and 1 BWRVIP has recently submitted a comprehensive summarize the results of the program review. The I safety assessment of the BWR internals listed in report will be placed in the public document room NUREG/CR-5754 as having the potential to upon completion, undergo age-related degradation. In addition, the BWRVIP has revised its guidelines and Data collection and analysis activities are recommendations for performing and qualifying continuing, and the review of operating experience NDE techniques, and has submitted its proposed was completed in 1994. As a result of that review, guidelines regarding standardized submittal the staff concluded that there are relatively few ; formats. The staff is currently reviewing these EQ problem reports, that degradation of EQ submittals. equipment was more frequent inside containment, znd that moisture intrusion was a significant contributor to degradation of EQ equipment. Information on replacement of EQ equipment, ENVIRONMENTAL QUALIFICATION compiled in 1994, led to the conclusion that cables, connectors, and penetrations should be OF ELECTRIC EQUIPMENT , meluded m, agmg reviews. In early 1995, the staff issued a report on the impact of the revised A review of environmental qualification (EQ) source term (from NUREG-1465, " Accident requirements for license renewal and failures of Source Terms for Light-Water Nuclear Power qualified cables during research tests led to the Plants") on environmentally qualified equipment development of the EQ lhsk Action Plan (TAP), at operating power plants. Brookhaven National which was issued in July 1993. The EQ TAP was Laboratory (BNL), under contract to the Office of developed to address (1) staff concerns relative to Nuclear Regulatory Research (RES), identified the differeaces in EQ requirements for older and and evaluated 260 documents related to EQ of newer plants,(2) concerns raised by research tests class 1E electric cables. This literature review indicating that qualification of some electric resulted in a NUREG/CR report scheduled to be cables may have been non-conservative, and published in early 1996. BNL has also developed a (3) concerns that programmatic problems database of EQ literature on class 1E cables, and identified in the staff's " Fire Protection will develop a database of cable materials. Reassessment Report" might also exist in the NRC EQ Program. The EQ TAP is intended to In August 1994, RES issued its EQ Research resolve these concerns through meetings with Program Plan, which provides for a cable industry, a program review of EQ, data collection condition monitoring program and a cable testing and analysis, a risk assessment, and research on program in support of the EQ TAP. BNL has aging and condition monitoring. Additional developed cable testing and cable acquisition background information regarding tiv 1 AP was programs, and has found several sources of provided in the 1993 and 1994 Annal Reports, naturally aged cable for the program. BNL also plans to test new, naturally aged, and artificially Since the development of the EQ TAP, the staff aged cables, and to evaluate condition monitoring 0 met several times with the NEI, the Nuclear techniques that could give insights into methods Utinty Group on Equipment Qualification, the for determining how equipment is actually aging EPRI, and licensees to discuss activities under the and performing in plants. EQ TAP. l In early 1996, the staff will evaluate the results of In June 1995, the staff completed the EQ program the program review, data collection and analysis, i review which involved a look back at the basis for other information collected to date, and the having different EQ requirements, as well as a current status of the EQ TAP to focus the
52 research efforts on the most critical issues. On the 1993, the staff initiated a program to system-basis of this evaluation the staff may adjust the atically evaluate the larger implications of the scope and schedules for research in the areas of Barsebsck and Perry experiences. accelerated aging, condition monitoring In January 1994, the preh,m, m ary results of the techniques, and accident testing. analytical program indicated that there was a high probability of strainer clogging and NPSH loss for a LOCA in a U.S. BWR. In response to this ECCS STRAINER BLOCKAGE IN finding, as well as the results of international r search studies, the staff issued Supplement 1 to BWRS NRC Bulletin 93-02, requesting that licensees take interim compensatory actions to limit the risk Unresolved Safety Issue (USl) A-43 dealt with from this failure mechanism. The interim actions concerns regarding the performance of include operator training, enhanced awareness of safety-related pumps during an emergency. The the potential event, and procedures to mitigate the principal concern was the potentialloss of net effects of strainer clogging. l positive suction head (NPSH) resulting from clogging of the suction strainers by fibrous debris On September 11,1995, Limerick 1 (Pennsylvania) dislodged during a loss-of-coolant accident experienced an event in which a stuck-open safety (LOCA). Based on an evaluation of low risk relief valve led operators to initiate two trains of significance, the issue was resolved in 1985 the residual heat removal system to provide without backfitting operating plants or plants suppression pool cooling. Approximately 30 under construction. However, more recent minutes into the event, the operators observed operational experience in the United States and flow and electrical current oscillations on the "A" abroad indicates that the potential for strainer train. As a result, the pump was shut down and clogging may be more significant than was subsequently restarted, and the shutdown of the perceived at the time USI A-43 was resolved. For unit proceeded with no further complications. The example, on July 28,1992, at the Barseb5ck 2 licensee subsequently determined that the flow plant in Sweden, the strainers on the suction side oscillations were caused by How blockage and of the containment spray system became clogged reduction in NPSH as a result of fibrous foreign l with fibrous insulation material dislodged by a material and corrosion product buildup on the I stuck-open relief valve. Similarly, in January and surface of the suction strainers. In response to the March 1993, the ECCS strainers at Perry Unit 1 event, the NRC issued NRC Bulletin 95-02 on (Ohio) became clogged with particulates and October 17,1995. This bulletin requested that fibrous material. licensees determine the operability of their ECCS and other pumps that draw suction from the The NRC staff has issued information notices suppression pool while performing their safety (ins) regarding the Barseb5ck event (IN 92-71) function. To do so, the bulletin requested that and the Perry events (IN 93-34). In addition, the licensees examine and evalu;'e suppression pool staff issued NRC Bulletin 93-02," Debris Plugging cleanliness, suction strainer cleanliness, and the of Emergency Core Cooling Suction Strainers," on effectiveness of their foreign material exclusion May 11,1993. All operating reactor licensees were (FME) practices. In addition, the bulletin requested to identify fibrous air filters, or other requested that licensees implement appropriate temporary sources of fibrous material not procedural modifications and other actions (e.g., designed to withstand a LOCA, which are suppression pool cleaning), as necessary, to installed or stored in their primary containment. minimize foreign material in the suppression pool, In addition, the staff requested that licensees take drywell, and containment. Finally, the bulletin l prompt action to remove any such material, and requested that licensees verify their operability implement any immediate compensatory evaluation through appropriate testing and measures that may be required to ensure the inspection. The staff is currently evaluating functional capability of the ECCS. The responses licensee responses to this bulletin. to NRC Bulletin 93-02 indicate that all licensees either do not need, or have already performed, Throughout 1994 and 1995, the staff worked with necessary corrective actions. In addition, in June the BWR Owners' Group (BWROG) to quantify 1
53 the factors contributing to the phenomenon, and submit quarterly PDMS reports summarizing to evaluate potential remedies. This effort led to ongoing Unit 2 activities. the development of a draft bulletin entitled, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," and a draft reg latory guide (RG) LOSS OF SPENT FUEL POOL DG-1038 (proposed revision 2 to RG 1.82) entitled, " Water Sources for Long-Term COOLING FUNCTION Recirculation Cooling Following a Loss-of- l Coolant Accident." The draft bulletin and RG The staff has completed its site-specific evaluation l detail the staff's proposed resolution for this of a 10 CFR Part 21 report, which was filed on ; issue, and were issued on July 31,1995, for a November 27,1992. That report contends that the 60-day public comment period. The draft bullet.in design of the Susquehanna Steam Electric Station outhnes three options for resolvmg this issue, . (SSES)(Pennsylvania) failed to meet numerous although licensees are free to propose alternative
, regulatory requirements with respect to a means of resolution: postulated sustained loss-of-cooling function in the spent fuel pool mechanistically resulting from (1) Install large strainers of sufficient capacity to a LOCA. The 1993 and 1994 NRC Annual prevent the strainers from clogging. Reports provide background regarding the postulated event sequence and early NRC review (2) Install a self-cleaning strainer with the activities. In general, the staff concluded that capability to remove debris from the strainer suitable modifications had been made to SSES to surface, thereby preventing clogging. address postulated seismically induced design-basis events within the facility's licensing basis.
(3) Install a backflush system. The staff further concluded that other postulated events leading to a sustained loss of spent fuel Each of these options would require additional pool cooling were outside the licensing basis for supporting measures to ensure compliance with SSES, and the potential for occurrence was 10 CFR Part 50.46. For example, for backflush, an remote. The staff presented its findings before the analysis would be required to demonstrate that Advisory Committee for Reactor Safeguards operators have sufficient time and system (ACRS) on December 8,1994, and documented capability to operate the backflush in a timely its conclusions in a safety evaluation report for fashion and for as many times as might be needed SSES, which was issued to the Pennsylvania during an accident. The current schedule for Power and Light Company (the licensee) on June resolving this issue calls for issuance of a final 19,1995. The staff also issued NRC Information bulletin by early 1996. Notice (IN) 93-83, Supplement 1, on August 24, 1995, to summarize the conclusions for the nuclear industry and members of the public. The staff is currently implementing a generic plan CLEANUP AT TIIREE MILE ISLAND to address the concerns identified in the 10 CFR Part 21 report, as well as separate concerns During 1994, the damaged reactor at Three Mile related to spent fuel storage pools identified Island Nuclear Station (TMI) Unit 2 during a special inspection at a permanently (Pennsylvania), was placed in post-defueling shutdown reactor facility. The generic plan monitored storage (PDMS). a passive, monitored includes the following actions: state similar to the SAFSTOR decommissioning alternative. GPU Nuclear, the TMI licensee, plans e search and analysis of information regarding to maintain Unit 2 in PDMS until TMI Unit 1 spent fuel storage poolissues permanently ceases operation. At that time, the licensee will decommission both units e assessment of spent fuel storage pool simultaneously. The NRC staff continues to operation and design at selected reactor monitor TMI Unit 2, and requires the licensee, to facilities
54 e evaluation of the assessment findings for edvational background, personal and career safety concerns preferences, and the needs of the agency. o A total of 80 entry-level engineers have selection and execution of an appropriate
- course of action based on the safety successfully completed the Reactor Engineer -
sigmficance of the findings Intern Program since its inception in 1988. In I June 1995, seven reactor engineer interns were l honored at a joint ceremony recognizing the i Tne staff has identified particular issues related graduates of intern programs established by the to spent fuel storage pools and completed onsite NRC's program offices. Currently,14 additional l assessments of spent fuel pool operations at four Headquarters-based interns are pursuing the sites in addition to SSES. The staff has docu- requirements of the program. mented the findings from these assessments, which focused on design features and admin-istrative controls, in reports for these sites. In addition, to address concerns that the sites selected for the assessments may not be ANTITRUST ACTIVITIES representative of all reactor sites, the staff has . expanded the scope of the technical review to As required by law sinN December 1970, the staff include a design and licensing document review, has conducted prelicensing antitrust reviews of all which is currently underway. On the basis of the construction permit and operating license appli-nature and significance of the findings from these cations for nuclear power plants and certain technical reviews, the NRC staff will develop commercial nuclear facilities. (See NUREG-0970, criteria for specific spent fuel pool operations for "Proccdures for Meeting NRC Antitrust potential use in formulating generic communica-
, Responsibilities," May 1985.) In addition, I tions, revisions of regulatory gu,i dance, and other
, applications to amend construction permits or appropriate regulatory actions. operating licenses resulting from a proposed transfer of ownership interest or operating responsibility in a nuclear facility are subject to antitrust review. Over the past several years, the staff has concentrated its antitrust activities in the areas of license amendment reviews (usually REACTOR ENGINEER associated with proposed new owners or l INTERN PROGRAM Paatornesuhing kom magus or acquishions J involvmg heensees, or proposed corporate !
reorganizations) and compliance proceedings ' initiated by requests to enforce antitrust license The NRC established the Reactor Engineer Intern
, conditions.
Program m 1988 to tram, new engineers m anticipation of the agency's future workforce During FY 95, the staff completed the following requirements. The program seeks recent reviews activities associated with the NRC's engmeering graduates, recruited primarily from antitrust responsibility- , colleges and universities with reputations for i strong engineering programs. Through . three reviews associated with requests by l individually tailored assignments at Headquarters, licensees to restructure their utility l Regional Offices, and plant sites-coupled with operations I extensive formal training in nuclear reactor ! technology-reactor engineer interns are given e a "No Significant Antitrust Change" ; wide exposure to the activities of the NRC. As a evaluation and subsequent reevaluation in result, they have the opportunity to acquire a conjunction with the merger of Gulf States broad grasp of the various concerns, roles, and Utilities Company and Entergy Corporation tasks of the agency. Upon completing the rigorous 2-year program, interns are given permanent
- termination of the review concerning the
!cchnical professional assignments based on their proposed merger agreement between El Paso
55 Electric Company and Central & Southwest its review of the proposed change in ownership of Corporation (CSW) Palo Verde. j 4 The staff also reviewed the competitive o review of the competitive implications l associated with a proposed sale / leaseback implications associated with the proposed sale or arrangement involving the Vermont Yankee leaseback of a significant portion of Vermont Yankee. After analyzing the proposed arrange-Nuclear Power Station (Vermont) ment, the staff determined that the new owner o a decision by the director of NRR issued could not exercise control over power or energy pursuant to a request for enforcement of produced by Vermont Yankee; the staff therefore antitrust license conditions associated with approved the sale / leaseback arrangement. Unit 2 of the St. Lucie nuclear plant (Florida) The Director of NRR issued a decision denying Each of these is discussed in the following the request by Florida Municipal Power Agency paragraphs. (FMPA) to initiate compliance proceedings against the Florida Power & Light Company The staff also conducted restructuring reviews of (FPL). FMPA alleged that FPL was in violation of the competitive implications associated with the certain antitrust license conditions attached to requests of San Diego Gas & Electric Company Unit 2 of the St. Lucie nuclear plant. The (San Onofre 2 and 3), Detroit Edison Company Director's decision stated that there was no basis (Fermi 2), and Pennsylvania Power & Light to initiate a compliance proceeding because Company (Susquehanna) to reorganize each of FMPA received adequate reliefin a parallel their operating units under a separate holding proceeding at the Federal Energy Regulatory company framework. In each of these reviews, the Commission. staff determined that the change in ownership or control associated with the restructuring did not adversely affect the relevant bulk power services market served by each of the facilities. Consequently, in each of its reviews, the staff INDEMNITY FINANCIAL ? concluded that the restructuring d;d i not represent PROTECTION, AND a sigmficant change from the previous antitrust review of the facilities. PROPERTY INSURANCE As a result of an appeal to the Eleventh Circuit by Cajun Electric Power Cooperative, Inc., regarding the staff's initial "No Significant 1995 INSURANCE PREMlUM Antitrust Changes" findmg, the staff completed another significant change evaluation of the REFUNDS merger between Gulf States Utilities Company and Entergy Corporation. After further review, The two private nuclear energy liability insurance the staff again found no basis upon which to pools American Nuclear Insurers and the conclude that any changes in the licensee's Mutual Atomic Energy Liability Undenvriters-activities would tend to create or maintain a paid policyholders a 29th annual refund of situation inconsistent with the antitrust laws. premium reserves, under their Industry Credit Cajun requested reevaluation of the staff's Rating Plan. Under the plan, a portion of the finding, and the staff affirmed its finding of no annual premiums is set aside as a reserve significant antitrust changes. available for refund to policyholders. The amount of the reserve available for refund is determined The staff reviewed testimony and filings provided on the basis of the loss experience of all by El Paso Electric Company (the licensee of Palo policyholders over the preceding 10-year period. Verde Nuclear Generating Station)in conjunction with the company's proposed merger with CSW. Refunds paid in 1995 (for the period from 1985 However, when CSW cancelled the merger through 1995) totaled $19,300,000, which is agreement in early June 1995, the staff terminated approximately 46 percent of all premiums paid on
56 l l the nuclear liability insurance policies issued in respect to reactors that are already licensed to 1985.The refunds represent about 62 percent of operate, the ACRS is involved in the review and the premiums placed in reserve in 1985. evaluation of any substantive licensing changes, i corrective actions resulting from operating events and incidents, and the resolution of generic safety issues. PROPERTY INSURANCE Activities of the ACRS are conducted in accord- ! The 13th annual property insurance reports ance with the Federal Advisory Committee Act ! submitted by power reactor licensees indicated (FACA), which provides for public attendance at l that, of the 73 sites insured,59 are covered for at and participation in ACRS meetings. Consistent least the $1.06 billion required in the revised with the charter of the ACRS and FACA property / accident recovery insurance rule, requirements, unclassified ACRS reports are published on April 2,1990, and 31 of those sites made part of the public record. carry the maximum $2.62 billion currently The ACRS membership is drawn from scientific available. The remaining 14 sites have sought or and engineering disciplines and includes been granted exemptions from the full amount of required coverage, because of their small size or individuals experienced in conducting safety-related reviews of nuclear plant design, their operating status. construction, and operation. During FY 95, the ACRS completed its annual report to Congress on the NRC Safety Research Program and other closely related matters. It also ADVISORY COMMITTEE reported to the Commission on the Regulatory i ON REACTOR Rdonn Inidadves and Nadonal Pufonnana Review Phase II, and on the following design SAFEGUARDS certification related matters: e General Electric Nuclear Energy test and The Advisory Committee on Reactor Safeguards analysis program for the Simplified Boiling (ACRS), established by statute in 1957 by revision Water Reactor Design, of the Atomic Energy Act of 1954, provides advice to the Commission on potential hazards of e NRC test and analysis program in support of proposed or existing reactor facilities and the AP600 Advanced light water passive plant adequacy of proposed safety standards. The design review. Atomic Energy Act also requires that the ACRS advise the Commission with respect to the safety e Proposed Commission Paper on staff of operating reactors and perform such other positions on technical issues pertaining to the duties as the Commission may request. Consistent Westinghouse AP600 standardized passive with the Energy Reorganization Act of 1974, the reactor design. committee will review any matter related to the safety of nuclear facilities specifically requested The committee also provided reports on topics l by the Department of Energy. Also,in accordance rehted to NRC training programs and the safety ; with Public Law 95-209, the ACRS is required to of operating reactors: ' prepare an annual report to the U.S. Congress on the Reactor Safety Research Program.
- Potential for BWR ECCS strainer blockage due to LOCA generated debris.
The ACRS reviews requests for pre-application site and standard plant design approvals, as well e NRC Technical'Iraining Center programs, as applications for construction permits, operating licenses for power reactors,10 CFR e Loss of spent fuel pool cooling following a Part 52 licenses, and certain test reactor facility LOCA at the Susquehanna Steam Electric licenses for construction and operation. With Station.
57 o Reactor \Wter Cleanup System line break for e Proposed Final Rule Change to 1D CFR operating Boiling Water Reactors. 50.36. " Technical Specifications." o Development of improved nondestructive e Proposed Final Generic Letter 95-XX, examination techniques. " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tbbes." In addition, the committee provided advice to the NRC on proposed rules, policy matters, and e Proposed Final Rule and Regulatory Guide regulatory guidance related to the following: for fracture toughness requirements for Light
.. \Wter Reactor pressure vessels. .
o Revisions to 10 CFR Part 71, " Packaging and l Transportation of Radioactive Material." e Proposed Final Revisions to Appendix J of 10 CFR Part 50, " Primary Reactor i o Proposed Final Draft Regulatory Guide Contamment Leakage Testmg for i DG-1023, "Evalt.ation of Reactor Pressure W ter-Cooled Power Reactors. Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft.-Lb." e Proposed Final Policy Statement on the use o f robabilistic P risk assessment methods in Proposed Final Revision 3 to Regulatory nuclear regulatory activities. Guide 1.118, " Periodic Testing of Electric Power and Protection Systems." .
- Proposed resolution of Genen.cIssue 24, o Proposed Final Amendment to 10 CFR " Automatic ECCS Switchover to 50.55a to Incorporate by Reference Recirculation."
Subsections IWE and IWL, Section XI, Division 1, of the ASME Boiler and Pressure e Health effects valuation. Vessel Code. e The Nuclear Energy Institute Petition for o Proposed Amendment to 10 CFR Part 54 Rulemaking to Amend 10 CFR 50.48, " Fire
" Requirements for Renewal of Operating Protection."
License for Nuclear Power Plants." e Review of best-estimate models for evaluation e Proposed Rulemaking-Revision to 10 CFR of emergency core cooling systems Parts 2,50, and 51 related to decom- performance, missioning of nuclear power reactors. In performing the reviews and preparing the o Proposed Rulemaking on reporting reliability reports previously cited, the ACRS holds and availability information for subcommittee meetings as needed, and full risk-significant systems and equipment. committee meetings regularly throughout the year. i t
CHAPTER 3 j 4 3
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Gh%ddb Sds). M v4 > m 4 .a n .m ; U.b s J Li. oded "i d ( ~ # 'dd u . & W: * /+ OPERATION ^l'INFORMATION AND INVESTIGATIONS AND ENFORCEME r TIONS This chapter deals with activities of NRC offices analyzes, and disseminates operational data; (2) concerned with (1) gaining the fullest possible identifies important events and their associated understanding of every aspect of operations at safeiy concuns and root causes; (3) assesses facilities licensed by the NRC, in particular of trends in performance; (4) evaluates operating unplanned and unforeseen occurrences from experience to provide insights into, and to which safety lessons may be drawn;(2)inves- improve the understanding of, the tigating alleged wrongdoing by licensees, risk-significance of events;(5) conducts reliability applicants for licenses or vendors to licensees, or studies of risk-important systems;(6) analyzes their contractors; and (3) taking appropriate human performance in operating events; and enforcement action against licensees for violations (7) produces periodic Performance Indicator, of NRC regulations, through the issuance of Abnormal Occurrence, and Accident Sequence notices of violation, assessment of civil penalties, Precursor Reports. and orders for the modification, suspension or revocation of licenses. The three offices dedicated AEOD's role was strengthened and expanded in to these tasks are the Office for Analysis and 1987 to include responsibility for diagnostic Evaluation of Operational Data (AEOD), the evaluations conducted under the Diagnostic Office of Investigations (OI), and the Office of Evaluation Program, incident investigations Enforcement (OE), respectively. conducted under the Incident Investigation Program, the Incident Response Program, and the Technical Training Center. The Diagnostic Evaluation Program, which has been dis-continued, provided independent assessments of ANALYSIS AND selected iicensees to suppiement information from ther NRC prpgrams. The Incident Investigation EVALUATION OF Program provides a structured NRC mvestigative resp nse to significant operationai events OPERATIONAL DATA . according to their safety sigmficance. The Incident Response Program };tovides a coor-The Office for Analysis and Evaluation of dinated NRC emergency response to ongoing Operational Data (AEOD) was created in 1979 to events through the NRC Operations Center. The provide independent capability to analyze and Technical Training Center provides initial and evaluate operational safety data associated with continuing technical training for NRC staff and activities licensed by the NRC. The office serves contractors. AEOD also provides administrative as the focal point for the assessment of and technical support to the NRC's Committee to operational events through the collection, review, Review Generic Requirements. analysis, and evaluation of the safety performance of both reactor and nuclear materials facilities. To The AEOD programs, taken as a whole, accomplish this mission, AEOD (1) collects, constitute the essential independent review and l
i 0 \ l l l , assessment of power reactor and nuclear unusual occurrences issued by the NRC, and I materials safety performance, and complement allegations. the regional, the Office of Nuclear Reactor Regulation (NRR), and the Office of Nuclear AEOD employs foreign event data in its Material Safety and Safeguards (NMSS) reviews comparative studies of reactor operational i of operating events. They perform a quality experience. Reports of operational events received I verification function that provides assurance of from the Nuclear Energy Agency (NEA) of the l feedback of important operational safety lessons. Organization for Economic Cooperation and l AEOD findings and recommendations continue Development, from the International Atomic to be addressed through generic correspondence, l Energy Agency, and from bilateral exchange i in the resolution of generic issues, and in programs with over 20 countries supplement the 1
- initiatives taken by industry. domestic data. AEOD continues to review and assess foreign operational experience for AEOD publishes annual reports of its activities in applicability to nuclear power plants in the NUREG-1272. Part 1 of NUREG-1272 addresses United States.
power reactors, Part 2 covers nuclear materials, and Part 3 presents the NRC's technical training During fiscal year 1995 (FY 95), the AEOD staff activities. The latest issue of NUREG-1272 is and contractors reviewed about 40 reports of Volume 9, published in June 1996. This report foreign events submitted to the NEA/ Incident provides greater detail on all the AEOD Reporting System (NEA/ IRS). The NRC programs described below. continued to participate in the NEA/ IRS to share U.S. reactor operational experience with the world i nuclear community. In FY 95 AEOD submitted 28 reports to the NEA/ IRS (see Chapter 8, P*' " " }' ! ANAIXSIS OF REACTOR OPERATIONAL EXPERIENCE Nuclear Reactor Safety Performance Trends Data Sources A subset of the information AEOD collects is used in the NRC Performance Indicator (PI) AEOD collects, analyzes, and evaluates a wide Program:(1) automade scrams while critical, range of operational data and publishes periodic (2) safety system actuations, (3) significant events, , Performance Indicator (PI), Accident Sequence (4) safety system failures, (5) forced outage rate, ! Precursor (ASP), and Abnormal Occurrence (AO) (6) equipment forced outages per 1000 reports, as well as technical studies on a variety of commercial critical hours, (7) collective radiation subjects. The data AEOD uses in its activities exposure, and (8) cause codes. Industry-wide include immediate notifications to the NRC annual averages of the first seven of these Operations Center in compliance with 10 CFR indicators are used to monitor industry safety 50.72, "Immediate notification requirements for performance. operating nuclear power reactors;" licensee event reports (LERs) submitted to the NRC in Since 1987 AEOD has monitored trends in overall accordance and 10 CFR 50.73, " Licensee event safety performance of power reactors through the report system;" monthly operating reports PI program. The PIs show a substantial reduction submitted in accordance with plant Technical in safety-significant operational events since then. Specifications; and the data base of component In 1995, the industry average number of scrams, failures in the Nuclear Plant Reliability Data safety system actuations, and significant events System (NPRDS), a system managed by the continued to decline slightly. Also,in 1994 and Institute of Nuclear Power Operations (INPO). 1995, the number of safety system failures began Other operational data include 10 CFR Part 21 to decrease after many years with no reports," Reporting of Defects and improvement. The 1995 data show, also for the Noncompliance," NRC regional inspection first time, an indication that the industry average reports, preliminary notifications of events or forced outage rate may be starting to improve. In
61 contrast, there has been a leveling off of what had manual or automatic actuations of certain been steadily improving trends in the equipment emergency core cooling systems, actuations of the forced outage rate and collective radiation emergency AC power system in response to low exposure. And while average unit availability has voltage on a vital bus. The annual industry improved considerably over the past nine years, average number of SSAs has declined steadily this has been due not to fewer forced outage since 1991, with continued slight improvement in hours (which remained essentially constant until 1995. 1995), but to greatly reduced scheduled outage hours. This is a consequence of longer fuel cycles, which result in greater intervals between refueling SIGNIFICANT EVENTS outages, and of shorter refueling outages. These changes are in part the industry's response to the Significant Events (SEs) are those events that the need to become more competitive. While the NRC staff identifies for the PI Program as industry has made significant improvement in meeting one or more of the following criteria: operational safety, problems with equipment (1) degradation of important safety equipment, failures continue, as evidenced by the percentage (2) a major transient or an unexpected plant of scrams caused by equipment failure (the response to a transient,(3) degradation of fuel leading cause of all scrams), the leveling off of integrity, the primary coolant pressure boundary, equipment forced outages per 1000 critical hours or important associated structures, (4) a reactor in 1994 and 1995, and the sustained high forced trip with complications, (5) an unplanned release outage rate through 1994. Implementation of the of radioactivity exceeding the Technical maintenance rule, and the collection and use of Specifications (TS) or regulations, (6) operation equipment reliability and availability data outside the TS limits, or (7) other events associated with it, will provide a means to reduce considered significant. The annual industry both the number and duration of forced average number of significant events decreased in shutdowns. 1995. REACTOR SCRAMS SAFETY SYSTEM FAILURES AEOD monitors automatic reactor scrams that The Safety System Failure (SSF) PI includes any occur while the affected reactor is critical. Reactor actual event or condition that could prevent the scrsms can result from initiating events that range fulfillment of the safety function of any of 26 from relatively minor incidents to precursors of safety systems, subsystems, or components. For a accidents. The annual industry average number of system that consists of multiple redundant . scrams has decreased each year since 1985, subsystems or trains,inoperability of all trains Equipment failures continue to be the leading constitutes an SSE Safety System Failures may be cause of scrams. Of the scrams caused by indicative of a plant's readiness to respond to equipment failure during FY 95, over half were anticipated events and postulated accidents. SSFs initiated by problems in four systems: feedwater, include unconditional failures (those events or main turbine and control, main generator, and conditions which render the system incapable of electrical. Over half of all scrams in FY 95 performing its safety function in all situations), occurred during normal plant operation, while and conditional failures (conditions that could, in most of the remainder occurred during testing certain specific situations, e.g., high energy line and maintenance. break or seismic event, prevent the system from performing its safety function). The annual industry average number of SSFs dropped by about one-third in 1994, and declined further in SAFETY SYSTEM ACTUATIONS 1995, after remaining essentially constant for the previous three years. This decrease is attributed AEOD monitors a subset of engineered safety to several factors, including an improvement in features actuations as safety system actuations the SSF definition, a reduction in the number of events reported in LERs, and a decline in SSF l (SSAs)in the Pi Program. The SSA PI includes
62 events discovered during design basis Reactor Operational Experience reconstitution efforts. Feedback AEOD studies of operational experience are broadly disseminated throughout the nuclear community and to the public. They provide a , FORCED OUTAGE RATE basis for decision-making based on actual I operational experience. In FY 95, the AEOD staff The Forced Outage Rate (FOR) PI is calculated continued to analyze and evaluate operational , by dividing the number of forced outage hours in experience and to publish reports of equipment I a period by the sum of the generator online hours Problems, events, and operatmg experience ' and the forced outage hours. Forced outages are reliability analyses. The staff placed increased defined m; those outages required to be initiated emphasis on the quantitative analysis of risk , by the end of the weekend following the discovery associated yvith operational events and conditions. of the off-normal condition. The trend in FOR Probabilistic risk assessment (PRA) and reliability can provide a perspective on overall plant analyses continued to be applied to a greater performance. The annual industry average FOR range of event studies. remained relatively constant from 1988 to 1994. 1 The decrease in 1995 may be an indication that AEOD ACTIVITIES TO IDENTIFY AND l the FOR is beginning to improve, or it may ADDRESS SAFETY ISSUES simply be a reflection of variability m the indicator. AEOD uses a systematic process to nominate, prioritize, and select safety issues to be studied, with emphasis on broad-based, programmatic )i issues and the industry's follow-up to previously s EQUIPMENT FORCED OUTAGES PER fya at on e dolo to ssess ach opic using 1000 COMMERCIAL CRITICAL IIOURS the following six attributes: (1) risk significance, (2) issue complexity, (3) requirement factors, The Equipment Forced Outage (EFO) PI is the (4) review factors, (5) industry initiatives, and number of forced outages caused by equipment (6) other considerations. failures in each 1000 hours that the reactor is
, The view of operating data includes allegations, critical after entering commercial operation. The vendor test data, plant test data, vendor EFO rate is the inverse of the mean time betnmen inspection reports, and regional inspection forced outages caused by equipment failures, reports. AEOD solicits identification of potential AEOD monitors the EFO rate as an indicator of safety issues from other program offices, regions, the effects of equipment problems on overall plant and interested parties. This approach strengthens performance. The annual industry average EFO AEOD's independent means of identifying and rate improved from 1991 through 1993, but has studying generic lessons learned from operating leveled off since then.
experience. AEOD staff also continued efforts to more effectively communicate the lessons of operating COLLECTIVE RADIATION EXPOSURE *Per "8 "' 8 pan cipat on in ind t oeo t e, presentation of papers at professional meetings, Although the NRC receives radiation exposure and attendance at owners' groups meetings and data on an annual basis. INPO routinely collects international meetings, the data on a quarterly basis. AEOD uses the INPO data in the Performance Indicator Program AEOD REPORTS to avoid duplication of effon. The annual industry average collective radiation for 1995 was Based on its review and analysis of operational unchanged from 1994. data, AEOD issued five reports during FY 95
63 that were broadly distributed within both the which are publicly available, are listed in Table 1 NRC and the regulated industry. These reports, and summarized in the following paragraphs. Table 1. AEOD Reactor Reports Issued During FY 95 Special Studies 1 D:te Title No. Author 10/94 Operating Experience Feedback Report- NUREG-1275, J. Boardman Reliability of Safety-heked Steam Vol.10 lbrbine-Driven Standby Pumps [AEOD/94-01] 03/95 Reactor Coolant System Blowdown at S95-01 J. Kauffman Wolf Creek on September 17,1994 S. Israel Engineering Evaluations 07/95 Operating Events With Inappropriate Bypass E95-01 J. Kauffman or Defeat of Engineered Safety Features l T:chnical Reviews 12/94 Potential for Boiling Water Reactor Emergency P)4-04 J. Boardman Core Cooling System Strainer Blockage Due to Loss-of-Coolant Accident Generated Debris 03/95 Major Disturbances on the Western Grid and T95-01 M. Wegner Related Events Operating Erperience Feedback Report-Reliability Power Operations (INPO) seminars in February of Safety-Related Steam Turbine-Driven Standby 1981 on inadequate TDP reliability, and a Pumps (NUREG-1275, Vol.10, [Special Study February 1990 Nuclear Management and Report AEOD/S94-01]). This study was Resources Councilletter to the NRC Executive conducted to review operational failures of Director for Operations which included these auxiliary feedwater (AFW), high pressure coolant standby turbines on a list of problem components. injection (HPCI), and reactor core isolation cooling (RCIC) pump turbine assemblies installed Most HPCI, RCIC, and AFW TDPs have as their in U.S. commercial nuclear power plants. The drivers Terry steam turbines designed to reach purpose of the study was to gather and review their required speed in 60 to approximately 120 available data on failures of standby turbine- seconds from cold shut-down. This is called a driven pumps (TDPs) to identify failure " cold quick-start." Leaking steam inlet valves mechanisms and corrective actions for feedback aggravate the situation by allowing condensed to the NRC staff and to industry. There have been steam to contaminate the turbine lubricating oil recurring problems with the reliability of these (frequently used as the hydraulic fluid for the turbine assemblies despite 71 NRC and industry governor and actuator, for which a primary failure generic communications and studies on the cause is water-contaminated oil). These conditions subject in the past 16 years, Institute of Nuclear can cause accelerated deterioration of turbines
l M and governors in a standby mode, resulting in the blowdown had continued unabated, RHR failures that are not identifiable until startup. cooling could have failed in 3.5 minutes and the RWST header line would have filled with steam in The results of this study confirmed the continuing 6 minutes. The licensee estimated that the core validity of earlier NRC and industry studies which would have uncovered in 30 minutes if the flow have shown that the most significant factors in Path had not been isolated. failures of standby TDPs have been the failures of the turbine drivers and their controls. 'Rirbine All f the emergency core cooling system (ECCS) failures during cold quick-start transients appear pumps take their suction from the RWST header to be due primarily to governor response, the Ime. If the ECCS pumps were turned on after six coordination of the opening of governor valves mmutes to mitigate an unabated blowdown and steam inlet valves, and condensate in turbine through this path, there could be a common- ; steam supply lines. These recurring problems m de failure of the pumps to operate caused by a i have as their apparent cause the failure to steam-filled RWST header lm, e. The ECCS pumps j perform the preventive maintenance identified at could also fail due to pressure pulses caused by i the INPO seminars and in manufacturers, cold RWST water collapsmg the steam m the RWST header Ime. These pumps are the normal l guidance, including specified periodicities. , 1 Enhancement of standby turbine reliability means of mitigatmg such a blowdown. If they all appears to be achievable by better industry-wide failed, successful mitigation of the event would l implementation of existing requirements and depend on the control room operators' cognitive guidance for design, maintenance and operation abilities to establish an alternate mitigation of the turbine assemblies. scheme. If core damage did occur, there would be a potential for sigmficant offsite doses because AEOD staff found that the demand failure the blowdown path bypassed the reactor probability for the AFW TDP was 6.5x10-2, contamment. excluding maintenance unavailability, compared The staff attributed this event to three causes: with a value from the Surry probabilistic risk assessment in NUREG-1150 of 1.1x10-2 for AFW. (1) An unrecogni cd design udnerability-an Failures were caused primarily by turbine RHR-RWST connecting line was designed overspeed trips. The staff found demand failure for operational convenience for refilling the probabilities of 1.9x10-2 for the HPCI T' pump RWST after a refueling outage, not for safety and 1.3x10-2 for the RCIC TDP, again et iding purposes. maintenance unavailability. Failures were due to a turbine overspeed trip and a failed flow controller. (2) Inappropriate use of the RHR-RWST The demand failure probability for both HPCI connecting line-The licensee inappropriately and RCIC at Peach Bottom in NUREG-1150 was used the RIIR-RWST connecting line to 3.0x10-2, increase the boron concentration of an RHR j train. (Other boration paths existed that i Reactor Coolant System Blowdown at Wolf Creck w uld n t have exposed the plant to this on September 17,1994 (Special Study Report hazard.) , AEOD/S95-01). On September 17,1994, with the
, , (3) Inadequate work control-The licensee was reactor m Mode 4 on RHR cooling (350 psig and deficient in the control of maintenance and 300* F) and the pressurizer nearly solid, there was operational evolutions by allowing an inadvertent blowdown of about 9200 gallons of incompatible activities to occur reactor coolant through the residual heat removal simultaneously while in a degraded safety (RHR) system to the refueling water storage tank mode on RHR cooling.
(RWST) at the Wolf Creek Nuclear Generating Station. This event occurred because of The NRC issued Information Notice No. 95-03, incompatible, concurrent activities involving " Loss of Reactor Coolant Inventory and Potential borating one train of RHR and testing a valve in Loss of Emergency Mitigation Functions While in the other RHR train while cooling down to begia a Shutdown Condition," to inform all reactor a refueling outage. The event was terminated in licensees of the circumstances and potential one minute by operator intervention: however, if consequences of the Wolf Creek event. The event
65 was characterized by the Accident Sequence 3. Poor watchstanding practices in the areas of Precursor methodology as the most risk- communications, shift turnovers, control significant event of 1994, with a conditional core board walkdowns, verification of automatic damage probability of 3.0x10-3, and was reported actions, and response to alarms contributed to Congress as an abnormal occurrence. to inappropriate ESF defeats and delayed their recognition and recovery. Operating Events IVith inappropriate Bypass or Potentialfor Boiling il'ater Reactor Emergency Core Defeat of Engineered Safety Features (Engineering Cooling System Stramer Blockage Due to Evaluation Report AEOD/E95-01). AEOD staff evaluated events involving operator control of bss-(-Coolant Accident Generated Debn,s (Techmcal Review Report AEOD/r94-04). Tlu,s enginecid safety feature (ESP) equipment. report addresses the status of the issue of i Appropriate control of ESFs is an essential blockage (cloggm, g) of BWR emergency core element of reactor safety, as evidenced by the , Three Mile Island Unit 2 and Chernobyl Unit 4 cooling system stramers followmg a loss-of-coolant accident which was previously accidents, in which operators defeated ESFs that addressed in Unresolved Safety Issue (USI) A-43, could have prevented or mitigated the accidents. " Containment Emergency Sump Performance," The accidents and literature on human error show January 1979. AEOD performed an mdependent that operator recovery from an inappropriate ESF review of events and activities (including the event defeat is not certain. at Barsebsck in 1992) which have occurred since the closure of USI A-43, to determine if For the nine events included in this study, dditional or more expeditious actions are recovery from operator defeat of the ESF needed. Based on that review, and the present occurred prior to any serious safety consequences. estimated core damage ticquency attributed to if any of these events had continued, the recovery this issue of between 4.2x104 and 2.5x10-5 per guidance in emergency operating procedures Pl ant year, the staff found that progress toward would likely have led operators to attempt to , resolution of this issue appeared to be restore the ESF function. Nevertheless, these commenmate with other complex safety issues of events are precursors to more serious events and , the same relative nsk, such as station blackout, ; indicate weaknesses in operator control of ESFs. loss of shutdown coohng, and motor-operated Strengthening these weak areas offers the opportunity for better operator control of ESFs. y lve perebility. The NRC issued Bulletin 95-2, Unexpected Cloggmg of Residual Heat Removal 1 (RHR) Pump Strainers While Ogerating in the The AEOD staff review indicates that there Suppression Pool Cooling Mode, prepared a continue to be m. stances where management has proposed Bulletin, " Potential Plugging of not consistently determmed, commumeated, a,nd
, Emergency Core Cooling Suction Strainers by implementeu a pohey defining when it is and is Debris," and prepared a proposed Revision 2 of not appropnate to bypass, defeat, or turn off a Regulatory Guide 1.82, " Water Sources for safety system. Tins is evidenced by the follow,mg Long Term Recirculation Cooling Following a findmgs: Loss-of-Coolant Accident."
- 1. Procedures and other written guidance Major Disturbances on the IVestern Grid and sometimes did not provide clear, consistent Related Events (Technical Review Report guidance to address situations where safety AEODTI95-01). Shortly after midnight on systems should be throttled, bypassed, turned December 14,1994, a line fault, caused by a off or reconfigured, and when they should be contaminated insulator flashing over in a heavy reset or reinitiated. fog in Idaho, tripped a major 345 Kv transmission line. The parallel 345 kV line opened and a third
- 2. Operators were not consistently fully 345 kV line in the area opened shortly afterward.
knowledgeable of emergency operating Some seconds later, the three 500 kV lines from procedures, their bases, and appropriate ESF Midway to Vincent stations in California tripped control practices in that some operators had on overload. Diablo Canyon Units 1 and 2 saw difficulty in using procedures during routine, undervoltage on the reactor coolant pump buses uncomplicated events. and the reactors automatically tripped. After the
1 66 loss of about 2169 MW from Diablo Canyon,30 high voltage lines and 29 generating plants Nuclear Material Events Data Base tripped. More than 4800 MW ofload was lost and AEOD collects, reviews, and codes nuclear the Western grid split into four islands, each of materials event information reported by NRC , which experienced frequency disturbances. licensees and Agreement States. Approximately 7000 NRC heensees and 15,000 Agreement State i Palo Verde experienced a five minute transient ense su reporb o e n s, as " that the licensee called a roIler coaster nde, ( 9 e 9{ pe ,} g9lat n (10 during which the frequency m, ereased to 60.4 Hz CFR), comparable Agreement State regulations, then dipped to 59.3 IIz before it recovered. or license conditions. NRC licensees submit Information from Washington Nuclear Power Unit reports directly to NRC regional or headquarters 2 indicated that the mam generator output offices. Agreement State licensees submit reports voltage, frequency, and power fluctuated. The to the States, which in turn voluntarily transmit reactions of the Western gnd m response to the summary reports to the NRC under an informal transient appear to have been appropnate to the information-sharing agreement. In addition, the transient. NRC obtains reports of events from other sources, such as NRC inspection reports, and occasionally from non-licensees, including members of the public. Reportable nuclear materials operating events ALLEGATIONS include (1) medical misadministrations of radiation or radiopharmaceuticals to patients, (2) personnel radiation overexposures, (3) loss of The NRC receives allegations from individuals or control of licensed material, (4) problems with organizations who assert some impropriety or ,quipment that uses licensed material or is I l inadequacy in activities regulated by the NRC. otherwise associated with the use of licensed Allegations received from nuclear power plant material (5) releases of material or sites are entered into the Allegation hianagement contamination, (6) leaking radioactive sources, i System managed by NRR; NRR and the regions (7) problems during transportation of licensed I validate and track their resolution. AEOD material, (8) problems in fuel cycle facilities, and analyzes trends in the numbers of allegations (9) problems at nonpower reactors, received and publishes the data without revealing the identity of the alleger. Each allegation may In 1993 AEOD developed a new database called contain one or more individual concerns, and no the Nuclear Materials Events Database (NMED). . differentiation is made in the data for the vaiying In developing the data base structure, AEOD levels of safety significance of the allegations, solicited and received substantialinput from the NRC Headquarters Offices of Nuclear Matenals Safety and Safeguards (NMSS) and Nuclear Regulatory Research (RES), the regional offices, and the Agreement States. The NMED contains ANALYSIS OF NUCLEAR bout 12,480 detailed records of reported events. (Agreement State data are available only from MATERIALS EXPERIENCE 1991 on.) The NMED contains records of materials events for all categories of materials AEOD conducts an m. dependent review and licensees, including non-power reactors. Radiation 1 evaluation of the operational expenence of overexposure events for commercial power programs involvmg the use of matenals bcensed reactors are also maintained in the NMED. by the NRC and the Agreement States, such as In previous annual reports, nuclear materials data reactor-produced isotopes, natural and enriched were presented for the prior calendar year uranium, and other special nuclear materials. The because of the delay in obtaining the data from primary concern with the use of these materials is the Agreement States. For example, the FY 94 the potential for overexposure which can cause NRC Annual Report included data for calendar cancer or, in severe cases, death. year 1993. The NMED now provides the
67 capability to maintain nuclear materials data treatment. Sodium iodide events are the second current, with regular, periodic updates from most frequent type of misadm'nistration among Agreement States. Therefore, this anual report NRC licensees and the third most frequent among contains data for calendar year 1994 and the first Agreement State licensees. Misadministrations nine months of 1995, to cover the time period involving brachytherapy and sodium iodide most j from the FY 94 report. Future reports will include often result in overdoses rather than underdoses. data for the then current fiscal year. The primary causes of the reported misadministrations were (1) the use of an Nuclear Materials Performance incorrect factor in calculating a therapeutic dose, (2) misunderstandmg of the physician's request, In 1994 and the first nine months of 1995, the (3) source migration, (4) not following the Quality NRC received reports of 1058 events from nuclear Management plan,(5) incorrect entry of data into materials and nonpower reactor licensees-614 the automated equipment, and (6) sources from NRC licensees and 444 from Agreement improperly loaded into the applicator. As part of States. (Each report may result in more than one the response to medical misadministration events, event; for example, an equipment problem may the NRC issued nine Information Notices to cause an overexposure, in which case, two events inform licensees of these events. would be assigned to that report. The number of reports is therefore smaller than the number of events.) Because licensees submit revisions, late RADIATION OVEREXPOSURE reports, or retractions, minor changes may occur in the data published from year to year. NRC and Agreement State licensees reported 28 events during 1994 and the first nine months of 1995 that resulted in overexposures to 57 people. NRC licensees reported 9 cvents which MEDICAL MISADMINISTRATIONS overexposed 11 people, and Agreement State licensees reported 19 events which overexposed 46 The NRC regulates approximately 2000 h.eensees people. Four of the 28 events resulted in multiple m 21 states, the District of Columbia, and ,U.S. overexposures; three of the four caused multiple territones, that use radionuclides m radiation overexposures to members of the public, and the therapy and nuclear medicme applications. These fourth was a radiography event in which two heensees include hosp,tals, i chm,es, and physicians workers exceeded their annual exposure limit. m private practice. Such facilities submitted
, Four overexposure events (only one of which was reports of 49 cvents that resulted in a multiple overexposure) met the criteria for misadministrations durm, g 1994 and the first nine reporting to Congress as Abnormal Occurrences.
months of 1995. The 29 Agreement States, which regulate about 5000 medical licensees, submitted Among NRC licensees, research/ commercial users reports of 20 events that involved reported the most overexposure events and misadministrations during the same period. individuals overexposed. Agaement State Misadministration events that demonstrate a industrial radiography licensees reported the most major failure of the radiation safety program or overexposure events, but research/ commercial result in an adverse health effect to a patient are users reported the most individuals overexposed. reported to Congress as Abnormal Occurrences. (Agreement States have approximately three times Of the 69 misadministration events,26 were as many industrial radiography licensees as does reported by the NRC to Congress as Abnormal the NR'C.) Occurrences (two of these events were reported with the same Abnormal Occurrence number The primary causes of the overexposures to both because they involved the same type of error at medical / academic and research/ commercial the same facility within a week of each other). licensees included failure to ensure that adequate dosimetry was issued and monitored, and failure For both NRC and Agreement State licensees, the to wear adequate protective clothing in areas majority of the reported medical containing radioactive particles. There were misadministrations involved brachytherapy several direct causes of overexposure events
l 68 1 l l involving industrial radiographers, including overexposures account for a significant number of failure to conduct the required radiation surveys, the overexposures reported to the NRC and for failure to set up or monitor posted radiation most of the acute overexposures that have l boundaries, failure to follow established resulted in physical injury. This is especially . l emergency procedures, and the lack of supervision significant because radiography licensees account j of untrained assistants. As a part of the response for less than 10 percent of all NRC and to overexposure events, the NRC issued four l l ' Agreement State licensees. While the direct cause information notices to inform licensees of these of most radiography overexposures generally can events, be ascribed to " failure to use survey meters," underlying causes of radiographer overexposures are not always documented. OTIIER NUCLEAR MATERIALS EVENTS The major findings from the study are the following: Other nuclear materials events included loss of control of licensed material, leaking sources, (1) He primary factors contributing to release of material, transportation events, radiography overexposures are procedural equipment problems, fuel cycle facility events, and err rs, equipment problems, and external test, research, and training reactor events. In,1994 factors, such as supervision and area control. and the first nine months of 1995 the NRC (2) Errors were found to commonly occur in the received reports of 556 such events from NRC setting-up of equipment before the licensecs and 405 events from Agreement States. radiograph. One equipment problem, one loss of control of material, and one transportation event resulted in (3) Reported data describing radiography overexposures which met the criteria for reporting exposure events are sparse and lack many of to Congress as Abnormal Occurrences. Another the details needed for rigorous human factors equipment problem resulted in a misadminis- evaluation. tration which met the criterion for reporting as an Abnormal Occurrence. A third eqmpment Misadministrations and Other Medical Events problem caused a release of material which was Caused by Computcr Errors. The NRC sponsored also reported to Congress as an Abnormal a study at the Lawrence Livermore National Occurrme. Laboratory of events involving computer errors that resulted in misadministrations. The lab analyzed the 22 events involving 172 patients that Nuclear Materials Operating were reported to the NRC by NRC licensees and Experience Feedback A 8reement States. The analysis addressed treatment plannmg and dose delivery systems. Based on its review and analysis of operational The patient risk associated with these types of data, AEOD issued two reports on nuclear misadmimstrations was determmed to be about materials issues during 1995 that weie distributed the same as for those not mvolvmg computer within the NRC and the industry. These reports, errors. The major findings of the study are as which are publicly available, are summarized f0ll0*S: below. e The number of ccmputer-based rnisadministrations per year has been Human Performance Evaluation ofIndustrial increasmg, based on the number of events Radiography Erposure Events (INEL-95-0387). AEOD contracted with the Idaho National reported to the NRC from 1981 th.ough 1993. Engineering Laboratory (INEL) to perform a e The number of reported misadministrations human factors review of radiography involving the treatment planning process has overexposure events using data in the NMED. been liigher than that associated with the The purpose of the study was to develop better dose delivery process. l information on the causes, and ways to minimize the occurrence, of radiation overexposures. De e Events resulting in reported misadminis-data show that industrial radiography trations to multiple patients occur more often
69 in computer-based radiation therapy data for individuals for whom personnel processes than in manual therapy. monitoring is required. o Nearly three-quarters of the computer Almost all radiation doses from nuclear power error-related medical misadministrations of plants are occupational doses, that is, doses to byproduct material are directly linked to nuclear power plant employees and contractors human errors and procedural deficiencies. who work at the plant. The economics of operatmg a plant creates a strong impetus to o Nearly one-half of the events have involved reduce exposures and achieve ALARA (as low as reasonably achievable) object,ves. i As a result, user interface deficiencies. , utility violations of NRC limits on personnel exposure are rare, and the vast majority of o In none of the events evaluated did the nuclear power plant personnel have annual software or the hardware limit the exposures far below NRC regulatory limits consequences of a misadministration. . specified in 10 CFR Part 20. The mean value of ecupational radiation exposure has been reduced The NRC issued an NMSS News Letter article in from .94 cSv (940 mrem) per worker m 1973 to .29 NUREG/BR-0117, No. 95-4, Dec. '95/Jan. '96 cSv (290 mrem) per worker m 1994. Tius informing licensees of the findings of the study. reduction is beh,eved to result primarily from the licensees' extensive dose-reduction efforts. Some measures that reduce collective exposure are an effective maintenance program, experienced and RADIATION EXPOSURES FROM well. trained personnel, a good water chemistry REACTORS AND NONREACTORS control program, effective decontamination and cleanup practices, good fuel cladding integrity, effective radiation exposure control programs, According to the National Council on Radiation good housekeeping, and an alert health physics l Protection and Measurements, the average total staff. I effective dose equivalent to a person in the United States is approximately .36 centiSieverts (cSv)(360 Nonoccupational doses from operation of nuclear l millirem [ mrem]) per year, mostly from natural power plants have declined faster than sources of radiation. He average person in the occupational doses. In 1975, nonoccupational United States receives an effective dose equivalent collective exposures were approximately 6.5 of about 0.05 cSv (50 mrem) per year from percent of occupational doses. By 1990, the medical applications. The entire fuel cycle, nonoccupational collective doses were less than including operation of reactors, contributes less 0.2 percent of occupational exposures. The I than 0.001 cSv (1 mrem) per year. All other calculated annual offsite dose commitments are i human-controlled sources of radiation combined reported annually in NUREG/CR-2850, add up to an effective dose equivalent of " Population Dose Commitments Due to approximately 0.006 cSv (6 mrem) per year. Radioactive Releases From Nuclear Power Plant Sites." The NRC regulates both reactor aad nonreactor applications of nuclear materials. All NRC Exposure data for 1994 show that, of the six licensees are required to monitor employee categories of licersees that are required to report exposure to radiation and radioactive materials at collective exposures for monitored individuals, levels sufficient to demonstrate compliance with reactor licensees, by virtue of the large number of the occupational dose limits specified in 10 CFR employees, had the highest annual collective Part 20. Licensees of power reactors, and those exposure, followed by radiographers, fuel involved in industrial radiography, the fabrication licensees, and manufactures and manufacture and distribution of radioactive distributors. Low-level waste disposal and materials, low-level radioactive waste disposal, independent spent-fuel storage licensees had and independent spent fuel storage and relatively low collective doses. On a processing, are required by 10 CFR 20.2206 to dose-per-worker basis, however, industrial provide to the NRC annual reports of exposure . radiographers received the highest exposure.
l 70 l l 1 Nevertheless, for all categories of licensees damage probabilities associated with nuclear ; including radiographers, the dose-per-worker is power plant events or conditions. The principal far below the allowable limits established in objectives of the program are to quantify and 10 CFR Part 20. rank the safety significance of operating reactor events, to determine their generic implications, to characterize risk insights, and to document and disseminate the evaluations for feedback to plant ABNORMAL OCCURRENCES operators to promote learning from experience. l An accident sequence precursor is an operational
,The NRC prepares periodic seports to Congress event or plant condition that is an important of abnormal occurrences (AOs)involymg facilities element of a postulated accident sequence and activities regulated by the NRC. (In associated with inadequate core cooling, a December 1995, Public Law 104-66 changed the sequence which would be expected to result in AO reportmg frequency from quarterly to core damage. The ASP methodology evaluates annually.) An AO is defined as an unscheduled disparate elements of operational experience, with meident or event that the Commission determmes random failure probabilities used for other to be sigmficant from the standpo,mt of pubhc branches of the event tree models. The figure of health or safety. AEOD is responsible for merit for ASP analyses is conditional core preparmg the NRC's " Report to Congress on damage probabilit Abnormal Occurrences" (NUREG-0900). (These greater than 1x10"7 (CCDP).
are considered Events with accident CCD reports may be purchased from the sequence precursors. Supenntendent of Documents, U.S. Government Printing Office, Post Office Box 37082, The results of the ASP analyses are considered Washington D.C. 20420-9328, or the National indications of the level of risk associated with Technical Information Service,5285 Port Royal operating nuclear power plants based on direct Road, Springfield, Virginia 22161. Copies are also assessment of actual operating experience. The available for public inspection or copying for a fee precursor events from the ASP Program comprise at the NRC Public Document Room,2120 L a unique database of historical system failures, Street (Lower Level), N.W., Washington D.C. multiple losses of redundancy, and infrequent 20555, or at local public document rooms core damage initiators. Several of the recorded throughout the country. See Appendix 4 for a list precursor events involved equipment failure of local public document rooms.) caused by factors, conditions, or phenomena that affected the ability of safety equipment to The five AO reports published in FY 93 perform its function. These mechanistic failures (NUREG-0090, Vol.17, Nos. 3 and 4, and Vol.18, are different from " random" failures or Nos.1,2, and 3) described 3 AOs at nuclear unavailabilities of equipment. power plants,15 AOs at other NRC licensees, and 10 AOs reported by Agreement States (see The results of the ASP analysis of 1994 Table 2). The reports also provided updates of operational events are shown in Table 3. There certain AOs previously reported as well as were 11 precursors in 1994, as a result of 9 events descriptions of Other Events of Interest. or conditions (11 different units were affected). Consistent with current practice in the ASP Program, the preliminary ASP analyses of 1994 operational events were reviewed by the affected RISK AND RELIABILITY ANALYSIS licensees, the NRC staff, and an independent NRC contractor, Sandia National Laboratories. Based on the comments received from these Accident Sequence Precursor Program reviewers, the analyses were revised as necessary to provide more accurate risk assessments of the The Accident Sequence Precursor (ASP) Program events. Details of the analyses may be found in wcs px.babistic risk assessment (PRA) NUREG/CR-4674, Volumes 21 and 22, published techniques to evaluate the conditiend s.are in December 1995.
71 Table 2. Abnormal Occurrences Reported During FY 1995 NRC LICENSEES 94-15 Sodium Iodide Event 03/09/94 Welborn Memorial Moderate exposure to Baptist Hospital radioactive material. Evansville, IN 94-16 'Ieletherapy 07/21-22/94 Medical Center Irradiation of wrong part Misadministration Hospital of the body. Chillicothe, OH 94-17 Sodium Iodide 07/06/94 St. Joseph Mercy Overdose to treatment Hospital site. Pontiac, MI 94-18 Multiple Teletherapy 07/28-08/03/94 Sinai Hospital Irradiation of wrong part Misadministrations Detroit, MI of the body. 94-19 Brachytherapy 07/29/94 University of Underdose to treatment Misadministration Massachusetts site. Medical Ctr. ; Worcester,MA i 1 94-20 Core Shroud Cracking 10/93-Present Boiling Water Reac- ' 'though no adverse conse-tors; Intergranular vences are expected at stress corrosion currently observed levels of cracking of core shroud cracking, it has been I shrouds. postulated that a 360-degree through-wall core shroud crack in concert with a loss-of-coolant accident has the potential to lead to core damage. 94-21 Radiopharmaceutical 10/88-6/93 Ball Memorial Recurring incidents of Diagnostic Hospital administering higher doses Misadministration Muncie, IN than procedurally allowed for diagnostic imaging. 94-22 Radiopharmaceutical 08/09/94 Veterans Medical Administering the wrong Diagnostic Center radiopharmaceutical for a Misadministration Long Beach, CA diagnostic study. 94-23 Brachytherapy 08/03/94 N. Memorial Irradiation of wrong part Misadministration Medical Center of the body. Robbinsdale, MN 95-1 Brachytherapy 11/18/94 Welborn Memorial Overdose to treatment site. , Misadministration Baptist Hospital l Evansville, IN 95-2 Reactor Coolant 09/17/94 Wolf Creek Nuclear Inadvertent blowdown which System Blowdown Generating Station could have uncovered the Burlington, KS core, disabled the emergency core cooling system pumps, and led to core damage.
72 4 i Table 2. Abnormal Occurrences Reported During FY 1995 { (continued) 1 NRC LICENSEES (continued) 1 95-3 Previously Unidenti- 12/06/94 Millstone Nuclear Identification of a condition ; fled Containment Power Station Unit 2 which established a potential ' Bypass Path New London, CT path for the release of radio-activity to the atmosphere. 95-4 Brachytherapy 03/14/95 University of Virginia Irradiation of wrong part of Misadministration Medical Center the body. Charlottesville, VA 95-5 Radiopharmaceutical 05/09/95 Massachusetts Overdose to treatment sites. Therapeutic General Hospital Misadministration Boston, MA 95-6 Brachytherapy 02/94-05/95 Madigan Army Overdoses or underdoses to Misadministrations Medical Center treatment sites. Fort Lewis, WA 95-7 Brachytherapy 06/08/95 Marshfield Clinic Overdose to treatment site. Misadministration Marshfield, WI 95-8 Brachytherapy 07/25/95 Providence Irradiation of wrong part of Misadministration Hospital the body. Southfield, M1 95-9 Ingestion of 06/28/95 National Institutes Ingestion of radioactive Radioactive Material of Health material by 27 research Bethesda, MD employees from an unknown cause. AGREEMENT STATES AS 94-6 Loss of Manage. 01/93-04/93 Georgia-Pacific An incident with implications ment and Proce- Paper Mill for similar facilities that dural Control of Palatka, Florida created a major safety con-a Radioactive cern. A series cf events, Source recurring incidents, and incidents with implications for similar facilities that create a major safety concern. AS 94-7 Breached Source 04/21/94 Kay-Ray /Sensall, Inc. Major contamination event. Mount Prospect, IL AS 94-8 Brachytherapy 10/17/94 St. Joseph's Hospital, Irradiation of wrong part of Misadministration Orange, CA the body.
73 Table 2. Abnormal Occurrences Reporf .ng FY 1995 (continued) AGREEMENT STATES (continued) AS 94-9 Brachytherapy 12/07/93 University of Overexposure was due to Misadministration California's data entry error. Long Hospital San Francisco, CA AS 94-10 Tbletherapy 05/10/93 New York State Irradiation of wrong part Misadministration Department of of the body. Health " Unspecified Licensee" (Informa-tion omitted by State Law) AS 95-1 Teletherapy 05/23-26/93 " Unspecified Irradiation of wrong part of Misadministration Licensee", the body. New York, NY (Information omitted by State Law) AS 95-2 Brachytherapy 03/14/95 Irvine Medical Irradiation of wrong part Misadministration Center, of the body. Irvine, CA AS 95-3 Overexposure of 04/06/95 Gwinnett Medical Overexposure of personnel PersonnelInvolved Center, from mistake made in in Brachytherapy Lawrenceville, GA handling a radioactive source. Treatment AS 95-4 Brachytherapy 07/28/94 Southwest Texas Overexposure of patients Misadministration Methodist Hospital, was due to administering San Antonio, TX radiation from the wrong source. AS 95-5 Importation of a 12/20/94 Omnitron At least 32 people were Package Having International, Inc. exposed to high radiation Excessive External Edgerly, LA because package contained Radiation into the radioactive material which the United States was not secured in a shielded ! from Republic of position. l Korea i
74 Table 3.1994 Accident Sequence Precursors Plant LER No. Date CCDP Description At Power Precursors Involving an Initiator River Bend 458/94-023 09/08/94 1.8x10-5 Scram, Main 'Ibrbine-Generator Fails to Trip, Reactor Core Isolation Cooling and Control Rod Drive Systems Unavailable. Calvert Cliffs 2 318/94-001 01/12/94 1.3x10-5 Trip, Loss of 13.8 kV Bus, and Short Term Saltwater Cooling System Unavailable At Power Precursors Involving Equipment Unavailabilities Haddam Neck 213/94-004, 02/16/94 1.4x10-4 Power-Operated Relief Valves and
-005,007, Vital 480 Vac Bus Degraded
-013, & IR 213/94-03 Zion 2 304/94-002 03/07/94 2.3x10-5 Unavailability of'Ibrbine-Driven Auxiliary Feedwater Pump and Emergency Diesel Generator Point Beach 1,2 266/94-002 02/08/94 1.2x10-5 Both Diesel Generators Inoperable Dresden 2 237/94-018 06/08/94 6.1x104 Motor Control Center Trips Due to Improper Breaker Settings Dresden 2 237/94-021 08/04/94 3.1x104 Long-Term Unavailability of High Pressure Coolant Injection
'Ibrkey Point 3,4 250/94-005 11/03/94 1.8x104 Load Sequencers Periodically Inoperable Shutdown Precursors Involving an Initiator Wolf Creek IR 482/ 09/17/94 3.0x10-3 Reactor Coolant System Blows Down to 94-018 Refueling Water Storage Tank during Hot Shutdown Note: TR number following a plant name denotes a particular unit at the site. Where a precursor affects more than one unit, there will be multiple numbers following the name. For example, Point Beach 1,2 is a ;
precursor affecting both Unit 1 and Unit 2. l l l
I 75 The Wolf Creek reactor coolant system blowdown HPCI SYSTEM PERFORMANCE event is the first precursor with a CCDP in the 10-3 range since the 1991 Shearon Harris high This study addressed the performance of the high pressure injection relief valve failure. The next pressure injection (HPCI) system at the 23 previous precursor with a CCDP in the 10-3 range operating boiling-water reactors (BWRs) which occurred in 1986. The results of the Wolf Licek have a dedicated HPCI system. Notable findings analysis were strongly influenced by uncertainty in include the following: i l assumptions about (1) human reliability, (2) the ability of the operators to recover ECCS systems e The overall HPCI unreliability was given the effort involved and the relatively short determined to be just over 0.05, including time available, and (3) the viability of the " reflux" credit for operator recovery. The unplanned cooling method, in which steam from a boiling demand and failure rates have steadily core may be condensed in the steam generator decreased while the overall unreliability has tubes with the condensate draining back to the remained fairly constant (see the following 3 reactor. There was also significant uncertainty figure of HPCI system trends). associated with the thermal-hydraulic behavior of the reactor coolant system under these conditions.
- The dominant contributors to HPCI As a result, there is large uncertainty in the unreliability were failure to run and estimated CCDP. maintenance out of service. The failu es to j run were not recoverable by simple operator actions.
An analysis of the 1994 ASP results shows that two important trends continued. First, conditions e The failures to start were recoverable with a or equipment unavailabilities are producing an value of 0.08 before consideration of ecovery, , ever greater share of the precursors as compared but 0.007 after recovery. to initiating events. There were only two precursors involving initiating events at power in
- The nature of the failures experienced during 1994 (down from eight in 1993), while there were actual demands and full flow tests differed somewhat from those discovered during six due to conditions or unavailabilities (versus eight in 1993). Second, electrical systems and monthly surveillance tests, engineering and components are involved in a significant fraction design reviews, and routine inspections.
of the precursors. In 1994, six of the nine e The observed unreliability for initial HPCI precursors involved electrical problems, although , none involved a total loss of offsite power. For the system injection is generally comparable with the values used in PRAs and IPEs. However, previous four years (1990-1993), about 60% of the there were ten plants for which the PRA/IPE precursors involved electrical problems. See the following two figures showing Annual Industry mean values were outside the uncertainty Averages of events and CCDP results from the bounds of the means computed from Operating experience. ASP program.
- While some specific component age-related failures were identified, no correlation was found between the low power license date System Reliability Studies and either the plant-specific annual failure rate or the plant-specific unreliability.
The first two studies in a series of reliability and risk analysis reports were completed and issued in 1995 and early 1996. The purpose of the studies EMERGENCY DIESEL GENERATOR was to use operational data to determine the STUDY reliability of the risk significant systems in U.S. commercial reactors. The data are obtained from The performance of the emergency diesel Licensee Event Reports (LERs). special reports, generator (EDG) trains was evaluated using the and monthly operating experience reports. The same techniques employed in the HPCI study. study period covered 1987 through 1993. Because inconsistences exist in the available i
76 l Annual Industry Averages Automatic Reactor Scrams While Critical Safety System Actuations y f EJmh. n 985 1987 1989 199t sioniricani events 1993 1 d999lhmim , 989 1987 1989 1991 sareiy sy.iem raiiures 1993 1999 e id-j' g3- . j,_ j 2- 7
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79 information between plants reporting under e The nature of the failures experienced during Regulatory Guide 1.108 (RG-1.108) and those that actual demands by the plants reporting per do not, this study focused primarily on the RG-1.108 differed somewhat from those RG-1.108 plants, with limited analyses and discovered during monthly surveillance tests, i comparisons for non-RG-1.108 plants. Notable engineering and design reviews, and routine findings include the following: inspections. o The mean unreliability including recovery was Upcoming reports in this series include the 0.044 for the population of plants reporting isolation condenser, reactor core isolation cooling, under RG-1.108. The overall unreliability and high pressure core spray systems at BWRs, remained fairly constant over the 7 year study and the auxiliary / emergency feedwater systems at period, even though the rates of unplanned PWRs. Planned future studies include the low demands and failures were steadily pressure injection systems at both BWRs and decreasing (see the following figure of EDG PWRs. Simplified models of the various reactor train trends). protection systems for both PWRs and BWRs are also being developed to estimate their reliability , o Failures to start and mam. tenance out of based on recent actual operating experience, service (MOOS) while at power were the dominant contributors to the EDG train unreliability for the plants reporting under RG-1.108, with the MOOS contribution accounting for 70 percent of the unreliability. INCIDENT RESPONSE PROGRAM The failures to start were not easily recoverable by simple operator actions. o The mean failure to start unreliability, Operations Center including recovery, was 0.01 and the mean failure to run unreliability was 0.004. The NRC maintains an Operations Center in However, the MOOS unreliability observed Rockville, Maryland, which is continuously staffed was four times higher than the value by a Headquarters Operations officer, who is a originally calculated in support of the station reactor systems specialist trained to receive, evaluate, and respond to all types of events. The blackout rule (0.030 versus 0.007). Operations Center provides the focal point for o No common cause failures of multiple EDG NRC communications with Commission licensees, trains were observed during the unplanned State agencies, and other Federal agencies demands reported by the RG-1.108 plants. In regarding the events that occur in the commercial the larger population of test demands, some nuclear sector. The center features a state-of-the-common cause failure events did occur. art Operations Center Information Management < System which integrates voice, video, and data o The observed mean unreliability was subsystems to provide timely and effective generally comparable with the values used in information flow. In FY 95, this system received , PRA/IPEs with mission times under 8 hours. the 1994 Federal Technology Leadership Award The results indicate that PRA/IPEs may be for outstanding achievement in making overestimating the contribution of failure to government more effective through the use of run events for longer mission times. information systems. o No correlation was found between the low NRC licensees make telephone reports to the power license date and the plant-specific Operations Center of events or conditions that are unreliability for the plants reporting per required to be reported by 10 CFR 50.72, RG-1.108. However, the plants licensed from "Immediate notification requirements for 1980 to 1990 did experience higher failure operating nuclear power reactors." A few of these rates than the plants licensed earlier, with events meet the criteria for categorization into one most of these failures occurring during the of four emergency classes, as follows (in order of first 2 years of operation. increasing severity): Unusual Event, Alert, Site
oc o EDG TRA N TRENDS g 0.350 - 0.800 - g -- 0.700 o 0.300 o , ...' m m 0 250 -
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81 Area Emergency, or General Emergency. An planning exercise with a uranium fuel fabrication Unusual Event signifies a potential degradation of facility were also conducted in 1%5. The following plant safety with no immediate threat to public two photographs show the executive and reactor health, while an Alert indicates substantial actual safety teams as they review and evaluate plant or potential degradation of plant safety. A Site status and licensee actions to determine the Area Emergency or General Emergency indicates appropriate NRC response, including the i a major failure of one or more systems required appropriate guidance to offer State and local for public safety or an event with the potential for governments. a major offsite radiological release. Actions taken by the NRC Headquarters State Outreach Operations Officer in response to notifications of events ranged from computer and log entries During 1995, AEOD conducted a State Outreach followed by appropriate notifications, to Program designed to increase and improve the establishing emergency conference calls among NRC's interaction with States during events and the licensee and senior NRC regional and exercises. It included briefings of State officials on headquarters staff. For four of the more the NRC Emergency Response Program, the significant events in 1995, these conference calls Emergency Response Data System (ERDS), resulted in the employment of the Operations NRC/ State liaison during an emergency, and Center to monitor the progression of the event. financial assistance. The program also included These four events were an ammonia release at a eight exercises with 11 states, consistent with the
- chemical facility located in proximity to the goal to exercise with each State on a 3-year cycle.
Waterford Steam Electric Generating Station, In addition, AEOD organized and conducted
- high radiation levels in containment due to over- 1-1/2 day State Outreach Program training retraction of a traversing incore probe at LaSalle sessions in each NRC regional office, which County Station, and Hurricanes Erin and Opal. included Federal organizations, licensees, and two representatives from each State with nuclear power plants. During 1995, the NRC negotiated an ERDS Memorandum of Understanding Emergency Exercises (MOU) with the State of Delaware, and the State f Wrniont applied for an ERDS MOU. ERDS is Emergency exercises are held periodically to ,
a real time data system designed to provide direct ensure that response organizations of the NRC, , the licensees, the States, and other Federal transmission of selected plant information from hcensecs' onsite computers to the NRC agencies are proficient in dealing with each type of emergency. In 1995 the NRC headquarters and Operations Center. These Memoranda of Understandmg will enable States to receive ERDS regional offices participated in full scale data during events at nuclear power plants. emergency preparedness exercises with four nuclear power plant sites. The NRC's main role in these exercises is to assist the licensee as requested, review the protective action Coordination with Other Federal recommendations licensees make to state and Agencies local authorities, and facilitate communications between licensees and these authorities. These The NRC continued to participate in the effort to exercises typically include a postulated accident revise the Federal Radiological Emergency scenario that goes well beyond the plant's design Response Plan (FRERP). The FRERP, which is basis and that results in the release of some the plan that outlines the Federal response to radioactivity outside the plant's boundary. During radiological emergencies, has been undergoing a j one exercise a simulated news media information major revision by seventeen Federal agencies ! center was established at the headquarters offices during the last two years. The NRC also i and senior NRC managers responded to questions participated in the effort to revise the Federal , regarding the event. Three limited participation Response Plan (FRP), which is the master plan ! cmergency preparedness exercises with power used by the Federal government to respond to any reactor licensees and a table top emergency emergency in suppoit of the affected States. The
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83 l FRP and the FRERP together outline the Federal investigations of significant operational events are response to a radiological emergency in a timely, thorough, and systematic. The llP includes comprehensive manner. In addition, NRC investigations of events involving reactors and representatives participated in meetings and nuclear materials licensed by the NRC. The i working groups called for by these plans, such as program is structured so that the NRC responds the National Response Team, the Catastrophic to an operational event according to its safety Disaster Response Group, and the Federal significance. For an event of potentially major Radiological Preparedness Coordinating safety significance, the Executive Director for Committee. Operations (EDO) establishes an Incident Investigation Team (IIT) to investigate the event: for an event of less safety significance, the Gaseous Diffusion Process Activities responsible NRC Regional Administrator may establish an Augmented Inspection Team (AIT) to The President signed li.R. 776, the " Energy Policy investigate the event. Both IITs and AITs are Act of 1992," into law on October 24,1992, tasked to determine the circumstances and causes Among other things, the Act amended the Atomic of the event and to assess its safety significance so Energy Act of 1954 to establish a new government that appropriate followup actions can be taken. corporation, the United States Enrichment While AEOD is responsible for administration of Corporation (USEC) for the purpose of managing the llP, NRR is responsible for maintaining the j and operatmg the uramum ennchment plants procedures for Arrs. owned and previously operated by the Department of Energy (DOE). These enrichment In FY 95, there were no events that were judged plants are the Portsmouth Gaseous Diffusion to have a level of safety significance sufficiently Plant at Piketon, Ohio, and the Paducah Gaseous high to warrant an IIT investigation. There were, ! Diffusion Plant at Paducah, Kentucky.The Act however, three AITs established to investigate the I further directed the NRC to establish a process following significant incidents: (1) the operation of whereby these two plants will be certified annually a bypass valve in the Reactor Water Cleanup by the NRC for compliance with NRC standards. System contrary to a procedural caution at These standards, when implemented, will include Washington Nuclear Project No. 2, (2) a those for emergency response to events at the switchgear fire and loss-of-offsite power at plants. Waterford Steam Electric Generating Station, and (3) internal contamination of 27 individuals with During 1995, in preparation for the certification phosphorus-32 at the National Institutes of Health process for emergency response, AEOD in Bethesda, Maryland. participated in general gaseous diffusion process training and a round-table discussion on potential events and emergency response at the gaseous diffusion facilities. Participants included indi- DIAGNOSTIC EVALUATION viduals from the Portsmouth and Paducah Plants, PROGRAM the USEC, DOE, and the NRC. Representatives from the USEC, DOE, and both the Portsmouth AEOD manages the NRC's Diagnostic Evaluation and Paducah Plants observed a drillin the Program (DEP) to provide an independent Operations Center during October 1995. During assessment of licensee performance at selected the drill, gaseous diffusion process experts served reactor facilities. A diagnostic evaluation on the NRC's Protective Measures Team. assessment augments information provided by the Systematic Assessment of Licensee Performance program, the Performance Indicator program, and the inspection program implemented by NRC INCIDENT INVESTIGATION headquarters and regional offices. PROGRAM . A Diagnostic Evaluation Team consists of a core of experienced AEOD evaluators supplemented The Incident Investigation Program (IIP) is by expert technical staff members from administered by AEOD to ensure that NRC headquarters and regional offices, as well as
84 contractors, if appropriate. The team managers Installations'(CSNI) Principal Working Group 1 and members will not have had recent significant (PWG-1), " Operating Experience and Human involvement in the licensing, inspection, or Factors." AEOD is also a participant in the enforcement process at the selected facility. The Expert Group on Nuclear Emergency Matters, a onsite evaluation process involves observations of group established by the Committee for Radiation plant and corporate activities, in-depth technical Protection and Public Health in 1989 to improve reviews, employee interviews, equipment the quality of national and international nuclear walkdown inspections, and programmatic reviews emergency arrangements. in a number of functional areas important to safety. Areas evaluated generally include maintenance, surveillance and testing, management effectiveness, operations, LIMITED PARTICIPATION IN THE l engineering, and quality programs. INTERNATIONAL NUCLEAR EVENT l The EDO makes the decision to conduct a SCALE Diagnostic Evaluation and appoints the Diagnostic Evaluation Team. The EDO did not Since December 1992, the NRC has participated authorize any Diagnostic Evaluations in FY 95. In in a limited manner in the International Nuclear FY 97 the DEP will be terminated and replaced Event Scale (INES). The INES is a ranking by the Integrated Performance Assessment system that is intended to be used to promptly Program of NRR. and consistently communicate to the public the i safety significance of reported events at nuclear installations worldwide. It was designed by an l intemational gmup of experts convened jointly by INTERNATIONAL SUPPORT the International Atomic Energy Agency and the l ACTIVITIES Nuclear Energy Agency. The international scale is currently in use in 54 countries throughout the The Incident Reporting System is a cooperative w rld. The NRC limits its participation in the
- program of the Organization for Economic INES to ratmg only events at nuclear power Cooperation and Development's Nuclear Energy Pl ants that are classified as an Alert or higher on Agency (OECD/NEA) and the International the emergency response scale used in the ' United Atomic Energy Agency (IAEA) of the United States. After a trial period of more than two Nations. The U.S. and 13 other countries are y rs, We NK decided to continue mdefinitely its members of the NEA. The NEA member II"ited part,cipation i m the INES. These classifi-c t. ions for FY 95 are given in Table 4.
countries and the IAEA member countries submit reports of operational experience that may be applicable to other nuclear power plants. This broadens the operational experience database t include all nuclear power programs except that of LISBON INITIATIVE ACTIVITIES Taiwan. The reports are maintained in a database managed by the NRC at the Oak Ridge National As part of the Lisbon Initiative, AEOD is . Laboratory and distributed to all member states, assisting Russia and Ukraine in the development AEOD reviews and disseminates within the NRC of their own capabilities to respond to nuclear reports of selected foreign reactor events of power plant emergencies. AEOD is helping the particular interest to the staff regulating the U.S. regulatory authorities in each country to establish program. It identifies significant foreign events reliable emergency communications with each that could be applicable to U.S. plants and site, to prepare response plans and procedures, provides reports of these events to interested and to provide equipment for a basic but parties within the NRC. functional emergency response center. The staff will also train Russian and Ukrainian personnel to In addition, AEOD is the principal U.S. technical prepare, conduct, and evaluate exercises so that representative on reactor operating experience to they will be able to test and improve their the NEA's Committee on the Safety of Nuclear capabilities. When these tasks are completed,
85 Table 4. U.S. Events Reported on the International Scale 1995 Plant Name Event INES U.S. Emergency Event Qpe) Date Level
- Classification Description Robinson 2 2/13/95 Out of Alert Release of a toxic gas in the (PWR) scale auxiliary building l Waterford 3 3/25/95 Out of Alert Ammonia release at a nearby (PWR) scale chemical facility Robinson 2 6/20/95 Below Alert Reactor coolant system leakage in ex- l (PWR) scale cess of 50 gallons per minute due to a charging pump relief valve failure Waterford 3 7/20/95 Below Alert Ammonia release at a nearby (PWR) scale chemical facility Salem 1 10/04/95 Below Alert Loss of control room annunciators (PWR) scale for greater than 15 minutes (NOTE:
The Alert was declared on 10/5/95, after the initial event notification.) LaSalle 10/31/95 1 Alert 'ligh radiation levels in containment (BWR) due to over-retraction of a traversing incore probe to an unshielded i location CEvents are classified on a scale of seven levels. The lower levels (1-3) are termed incidents and the upper levels (4-7) accidents. Events which have no safety significance are classified as below scale / level 0 and are termed deviations. Events which have no safety relevance are termed "out of scale." i cach country will have an emergency operations exchange between countries of the former Soviet center at regulatory headquarters in Moscow and Union with similar reactors. Four information Kiev, good voice and data communications with exchange sessions and meetings have taken place. each nuclear power plant, emergency plans and Training was provided by Idaho National procedures, essential technical tools and Engineering Laboratory under contract to the equipment, and agreements for coordination with NRC in September and October 1995 in other response organizations. They will also have probabilistic risk assessment of operating events the skills, handbooks, and experience needed to and NRC performance indicators. Additional maintain, exercise, and continually improve their training in equipment and human performance . response capabilities after U.S. assistance ends. reliability is planned. This effort is expected to be completed in 1997. The work is being coordinated with related assistance provided through other agencies of the United States Government, other governments, AEOD is also helping Russia and Ukraine and international organizations. establish a comprehensive system for training and i qualification of technical personnel. For Russia 1 AEOD is also assisting Ukraine in establishing an this also includes assistance in creating a incident reporting and operating experience functional training center. In addition, AEOD will feedback system. This system includes strategies provide analytical simulators to Russia and for data collection, events analysis and evaluation, Ukraine for training of regulatory personnel, and regulatory response to events, and experience will provide training of the Russian and Ukrainian j feedback to nuclear plants as well as information staff who will use and maintain the simulators. l l
86 TECIINICAL TRAINING technology course series to complement that obtained in the PRA curriculum and to give NRC AEOD manages and conducts the NRC technical staff insights, practical discussion, and exercises training program at the Technical Training Center regardm, g PRA use by bcensees m managing risk in Chattanooga, Tennessee. AEOD coordinates at the plants. In addition, a risk management with NRC headquarters offices and the regions in m dule is under development for the techmcal policy development and implementation of formal issues section of the advanced technology courses. staff qualification and training programs. New New BWR/4 course matenals were developed to courses are developed and existing courses are support integration of the BWR/4 simulator modified to meet new or changing needs Uormerly the Shoreham plant simulator), and the identified by the NRC line organization. AEOD Westinghouse technology course matenals,are l staff provide technical assistance in areas of bemg revised to support the recently acquired ' expertise and provide advice and limited technical Jr j n sunulator. Simulator refresher training was ; training assistance to foreign regulatory incre sed m all reactor technology areas to j counterparts. support staff requalification. J Reactor technology courses are provided for each A variety of other stand-alone reactor technology ! of the reactor vendor designs: General Electric courses are aumble, including new, three week cross-training courses in the CE and B&W (GE), Westinghouse, Combustion Engmeermg technologies. These courses were designed to meet (CE), and Babcock and Wilcox (B&W). These the needs of experienced personnel who have courses melude both classroom instruction and already completed a PWR full course series and trammg on full-scope simulators for each vendor design. only need training in the differences between PWR vendor technologies. These courses are ! Specialized technical training courses are relatively fast-paced with a high degree of reliance provided in probabilistic risk assessment, n existmg knowledge and expenence. The J engineering support, radiation protection, fuel Nuclear Engmeenng Workstation Simulator j cycle technology, security and safeguards, and (NEWS)was used to develop mteractive plant ' regulatory skills. Specialized technical training is system d,agrams i for the Westinghouse, GE, and provided through customized courses, B&W technologies. Mse diagrams are used in coordination of training opportunities in courses re ctor technology courses to enhance student presented by other Government agencies, and understanding of system dynamics and interfaces. identification of appropriate commercially available courses for NRC personnel. Specialized Technical 'IYaining During FY 95 AEOD provided 66 courses in During FY 95 many new specialized technical i reactor technology and 90 specialized technical training c,ourses were developed. In the training courses requiring 178 course-weeks and Engmeenng Support trammg program, a new 63,759 instructional hours. Most of this technical Welding and Nondestructive Examination (NDE) training was provided in support of qualification Overview course provides a general familiarity programs for NRC technical staff, although the with metallurgy, welding, and NDE technologies. reactor technology courses included a significant In addition, new commercially available courses number of foreign regulatory personnel. have been added to support training in digital mstrumentation and controls. Reactor Technology 'IYaining Four new courses were added to the PRA training program curriculum: the Advanced Integrated The core of the reactor technology training Reliability and Risk Analysis System (IRRAS) program is an integrated series of courses course, which covers advanced features of the consisting of a three-week systems course, a IRRAS software, the PRA Insights Into an IPE two week advanced course, and two weeks of course, the Systems Modeling Techniques course reactor simulator training (including one week of and the Risk Assessment in Event Evaluation emergency operating procedures [EOPs]). PRA course. In addition, a special seminar on Poisson information has been added to these reactor and Binomial Faihtre data was developed and
- 87 presented in December 1994. Material from this AEOD Director serves as the CRGR Chairman, seminar is being added to other courses, and the AEOD staff provides support for all of the Committee's activities. In 1995, one new In the Radiation Protection training program, member from headquarters was appointed to the i three new courses were completed and presented CRGR.
during FY 95. The Health Physics Technology Overview course familiarizes NRC technical The members of the CRGR determine whether managers and supervisors with important proposed new generic requirements have radiation protection issues and hazards sufficient merit in terms of safety and are justified encountered in various areas within the nuclear in terms of cost (where appropriate) before industry. The Introductory IIcalth Physics course reaching a consensus recommendation about each provides a basic understanding of health physics issue considered. A CRGR member expresses an and radiation protection principles. The Health individual professional opinion about each issue. Physics Topical Review course emphasizes new Each independent CRGR recommendation is modalities in teletherapy and brachytherapy. In given to the EDO for consideration. addition to these courses, AEOD, at the request of NMSS, coordinated the development of a new The CRGR held 12 meetings in FY 95 in which 21 Radiological Surveys in Support of issues were reviewed. These meetings concerned Decommissioning course. Generic Letters, Bulletins, Regulatory Guides, proposed and final rules, and discussions with l In the Regulatory Skills training program during NRC senior managers and staff relating to power FY 95, at the request of the Office of the reactor and nuclear materials concerns. Inspector General (OIG), AEOD developed and < conducted two courses for OIG and Office of l Investigations personnel and assumed ! responsibility for coordinating the Inspection Procedures and Licensmg Practices and OFFICE OF Procedures courses. In addition, reactor and nuclear materials versions of the Inspectmg for INVESTIGATIONS Performance course were made available, and a Root Cause/ Incident Investigation Refresher The Office of Investigations (01) conducts Workshop was developed. investigations of alleged wrongdoing by individuals or organizations other than employees In FY 95, AEOD assumed responsibility for of the Nuclear Regulatory Commission (NRC) or several new areas of training. These included NRC contractors. (Allegations involving NRC training in fuel cycle technology, requested by employees or NRC contractors come under the NMSS, and training of Agreement State purview of the NRC Office of the Inspector Personnel. In addition, work continued on the General). Thus, OI is concerned with the activities development of a training program in digital of NRC licensees, applicants for licenses, licensee instrumentation and control. contractors and vendors. In fiscal year 1995 (FY 95), 218 investigations were opened and 259 insestigations were closed. COMMITTEE TO REVIEW GENERIC These investigations resulted in nine civil , penalties totalling approximately $260,000 (as of ; REQUIREMENTS November 1,1995) and in other enforcement actions.
'Ihe Committee to Review Generic Requirements (CRGR) reviews all generic requirements In FY 95, the OI provided continued support to l proposed by the NRC staff that involve one or the Department of Justice and other Federal more classes of power reactors. The CRGR agencies in prosecuting criminal violations that consists of senior managers from various were substantiated during OI investigations. Of headquarters program offices and, on a rotational the 259 investigations closed in FY 95,42 cases basis, from one of the NRC regional offices. The were referred to the Department of Justice (DOJ)
1 88 for prosecutorial review. During FY 95,01 was referred to the U.S. Attorney's office, supported 11 Federal grand juries, and OI Indianapolis, Indiana, for prosecution. investigations resulted in 5 indictments,3 convictions, and 3 guilty pleas in Federal courts. An investigation into the activities at Palo Verde Nuclear Generating Station (PVNGS) determined The following sections contain examples of that a former contract Instrumentation and significant 01 investigations on which the DOJ or Control (I&C) employee at PVNGS was the Office of Enforcement took action during discriminated against by not being rehired for a ; FY 95: second outage because he reported safety i concerns to the NRC. On hiay 30,1995, a Federal grand jury in Phoenix, Arizona, indicted a former I&C Supervisor at PVNGS, on one count of ! DEPARTMEN,f OF JUS,FICE, violating Title 42 U.S.C. 2273 (10 CFR 50.7). The former supervisor subsequently pleaded guilty and ACTIONS on August 7,1995, was sentenced in Federal I District Court, in Phoenix, Arizona, to 1 year of I An extensive investigation into the activities of the probation,75 hours of community service, a $50 l l fine, and court costs for " discrimination against radiatjon safety officer (RSO) at Logan General an employee of a nuclear power plant." Hospital, Logan, West Virgima, culmmated m a guilty plea in U.S. District Court. The RSO < falsified both training records of lab employees and required radiation survey records. He was ENFORCEMENT ACTIONS sentenced to probation for 2 years for providing false information to the NRC. An investigation involving an Agreement State licensee, Quality Inspection Services, Inc. (QIS), A joint investigation of National Circuits Caribe, disclosed that OlS had performed work in Inc., by the Environmental Protection Agency Pennsylvania without NRC authorization for an (EPA), the Federal Bureau of Investigation (FBI), extended period, and continued to do so after and OI resulted in an indictment in Puerto Rico. being notified by the State of New York, This investigation required extensive use of the Department of Labor, that NRC authorization Federal grand jury in Puerto Rico and resulted in was required. The investigation also disclosed that a two-count indictment of the president of a QIS quality control field supervisor deliberately National Circuits. The president was indicted on provided false information to an NRC inspector. October 4,1995, for abandoning a gauging device On the basis of the investigation, on June 28, containing byproduct material at National 1995, the NRC assessed a $13,000 civil penalty Circuits' facility in Fajardo, Puerto Rico. The against QlS and issued a Notice of Violation to indictment also charged the president with the individual. improper storage of hazardous wastes, an EPA violation. He was arrested by the FBI on An investigation involving Carlisle Hospital October 11,1995. disclosed that the licensee had knowingly permitted unauthorized physicians to utilize its An investigation of Ball hiemorial Hospital cobalt-60 teletherapy equipment for the treatment (Bhf H), hiuncic, Indiana, revealed that two of patients without the required oversight. supervisory nuclear medicine technologist (NhiTs) Specifically, a hospital vice president, the had administered greater than-prescribed dosages radiation safety officcr, and the Radiation Safety of radiopharmaceuticals to Bh1H patients and Committee Chairman knowingly condoned the had also instructed subordinate NhiTs to do so. unauthorized activity. The investigation further Patients' records of radiopharmaceutical dosages disclosed that the vice president had made false were falsified to create the appearance that the statements to an NRC Region I representative correct prescription had been administered to the concerning the unauthorized use of the patients. Through investigation, the OI teletherapy equipment. On the basis of the determined that these actions had begun in 1988 investigation, on August 7,1995, the NRC and continued until June 1993. This investigation assessed a $5,000 civil penalty against the licensee,
89 having previously issued Notices of Violation to Blackhawk's NRC license had expired. The two of the individuals. president also made a false statement to an NRC inspector by telling him that she had not used the I
. nuclear gauges. On August 3.1995, the NRC I As a result of the m.vestigation referenced issued an order to Blackhawk's president previously regarding the Logan General Hospital prohibiting involvement in NRC-licensed activities radiat,on i safety officer, an $8,000 civil penalty was and requiring certain notification to NRC. The assessed and paid, order prohibited her from becoming involved in NRC-licensed activities for 1 year and, for 1 yeat An investigation into activities at Washington after the first year, required that she notify the Nuclear Project, Unit 2 (WNP-2), determined that NRC within 20 days of becoming involved in on April 9,1995, during plant heatup and startup, NRC-licensed activities, a reactor water cleanup system (RWCU) valve was improperly manipulated by a control room supervisor in violation of plant procedures. The An investigation into activities at Atlas Uranium mvestigation concluded that the control room Mill determined that Atlas' radiation control supervisor did not deliberately violate plant coordinator deliberately failed to conduct procedures when he imtially opened the RWCU
, complete and accurate surveys and obtain wipe valve, but did deliberately violate procedures after tcst results to ensure that material contaminated discussmg them with a reactor operator and then by radiation above the NRC release criteria was failing to close the RWCU valve or direct that it not released from the Atlas mill site. As a result be closed. On August 17,199p, on the basis of the
, of these actions, radiation-contaminated scrap Of mvestigation and special mspections, . metal and equipment were not properly identified conducted by the NRC, the NRC issued a Notice
, and were subsequently released from the site as of Violation and assessed a civil penalty of uncontaminated materials. On June 15,1995, the
$50,000. The control room supervisor was NRC issued a Notice of Violation and assessed a terminated by WNP-2. civil penalty of $5,000.
An investigation into activities at Mattingly Testing Services, Inc., determined that Mattingly's An investigation into activities at Western owner and/or other employees deliberately Industrial X-Ray, Inc. (WIX), determined that (1) failed to amend its NRC h,eense to reflect a (1) a WIX radiographer deliberately allowed a work and storage locaon in Billings, Montana; radiographer's assistant to perform radiographic (2) failed to conduct required field audits of operations without proper supervision, (2) the radiography personnel; (3) allowed a WIX president and Radiation Safety Officer radiographer's assistant to work without proper
, , deliberately failed to conduct an evaluation of a traming and/or supervision; (4) failed to post high potential overexposure incident, and (3) a radiation areas;(5) failed to ensure the radiographer and a radiographer's assistant radiographic device was k>cked after each deliberately prepared and submitted false reports <
exposure; and (6) failed to perform a required - about the potential overexposure incident to the survey. On May 5,1995, the NRC issued a Notice licensee. From this investigation the OI further of Violation and assessed a civil penalty of determined that the licensee deliberately failed to
$15,500. Ihe NRC also issued an Order Modify.mg pr vide calibrated alarm ratemeters to a License requiring Mattingly to retain the services radiograpner and a radiographer's assistant, of an independent consultant to assess the ,
which was a recurrmg violation. On the basis of licensee's radiation safety program and coduct semiannual audits for the next 2 vears, the investigation, on September 27,1994, the NRC issued an order revok,mg the WIX license, and an order prohibiting involvement in NRC-licensed An investigation into activities at Blackhawk activities for 5 years to the president of WIX. On Engineering determined that the President of October 31,1994, the NRC issued an order Blackhawk deliberately used gauges containing prohibiting involvement in NRC-licensed activities NRC-licensed material although she knew for 1 year to the radiographer.
90 - 1 OFFICE OF e Emphasize the importance of identifying , problems before events occur, and of taking i ENFORCEMENT prompt, comprehensive corrective action when problems are identified. The Commission has developed an enforcement e Direct agency attention at licensees with program and Enforcement Policy to support the multiple enforcement actions in a relatively NRC's overall safety mission in protecting the short penod. public and the environment. The NRC Office of e Focus on current performance of licensees. Enforcement is responsible for managing the Commission's enforcement program. The office is In addition, the review team found that the subject to oversight by tne Deputy Executive
. process for assessing civil penalties could be Director for Nuclear Reactor Regulation, Regional Operat,ons, i and Research for enforcement actions simplified to improve the predictability of related to reactor licensees, and by the Deputy decision-making and obtain better consistency between regions.
Executive Director for Nuclear Matenals Safety, Safeguards and Operations Support for The major changes to the Enforcement Policy enforcement matters for enforcement actions include-involving all other licensees.
. Clarified purpose.
On June 30,1995, the Commission published a . . e Eh. .mmation of Severity Level V revised Enforcement Policy in the Fedemi Register categorization. that became effective on that date (60 FR 34381). The Commission also announced that the e Enforcement Policy was bem, g removed from the Modified threshold and criteria for renamed Code of Federal Regulations where it has "predecisional" enforcement conferences. traditionally resided as Appendix C to 10 CFR e Continuation of a trial program for opening Part 2, because it is a policy statement and not a approximately 25 percent of conferences to regulation (60 FR 34380). To provide widespread public observation. dissemination, the Enforcement Policy is now published as NUREG-1600, " General Statement e Elimination of responses to certain Notices of of Policy and Procedure for NRC Enforcement Violation. Actions."
- Revision of Base Civil Penalty Tables.
The changes that are reflected in this revised e Streamlined civil penalty assessment process. Enforcement Pohey result from the efforts of a review team established in 1994 to assess the e Preservation of the ability to exercise NRC's enforcement program. De team. , discretion. conducted a thorough program review, meludm.g . I solicitation of comments.from within the NRC, he Commission expects that the changes to the from other Federal agencies, members of industry, ! Enforcement Policy should result in an increase in and the public. In its report (NUREG-1525, the protection of the public health and safety by
" Assessment of the NRC Enforcement Program," better emphasizing the prevention, detection, and April 5,1995), the review team concluded that the correction of violations before events occur with existing NRC enforcement program, as impact on the public. The Commission intends to implemented, is appropriately directed toward review the Enforcement Policy after it has been in j supporting the agency's overall safety mission. effect for about 2 years. In that regard, it is ex- 1 However, the review team found that the existing pected that in about 6 months prior to that time, enforcement program at times provided mixed an opportunity will be provided to receive public regulatory messages to licensees, and room for comments on the implementation of this Policy.
improvement existed in the Enforcement Policy. The review suggested that the program's focus Appendix 7 provides a listing and brief summary should be clarified to- of the civil penalties proposed, imposed, and/or
91 paid during fiscal year 1995; and a listing and requirement and how it was violated, and brief summary of the 22 orders issued during formalizes a violation pursuant to 10 CFR 2.201. fiscal year 1995. Recognizing that enforcement A civil penalty is a monetary fine issued under actions can sometimes span several fiscal years, authority of section 234 of the Atomic Energy there were a total of 63 civil penalties acted upon Act. That section provides for penalties of up to in fiscal year 1995 for a total of $2,838,450 in $100,000 per violation per day. NOVs and civil proposed penalties. Of these,56 were proposed in penalties are issued based on violations. Orders fiscal year 1995 for a total of $2,263,950. Fourteen may be issued for violations, or in the absence of cases were imposed for a total of $620,750, with 11 a violation, because of a public health or safety of the cases imposed in fiscal year 1995 for a total issue. of $615,250. Forty-seven cases were paid (including the total amount for those civil The Commission's order issuing authority is penalties being paid over time) for a total of broad and extends to any area of licensed activity
$2,265,949. A total of 76 cases were issued as that affects the public health and safety. Orders 4 escalated enforcement actions without a civil modify, suspend, or revoke licenses or require penalty for reasons unique to each case. specific actions by licensees or individuals. As a result of a rulemaking in 1991, the Commission's In addition, an overview of the NRC's regulations now provide for issuing orders to enforcement program follows: individuals who are not themselves licensed.
The first step in the enforcement process is assessing the severity of the violation. Severity OVERVIEW OF NRC Levels range from Severity Level I, for the most significant violations, to Severity Leve1 IV for ENFORCEMENT PROGRAM those of more than mmor concern. M,mor i violations are not subject to formal enforcement 1 The Commission has developed an enforcement action. Severity levels may be increased for cases l program and Enforcement Policy to support the involving a group of violations with the same root NRC's overall safety mission in protecting the cause, repetitive violations, or willful violations. public and the environment. Consistent with that purpose, enforcement action should be used as a A predecisional enforcement conference is deterrent to emphasize the importance of normally conducted with a licensee before making compliance with regulatory requirements, and to an enforcement decision if escalated enforcement encourage prompt identification and prompt, action (i.e., Severity Level I, II, or III violations, comprehensive correction of violations. civil penalties or orders) appears to be warranted, and if the NRC concludes that it is necessary or Violations are identified through inspections and the licensee requests it. If the NRC concludes that investigations. All violations are subject to civil a coaference is not necessary, it will normally i enforcement action and may also be subject to provide a licensee with an opportunity to respond criminal prosecution. After an apparent violation to the apparent violations before making an is identified, it is assessed in accordance with the enforcement decision. The purpose of the Commission's Enforcement Policy. The Policy is conference is to obtain information that will assist published as NUREG-1600, " General Statement the NRC in determining the appropriate of Policy and Procedure for NRC Enforcement enforcement action, such as (1) a common Actions," to provide widespread dissemination. understanding of facts, root causes and missed Because it is a policy statement and not a opportunities associated with the apparent regulation, the Commission may deviate from this violations, (2) a common understanding of statement of policy and procedure as appropriate corrective action taken or planned, and (3) a under the circumstances of a particular case. common understanding of the significance of issues and the need for lasting comprehensive There are three primary enforcement sanctions corrective action. The decision to hold a available: Notices of Violation, civil penalties, and conference does not mean that the agency has orders. A Notice of Violation (NOV) summarizes determined that a violation has occurred or that the results of an inspection, identifies a enforcement action will be taken. In accordance
92 with the Enforcement Policy, conferences are given case, the outcome of the assessment process normally closed to the public. However, the for each violation or problem, absent the exercise Commission is continuing a trial program to allow of discretion, is limited to one of the following approximately one out of every four conferences three results: no civil penalty, a base civil penalty, to be open to public observation. or twice the base civil penalty. Civil penalties are considered for Severity Level If a civil penalty is to be proposed, a written Ill violations and are normally assessed for Notice of Violation and Proposed Imposition of Severity Level I and II violations and knowing and Civil Penalty is issued and the licensee has 30 conscious violations of the reporting requirements days to respond in writing, by either paying the of Section.206 of the Energy Reorganization Act. penalty or contesting it. The NRC considers the response, and if the penalty is contested, may The NRC imposes different levels of civil either mitigate the penalty or impose it by order. penalties based on a combination of the type of licensed activity, the type oflicensee, the severity If the civil penalty is to be imposed by order, the level of the violation, and (1) whether the licensee order is published in the Fedeml Register. has had any previous escalated enforcement Thereafter, the licensee may pay the civil penalty action (regardless of the activity area) during the or request a hearing. past 2 years or past two inspections, whichever is longer; (2) whether the licensee should be given In addition to civil penalties, orders may be used credit for actions related to identification; to modify, suspend, or revoke licenses. Orders ! (3) whether the licensee's corrective actions are that modify a license may require additional prompt and comprehensive; and (4) whether, in corrective actions, such as removing specified view of all the circumstances, the matter in individuals from licensed activities or requiring question requires the exercise of discretion. additional controls or outside audits. The NRC Although each of these decisional points may issues a press release with a proposed civil have several associated considerations for any penalty or order.
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$_ & k , . . J* k ,= A L; u w = a.w w w: = d LC b- ?i < al A $ 1 : it NUCLEAR MATERIALS REGULATION Together with the NRC's four regional offices, the e approximately 2100 materials licensee NRC Office of Nuclear hiaterial Safety and inspections Safeguards (NhfSS) regulates the safe use of nuclear materials. Materials regulation involves three broad programs: materials safety discussed in this chapter; fuel facility safety and safeguards, discussed in Chapter 5; and waste management activities, discussed in Chapter 6. STORAGE AND This chapter addresses licensing, certification, TRANSPORTATION inspection, and other regulatory activities concerned with materials safety. Specifically, thes:: , Regulatory activities related to materials storage activities regulate (1) storage of spent reactor fuel; and transportation of nuclear materials have (2) transportation issues associated with fuel and radioactive materials, and (3) production and use historically been conducted by the Division of Industrial and Medical Nuclear Safety (IMNS) of reactor-produced radioisotopes (byproduct within NMSS. In April 1995, however, the NRC material). established the Spent Fuel Project Office (SFPO), and transferred to it the duties of the former During fiscal year 1995 (FY 95), the NMSS Storage and Transportation Safety Branch. completed the following activities related to Creation of this new orgamzation and its charter nuclear materials regulation: are discussed later in this section. o nearly 90 reviews of transportation and spent fuel storage packages, and 6 route approvals for transporting special nuclear material and spent fuel INTERIM SPENT FUEL STORAGE o safety inspections of 7 transportation packaging and dry spent fuel storage system Under the Nuclear Waste Policy Act of 1982, suppliers, and observations of 3 Department licensed utilities are responsible for storing their of Energy (DOE) audits of multipurpose spent fuel until a Federal repository or centralized canister (MPC) contractors interim storage (CIS) facility is available. All utilities have either installed or are planning to o more than 4600 licensing actions on install high-density racks in their existing spent applications for new byproduct materials fuel pools. However, even with these licenses, as well as amendments and renewals modifications, pools are reaching capacity. To of existing licenses, and reviews of sealed provide for " full-core" reserve, many utilities are sources and devices constructing independent spent fuel storage
94 installations (ISFSis), which generally consist of a additional dual-purpose cask designs, the Vectra passive storage system using dry cask technology. h1P-187 and the HOLTEC International HI-STAR 100, are currently being reviewed..In Utilities have two options for licensing ISFSis-a addition to new licensing actions, the staff is site-specific license or a general license. At this currently reviewing amendments to existing time, six utilities have applied for and received certificates and safety analysis reports for site-specific licenses. The most recent ISFSI approved casks. license was issued to Northern States Power for Prairie Island, and fuel at this site was loaded into dry casks during summer 1995. CREATION OF SPENT FUEL A general license, issued to a 10 CFR Part 50 PROJECT OFFICE licensee, allows the storage of fuel in casks that l i have been reviewed and certified by the NRC before use. Such cask designs are given a In calendar year 1995, the Department of Energy Certificate of Compliance (CoC), and are listed in (DOE) stated its intent to submit a storage and Subpart K tc 10 CFR Part 72. At present, seven transportation system known as the hiultipurpose 4 I Canister (hf PC) to the NRC for certification and systems deugns hold CoCs. On1y one utility, . licensing as part of its high-level waste program. Consumus Power-Palisades, is currently storing fuel under the provisions of a general heense. The hiPC was envisioned as a key element in Four additional utilities are planmng to load DOE's solution for spent fuel storage, and would spent fuel into dry casks under a general licenses provide a standardized system for transporting m early 1996. spent fuel to a monitored retrievable storage (hf RS) facility. The hf PC system includes four During 1995, the SFPO finalized and issued canister designs, each of which require a detailed NRC review before approval. To effectively regulations regarding emergency preparedness . support both DOE's spent fuel programs and plans for ISFSIs. Related requirement included in 10 CFR Part 72 became effective on ongoing NRC reviews of transportation and spent September 20,1993. fuel storage systems, the NRC created the Spent Fuel Project Office (SFPO) within NhtSS in April 1995. The SFPO is responsible for regulating and certifying transport containers, package designs, and interim storage of spent fuel, whether at CERTIFICATES OF COMPLIANCE reactor sites or at separate consolidated sites. The new office serves as the Agency's focal point for As previously indicated, the general license is very design adequacy and safety direction for spent attractive to utilities because it permits the use of fuel storage and transportation packages. The an approved cask design without the need for SFPO is also responsible for formulating and additional licensing action. In FY 95, the implementmg transportation safety and interim Standardized NUHOhiS Horizontal hiodular storage policy for the agency. Storage System for Irradiated Nuclear Fuel, designed by Vectra Technologies Incorporated, received its CoC and was incorporated into the li of a oved storage cask designs by DEVELOPMENT OF THE DRY CASK STORAGE ACTION PLAN In FY 95, the NRC completed its review of the Soon after its formation, and in anticipation of tepical report for the Nuclear Assurance increased industry activity in the area of ISFSIs, Corporation Storage and Transport Cask (NAC the SFPO staff evaluated past performance of STC); however, the NRC has not yet received a both the industry and the NRC in the area of dry request to add this cask to Subpart K. The NAC cask storage of spent fuel. This evaluation STC already holds a transportation CoC, and is revealed that improvements were needed in { the first approved cask design to meet both communications both within and external to the j transportation and storage requirements. Two NRC, and that NRC requirements and j
L - 95 expectations required clarification. As a result, e adoption of IAEA limits on the amount of the NRC Office of Nuclear Reactor Regulation material that can be shipped in a '1ype A (NRR) and NMSS developed the Dry Cask package Storage Action Plan, which identifies major issues and concerns related to storing spent fuel at The final rule also incorporates criteria for ISFSis, and suggests measures for addressmg packages used to transport plutonium by air j such issues. Specificahy, tye pian addresses under the Scheuer Amendment (Public Law concerns regardmg techmcal near-term and 9gg)- long-term actions, commumcations, and procedural issues. One key factor in the plan is to encourage and enhance communication with the nuclear industry. Toward that end, the NRC staff has initiated discussions with members of the Nuclear Energy Institute (NEI), which subse- TRANSPORTATION AND STORAGE quently formed a dry cask storage workmg group INSPECTION ACTIVITIES and will periodically inform the agency of activities to resolve issues raised in the plan. In the meantime, the NRC continues to assess utility In FY 95, NMSS expanded and broadened its performance in the area of dry cask storage, and will review and update the plan on a quarterly inspection activities to ensure that transportation
, basis. The SFPO also plans to issue procedures packaging and dry spent fuel storage systems for inspecting ISFSis, and a standard review plan certified and licensed by the NRC are designed, fabricated, tested, maintained, and used in for spent fuel storage systems.
accordance with commitments made to the NRC. In prior years, for example, NMSS inspection teams examined licensees' implementations of quality assurance program commitments. 'lhis year, by contrast, NMSS redefined its inspection Pr gram to focus on performance-based REVISION OF 10 CFR PART 71 inspections of activities affecting safety and reliability. The safety inspection teams consist of individuals experienced in fabrication tech-On September 28,1995, the NRC published nologies, design requirements, quality assurance revised regulations (in 10 CFR Part 71) for the practices, and other technical specialties. Safety transportation of radioactive materials. Effective inspectors also participated as observers on three April 1,1996, the revisions bring the NRC's DOE audits of MPC program contractors regulations into general compatibility with those involved in transporting and storing dry spent of the International Atomic Energy Agency reactor fuel. The objective of these observations (IAEA). Specifically, the NRC adopted the was to verify adequate DOE oversight of following major revisions to achieve compatibility contractor activities affecting the safety and with IAEA regulations: reliability of MPCs. NMSS inspections were performed at seven o requirements for additional performance suppliers representing a broad spectrum of the tests for Type B packages industry, including designers, fabricators, and vendors of transportation packaging and dry o adoption of IAEA provisions for shipping storage systems. The inspection program is low-specific activity material and structured to provide information on whether surface-contaminated object suppliers comply with technical specifications and design requirements, as well as the provisions of 10 CFR Parts 71 and 72. The following photo-e simplification of requirements for shipping graph shows a primary containment vessel in a fissile material dry spent-fuel storage system.
96
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1 i -
! .- The NMSS Materials Licensing and Inspection f- Program is designed to ensure that activities involving use of radionuclides do not endanger the public health and safety. During FY 95, the NRC 1 ~- '
regional staff completed 2112 inspections of materials facilities. The NRC Regional Offices 1 i .- administer almost all materials licenses, with the l 1 N 7 "y exception of exempt distribution licenses, sealed l
._ . source and device design reviews, and licenses for ' ] companies that extract other metals from ores i
j and slags containing uranium and thorium. These 5 licenses are handled by the NRC Headquarters.
- 1 During FY 95, the NRC completed 4630 licensing '
j actions, of which 293 were new licenses,2882 were ; amendments,1054 were license renewals, and 401 ' } NMSS Inspector (from left) D. Reid, K. I.eu, and were scaled source and device reviews. j S. O'Connor perform safety inspection of the primary ' containment sessel of the VSC-24 dry spent fuel storage j system. l i MATERIALS LICENSING BUSINESS PROCESS REENGINEERING
'In October 1994, the staff began to examine the l MATERIALS LICENSING process used to issue materials licenses,in order to identify ways to improve the process. During AND INSPECTION this examination, the staff found that licensing j
was being accomplished using a complex process 1 involving anywhere from 54 to 94 exchanges of j NRC Headquarters and Regional Offices l information among individuals and computer currently administer approximately 6500 licenses systems during a routine license review. On for the possession and use of nuclear materials in i average, the NRC took 84 days to complete a ' medical and industrial applications. (This represents a reduction of about 200 licenses in the licensing action, although only 2 days were 1 j past year.) Table 1. shows the distribution of actually needed to complete the technical safety review of a typical licensing request. During the
- licenses by Region. Tiu 29 Agreement Statt
- remaining 82 days, paper was either in transit or 1 administer about 15,000 additional licenses.
in the queue. The staff proposed to reduce the { licensing process to an average of four days. i. Therefore, consistent with the goals of the Table 1. Distribution of NRC-Administered National Performance Review and the Paperwork ; ' Nuclear Materials Licenses Reduction Act of 1995, the staff initiated an i i (as of October 11,1995) innovative approach to improve management of 3 i information collections. As directed by the 1 l Commission, the staff held various meetings and j i Region I 2285 i workshops to gather input from Agreement Region II 878 States, licensees, and the public. The selected l Region III 2235 approach, called Business Process Reengineering
- Region IV 872 (BPR), fundamentally changes the way work is j Headquarters 208 i performed, to achieve significant improvements in speed, cost, and quality. This new process BPR,
} Total 6478 will also most likely lead to more clear, consistent, i
and timely regulatory guidance, ensuring that its 1 i
97 i i implementation will not have any adverse effect technology developed a generalized design for a l on public health and safety. In fact, many new materials licensing process. Specifically the l licensees believe that fewer operational problems core team proposed using a graded licensing l l will occur if the NRC is able to significantly approach that matches the safety hazards < reduce the time necessary to process licensing associated with a license application. The
- actions. following diagram shows a more streamlined workflow for materials licensing actions that is In the first BPR phase a core team of people who expected as a result of the Business Process work in licensing, administration, and informatior Reengineering initiative.
j Graded Processing of Licenses i Gas Chromatograph' ; EppiflaE0E'$c'Uno 100% Initial
- Gatekeeper &
Workflow "* ---
" ' QA Audit Manager ,
! Applicants & , NRC Licensing Tool Set License
- Licensee ! , ji. i ,
~ _
h( n h Y !
- W 929 === {
E A Application Tgig Bad 4 issum Applications Broad Scope =
- Licensees Business Process Reengineering
) Applications for relatively simple actions would resolution. This system would significantly alter go through a computer assisted process. This the practice of using technical staff to review
; process would use artificial intelligence-assisted well-established and relatively low-risk uses of scripts to help reviewers rapidly determine if the licensed materials.
applications conform with established NRC regulations and licensing policies. Any Applications for more complex uses would be
, unanticipated circumstance or any improper or processed by trained technical reviewers, working l incomplete respons0 would automatically alert either individually or in teams. The staff plans to reviewers and require separate action for develop a new set of tools to facilitate consistent,
98 l high-quality reviews. These tools will include a of the American Society of Hospital Pharmacists, single, comprehensive licensing manual that and was attended by more than 200 people. The consolidates all NRC regulations and guidance in analyst also made a presentation on " Failed one easily accessible form. This licensing manual Functions and Wrong Patient Misadministrations" will be made available to the Agreement States, to more than 100 people at the October 1994 the public, and licensees in both hard copy and Annual Meeting of the Human Factors and electronic media (e.g., a bulletin board), when it is Ergonomics Society, completed. During the second BPR phase, which began in November 1995, the team began the detailed REGULATORY IMPACT SURVEY design, and testing of the NRC's new materials licensing process. Implementation of this new In May 1992, the staff submitted to the process is scheduled to begin in 1996 Commission a plan to conduct a regulatory impact survey of fuel facility and materials licensees (SECY 92-166). The survey was intended to determine if the licensees believed that there is IIUMAN FACTORS an appropriate balance between the burden imposed by NRC requirements and the level of
.. safety achieved as a result. In Phase I of the plan, NMSS participated m. developing the NRC's the staff conducted a pilot series of nine onsite
" Human Performance Program Plan," which was interviews at selected fuel cycle and major published in August 1995. The plan identifies materials facilities between August and October activities needed to contmue the NMSS program 1992, and integrates those activities with those of other NRC offices. On the basis of the results of those interviews, the staff submitted a report a report (SECY 93-130)
In summer 1995, the NRC published two recommending a number of changes to staff contractor reports entitled " Human Factors practices and a plan for obtaining a broader Evaluation of Remote Afterloading Brachy- range of licensee views. The Commission therapy" (NUREG/CR-6125) and " Human instructed the staff to present a plan for obtaining Factors Evaluation of Teletherapy" additional information from licensees, and for (NUREG/CR-6277). Those reports identified evaluating and incorporating that information into human factors problems in remote afterloading the regulatory program. The Commission brachytherapy and teletherapy (tasks with a high approved the plan, recommended by the staff in potential for human error that could adversely SECY 93-268, to conduct a survey of several affect system performance), proritizing those hundred licensees through mail questionnaires. problems in terms of their safety consequences. In addition, the reports identified factors that Respondents to the questionnaires identified a contribute to those given human factors, and number of issues. Most significantly, respondents evaluated alternative means for resolving those noted timeliness of licensing actions, the need for that are safety significant, updated and clear regulations and guidance, costs of compliance and fees, licensee reluctance to An NRC human factors analyst made disagree with reviewers and inspectors, and the presentations based on the two contractor reports perceived safety significance of enforcement to the Staff College of the Center for Devices and actions. Although these matters are all addressed Radiological Health and to the Great Lakes in current initiatives, the survey helped to focus Chapter of the Health, Physics Society. staff activities. In a subsequent Commission l Paper (SECY-95-198), dated July 27,1995, the In addition, an NRC human factors analyst staffinformed the Commission of the results of developed, coordinated, and participa'ed in a the mail survey (reported in more detail in 3-hour seminar on " Ergonomics: Identifying and NUREG/CR-6330) and of the staff measures to Resolving System Errors." This seminar was deal with issues identified in that survey. For presented at the 1995 Mid Year Clinical Meeting example, the survey findings provided important
99 licensee feedback to NRC staff involved in the INDUSTRIAL USES Materials Licensing BPR endeavor. Industrial Radiography As described in the 1994 NRC Annual Report INTEGRATED MATERIALS (p. 90), the NRC staff has been mvolved for some PERFORMANCE EVALUATION time with an initiative to develop a certification PROGRAM program for industrial radiographers. During FY 95, the staff co*:tinued to support the American Society for Neudestructive Testing (ASNT)in In January 1994, the NMSS staff prepared a implementing the ASNT " Industrial Radiography Commission Paper (SECY 94-011), which Radiation Safety Personnel" certification program. presented an approach for the use of common The staff also worked toward completing a final performance indicators in reviewing Agreement rule that would mandate radiographer State and NRC regional materials programs. The certification. This rule was combined with a Commission subsequently appioved the use of rulemaking that would result in an overall revision five programmatic indicators as part of a pilot of 10 CFR Part 34. The combined rule was program in 1994-1995. These indicators allowed a published for comment on February 28,1994. The team comprised of technical staff from NMSS and NRC staff anticipates publishing the final rule the Office of State Programs to evaluate a region sometime in 1996. or State based upon the status of its materials inspection program, its technical staffing and In a separate action, on May 31,1995, the staff training, the technical quality of its licensing and published a final rule (60 FR 28323) to permit the inspection programs, and its responses to ure of an alternative value for the torque test of l incidents and allegations. After conducting a drive cables. This amendment to 10 CFR Part 34 ! 1-week onsite evaluation, the team issued draft was needed because the existing regulation cited a i I reports for regional or State comment, considered value from the American National Standards the comments, and prepared final reports for Institute (ANSI) standard for radiographic approval b;' a senior-level NRC Management equipment that was not practical to meet, given Review Board (MRB), the design of the equipment. In addition, the amendment also permits the use of an engineering During the pilot phase of this Integrated analysis to demonstrate that a modest change in a Materials Performance Evaluation Program, the previously approved design is acceptable without team used this process to review two regions and the need to perform prototype tests, three Agreement States, each of which had volunteered to participate. Following the Source and Device Registration evaluations, the team held a separate MRB meeting with each region or State before issuing Manufacturers and distributors of radiation j of final findings. sources and devices containing such sources are J required to submit to the appropriate regulatory 1 At the conclusion of the pilot program, the staff agency (i.e., the NRC or an Agreement State) prepared another Commission Paper safety information about their products, along (SECY-95-047), presenting the findings from the with information about their quality assurance pilot program, and recommending a revised (QA) programs. The regulatory agency evaluates approach based on comments received and the information to ensure that each product meets experience gained from the pilot reviews. The all applicable radiation safety requirements, is Commission approved the staff's adequately designed to protect the public health recommendations, and issued Management and safety, and that the company's QA program tember 1995; this is adequate to ensure that the product meets the Directive directive was subsequently pub i Sg' shed in the 5.6 in final form in design specifications. The regulatory agency then Fcdemi RegEtcr in October 1993. Based on that issues a registration certificate to the vendor. This directive, a series of nine Agreement State and certificate is used by the regulatory agency in ^ two regional reviews are scheduled for FY 96. issuing specific licenses to users of the products.
l 100 The NRC maintains a nationwide registry, Scaled Sources, Devices, and Other including registration certificates issued by both the NRC and the Agreement States. 7% registry Radioactive Materials Retrieved by the consists of a hard-copy file of all registration DOE eenificates, two database systems containing Several thousand NRC licensees possess material iMonnation commonly found on the first page of that exceeds 10 CFR Part 61 Class C limits and a registration certificate, and background files will need to be stored for an extended time until containing supporting information for the the DOE provides a disposal facility, or for which registration certificates issued by the NRC. The control cannot be assured because of the NRC also maintains a tracking system to facilitate licensees' financial or other difficulties. The NRC the retrieval of information regarding requests for has negotiated with the DOE to assist with new registration certificates or for amendments to managing such radioactive material when these existing certificates. The NRC also undertook the cases threaten the public health and safety. On following initiatives in support of these products two occasions during FY 95, the NRC requested evaluations: DOE assistance to retrieve, control, dispose of material that had become a threat to the public e health and safety because of a licensee's loss, or A Bulletin Board System (BBS) created on potential loss, of control of the material. In each the FedWorld System contains current case, the DOE provide the required assistance. information and documents related to the registration of scaled sources and devices. A number of Agreement States have noted similar This information includes electronic copies of problems with their respective licensees. The guidance documents, the Radiography NRC/ DOE agreement has been extended to Cross-Reference Program (RADXREF), the include licensees located in Agreement States in PC-based Registry database system, and the which the State is unable to manage the material Scaled Source and Device Newsletter. Infor- and requests assistance from the NRC. During mation on the BBS is updated frequently and FY 95, the NRC requested DOE assistance on can be downloaded remotely. behalf of an Agreement State on two occasions. e The NRC staff has defined procedures for A workshop on sealed source and device determining if DOE assistance is appropriate, safety evaluations, was presented to and for making the request. In addition, the NRC participants from the NRC and other and DOE staffs have formalized the agreement regulatory agencies. The topics included under which the NRC requests DOE assistance. guidance on what is required to perform a A Memorandum of Understanding (MOU) has safety review, engineering and technical skills been drafted for this pumose, approved by the required to perform the review, and the use NRC, and sent to the DOE for approval. The of agency and industry standards. The NRC and DOE staffs have also explored options workshop was intended to provide additional to resolve the issues involved with licensees that guidance and information regarding the have limited or no disposal options and for which registration process, and to form a basis for materials control cannot be assured. the standardized application of review principles and procedures throughout the . . regulatory agencies. Scaled Source and Device Design Safety Testing Contract e The number of pending requests for review The NRC has in place a contract for securing was reduced to less than 200, thereby third-party examinations of products containing decreasing the total time required to issue a radioactive material for which safety evaluations registration certificate. To accomplish this have been performed. As needed, the NRC may goal, the staff completed more than 400 request that the contractor examine a product, sealed source and device reviews-more than along with information supplied in support of the double the number completed in previous application for safety review and approval. years. Through that examination, the contractor i
101 i evaluates the product's ability to perform as complete a report containing its recommendations intended and to provide adequate radiological during FY 96. safety for the intended and actual conditions of use. In addition, the NRC has requested that the contractor evaluate products that (1) have known or suspected generic design defects; (2) are MEDICAL USES suspected to be inadequately designed or constructed for their intended conditions of use, and (3) have failed and for which the failure mode Status of Medical Management Plan needs to be determined. In FY 95, the contractor performed and issued final reports on three such The Medical Management Plan (MMP) is a 5-year evaluations. plan, which began in October 1994. It contains more than 90 action items categorized in 9 major program areas, including such areas as licensing Centrol of Radioactive Devices and inspection, rulemaking, misadministration policy, enforcement, and research studies. Since 1983, there have been 24 reports of Approximately 70 percent of the action items radioactive sources accidentally smelted in the identified in the MMP are considered closed, United States as a result of becoming mixed with while others are either partially closed or not yet metal scrap intended for recycimg. Of the 24 addressed because they depend on the closure of reports,16 occurred at steel mills. In 1994, a precursor items. The staff continues to address 14-GBq (330-mci) unshielded cesium-137 source both short- and long-term action items to resolve was found buried in soil at a metal scrap policy issues and specific tasks, while adjusting processing plant in Illinois, and in 1995, a program priorities in response to unforeseen shredder at a processing plant in Kentucky events and changing needs. separated a 12-GBq (330-mci) cesium-137 source from its shielded holder. Although no significant l radiation doses have been documented as a result Quality Management Rule of these or other events in the United States, Implementation similar events in Mexico in 1983, and in Estonia in 1994, resulted in radiation injuries and death. On January 27,1992, regulations became effective that required N~RC medical licensees to establish In 1995, the Commission approved a staff plan to and implement a quality management program form a joint Agreement State-NRC Working (QMP) in compliance with 10 CFR 35.32. On Group to evaluate current regulatory programs January 25,1995, the regulations became effective for devices containing radioactive material, for Agreement State licensees. This performance-including devices held under both specific licenses based regulation focuses on therapeutic and general licenses. The Working Group will applications of byproduct material, and any determine whether the current regulatory patient dosage of sodium iodide-125 or -131 in programs provide an adequate level of assurance quantities greater than 30 microcuries. During in each of the following criteria: FY 95, implementation c.ctivities included developing a standard reviewing plan and I o The devices are properly controlled and inspection guidance, reviewing licensre-submitted accounted for by licensees. quality management plans, resolving enforcement issues, tracking inspection findings, and o The devices do not present unacceptable developing staff recommendations on the l levels of risk of radiation exposure to workers regulation. or the public. The NRC, under contract with Lawrence o The devices do not present unacceptable Livermore National Laboratory (LLNL), reviewed l financial risk to the metal recycling industry, the 1709 QMPs submitted by applicable licensees, l and provided each licensee with a letter outlining ; The Working Group will also examine regulatog the review findings. A Temporary Instruction (TI) l alternatives, including their costs, and expects to regarding the inspection of implemented QMPs l t l
102 became effective in August 1994, and will remain Medical Use"; " Release of Patients Containing in effect for 2 years. This TI established areas of Radiopharmaceuticals or Permanent Implants" inspection and created a procedure for assessing (10 CFR Part 35.75); " Medical Administration of compliance. Data collected using this TI will be Radiation and Radioactive Materials"; included in the evaluation of the effectiveness of " Administration of Byproduct Material or the Qua.'ity Management rule. Radiation from Byproduct Material to Patients Who May be Pregnant or Nursing"; and guidance documents for the final Radiopharmacy Rule. Advisory Committee on the Medical Participants also discussed implementation of the Uses of Isotopes Quality Management Rule, the study of the medical use program by the National Academy of The Advisory Committee on the Medical Uses of Sciences, and Phase 11 of the National Isotopes (ACMUI) met in November 1994 and Performance Review. May 1995. Topics of discussion at these meetings included brachytherapy issues (including In addition, a subcommittee of the ACMUI met fractionation), revisions to abnormal occurrence in September 1995 to review draft licensing criteria, an advance notice of proposed modules to be incorporated into Regulatory rulemaking for 10 CFR Part 35, issues involving Guide 10.8, " Guide for the Preparation of misadministrations and patient followup, NRC Applications for Medical Use Programs." In use of consultants, prostate implant procedures, particular, the subcommittee discussed guidance training and experience of authorized users to concerning the Mobile Nuclear Medical Service, allow exemptions to Subpart J, dose ranges in radioactive drug therapy, remote afterloaders, written directives, a petition on the final manual brachytherapy, teletherapy, and gamma Radiopharmacy Rule, and information on stereotactic radiosurgery. calibration errors in strontium-90 eye applicators. Participants in the ACMUI meetings also As directed by the Commission, ACMUI ; presented status reports on several rulemakings members serve 2-year terms and are limited to 3 and guidance documents, including " Preparation, terms. Current membership of the committee is Transfer, and Use of Byproduct Material for shown in Appendix 3. l l l l l i I
CHAPTER 5 s o I e n / FUEL CYCLE SAFETY AND SAFEGUARDS The regulation of nuclear fuel cycle safety and activities with respect to the safeguards program safeguards in the United States is the for nuclear power reactors. responsibility of the NRC's Office of Nuclear . Material Safety and Safeguards (NMSS) and the NRC's four regional offices. NMSS is responsible for developing, implementing, and evaluating overall agency pohey with regard to the safety and FUEL CYCLE LICENSING safeguards of fuel cycle facilities licensed under the Atomic Energy Act of 1954 (AEA), as AND INSPECTION amended, or certified in accordance with the Energy Policy Act of 1992. NMSS also carries out the agency's principal licensing, certification, inspection, and regulatory activities to ensure FUEL CYCIE ACTION PLAN adequate safety and safeguards of licensed facilities. Action Plan for Regulating Fuel Cycle NMSS develops and continually evaluates the Facilities NRC's " design-basis" threats, and assesses The Commission has directed the staff to threats to the domestic environment as a result of implement a fuel cycle facility action plan to all NRC-h,eensed activities. The NMSS als enhance the rigor of the regulatory base for the directs the NRC s contingency planning and fuel cycle facility safety program, and to improve emergency response operations for accident the timeliness of the license renewal program. The events, mcidents, threats, thefts, or radiolog.ical commission further directed the staff to make sabotage related to NMSS-heensed activities. In
, numerous program improvements identified by addition, NMSS provides technical support (in th various sources, such as the " Proposed Method form of safeguards reviews) for export and import for Regulating Major Materials Licensecs" requests, retransfers, implementation of
, . (NUREG-1324) and the " Regulatory Impact Agreements for Cooperation, and transportation Survey for Fuel Cycle and Materials Licensees."
of strategic special nuclear material (SSNM). To accomplish these objectives, the action plan focuses on improvements in the regulatory base, Interaction between NMSS and the International as well as licensing, inspection, and training. Atomic Energy Agency (IAEA) occurs in connection with the implementation of the Staff activities to clarify and improve the rigor of US/lAEA Safeguards Agreement and technical the regulatory base include a major revision of support to strengthen IAEA safeguards. NMSS 10 CFR Part 70. " Domestic Licensing of Special also coordinates its activities with the NRC's Nuclear Material" (SNM). The objectives of this Office of Nuclear Reactor Regulation (NRR) to revision are to clarify and refine existing ensure consistent implementation of these requirements, to develop requirements that are
104 performance-oriented rather than prescriptive While contributing to the development of the SRP, (where possible), grade those requirements the licensing staff has continued to review according to risk, and to reduce unnecessary and pending license renewal applications, adhering to burdensome regulatory requirements. This activity the accelerated license renewal schedule. Until a could realize many of the improvements to the revision to 10 CFR Part 70 becomes effective, the fuel cycle regulatory program recommended in SRP now in development is being used in the NUREG-1324. In the course of this activity, the review oflicense renewal and amendment NMSS has initiated a series of public meetings applications. with industry and other major interested parties. Through these meetings, the parties discussed the Upgrading the inspection program through grounds for revising 10 CFR Part 70, the staffing of the Headquarters Inspection Section improvements in regulation sought by the staff, has permitted more efficient use of limited l and the different revision approaches the staff technical expertise for performing nuclear ; might take to achieve the stated objectives. criticality and chemical process safety inspections, l along with ongoing Headquarters material control and accounting (MC&A) inspections. I Another high priority for the staff is to develop a Headquarters staff will provide the technical j standard review plan (SRP) to be used in expertise to address difficult design, integration, reviewing fuel fabrication license amendments and adequacy concerns, and renewal applications. Along with the SRP, the staffis preparing a conformant revision of the An enhanced training program is being developed for the NRC licensing and inspection staffs. Of Standard Format and Content Guide (SF&CG) eight courses under development, six have been and a document to gmde beensees in selectmg presented to date* integrated safety analysis (ISA) methodologies. The SRP will be useful to the NRC staff in reviewing the applications and amendments, as - well as to applicants and licensees in understanding the intent of the new performance-FUEL CYCLE LICENSING oriented requirements. NMSS has imtiated pubhc ACTIVITIES ' I meetings with fuel cycle facility licensees to obtain input regarding the development of the ISA and By the end of FY 95, the NRC had completed 121 the SRP, and preliminary drafts of these fuel cycle licensing actions. 'lable 1 shows these
?ocuments have been made publicly available. licensing actions by category.
I Table 1. Fuel Cycle Licensing Actions (Safety / Safeguards) Completed in FY 95 Category No. of Actions Fuel Fabrication and Conversion 73 Critical Mass Materials 6 Fuel Research, Development, Pilot, and Fresh Fuel Storage 6 I Other Source Materials 3 Material Control and Accounting 24 Physical Security 4 West Valley Demonstration 4 Department of Energy Waste Processing 1
105 FUEL CYCLE SAFETY The primary activities conducted at B&W Parks Township melude decontammation, repair, maintenance, and testing of equipment and components contaminated with radioactive FUEL CYCLE SAFETY LICENSING ***'**I"***"'"""*^***'!"* waste; decontammation of ons ite facilities; and l i l management of an onsite burial area known as 1 l the Shallow Land Disposal Area. l IRT Corporation i On March 2,1995, the NRC terminated IRT l Corporation's license, SNM-1405, following the In the Fedeml Register on November 3,1993, the l disposition of all nuclear material stored at its NRC published a " Notice of Opportunity for a Arjons Road facility (San Diego, California) and Hearing" pertaining to the renewal of License after decommissioning was completed at the SNM-414. Citizens' Action for a Safe facility. IRT which filed for bankruptcy in July Er vironment and the Kiski Valley Coalition to l 1994, was purchased out of bankruptcy by Save our Children filed a joint request for a l Thermo Instrument Systems with the hearing, dated January 5,1994. On January 3, understanding that Thermo would not assume 1995, the Atomic Safety and Licensing Board responsibility for the nuclear material held under Panel (ASLBP) issued an initial decision resolving IRT's license (hence, the neces,sity for material
, all issues raised in the hearing, and authorized the disposition and decommissiomng before the renewal of License SNM-414. The renewal is takeover by Thermo). All of the stored nuclear expected to be issued in October 1995.
l l material was transferred to the Department of I Energy (DOE) and shipped to IIanford, Washington, and Los Alamos, New Mexico. i l Following acceptable decommissioning, as verified j l by the NRC through independent confirmatory measurements, the IRT facility was released for West Valley Demonstration Project unrestricted use. Oversight Allied-Signal, Inc. License Renewal i Throughout FY 95, the NRC staff continued its On June 13,1995, the NRC issued a 10-year
, safety oversight at the DOE West Valley renewal of Material License SUB-526, which l Demonstration Project (WVDP) near Buffalo, ;
i authorizes Allied to convert uranium ore New York, as shown in the following photograph. concentrates to uranium hexafluoride at the Allied The purpose of the WVDP is to demonstrate the conversion plant in Metropolis, Ilhnois. This preparation and solidification of high-level waste action followed an environmental assessment from spent nuclear fuel reprocessing for disposal ! (EA)in May 1995, and publication of a , Finding . . in a Federal repository. The maj.ority of the l of No Significant Impact" in the Fedeml Register high-level waste is contamed in a 750,000 gallon on May 17,1995. carbon steel tank, and is comprised of plutonium / uranium recovery extraction waste and Babcock & Wilcox Company, thorium recovery extraction (THOREX) waste. A Pennsylvania Nuclear Services minimal amount of cesium-coated zeolite from Operations, Parks Township, Preprocessing activities is stored in a separate carbon steel tank, and is currently being Pennsylvania comb,ned with the remainder of the wastes. i The B&W Parks 'Ibwnship's License, SNM-414, Beginning in 1996, the combined wastes will be has been in timely renewal since May 31,1989. solidified (vitrified) in borosilicate glass. i l l
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L Aerial Photograph of the DOE West Valley Demonstration Project ! l l The NRC staff monitors public health and safety process, as described in the submitted SAR, was j j aspects of the WVDP through inspections at the not expected to have a significant impact on the
- WVDP site and the review of safety analysis health and safety of the public or the l reports (SARs) submitted for each process by the environment. The NRC also reviewed and DOE. The staff reviews each submittal and issues commented on THOREX waste transfer, which l
- a corresponding safety evaluation report (SER),
was subsequently completed safely, rd the statmg the NRC,s conclusions on the pubhc combined SAR on low-level waste processing and health and safety implications of the process . . segment. In FY 95, the DOE submitted its latest support activities. The NRC contmued SAR for vitrification operations, as well as a new discussions with the DOE to develop SAR, for low-level waste processing and support decommissioning criteria to be addressed by the ! activities, which combined previously issued SARs DOE for various aspects of the WVDP. However, ! into a single volume. the NRC determined that a draft environmental In FY 95, the staff continued to monitor the imp ct statement (EIS) for site termination, , I ongoing construction and installation of scheduled for pubhcation by the DOE and the i equipment for the vitrification process building. State of New York in late 1995, would not provide
! The staff also continued to assess data from an acceptable basis on which to develop the j cement produced through the completion of criteria. Consequently, the NRC suggested that ! " sludge washes" and "TIIOREX washes." The these criteria be discussed as part of a decom-l NRC issued an SER stating that the vitrification missioning plan to be submitted in 1996 or 1997.
4 --- -
107 Shieldalloy Metallurgical Corporation issue an environmental assessment before the end of 1995. However, completion of the renewa; (SMC) process may be delayed because SMC's financial Since 1955, SMC has operated a manufacturing condition is having a significant adverse effect on facility located in Newfield, New Jersey, where it the company's ability to meet decommissioning has manufactured specialty steel and super alloy financial assurance requirements. additives. Under License SMB-743 the NRC licenses activities at the site related to processing Nuclear Fuel Services (NFS) a mineral concentrate (pyrochlore) to recover niobium. The pyrochlore contains more than 0.05 In December 1993, NFS submitted for NRC , percent natural uranium and thorium that, as review and approval an m, terim decomm,ssionmg i source materials, require a license under 10 CFR Pl an for phased remediation of portions of the Part 40. During the manufacturing process, these NFS facility in Envin, Tennessee, under License radioactive materials are concentrated in SNM-124. The NRC found the plan acceptable, high-temperature slag and baghouse dust. The and issued a confirmatory order in June 1994 slag contains the highest concentrations and Permitting NFS to begin decontamination and volumes of source material. decommissioning activities, including the removal of radiation sources from a previously authorized burial area. Additional NRC approval will be In September 1993, SMC notified the NRC that it , required for final decontammation and had filed for bankruptcy protection under ,, decommissionmg of the Erwm site, after Chapter 11 of the U.S. Bankruptcy Code. The termmation of plant operations, before the facility disposal of slag and baghouse dust at the can be released for unrestricted use. Newfield facility is one of SMC's largest and least defined liabilities. In 1993, SMC's regulatory NFS is currently separating buried contaminated counsel informed the staff that in-situ disposal of debris from the soil using special segregation the material is the only alternative that SMC equipment. A new groundwater treatment system could reasonably afford, given its financial is being used to decontaminate the groundwater condition. In October 1993, the staff began pumped from this area, as well as the water developing an EIS to evaluate the proposal for generated during soil washing. NFS has proposed in-situ disposal, and completed the scop, mg further work of this kind on other areas of the process in July 1994. In December 1994, SMC plant site. submitted to the NRC an application to export a test quantity of the slag for use in steel processing In addition to these measures, the licensee is in a foreign country. SMC expects that preparing proposals for potential business characteristics of the slag would allow steel ventures such as decontaminating equipment manufacturers to produce a higher quality steel at from other facilities, and possible downblending lower cost. SMC has successfully provided of Russian high-enriched uranium (HEU), under similarly produced slag, which does not require the Russia-U.S. Government-to-Government NRC licensing, to the domestic steel industry. In Agreement. cooperation with the Department of State, the NRC is awaiting agreement of the foreign nation
, Chem-Nuclear Systems, Inc. (CNSI) involved before issumg the beense to SMC.
Because the success of this process could License Amendment significantly affect the scope of the EIS, the staff On June 21,1995, the NRC amended CNSI's postponed further development of the EIS until a Service License 39-23004-01 to increase the decision is reached concerning the acceptability of possession limit for uranium-235 to 30,000 grams, the export license. This increase will facilitate processing operations in which CNSI, under contract to the Fernald SMC's operating license has been in timely Environmental Restoration Management renewal since July 1985. The Newfield facility Corporation, will neutralize and solidify continues to operate and to provide a source of approximately 100,000 gallons of uranyl nitrate revenue for the corporation. During FY 95, the hexahydrate waste solution located at the DOE's staff completed data collection and expects to Fernald Facility.
i ! 108 - i i
- Gaseous Diffusion Uranium basis. The USEC is also directed to negotiate the
! Enrichment purchase of HEU offered by any State of the i former Soviet Union. This uranium comes from
- In October 1992, Congress enacted the Energy material produced in the nuclear weapons l Policy Act of 1992, which created the United program of the former Soviet Union. Finally, the j States Enrichment Corporation (USEC) and USEC is directed to assume management of new j directed the DOE to lease the two gaseous alternative technologies for the enrichnwnt of l diffusion plants (GDPs) located in Portsmoutl- uranium, including the " atomic vapor laser l Ohio, and Paci ucah, Kentucky, to the USEC. The isotope separation" technology. The following j USEC is to operate the plants and to market the three photographs are from the Portsmouth, Ohio, enriched product on a profitable and efficient plants.
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, . =, .. . t . leading Customer C 31inder on Transport Vehicle 1 1 The Energy Policy Act of 1992 provides that the The Energy Policy Act of 1992 also makes NRC shall regulate safety and safeguards at the provision for the DOE to prepare a plan for GDPs operated by the USEC. In consultation bringing the plants into compliance with any with the EPA and DOE, the NRC is to report to unsatisfied provisions of the NRC regulations. Congress at least once each year on the status of This plan would be submitted to the NRC health, safety, and environmental conditions at the together with the USEC's initial application for , plants. The report is to include a determination of certification. j whether the plants are in compliance with j applicable NRC regulations. In addition, the NRC A new rule (10 CFR Part 76) to govern the j is to establish a certification process to ensure certification of the GDPs was issued in proposed t that the USEC complies with the regulations, and form in February 1994, and in final form in j the USEC is to apply to the NRC for an annual September 1994. This regulation establishes
; certificate of compliance with NRC standards. standards for adequate protection of public health j This certification process is to be in lieu of any and safety and the environment, as well as for j requirement for a license. safeguarding n0 clear materials in the interest of 1
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- national security. This rule applies only to the prevention, accident analysis, and fire protection, GDPs operated by the USEC. among others.
The USEC submitted its initial application for . certification on April 18,1995. However, the NRC On September 15,1995, the USEC submitted a determined that USEC's April 1995 submittal did revised application, which the NRC accepted for I not include adequate information for the NRC to review by letter dated September 21,1995.
, assess compliance with the standards established Subsequently, the NRC issued its first request for , ,
l for the GDPs. Therefore, the NRC rejected the additional information (RAI) in October 1995. l i application on May 5,1995. The NRC's decision Public meetings to receive pubh,c comments on i j to reject the application did not constitute a the USEC s application were held in late 1995 at determination that the plants were unsafe. the Kentucky and Ohio plant sites. ] j Following the rejection, the NRC staff met several times with USEC staff to discuss the content of Review of the USEC's application will continue i the USEC's application. Topics discussed into 1996, and the NRC intends to issue a included radiation protection, criticality certification decision around February 1996.
i 111 , An important part of the certification process is The Citizens Against Nuclear Trash (CANT) the NRC's assessment of the GDPs, with regard oppose facility licensing for the CEC. In response to the requirements listed in 10 CFR Part 76. In to that opposition, the NRC's ASLBP held a support of the certification process, the formal adjudicatory hearing in two phases. The I headquarters and Region III staff jointly first phase of the hearing covered safety issues, performed numerous safety and safeguards and was held in Shreveport, Louisiana, in July l' assessments covering security, material control 1994. The second phase of the hearing covered and accounting (MC&A), criticality, and chemical environmental issues and was held in Shreveport, safety at the GDPs. Results of these assessments Louisiana,it March 1995. Issues addressed were presented in 13 integrated inspection reports included completeness of the licensee's issued during FY 95. application, decommissioning cost estimates, the need for the facili:y, groundwater and surface water impacts, environmental justice, analysis of the "no action" alternative, financial qualifi-cations, and tails disposition. CANT, LES, and Gas Centrifuge Uranium Enrichment the NRC staff participated in the hearing and the ASLBP is expected to issue a decision soon. In November 1990, the President signed into law , the " Solar, Wind, Waste, and Geothermal Power 1 Production Incentives Act of 1990"(Public Law FUEL CYCLE SAFETY 101-575). This law amended the AEA to establish new requirements for regulation of commercial INSPECTIONS uranium enrichment facilities. The NRC published rule changes implementing the amendment in the Fedeml Register on Headquarters-Based Inspection September 16,1991. Activities I As part of the ongoing reorganization of fuel cycle Ir. January 1991, the Louisiana Energy Services, facility activities within the NMSS, several L.P. (LES), submitted an application for a license inspection activities have been consolidated in to construct (at a projected cost of over $800 NRC Headquarters since February 7,1993. In million) and operate a gas centrifuge uranium particular, Headquarters staff will now conduct enrichment plant, to be known as the Claiborne chemical process safety and nuclear criticality Enrichment Center (CEC). The CEC will be safety inspections, as well as MC&A inspections, located in Claiborne Parish near Homer, and Headquarters developed and initiated the Louisiana, and will have a capacity of 1.5 million chemical process safety inspection program. A kilograms of " separative work units per year," total of 13 criticality safety and chemical safety ; about 15 percent of the annual enrichment service inspections and assessments were performed i requirement of United States nuclear utilities. A during FY 95. Of these, four chemical safety draft EIS was published for comment in assessments at the GDPs and three chemical November 1993, and the NRC subsequently safety inspections at NRC licensees were . received more than 500 letters concerning the conducted as a pilot program, and draft I draft EIS. The final EIS (NUREG-1484) was inspection procedures were prepared. A criticality issued in August 1994, and the SER and chemical safety assessment was also (NUREG-1491) was issued in January 1994. As conducted at the WVDP. stated in the EIS and SER, the NRC staff concluded that the CEC can be constructed and A technical assistance contract has been awarded operated with small and acceptable impacts on to support development of a complete set of the environment, and the facility does not pose criticality safety inspection procedures. In undue risk to the public health and safety. The addition, Headquarters staff provided technical NRC staff documents therefore support issuance expertise to regional inspectors to address design, of a combined construction / operating license for integration, and adequacy concerns in the areas of the facility, criticality and chemical process safety.
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Region-Based Inspection Activities comprehensive safeguards requirements during FY 95. Of the eight facilities, only one contains i The four regional offices conducted more than 92 significant quantities of HEU, requiring extensive
; safety inspections at 18 operating and decom- physical security and MC&A measures. Another
- missioning fuel cycle facilities during FY 95. of the eight facilities, NFS (Envin, Tennessee), l These inspections included resident inspector previously reduced the quantity of HEU material !
, activities at one facility. The areas covered by the stored on site, thus substantially reducing the I j regional staff included criticality safety, radiation physical protection and MC&A measures l protection, emergency preparedness, environ- required. NFS continues to work with the Russian mental safety, and transportation. Participants in Federation toward the possible conversion of a regional NRC inspection are shown in the HEU from the former Russian nuclear weapons following photograph. program into light-water reactor fuel. However, there was no significant activity in this area l during 1995. ! y ug eq g'yg.- The fully implemented pnysical protection j a E; i 4
- -: - . requirements provhie for performance testing j % e.- / through the use of mandated tactical drills and NITOR
- g 1 exercises. The singie Category naciiity,8&w s Naval Nuclear Fuel Division (NNFD), continues I ,
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# mc asures as a result of lessons learned during L.; ~ ).1 '
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developed additional drill scenarios during L . calendar year 1995, to further test its physical p.' protection program.
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1 The COGEMA Irigaray uranium recosery facility in i Northern Wyoming is licensed by the NRC and produces natural uranium (yellowcake) through an in-situ leaching INSPECTIONS process. Pictured are NRC Branch Chief Charles Cain and l Inspector Vincent Everett monitoring themselves for During FY 95, the Headquarters staff conducted l contamination before leaving the licensee's restricted area in J""' IN-24 comprehensive MC&A inspections, while the I regional and resident inspectors performed six l physical security inspections at major fuel i fabrication facilities. Performance-based inspection procedures were used by the physical
- FACILITIES AND security inspectors during all of these inspections.
l TRANSPORTATION i SAFEGUARDS REACTOR SAFEGUARDS 1 4
, Reactor Safeguards Inspection and
- FUEL CYCLE SAFEGUARDS Licensing j LICENSING During FY 95, the four NRC regional offices conducted a total of 115 core inspections at A total of eight active, licensed nuclear fuel cycle licensed nuclear power reactor sites. In addition, facilities were subject to the NRC's the regional offices participated in reactive and i
1 I 113 l l regional initiative inspections as a result of Commission's original intent; and enhance overall unusual activities that took place at some sites. program integrity, effectiveness, and efficiency. I Approximately 181 revisions to the licensee Program performance data provided by licensees security, guard training, and contingency plans were summarized in " Fitness for Duty in the were received and reviewed by both the regional Nuclear Power Industry: Annual Summary of and headquarters staff. Because of changes in Program Performance Reports, CY 1994" security technology for automated access control (NUREG/CR-5758, Volume 5), dated August I systems, numerous licensees have requested and 1995. This report indicates that 163,241 tests for been granted an exemption to the 10 CFR the presence ofillegal drugs and alcohol were 73.55(d)(5) requirements that address control of conducted during calendar year 1994, of which site access badges. 1,372 were positive. The majority of the positive , test results (977) were obtained through ; i pre-access testing (1.22 percent positive rate). An I additional 223 positive tests were obtained Operational Safeguards Response through random testing (0.28 percent positive Evaluations at Power Reactors , rate). The positive rate also varied by worker category. For example,0.18 percent of random l After completing the Regulatory Effectiveness tests of heensee employees were positive; for Review Program in May 1991, the NRC staff , I ng-term contractors, the positive rate was 0.19 initiated an Operational Safeguards Response Percent; and for short term contractors, the Evaluation (OSRE) program at power reactors. ,, An OSRE is an effectiveness review conducted by p sitive rate was 0.54 percent. In general, positive rates, with minor exceptions, were reduced; l l an interdisciplinary team, consisting of a nuclear however, the positive rates for pre-access and l engineer and physical security specialists, assisted r ndom tests mereased in 1994. This increase may ! i by contractors. The team evaluates a licensee *s be attributable to the actions of several heensees l contingency response capabilities by focusing on to lower the cutoff levels for marijuana screening the interactions between operations and security tests, and to increase emphasis on detectmg l personnel in establishing priorities for the subversion of the testmg process. The decreased protection of safety equipment, and by random testmg rate also may have contributed to scrutinizing and testing the defensive strategies the increased positive rate, used. OSRE teams also conduct safety and safeguards interface reviews to ensure that safeguards do not adversely affect the safe Access Authorization Programs at operation of the plant. Nine OSREs were Power Reactors conducted during FY 95, for a total of 36 to date. These evaluations resulted in a total of 34 Power reactor licensees are required to implement sigmficant improvements at 16 power reactor access authorization programs under 10 CFR sites. 73.56. These programs are intended to ensure that individuals granted unescorted access to protected and vital areas at nuclear power plants Fitness-for-Duty Programs at Power are trustworthy and reliable and do not constitute Reactors an unreasonable risk to the health and safety of the public, including the potential to commit i Power reactor licensees are required to implement radiological sabotage. Toward that end, l fitness for-duty programs under 10 CFR Part 26. established access authorization programs use l Although the existing rule appears to be achieving background investigations, psychological the desired effect, the Commission is considering assessments, and behavioral observatians. changes that would reflect lessons learned during the first 5 years of the program. The changes The NRC conducted 16 initial access authoriza-being considered would ensure compatibility with tion program inspections under Temporary changes the Department of Health and Human Instruction (TI) 2515/116, and found that the Services made to its testing guidelines in 1994, programs are generally effective. However, and would substantially reduce burden; clarify the because of the number of implementation issues l
l l l 114 identified, the staff determined that initial 21 shipments 13 were by rail,2 were exports, and inspections were necessary at all facilities not 1 was an import. l previously inspected. These inspections are currently being conducted under TI 2515/127. Strategic Special Nuclear Material Once a program receives its initialinspection Shipments under one of the above tis, continuing routine inspections of the program are conducted under During FY 95,12 domestic shipments of less than the NRC Core Inspection Program. The results of 5 but more than 1 kilogram of HEU were these mspections will be evaluated to determme if completed. No commercial domestic, export, or further program changes are necessary. import shipments were made of 5 or more kilograms of HEU during FY 95. Nonpower Reactors (NPRs) 'nacking International Shipments of During FY 95, the NRC completed 16 safeguards inspections of NPRs. The program to convert 25 NRC regulations require licensees to notify the NPRs from HEU fuel to low-enriched uranium agency ofinternational shipments of SNM and (LEU) fuel is continuing. Its progress depends on natural uranium. During FY 95, the NRC received the availability of DOE funding, the availability of about 252 such notifications. When appropriate, a suitable replacement fuel, and whether a reactor these were forwarded to the Department of has some " unique purpose" requiring HEU fuel. Transportation for notification of international As of the end of FY 95, one license had been authorities. terminated, three licensees had received conversion or decommissioning orders, and eight licensees had converted to LEU fuel. Th remammg 13 reactors are operatmg with HEU INTERNATIONAL fuel, and two have submitted SARs. The NRC has ordered one of these two to convert from HEU to ACTIVITIES LEU, and is currently preparing the conversion order for the second one. Six of the 13 NPRs operatmg with HEU fuel have been funded by INTERNATIONAL SAFEGUARDS l DOE for evaluation of the operational effects of ACTIVITIES the fuel conversion and for preparation of an 3 SAR. However, the DOE has not funded one The NRC is responsible for implementing IAEA university reactor because of the unavailability of safeguards at licensed and certified nuclear suitable replacement fuel, and another two facilities in the United States. Although there are commercial reactor licensees will not be funded currently no NRC-licensed facilities under IAEA by DOE for fuel conversion. The Commission is inspection, the United States continues to report also reviewing two " unique purpose" applications, to the IAEA all exports and imports, as well as all but there is no suitable replacement fuel for one accounting information required by the Protocol of these reactors. to the U.SJIAEA Safeguards Agreement for five fuel fabrication facilities. The NRC also ensures that licensed facilities maintain their MC&A systems and carry out their reporting responsibili-TRANSPORTATION SAFEGUARDS ties to meet the terms of the U.S/IAEA Agreement, as specified in 10 CFR Part 75. i The NRC continues to contribute to the total U.S. i Spent Fuel Shipments support of IAEA safeguards through interagency I efforts that also involve the DOE, the Arms During FY 95, the NRC applied safeguards Control and Disarmament Agency, the requirements to 21 shipments of irradiated spent Department of State (DOS), and the Department reactor fuel made over approved routes. Of these of Defense.
115 During 1995, an NRC staff member served as with the NRC before authorizing subsequent Chair of the Subgroup on IAEA Safeguards in arrangements for the retransfer of nuclear the United States, which oversees all activities materials of U.S. origin from one country to related to the implementation of IAEA safeguards another, and before providing technological at U.S. facilities. In response to President assistance to foreign nuclear energy activities. Clinton's offer to place excess fissile material During 1995, the NRC performed 116 under IAEA safeguards, three DOE sites were international safeguards technical reviews selected for IAEA safeguards inspections. regarding export applications, agreements for Another NRC staff member served as a member peaceful nuclear cooperation, subsequent of the Subgroup on Safeguards Technical Support, arrangements, and technology transfers. which seeks to strengthen and improve IAEA safeguards through technical support. During In keeping with the NRC responsibility to ensure 1995, this Subgroup supported funding of the application of IAEA safeguards to exported U.S. IAEA's replacement of aging safeguards nuclear material, the NRC supports the equipment with state-of-the-art equipment. Both improvement of effective international safeguards. of these Subgroups report to the Subcommittee The NRC also continues to contribute to U.S. on International Safeguards and Monitoring Government efforts to strengthen IAEA (SISM) of the IAEA Steering Committee. The safeguards, and to maintain the effectiveness of NRC is also represented in the SISM which, in implemented safeguards. During 1995, the NRC addition to monitoring the activities of these continued a special study with respect to the , referenced subgroups, took an active role during difficult issues associated with establishing i FY 95 in collaborating with United States allies internationally acceptable criteria for terminating on international safeguards issues during IAEA safeguards on nuclear materials contained , multilateral meetings. in waste. Also during this reporting period, an NRC staff member continued serving as the Chair f the Technical Coordinating Committee, which In response to concerns regarding nuclear-related - versees a multinational effort to develop the activity in Iraq, the IAEA is planning to broaden IAEA safeguards approach for the final disposal its safeguards activities to include measures to of spent fuel. An NRC employee also serves as the detect undeclared nuclear facilities. The NRC is U.S. member of the Standmg Advisory Group on supporting this effort and contributing to the S fcguards Implementation (SAGSI), an advisory evaluation and implementation of new measures. group to the Dnector General of the IAEA. In this regard, during 1992 and 1993, the IAEA Recent SAGSI reviews have focused on measures Board of Governors decided, with the support of to improve the efficiency of IAEA safeguards. the United States, to request that Member States report certain additional information. Specifically, the request includes early provision of design information on new facilities, as well as FORMER SOVIET UNION information on major modifications and additions ACTIVITIES to existing facilities; expanded reporting of exports, imports, and production of nuclear During FY 95, the NRC continued to support the matenals; and reporting of the import or export of interagency Cooperative Threat Reduction certam nonnuclear matenals and equipment. The, Program. This initiative coordinates support to NRC took measures to satisfy this request during the republics of the former Soviet Union (FSU)in the FY 95 reporting period. dismantling their nuclear arsenals and deterring proliferation of weapons of mass destruction. The The NRC is responsible for licensing exports and NRC's primary role is to assist these republics in imports of nuclear facilities, equipment, material, establishing national regulatory systems for and related substances, as authorized by the MC&A and physical protection. AEA, as amended. Further, under amendments to the AEA adopted in the Nuclear Non- In 1995, the NRC hosted delegations from Proliferation Act of 1978, the DOS must consult Kazakstan and Ukraine for safeguards regulatory with the NRC about new agreements for peaceful workshops during which the NRC staff explained nuclear cooperation. Also, the DOE must consult the U.S. regulatory process. The NRC also
116 coordinated a visit by a Kazakstani delegation to nuclear fuel facility in Hematite, Missouri. the Westinghouse Commercial Nuclear Fuel Representatives from the Russian nuclear Division in South Carolina to discuss regulatory agency GOSATOMNADZOR (GAN) implementation of MC&A regulations. also accompanied and observed the NRC staff during an MC&A inspection. The NRC has coordinated trips by several FSU safeguards inspectors to observe NRC MC&A Headquarters inspection staff participated with l and physical protection inspections as shown in officials from GAN in July 1995 meetings at NRC the following photograph. NRC representatives Headquarters in accordance with the NRC/ Russia also observed an MC&A inspection by the Lisbon-9 initiative. 'Ibpics on the agenda included Russian nuclear regulatory authority at the an Introduction to NRC Structure and Elektrostal nuclear fuel facility in Russia. Organizations, How NRC Regulates, Fuel Cycle i Inspection, and the Regional Inspection Programs l for Fuel Cycle Facilities. GAN officials requested and were given copies of publicly available m,mw' t 4' n _ _ Federal regulations, regulatory guides, and [ 4 NUREG-series reports that pertain to regulating fuel cycle facilities. After these meetings, GAN _ officials accompanied and observed Region HI
- c. y. i staff as a safety inspection was performed at the 4 j ABB-Combustion Engineering facility in
' I_ . - qmu Hematite, Missouri.
y 4' ~}N{. Jy? >m
* $ ls "
; The NRC also serves in a technical advisory
,~ L capacity on an Interagency Working Group (IWG) d %' R f on the Dispo.sition of Excess Weapons Plutonium.
gs, . ip _w. h;yi This IWG is considering technical, economic, nonproliferation, scheduling, and environmental aspects of the disposition of surplus plutonium. Steve Caudill (third from the left), FCSS International The NRC staff has provided input to the IWG safeguards section,with the Delegation from Kazakstan at and DOE on regulatory and international AllH/ Combustion Engineering Nuclear ruel racility for safeguards issues, and has participated in I?5C"553""5 '" 5.laterial Control and Accounting and meetings related to the joint U.SjRussia I hysical l'rotection . .. . disposit:on study, meetings with Canadian officials regarding the CANDU option, DOE In March 1994, the United States and the Russian public scoping meetings, and a meeting regarding Federation signed a protocol concerning German assistance in Russian disposition. transparency measures in both U.S. and Russian Support to DOE on plutonium disposition facilities that will process HEU extracted from alternatives is funded through a reimbursable former Soviet nuclear weapons. Under the HEU agreement. The NRC also participates in an Disposition Agreement signed in February 1993, interagency group examining alternative this material will be blended in Russia to form safeguards approaches for excess weapons LEU, which will subsequently be fabricated into components. light-water reactor fuel by NRC-licensed facilities in the United States. The NRC's role is to ensure that transparency measures in U.S. commercial fuel fabncation facilities are practical. The first INTERNATIONAL PIIYSICAL shipment of material subject to the agreement PROTECTION ACTIVITIES arrived in June 1995. Bilateral consultations on physical protection of Part of the follow-up activities resulting from a nuclear facilities and materials are arranged with Technical Working Group meeting in February countries that have SNM of U.S. origin or 1994 between the NRC and the Russians included material derived therefrom. These bilateral a visit to the ABB-Combustion Engineering consultations are designed to share technical
l 117 information "d cxperience concerning physical SAFETY AND SAFEGUARDS protection of e.m,han nuclear activities. During FY 95, the NRC visited Taiwan, Thailand, the EVENT EVALUATION AND Philippines, Spain, and Portugal. In exchame, a teans from Canada visited the NRC and an RESPONSE NRC-licensed facility. Substantial increases in reported incidents of smuggling and offers for sale of alleged REPORTING OF NUCLEAR weapons-usable nuclear materials have CRITICALITY SAFETY EVENTS demonstrated the importance of ensuring a high level of physical protection on materials and In October 1991, NRC Bulletin 91-01, " Reporting facilities. , Loss of Criticality Safety Controls," was issued to all NRC-licensed facilities with activities including hot cell operations, enriched uranium operations, uranium fuel research and development, or critical mass operations. The bulletin requested th t U ensees infonn the NRC of their dteria NUCLEAR MATERIALS and procedures to ensure prompt evaluation and reporting of conditions and events involving i MANAGEMENT AND nuclear criticahty safety. SAFEGUARDS SYSTEM Under Bulletin 91-01, licensees have since reported 67 " criticality" safety-related events, IUCIuding 6 events reported during FY 95. The ' Jointly funded by the DOE and :he NRC, the . , m j r ty of these events were reported within 24 Nuclear Materials Management and Safeguards , hours, and involved less-sigmlicant degradations System (NMMSS) is an accounting system f criticality safety controls.The NMSS Dmston encompassing all licensed SNM and foreign f Fuel Cycle Safety and Safeguards uses a i source material in the United States. The C mPuter database to analyze trends and patterns i NMMSS charter includes materials that m rder to focus NRC inspection resources on originated in the United States and elsewhere. areas of greatest criticality safety concern. Material is tracked between facilities, on a continuing basis, from original refinement to eventual disposal. Import / export transactions are also tracked with this system. Selected data, based THREAT ASSESSMENT AND on NMMSS output, are then furnished to the IAEA,in fulfillment of U.S. international LIAISON / DESIGN-BASIS , obligations and bilateral agreements. THRENT/ INCIDENT RESPONSE ACTIVITIES In October 1994, a new NRC rule to streamline the collection of nuclear material transaction data and increase the accuracy of the reported data Threat Assessment and Liaison became effective. In September 1995, the NRC successfully transferred the NMMSS system to a The NRC staff continually reviews the threat new contractor. The new system uses a downsized environment worldwide; assesses threats to computer platform that promises to improve the NRC-licensed facilities, materials, and activities; efficiency of operations, while maintaining and prepares safeguards incident response plans flexibility for responding to future programmatic for responding to actual thefts of nuclear material changes. Plans to further reduce and possibly or radiological sabotage of nuclear facilities or eliminate the need for paper transactions for activities. In performing these functions, the high-volume licensee users of NMMSS are now safeguards staff maintains close contact with the being considered. intelligence community, including participation in
g regt;lar meetings of Federal agencies that are Incident Response prepared to address terrorism. During FY 95, an NRC staff member was asked to Chair an During the FY 95 reporting period, the NRC interagency counterterrorism subcommittee (the reviewed and updated its fuel cycle safeguards first time a non-intelligence community incident response plan. representative has been given such responsibility). Liaison activities also include briefings and SAFEGUARDS
SUMMARY
EVENT consultations with the representatives of other governments regarding NRC threat assessment LIST and incident response activities. During FY 95, the NRC continued to participate in a variety of During FY 95, the staff continued to analyze sessions to train intelligence community threat safeguards events related to threats and incidents analysts and others, in order to augment their in order to identify trends, patterns, and understanding of nuclear-related matters. anomalies. On the basis of that analysis, the staff published the Safeguards Summary Event List (SSEL), NUREG-0525, Volume 2, Revision 3. During FY 95, the NRC continued to work closely with the DOE and other interested agencies to This SSEL represents a compilation of brief investigate reported attempts to sell alleged summaries of several hundred safeguards-related events m, volving nuclear materials or facilities nuclear materials. NRC activities in this area included participating in an international regul ted by the NRC, which occurred and were symposium on nuclear smuggling that was hosted reported from January 1,1990, through by the Federal Bureau of Investigation in December 31,1994. Events reported before Quantico, Virginia. The NRC also particiP ated in Congress established the NRC through a high-level interagency group concerned with the December 31,1989, were published in SSEL l Federal Government s response to nuclear Volume 1, which was issued on December 31, ' 1992. During FY 95, the SSEL was distributed to smuggh,ng and other events involving alleged nuclear materials. In addition, the members of the domestic and international l multidisciplinary NRC/ DOE Communicated intelligence community, in addition to the normal i Threat Credibility Assessment Team, was called distribution in the licensed community. upon periodically during FY 95, to assess attempts to sell alleged nuclear and radioactive materials' SAFETY AND SAFEGUARDS Design Basis Threat REGULATORY ACTIVITIES AND ISSUES In response to the April 1995 bombing in Oklahoma City, the staff gave information to the Commission regarding the implications of the attack and the possible need to modify the PROPOSED RULES AND STUDIES design-basis threat for radiological sabotage and l existing safeguards requirements. A Commission During FY 95, the NRC continued the following response to the information is pending. Also, in rulemaking actions and studies to determine the light of the Oklahoma City bombing, the NRC l need for rulemakings: l Information Assessment Team issued an information advisory in April 1995 to all power e Security Plan Format Changes. On April 17, reactors, NPRs, and certain fuel cycle facilities. 1995, the NRC published a proposed rule to The staff also continued its ongoing review of the amend 10 CFR Parts 50 and 70 to eliminate threat environment, and provided its findings to submittal of physical security plans in two the Commission and senior NRC management on parts by applicants for power reactor and a semiannual basis. Category I fuel cycle licenses. The two-part
119 format, specified by current regulations, is parameters used to define critical mass could now deemed unnecessarily restrictive and has be expressed in terms of SNM concentration, no regulatory advantage. Licensees whose instead of " total SNM mass," for very low-plans were approved before the effective date specific-activity soil.The staff had deter- - of the final rule would not be required to mined that this modification'was feasible; adopt the new format. They may, however, however, based on further development of the revise their security plans to conform to the issue, the staff is currently evaluating the new format on a voluntary basis, pursuant to need for a rulemaking to add an exemption the rules that permit licensees to make based on a concentration limit. changes in security plans provided that the changes do not diminish the effectiveness of the plans. . SSNM in Transit. Work continued on an initiative to upgrade physical protection of SSNM in transit. Because there are currently o Safeguards for Spent Nuclear Fuel or High- n ensees that would be affected by a Level Radioactive Waste. In a proposed rule , Proposed rulemaking. the NRC will handle published for public comment on August 15, the issue m a cost-effective manner on a 1995, the NRC amended its regulations to case-by-case bas,is, instead of performmg a clarify safeguards requirements. Specifically, , , the amendment concerned requirements gen nPing yulemaking@heensing manm enwna Gatd regarding safeguards for spent nuclear fuel or could be used as guidance for licensing an high-level radioactive waste stored at , entity desinng to transport Category I independent spent fuel storage installations, quantities of SSNM. power reactors that have permanently ceased reactor operations, monitored retrievable storage installations, and geologic repository l e Safety of Fuel Cycle Facilities and Others operations areas. This rule would allow general licensees the option to implement the Licensed for SNM. Work continued toward a major revision of the rule governing the proposed safeguards requirements for spent nuclear fuel stored in approved casks at possession and use of SNM,10 CFR Part 70. operating power reactor sites. This action is The pnmary objective is to update and enhance tne regulatory basis for facilities necessary to reduce the regulatory uncertainty regarding the safeguards Possessing large amounts of SNM. 'Ib further the revision of 10 CFR Part 70, the NRC requirements for the storage of spent nuclear initiated a series of meetings to discuss with fuel and high-level radioactive waste without reducing the level of protection for public the fuel cycle licensees and other interested health and safety. parties the reasons for revising the rule, the objectives the staff wants to achieve, and the potential changes in the requirements or o Independent Spent Fuel Storage Installations other aspects of staff's regulatory approach Vehicle Bomb Study. A study is underway to that can be made to achieve the objectives. determine whether a need exists for a The principal proposed changes are (1) ISA regulation to require the installation of of plant processes and changes to those vehicle barriers around independent spent processes, to identify potential areas of risk fuel storage installations. The study will and to elucidate how safety is achieved; examine whether the spent fuel storage casks (2) expanded focus on chemical process and are inherently robust enough to withstand an fire protection safety; and (3) more specific attack without a significant release of Performance requirements for management radioactive material. control systems for plant safety. In addition, proposed modifications to 10 CFR Part 70 would improve the organization of the o Safe Concentration of SNM in Soil. As a regulation, and would make it easier for result of a petition for rulemaking, the NRC applicants and licensees to distinguish those staff conducted an analysis to determine if requirements that apply to their activities.
120 GUIDANCE DOCUMENTS study to assess the usefulness of various analytical source term and dispersion models to estimate the consequences resulting from o ISA of Fuel Cycle Facilities. Under the inadvertent releases of uranium hexafluoride. proposed changes to 10 CFR Part 70, fuel Such releases constitute one of the most cycle facilities would be required to perform serious hazards at most NRC-licensed fuel an ISA, which is a comprehensive analysis of cycle facilities. To address concerns about the hazards and potential accidents at a such hazards, NRC licensees and applicants facility, and the items and actions relied on need to be able to evaluate the consequences for safety. Consequently, during FY 95, the that would result from potential accidents NRC continued its work to prepare a involving the release of uranium hexafluoride. document giving industry guidance on Such evaluations are important in three areas acceptable ways of performing an ISA. A of regulatory interest to NRC, including ISA, draft of this document will be provided with emergency planning, and post-accident the proposed rulemaking package of investigation. The assessment of various modifications to 10 CFR Part 70, previously analytic models will assist the NRC in discussed. judging the acceptability of such models for use in these three areas. o SRP for the Review of a License Application for a Uranium Fuel Processing and/or e Chemical Process Safety for Fuel Cycle Fabrication Facility. During FY 95, the NRC Facilities. The NRC is preparing a document continued to develop an SRP to provide to give industry guidance for minimizing guidance for the NRC staff to use in unwanted impacts of chemicals and chemical reviewing and evaluating the health and processes on licensed nuclear niaterials. The safety, safeguards, and environmental aspects issuance and continuance of specific licenses of applications for licenses to possess and use for activities involving SNM require the uranium to produce nuclear fuel. This applicants' proposed equipment and facilities guidance is also applicable to the review and to be adequate to protect health and evaluation of proposed amendments and minimize danger to life or property. For license renewal applications. In addition, the proper evaluations to be performed, - guidance is useful to licensees for applications for a specific license should understanding the intent of new risk-based include information regarding the chemical requirements proposed for the revision of process safety of the proposed equipment 10 CFR Part 70, and a draft will be included and facilities. This guide will describe to among the documents to accompany that licensees and applicants the NRC's general revision when it is proposed. philosophy concerning the role of chemical process safety as it pertains to NRC-licensed o Standard Format and Content Guide materials, the basic information needed for (SF&CG). During FY 95, the NRC continued proper evaluation of chemical process safety, j to develop an SF&CG for applicants to use and the evaluation methods used to in preparing applications for licenses, license determine the adequacy of the chemical amendments, and license renewals for fuel safety of the proposed equipment and cycle facilities. The SF&CG will describe the facilities. This guidance is being developed scope and type of information applicants concurrently with the guidance document should submit with their applications for concerning ISA and the proposed review by the NRC staff. The information modifications to 10 CFR 70, previously , specified by the SF&CG will also correspond discussed. l to the new SRP. The draft SF&CG will be ! published with the rulemaking package for e Physical Protection for Spent Fuel Storage. A the proposed revision of 10 CFR Part 70. new guidance document, " Interim Licensing Criteria for Physical Protection of Certain o Uranium Hexafluoride Vapor Cloud Model Storage of Spent Fuel"(NUREG-1497), was Study. During FY 95, the NRC initiated a published in November 1994. This document
121 4 presents interim criteria to be used in constructed specifically for the storage of licensing certain spent fuel storage spent fuel; the proposed geologic repository installations. These criteria apply to both dry operations area; or permanently shutdown cask and pool storage at installations that power reactors still holding a 10 CFR Part 50 store power reactor spent fuel at license. decommissioned power reactor sites; independent spent fuel storage installations e MC&A Guidance. A revision of Regulatory located outside of the owner-controlled areas Guide 5.15, "'Ihmper-Indicating Seals for of operating nuclear power reactors; Protection of Special Nuclear Material," is monitored retrievable storage installations currently being developed for public owned by the DOE, designed and comment. A 1 1
- ' CHAPTER 6 e
v' WASTE MANAGEMENT The responsibilities of the NRC's Office of rulemaking (PRM-60-3), submitted by the Nuclear Material Safety and Safeguards (NMSS) Department of Energy (DOE)on April 19,1990, include wgulating of all commercial high-level and requesting that 10 CFR Part 60 be amended to low-level radioactive waste and uranium recovery include quantitative dose criteria for a facilities. This chapter deals with the NRC's design-basis accident. Comments on the proposed high-level and low-level radioactive waste rule were received from 10 parties. The NRC is programs, decommissioning of nuclear facilities reviewing these comments, and expects to publish (including reactors) transferred to the NMSS from the final rule by April 1996. the NRC's Office of Nuclear Reactor Regulation), (NRR) and management of uranium recovery and Another area of NRC rulemaking activity mill taihngs. concerns regulations consistent with HLW standards promulgated by the Environmental Protection Agency (EPA). In the Energy Policy Act of 1992, the EPA was directed to contract with the National Academy of Sciences (NAS) to HIGH-LEVEL WASTE provide findings and recommendations on re son ble st na rds for Protecting the public PROGRAM , health and safety from releases of radioactive material stored or disposed of in a repository located at Yucca Mountain, Nevada. The EPA was also required to promulgate health-based standards that are consistent with the findings REGULATORY DEVELOPMENT , and recommendations of the NAS. The NAS ACTIV11,IES study considered three questions posed by the Energy Policy Act of 1992. During fiscal year 1995 (FY 95), the NRC continued to take steps to ensure that the . whether a standard based on doses to regulations governing the safe disposal of individuals is reasonable. high-level waste (HLW)(10 CFR Part 60) are clear and complete. On March 22,1995, the NRC o published in the Fedend Register a proposed rule, yvhether post-closure oversight and active mstitutional controls can effectively ensure
" Disposal of Iligh-Level Radioactive Wastes in that exposures of individuals will be Geologic Repositories: Design-Basis Events." This ,
m intained within acceptable limits. proposed rule clarifies the relationship of 10 CFR Part 60 requirements to potential accident conditions, and provides consistency among NRC e whether scientifically supportable probability regulations governing similar activities. The estimates of human intrusion into a proposed rule also addresses a petition for repository over 10,000 years can be made. L - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
124 The NAS released its completed report entitled 3, and completing several scheduled performance
" Technical Bases for Yucca hiountain Standards," assessment products.
on August 1,1995. The Energy Policy Act of 1992 requires the EPA to promulgate its final The NRC also completed work that will lead to standards by August 1,1996, and the NRC must the publication of a draft staff technical position ensure that the technical criteria in 10 CFR (STP) on the use of expert elicitation in the HLW Part 60 conform to the new EPA standards program. The STP provides general guidelines applicable to Yucca hiountain within 1 year of applicable to the formal use and documentation their promulgation. of expert judgments, identifying circumstances , that may warrant a formal process for obtaining I the judgments of more than one expert. In j addition, the STP describes acceptable pro-TECHNICAL ASSESSMENT cedures for conducting an expert clicitation when CAPABILITY FOR REPOSITORY formal judgments are used to support a LICENSING REVIEWS dem nstradon of compliance with the regulatory requirements of 10 CFR Part 60. The staff plans to release this draft STP for public comment in During FY 95, NRC staff continued its work on the first quarter of FY 96. the draft License Application Review Plan (LARP). Designated as NUREG-1323, the LARP is a comprehensive guidance document for NRC staff review of a potential DOE license YUCCA MOUNTAIN SITE application to construct and operate an HLW CIIARACTERIZATION REVIEWS repository. In particular, the LARP provides guidance to the NRC staff on how to review AND INTERACTIONS DOE's license application to construct a mined geologic repository for the disposal of spent During FY 95, the NRC staff continued nuclear fuel and other HLW at Yucca hiountain, prelicensing interactions with the DOE, and Nevada. The LARP is intended to ensure the provided guidance regarding the DOE's ongoing quality and consistency of the staff's pre-licensing site characterization activities. The NRC staff also and licensing reviews. Because it is a public conducted numerous DOE-related interactions, document, the LARP will also help the DOE and including 25 meetings and technical exchanges other interested parties to better understand the with the DOE, and one meeting with Nye County, NRC staff's review process by describing the Nevada, in which the DOE participated. There review strategies, procedures, and acceptance were also approximately 10 site visits to Yucca criteria that the staff will use. Afountain by the staff, as well as a visit by the Chairman and Executive Director for Operations. Having completed its work to revise the draft Early in FY 95, the staff had a full-time presence LARP, the staff expects to publish Revision 1 in at the Yucca hfountain site to observe the ently FY 96. Revision 1 and subsequent revisions opration of the tunnel boring machine. During l of the draft LARP are preliminary documents and this period, two new onsite representatives (ors) l are subject to change. Revision 1 will contain 10 were assigned to the Las Vegas office, where they j newly completed individual review plans and assumed their duties to provide day-to-day NRC l revisions to 3 appendices. oversight of the DOE's ongoing site l characterization DOE activities. During FY 95, the staff also completed the Phase l 2 activities to support the development of its In mid-FY 95, it became apparent that the NRC i independent performance assessment (IPA) staff would need to better focus its limited capability. The NRC staff plans to issue a report resources to adequately respond to the DOE documenting the Phase 2 results early in FY 96. program in light of budget reductions in the HLW In addition, the NRC and its contractor, the program. The staff began by reviewing the 54 key Center for Nuclear Waste Regulatory Analyses technical uncertainties identified in Appendix E (CNWRA), initiated Phase 3 IPA development to the LARP. In addition, the staff reviewed the activities by preparing provisional plan for Phase results of the DOE's total system performance
125 assessments (TSPAs), the NRC IPA, and other One area of concern previously identified by the technical interactions with the DOE. On the basis staff deals with the lack of an effective QA of this review, the staff identified the key technical program for the DOE's lead management and issues it deemed most important for licensing. operations contractor, as stated in a letter to the The staff intends to focus its resources in DOE in 1994. An effective QA program is resolving these key technical issues using an essential to correct identified problems and approach consistent with the Overall Review ensure full integration of issues related to the Strategy (. ORS), NUREG-1495, which was design and construction of the exploratory shaft published in 1994. Specifically, for each issue, the facility. During the week of April 3,1995, the staff intends to conduct an audit review NRC staff conducted a field verification to (sometimes referred to as a vertical slice review). determine if the DOE was effectively and acceptably implementing its commitments to address this issue. The NRC staff concluded that, within the scope of the field verification, the P ance vith its c t e s was INTERACTIONS WITH AFFECTED a sfac ory. GOVERNMENTAL UNITS AND identified issues remained open. By letter to the DOE dated June 16,1995, the NRC staff INDIAN TRIBES transmitted its report of the field verification. Before finally closing the open items identified in During FY 95, the State of Nevada, 1994, the staff will review additional documents representatives of affected units oflocal submitted by the DOE, and will conduct another government, and other interested parties inspection. l continued to participate in the technical j exchanges and meetings between the NRC and the DOE. To facilitate this participation, these parties continued to receive notification of upcoming CENTER FOR NUCLEAR WASTE NRC/ DOE HLW meetings, as well as meetings of REGULATORY ANALYSES (CNWRA) the NRC Advisory Committee on Nuclear Waste. In addition, the NRC staff continued its active On October 15,1993, the NRC renewed its role in ensuring that these parties receive all contract with the CNWRA. and the CNWRA correspondence and publicly available NRC completed its eighth year of operation in October reports regardm, g the HLW program. 1995. The CNWRA provides a broad range of HLW program support to the NMSS and to the Office of Nuclear Regulatory Research (RES). CNWRA staff are located at the Southwest Research Institute in San Antonio, Texas, and at QUALITY ASSURANCE ACTIVITIES the Washington Technical Support Office in During FY 95, the NRC staff continued to review the quality assurance (QA) plans and procedures During FY 95, the CNWRA continued working (document reviews) prepared by the DOE and its with the NRC staff to develop and implement a contractors. The staff had two main objectives for computer-assisted systems engineering approach, this review. First, the staff evaluated DOE's called the Systematic Regulatory Analysis (SRA), effectiveness in auditing its program to identify for the development of regulatory documents. The and correct problems in program implementation. purposes of the SRA are to identify and reduce Second, the staff evaluated the DOE contractors' uncertainties, to select strategies and methods for effectiveness in implementing QA programs. As assessing compliance with NRC regulatory part of these evaluations, the NRC staff observed requirements, and to define issues in licensing an DOE audits conducted at all major DOE HLW geologic repository. The NRC is using this contractor organizations participating in the site approach to ensure that all of its HLW activities characterization program for the Yucca Mountain under the Nuclear Waste Policy Act (NWPA) are Project. planned, integrated, implemented, documented, 1 l
126 and managed as thoroughly and effectively as comments, strategic assessment, and stakeholder possible. input. The CNWRA's special expertise also supports the NRC staff in such areas as review of study plans and design reports, NRC/ DOE pre-licensing REGULATIONS AND GUIDANCE meetings and technical exchanges, QA observation audits, technical support to NRC rulemaking and regulatory guidance development Rulemakings programs, development of analysis methods (e.g., ... computer codes), and research. Activities in the NRC staff from the Division of Waste research program include unsaturated mass Management (DWM) supported two rulemakings transport (geochemistry), thermohydrology, during the FY 95. First, the DWM supported the seismic rock mechanics, integrated waste package Office of International Programs m completmg a experiments, stochastic analysis of flow and final rule amendm, g 10 CFR Part 110, " Export and transport, geochemical analogs, modeling of Import of Nuclear Eqmpment and,Matenal." sorption mechanisms, regional hydrology, These amendments brmg the pohcies of the l performance assessment (PA) issues, United States into conformance with the J volcanism / seismology (review), volcanism (field), guidelines of the International Atomic Energy Agency (IAEA) " Code of Practice on the { and tectonic analysis. International Transboundary Movement of Radioactive Waste." In addition, these amendments strengthen the Commission's control over radioactive waste entering and leaving the United States by requiring a specific license for LOW-LEVEL WASTE exporting and importing radioactive waste. This rule became effective on August 21,1995. Second, the DWM supported RES in a final rule amending to 10 CFR Part 20, " Standards for The main objective of the NRC's low-level waste Protection Against Radiation," and 10 CFR (LLW) program is to ensure that LLW Part 61, " Licensing Requirements for Land management adequately protects the public health Disposal of Radioactive Waste." These and safety and the environment, in accordance amendments will improve the quality and with the Low-Level Radioactive Waste Policy uniformity ofinformation contained on manifests Amendments Act (LLRWPAA) of 1985. During that are required to control transfers of LLW FY 1995, the NRC staff assessed the implications ultimately intended for disposal at a land disposal of terminating the NRC's LLW disposal program facility. The amendments will also establish a set during a budget review aimed at meeting reduced of forms that will allow LLW to be tracked from targets for the agency. As part of the review, the its origin, and will serve as a uniform national staff identified and assessed two alternatives to LLW manifest to meet NRC, the Department of complete termination of the program, including Transportation, an'd State and Compact maintaining the program as is and reducing it to information requirements: In addition, the the legal minimum with additional activities that amendments will require LLW disposal site are essential to the national program. The staff operators to electronically store manifest provided its assessment to the Commission in information, and to be capable of reporting the July 1995 as a Commission Paper, SECY 95-201. stored information on a computer-readable In September T5, the Commission returned the medium. The rule will become effective on or paper to the s;aff to obtain comments from the before March 1,1998. l Advisory Committee on Nuclear Waste (ACNW) l and to consider program options as part of the During FY 95, the DWM also supported RES in agency's overall strategic assessment. The staff withdrawing a rulemaking that would have will provide revised recommendations to the allowed private ownership ofland disposal Commission in early 1996, based on the ACNW's facilities for LLW. The NRC published an advance
127 notice of rulemaking in August 1994, but formally BTP on disposal of emission control dust and withdrew the rulemaking in August 1995 after the related materials contaminated with cesium-137 Commission considered the proposal and related from the accidental melting of sealed sources. The public comments in July 1995. NRC has closely coordinated the development of the draft BTP with EPA and State regulatory authorities, and plans to issue the draft BTP for Guidance public comment before the end of calendar year 1995. Additional guidance development activities During FY 95, the staff cont.mued its program to related to mixed waste are described under the develop LLW PA guidance and to enhance staff heading " Cooperation with Other Federal
, , i expertise m PA. Guidance-related staff activities Agencies," in this chapter. i focused on three main objectives: l l
o Review comments received on the draft Topical Report Reviews branch technical position (BTP) on LLW PA, which addresses important issues in PA During FY 95, the staff completed its review of 4 modeling. two topical reports that address specific technical issues regarding compliance with NRC regulations o Revise the BTP as a result of these for disposal of LLW (10 CFR Part 61). After ; comments. review and approval by the staff, licensees may reference the processes described in these topical o Gaining experience with integrated PA reports, and may incorporate the technology for modeling through an NRC-developed test use in their operations. case model. The first topical report reviewed by the staff These activities will provide license applicants during FY 95 concerns a multi-use, high-integrity with additional guidance on acceptable container proposed by Chem-Nuclear Systems, approaches for evaluating the long-term Inc., for use as a fundamental component of the performance of an LLW disposal facility, and will North Carolina LLW disposal facility. The second further improve the NRC's ability to provide topical report reviewed by the staff (with the technical assistance to the Agreement States. The support of several states) addressed a waste staff plans to complete the BTP and the test case analysis software program called Vance 3R-STAT, model in FY 96. which yields results that are used to determine or project the inventory of the highly mobile and In January 1995, the staff completed and long-lived radionuclides technetium-99 and published a final branch technical position (BTP) iodine-129. In addition, the Vance 3R-STAT on " Concentration Averaging and Encapsulation". modeling results could significantly affect the NRC's regulations in 10 CFR Part 61 require that technical analyses used to demonstrate that the waste proposed for near-surface disposal be LLW disposal facility performance objectives of classified to ensure its suitability for disposal. 10 CFR Part 61 are met. The reviews of four other Part 61 also establishes a waste classification topical reports were discontinued because of the system based on the concentration of specific lack of progress in resolving open issues, radionuclides contained in the waste. In addition, the regulation states that the concentration of a In April 1995, DWM staff published a notice in radionuclide may be averaged over the volume or the Fedeml Register announcing the termination of the weight of the waste. The BTP builds upon the the NRC's topical report review program in requirements of 10 CFR Part 61 by defining a response to budget reductions and an assessment subset of concentration averaging and of the status of topical report reviews. In lieu of encapsulation practices that the NRC staff would reviews by the NRC, vendors are encouraged to fm' d acceptable in determining the radionuclide seek reviews, if necessary, by Agreement State concentrations required for waste classification. regulatory authorities. The NRC will be available, however, to provide a limited amount of technical In response to concerns from the steel industry assistance to Agreement State authorities on and others, the DWM staff also developed a draft topical report reviews, if requested.
128 TECHNICAL ASSISTANCE TO THE 1992 Oeneral Memorandum of Understanding l STATES between the agencies on regulation of radionuclides m the environmen:. During FY 95, the DWM staff continued to In FY 95, the NRC and the EPA also completed a support the NRC Office of State Programs (OSP) White Paper on risk harmonization transmitted in providing technical assistance to the States as for approval by a Commission Paper designated they implement their plans for LLW disposal SECY-95-249, which identifies and explains the facility development and licensing. Technical differences between the NRC and the EPA assistance to States included the following approaches to risk assessment and risk activities: management. In a related effort, the NRC and the EPA formed the Interagency Steering Committee e Participate in meetings of the LLW Forum, on Radiation Standards (ISCORS), which also the Technical Coordination Committee, the includes representatives from the DOE, the Council of Radiation Control Program Department of Defense (DOD), the Department Directors E-5 Committee, and groups of of Transportation, the Department of Health and State and compact officials that meet to Human Services, and the Occupational Safety and discuss policy and technical issues of Health Administration. ISCORS has been common interest. meeting quarterly since its first meeting in April 1995. Discussions of the ISCORS . Risk e Meet with State officials from New Jersey Harmonization Subcommittee resulted in a set of concerning LLW disposal facility licensing recommendations to resolve the differences procedures. identified in the aforementioned White Paper. These recommendations are included in a e At the request of the National Academy of Commission Paper designated SECY-95-249. Sciences, conduct a technical review of the State of California's projection of Also in FY 95, the NRC and the EPA completed plutonium-239 to be disposed of at the State's and published draft guidance on storing mived LLW disposal facility. waste and continued to develop guidance on testing mixed waste. The purpose of the.,e e Conduct a workshop on the LLW guidance documents is to ensure that the storage Performance Assessment BTP, and testing of mixed waste can be accomplished in a manner that is consistent with the regulatory e Participate in the annual DOE National LLW requirements of both agencies. Tne agencies also Management Conference and the LLW completed development of a proposed technical Decisionmaker's Forum, position on the management of emission control dust contaminated by the inadvertent melting of licensed sealed sources. Finally, the NRC provided the EPA with specific recommendations COOPERATION WITH OTHER for reforming the Resource Concervation and FEDERAL AGENCIES Recovery Act, with the goal of reducing or ehmmatmg duplicate reqmrements for mixed During FY 95, the DWM staff worked with the l EPA in five principal areas, including risk Regarding emissions of radionuclides to the air, harmonization, radioactive mixed waste, the NRC and the EPA continued to cooperate in regulation of air emissions of radionuclides, determining whether the NRC's existing development of radiological criteria for regulatory program under the Atomic Energy Act decommissioning, and LLW standards. The protects the public with an ample margin of agencies also cooperated in evaluating safety, as provided under the Clean Air Act. The groundwater protection, radioactive two agencies are coordinating rulemakings to contamination of sewage sludge, and other issues eliminate unnecessary dual regulation of airborne l and activities of mutual interest. The cooperative effluents of radioactive materials. At present, air l activities are generally governed by the March emissions of radionuclides from NRC-licensed 1
129 facilities, other than nuclear power plants, are decided to exclude NRC and Agreement State subject to regulation by the EPA under 40 CFR licensees from the scope of its rulemaking. Part 61, Subpart I. (The EPA rescinded Subpart I for nuclear power plants on September 5,1995.) Cooperation with the DOE during FY 95 was In March 1995, the NRC and the EPA reached a limited in waste management program areas other general agreement on the,mechamsms for than uranium mill tailings and HLW. Although rescinding Subpart I for heensees other than the NRC is cooperating in the DOE's power reactors.,Specifically the EPA agreed to development of its " Programmatic Environmental resemd its existmg regulations in 40 CFR Part 61, Impact Statement on Managing Treatment, Subpart I, if the NRC amends 10 CFR Part 20 to
, , Storage, and Disposal of Hazardous and add a 10-mrem /yr ceiling for air emissions of Radioactive Waste", the NRC declined radionuclides. The proposed NRC rule will be opportunities for early review of drafts because of ;
published for comment by the end of calendar budget limitations and higher priorities. The NRC ! year 1995. The EPA will take final action t did, however, provide cost estimates regarding resemd Subpart I for heensees other than power external regulation of various DOE activities to reactors as soon as practicable after the 10 CFF- the Advisoty Committee on External Regulation Part 20 rulemaking becomes final. at the end of the year. In addition, the agencies l continued to share information related to The NRC is also conducting an enhanced remediation of radioactively contaminated sites, participatory rulemaking on radiological criteria storage of greater-than-Class C radioactive waste, for decommissioning, and the EPA plans to and risk harmonization activities through publish a similar proposed cleanup rule in early ISCORS. 1996. The NRC and the EPA have actively cooperated by exchanging information and jointly evaluating technical methods necessary to support and implement the radiGogical criteria in these two proposed rules. The proposed NRC rule INTERNATIONAL COOPERATION amending 10 CFR Part 20 was published in the FedemlRegisterin August 1994. The NRC staff assisted the IAEA in the development of preliminary guidance on LLW The NRC staff is also cooperating with the EPA , regulatory mfrastructures for developing in its development of residual radioactivity , countries. In addition, the NRC actively 4 standards. The EPA circulated a pre-proposal Participated in the IAEA's International Nuclear craft of those standards in May 1994. Many of the , Waste Advisory Committee by reviewmg and same issues raised in the public comments on the approvmg international standards, guides, and NRC's proposed rule were raised regarding the safety fundamentals as part of the RADWASS EPA's draft standards. The objective of the Program. The IAEA Board of Governors interagency discussions is to allow the EPA to approved the RADWASS Safety Fundamentals 4 find that the NRC's requirements provide , for radioactive waste m February 1995, and the sufficient protection of the public and the Advisory Committee recommemied approval of environment. On the basis of such a finding, the standards for LLW d,sposal i in May 1995. The EPA would exclude NRC and Agreement State NRC also participated on the U.S. Government licensees from the scope of its standards. team in the planmng and initial negotiations for developing an international convention on In December 1994, the EPA staff released a radioactive waste management. The RADWASS pre-proposal draft of its " Environmental Safety Fundamentals provide the basis for Standards for the Management, Storage, and initiating the convention, which will be negotiated Disposal of Low-Level Radioactive Waste" for over the next several years with administrative comment by interested parties. The EPA and support from IAEA. The staff also briefed a NRC staffs met to discuss NRC comments on number of visitors from foreign countries on the these standards. After reviewing the comments NRC's regulatory program for LLW management received on the pre-proposal draft, the EPA and related topics.
130 i l I DECOMMISSIONING OF NUCLEAR Site Decommissioning Management FACILITIES Plan (SDMP) The NRC developed the SDhiP in 1990 to focus During FY 95, the NRC staff continued to on identifying non-routine decommissioning cases ! develop the guidance that both NRC licensing and ensuring that generic, as well as case-by-case, staff and licensees will need to implement the issues affecting the timely decommissioning of , Commission's regulations with respect to these contaminated sites receive the appropriate i decommissioning nuclear facilities. The staff is level of management attention. The SDhfP has i also performing decommissioning reviews for both been effective in ensuring coordination and materials facilities and nuclear reactors. resolution of policy issues affecting site decommissioning. A draft revision to the SDhfP was published in FY 95. Three sites were removed from the SDhiP list in REGUL'ATIONS AND GUIDANCE FY 95. These m, elude United Nuclear Corporation I (UNC), West Lake Landfill, and United In addition to suporting development of Technologies /Pratt & Whittney. A fourth site, ; rulemakings on radiological criteria for hiagnesium Elektron, was removed from the i decommissioning and clarification of NRC's SDhfP lis,t shortly after the end of FY 95. financial assurance requirements, during FY 95, Remediation was successfully completed at the the NRC staff completed the development of the UNC and United Technologies sites, allowmg draft BTP on " Site Characterization for rele se of the sites. However, the oversight 1 Decommissioning." In addition, the DWhi responsibility for remediation of the West Lake ' sponsored a workshop on this topic, which was Landfill site was deferred to the EPA under the attended by licensees, the DOE, Agreement State Comprehensive Environmental Response, regulators, industry groups, and other interested Compensation, and Liability Act, commonly referred to as SuperFund. The NRC took a partie.s. Response to the workshop was very , , p siti m similar action at the E.I. DuTont site in Newport, Delaware, and declined to add the site to the SDhiP. With regard to the Magnesium Elektron site in Flemington, New Jersey, the NRC d(termined that the site did not contain licensable MATERIALS DECOMMISSIONING quantities of source material. Consequently, hiagnesium Elektron was not required to obtain an NRC license or to decommission the site The NRC terminates several hundred materials according to NRC requirements. licenses each year, and the majority of NRC-licensed operations result in little or no At the close of the FY 95, the NRC terminated contamination of buildings or soil. Consequently, the special nuclear material license covering the decommissioning actions leading to termination UNC site at Wood River Junction, Rhode Island, of most licenses normally proceed in a routine and removed it from the SDMP. UNC had fashion. Nonetheless, over the past several years, previously reduced radioactive material the NRC has recognized the need to strengthen its contamination at the site to levels acceptable for decommissioning program, particularly for unrestricted release. However, license termination non-routine cases. These non-routine cases involve was made possible in late 1994, when UNC and sites where buildings, former disposal areas, large the State of Rhode Island Department of piles of tailings, groundwater, and soil are Environmental Management (RIDEM) signed a contaminated with low levels of uranium or consent agreement under which RIDEM, a l thorium (source material) or other radionuclides, governmental body with jurisdiction, would l Consequently, they present varying degrees of continue monitoring the site groundwater for i radiological hazard, cleanup complexity, and nitrate contamination. The NRC staff then held a associated cost. public meeting, and prepaied an environmental
1 l 131 assessment in support of license termination with Contaminated Sites." The GAO report contained a finding of no significant impact. no recommendations, however, it did identify several findings, concerning the SDMP including, Decommissioning has essentially been completed among others, that the NRC does not precisely at two additional sites. Specifically, these sites are know the number of formerly licensed sites that the facility Babcock and Wilcox (B&W)in Apollo, contain residual contamination above current Pennsylvania, and the Aluminum Company of criteria, and that progress has been slow on America in Cleveland, Ohio. Limited surveys or decommissioning sites with large volumes of other administrative activities need to be uranium and thorium contamination. The staff completed before these sites can be removed from agreed with the basic findings of the report, but the SDMP list. For example, at the B&W Apollo provided several comments to the GAO for i site, a 1-year period of groundwater monitoring additionalinformation and clarification. ! was required after decommissioning activities were completed. This 1-year period expires at the Concerning formerly licensed sites, the staff end of CY 1995. completed its review of all files for licenses terminated and archived before 1985. The staff is Portions of two other sites, Cabot (Reading, currently reviewing the files for licenses Pennsylvania) and Northeast Ohio Regional Sewer terminated before 1985, but archived in later District (Cleveland, Ohio), have also been years. The staff also plans to review files for decommissioned and released for unrestricted selected licensees terminated after 1985. As a use. Each will remain on the SDMP list until the resuk of this review,24 licenses at 26 sites have entire site is decommissioned. been identified so far as having residual conta.mination at levels that require further Of the 51 sites currently listed in the SDMP,35 characterization and remediation. Of those 26 l have completed all or part of the required site sites,5 have been added to the SDMP program, l characterization. In many cases, this activity and 4 have been released for unrestricted use included staff review and approval of after remediation. The NRC will determine characterization plans. After characterization,19 whether additional surveys or characterizations of the sites submitted decommissioning plans for are needed at the remaining sites and what all or part of the site; the NRC has approved 14 of organization is responsible for any needed work. these plans. By May 1997, four additional sites are The NRC notified the owners of the sites that had scheduled to be removed from the SDMP. been reviewed, and were either cleared from the need for further NRC review or found to be During FY 95, the NRC added six sites to the contaminated in excess of NRC release criteria. SDMP including AAR Manufacturing,Inc. (Livonia, Michigan), Clevite Corporation During FY 95, the DWM also conducted (Cleveland, Ohio), Fromme Investment Company workshops to acquaint the NRC staff with (Detroit, Michigan), Horizons, Inc. (Cleveland, requirements and guidance for financial Ohio), Jefferson Proving Ground (Madison, assurance, describing the various mechanisms Indiana), and Kaiser Aluminum Specialty that the NRC has found acceptable, and Products (Tulsa, Oklahoma). (These additions are summarizing NRC and other agency experience in described in a Commission Paper (SECY 95-209) reviewing and implementing financial assurance and Supp:ement 1 to NUREG-1444. Of these six mechanisms. sites, five were added as a result of the NRC's review of previously terminated licenses. (This The NRC issued Inspection Manual Chapter 2602, review is discussed later in this section.) " Decommissioning Inspection Program for Fuel Cycle Facilities and Materials Licensees," on June 6,1995. This new manual chapter formally Program Improvements establishes the general policy for the decommissioning inspection program, and In April 1995, the U.S. General Accounting Office provides guidance for inspections of fuel cycle (GAO) issued a report entitled, " Slow Progress in and materials licensees undergoing Identifying and Cleaning Up NRC Licensees' decommissioning. The staff is currently preparing
i 132 l l 1 separate inspection procedures, consisting of and assessing decommissioning issues. Several detailed instructions for inspectors. additional EISs are anticipated in FY 1996. The DWM staff initiated plans involving the The NRC is currently reviewing various policy NRC's radioanalytical capabilities to support issues related to the timely decommissionmg of decommissioning and 6*her agency programs. As SDMP sites. These issues include concentration part of the agency's independent radiochemical averaging, assumptions for exposure assessment scenarios, coordination with States and other measurements program for nuclear power reactors, the NRC has established both fixed and Parties, generic conclusions on disposal of mobile radiologic laboratories in each of the four u,ranium and thorium (based on the results of regions. As a result of bu4et constraints, site-specific EISs) and greater reh,ance on maturation of industry measurement programs, institut,onal i controls. Any staff proposals to and competing priorities, the NRC is planning to sigmficantly modify current policy in these areas reduce the need for independent raGological will be forwarded to the Commission for measurements. The DWM is working with consideration. headquarters and regional offices to develop a
, Finally, the staff undertook five initiatives to systematic plan to reduce current capabilities,, improve the effectiveness and accountability of while prepanng to meet future agency needs in
, , , the SDMP program, including-this area. This planning was mitiated near the end of FY 95 and recommendations will be completed (1) developing standardized Agency-wide and submitted for management review in early procedures for decommissioning; 1996.
(2) revising SDMP program performance Sites contaminated with large volumes of uranium measures; and thorium pose special problems because of the environmental impacts and costs associated with (3) coordinating with industry to develop a the decommissionmg alternatives. Many licensees process for interactive resolution of prefer to stabihze these materials on site. Under decommissioning issues- ' the existing program, the NRC considers such (4) developing a database, accessible to all NRC proposals through the development of an project managers, for SDMP site information; environmental impact statement (EIS) in and accordance with the National Environmental Policy Act and NRC requirements in 10 CFR (5) stabilizing NRC SDMP project manager Part 51. The development of an EIS typically assignments. requires several years. EISs are currently under development for four SDMP-sites (Shieldalloy. These initiatives are discussed in greater detail ir. Cambridge, Shieldalloy-Newfield, Babcock and a Commission Paper, SECY 95-209, " Policy and Wilcox Parks Township, and U.S. Army Jefferson Program Issues at Site Decommissioning Proving Ground). The NRC conducted public Management Plan Sites," which was published as scoping meetings on the Parks Township and Supplement 1 to NUREG-1444. Jefferson Proving Ground sites in January and , April 1995, respectively. Notice of the NRC's ' intent to develop a fifth EIS (for Sequoyah Fuels Corporation-Gore) was issued at the close of the REACTOR DECOMMISSIONING FY 95. In conjunction with the EISs, the NRC has initiated public information roundtable meetings In March 1995, NMSS and NRR completed a to provide a sustained, meaningful opportunity for Memorandum of Understanding on the discussion of decommissioning issues in the coordination of reactor decommissioning and communities around sites that have been spent fuel storage activities. Under the terms of proposed for onsite disposal of radioactive waste, the agreement, project management responsibility These roundtable meetings have been effective in is transferred to NMSS once the spent fuel has conveying information to participants and been permanently removed from a reactor's spent engaging their active participation in identifying fuel pool. The agreement also provides for NRR
=============m- 133 retention of project management responsibility for This processing resulted in a significant reduction decommissioning non-power reactors. in waste burial volume from the pre-decommissioning estimate of over 80,000 cubic The DWM currently has regulatory responsibility feet to 8,300 cubic feet (after volume reduction).
for three former nuclear power plantr that are . now being decommissioned, incluMag Fort St. On April 11,1995, the NRC issued an order that Vrain (Colorado), Peach Bous.a Unit 1 modified the order of June 11,1992, which (Pennsylvania), and Enrico Fermi Unit 1 originally authorized the Long Island Power (Michigan). The DWM exercises project Authority to decommission the SNPS. The management oversight for the facilities and, along modifying order terminated License No. NPF-82 with the regions, conducted regularly scheduled and released the site for unrestricted use. The inspections of these facilities during 1995. environmental assessment and the finding of no e significant impact were published in the Fedeml At the end of FY 95, Public Service of Colorado Registeron April 10,1995 (60 FR 18154), and the was completing the dismantlement of concrete modifying order became effective on May 1,1995. structures at the Fort St. Vrain plant, performing termination surveys, and decontaminating the site. Decommissioning is expected to be completed in early 1996. The Peach Bottom and Fermi plants are currently m long-term storage (SAFSTOR MANAGEMENT OF decommissioning) before the facility's URANIUM RECOVERY AND disraantlement. DWM also had regulatory responsibility over the Shoreham Nuclear Power Station (SNPS)in New The NRC staff in the uranium recovery and mill York, which completed decommissioning this tailings program license and regulate uranium year. Because the plant had operated the mills, commercial in-situ solution mining equivalent of only two effective-full-power days, operations, uranium extraction research and the decommissioning of SNPS was confined development projects, and disposal of uranium primarily to the reactor, radwaste, and turbine mill tailings and wastes. This requires the detailed buildings. Radioactive materials were eliminated health, safety, and environmental review and from the facility by dismantlement and removal inspection of facilities to provide reasonable for disposal at a LLW disposal facility and by assurance of safe operation. It also requires decontamination in place. Dismantlement developing the NRC's regulatory guidance to activities were primarily confined to the reactor implement EPA standards for regulating mill and radwaste buildings. Minor dismantlement and tailings, and the site-by-site approval of licensee decontamination were carried out in the turbine plans for disposal of mill tailings. In addition, the building. Most major SNPS structures and NRC evaluates and concurs in DOE remedial systems were left intact. Activated portions of the action projects for inactive uranium mill tailings reactor biological shield wall that exceeded NRC sites and associated vicinity properties, as release criteria were removed. Systems and required by Title I of the Uranium Mill Tailings equipment removed included the reactor pressure Radiation Control Act of 1978 (UMTRCA). vessel (except for the lower head) and major portions of the plant systems that were Of 27 NRC-licensed uranium recovery facilities, characterized as being radioactively 19 are uranium milis,5 are in-situ leach facilities, contaminated. Reactor control rods, fuel channels, 1 is an ion-exchange facility,1 is a heap leach, and and fuel storage racks were removed intact and 1 is a mill tailings waste disposal facility. At the shipped directly to the LLW disposal facility in close of the FY 95, three commercialin-situ Barnwell, South Carolina. A majority of mining operations were in operation, two were i radioactively contaminated piping and equipment licensed to operate but were not operating, and that was dismantled and removed from the facility two were under construction. One conventional was sent to an offsite vendor for volume reduction uranium mill was in operation, one was processing. Over four million pounds of piping processing mine water, two were in standby, and and equipment were processed in this manner. the remainder were in decommissioning and
134 t I l reclamation. If the market price of uranium first dealt with disposal, in a uranium mill tailings remains low, no new conventional mills are impoundment, of radioactive material that is expected to be licensed'soon, and the standby similar to, but does not meet the definition of, l mills are likely to resume operations only for short byproduct material defined in Section 11e.(2) of l runs. However, in-situ solution mining facilities the Atomic Energy Act.The second guidance are expected to remain moderately active, with document addressed the processing of material two applications currently under licensing review. other than natural ore for its uranium content. l Over the next few years, much of the casework After reviewing the many, varied comments confronting the Uranium Recovery Program will received, the NRC published final guidance on be in the area of remedial activity for the these two issues in September 1995. shutdown facilities, including decommissioning of mills, reclamation of mill sites and tailings In June 1995, the NRC finalized reclamation disposal areas, remediation of groundwater plans, previously approved by NRC staff, to l contamination, and environmental assessment of stabilize uranium mill tailings. In 1990 and 1991, such activities, the NRC staff requested that uranium mill licensees with previously approved reclamation 1 During FY 95, the NRC staff held three meetings plans evaluate their designs to determine if they with representatives of the industry and States to complied with staff guidance related to erosion review the status of general uranium recovery protecdon and radon barrier design. The staff issues. The NRC staff plans to continue holding guidance was developed to eliminate some such meetings three times a year, including a large inconsistencies in the review of erosion protection workshop in spring. and radon barrier design. Because some sites were reviewed without the benefit of formal guidance, the staff was concerned that the reclamation plans might not meet NRC requirements REGULATORY DEVELOPMENT e NRC has since determined that reclamations, performed m conformance with AND GUIDANCE plans approved by the staff, also meet the UMTRCA requirement that all applicable
. standards and requirements be met at license Durm.g FY 95, the NRC contmued to develop termination. As a result, the NRC will not revisit regulatory guidance to implement standards previously approved reclamation plans unless deahng with groundwater. The use of ahernat.ive certain conditions (primarily related to significant concentration limits (ACLs) for contammants in public health, safety, or environmental concerns) groundwater has been an area of interest to both are identified' the licensed mills and the DOE inactive mill tailings remediation program. ACLs are one of three options for demonstrating compliance with EPA and NRC groundwater protection standards. LICENSING AND INSPECTION The other two options are maximum concentration limits and background levels. In ACTIVITIES March 1994, the NRC staff issued a revised draft technical position on ACLs for uranium mills. A In FY 95, the NRC completed the license renewal major issue, which was unresolved at that time, for the Highland Uranium Project in-situ leach was the appropriate level of risk to use in facility operated by Power Resources, Inc., near evaluating ACLs. In September 1994, the NRC Glen Rock, Wyoming. The renewal incorporated and EPA reached agreement on this issue. In the new performance-based license condition, January 1995, interim guidance was issued to the which allows the licensee to evaluate and l staff on the appropriate risk level to use in ACL implement changes to facility operations through l reviews. The staff expects to issue the final a Safety and Environmental Review Panel (SERP) technical position in FY 96. without prior NRC approval. The licensee documents any changes made by the SERP, which l In 1992, the staff published two proposed are then inspected by NRC during routine facility guidance documents for public comment. The inspections. The performance-based license
135 condition is modeled after the NRC's regulation In support of UMTRA Project casework, the staff in (10 CFR 50.59) for reactor licensing. visited many,of the sites. Inspections of remed;al action in progress and/or site visits associateu In FY 95, Region IV performed 32 inspections of with NRC staff reviews were conducted at the uranium recovery facilities; each site was sites in Gunnison, Colorado; Salt Lake City, Utah; inspected at least once. During the FY, the NRC Green River, Utah; Falls City, Texas; Ambrosia issued 62 license amendments. Lake, New Mexico; Rifle, Colorado; Lakeview, Oregon;'Ibba City, Arizona; Maybell, Colorado; Naturita, Colorado: Slick Rock, Colorado; and Grand Junction, Colorado. REMEDIAL ACTION AT INACTIVE l Activities for the groundwater remediation phase l SITES of the UMTRA Project continued during FY 95. The initial site observational work plans (SOWPs) Under UMTRCA,24 abandoned uranium mill for this phase of the UMTRA Project have been ; tailings sites have been designated to receive submitted for the NRC's information review. The remedial action by the DOE. UMTRCA requires NRC is currently reviewing SOWPs for sites in the that the NRC concur with the DOE's selection Ambrosia Lake, New Mexico; Falls City, Texas; and performance of remedial action, such that the Riverton, Wyoming; and Spook, Wyoming. These , action mcets appropriate standards promulgated work plans identify the quantity and quality of I by the EPA. The DOE has established the available groundwater data at the sites, and UMTRA Project to implement the remedial identify any additional data needs for developing actions. These sites will be held by the DOE groundwater restoration programs at the sites. 4 under an NRC general license for long-term care, ) when all remedial work is completed. During FY 95, the NRC staff completed 36 review actions pursuant to its responsibilities at sites ADVISORY COMMITTEE under Title I of UMTRCA. These include,d three mspection plan reviews, two re nedial action plan ON NUCLEAR WASTE ! (RAP) reviews, six RAP modification reviews,13 other site-specific reviews, eight completion / The Advisory Committee on Nuclear Waste certification report reviews, and one review of a (ACNW) was established by the Nuclear generic item. The staff also prepared two Regulatory Commission (NRC) in 1988. The completion review reports documenting its review ACNW reports to and advises the NRC on of the DOE's completion of remedial actions for nuclear waste disposal facilities, as directed by sites in Riverton, Wyoming, and Canonsburg, the Commission. This includes 10 CFR Parts 60 Pennsylvania, and 61 and other applicable regulations and legislative mandates such as the Nuclear Waste The submittal of a site-specific long-term Policy Act, the Low-Level Radioactive Waste smveillance plan (LTSP) for NRC approval is one Policy Act, and the Uranium Mill'Ihilings of the final actions the DOE must take before a Radiation Control Act, as amended. The primary site comes under the NRC general license for emphasis is on disposal facilities. In performing long-term care under 10 CFR 40.27. During FY its work, the committee will examine and report 95, the DOE submitted, and the NRC staff on those areas of concern referred to it by the reviewed one LTSP. That review resulted in final Commission or its designated representatives, and acceptance of the LTSP for the site in Lakeview, will undertake other studies and activities related Oregon, making that site the fourth UMTRA to those issues as directed by the Commission. Project site accepted under the NRC general license for long-term care. (The site in Spook, ACNW reports, other than those that may contain Wyoming site was the first site subject to the classified material, are made part of the public general license in 10 CFR 40.27, followed by the record. Activities of the committee are conducted sites in Lowman, Idaho, and Burrell, in accordance with the Federal Advisory Pennsylvania. Committee Act, which provides for public
136 attendance at and participation in committee e The NRC research program on the meetings. The ACNW membership is drawn from Engineered Barrier System scientific and engineering disciplines and includes individuals experienced in geosciences, risk e EPA's Preproposal Draft of 40 CFR Part 193 assessment, radioactive waste treatment, and the NRC's Proposed Radiological environmental engineering, nuclear engineering, Criteria for Decommissioning e Issues related to guidance on 10 CFR 60 During fiscal year 1995, the ACNW reported to groundwater travel time regulations the Commission on a variety of issues, e Regulatory issues in low-level radioactive mcluding- , waste disposal performance assessment i . o Impact of the Department of Energy's e Lesson-learned from the Ward Valley, l Proposed Program Approach on the NRC's California, low-level waste disposal facility high-level radioactive waste licensing siting process activities e Streamlining the Site Decommissioning o Private ownership of low-level waste sites Management Plan Program In performing the reviews and preparing the o Regulations pertaining to contaminated steel reports cited above, the ACNW holds working smelting facilities and disposal of group meetings as needed, and full committee contaminated baghouse dust meetings regularly throughout the year. l l 1 l l
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lf k_ !' l l%as& *l WkV;Q' 'y' E i; COMMUNICATING WITH . THE PUBLIC AND THE GOVERNMENT The Nuclear Regulatory Commission maintains groups, petitioners, industry groups, the Congress, regular communication with a broad range of and licensees. The Report of the National governmental entities and with the general public. Performance Review placed new emphasis on Several NRC Headquarters Offices and the Federal agencies "to put the customer first." Regional Offices participate in the dissemination Consistent with this recommendation, the NRC of information about NRC activities. Com- initiated a variety of activities to augment its missioners and senior managers frequently take public responsiveness. Improvements in serving part in Congressional Hearings (see table on page the public were made in mission-related activities 147), and appropriate Congressional Committees such as rulemaking, emergency preparedness, are kept regularly and fully informed of NRC management of allegations, materials licensing, decisions and actions. Liaison with the general Agreement States and decommissioning. public, the Congress, Federal and State agencies, Administrative improvements focused on areas Indian Tribes, local community organizations, and such as contracting, correspondence, electronic the news media is maintained mainly through four information, public meeting notices, and offices of the NRC: the Office of the Secretary, responses to license fee inquiries. These initiatives the Office of Congressional Affairs, the Office of were documented in a draft report, " Responsive-Public Affairs, and the Office of State Programs. ness to the Public"(NUREG/BR-0199), published (The NRC's international programs and in March 1995. After assessing and responding to exchanges are carried out through the NRC Office public comments, the final report was published of International Programs, whose activities are in January 1996. covered in Chapter 8.) In a separate effort to improve the agency's responsiveness to the nuclear industry, the Commission in July 1995 endorsed a policy statement on maintaining open lines of COMMUNICATION WITH communication between NRC staff and licensees. THE PUBLIC w Comn? ssion i mognized "that honest, well-intentioned differences , of opimon between the staff and a licensee will occasionally occur and encouraged open communications for constructive and prompt resolution. PUBLIC RESPONSIVENESS INITIATIVES S.mce its m.eeption, the Nuclear Regulatory COMMISSION MEETINGS Commission has sought to conduct its business activities in an open and public manner. The The NRC Commissioners meet to discuss agency public includes individual citizens, public interest business in the Conference Room of the NRC
140 Headquarters building, located at One White Commission discussions at open meetings. It is Flint North,11555 Rockville Pike, Rockville, also the Commission's practice to allow camera Maryland. Members of the public are welcome to and television coverage of open meetings and attend and observe most Commission meetings. briefings without prior notification. In addition, in However, a Commission meeting may be closed to October 1995, the Commission began to make the public if it is convened to deal with one or available video tapes of staff briefings for more subjects specified in the Sunshine Act. reviewing and copying in the PDR. Specifically, the Sunshine Act allows the closing of meetings involving classified documents, In all cases, the Commission attempts to provide information deemed confidential by statute, trade advance notice at least 1 week before Commission secrets, investigations, adjudicatory matters, meetings. Notice of the next 4 weeks of internal personnel matters, matters involving Commission meetings is published each week in personal privacy, or similar information. Members the Fedeml Register, an electronic copy is posted of the public attend Open Commission sessions on the FedWorld Bulletin Board, and copies are as observers, but they may not actively participate distributed over the Internet. Notice of meetings unless specifically requested to do so by the is also given to the press through the wire services Commission. During fiscal year 1995 (FY 95) the and by mailings to individuals who have i Commission held 69 meetings that were cpen to requested such notice. Commission meetings are public observance. also regularly announced on a recorded telephone l message (301-415-1292), providing the schedule i The Commission endeavors to provide meaningful f r upc ming Commission meetings and voting, sessions. In addition, an announcement is public observation and understanding of open , 1 meetings. The Commission's Headquarters displayed on a television momtor in the lobby of j Conference Room is equipped with multiple NRC Headquarters, and is posted in the PDR. overhead speakers and a closed-circuit television The announcement discloses the time, place, and system to ensure that every person desiring to subject matter of the meetm, g: states whether it is attend a meeting can see and hear the proceeding. an pen r closed meet,mg; and gives the name A pamphlet entitled " Guide to NRC Open and telephone number of an official designated to Meetings" is available in the Conference Room respond to requests for mformation about the m eting. and in the Public Document Room (PDR) located j at 2120 L Street, N.W., Washington, D.C. The guide describes the normal seating arrangement l for participants at the conference table, the ADVISORY COMMITTEES l general functional responsibilities of these i participants, Commission procedures for voting The NRC engages the expertise and experience of l on agenda items, general rules for pubhc conduct a wide segment of the public through their service I at Commission meetm, gs, and sources o[ on the Commission's standing advisory additional information on the Commission and its committees and on its ad hoc committees. meetings. A Handbook of Acronyms and Initialisms (NUREG-0544, Rev. 2)is also Members of NRC committees are drawn from a broad cross-section of the scientific and technical available m the PDR to define and explain the . communities, as well as from State and local many' techmcal abbreviations used in Commission governmental organizations, the National meetmgs and papers. Congress of American Indians, and private l citizens. Committee mcmbers provide advice and Copies of viewgraphs and the principal staff recommendations to the NRC on a wide range of papers to be considered at open meetings are issues affecting NRC policies and programs. normally made available at the entrance to the Appendix 3 briefly states the purpose of each Conference Room before the meeting commences. NRC standing advisory committee, and lists the At the conclusion of each open meeting, a names and affiliations of current members. transcript of the meeting is placed in the PDR for inspection and copying, along with any papers In accordance with the requirements of the made available to the public at the meeting. The Federal Advisory Committee Act, NRC advisory public is also permitted to tape record committees meet in public sessions at
141 Headquarters locations and in venues throughout need assistance accessing the public meeting the United States. Notice of advisory committee database, or care to leave comments. Messages meetings is published in the Federal Register and are responded to within 24 hours. In addition, the in NRC press announcements. Notice of meeting telephone recording, the BBS, and the reports 4 dates and topics is also posted on the FedWorld posted in the PDR and LPDRs contain the name Bulletin Board and in the NRC PDR. Transcripts and phone number of the NRC meeting contact and minutes of meetings are also available for should a member of the public need additional inspection and copying at the NRC PDR. Persons information on an upcoming meeting, interested in committee meetings or the activities 1 of a particular committee may write to the NRC l Advisory Committee Management Officer Office i of the Secretary, Washington, DC 20555, or call HEADQUARTERS PUBLIC 301-415-1968. DOCUMENT ROOM Serving as a bridge between the agency and the public, the Headquarters PDR maintains a PUBLIC MEETING NOTICE comprehensive collection of unrestricted ! SYSTEM documents related to NRC licensing proceedmgs 1 and other significant decisions and actions, as l well as documents from the regulatory activities of In FY 95, the NRC revised its long-standing open the former Atomic Energy Commission. The meeting policy to further the goal of providing computerized, online Bibiiographic Retrieval 1 meaningful opportunities to inform the public of System (BRS) includes extensive indices to the j NRC activities without unduly affecting open and collection, as well as an online module for I candid discussions between heensees and the ordering the reproduction and delivery of specific NRC staff or interfering with the staff's ability to documents. During FY 95, the Commission exercise its regulatory and safety responsibilities enhanced the BRS to include full electronic text without undue administrative burden. The Final for selected materialin a number of categories; Policy Statement on Staff Meetings Open to the this information is also made available through an Public, dated September 14,1994, was published electronic bulletin board (FedWorld). Located at in the Federal Register on September 20,1994 (59 2120 L Street, N.W., Washington, D.C., the PDR is FR 48340). A toll-free telephone recording open Monday through Friday (e.xcept Federal announces upcoming public meetings, and a holidays), from 7:45 a.m. to 4:15 p.m., eastern toll-free electronic bulletin board system (BBS) time. However, the BRS is available through contains searchable information on each meeting. dial-up access 24 hours a day,7 days a week. The telephone recording accommodates multiple concurrent users. The telephone re-cording and the Persons interested in detailed, technical BBS are operational 24 hours a day. On information about nuclear facilities and other November 1,1994, centralized agency services licensees find this specialized research center to became available to the public for obtaining be a major resource. With some exceptions, schedules for the staff meetings that are open to documents from the collection can be reproduced the public. on paper, microfiche, or diskette, for a nominal fee. The PDR also offers a Standing Order More than 1020 open staff meetings were Subscription service for automatic mailing of announced during the first year of the new policy. selected serially published documents and reports. In addition, as of January 1996, Commission and Certain items of immediate interest, such as press Advisory Committee meetings and Atomic Safety releases and meeting notices, are posted in the and Licensing Board hearings that are open to the Reading Room at the facility. public will be announced on the Public Meeting Notice System. The wide variety of agency documents available to the public at the PDR include NRC NUREG-People using toll-free telephone recording and the series reports; transcripts and summaries of toll-free BBS can also leave messages should they Commission meetings and NRC staff and licensee
l 142 l meetings; existing and proposed regulations and agency's international safety cooperation rulemakings; licenses and amendments; and arrangements. correspondence on technical, legal, and regulatory matters. Most of the documents relate to the design, construction, and operation of nuclear power plants, and to nuclear matenals, meludmg LOCAL PUBLIC DOCUMENT ROOM the transportation and disposal of radioactive PROGRAM wastes. The PDR does not contain books, journals, trade publications, or documentation of Through the local public document room (LPDR) industry standards. program, citizens living or working near nuclear
. power reactors and certain other nuclear facilities Through its comprehensive document release have access to the records used by the NRC in pohcies, the NRC has made available rnore than I censing and regulating those local facilities.
two milh,on documents for pubhc viewmg and Appendix 4 presents a complete list of NRC's copying in the Headquarters PDR since its LPDRs' establishment in 1975. During a typical month, the PDR serves about 1300 documented users. LPDR collections are maintained in academic, I Technical reference librarians are available to public, and State libraries having evening and assist onsite users and those who call or write weekend hours. The NRC's LPDR program staff with information requests. has daily contact with the public and with local librarians and assists them in locating records in Persons wishing to visit and use the PDR or to the collections. obtain additional information regarding the PDR may call 202-634-3273 or 1-800-397-4209, Because the NRC converted the site-specific Monday through Friday, between 8:30 a.m. and paper collections to microfiche several years ago, 4:15 p.m. (eastern time); send a facsimile to the public now has local access to more than 1.5 202-634-3343; transmit electronic mail to Internet million records released by the NRC since 1981. address PDR@NRC. GOV; or write to the U.S. These records include information on all Nuclear Regulatory Commission, Public NRC-licensed facilities as well as NRC staff and Document Room, Washington, DC 20555-0001. In contractor publications, rulemaking documents, addition, the PDR staff make the BRS database and generic issues. Online access to a database of i available to the public either onsite (using publicly available records is currently provided to terminals in the Reading Room) or offsite (via 44 power reactors and 2 high-level waste LPDRs. modem). Offsite access (at 1200,2400, and 9600 Toll-free searches can be conducted each business baud)is available for searches 24 hours a day,365 day, from 7 a.m. to 8 p.m. Eastern time. Records days a year, through a toll-free (800) number, identified in searches can be viewed and copied j Access to the BRS may be ananged by calling the from microfiche records at each LPDR. telephone numbers previously given. Procedures for use of the system may be learned either through an online tutorial or through onsit personal instruction. The NRC segment of ' COMMISSION IIISTORY PROGRAM FedWorld may also be accessed from terminals in the PDR Reading Room. Through the Commission History Program, the origins and evolution of NRC regulatory policies l The PDR/BRS users' group comprises members are explored and set forth in their historical of Congressional staffs, personnel from other context. Research on the evolution of these Government and State agencies, foreign policies is drawn from the archives of a number embassies and governments, law firms, utilities, of Government agencies, the personal papers of consulting firms, public interest groups and other former Government officials and others involved institutions, media representatives, and individual in regulatory issues, and personal interviews. The ! members of the public. In addition, the PDR History Office is currently conducting research l provides the BRS document delivery, and a for the third volume of a detailed, scholarly general reference service to foreign nuclear history of nuclear regulation. The first volume, regulatory organizations who participate in the Controlling the Atom: The Beginnings of Nuclear
143 Regulation, 1946-1962, appeared in 1984. The and the public may now obtain news releases second volume, Containing the Atom: Nuc/ car electronically for significant agency policy Regulation in a Changing Environment, 1963-1971, decisions, workshops, or rulemaking activities. On appeared in 1992. Both were published by the the day ofissuance, PA also sends news releases University of California Press. The volumes are to reporters by facsimile or Internet electronic intended to serve as historical references for the mail. In addition, PA affords the public worldwide agency staff and the general public. A brief access to NRC news releases not only by mail, but summary of the books and the period after 1971is also through the Internet and a toll-free electronic available in "A Short History of Nuclear bulletin board that is part of FedWorld. Regulation, 1946-1990" (NUREG/BR-0175), which is available from the fiovernment Printing Office In addition to news releases, the agency's (GPO), electronic bulletin boards enable reporters and the public to access key documents and other information. Information available from that NRC Office of Commission Decision online service includes schedules of more than 1000 NRC staff meetings with licensees, proposed 'IYacking System Project rulemakm, gs, genen,c commumcations to heensees In hiay 1994, the Commission established a (such as bulletins and generic letters), and temporary project staff to identify and collect key operating nuclear power plant information. policy issues in 29 areas of interest, and to incorporate these issues into an automated, online For responses to general inquiries, PA continues system known as the Commission Decision to develop and distribute fact sheets, brochures, Tracking System (CDTS). The purposes of the and pamphlets that address such topics as the j CDTS are two-fold. First, the CDTS supports the NRC s mission, nuclear waste disposal, hcensmg j reference needs of the Commission and its senior of nuclear power plants, radiation protection, I staff by providing quick access to key documents Pl utonium, and the process by which the public ; pertaining to subjects of special interest. Second, may petition the agency to take enforcement the CDTS preserves the NRC's historical policy action against violators of NRC requirements. decisions, giving its staff and Commissioners ready access to the facts and data available to their predecessors. The CDTS contains the NEWS CONFERENCES electrome text of 4,000 documents (80,000 pages) that have been key to Commission decisions in Each of the NRC's four Regional Administrators major policy subject areas. It also permits users to retrieve documents by subject, by issue within a conduct special periodic briefings. During FY 95, sessions were held at Wilmington, Delaware; New subject area, or by document type, York City, New York; Portsmouth, New Mr. Chilk, the Secretary of the Commission, was Hampshire; Cordova, Illinois Cleveland, Ohio; initially asked to direct the CDTS project staff on Monroe, Michigan; the Crystal River nuclear a full-time basis. The CDTS Project Office was Pl ant'in Florida; the Browns Ferry plant in ; later disbanded on December 31,1995, and Alabama; the Watts Bar plant in Tennessee; and j responsibilities for the CDTS were assigned to the the Wolf Creek nuclear station in Kansas. Media Office of the Secretary, coverage focused on the performance of nuclear power plants, contaminated sites, dry cask storage of spent fuel, and enforcement actions. PUBLIC INFORMATION ENFORCEMENT CONFERENCES During fiscal year 1995 (FY 95), the Office of During FY 95, PA continued a trial program that Public Affairs (PA) increased the availability of its opened to the news media and the public selected press releases concerning important regulatory predecisional enforcement conferences with actions taken by the NRC. Both the news media material licensees and utilities operating nuclear
i 144 i power plants. This trial program will continue NRC's role as a regulator of nuclear safety as pending review in 1997, depicted in the following photograph. 4 i 4 SCHOOL VOLUNTEERS PROGRAM e s. i During FY 95, NRC volunteers renewed and ! expanded their goal of enriching the quality of i ~ public education. This year,140 employees- q % including chemists, engineers, geologists, and p
- attorneys-visited approximately 70 schools in the L .
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Students at Walter Johnson Iligh School proudly present l kb, their final project to NRC staff as part of the techaology and d research program. 66 To help volunteers save time in developing 1;- presentations to students, the NRC now has 10
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radiation (with actual household items containing i f minute amounts of radioactive materials), reactor i operations, transportation, risk assessment, safety considerations in siting and licensing nuclear waste facilities, and many other science and math Maudette Origgs from the Office of Nuclear Reactor topics that apply to the NRC and its mission. Regulation confers with a student about his science project at the ill Einstein-Kennedy-Springbrook liigh School For the fifth year, NRC Special Awards were given to six science students at the annual Montgomery Area Science Fair in Gaithersburg, Because of the success of the Headquarters' Maryland, shown in the first of the following three l program, each NRC Regional Office began its photographs. The winners were selected because own school volunteer program this year, their projects demonstrated scientific excellence encouraging volunteers to visit one or two schools and in some way were related to the NRC's in the vicinity of the Regional Office and perform multifaceted regulatory activities. The students activities being done by Headquarters employees. subsequently presented and explained their < winning projects to the Commissioners, interested - l The agency's program gives students an inside NRC employees, and their own parents. I look at the many career paths of NRC employees, and involves hands-on science and math demon- At Headquarters, the NRC also hosted and strations, mentoring and tutoring, assisting with participated in a Science and Technology Program science projects, and judging at science and math for Educators. To learn about the importance of fairs. This year, volunteers also served as mentors science and technology applications in the for a special program for learning-disabled and workplace,40 Montgomery County teachers spent gifted students. Coordinated by PA, the program 5 days teamed with scientists and other provides rewarding experiences for employees and professionals from area organizations such as students, while informing the public about the Holland Labs, TRW, Shady Grove Adventist
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NRC Special Award Winners for the l' air shown seated in the An NRC Special Award Winner presenting her project to the f Commission and fellow winners, j NRC Commission llearing Room, presenting their proje< ts j to the Commission. i i i Hospital, PEPCO, and Bell Atlantic. At the NRC, spent-fuel cask and the sitting of a low-level waste
- teachers toured the Emergency Operations disposal site. NRC volunteers also trained area l Center, and participated in problem-solving teachers with the portable classroom kits and exercises involving the transportation of a explained the NRC's mission and related
146 activities. The teachers subsequently incorporated NRC and Agreement State licensed facilities. The their experiences into classroom lesson plans. office's activities encompass three general areas: (1) The Agreement State Program (2) State, Local, and Indian Relations COMMUNICATION WITH '(3) Federai Liaison THE CONGRESS - These programs are implemented through the NRC Headquarters and Regional Offices. The Office of Congressional Affairs is responsible for developing, managing, and coordinating relations with the Congress, and is the principal point-of-contact between the agency and AGREEMENT STATES PROGRAM Congress. The office coordinates the appearances and testimony of all NRC officials at hearings, monitors and tracks bills relevant to the NRC, A total of 29 States have formal agreements with keeps the Congress mformed of current agency the NRC, under which those States have assumed activities, and keeps the NRC apprised of regulatory responsibility over byproduct, source, Congressional concerns and interests. and small quantities of special nuclear material (See map of The Agreement States). At the close of fiscal year 1995 (FY 95), approximately 15,000 During fiscal year 1995 (FY 95), NRC witnesses testified at 11 hearings before Congressional radioactive materials licenses were administered Committees and Subcommittees, as shown m the by the Agreement States, representing about 70 percent of all radioactive material licenses issued table. Congressional Affairs staff attended and in the United States. In addition, the States of prepared summaries and reports for Massachusetts, Ohio, and Oklahoma are actively approximately 50 hearings and markups. working to become Agreement States. The State of Pennsylvania also is negotiating a limited 4 agreement with the NRC, which will give Pennsylvania regulatory authority only the land disposal of byproduct, source, and small COOPERATION WITH 9"""""*"*'"'""#*"'""*"'"' STATES' INDIAN TRIBES $ Improving Cooperation With States AND OTHER FEDERAL Continuing the NRC's efforts to ensure early and AGENCIES substantialinvolvement of Agreement States in NRC rulemaking and other regulatory issues, the staff participated in a number of public meetings The NRC's program of cooperation with Federal, and workshops with States during the year. The State, and local governments; interstate use of electronic communication, via e-mail and organizations; and Indian Tribes is administered bulletin boards, has greatly facilitated the transfer primarily through the Office of State Programs of information, including announcements of (OSP). The goals of the office are two-fold. First, meetings and workshops of a regulatory nature; OSP ensures that the NRC maintains effective this resource has greatly facilitated the expanded relations and communications with these involvement of States in these procedures. Joint organizations. Second, the OSP promotes greater NRC-Agreement State Working Groups have been awareness and mutual understanding of the established to evaluate improvements in the policies, activities, and concerns of all parties general licensing of radioactive material and to involved, as they relate to radiological safety at develop implementation procedures for the Policy
147 Congressional Hearings at Which NRC Witnesses or Commissioner Nominees Testified or Submitted Testimony During FY 95 2 Date Committee Subject 01/19/95 Committee on Energy and Natural Resources North Korean Nuclear (Senate) Framework Agreement 02/16/95 Committee on Environment and Public Nomination of Works (Senate) Dr. Shirley Ann Jackson 02/16/95 Committee on Environment and Public Nomination of Works (Senate) Mr. Dan Berkovitz 02/24/95 Committee on Commerce, Subcommittee Privatization of U.S. on Energy and Power (House) Enrichment Corporation 03/02/95 Committee on Energy and Natural Resources High-Level Radioactive (Senate)-Testimony supplied for the record Waste Waste Legislation J 03/03/95 Committee on Appropriations, Subcommittee NRC's FY 96 on Energy and Water Development (House) Appropriation 05/16/95 Committee on Energy and Natural Resources High-Level Radioactive (Senate) Waste and Other Nuclear Issues 06/28/95 Committee on Commerce, Subcommittee on Interim Storage of Energy and Power (House) High-Level Radioactive Waste l l 07/12/95 Committee on Commerce, Subcommittee on High-Level Radioactive Energy and Power (House)-Testimony supplied Waste Legislation for the record 08/03/95. Committee on Environment and Public Nomination of f Works (Senate) Ms. Greta Joy Dieus 09/07/95 Committee on Science, Subcommittees on Regulation and Missions Basic Research and Energy and Environment of DOE National 4 (House)-Testimony supplied for the record Laboratories Statement on Adequacy and Compatibility of NRC, during fiscal year 1995, conducted three Agreement State Programs. kinds of reviews: (1) routine reviews Review of State Regulatory Programs (2) review visits The Atomic Energy Act .)f 1954, as amended, requires the NRC to periodically review Routine reviews are complete examinations of Agreement State radiation control programs. The State regulatory programs, normally conducted
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149 every other calendar year, Review visits are To effect this implementation, the NRC will usually conducted between routine reviews and suspend relevant portions of the hf ay 28,1992, serve to maintain familiarity with Agreement General Statement of Policy, " Guidelines for NRC State radiation control programs, to provide an Review of Agreement State Radiation Control opportunity to discuss areas of concern on an Programs,1992." Management Directive 5.6, informal basis, and to confirm the satisfactory " Integrated Materials Performance Evaluation status of the State radiation control programs. Program," which was approved September 12, Followup or special reviews are conducted as 1995, will be used as the implementing procedure. needed, and they tend to focus on State actions in The NRC will implement IMPEP, on an interim specific areas. When appropriate, multidisci- , basis beg,mnmg in fiscal year 1996, in the plinary teams are sent to conduct reviews of evaluation of Agreement State Programs until Agreement State programs. The teams include , , such time as final implementmg procedures for NRC Program and Regional Office staff. the pohey statements," Statement of Prm, eiples nd Policy for the Agreement State Program" and In fiscal year 1995, the NRC performed 11 routine
" Policy Statement on the Adequacy and reviews,7 review visits, and 1 followup review.
Compatibility of Agreement State Programs," and The results of the reviews indicated that each any revisions to these pohey statements are State was adequately protecting the public health approved by the Commission. Conformmg and safety, although not all of the States that were revisions to IMPEP m connection with the reviewed had regulations in place that were fully completion of work on these two pohey compatible with those of the NRC. statements will be done as appropriate. IMPEP will then be implemented on a permanent basis, The NRC technical staff accompanied State nd the remammg portion of the 1992 pohey inspectors to State-licensed facilities to evaluate statement on "Guidehnes for NRC Review of inspector performance, and the staff examined Agreement State Radiat,on i Control Programs,, selected license and compliance casework in detail will be rescinded. in connection with these reviews. Policy Statements and Agreement State Integrated Materials Performance Program Policy Decisions Evaluation Program In 1995, the Commission approved, in principle, the policy statements entitled " Statement of On June 27,1995, the NRC approved Prmciples and Policy for the Agreement State implementation, on an interim basis, of the Program and Policy Statement on Adequacy Integrated Materials Performance Evaluation nd Compatibih,ty of Agreement State Programs.,, Program (IMPEP). The IMPEP process will be , The Commission is deferring implementation of used in the evaluation of NRC Regional Office the poh,ey statements untilimplementmg and Agreement State materials licensing and Procedures are developed and approved by the inspection programs in an integrated manner, Comnu,ssion. The NRC staff is developmg the using five common performance indicators: implementation procedures and any necessary changes to the two policy statements, and will (1) the status of its materials inspection resubmit the pohey statements and implemen-program , tation procedures to the Commission m September 1996. (2) its technical staffing and training The " Statement of Principles and Policy for (3) the technical quality of its licensing Agreement State Programs" describes the program respective roles and responsibilities of the NRC and the States in the administration of programs (4) the technical quality of its inspection carried out under Section 274 of the Atomic program Energy Act of 1954, as amended. The document provides broad guidance in delineating the NRC's (5) its response to incidents and allegations and the States' respective responsibilities and
150 expectations in the administration of a regulatory of terminated license files, regulation changes, and program for the protection of public health and jurisdictional determinations. safety in the industrial, medical, and research uses of nuclear materials.
'lYaining Offered State Personnel by The " Policy Statement on Adequacy and the NRC Compatibility of Agreement State Programs" establishes a basis for NRC determinations that The NRC sponsors training courses and an Agreement State Program is adequate to workshops for Agreement State and NRC staff to protect the public health and safety and is assist State radiation control personnel in their compatible with NRC's regulatory program. It goal of maintaining high-quality regulatory strikes a balance between the extent of uniformity Programs. Course subjects are diverse, covering required in a State program and the extent of health physics, industrial radiography safety, flexibility allowed to a State in tailoring its well-logging, radiation protection engineering, program to the individual circumstances within environmental monitonng, irradiator technology, that particular State. The underlying philosophy transportation of radioactive nuclear materials of this approach is that the State program must and low-level waste, site decommissioning ,
be adequate to protect the public health and charactenzation, nuclear medicme, inspection safety within the State and must be compatible, Procedures, and materials licensing. In addition, by incorporating those elements of the NRC special workshops on specific areas are held as l program necessary to achieve the national interest needed. The NRC sponsored 32 such training ' in radiation protection. The elements of an courses and workshops, which were attended by l adequate program have been developed to reflect 600 State radiation control personnel during the those which are essential to ensuring protection of fiscal year. The sessions were also attended by the public health and safety, and to be consistent NRC staff and by military personnel,in addition with the elements which will be evaluated as to officials from Canada and Mexico. common and noncommon performance indicators under IMPEP. The NRC conducted three special workshops across the country this past year addressing The Commission also decided that the NRC Agreement State Licensee Wrongdoing would discontinue funding for Agreement State Awareness. The purpose of the workshops was to staff training, travel, and technical assistance, Promote awareness of wrongdom, g by Agreement beginning in fiscal year 1997. This policy decision, State regulators, to better prepare participants for made to address the inequity of NRC licensee fee identifymg and handhng wrongdoing issues when funding of the Agreement State Program, will they surface, and to famiharize the parti, result in program revisions that will be developed with the investigative process andques, techm,cipants jointly by the NRC and the Agreement States. A workshop on the evaluation of sealed sources and devices was also held. The workshop was designed to familiarize State licensing personnel NRC Technical Assistance to States with the latest evaluation practices and guidance The NRC continues to provide technical assistance to Agreement States in the areas of licensing, inspection, enforcement, and in Organization of Agreement State response to incidents. Technical assistance is Managers' Workshop provided by responding to requests for information, performing limited confirmatory A public workshop for managers of the license application reviews, and dealing with Organization of Agreement States (OAS) was specific or unusual radiation applications conducted April 5-6,1995, in Rockville, Maryland. requiring specialized expertise and knowledge. Topics for this workshop included the following: This fiscal year, the NRC provided technical assistance to the States dealing with sealed source e an open discussion of Agreement State (A/S) and device evaluations, uranium milling, retention issues
151 i o The Status of A/S Program Improvements e IMPEP Implementation Procedures (i.e.,IMPEP, Adequacy and Compatibility e BPR Policy, and early and substantive involvement of A/S views) e Materials Licensing issues o Federal Advisory Committee Act Update e The Working Group on Control and o National Performance Review e Reciprocity and Jurisdictional , o Status of Selected NRC Rulemakings Determinations
)
o Parallel Process of Federal Rule Promulgation Operational Events in Agreement and Suggested State Regulations for the States Control of Radiation Information on events that have occurred in I o State Interface with Federal Agencies Agreement States involving the use of radioactive ! Relative to Incidents Involving Radioactive by-product material is routinely exchanged with Material Under State Authority the NRC. Safety-significant Agreement State and NRC operational events are discussed at periodic o NRC staff meetings, with an emphasis on Overview of the Business Process Reengineering (BPR) Project identifying the cause of each event. During the past year, Agreement State personnel mvestigated material events involving overexposures, o Accountability of Generally Licensed Devices; Status of Electronic unplanned contammation, leakmg sources, , ndustrial radiography, well loggmg, lost or stolen ' Communications Between NRC and A/S equipment and equipment failure, as well as incidents involving the administration of o Status of the National Database for Events , radioactive byproduct material to mdividuals for Reporting medical diagnosis and therapy. When these studies lead to effective generic remedies, the o Reciprocity and Enforcement Relative to , inform tion is dissemmated to the appropriate Exclusive Federal Jurisdiction regulatory agencies and users. l Annual Agreement States Meeting STATE, LOCAL AND INDIAN ' , The 1995 annual meeting of Agreement State RELATIONS PROGRAM radiation control progrcm directors was held October 30-November 1,1995, in Chicago, One of the NRC's priorities is to maintain open Illinois. Panel discussions and individual 1 nes of communication and close liaison with presentations addressed the status of the State and local government officials and their followmg topics: organizational representatives, as well as with Native Americans and organizations representing o Development of Implementat. ion Practices for American Indian Tribes. These relationships are New Policy Statements developed in an effort to fully address concerns and to promote increased understanding of issues o Selected Rulemakine Actions related to NRC regulation, inspection, and oversight activities to protect the public health a Operational Events and safety. o Medical Issues Outreach Activities o NRC Support for Training and Travel for The NRC continued to pursue cooperative State Personnel activities with the States and their national
152 - organizations. In addition to routine interaction with State and h> cal government and Indian Tribe The Conference of Radiation Control officials, NRC representatives participated m a Prograin Directors, Inc. number of special State-related events, including The NRC, through the Office of State Programs, the activities of the National Association of continues to be represented in the Conference of Regulatory Utility Commissioners, as they relate Radiation Control Program Directors, Inc. to nuclear issues and spent fuel disposal and (CRCPD), to help ensure that State and storage. NRC staff met with State and local Commission programs for protection against the officials throughout the year to discuss the results hazards of radiation are coordinated. The of systematic assessment of licensee performance CRCPD was formed in 1968 to provide a forum reviews of nuclear power plants and outreach where Federal, State, and local radiation control activities related to emergency response planning. program officials could address governmental The NRC also maintained cognizance of the radiation protection issues, mainly through activities of other State-related organizations, committees and task forces. At any given time,50 such as the National Governors' Association, the or more groups may be working on specific Western Governors' Association, and the National projects. An example is the group working on Conference of State Legislatures. Suggested State Regulations, seeking to promote uniformity in radiation protection programs ; throughout the United States. The NRC is l participating in a parallel process for rulemaking I with CRCPD, initiated in May 1995. As many as Cooperation With States 11 NRC resource person., are represented on approximately 14 wm-attees and task forces The NRC staff continues to implement a policy which meet throughout the year. The NRC allowing State officials' observation or contributed $110,000 in FY 1995 to the CRCPD. participation in NRC inspections at reactors, pursuant to the policy statement on " Cooperation Low-Level Waste With States at Nuclear Power Plants and 0ther Nuclear Production or Utilization Facilities,,(57 The NRC continued its support of disposal facility licensing activities in host Agreement FR 6462). In some cases, States ,may observe special mspections, as well. Durmg the year, the States. For example, it assisted in coordinating NRC staff engaged m negotiations relative to a with the CRCPD's E-5 Committee and the Host State Technical Coordinating Committee to memorandum of understanding with officials from the State of New Jersey to conduct low-level organize a workshop on low-level (LLW) radioactive waste performance assessment for radioactive waste storage mspections and LLW disposal facilities. The workshop included responded to other State mqumes concerm.ng implementation of the pohey. the participation of I.LW host States and took place in November 1994. In related areas, OSP assisted in disseminating technicalinformation on LLW facility licensing to LLW host Agreement States and potential Agreement States, which State Liaison Officer Prograin included the "NRC Review of the Vance and Associates, Inc., Topical Report,3R-STAT: A TC-99 and I-129 Release Analysis Computer The NRC policy statement on Cooperation With Code," and approval of the final licensing topical States identifies the governor-appointed State report by Chem-Nuclear Systems, Inc., Liaison Officer (SLO) as the primary State " Multi-Use High Integrity' Container." The NRC contact for all requests involving observation of also coordinated comments on the Ohio draft NRC inspections of plants or facilities. The SLOs version of the Midwest Compact. are also the NRC's primary point of contact with the States regarding all relevant NRC decisions and actions. The NRC hosts a National SLO Liaison With American Indian 'Ribes me, ting every three years and hosts Regional The NRC continues to maintain communications meetings on an as-needed basis in the off years. with those American Indian Tribes, and with their
153 national organizations, potentially affected by, or As the NRC's Federal Preservation Officer (FPO) otherwise interested in, NRC regulatory activities. under the National Historic Preservation Act of Tribal interest in nuclear-related activities, 1992 (NHPA), as amended, the Federal Liaison including those of the Mescalero Apache in New maintains communication with officials at the Mexico and the Prairie Island Dakota Indian National Park Service and the Historic Community in Minnesota, has provided for a Preservation Advisory Council. In 1995, the number of government-to-governrrent exchanges Federal Liaison coordinated and drafted the NRC of information relative to the NRC's regulatory input to the Secretary of the Interior's Annual 1 4 authority in the areas of high- and low-level waste Report to Congress on Federal Archeological storage, disposal, transportation and reclamation. Activities. In addition, the Federal Liaison Tribal interests are also represented by the participated in discussions on the proposed National Congress of American Ind,ans i streamlined revisions to the NWPA Section 106 membership on the NRC's Licensing Support
, process. The final rulemaking is expected in 1996.
System Advisory Review Panel. The NRC staff maintains liaison with the Department of the Interior / Bureau of Indian The Federal Liaison also serves as the NRC's
. Affairs in an effort to keep their constituency Point of contact with the National Science and abreast of nuclear-related issues affecting Indian Technology Center (NSTC), formerly the Federal interests, and also participates in EPA-sponsored Coordinating Council for Science, Engineering interagency meetings to exchange information of and Technology. Th6 NSTC considers issues a id potential relevance and importance to Federal and developments in science and technology that Tribal activities, affect multiple Federal agencies. The NSTC also i provides a forum for coordinating those agencies' !
programs, sharing information, resolving conflicts, making policy recommendations, and identifying ! research needs. FEDERAL LIAISON In 1995, the Federal Liaison continued to serve as The NRC's Federal Liaison is responsible for the pomt of contact regarding NRC activities for establishing and maintaining effective complymg with the President's February 11,1994, communications at the policy level between the Executive Order No.12898," Federal Actions to NRC and other pertinent Federal agencies. Liaison tasks include keeping appropriate NRC Address Environmental Justice in Minority officials apprised of activities at other Federal Populations and Low-Income Populations." Pursuant to the order, the NRC established an agencies that may affect the NRC, and conveying to NRC management the salient views of other internal Environmental Justice Group (EJG), agencies regarding NRC policies, plans, and headed by the Deputy Executive Director for activities. Operations. The Federal Liaison serves as the EJG executive officer. The EJG is responsible for the development of the NRC work products, as The Federal Liaison is the NRC's contact with the Council on Environmental Quality (CEO), as well as for the formulation of the NRC's j prescribed by the National Environmental Policy environmental justice strategy, The EJG Act (NEPA). In this capacity, the Federal Liaison developed the NRC's Final Environmental Justice communicates NRC analysis and comment on Implementation Strategy, which was submitted to matters related to NEPA procedures and the President on April 11,1995. As called for in implementation to the CEQ and provides the Executive Order, in 1995 the Federal Liaison coordination with the NRC on those matters. In was named the NRC's Environmental Justice 1995, the Federal Liaison participated in the Coordinator. In this capacity, the Federal Liaison conferences and focus groups convened by the continues to represent the NRC in the interagency CEO to review the effectiveness of the NEPA Environmental Justice Policy and Coordination process. A CEO report is expected in 1996. Subcommittee.
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INTERNATIONAL COOPERATION The Nuclear Regulatory Commission (NRC) has international arena, including the following long maintained a wide-rarging program of noteworthy activities: international cooperation to help ensure the peaceful, safe, and environmentally acceptable
- Support for meetings of the U.S.-Russia Joint uses of nuclear energy. As the regulator of the Commission on Technological Cooperation in world's largest and oldest civil nuclear program, Energy and Space, chaired by Vice President the NRC has broad capabilities to contribute to Gore and Russian Prime Minister international programs. These capabilities span Chernomyrdin. NRC activities with Russia such areas as nuclear power plant safety, regarding nuclear safety and security issues radiation protection, nuclear materials continued to play an important part.
safeguarding and phynal protection, waste management, and decommissioning of nuclear
- Nuclear safety cooperation with the New facilities. At the same time, the NRC and the Independent States of the former Soviet regulated nuclear industry in the United States Union and countries of Central and Eastern gain insights and useful technical information Europe. These activities included from these NRC international activities. strengthening their regulatory organizations, training foreign inspectors, and working The NRC's international program, administered together in the areas of operational safety by the Office of International Programs (OIP), and risk reduction.
has three broad objectives:
- Efforts to help countries of the former Soviet Union-particularly Russia, Ukraine, and (1) Improving the safety of NRC-licensed Kazakstan-to improve their systems for facilities in the United States:
protecting, controlling, and accounting for nuclear materials. These efforts focused on (2) Helping to enhance U.S. national security; and improvmg regulatory programs and enhancing facility safeguards within the frarnework of agreements signed by the (3) Supporting U.S. foreign policy objectives. Um,ted States with these countries in the fall of 1993.
- Continued efforts to work (in conjunction with other U.S. Government and related ,
FISCAL YEAR 1995 entities) with countries of the Former Soviet union-specificatiy Russia, ukraine, and ACTIVITIES Belarus-to study the health effects of exposure to ioniz'ing radiation resulting from During the fiscal year 1995 (FY 95) reporting the Chornobyl accident and from Russian period, the NRC continued its involvement in the defense-related activities.
156
- Raising the priority of regulatory cooperation SAFETY COOPERATION with several Pacific Rim areas (Indonesia, China, Korea, and Taiwan) that are ARRANGEMENTS embarking on, or are considering, new or expanded nuclear power programs. The NRC formalized the information exchange program in 1974. Since that time, the NRC has
- Maintaining an active information exchange conducted most of its technical regulatory with countries that have substantial nuclear exchanges under the umbrella of a growing programs, and with multilateral organizations number of general safety cooperation arrange-promoting international nuclear safety, as ments that have been signed and renewed over the well as assuming a proactive role in support years. These now total 33, including arrangements of significant international initiatives in the with Argentina, Belgium, Brazil, Canada, China, interest of nuclear safety. the Czech Republic, Egypt, Finland, France, I Germany, Greece, Hungary, Indonesia, Israel, I
- Playing a leading role in resolving implemen. Italy, Japan, Kazakstan, the Republic of Korea, j tation issues for the international Convention Lithuania, Mexico, the Netherlands, Peru, the -
on Nuclear Safety resolutions, which were Philippines, Russia, the Slovak Republic, Slovenia, submitted to the Congress in May 1995 for its South Africa, Spain, Sweden, Switzerland, l advice and consent and ratification. If Ukraine, the United Kingdom, and Taiwan. 1 ratified, these resolutions could become . effective during 1996. Implementation of U.S. 11ese arrangements serve as communication obligations under the Convention will be channels yvith foreign nuclear regulatory carried out primarily by the NRC. A separate org m ations. They ensure prompt, reciprocal Convention on the Safety of Radioactive no ication of reactor safeiy problems that could Waste Management is now in active affect either U.S. or foreign nuclear facilities. international negotiation, with the NRC They also assist m identifymg possible precursor playing an active role in its development. events meritmg further mvestigation. In addition, the arrangements provide a framework for
- Continuation of active, cooperative nuclear bilateral cooperation on nuclear safety, safety research with other nations having safeguards, waste management, and major nuclear power programs, including envir nmental protection, and they serve as the France, Germany, Japan, and the United vehicle for NRC assistance to other countries to Kingdom. impr ve he Ith and safety practices.The ,
arrangements are typically 5 years m duration and The following sections describe these highlights of may be renewed by mutual written agreement of the NRC's major international involvement in the parties. nuclear safety, along with other noteworthy As a key part of the NRC's bilateral nuclear activities durmg the reportmg peaod, safety cooperation program in FY 95, OIP planned and coordinated visits by Commissioners to Argentina, Brazil, Canada, the Czech Republic, China, India, Japan, France, Finland, Russia, BILATERAL SAFE'IY Mr ine and the Unhed Kingdom. Thysnishs are an important means for encouragmg the INFORMATION EXCHANGE exchange of information and experience on nuclear safety. They allow the NRC to gam first-hand knowledge of specific programs The NRC participates in a wide range of mutually (through selected site visits) and to evaluate the beneficial programs involving information assistance that the NRC might provide. During exchange and cooperative safety research with the year, the NRC also received high-level visitors counterparts in the international community. This from Armenia, Brazil, France, Germany, section discusses the NRC's arrangements for the Indonesia, Korea, Russia, Sweden, Ukraine, and exchange of information related to nuclear the Nuclear Energy Agency (NEA) to discuss regulatory and licensing responsibilities. nuclear safety matters of mutual interest.
157 FOREIGN ASSIGNEES WORKING e preparation and administration of licensing examinations cnd the full scope of regulatory AT THE NRC and licensing practice The NRC has an extensive on-the-job training e review of digital systems for operating program for assignees from other countries nuclear plants and advanced light-water (usually from their regulatory organizations) reactors operating under the aegis of the bilateral information exchange arrangements. During e development of rules, regulations, and FY 95, Australia, China, France, Indonesia, Italy, regulatory guides, as well as other aspects of Japan, Mexico, Romania, Slovenia, Spain, Taiwan, developing a regulatory program and Ukraine sent 22 people to participate in the program. Their assignments generally ranged During their time at the NRC, foreign assignees from a few months to a year or more, during often make significant contributions to the which assignees worked in the following areas: resolution of U.S. regulatory issues. At the same time, they learn the NRC's approach to nuclear o events analysis and assessment safety, which helps them and their organizations understand Western safety practices. Assignees o regulation of non-power reactors often become senior officials in their regulatory organizations during their careers. o U.S. probabilistic risk assessment techniques for analyzing operational safety data and implications o U.S. technical tools for determining severe BILATERAL NUCLEAR accident classification, core and containment conditions, consequences of radioactive
, SAFETY COOPERATION releases, and appropriate protective actions During FY 95, the NRC carried on active nuclear o review of regulatory applications issues safety cooperation programs with a large number -
of countries. Each geographical area involved o design certification reviews of advanced reflects somewhat different needs and interests. reactors and licensing procedures o emergency preparedness FORMER SOVIET UNION (FSU) o inspections and implementation of a reactor resident inspection progrsm In 1995, the NRC continued to play an important role in U.S. assistance to the FSU in developing o storage and transport of spent fuel and and enhancing their regulatory systems. licensing activities o thermal hydraulic safety analysis to prepare Russia: The Gore-Chernomyrdin safety evaluation reports of the Westinghouse Commission AP600 The NRC continues to participate in activities o applications of new technical specifications under the U.S.-Russia Joint Commission on Technological Cooperation in Energy and Space, o scope and purpose of the medical use which is chaired by Vice President Gore and program, including the NRC's organization, Russian Prime Minister Chernomyrdin. The function, statutory authority, and Gore-Chernomyrdin Commission (GCC) has been responsibility an important forum for strengthening bilateral ties between the United States and Russia. At the o use of simulators in training operators fourth meeting of the GCC in Moscow in
158 December 1994, the Vice President and the Prime completed 40 scheduled activities with the Minister signed an agreement that will allow the Russian and Ukrainian regulatory bodies, as exchange of technicalinformation in the field of planned. A significant proportion of these nuclear warhead safety and security. This is one activities involved technical training covering all of the most important accomplishments of the facets of safety regulation. GCC to date. Two U.S. Trade and Development Agency (TDA) grants will provide $1.6 million for Activities included regulatory training programs feasibility studies of possible fossil-fuel power at the NRC Technical Training Center in plants to replace Russian plutonium production Chattanooga, Tennessee; training for licensing and reactors scheduled to be shut down at Tomsk and inspection of nuclear power plants at the l Krasnoyarsk. The two sides also agreed to Brookhaven National Laboratory in Upton, New support a similar analysis of possible replacement York; and short-term training sessions at NRC of nuclear power plants. headquarters in areas such as the creation of an Emergency Response Center. This involved In late June 1995, just before assuming the chair. approximately 70 visits by regulatory personnel manship of the NRC on July 1, Commissioner and included over 200 Russian and Ukrainian Shirley Jackson attended the fifth meeting of the representatives, each of whom spent approxi-GCC in Moscow as Vice Chairman of the Energy mately 10 person-days in training provided by the Policy Committee. At this meeting, two agree. NRC, using funding provided by the U.S. Agency ments were signed between the U.S. Department for International Development. of Energy (DOE) and the Russian Federal Authority on Nuclear and Radiation Safety Commissioner Rogers visited Ukraine and Russia (GAN). These agreements involve procedures for in early July 1995. During that visit, he presented protecting, controlling, and accounting for nuclear a paper on Opportunities for Advancement of materials and the safety of fuel cycle facilities and Nuclear Safety Through International Coopera-research reactors. Both agreements included tion at a nuclear conference in Kiev, and met with provisions for coordinating activities with the various officials in both countries, including the NRC. Dr. Jackson had fruitful discussions with f llowing individuals: GAN Chairman Vishnevsky on the future of the . e Dr. Lapsh.m, a semor official of the Russ.ian NRC-GAN assistance program and accompanied , DOE Secretary O' Leary on a visit to the MINATOM organization Kurchatov Institute. In addition, the results of the e Y. Vishnevsky, the Chairman of the Russian Joint U.S.-Russian Electric Power Alternatives Study were released, with the final report regulatory body (GAN) presented to Vice President Gore and Prime B. Gordon, Director of the Science and e Minister Chernomyrdin. The results of this study are intended to be provided to international Engineering Center of GAN banks and other financial institutions with th? e A. Smyshlyayev, Director of the Ukrainian objective of encouraging Western m, vestment in Russ,ai s energy economy. Nuclear Safety Administration e M. Pavlovsky, the Chairman of the
. . . Committee for Nuclear Policy and Nuclear NRC Activities mth Russia and Affairs of the Ukrainian Parliament Ukraine Under the JCCCNRS and the Lisbon Initiative
- M. Umanets, the Chairman of the Ukrainian State Committee for Nuclear Power j The Joint Coordinating Committee on Civilian Utilization j Nuclear Reactor Safety (JCCCNRS) was estab- 1 lished in 1988 by a U.S.-USSR Memorandum of e A. Abagyan, Director General of VNIIAES, Understanding. This committee provides the the Russian organization that addresses framework for cooperation between the United scientific and technical issues for operating States and the former Soviet Union with regard to nuclear power plants, and designs and nuclear safety. During 1995, the committee fabricates simulators for such plants
159 o B. Antonov, the Vice President of framework of the NRC-Kazak Agreement for Rosenergoatom, a technical service Nuclear Safety Cooperation. Topics discussed organization for nuclear power plants (NPPs) included the training of KAEA personnelin NRC nuclear safety inspection practices for power and o L. Bolshov, the Director of the Russian research reactors, the establishment of an early Institute of Nuclear Safety warning and incident reporting system in Kazakstan, and the NRC's radiation monitoring Chairman Jackson traveled to Ukraine for several rules and regulations for power reactors. days in September 1995 to discuss issues related to the regulation of nuclear safety in Ukraine and negotiations between the G-7 (an association of Armem.a severrindustrialized countries: Canada, France, In November 1994, NRC hosted Mr. Ashot t Germany, Italy, Japan, the United K,ingdom, and Martirossian, Head of the Armenian State Atomic the United States) and Ukram, e (m the closure of
, Supervision Authority (ASAS) for discussions Chornobyl. Her travels melude visits to Kiev, the regarding possible NRC regulatory activities to Chornobyl NPP, and the nearby town of Slavutich assist Armenia. In May, the NRC began initial (where plant workers live). Durmg those visits, implementation of its regulatory assistance efforts Chairman Jackson met with Yuri Kostenko, with ASAS when three ASAS representatives Minister of Environmental Protection and Nuclear attended a 3-week fire protection training class at Safety; his First Deputy Minister for Nuclear Brookhaven National Laboratory. ASAS staff also Safety Alexander Smyshlyayev; top officials of the received training in the areas of site security and State Committee on Nuclear Energy, the spent fuel and waste management.
Chornobyl plant, and the town of Slavutich; and the Chairman of the Parliamentary (Rada) Committee for Nuclear Policy and Nuclear Safety. The meetings on nuclear regulation covered nuclear legislation, the nuclear fuel cycle, CENTRAL AND EASTERN EUROPE resources for the nuclear regulator, licensing for nuclear power plants, and energy infrastructure During FY 95, the NRC continued its extensive development. The meetings on Chornobyl covered program to assist the countries of central nnd i the linkage of its closure by the year 2000 to the eastern Europe (CEE) in improving safety ; implementation of a comprehcnsive energy plan. practices at their Soviet-designed reactors.The An integral part of this plan is the creation of an objectives of the regulatory assistance program International Nuclear Safety and Environmental are as follows: Center at Slavutich. e Assist in developing an effective regulatory The U.S. chair for the JCCCNRS, Executive organization Director for Operations (EDO) James Taylor, met in November 1994 with Alexander Gutsalov, First e Advance safety culture awareness and Deputy Chairman of GAN, and in May 1995 with practices Alexander Smyshlyayev. Discussions in both meetings included a review of ongoing assistance e Strength'en the legal framework and projects and the results achieved, as well as plans regulatory capability governing nuclear safety for future activities, e Improve analytical capabilities for performing safety analyses (computer codes) Kazakstan e Strengthen inspectorates through intensive in December 1994, a small delegation from training in NRC regulatory inspection Kazakstan visited the NRC for a tour of the philosophy, procedures, and techniques Operations Center and discussions with OIP concerning the NRC's assistance to the Kazak
- Prepare training programs for safety Atomic Energy Agency (KAEA)within the evaluations at the NPPs
160 e Emphasize a regional approach by inviting (SER). Training thus far has included clashroom representatives from all CEE countries to lectures, hands-on analyses and documentation attend NRC training courses reviews, and identification of numerous areas and issues for which additional information was , During 1995, the NRC offered the following required from the vendor to resolve safety courses to members of the nuclear regulatory questions. authorities of all five CEE countries: Chairman Jackson visited the Czech Republic in e Seismic Margins Evaluation September 1995 during the IAEA General Conference. During this visit, she toured the
- U.S. Commercial Nuclear Power Plant Fire Temelin NPP site and the Nuclear Research Protection Practices Institute at Rez, and held discussions with senior regulatory officials.
- Fundamentals of Inspection e Welding and Nondestructive Examination for Slovakia Technical Managers The Slovak Nuclear Safety Authority (SNSA) e
. requested a one-week training assignment at NRC Risk-Based Regulations headquarters to assist their Division of Decommissionmg and Decontamm.ation of
. International Relations in implementing its NPPs international obligations and other support
' functions. The Deputy and Assistant Deputy of e that Division spent one week in meetings with the Validation and Verification of the Office of Public Affairs, Office of Congressional Applicability of NRC Computer Codes to Affairs, Division of Contracts, Office of the VVER Reactors (PWR-type). Controller, Office of the General Counsel, and Two NRC representatives attended the Second the Technical Specifications Branch. They also Regular Meeting of the Association of the State met with OIP's Director of the Division of Nuclear Safety Authorities of the Countries Bilateral Cooperation and Assistance and various Operatmg VVER 'Iype Reactors, which was held OIP country officers. in Slovakia. Tbpics covered by CEE participants included country-specific reports on the safety of Lithuania nuclear facilities, information on safety-significant events, illicit trafficking in nuclear and radioactive A safety analysis was mandated by the European materials, adherence to the international Bank for Reconstruction and Development Convention on Nuclear Safety, decommissioning, (EBRD) as one of the conditions to be met before and treatment of radioactive waste. the EBRD will consider releasing nuclear safety account funds for hardware upgrades to the Ignalina NPP. The NRC recommended that a Czech Republic technical support organization participate in the review, but the NRC does not intend to have l During the FY 95 reporting period, the NRC, direct involvement with the analysis. The OIP l Idaho National Engineering Laboratory (INEL), initiated a bilateral assistance project on the basis j and Lawrence Livermore National Laboratory of recommendations prepared by a consultant (LLNL) continued training senior Czech (Dr. Thomas Murley), who conducted a two-week regulators on how to evaluate the safety of the survey of Lithuanian regulatory assistance needs. ; Temelin nuclear power plant in accordance with The project will help the regulators develop l current NRC regulatory requirements. The country-specific norms, standards, and related l Temelin plant is being backfitted with inspection guidelines. I Westinghouse-provided fecl and updated instrumentation and control (I&C) systems. The Attorneys from the NRC's Office of General Czech regulators are also being shown how to Counsel traveled to Lithuania to comment on the prepare a final reactor safety evaluation report preparation of Lithuania's draft atomic energy
161 law. The NRC representatives also met with in nuclear power, the Commission has placed a members of the Lithuanian Parliament and the high priority on safety cooperation with Pacific Director of the Lithuanian Parliament's legal staff Rim countries. to explore various legal issues. The NRC attorneys then reviewed the draft law and made numerous constructive comments. Japan In January, a large earthquake (magnitude 7.2) ccurred near the port city of Kobe in central IIungary Japan. The Ministry of International Trade and Dr. Lajos Voross, who was nominated Chief Industry (MITI), the NRC's regulatory inspector of the Hungarian Atomic Energy counterpart for operating reactors, promptly Commission (HAEC) on January 1,1995, took notified the NRC that none of Japan's power part in a mini-fellowship with OIP and the Office reactors were shut down as a result of the quake of Nuclear Reactor Regulation (NRR). This and no damage was reported by any nuclear mini-fellowship included two weeks at NRC facility. A month later, an NRC team visited the headquarters and one week in Region IV, during quake site to gather data on the effects of the which Dr. Voross was exposed to NRC's quake and its aftershocks. In addition to touring management techniques, organizational issues, various commercial and residential sites, the team and program tracking procedures. Dr. Voross will met with the Kansai Electric Power Company to rely on this experience to implement changes in discuss the overall performance of the power the way the HAEC will manage some nuclear generating and distribution facilities, the effect of safety activities in the future, grid disturbances on the nuclear plants, design criteria used, steps necessary for recovery, and lessons learned. The team determined that the Bulgaria earthquake damage did not indicate a need for reevaluation of seismic design criteria for nuclear While no specific program has been implemented power plants in the United States. However, to for Bulgaria, the Bulgarian regulators have sent address the potentially high velocities and an average of two technical specialists to each of displacements in the low-frequency range, the the several training courses the NRC has offered. team decided that new measures of damage Brookhaven National Laboratory is now helping a potential, such as drift, need to be investigated. Bulgarian specialist to develop a RELAP5 computer code input deck for the VVER-1000 In April, former Chairman Ivan Selin visited reactor, which will simulate the thermal hydraulic Japan to present a keynote address to the 28th behavior of the plant. Bulgaria's Committee on Annual Meeting of the Japan Atomic Industrial the Use of Atomic Energy for Peaceful Purposes Forum. In his remarks, the Chairman discussed (CUAEPP) plans to install this deck on a the crucial role that a well-developed safety simulator acquired from the United States. The culture plays in nuclear power programs and the NRC will assist CUAEPP in preparing licensing responsibility to share its experience with guidelines for this simulator. less-developed programs. While at the conference, the Chairman held a series of bilateral discussions with key representatives from other nuclear PACIFIC RIM Programs. He also met with senior Japanese officials, including the Minister for Science and Technology, to discuss Japan's long-range plans This region includes a number of well-established for nuclear energy. nuclear power programs in Japan, the Republic of Korea, and Taiwan. The Pacific Rim is also the fastest growing energy market in the world. The China energy demand in many Pacific Rim countries is expected to triple over the next 30 years, and In April 1995, Chairman Selin visited China for nuclear power is expected to capture an the third time since becoming Chairman. The increasing share of this demand. In response to highlight of his visit was the opportunity to meet the growing energy market and increased interest with Vice Premier Wu Bangguo. In an exchange of
162 views on nuclear safety, Chairman Selin stressed The 16th meeting of the U.S.-ROK Joint Standing the importance of investing adequate resources in Committee on Nuclear and Other Energy the construction and operation of nuclear plants Technologies (JSCNOET) was held at the and the nuclear industry's regulatory authority. Department of State in hiay 1995. At the meeting, The Chairman also met with other senior energy participants reviewed bilateral cooperation over officials from the National Nuclear Safety the past year, proposed cooperation for the Administration, the State Planning Commission, coming year, and discussed nuclear energy issues, and the China National Nuclear Corporation. In including nuclear safety and safeguards. The NRC cach discussion, Chairman Selin expressed the covered its technical information exchange hope that China could avoid costly mistakes by arrangement, training, emergency cooperation. l accounting for lessons learned from the developed and ongoing safety research projects with Korea. nuclear programs around the world. Accompany- ! ing the Chairman, EDO James Taylor visited the Korea Institute of Nuclear Safety (KINS) l Qinshan NPP (a 300-hiWE PWR) and gave a President Yong Kyu Lim visited the NRC on i series of safety lectures to the regulators. August 15,1995, to meet with Chairman Jackson ) and senior managers from the Office of Nuclear Reactor Regulation (NRR), the Office of Nuclear
'Paiwan Regulatory Research (RES), and the Office for l Analysis and Evaluation of Operational Data l In October 1994, the NRC participated in the (AEOD). The purpose of these meetings was to ,
Joint Standing Committee hieeting on Civil discuss NRC/ KINS cooperative safety activities Nuclear Cooperation between the American and to propose new or expanded activities. The KINS remam, s highly interested m contmumg Institute on Ihiwan (AIT) and the Taiwan , Coordination Council for North American Affairs 1-year on-the-j,ob trammg assignments at NRC (CCNAA) that was held in Washington. At the lieadquarters for its regulatory personnel, as well meeting, CCNAA announced that it would be as 6 month techm, cal traming and reactor changing its name to Taipei Economic and inspection assignments at the Techm,ca1 Tra,m,ng i Cultural Representative Office (TECRO). The Center and in the regions. Stx of KINS, inspectors meeting provided the opportunity for both sides have now completed these traming assignments. to offer briefings on key elements of their nuclear The KINS also wishes to establish a formal, programs and identify areas for future coopera- annual 2- or 3- day techm, cal exchange meeting tion. During the 1994 to 1995 program year, NRC with the NRC. and TECRO were involved in 20 bilateral cooperative programs. In addition, Taiwan is an Democratic Peoples' Republic of Korea important partner m many of the NRC s international research programs, m, eludmg seismic (DPRK) effects, piping integrity, and severe accident On February 1,1995, an NRC team composed of Programs. Carlton Stoiber, Director, OIP; Jack Martin, then-l Region III Administrator; and hiichael Case, 1 NRR; participated in the first detailed safety l Republic of Korea (ROK) discussions with a DPRK (North Korea) ! delegation in Berlin. He safety discussions were l ROK Minister of Science and Technology Kun Mo an adjunct to a larger,4-day session scheduled for Chung visited the NRC in June 1995 to meet with the U.S. and DPRK Governments to reach Chairman Selin, Commissioner Jackson, and concurrence on the terms of a supply agreement Commissioner Rogers to discuss current nuclear under which two 1000-MWe light-water reactors policies and issues, as well as new directions. In a are to be provided to the DPRK in return for ceremony scheduled between mecthe he and the freezing its indigenous nuclear program and Chairman also signed the second renewal of the related activities. Unlike the supply agreement "NRC-Ministry of Science and Technology talks, the safety session was marked by a good Arrangement for the Exchange of Techrical exchange on both sides. The NRC's presentations Information and Cooperation in Regulatory and covered the role and responsibilities of a Safety Research Matters." regulatory organization; typical NRC licensing,
163 inspection, and international assistance activities; power plant's March 1993 turbine generator fire. and the international Convention on Nuclear The entire NRC team also accompanied three Safety. The staff participated in these discussions members of Secretary O' Leary's energy to impress upon the DPRK the necessity of delegation. which was in India at the same time, developing a true safety consciousness and on a visit to the Bhabha Atomic Research Centre committing to a solid safety culture in the earliest (BARC) at:d the Tarapur Atomic Power Station stages of planning its nuclear power program. (TAPS). During this visit, the NRC delegation held meetings with representatives of the AERB, the Atomic Energy Commission (AEC), and the Indonesia Nuclear Power Corporation. Djali Ahimsa, Director General of the Indonesian At the end of the visit, the NRC and AERB National Atomic Energy Agency (BATA.N), visited agreed to continue discussions on the the NRC on May 5,1995. During that visit, he met development of symptom-based emergency with Chairman Selin and Commissioner Jackson procedures, technical exchanges on design issues, to discuss the status of Indonesia's consideration fire safety at nuclear power plants, and materials of the nuclear power option and the on-the-job aging and inservice inspection. Other topics regulatory training program for BATAN suggested for a future reciprocal visit included personnel, which the NRC has undertaken at radiation protection, regulation of medical and Indonesia's request. Director General Ahimsa industrial uses of radiological sources, licensing of indicated that he was very pleased with the byproduct materials, initiation of a joint knowledge and experience gained by the first four NRC-AERB CANDU reactor study, continued BATAN trainees, who completed their 1-year discussions on aging boiling water reactors, and assignments at the NRC in February 1995. He fire protection also advised that final decisions were being made l on the next four trainees, who are scheduled to begin similar NRC assignments in January 1996. WESTERN EUROPE AND CANADA Indian Subcontinent The NRC has traditionally maintained strong ties with countries in this region, many of which have In July 1994, the U.S. Government began ctive and advanced nuclear programs. The discussions with India on a broad range of energy NRC s relationships with these countries enable issues. As part of those discussions, the NRC , us to increase our knowledge of important new initiated a reciprocal nuclear safety dialogue with
. . techm, cal developments, both for operatmg its Indian counterpart, the Atomic Energy facilities and advanced designs, and to harmonize Regulatory Board (AERB). regulatory approaches to the extent possible.
In October 1994, representatives of the AERB visited the United States for safety discussions France and site tours. In February 1995, Chairman Selin, accompanied by an NRC technical team, visited The NRC and the nuclear establishment of France India at the invitation of AERB Chairman actively continued their cooperative exchange A. Gopalakrishnan. NRC-AERB topics of activities during the FY 95 reporting period. In discussion included fire safety, design issues, September 1995, Chairman Jackson made an symptom-based emergency operating procedures, official visit to France to meet with key nuclear and issues related to the internals of reactor officials and visit nuclear facilities. Chairman vessels (e.g., core shroud cracking and steam Jackson met with Ambassador Harriman; A.C. generators). All discussions were based on Lacoste, Director of the Directorate for the Safety publicly available information. of Nuclear Installations; Y. d'Escatha, Administrator General of the Atomic Energy Several members of the NRC team visited the Administration: G. Menage, Chairman of Narora Atomic Power Station (NAPS) for Electricite de France; Claude Mandil, Director of discussions and site tours relevant to the nuclear Energy and Raw Materials, Ministry of Industry;
164 P. Vesseron, Director of the Institute for and renewals for CSN members on hold for about Radiation Protection and Nuclear Safety; Jean 4 years. Syrota, Chairman, COGEhfA; and Y. Kalusney, Director of ANDRA (the French waste ,. management organization). She also visited the The United Kingdom Centre de l'Aube low-level waste facility and the During October 1994, Commissioner de Planque Nogent nuclear power plant. The Chairman was traveled to the United Kingdom (UK), where she favorably impressed with both of the facilities visited a number of nuclear facilities, including visited, and she expressed her desire to continue the Sellafield spent-fuel management facility, the important safety cooperation that the NRC Drigg low-level waste site, Calder Hall nuclear has developed with France. power plant, the BNFL Capenhurst enrichment i site, the Nuclear Radiation Protection Board l In October 1994, Commissioner de Planque was a facilities, and the Nirex facilities. The keynote speaker at the European Nuclear Commissioner also met with UK utility and Conference (ENC 94) in Lyon, France. She government officials. Of particular interest to addressed a full conference session on " Radiation Commissioner de Planque was the 1994 UK 1 nuclear energy policy review and privatization of Protection: A Lesson in Societal Decision hiaking." She also made a short visit to the the British nuclear program. French Cadarache Nuclear Research Center. Sweden In October 1994 and July 1995, French parliamentarian Dr. Claude Birraux, and his During December 1994, hir. Lars Hogberg, assistant, hir. hiichel Bermond, met with the Director General of the Swedisti Nuclear Power Chairman, Commissioner Rogers, and senior Inspectorate, made an official v,i sit to the NRC. NRC staff. On the first trip, he discussed Durm, g that visit, he uet with the NRC Chairman, dismantling and decommissioning nuclear sites; Commissioners, and senior staff managers at the subject of the second visit was the regulation headquarters to discuss a full range of nuclear of low levels of radiation. In the past, Dr. Birraux safety topics and to sign the renewal of our prepared a number of reports on nuclear safety bilateral cooperative safety arrangement. ,ted th and control for the Parliament. He is now Followmg the visit to headquarters, he visi preparing reports in connection with plans to Limerick NPP in Pottstown, Pennsylvania, and decommission five of France's older reactors and concluded his visit with a trip to the Region I the possible need to revise occupational dose office m, Kmg of Prussia, Pennsylvam,a. limits. Finland In October 1994, Commissioner de Planque Spa.in traveled to Finland to meet with the Finnish Women in Nuclear (WIN) section of the European In November 1994, three new Commissioners Nuclear Society, sponsored by the Energy were appointed to 6-year terms on the Spanish Channel of the Finnish Nuclear Society (FNS). Nuclear Safety Council, the Consejo de Seguridad The Commissioner's presentation focused on her Nuclear (CSN). Socialist Juan Kindelan, the responsibilities at the NRC and the role of the former President of ENRESA (the Spanish waste NRC in the American nuclear energy program, management company), was named President of During her visit, the "Helsingin Sakomat" the Spanish Commission, replacing Conservative newspaper conducted an interview to obtain the Donato Fuejo. The other two appointees were Commissioner's perspective on nuclear energy. At Dr. Agustin Alonso, an Independent who is the that time, Commissioner de Planque was one of former head of nuclear safety at the Junta de only two women nuclear safety commissioners in Energia Nuclear (the forerunner of the CSN), and the world. The visit included tours of the Dr. Anibal hfartin, a Conservative. They replaced Radiation Safety Center (VIT) and the Loviisa Luis Echavarri and Fabio Sarmiento. A fragile Nuclear Power Plant, as well as meetings with Socialist political alliance had kept nominations utility and government officials. I
165 Canada (3) Nucleoelectrica Argentina S.A. (NASA), which is the utility operating the Embalse l In December 1994, the EDO, accompanied by the and Atucha power reactors RES and NRR Directors and additional NRR and OIP staff, met with members of the Atomic The CNEA is now responsible for operating the Energy Control Board (AECB), Atomic Energy of country's three research facilities (Ezeiza, Canada Limited (AECL), and Atomic Energy of Constituyentes, and Bariloche), as well as the Canada Limited %chnologies (AECLT). During waste management program and assoc,ated i that meeting, participants discussed the results of facilities. In addition, the CNEA is responsible the NRC's acceptance review of the CANDU 3U for technology management, development of the design certification application and AECLT's Prototype CAREM reactor, and the intentions regarding continuation of the commissionmg of nuclear power plants. The application. Discussions centered on the schedule CNEA is developing options to help pay for their and cost of the effort. national nuclear program. These options presently include selling goods and services overseas, Participating as a subcontractor in international In May 1995, Commissioner Rogers visited Toronto, Canada, to give a speech at the j nt nuclear enterprises, developmg the 25-MW Intctnational Workshop on Reliability Data CAREM prototype reactor for sale to countnes Collection. He then went to Ottawa, where he met just begmnmg the,ir nuclear programs, and with nuclear officials at the AECB, the AECL, developing their uranium mmmg base for possible the National Research Council, and the sale of fuel overseas. D,epartment of Natural Resources, Canada, t ENRN, the new Argentine counterpart to the discuss a number of nuclear issues. Specifically,
, NRC, has assumed the regulatory activities l these issues meluded waste management, the i
. formerly managed under the CNEA. ENRN will contmued supply of medicalisotopes by Nordion, regulate waste management and all nuclear and the use of CANDU reactors for burmng activities, including radioisotopes and accelerators Pl utonium. but not x-rays, which are regulated by the Department of Public Health. ENRN has signed the thermohydraulic code management program (CAMP) agreement with the NRC, and is LATIN AMERICA interested in joining with the NRC in its severe accident management research program.
The three largest countries of Latin America- In August, Commissioner Rogers visited Argentina, Brazil, and Mexico-all have Argentina where he conducted useful discussions long-standing nuclear programs. In recent years, with nuclear authorities. He also visited the initiatives by Argentina and Brazilin the Ezeiza Nuclear Research Center with its RA-3 nonproliferation area have increased research reactor, the Conuar fuel fabrication opportunities for U.S. nuclear cooperation with facility, and the waste management facility. In them. addition, Commissioner Rogers visited the Atucha I and II nuclear power plants and the Bariloche Atomic Center, where he received a tour of the RA-6 research reactor and a briefing on the Argentina , Pilcaniyeu enrichment program (in heu of a tour because the enrichment facility was inaccessible In 1994, the Argentine government reorganized the nuclear sector, dividing the Comision as a result of snow). Nacional de Energia Atomica (CNEA)into three Follow-up actions by both sides include new entities: negotiating an NRC-ENRN arrangement for technical and safety cooperation to replace the (1) CNEA arrangement signed in 1990 with the CNEA, as well as defining possible future areas for (2) Ente Nacional Regulador Nuclear (ENRN) cooperation.
166 Brazil The Commissioner also met with the President of the Comision Nacional de Energia Nuclear Commissioner Rogers visited Brazilin August to (CNEN) to discuss CNEN's organization, attend the 13th International Conference on licensing, reactor activities, and possible areas of Structural Mechanics in Reactor Technology cooperation with the NRC. The following day, the (SMIRT)in Porto Alegre. His visit also included Commissioner toured the Angra dos Reis nuclear ceaducting discussions with Brazilian nuclear Power plant site south of Rio de Janeiro. When authorities, and touring nuclear sites. completed, Angra will have three nuclear power plants: Commissioner Rogers presented the keynote , address at the SMIRT conference, for which NRC (1) Angra I, a 626-MWe Westmghouse was one of many international sponsors. P.ressurized-water reactor (PWR) operational Representatives of most of the countries of the smce 1985 world with nuclear interests attended the 4 conference. This conference provides a forum for (2) Angra II, for which construction is expected members of the international scientific and to be completed in 1998, with operation engineering communities who are involved with starting in 1999 the structural mechanical aspects of design, construction, and operation of nuclear reactors t exchange the latest information and ideas, and (3) Angra III, for which construction is planned reestablish personal contacts. to start in 1998 or 1999 (both 1229-MWe German Siemens AG PWRs) The Commissioner also conducted discussions in . Sao Paulo at the Instituto de Pesquisas During the tour, the group also saw the simulator Energeticas e Nucleares (IPEN), where he was I b ratoiy and the environmental momtormg briefed on the organization and distribution of facility. nuclear research responsibilities among Brazil's three research centers (IPEN, CDTN, and IEN). Followup actions by both sides ?nch'de working An NRC team also toured the IEA-R1 research out details of possible cooperative projects under reactor and the pilot uranium hexafluoride (UF6 ) the NRC-CNEN arrangement for technical and ; production line, designed to process uranium safety cooreration (e.g., possible technical training 1 yellowcake into UF6. of CNEN personnel and reciprocal visits to NRC { sites). j The Commissioner met with officials of the I Brazil Argentina Agency for Accounting and ' Control of Nuclear Materials (ABACC)in Rio de Janeiro and was given a comprehensive overview of the ABACC's work. The speaker noted with SOUTH AFRICA pride that Argentina and Brazil are moving toward a good relationship after 150 years of
" peaceful but worried coexistence." ABACC has a Following many years of being cut off from the total staff of 12 technical personnel divided world community because of their now disbanded among four sections: nuclear weapons program and other policies, South Africa concluded an Agreement for (1) planning and evaluation Cooperation Concerning Peaceful Uses of Nuclear Energy with the United States in August 1995.
(2) nuclear accounting This is a milestone accomplishment in that it renews nuclear exchange and trade between the two countries. The NRC, required by statute to (3) techm. cal support review this action, issued a letter from Chairman Jackson recommending approval of the (4) operations agreement.
167 MULTILATERAL NUCLEAR ci i reactor pressure vessels and changes to U.S. requirements for containment leak rate testmg. SAFETY COOPERATION Participants at the meeting, who included regulators from several newly independent countries and Eastern Europe, responded with In addition to its extensive program of bilateral their own experiences in these areas. cooperation with other countries, NRC also works closely in the area of nuclear safety with The IAEA General Conference agenda dealt with international organizations such as the a range of topics on the IAEA's policies, International Atomic Energy Agency (IAEA)in programs, and budget. These included measures i Vienna and the Nuclear Energy Agency (NEA) of to strengthen international nuclear safety and i the Organization for Economic Cooperation and technical cooperation, measures to strengthen and Development (OECD) in Paris. For example, improve the safeguards system, and measures using data on events at nuclear power plants against illicit trafficking in nuclear materials and i received from other countries through both other radioactive sources. A resolution adopted in agencies, the NRC performs comparative studies the safety area urged member states to sign and , of reactor operational experiences that may ratify the Convention on Nuclear Safety so it can l produce information applicable to the safety of go into effect in 1996. The United States agreed to U.S. reactors. The NRC also uses repotts of a general 3-year increase in contributions to the operational events received from the NEA/IAEA Technical Cooperation and Assistance Fund in l Incident Reporting System, from the IAEA, and exchange for support of a refinancing approach ; from bilateral exchange programs with more than that would have more member states pay an i 20 countries to supplement domestic data. The assessed share of the safeguards budget. The NRC also uses these mechanisms to provide U.S. September Board of Governors met before the incident reports to the international community. General Conference to discuss issues arising from Chapter 3 provides further information on this proposed resolutions for the General Conference. program. Among the major issues were the financing of technical assistance and safeguards and, in the l safety area, liability for nuclear damage. It has been difficult to reach a consensus concerning an INTERNKFIONAL ATOMIC ENERGY updated liability regime such as the AGENCY U.S -Proposed global convention covering transboundary effects. General Conference and Board of IAEA Meeting Participation Governors Meetings NRC staff attended 20 meetings on a range of In September 1995, Chairman Jackson attended nuclear safety topics: the thirty-ninth regular session of the IAEA General Conference m Vienna, Austria. While e the Incident Reporting System there, she met with IAEA nuclear safety officials
, , e the International Nuclear Event Scale and conducted bilateral discussions with Argentina, Armenia, Canada, China, the Czech e radiation safety Republic, Germany, Ghana, Hungary, India, Indonesia, Japan, the Republic of Korea, the e advances in the operational safety of nuclear Russian Federation, the Slovak Republic, South power plants Africa, Spain, Ukraine, and the United Kingdom.
The NRC's EDO, James Taylor, also attended the e safe management of radioactive waste General Conference, representing the United States in a meeting of senior regulators, where he e safe transport of radioactive material led a discussion on the regulatory approach to pressure vessel integrity and annealing. He
- generic safety issues pertaining to light-water presented a paper on annealing of U.S. commer. reactors
168 e decommissioning of nuclear power plants and March 1995, the signatories agreed to hold research reactors periodic (approximately every six months until the CNS is entered into force) topic-related meetings, e nuclear power plant diagnostics to coordinate the approach to formulating options and alternatives to implementing the CNS. e cracking in light-water reactor pressure vessel Signatories' suggestions may be submitted to the head penetrations preparatory meetings for formal consideration and approval. These preparatory meetings, called e strengthening structural materials used for soon after the Convention enters into force, will transporting radioactive material shape the implementation of the convention. e preparation of a program for the revision of Implementation of the U.S. obligations under the ; Convention will be carried out primarily by the the NUSS Design Series documents NRC as the U.S. civilian nuclear regulatory e industrial radiography safety practices authority. Other than the requirement to prepare the national report required in Article 5, e advancements in the implementation of new obligations incurred under the Convention are l basic safety standards already embodied in NRC regulations and l procedures, and the conforming practices of the l e advances in and experiences with accident U.S. civil nuclear power industry. consequences analysis e a plant self-assessment program to enhance Waste Convention nuclear safety In February 1995, the IAEA convened a I preparatory meeting of member states' experts to j e safeguards discuss development of a Convention on the Safety of Radioactive Waste Management. Several e computer codes for severe accident issues were raised during the meeting, and the management IAEA compiled them into a document, entitled
" Inventory of Issues," similar to the Convention
, on Nuclear Safety. The purpose of the document Convention on Nuclear Safety was to provide member states with a tool to help The United States signed the Convention on f cus the negotiation process for a waste ;
Nuclear Safety (CNS) at the IAEA General Convention. I Conference in September 1994. As of June 30, 1995, there were 58 signatories and 11 ratifications l (Bangladesh, France, Japan, Norway, Poland, Romania, the Slovak Republic, South Korea, NUCLEAR ENERGY AGENCY (NEA) i Spain, Sweden, and Thrkey). On May 11,1995, the U.S. Government completed its review of the . NEA Steering Committee Meetings CNS, and the President submitted the Convention , i to the Congress for its advice and consent and The NEA Steering Committee met in October ratification. 1994 to give final approval to the 1995-1996 Program of Work and Estimate of Expenditures. During negotiation of the CNS, certain basic This was the first proposed 2-year budget implementation approaches were informally approved for the NEA, and discussion focused on discussed but not embodied in the CNS text. In the increasing demands of an expanding December 1994 and March 1995, signatories held membership and the Agency's growing program meetings to clarify some of the implementation for nonmembers in the face of diminishing issues on which the Convention is silent. Carlton resources. Stoiber, Director, OIP, represented the U.S. Government at both of these meetings, chairing A Special Session in March 1995, focused on the latter as well as the November 1995 session. In clarifying the role of the NEA and its balance of
169 priorities, relations with nonmember economies, G-24 Nuclear Safety Assistance the structure and role of the Steering Committee, l Coordination Activities the possibility of changing NEA statutes to give the NEA more autonomy (particularly with In February and June 1995, the NRC participated respect to future membership), and the possible
, in the G-24 Nuclear Safety Assistance Center's l restructurmg of technical standmg committees. Steering and Plenary Committee meetings in
. Brussels, Belgium. The purpose of these meetings
. ; May 1995, the Steering Committee held its
, was to discuss coordination of safety assistance second regularly scheduled meetmg, during which programs worldwide for the countries of the Director General Uematsu announced the former Soviet Union and Central and Eastern appointment of Mr. Makoto Takahashi (Japan) as Europe. In addition, in June 1995, the NRC the new NEA Deputy Director for Safety and participated in an ad hoc meeting to coordinate Regulat,on.
i The Director General noted that he ongoing or planned assistance activities with the was retirmg at the end of October 1995.
, . Federal Nuclear and Radiation Safety Authority Discussion topics meluded cooperation with . of Russia (GAN). This meeting successfully Argentma and Brazil, NEA-IAEA coordination, identified priority areas of assistance for GAN, the Collective Opimon on the Environmental and and highlighted potential overlaps or gaps in Ethical Aspects of Geological Disposal, and the assistance efforts. In addition to the NRC and need for voluntary contributions to support the GAN, the regulatory authorities of Canada, NEA Program on Nonmember Economies. France, Germany, Italy, Spain, and the UK were represented. Representatives of the European Union's safety assistance programs also attended.
Visit to the NRC by the NEA Deputy Director General Samuel Thompson, NEA Deputy-Director G-7 Nuclear Safety Activitics/EBRD General, met with Chairman Jackson in July 1995 Nuclear Safety Role to discuss bilateral cooperation. 'Ibpics of interest included U.S. Government funding for the NEA, The European Bank for Reconstruction and a possible 1996 meeting of heads of regulatory Development (EBRD) plays a dual role in helping organizations, and the upcoming technical to improve nuclear safety in Central and Eastern standing committee (CSNI) meeting on the safety Europe and the FSU-first, through EBRD's of Soviet-designed RMBK and VVER reactors. Nuclear Safety Account (NSA), which is focused on financing existing NPPs; and second, through j the EBRD loan program, which is available to Energy Charter '&eaty Protocol on finance nuclear safety upgrades and completion of Nuclear Safety newer, safer plants. However, such loans have been difficult to justify because of the EBRD's i The Energy Charter Treaty Working Group IV 71 east cost" criteria for making energy ) met in May 1995 to finish drafting a Nuclear infrastructure loans and because nuclear energy Safety Protocol. The European Union (EU) tends to be very capital intensive. suggested that the draft protocol text be modified, and placed a nonbinding hortatory Declaration on The NSA is expected to assist in implementing Nuclear Energy on the table for discussion. A the G-7 action plan for closure of Chornobyl by working group majority favored forwarding su a a financing near-term safety upgrades and declaration to the Energy Charter Treaty decommissioning studies at this plant. In the Conference. However, consensus was not possible spring of 1995, the NSA made a grant to Russia of because of objections raised by the delegations about $100 million for safety upgrades to the from Russia, Ukraine, Belarus, and Armenia on Kola, Novovoronezh, and Leningrad (Sosnovy the failure of the text to cover trade, economic, Bor) nuclear power plants. As a condition of this and technology issues, and to be legally binding. loan, Russia agreed to set up a Western-style The subject will be taken up by the Charter nuclear reactor licensing regime on the basis of a Conference in 1996. safety analysis of its nuclear reactors.
170 Proposed U.S.-EURATOM Agreement Examples of activities conducted during FY 95 for Cooperation under the NRC's international nuclear safety research program include the following: The Agreement between the U.S. Government e using the ROSA Large-Scale Test Facility in and the European Atomic Energy Community , (EURATOM) Concerning Peaceful Uses of Japan for confirmatory safety system testmg Atomic Energy has been aoproved by the to help provide technical bases for NRC President and EURATOM'. U.S. law requires that licensing decisions on the AP600 advanced the new Agreement sit before the U.S. Congress reactor design for 90 days of continuous legislative session, . which could extend into April or May 1996. The
- C Peratm.g mternatiocally to develop agreement expired at midnight December 31, pr etical advanced anaytte methods to 1995. After that date, EURATOM licenses improve predictions of passure vessel (PV) authorizing export of reactors, special nuclear fracture and assess integrity of PVs under material, or source material for nuclear uses y rious operatmg conditions become invalid (i.e., they will expire or be e reviewing data from researchers in Russia, suspended). A separate exchange of notes, '
expected to take place between the U.S. and the Czech Republic, the United Kingdom, . EURATOM, will allow the NRC to contmue t and other East and West European countries authorize nuclear-grade graphite, deuterium, and related to reactor PV embrittlement under reactor components to EURATOM after intensive neutron bombardment and thermal December 31,1995, without interruption, annealing of the vessel to mitigate embrittlement effects Chapter 9 (RES) provides additional details on these activities. COOPERATIVE NUCLEAR SAFETY RESEARCH EXPORT AND IMPORT The NRC conducts confirmatory regulatory LICENSING research in partnership with nuclear safety agencies and institutes in more than 20 countries. Much of this activity is concentrated in three major subject areas: NRC'S EXPORT / IMPORT ROLE
- (1) severe accident research Under the Atomic Energy Act of 1954, as amended, the NRC is responsible for licensing the (2) thermal / hydraulic code maintenance and export and import of nuclear-related materials assessment and equipment to ensure that these items are
,, , , used only for peaceful purposes. This authority (3) pipmg integrity and material research extends to production and utilization facilities, special nuclear and source material, byproduct More than 60 agreements are currently in force materials, certain nuclear-related components, covering the NRC's international research work. and other materials.
Such agreements provide for shared use of research facilities, joint funding arrangements, In carrying out these responsibilities, the NRC prompt exchange of experimental results, obtains the views and recommendations of other coordinated analyses, and other forms of governmental agencies and departments as . cooperation to yield confirmatory safety data of needed or required. The NRC is also consulted by ! mutual benefit in a timely and cost-effective the Executive Branch on nuclear-related, dual-use manner. exports licensed by the Department of Commerce
171 . 1 l (DOC), as well as nuclear technology transfers e assorted by-product materials for DOE use and nuclear material retransfers (subsequent in work on the spent fwl pool at arrangements) licensed by the DOE. In addition, Nyongbyong, North Korea i the NRC is consulted by the Department of State j (DOS) regarding agreements for nuclear > cooperation between the United States and other countries. NUCLEAR SUPPLIERS GROUP The NRC published new regulations, effective November 4,1994, that conform its export c ntrols to the international Nuclear Suppliers NRC EXPORT LICENSING Group (NSG) Guidelmes for exports of dual-use
SUMMARY
commodities. The NRC participated in the April 1995 NSG Plenary Meeting and dual-use consultations in Helsinki, Finland. Representa- 1 In FY 95, the NRC completed 105 export licensing tives of 30 member states attended, including new i actions. Of these, approximately 70 involved members New Zealand and South Africa. I exports of natural and low-enriched uranium for Ukraine was an observer. The NSG agreed to use in reactors in Western Europe, Indonesia, place controls on technology associated with all Japan, South Korea, and Taiwan; 8 covered trigger list items and to require government , reactor component exports to Argentina, Eastern assurances for retransfers of those items. A 1 Europe, Nomay, and Russia; 3 were amendments working group was created to review the graphite of previously issued power reactor export licenses entry to resolve the issue of whether large to Taiwan and Switzerland; and I authorized quantities of graphite can be exported to a shipments of depleted uranium components to the county without fullscope safeguards for Sellafield reprocessing facility in the United nonnuclear end use. The NSG encouraged efforts Kingdom. Among the other cases in 1995, one to maintain contacts with the New Independent authorized the DOE to export low-enriched States of the FSU. In addition, the NSG held its uranium (and one-half gram of plutonium)in first meeting for the purpose of information i nitric acid solutions to the Sellafield reprocessing sharing among members and affirmed the I facility; another authorized shipment of heavy principle of transparency in exporting nuclear l water to Canada for upgrading and return to the items. I National Institute for Standards and Technology l (NIST); three involved tritium exports to Canada, l Switzerland, and the United Kingdom for use in l light sources or industrial equipment; and several SUBGROUP ON NUCLEAR EXPORT others involved natural uranium, depleted uramum, and thorium exports for nonnuclear COORDINATION (SNEC) industrial, munitions, or resource-recovery uses. The remaining cases included several exports of The NRC continued to participate in this l small(gram quantity) samples of nuclear material interagency body, which meets regularly to reach ; for laboratory, calibration, or safeguards use, as consensus decisions on nuclear export licensing i follows: activities that may raise nuclear proliferation concerns. Export cases licensed by DOC and o high-enriched uranium for use in laboratories NRC and nuclear technology transfers authorized in Italy, Japan, and South Korea by DOE are referred to SNEC because of country destination, concerns about the end user / commodity, the precedent-setting nature of the o 19.9 percent low-enn.c hed uranium for use by proposed export, or by agency request. Most of the IAEA's Seibersdorf LaboratoU the cases reviewed by the SNEC are dual-use exports. The number of cases continues to o neptur Nm-237 for Germany's Karlsruhe decrease as a result of revisions to DOC licensing Resea > Center controls over computer exports.
172 DEPARTMENT OF ENERGY ASSISTANCE TO FSU IN NUCLEAR TECHNOLOGY TRANSFERS MATERIALS SAFEGUARDS AND PHYSICAL PROTECTION In 1995, the NRC worked with DOE to process two technology transfer cases, the first involving The Nunn-Lugar legislation was enacted by the approval of a Combustion Engineering-French United States to support the destruction of CERCA joint venture to produce TRIGA fuel, nuclear, chemical, and other weapons of mass and the second involving the transfer of PWR destruction in the former Soviet Union and to technology and fuel to Ukraine. As part of a carry out other nonproliferation-related activities. cooperative project involving the U.S., the IAEA, Under this legislation, a Safe and Secure the Russian Federation, and the European Union, Dismantlement (SSD) interagency group (which is the NRC issued an exemption permitting DOE to now known as the Cooperative Threat Reduction distribute four grams of plutonium to Russia for (CTR) Program) was established a few years ago isotopic separation at the International Science to assist the FSU in dismantling nuclear weapons. i and Technology Centre. This material will subsc- The group's activities include supporting the quently be transferred to Belgium's Institute for development of national systems for nuclear Reference Materials and Measurements for materials control and accounting (MC&A) and assembly into certified reference materials for physical protection. distribution to the IAEA, the United States and other users for safeguards-related applications. Under the auspices of the CTR program, the The DOE also consulted the NRC on a NRC and DOE have established bilateral subsequent arrangement involving Switzerland technical assistance programs with Russia, and the United Kingdom. Ukraine, and Kazakstan to help these countries improve their capabilities to effectively safeguard nuclear facilities and materials. The Presidential Decision Directive on Nuclear Materials Security issued in September 1995 indicated that the NRC, mainly through efforts to strengthen the Russian INTERNATIONAL re8ulatory body (GAN), would support the high-priority U.S. effort to strengther controls on SAFEGUARDS AND nuclear materials in the FSU so they do not
' "t'ib te t the proliferation of a nuclear PHYSICAL PROTECTION explosn?es capability.
ACTIVITIES The NRC staff reviews pending export cases to OTHER PHYSICAL PROTECTION confirm that appropriate IAEA safeguards and ACTIVITIES physical security arrangements will be applied to exports by the receiving country. Reviews are In support of its review of physical protection performed in conformance with U.S. arrangements for U.S.-controlled materials in nonproliferation laws, which are intended to other countries, the NRC participates jointly with ensure that U.S. exports will be protected and other U.S. Government agencies in information safeguarded during transit and use in the exchange trips for the purpose of discussing importing country, and that exports will be used national physical protection programs. During only for peaceful purposes. FY 95, visits were made to Thailand, Taiwan, Philippines, Spain, and Portugal. Similarly, teams The NRC also participates in the U.S. Program of from Canada and France visited the NRC and i Technical Assistance to IAEA Safeguards NRC-licensed facilities. (POTAS), which provides the largest share of voluntary technical support of any IAEA member Additional information on items discussed in this state, section can be found in Chapter 5.
173 in favor of indefinite extension. South Africa NUCLEAR proposed calling for indefinite extension along NONPROLIFERATION with strengthening the review process, mainly i through the creation of a virtually permanent I ACTIVITIES body that would meet between review conferences l for both substantive and procedural discussions, as well as to adopt a set of nuclear nonprolifer-ation and disarmament principles to measure Progress in the NPT implementation. This U.S. NONPROLIFERATION POLICY proposal became the basis for a set of measmes to strengthen the review process, ano a set of
. The United States continues to provide strong nuclear nonproliferation and disarmament support for the Treaty on the Nonproliferation of principles and objectives for the purpose of Nuclear Weapons (NPT), for the IAEA and its determining progress in states' compliance with safeguards role, and for multilateral export the Treaty.
4 controls. The three hiain Committees also submitted l i reports on their respective review activities. The Main Committee I report on arms control issues NPT EXTENSION AND REVIEW reflected the minimal agreement ainong its embers, with particular disagreement with CONFERENCE regard to nuclear disarmament and security assurances. The Main Committee II report, 4 During the FY 95 reporting period, two NPT covering safeguards issues, showed greater conferences were held. In January 1995, the member agreement. Af ain Committee III, charged Fourth Preparatory Committee (PrepCom) with reviewing the assistance and cooperation convened, and in April and hiay 1995, a among NPT members, emerged with virtually a conference to extend the NPT took place in New consensus report. Carlton Stoiber, Director, OIP, York. The Fourth PrepCom focused its represented the U.S. Government on hiain discussions on the rules of procedure for the Committee III. Review and Extension Conference. Specifically, discussions concerned the way in which the With a majority of the states party to the Treaty in decision to extend the Treaty should be made, and favor of its indefinite extension, the Conference whether the vote should be secret or open. Neither ended with the decision to continue the Treaty in of these issues was resolved at the Fourth force indefinitely. The Conference also adopted a PrepCom. Final Report reflecting the decision, but without a Final Declaration consensus with respect to the The Extension and Review Conference was results of the review and decisions to attended by delegates from 175 of the 178 states (a) strengthen the review process for the NPT and then party to the Treaty. Early on, it became (b) develop principles and objectives for nuclear obvious that there would be a numerical majority nonproliferation and disarmament. f 4
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NUCLEAP, REGULATORY RESEARCH This chapter summarizes RES activities during Activities of the NRC Office of Nuclear FY 95 under the following major headings: Regulatory Research (RES) constitute an essential service to the regulatory process that are vital to Reactor Regulation (which addresses reactor implementing a number of the agency's programs. aging and renewal, as well as reactor safety assessment and regulation development), The goal of the office is to ensure the availability of sound technical bases for timely rulemaking Standard Reactor Designs, Materials Users, and related decisions in support of NRC licensing Low-Level Waste and Decommissioning, and and inspection activities. RES also has fligh-Level Waste. responsibilities related to implementing Commission policies on safety goals and severe accident regulation, resolving generic safety issues, and reviewing licensee submittais . REACTOR REGULATION regarding mdividual plant examinations. It is the responsibility of RES to conduct the NRC's rulemaking process, including issuing regulatory s nd rules that govern NRC-licensed REACTOR AGING AND LICENSE RENEWAL Appendix 5 lists regulations issuert by the NRC during fiscal year 1995 (FY 95), while Appendix 6 Pressure Vessel Safety describes and lists regulatory guides issued, revised, or withdrawn during FY 95. This area of NRC research focuses on ensuring the structuralintegrity of the reactor system Pursuant to the Small Business Research and pressure boundary; that is, keeping the boundary Development Enhancement Act of 1992, Pubh. c leaktight and free from damage. The underlying Law 102-564, the NRC supports the Small concern in this research is that failure to ensure Bus,mess Innovation Research (SBIR) program. the integrity of the pressure boundary could As of FY 95, the NRC was supportmg 28 SBIR compromise the operator's ability to cool the projects in progress. reactor core, and could lead to a loss-of-coolant accident (LOCA) accompanied by the release of In 1995, the NRC staff continued to participate in hazardous fission products. national standards activities, particularly with Since its initiation in 1967, research in this area respect to setting priorities. NRC participation has evolved into a broad-based program. Initially, derives from a need for national standards to define acceptable ways of implementing the the program focused on the properties rd fracture behavior of the reactor pressure vessel NRC's basic safety regulations. Approximately 100 NRC staff members serve on working groups (RPV) the large, thick-walled steel cylinder that houses and supports the reactor core. As the organized by technical and professional societies.
176 NRC realized the full challenge of ensuring the integrity of this critical component, the staff continued to develop improved analytical methods, and to evaluate those methods against modified the scope of the research program to include irradiation damage, service-induced test data developed as part of this program by the ORNL, PNL, NSWC, and the National Institute cracking mechanisms, and methods for for Standards and Technology (NIST). This work periodically inspecting the RPV. Since then, permits evaluation of test geometries and loadings incidents of cracks and leaks in piping and steam that are more typical of RPVs in the ductile-generator tubes have highlighted the need for to-brittle fracture toughness transition region in materials data, analysis methods, and inspection the operating temperature range. The researchers techniques for these components, and the have also made significant progress in research program was again modified to meet the determining the effects of shallow flaw constraint added challenges. on fracture toughness of RPV steels under realistic biaxial loading, and on the effect of To put the results of past research into practice, the NRC has implemented regulations, regulatory fracture-mode conversion from ductile to brittle in the transition region. The researchers are also guides, the Standard Review Plan, and various coordinating their work with international national codes and standards. Future work will research efforts, through a cooperative project on provide the bases for confirming and revising fracture analysis of large-scale experiments, under some of the earlier regulatory positions, with the the auspices of the Committee on Safety of overall objective of providing a stable, well-Nuclear Installations. Collaborative efforts with validated regulatory framework for ensuring the another European Community program are well integrity of the primary pressure boundary. The under way, and are expected to yield results from technical espects of the research program- a large-scale test that will closely simulate an RPV fracture evaluation and irradiation subjected to accident loads. This will provide a embrittlement-are central to sound regulatory more realistic validation of the revised analysis positions addressing the safe operation of the methods. RPV. For example, results from the pressure vessel safety research program were used to revis During FY 95, NRC issued Regulatory Guide the basis for determmmg the allowable operatmg 1.161 to provide guidelines for assessing the pressure and temperature limits to preclude integrity of RPVs fabricated from materials with brittle failure of the RP\. low resistance to a " ductile tearing" failure mode. In the early 1970s, the NRC recognized that some RPVs were fabricated using steel plates and weld l types that were less resistant to ductile tearing FRACTURE EVALUATION than most other plates, forgings, and welds used l I in RPVs. In 1973, the NRC issued Appendix G to During FY 95, the development and validation of 10 CFR Part 50 to provide explicit requirements fracture analysis methods played . large role in concerning the Charpy upper-shelf energy-a the overall pressure vessel safett research measure of the ductile teanng resistance of these program. Fracture analysis involves an ongoing materials-for both new construction and program to develop and implement advanced operatmg plants. The American Society of analysis methods that will improve the ability to Mechanical Enginects (ASME) published predict the allowable pressures and temperatures Appendix K (Section XI, Division 1, February for RPVs, and to evaluate the integrity of RPVs 1993), which addressed this issue, but did not under design-basis and hypothetical accident include complete details for all the potential conditions. loading conditions for RPVs. In addition, OzAppendix K did not include guidance on Researchers at the Oak Ridge National determining appropriate material properties for Laboratory (ORNL) and the Pacific Northwest use in the evaluation method. In September 1993, Laboratories (PNL) perform the core studies, the RES staff published a draft regulatory guide augmented by researchers at Brown University, to supplement the ASME Code guidance that the University of Illinois, and the U.S. Naval includes evaluation methods pertment to all Surface Warfare Center, Annapolis Detachment service loading conditions, as well as guidance for (NSWC). During FY 95, these researchers selecting transients for consideration at various
177 service load levels and estimating material pressure vessel wall during plant operation. properties. In FY 95, the staff analyzed the public Through a complex process, these neutrons comments on the draft regulatory guide, and u7ed reduce the ability of the steel to resist fracture. the comments in preparing the final guide, which was subsequently issued. Consequently, the research program devotes significant attention and resources to quantify the During FY 95, the RES staff worked with effects of neutron radiation embrittlement, to researchers at the ORNL and PNL to develop understand the mechanisms that control this technical bases, founded in probabilistic fracture process, and to find methods to mitigate the mechanics, to revise Regulatory Guide (RG) 1.154, embrittlement and restore the original fracture which addresses plant-specific evaluation of toughness of the RPVs: pressurized thermal shock in pressurized-water reactor (PWR) RPVs. In accordance with lessons e measuring toughness changes with increasing learned from the Yankee Rowe RPV integrity levels of neutron embrittlement evaluation, SECY-92-283, additional research was coordinated with the efforts of staff specialists in
- recovering toughness of embrittled stecis thermal-hydraulics and probabilistic risk through thermal annealing assessment (PRA) for use in resising RG 1.154.
Development of the technical bases is planned for
- modeling embrittlement mechanisms completion in FY 96, and the draft revisions to the regulatory guide are expected to be published
- developing a better understanding of the in 1997. original chemistry of RPV welds In FY 95, with support from the Nuclear Energy
- using small surveillance specimens to !
Institute (NEI), the RES staff organized and held produce direct measurements of fracture a public workshop concerning RPV integrity. The toughness 1 objectives of the workshop were to discuss technical improvements in nuclear RPV In FY 95, research continued on development of a operation, maintenance, and inspection, and to Physical model of the neutron embrittlement achieve a mutual understanding of the progress Process. This included atom probe field-ion and plans made by industry and government in microscopy of neutron embrittled copper bearing the area of RPV integrity. Workshop participants steel, which was used to identify and analyze discussed a variety of specific issues: copper-rich precipitates (CRP). These CRPs are believed to be responsible for the increased o the impact of steel chemistry variability on hardness and loss of toughness in copper-bearing vessel integrity weld metal in many RPVs. The results of this work have been published in the open literature o RPV annealing to recover fracture toughness and in NUREG/CR-6231. Concerns about the effects of copper content on the sensitivity of o recent progress in model development to welds to embrittlement resulted in an assess recovery investigation of the copper distribution along and through welds, using weld metal from the nozzle o efforts to improve analyses and approaches and beltline of an operating RPV. The study, being considered by the NRC in revising RG which was reported in NUREG/CR-6249, also 1.154 quantified the measured variations in unitradiated weld impact and fracture toughness levels. RADIATION EMBRITTLEMENT As a result of activity concerning the properties of weld metal from steam generators removed from In ensuring the integrity and continued safe the Palisades (Michigan) nuclear power plant, the operation of RPVs, a special concern is the research staff performed a study during FY 95 to increasing embrittlement of the pressure vessel determine the effects of thermal aging on the steel caused by neutrons that impinge on the toughness of RPV steels. No significant trends
178 were observed regarding thermal embrittlement in Society for Testing and hiaterials (ASTM)is U.S. RPV steels. continuing to confirm the re-embrittlement behavior of thermally annealed steel. During FY 95, ORNL and SRI used small surveillance specimens to produce direct measurements of fracture toughness. Tin.s During FY 95, the NRC and the DOE developed and implemented a Memorandum of research yielded encouraging results usmg precracked, notched, round bars and precracked Understanding (MOU) concerning NRC Charpy specimens. Couph,ng these small participation in the DOE Annealing Demonstration Projects (ADPs). The MOU specimens with the Master Curve', approach-a recognizes the mutualinterest of the NRC and Weibull statistical analysis of fracture toughness DOE in the ADPs, and establishes a framework transition curves-may provide an alternative t for cooperation and coordination of activities. mferring changes in fracture toughness from standard Charpy surveillance specimens. To demonstrate the engineering feasibility of Also during FY 95, ORNL continued to measure thermal annealing, two separate industry the changes in material strength, impact consortia will perform the ADPs during 1996 toughness, and fracture toughness that result from using the reactor vessels at the cancelled Marble neutron embrittlement. The materials included Hill and Midland facilities. NRC activities will submerged-arc welds with a range of copper include independent review of the two test i concentrations representative of welds in the facilities, independent analysis of thermal and United States and A302B steel weld heat. stress distributions that would result from affected-zone material. This long-term research annealing, and possible independent requires neutron embrittlement of materials in instrumentation of both facilities. These activities research reactors and mechanical testing in hot are intended to facilitate understanding of the cells. Through this research, ORNL will determine ADP results to confirm the adequacy of the the sensitivity of changes in weld copper content, Proposed NRC thermal annealing rule (10 CFR as well as whether the ductile-to-brittle transition 50.66) and the supporting draft regulatory guide. region of the fracture toughness curve changes The results from the two ADPs are anticipated to shape with a shift in transition temperature. This Provide a basis for annealing, and possible research is necessary to develop better empirical independent instrumentation of both facilit,ies. relationship between Charpy impact toughness behavior and fracture toughness for regulatory In independently assessing the engineering Purposes. feasibility of the two ADPs, the NRC will develop thermal and stress analysis models for the key Thermal annealing is the only known way to reactor system components affected by the reverse the effects of neutron embrittlement of demonstration annealing, including the RPV and RPV steels. Research confirmed the efficacy of reactor coolant system piping, as well as the annealing, and provided background information surrounding reactor cavity concrete wall and for the draft annealing rule,10 CFR 50.66, and insulation. By analyzing these models, the NRC draft supporting regulatory guide that were issued will then predict thermal response and resulting for public comment in FY 95. The NRC has deformations, strains, and stresses in key reactor addressed the public comments, and expects to system components at the two ADP plants. In issue the final rule early in FY 96, with the guide addition, the NRC will take selective to follow shortly thereafter. The guide provides measurements at the two ADP sites during the embrittlement recovery equations, developed as demonstration annealing, and will derive a part of the research program, that licensees can comprehensive interpretation of the use to determine the impact toughness recovery DOE / industry and NRC measured data. On the expected from thermal annealing. The equations basis of this interpretation, the NRC will then include the effects of copper concentration, recommend instrumentation plans for future irradiation temperature, and flux, along with annealing of U.S. RPVs. The NRC plans to issue thermal annealing time and temperature. its independent assessment and final reports Research in cooperation with the American within 6 months of each demonstration anneal.
179 Environmentally Assisted Cracking Inspection Procedures and Techniques In recent years, the industry has becom mereasingly concerned with intergranular stress INTERNATIONAL PROGRAMS corrosion' cracking (IGSCC) in BWR piping systems and, in general, with the integrity of The NRC has been a leader and active participant piping as reactors age. This concern has led to in the Program for the Inspection of Steel increased research on piping integrity, as part of Components, Phase III (PISC III), which reached the overall pressure boundary integrity research closure in FY 95. The participants m this program. mternational program, organized in 1986, have invested an estimated $40 million, including contributions of materials, inspection services, During FY 95, Argonne National Laboratory and manpower, to assess the effectiveness of (ANL) conducted extensive research on the effects nondestructive testing technologies and of LWR coolants on fatigue life of reactor coolant Procedures for inservice inspection (ISI) of system components. The ANL findings supported nuclear power plant components. Participants in Japanese research and observations that the PISC III research focused on the nondestructive present ASME Code design curves may not testing of LWR primary circuit components adequately account for such coolant effects. In containing realistic flaws. The results of the addition, the ANL research yielded significant Program will assist regulators and code-making information on dependence of fatigue life on the bodies in establishing technical bases for rate of loading. This information will be used in improving ISI requirements. applying laboratory data to cumulative usage factor calculations, as an essential aspect of NRC S.mce the program reached closure during FY 95, evaluations of the service life remaining in aging Participants have published reports to document the studies. These reports included prehmmary plants
- results for steam generator tube:,, which revealed a significant variation in flaw detection capabihty among the 17 teams participating in this study.
This variation, compounded by the relatively low Core Internal Components performance of several teams, indicates the need to upgrade the capability of ISI techniques and As reactors age and core components accumulate teams; Similarly, the PISC III results revealed that Daw sizing was inaccurate, and there was little higher fluence, irradiation-assisted stress , corrosion cracking (IASCC) of reactor core '. relation (that is, sigmficant error) between the estimated and true sizes (depth. length) of the internal components is becoming more common n ws. in both BWRs and PWRs. Because some affected components, are difficult or impractical to replace, During FY 95, teams from the United States, it is mereasmgly important for the NRC to assess Japan, Europe, and Russia completed round the potential for IASCC in particular materials, robin studies of service-degraded stainless steel the residuallife of affected components, and the pipes with stress corrosion cracks removed from potential consequences of repair measures- U.S. plants. These studies will provide an international database for assessing the reliability of the ISI of stainicss steel piping. During FY 95, research on test specimens cut from components of operating reactors was supplemented by specimens prepared from carefully characterized material and irradiated in FABRICATION FLAW DENSITY AND the Halden reactor in Norway. As a result, DISTRIBUTION IN REACTOR PRESSURE researchers are making important progress VESSELS toward identifying the impurities most important in IASCC of materials commonly used in core An important parameter in structural integrity components. assessments of the reactor pressure vessel is the
180 size, distribution, and density of pre-existing In response to these safety concerns, the NRC flaws. However, until recently, little data existed has, since 1977, sponsored a series of research on this topic. programs on tube integrity and inspection. These programs developed quantitative relationships for During FY 95, a reactor pressure vessel from a Predicting the burst pressure of degraded steam cancelled plant was inspected using the Synthetic generator tubm, g as well as leak rates through Aperture Focusing Technique for Ultrasonic cracked tubes. 'Du,s work provides an independent Testing (SAFT-UT). This improved method for verification of similar relationships developed by reliably and accurately detecting and sizing flaws the mdustry. NRC research also developed has been developed through extensive laboratory samplmg plans for ISI of degraded steam testing and validated through blind trials. The generators as well as performance demonstration SAFT-UT study at the cancelled plant yielded an enteria to help ensure their effectiveness of ISI extensive database, which was analyzed to systems used to detect and ssze flaws. evaluate and size the flaws detected. This analysis revealed that very high-sensitivity m, spections were The results of these research programs have performed, and the majority of the flaws were helped to ensure the safe operation of nuclear quite small (less than a few millimeters m size). In steam generators; however, in recent years, stress addition, the extensive database provided corrosion cracking has become the most sufficient flaw numbers m, different size categories widespread mode of tubing degradation. This to develop statistically valid flaw size and density nereased incidence of cracking in steam distributions. The results mdicate that the ratio of generator tubes has occurred at the top of the i flaws between the weld metal and the plate metal tube sheet, at tube support plates, in regions of is lower than normally assumed. Results from this sludge accumulation, and in the tube free span. l At the tube support plate locations, the study will be validated through destructive testmg of material removed from the reactor pressure morphology of the cracking observed is often vessel. distinctly different from that observed at other locations, with cracking commonly occurring in the form of numerous short segments separated by uncracked ligaments. Steam Generator Integrity In FY 95, the NRC initiated a new research program at ANL to provide the data and Corrosion problems m. PWR steam generator methodologies needed to independently evaluate tubes can be traced back as far as 1957 to the Shippingport reactor, the first commercial PWR and assess industry proposals for ensuring steam generator tube integrity. This new research operated in the United States. In early 1993, the program is divided into four tasks. The objective Trojan nuclear plant was shut down long before the end of its design life, m part because of severe of the first task is to evaluate and quantify the reliability of the current ISI methods for steam steam generator tube degradation problems. By generator tubes. The second task will evaluate the end of 1995,38 steam generators m 13 PWRs had been replaced in the United States because of advanced nondestructive examination and signal analysis techniques for ISI of original and senous tubmg degradation, and the replacement repaired steam generator tubes, and will develop of 24 additional steam generators at eight plants was planned. improved correlations between eddy current results and flaw morphology, leak rate, and failure pressure. The objective of the third task is to Steam generator tubing degradation is a evaluate and experimentally validate models for potentially significant safety concern, as well as an predicting potential degradation modes, important economic problem, for the utility progression rates, leak / rupture behavior, failure industry. Steam generator tube leaks and ruptures pressures, and leak rates for original and repaired can result in containment bypass leading to the tubes under normal operating, accident, and release of radionuclides to the environment. Tube severe accident conditions. The final task of this i ruptures also result in the loss of primary reactor new program will be to synthesize the data, l coolant, which can significantly exceed the results, correlations, and models from the makeup capacity of the charging pumps. previous tasks to provide technical assessments l
~
181 and evaluations of current and emerging e Detection of Pump Degradation regulatory issues related to steam generator tube (NUREG/CR-6089) integrity. Work on this new program began late FY 95, and will continue for approximately 5
- Aging and Service Wear of Spring-Loaded years. Interim results will be available during the Pressure Relief Valves Used in Safety-Related course of the project. Systems at Nuclear Power Plants (NUREG/CR-6192) e Effects of Aging and Service Wear on Main Aging of Reactor Components Steam Isolation Valves and Valve Operators (NUREG/CR-4246) e Review of Monitoring and Diagnostic AGING RESEARCil Methods for Motor-Operated Valves Aging affects all nuclear reactor structures, systems, and components. If aging degradation is e An Evaluation of PWR Safety Injection not detected and corrected, it can increase risks Accumulator Tank Discharge Check Valve to public health and safety. Failures of Performance (ORNUNRC/LTR-95/22) safety-related components have occurred in the past because of age-related degradation processes
- A Characterization of Pump and Pump such as corrosion, embrittlement, wear, and Motor Degradation and Failure Experience in fatigue. The objectives of aging research are to the Nuclear Power Industry develop the technical bases for continuous safe (ORN11NRC/LTR-95/24) operation of nuclear power plants; to define the operative aging mechanisms; to confirm the
- Large Eectric Motors (NUREG/CR-6336) effectiveness of existing detection and mitigation e Contam. ment Isolat. ion Funct. ion methods; and to develop recommendations for new detection and mitigation methods. Aging (NUREG/CR-6339) research also provides information and technical e Electrical Surge Protective Devices {
bases useful m understandmg the effects of agmg I on the safety functions of electrical and (NUREG/CR-6340) ) mechanical components.
- Applications of Reliability Degradation f Analysis (NUREG/CR-6415) i Dunng FY 95, preh. .mmary or comprehensive l agmg assessments were completed, or final reports were issued, for the following AGING EFFECTS ON MOTOR OPERATED l as late spec al opics VALVE PERFORMANCE In FY 95, research efforts continued to determine o Boiling Water Reactor High Pressure whether corrosion can affect the torque and thrust Injection Systems (NUREG/CR-5462) requirements of the mternal parts of motor-operated valves (MOVs). This information is o Transformers (NUREG/CR-5753) necessary to assess the performance of MOVs, particularly when they are needed to mitigate o Evaluation of Inspection, Surveillance, and accident conditions. Friction experiments were Monitoring Methods for the Class 1E Power conducted on samples of corroded materials and Reactor Protection Systems typical of certain valves. The test results indicate (NUREG/CR-5719) that corrosion increases the thrust requirements.
However, the results also indicate that, for the o Aging of'Ibrbine Drives for Safety-Related material tested, the effects of friction do not Pumps in Nuclear Power Plants change after long periods in typical nuclear plant (NUREG/CR-5857) water environments. This latter finding is very
182 important because motor-operator outputs may information on the use of digital I&C equipment not need to be readjusted after iong periods of in nuclear power pl;mts, the experience of military service. Additional experiments were started in applications has been used in this work. So far, FY 95 to determine the effects of corrosion on researchers have completed an example other materials that are also typical in MOVs. application showing that, for a PWR plant, lightning-related (EMI) events and humidity Information derived from this project is associated with high temperatures can impose important to the NRC because it can be used to significent risks. Additional evaluations will be evaluate the capability of MOVs during the made during FY 96. periodic verification phase outlined in Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance." , AGING OF PASSIVE COMPONENTS l Earlier research established an approach for PRA-BASED METHODOLOGY FOR AGING determining the aging effects of active ASSESSMENTS AND RANKING CmnPonents (pumps and valves) on plant risk. ASSIGNMENTS H wem, the agmg effects of passive components, such as pipes and structures, could not be l analyzed until a similar approach was completed 1 In FY 95, work continued on evaluating the in FY 95. Consistent with the approach for active effects of component aging on plant risk, with components, the new approach uses available specific focus on determining whether changes to engineering information to estimate failure rates inservice test (IST) intervals for check valves can associated with the aging of passive components. influence risk. When coupled with ranking information, the results of this work will provide the regulatory staff with the technical basis for evaluatmg heensees submittals for extending IST AGING EFFECTS ON TURBINE DRIVES intervals on safety-related check valves. These types of engm, eermg applications will also provide In 1995, the staff oversaw a study to examine the guidance to determme which dommant aging relationship between time-dependent degradation and current industry practices in the areas of stressor (s) should be monitored and mamtamed durm, g ISTs. maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the auxiliary feedwater (AFW) system for PWRs, and in the reactor core REPLACEMENT OF AGED isolation cooling (RCIC) and high-pressure INSTRUMENTATION AND CONTROL coolant injection (HPCI) systems for BWRs. This research entailed examm, m g failure data m the EQUIPMENT Nuclear Plant Reliability Data System (NPRDS), reviewing Licensee Event Reports, discussing During FY 95, work continued to assess the effect problems with operating plant personnel, and of replacing aged analog mstrumentation and conducting personal observations. The reported control (I&C) equipment with digital I&C failure data were reviewed to determine the cause equipment. This work was initiated in FY 94 to of the event and the method of discovery. study the effects of operational and environmental stressors on the long-term performance of digital Based on the research results, attempts have been I&C equipment. Environmental stressors have made to determine the predictability of failures been ranked according to their impact on the and possible preventive measures that may be operability of digital I&C and plant risk. implemented. In addition, the study has shown Specifically, the environmental stressors being that turbine pump drives have the capability to considered in this work include humidity, function in a reliable manner. Although 20 temperature, vibration, smoke, radiation, and percent of the failures noted in 1991 were electromagnetic interference /radiofrequency discovered under demand circumstances, the data interference (EMI/RFI). Because of limited evaluated between 1984 and 1991 generally
183 indicate a decreasing trend in the number of populations used in nuclear plants found that the failures detected during demand conditions. Also, squirrel cage induction motor was the most widely the number of failures detected by programmatic used. A review of the failure records contained in methods increased 21 percent between 1984 and the licensee event report and NPRDS databases 1991(from 48% to 69% of the total failures per indicated that a significant portion of the reported year). (These methods include routine testing, failures were attributable to normal aging
- walkdowns, and scheduled preventive degradation of the motors, subcomponents, maintenance.) This is a positive trend since it is support equipment, and materials. The preferable that failures be detected components most often contributing to large programmatically, rather than in demand motor failure were bearings, stator windings and situations. Experience and education appear to a insulation, terminations and motor leads, shafts major role in the observed trend. and couplings, and motor mounts. A review of plant maintenance programs indicated that these programs are based on manufacturer recommendations. The additional maintenance, AGING ASSESSMENT OF SURGE monitoring, and surveillance received by Class 1E PROTECTIVE DEVICES pump motors was found to result in improved ;
operating performance. ! Devices commonly known as surge arresters and surge suppressors are used extensively in nuclear power plants to protect electrical power and EQUIPMENT OPERABILITY control systems from overvoltages mduced by lightning and switching transients. Their
, For the past 6 years, the NRC has made applications are important m mmimizmg significant progress in advancing the i imtiat,ng i event frequencies associated with loss of understanding of MOV technology. During FY 95, l offsite power and reactor trips. However, aging efforts continued to evaluate the effects of failures of these devices may result in the same reduced voltages and elevated temperatures on events through a short ciremt or overvoltage. the efficiency of motor-operators, which are Fifteen years of operatmg data were reviewed as essential to opening and closing MOVs. Current part of this, study. Short circuits were found to be industry guidelines provide licensees with the predommant failure mode, and, for some technical information for specifying the low-voltage suppressors, an open circuit was capabilities of their specific motor-operators.
found to follow short circuits. Although the However, the guidelines may be overstated when frequency and type of surve,llance i testing was these components are subjected to reduced found to vary s. Jely among plants, suppressor voltage and elevated temperature conditions that testmg on plant systems on which they are are typical of some nuclear plant installations.
- mstalled was generally not performed. Failure
- frequencies for lightning-induced loss of offsite Results obtained from this research over the past power events were found to be low. 6 years are being used by the NRC to evaluate the Electric Power Research Institute (EPRI) report on MOVs. This 25-volume report presents the EPRI MOV research findings that the licensees AGING ASSESSMENT OF LARGE will rely n in meeting the provisions of GL 89-10.
ELECTRIC MOTORS , The NRC evaluation will be completed early in FY 96. Electric motors, rated at more than 500 hp, operating at 4 kV or above, serve as the prime Other research efforts under this program focused movers for various systems. Their applications on updating the computer program, developed in include both safety-related and non-safety-related a prior year, that provides the NRC regulatory ! nuclear process and balance-of-plant systems. By staff with a user-friendly tool for performing virtue of their large size, these motors provide difficult MOV calculations. The program now important roles in safe and reliable operation in incorporates the current technical information nuclear plants. The review of large ac motor resulting from the research efforts completed over
184 the past 2 years. In addition, a computer program additional work. An additional six topics were was developed to evaluate licensee MOV found to be unresolved, but did not warrant measurement data that are obtained directly from further research in this program. The remaining l in situ tests. When completed in FY 96, this latter 19 topics were found to be unresolved, and ' program will provide the regulatory staff with additional work was recommended in these areas. j another tool for quickly assessing and resolving The results of the literature review will be j specific MOV problems that frequently arise incorporated into the test plans that govern the j during nuclear plant MOV inspections. future work for this program. j Also in FY 95, the Idaho National Engineermg l Laboratory (INEL) performed an evaluation of 1 ENVIRONMENTAL QUALIFICATION the Class 1E power system, including RESEARCII transformers, and the reactor protection system (RPS). The results of the study indicated that the NRC staff activities related to license renewal, m j rity of the RPS components in the 1E power identified environmental qualification (EQ) of system are outside the scope of 10 CFR 50.49. electric equipment as an area that required RM cpmponents that must demonstrate , further review. A major concern related to C mPhance with EQ requirements are electncal whether the EQ requirements for older plants Penetrations and some connections, cables, cable were adequate to support license renewal. sphces, and sensors / transmitters. With the Consequently, the staff concluded that difrerences exception of cables, these RPS components will be in EQ requirements between older and n.:wer covered by the maintenance rule, which requires plants constituted a potential generic issue that identification of performance or condition goals should be evaluated independent of license that define whether the equipment is capable of renewal. fulfilhng its intended function. As a first step in responding to an NRR task action plan on environmental cualification, RES SAFETY-RELATED PUMP DEGRADATION held a public workshop to obtain technical input from industry representatives, as well as from In 1995, the NRC issued a Phase II Nuclear Plant experts in the field. This workshop determined Aging Research study report in which the staff that a great deal of work has already been evaluated various methods of detecting pump performed that may be useful in fully or partially degradation that are currently employed in resolving some of the questions and concerns domestic and overseas nuclear facilities. This related to EQ. Therefore, a literature review was report also evaluated the pump testing criteria undertaken to obtain and evaluate significant past used in U.S. nuclear power plants, comparing research, including both domestic and foreign them to features characteristic of advanced work. The purpose of this review was to optimize diagnostic programs and practices currently this research program and avoid duplication of implemented by other major industries. In effort. addition, since the working condition of the pump driver is crucial to pump operability, the report The literature review was completed in FY 95, briefly reviewed new applications of motor and the results were documented in draft diagnostics, highlighting recent developments in NUREG/CR-6384. This two-volume report this expanding technology, includes summaries of the work reviewed, along with an analysis of the work in relation to the The Phase Il report also discussed vibration issues of interest in this program. A total of seven spectral analysis, the most powerful diagnostic major issues were identified. These major issues tool for the pump analyst. The routine collection j were further broken down into 43 specific topics and analysis of spectral data are superior to all - to be addressed, and each topic was analyzed other technologies in the ability to accurately ' separately to determine ifit could be resolved by detect numerous types and causes of pump , past work. As a result of the literature review,18 degradation, such as misalignment, imbalance, of the 43 topics were resolved without the need for looseness, and various bearing anomalies. Existing
185 ASME Code testing criteria do not require MAIN STEAM ISOLATION VALVE evaluation of pump vibration spectra, focusing DEGRADATION instead on overall vibration amplitude.The mechanicalinformation discernible from vibration
, In 1995, the NRC completed a study of historical amplitude analysis is limited, and such analys,es main steam isolation valve (MSIV) failure data for failed to detect several cases of pump failure in both BWRs and PWRs. Failure records from the the nuclear power mdustry (domestic and
, NPRDS database were reviewed and l overseas)in their early stages. characterized. In the research report, the staff evaluated age-related degradation associated with Pump drivers also are not included in the current MSIVs by focusing on MSIV failure modes, actuator failure modes, consequences of failure on battery of required testing. Numerous operational problems thought to be caused by pump Pl ant operations, method of failure detection, and major stressors affecting both valve and valve ;
degradation were found to actually be the result of motor degradation. Recent advances in Operators. I non-intrusive monitoring techniques have made For BWRs, the major MSIV failure modes motor diagnostics a viable technology for assessing motor operability. In particular, motor affecting plant operations were valve seat leakage current or power analysis techniques can detect in excess of techmcal specification (TS) limits, valve failure to close within TS limits, and loss of rotor bar degradation and ascertain ranges of MSIV closure capability. The BWR globe valves l hydraulically unstable operation for a particular pump and motor set. Damaging low flow have the lowest relative failure rate of all, MSIV types. One possible explanation for this is that phenomena, such as cavitation and recirculation, these valves are subjected to much more may be avoidable if the pump is not operated in these unstable configurations. The concept of maintenance because of failure to meet local leak rate test requirements. using motor current or power fluctuations as an indicator of pump hydraulic load stability is presented in the Phase II report. The second lowest relative failure rate was associated with PWR globe valves, followed by check valves, and then gate valves. The relative Also in 1995, the NRC studied failures of pumps failure rate for gate valves is the combined failure within several BWR and PWR plant systems rate for both 'Iype I and 'Iype II gate valves. Type reported to the NPRDS database. Each failure II gate valves, which use hydraulic pressure to was assigned to one of three general detection open and pneumatics to close, are considered to method categories, those detected by be more reliable. regulatory / code required monitoring: those detected by nonmandatory, but routinely implemented monitoring (called plant programmatic); and those that were not detected CIIECK VALVES by either of these types of programs. Failures were also classified by extent of degradation, affected Since operating experience indicates that check area, and specific failure indicator. Considerable valve performance is becoming more predictable, variation in failure rates was found among the the industry began seeking ways to extend the , examined categories of pumps. The emergency required test and inspection intervals. One avenue l service water (ESW) pumps at PWR plants had a open to licensees is to submit relief requests, I failure rate that was more than twice that of the supported by data, to the NRC for consideration overall PWR pump population (including ESW of whether longer intervals might be acceptable, pumps), and about 2.7 times that of the other In anticipation of such requests, the NRC started PWR pumps studied. At BWR plants, over 75 a research program at ORNL to investigate percent of all reported pump failures, and over 90 whether failure data, such as those used in the percent of the significant failures, occurred in the Nuclear Plant Aging Research program, could be ESW system. Excluding ESW pumps, the rate of used with confidence to identify valves for which significant failures for pumps studied at PWR the test and inspection intervals could be units was almost nine times that of BWR units. extended without compromising plant risk.
186 l l In 1995, the NRC undertook an analysis to failures are lack of monitoring, human errors, and evaluate check valves in an application that had omission of scheduled maintenance. Evaluation of been reported to have experienced good licensee event reports indicated that 38 percent of , performance and reliability. The purpose of the failures were related to aging,55 percent were l analysis was to examine the potential for partially related to aging, and 7 percent were l relaxation of current requirements for inspection unassignable. About 25 percent of all failures i and inservice testing for check valves. were caused by human errors. A periodic } Accordingly, the staff identified 231 safety maintenance program with effective monitoring injection accumulator tank discharge check valves, will reduce and possibly eliminate chiller failures, and reviewed their performance history from 1984 Such programs and equipment are available, and through 1992. During this period, only 18 failures some plants have successfully implemented such involving these valves were reported to the programs. NPRDS database. Of these, only seven failures were characterized as being significant in terms of the extent of degradation (to the valve), and none of the reported failures would have affected the ISOLATION CONDENSER ability of any valve to perform its forward flow The isolation condenser system is an emergency function in the event of its actuation during an core cooling system designed to provide accident. emergency cooling to selected BWRs when the reactor vessel becomes isolated from the turbine Studies are continuing to determine whether and main condenser by closure of the main steam advanced non-intrusive condition monitoring isolation valves. The system removes residual and , techniques can be used effectively to predict decay heat from the reactor, and depressurizes acceptab!c check valve performance, thus . the reactor vessel in the event that the main l justifying longer test and inspection intervals. condenser is not available as a heat sink. A preliminary aging assessment of BWR isolation condenser systems was completed in FY 94. In FY 95, the results were documented in the report, ClHLLERS " Pre-Phase I Aging Assessment of the BWR Isolation Condenser"(PNL-10719), published in Chillers are required in nuclear plants to cool September 1995. rooms, such as the control room, that contain equipment essential to plant safety. Without proper cooling, control room temperature can rise ACCUMULATORS rapidly, leading to operator stress, and can cause electronic equipmer.t to give erroneous wadings Accumulators are vessels attached to reactor or spurious alarms, and even begin to fail. The coolant systems to provide (1) a limited backup newer digital controls in the plants are more source of stored fluid energy for hydraulic or sensitive to high temperatures than the older pneumatic mechanical equipment, (2) a damping analog controls. A Phase 11 Nuclear Plant Aging effect on pressure pulses in fluid systems, and (3) Research assessment of essential chillers was a volume of fluid to be passively injected into a completed in FY 94. During FY 95 Se NRC fluid system. A preliminary aging assessment of completed its review of the draft report, and BWR and PWR accumulators was completed in developed a report entitled," Aging Assessment of FY 94. In FY 95, " Pre-Phase I Aging Assessment Essential HVAC Chillers Used in Nuclear Power of BWR and PWR Accumulators"(PNI 10720), Plants"(NUREG/CR-6043, Vol. 2). The review of published in September 1995, documented the operating experience indicated that chillers findings that the accumulator subcomponents are experience aging and failures associated with experiencing aging degradation, the most vibration, thermal cycling, chemical attack, and prevalent effect being deterioration of the poor quality cooling water. Aging is accelerated bladders. Other aging-related concerns include l by moisture, noncondensable gases, leakage of the gas precharge through the contamination, and corrosion of condenser and precharge valve, gasket failures on the safety evaporator tubes. The principal reasons for chiller injection tank manway covers, and degradation of l l l
187 l i the O-rings causing leakage of the fluid into the ENGINEERING STANDARDS accumulators or leakage of the gas into the SUPPORT system. The national standards program is coordinated by i the American National Standards Institute (ANSI). ANSI provides procedural guidelines to NUCLEAR AIR-TREATMENT AND help ensure that participation in the private sector standards development process is sufficiently COOLING SYSTEM FANS broad based, and that input from individual interests are fairly considered. NRC participation Fans are used to recirculate, supply, and exhaust in this process is consistent with Office of large quantities of air in several nuclear power Management and Budget Circular A-119, dated plant air-treatment (cleaning) and air-cooling October 26,1993, which sets forth policies for systems. Failure of fans in these systems can Federal participation in the development and use impact both plant and public safety. A of voluntary standards. preliminary agmg assessment of fans was conducted, completed, and reported in FY 95, The NRC staff is particularly active on ASME and the " Preliminary Aging Assessment of code and standards writing committees because ; Nuclear Air-Treatment and Cooling System Fans" Portions of the ASME Boiler and Pressure Vessel (PNL-10617) was published in July 1995. The (B&PV) Code have, since 1971, been incorporated into 10 CFR 50.55a, " Codes and Standards," to l results suggest that aging degradation is an ' important factor in fan failure resulting from estabh;sh requirements Ior the eonstruction, mechanical, thermal, and environmental stressors, inservice mspection, and mserv,ce i testmg of nuclear power plant components. Section 50.55a is ,~ including wear, fatigue, corrosion, erosion, and deterioration of belts and lubricants. Periodically amended to update the references to include more recent versions of the ASME B&PV Code. In addition, during FY 95, work continued on rulemaking that would, for the first time, incorporate by reference the new ASME APPLICATIONS OF RELIABILITY Operations and Maintenance Code, which DEGRADATION ANALYSIS Provides rules for inservice testing of pumps, valves, and snubbers. The proposed rulemaking would expedite implementation of certain new To understand aging degradation and the value of ASME B&PV Code requirements for mitigating actions to control aging in standby qualification of personnel and equipment used to safety system components that are periodically perform inservice nondestructive ultrasonic tested and maintamed, a reliability degradation examinations on nuclear power plant components, model was developed. This model, developed at the active component level (e.g., pumps, valves, ASME Code Cases provide alternative; to the compressors), uses maintenance and degradation criteria specified in the ASME B&PV Code. data to analyze time trends in degradation and Regulatory Guides 1.84, L85, and L147 identify the implication of maintenance performed. those Code Cases that the NRC has found to be acceptable for design and fabrication, materials, Previous studies (NUREG/CR-5612 and -5967) and inservice inspection, respectively. These defined the methods development associated with this new concept of reliability degradation regulatory guides, which are updated on a regular modeling. This research describes and documents basis, were revised and issued in the first quarter how methods of reliability degradation analysis of FY 95 (see Appendix 6). , i can be incorporated into an application program to determine the reliability and risk effects of License Renewal Regulatory Standards maintenance. It also provides the analysis steps for using reliability degradation modeling A final rule (10 CFR Part 51) concerning the approaches to analyze component degradation environmental review for renewal of a nuclear and the effectiveness of maintenance. power plant operating license is nearly completed.
188 When final, this rule will facilitate relicensing and analyzing fuel with burnups in the range of 60-70 save resources by providing for generic resolution GWd/t. Work has been initiated on code of a number of environmentalimpacts of validation, which will be followed by a peer relicensing, including waste disposal. In addition, review. The plant transient calculations were also this rule will eliminate NRC evaluation of the completed, showing that moderate energies can be need for generating capacity, and will simplify the deposited in high-burnup fuel during reactivity approach to considering alternative sources of transients. This result confirms the need to generating capacity. The final rule and supporting modify the fuel damage criteria used for generic environmental impact statement is regulatory analysis. expected to be published in FY 96. During 1994, the NRC, through its international cooperative safety arrangements, became aware of new test results on high-burnup fuel that were l REACTOR SAFETY ASSESSMENT being obtained in France, Japan, and Russia. AND REGULATION DEVELOPMENT Since no such testing is being performed in the United States, efforts were made to enter m, to specific cooperative arrangements with foreign laboratories to obtain these data. Agreements Plant Performance providing access to the data from these three countries were signed in 1995. Invitations were extended in 1994 and 1995 to these laboratories to IllGH-BURNUP FUEL BEllAVIOR present preliminary information at the NRC's annual Water Reactor Safety Information By the early 1990s, it had become clear that Meeting, and such presentations were made. More definitive results were obtained in 1995, and these burnups m commercial power reactors were exceeding the burnup range for validatmg the test results are being used to assess and modify NRC s fuel behavior computer codes and related fuel damage criteria used by the NRC in licensing for reactivity transients. An additional effort was fuel damage critena. The followm, g figure shows the burnup distribution of fuelin U.S. power started to examine the need for modification of reactors as of mid-1994. fuel damage criteria used in assessing other accidents in licensing safety analyses. Fuel suppliers were providing high-burnup performance data to support the licensing of endent nal ic c p bi y I ad ot een SAFETY CODE DEVELOPMENT AND updated. In light of these higher burnups and l\1AINTENANCE emerging new data, the NRC decided to update (1) fuel performance models (e.g., UO2 thermal It is generally not feasible to assess the safety conductivity, fission gas release) used in NRC performance of reactor and plant systems with ; computer codes, (2) fuel performance codes ~ tests in full-scale facilities, and an understanding (particularly the FRAPCON code used for of the thermal-hydraulic behavior of these plants auditing regulatory analyses), and (3) fuel damage must be established using computer codes. Most regulatory criteria (including the thresholds and of the NRC's independent analyses for the AP600 ' limits used for reactivity transients). and the simplified boiling water reactor (SBWR) will be done with the RELAP code, which is Initially, the NRC placed contracts with three upgraded for application to these designs. Before laboratories to respond to this need. One focused versions of the NRC codes are used for this on phenomenological models, one on modifying purpose, or released for use by others, they computer codes, and the third on plant transient undergo developmental assessment and peer calculations to estimate the impact on reactor review. Revised documentation is also provided safety. Modeling and computer code for these improved codes. The upgraded version modifications were completed in 1995 to provide a of RELAP for use on the new passive plant fast running FRAPCON code that is capable of designs was released in October 1995.
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_ ._ _ . __ .__ ___ _ _ _ _ . ~ _ _ _ _ _ . _ . 190 As part of the code maintenance activities for Elements of the control, instrumentation, and RELAP and for the TRAC code (both PWR and human factors regulatory research program are BWR versions), the NRC conducts an (1) personnel performance, (2) human-system international Code Applications and Maintenance interfaces, and (3) reliability assessment. Program (CAMP). There are now 19 member countries in CAMP, each of which participates in The purpose of the personnel performance semiannual meetings and makes cash element is to develop enhanced methods for contributions to supplement the NRC code collecting and managing personnel performance development and assessment studies, recommend data, and to improve understanding of the effects code improvements, and make other technical of personnel performance on the safety of nuclear contributions to assist in the developmei.t and operations and maintenance. In addition, assessment of the codes. Personnel performance research broadens the understanding of such factors as staffing, qualifications, and training, all of which influence Control, Instrumentation, and Human human performance in nuclear systems. Research Factors Assessment in this area will develop information necessary to reduce any negative impact these factors might About half of all safety-related events reported at have on nuclear safety. nuclear power plants continue to involve human performa' ice. Methods and data are needed t Research in the human-system interfaces element identify, systematically set pnon, ties for, and provides the technical basis for guidelines and suggest solutions to human performance issues criteria to evaluate the interface between the dunng operation mid mamtenance activities at system and the human user from the perspective of safe operations and maintenance. nuclear facilities. To best account for human performance issues, the human must be viewed as Reliability assessment includes work on data part of a total system, which also includes the acquisition and management systems and the instrumentation and control hardware and human reliability analysis /probabilistic risk software that drive the controls, as well as assessment (HRA/PRA) methods and application. displays that allow the human to monitor and The reliability assessment element includes operate within the larger plant system. multidisciplinary research that integrates human, organizational, and hardware considerations for The control, instrumentation, and human evaluating reliability and risk in NRC licensing, performance assessment research program has inspection, and regulatory decisions. three objectives: e Broaden the NRC's understanding of human Personnel Performance performance, and identify causes of human C" I During FY 95 work continued on a study to establish a technical basis for minimum shift e staffing for both control room crews and Accurately measure the total control,
, operational support staff outside the control room mstrumentation, and human system at nuclear power plants, based on workload and performance for enhancmg safer operations task alk> cation. Technical letter reports were and precludmg entical errors completed for an analysis ofliterature, incident, and investigation reports related to staffing, and e Develop the technical basis for requirements, on a survey of a sample of plants regarding their recommendations, and guidance related to staffing practices and activities for operational total system performance staff outside the control room. These reports were used as the basis for NRC Information Notice Additional human factors research focuses on 95-48, "Results of Shift Staffing Study."
systems performance of advanced reactors and materials licensee performance. The human Research continued on communication errors in factors research for these activities is reported nuclear power plant events to characterize the under the related headings of this chapter. root cause(s) of these errors, to identify potential
191 1 corrective actions for each category of " Guidelines for Control Room Design Reviews" I communication error, and to develop proposed (September 1981). review criteria and guidelines. In addition, a study was completed to determine whether links exist Work continued on a project entitled " Advanced between operator effectiveness and the simulator Alarm System Review Criteria," intended to training received by operators at multi-unit develop guidance for reviewing advanced digital stations, compared to simulator training at alarm systems. After refining the research study single-unit stations. design, the staff visited candidate study sites, and selected the HAMMLAB at the Halden Reactor A technicalletter report was completed on a Project as the site from which data will be study to evaluate the use of a circadian lighting collected. A bilateral agreement will be prepared system (bright lighting system) to improve the to allow the conduct of these experiments. night shift alertness and performance of NRC headquarters operations officers. The results of A new effort to evaluate the effects on human the research supported the continued use of the Performance of mixing analog and digital displays system in the new operations center. NUREG/ in control stations was initiated during FY 95. If a CR-6046, " Alertness, Performance, and Off-Duty safety issue is identified, review guidance will be Sleep on 8-hr and 12-hr Night Shifts in a developed. Simulated Continuous Operations Control Room l Setting," was published. This research confirmed that a 12-hour shift regimen did not have adverse SOImVARE affects on operator performance when compared with an 8-hour shift. NUREG/CR-6316, " Guidelines for the NUREG/CR-6159, "Using Micro Saint to Predict Verification and Validation of Expert Systems Software and Conventional Software, , was Performance in a Nuclear Power Plant Control Room," was published. This report describes the published m eight comprehensive volumes. These use of task-network modeling to develop a y lumes provide detailed coverage of methods for computer simulation of operator performance ssessmg both conventional and expert system when using computerized and paper-based softwaye, certifym, g knowledge bases, validathig procedures. scenarios, and establishmg procedural guideh,nes. NUREG/CR-6293, " Verification and Validation Guidelines for High-Integrity Systems," was also Human-System Interfaces completed, and work is continuing to develop tools to assess software used in safety systems. Such tools would be used to identify undesirable I ngu ge characteristic HUMAN FACTORS The languages under m, swere vestigation thatselected could affect sa based on the probability that they might be used Revision 1 to NUREG-0700, " Human-System in safety system applications. The undesirable Interface Design Review Guideline," was issued characteristics will be ranked for their potential for public comment in February 1995, and several impact on safety. The final report will be used comments were received, reviewed, and resolved. during the software audit to evaluate the This revision incorporates and integrates review submitted product. guidance previously developed in other RES projects and published as NUREG/CR-5908. The development of a CASE tool to provide NRC " Advanced Human-System Interface Design auditors with the capability to investigate the Review Guideline"(July 1994); NUREG/CR-6146, amount of diversity in safety system software and " Local Control Stations: Human Engineering to locate common code, or non-diverse software, Issues and Insights"(September 1994); between two or more safety systems and their NUREG/CR-6105," Human Factors Engineering functions continues. A CASE tool developed in Guidance for the Review of Advanced Alarm earlier phases of this effort is being enhanced to Systems" (September 1994); and NUREG-0700, improve the user interface.
192 NUREG/CR-6263, "High-Integrity Software for research includes evaluating the means by which Nuclear Power Plants: Candidate Guidelines, smoke may damage this hardware, as well as Technical Basis, and Research Needs," was some possible methods to protect the hardware published in June 1995. This report discusses the from smoke damage. results of a study performed to examine the technical basis for guidelines that might be used in reviewing and evaluating nuclear power plant TOTAL SYSTEM safety system software. In areas where the potential guidelines were judged to have an Human-system interface research includes NRC inadequate technical basis, potential research participation in the Halden Reactor Project, a ! needs were identified. The report also discusses multifaceted program that includes verification the lifecycle framework, development of and validation of digital systems, man-machine framework subelements, development of interaction, and smveillance and support systems candidate guidelines, and evaluation of the for advanced control rooms. Information was technical basis for the candidate guidelines. developed in the following areas: o methods and tools for developing, and verifying and validating safety-related HARDWARE software e experience with development and quality Confirmatory research is under way to develop the technical basis for test methods and assurance of software systems at the Halden acceptance criteria to address electromagnetic Reactor Project and radiofrequency interference (EMI/RFI) and e methods for better assessing human error in power surge issues for mstrumentation and Halden research control (I&C) systems. The electromagnetic environment in a nuclear power plant is virtually A National Research Council effort was initiated unknown; thus, electromagnetic measurement during FY 95 to define the important safety and data are being collected at various plant sites. reliability issues that arise from the introduction These data will be employed to profile the of digital I&C technology in nuclear power plant electromagnetic environment at nuclear power operations. This research will also identify criteria plants and establish EMI/RFI-related acceptance for reviewing and accepting digital I&C criteria. In the meantime, interim acceptance technology. In addition the research will provide a criteria have been developed for use until basis for characterizing and evaluating alternative permanent criteria based on plant measurements licensing approaches, and for recommending can be established. These criteria are described in guidelines for the regulation of digital NUREG/CR-6304, " Interim Electromagnetic instrumentation and controls. The definition of Operating Envelopes for Safety-Related I&C issues was completed in the first phase of the Systems in Nuclear Power Plants." effort. Environmental compatibility studies are being conducted to identify failure modes and system Reliability Assessment vulnerabilities that are unique to advanced digital During FY 95, the NRC published NUREG/ systems. The digital components under CR-6002, " Risk-Based Maintenance Modeling," l investigation include fiber optic network interface which describes risk methods for setting systems, serial communication links (optical fiber maintenance priorities and quantifying and copper transmission), analog-to-digital maintenance effectiveness. converters, multiplexers, and microprocessor-based trip systems. The environmental stressors In addition, research was completed to analyze applied in the investigation are EMI/RFI, information from the simulator pc,rtion of the j temperature, humidity, and smoke exposure. NRC-administered operator requalification
- examinations. Estimates from this source were Research is also being conducted to assess the compared with human error probabilities derived impact of smoke on digital I&C hardware. This from the Accident Sequence Evaluation Program. .
1 j
193 Reactor Risk Analysis programs were used extensively to perform the low-power and shutdown risk analyses previously ' Probabilistic risk analysis (PRA)is used by the described, and are currently being used to analyze NRC staff to support the resolution of a wide operating plants and evaluate the safety aspects of spectrum of reactor regulatory issues. In 1995, nuclear plant designs. work in this area consisted of both specific j issue-oriented projects, as well as more general GEM, a new SAPHIRE program has been i work, including development and demonstration developed specifically for the Accident Sequence of risk analysis methods and development of Precursor (ASP) program, and is being used in risk-related training and guidance for the NRC event assessment applications by the Office for l staff. The following paragraphs describe the Analysis and Evaluation of Operational Data l progress in these projects during FY 95. (AEOD) and the Office of Nuclear Reactor ! Regulation (NRR1" primary use of GEM is to quantitativelv - ._ .ie if either the occurrence f an existing event or the operating plant ANALYSIS OF LOW-POWER AND condition adversely impacts safety. SHUTDOWN ACCIDENT RISKS During 1995, many of the 75 plant models used in As a result of the Chernobyl accident and other the ASP program were improved. These precursor events, an extensive, two-phased project train-level models, representing the 110 operating j was begun in 1989 to examine the potential risks plants, were modified to include more of accidents initiated during low-power and plant-specific features needed for ASP analyses. shutdown modes of operation. Phase 1, completed In addition, many of the full PRA data loads in at the end of 1991, was a coarse screening analysis the SAPHIRE database were modified to use the of all operational modes (other than full power) new features added to the code. for one BWR and one PWR. Based on the Phase 1 results, the Phase 2 effort concentrated Also during 1995, the final two reports on a specific operating state for each of the two documenting SAPHIRE version 5.0 were plants, selecting the potentially highest risk completed, resulting in a 10-volume set published operating state for further detailed analysis. In as NUREG/CR-6116. Training courses on using addition to a Level 1 PRA, a simplified analysis SAPHIRE continued to be provided to the NRC (Levels 2 and 3) of potential in-plant and offsite staff, their contractors, and a number of foreign accident progression and health consequences of regulatory agencies who have established specific such accidents was performed. The complete cooperative agreements with the NRC. results of Phase 2 were published as NUREG/CR-6143 for the BWR, and NUREG/CR-6144 for the DWR..The six-volume set for each plant was completed during 1995 with OFFSITE CONSEQUENCE UNCERTAINTY the publish,mg of a comprehensive summary ANALYSIS (Volume 1) and the Level 2 and 3 analyses (Volume 6). The NRC has completed a pilot, probabilistic , consequence uncertainty analysis m atmosphenc dispersion and deposition in cooperation with the Commission of the European Communities SAPIllRE COMPUTER TOOLS (CEC). A formal expert judgment elicitation and evaluation process was used to obtain the ne set of System Analysis Programs for probability distributions needed. The methods Hands-On Integrated Reliability Evaluation used in, and results and findings of, this pilot (SAPHIRE) underwent numerous improvements study were published in January 1995 in a leading to version 5.0 released during FY 94. Ris three-volume joint report, NUREG/CR-6244. The set of programs used in performing PRAs permits CEC has taken the lead, with the NRC providing an analyst to achieve many of the functions the necessary technical support, in using the necessary to create, quantify, and evaluate the methods formulated during the joint pilot study to accident risks of nuclear power plants. The obtain quantitative information in a consequence
I 194 . l l I analysis regarding the dose received from actions, and thereby created a systematic basis for deposited material, and the ingestion pathway, evaluating the significance and characteristics of The NRC and CEC are currently planning for the EOCs and dependency from operational events. next and final set of joint formal expert judgement Thus, the framework enabled important aspects elicita* n exercises in the areas of radiation of EOCs and dependency to be considered in the healtl. d: cts and dosimetry. This final set of development of an improved HRA methodology, exercise; is scheduled for completion in 1996. The and clarified the requirements for their more NRC and CEC will also use the same jointly realistic inclusion in PRA models. By providing a established process to obtain other needed single language and common structure for relating information in performing independent the different dimensions of human-system probabilistic consequence uncertainty analyses. interactions, the framework demonstrated that the evaluations of EOCs and dependencies is both I tractable and tenable. Considering the importance f these issues in nuclear power plant safety, this ' IIUMAN RELIABILITY ANALYSIS change is an important advance. These EOC and dependency capabilities will be refined and As part of an NRC-sponsored program evolving expanded upon in subsequent tasks pertaining to from an assessment of human reliability issues in the development pha.se, low-pcwcr and shutdown operations in nuclear power plants, an improved approach to human The primary product of the work during FY 95 reliability analysis (HRA) is currently being and 96 will be a working HRA quantification developed. This approach is intended to be fully process involving the following methods: integrated with PRA methodology to improve assessment of the human contribution to plant e how to identify and incorporate human risk, both during low-power, shutdown and failure events in the logic models used in J at-power operations. PRAs In FY 92 and 93, a Human Action Classification
- what information is required for assigning Scheme for categorizing human actions and probabilities to these failure events associated influences in actual low-power and shutdown events was developed and implemented. e how this information is used to estimate the These accomplishments were documented in probabilities NUREG/CR-6093,"An Analysis of Operational Experience During Low Power and Shutdown and
- how the probabilities are incorporated into a Plan for Addressing Human Reliability the PRA quantification process Assessment Issues."
The final phase of the project during FY 96 will During FY 93 and 94, work continued on demonstrate the usefulness and acceptability of developing a multidisciplinary framework for the developed methodology,s implementation i integrating HRA with PRA, and characterizing guidehnes, usmg selected parts of a full-power PRA. errors of commission (EOCs) and human 1 dependencies, including general guidance for their j identification and representation in PRAs. Work Severe Accident Analysis ! also continued on recognizing database ) improvement needs, including better In order to ensure that existing regulations i characterization of human actions and their adequately protect the public from the l associated performance context (e.g., plant consequences of severe accidents, the NRC conditions, performance shaping factors, and conducts research in several areas. Specifically, dependencies), as well as better description of an these areas include direct containment heating, event timeline. These accomplishments are hydrogen combustion, melt-concrete interactions currently being documented. and debris coolability, source terms, core-melt progression, reactor vessel integrity, and This framework provided the capability to identify fuel-coolant interaction. The overall goals of the factors that influence humans to perform unsafe research are three-foid. First, the research will
195 develop technical bases for assessing containment Subatmospheric Containments," has undergone performance over the range of risk-significant peer review and will be published in FY 96. core-melt events. Second, the research will . . improve understanding of the range of The culmm.at. ion of extensive experimental and phenomena expected during severe reactor analytical research has produced the finding that, accidents. Finally, the research will yield improved f r those nuclear power plants studied, DCH loads are lower than once estimated, and methods for assessing fission product behavior. With these data, the NRC will be better able to e nsequently they pose no significant threat to the confirm the adequacy of its requirements for the contam, ment durmg a severe accident. This design and reliability of the systems that may be conclusion 1s based mainly on the inherent des,gn i used to mitigate the consequences of severe charactenstics of many U.S. reactors. Future accidents. efforts will seek to extrapolate these findmgs to the Westinghouse nuclear power plants with ice condenser containments, as well as the Combustion Engineering and Babcock & Wilcox HIGH-PRESSURE MELT EJECTION-DIRECT CONTAINMENT HEATING IIYDROGEN COMBUSTION Significant information exists on hydrogen In certain reactor accidents, the reactor core can combustion to assess the possible threat to degrade while the reactor coolant system remains containtnent and safety-related equipment. pressurized. In such instances a molten core left However, some ancillary issues remain related to uncooled will slump and relocate to the bottom of a better understanding of the likelihood of various the reactor vessel. If the reactor vessel fails, the modes of combustion at high temperature and in core melt will be ejected into the containment the presence oflarge quantities of steam. l cavity under pressure. If the material should . subsequently be ejected from the reactor cavity The largest current NRC program in this area into the surrounding containment volumes in the comes out of a joint agreement between the NRC form of fine particles, thermal energy can quickly and the Ministry of International'nade and be transferred to the containment atmosphere, Industry of Japan, managed by the Nuclear Power pressurizing it. The metallic components of the Engmeering Corporation (NUPEC). Under the ejected core debris could further oxidize in air or agreement, a high-temperature hydrogen in steam, and could generate a large quantity of combustion program related to high-speed l hydrogen and chemical energy that would further combustion modes (i.e., detonation and 1 pressurize the containment. This process is called deflagration to detonatson trans,i tion)is under way direct containment heating (DCH). at the Brookhaven National Laboratory. A small-scale developmental apparatus was i
. constructed, and has provided preliminary I As part of the DCH issue resolution plan for U.S. experimental data and solutions to a number of PWRs, completed studies encompass 41 , design and operational problems for a larger-scale Westinghouse nuclear power plants with large dry high-temperature combustion facility (HTCF).
or subatmosphenc contamments. The DCH issue The construction of the HTCF was completed in resolution for the Zion (Illmois) nuclear power FY 94, and intrinsic detonability and deflagration-plant was specifically documented in NUREG/ to-detonation transition experiments at high CR-6075 and its Supplement 1, "The Probability temperature were completed in FY 95. As a result of Containment Failure by Direct Contamment of the cooperative agreement, the NRC has access Heatmg m Zion," December 1994; and for the to the ongoing hydrogen research in Japan Surry (Virgm,a) i plant in NUREG/CR-6109, "The managed by NUPEC. This research provides a Probability of Contamment Failure by Direct greatly expanded and improved database for Contamment Heatmg m Surry," May 1995. The validating analytical tools. more generic report, " Resolution of the Direct Containment Heating Issue for All Westinghouse A hydrogen research program is also under way Plants with Large Dry Containments or to investigate diffusion flame behavior in
196 low-speed hydrogen combustion. Experiments sixth test is currently planned for spring 1996. were performed in a small-scale facility to This test, to be performed at a scale more than examine the influence of ignition source strength two times larger than earlier tests, is designed to on the lean flammability limits of hydrogen-air provide information on the effect of scale on crust mixtures at temperatures of 300 K and pressure of formation, stability, and debris coolability. one bar. The facility has been redesigned to climinate diffusion flame interference with the walls. Construction has been completed, and SOURCE TERMS shakedown tests are under way. The results will be used to help resolve several outstanding issues " Source terms" refer to the magnitudes of the in severe accident behavior, such as high- radioactive materials released from a nuclear temperature combustion phenomena and reactor core to the containment atmosphere, detonation initiation by high-temperature taking into account the timing of the postulated steam-hydrogen-particle jets. releases and other information needed to calculate offsite consequences of a hypothetical severe accident. NRC research in this area is reflected in the updated version of TID-14844, which has MELT-CONCRETE INTERACTIONS AND been used for three decades in connection with DEBRIS COOLABILITY plant siting assessments. An extensive review of the updated TID-14844 has been completed, and In those severe accident scenarios in which the the final NUREG-1465, " Accident Source Terms reactor vessel fails, high-temperature core debris f r Light-Water Nuclear Power Plants," was may fall into the reactor cavity where it can Published in February 1995. The revised source thermally and chemically interact with structural terms are currently bemg used in the AP600 concrete. The major areas of concern associated design. I evaluatm, n addition, g their the NRC use for current reactor andlicensing the utilities are with melt-concrete interactions during a severe accident are the penetration of the basemat and applicms. failure of the liner, the generation of radioactive The NRC has also entered into an agreement with aerosols and gases, includmg combustible gases, the Commissariat a l'Unergie Atomique of France and the overpressun,zation of the contamment. (CEA) to participate in the PHEBUS-FP (fission
. . product) program sponsored by the CEA and the Early experiments on melt-concrete interactions Commission of the European Communities. This were conducted without an overlying water pool. program is aimed at studying-under sufficiently More recent experiments on melt concrete prototypical conditions in an inpile facility-those interactions, otherwise known as debris coolability phenomena governing the transport, retention, experiments, were conducted in the presence of an and chemistry of fission products under severe overlying water pool. It has been postulated that accident conditions in light-water reactors adding water to cover the core debris will (LWRs). Phenomena to be studied are those effectively quench the molten core debris and occurring in the core, the primary reactor coolant termmate melt-concrete mteractions. The circuit, and the containment.
currently active experimental research on debris coolability, called the Melt Attack and Coolability This agreement is of significant benefit to the Experiments (MACE) program, was developed as NRC because, at a relatively modest cost, the an extension of the Advanced Containment NRC can participate in the PHEBUS-FP project Experiments (ACE) program under the over its lifetime. The NRC will be able to obtain sponsorship of the NRC, the Electric Power integral experimental data to further validt.te its Research Institute (EPRI), and other, mostly analytical models for fission product transport in governmental. agencies in several countries. T the reactor coolant system and containment and MACE program is intended to determine the for iodine chemistry in the containment. The ability of water to cool prototypic ex-vessel coie experimental data from PHEBUS-FP will be used debris of urania-zirconia composition. Five tests, to confirm the conclusions reached from the including a scoping test, were conducted under NRC's completed fission product research the MACE program during 1992 through 1995. A program.
197 The first PHEBUS-FP test, FPT-0, was Following this demonstration, the XR2-1 test is successfully conducted in December 1993. The scheduled to be run in early FY 96. analysis and interpretation of FPT-0 is continuing: lessons learned from FPT-0 are being taken into account in planning for the next test, REACTOR VESSEL INTEGRITY FPT-1, scheduled for early 1996. During the late phase of a severe accident, a significant amount of core material may relocate downward into the lower head of the reactor CORE-MELT PROGRESSION vessel. A molten pool then forms and can impose a significant heat load on the reactor vessel lower head. When this molten pool forms on the lower "In-vessel core-melt progression" describes the head, a solid crust of matenal forms around the state of an LWR core from a core being uncovered up to reactor vessel melt-through in Periphery of the pool, but internal heat generation resultmg from radioactive decay of fiss,on i unrecovered accidents, or through stabilization of , , the temperatures and core geometry in accidents Products ensures that most of the debris remams m lten and, in fact, undergoes sigmficant internal recovered by core reflooding. Melt progression natural convection m the pool, 3rovides the initial conditions for assessing the oads that may threaten the integrity of the Knowledge of in-vessel and ex-vessel heat transfer reactor vessel and the contamment. Significant phenomena to the lower head is needed to assess results of melt progression are the melt mass, the ability of the reactor pressure vessel to composit,on, i temperature (superheat), and rate of maintain its integrity during a severe accident. release of the melt from the core (and later from Detailed understanding of the natural convection the reactor vessel if vessel failure occurs). Melt process provides information on the local heat progression research also provides mformat,on i Hux distribution around the inside surface of the about the in-vessel hydrogen generation, the crust. This distribution, in conjunction with the conditions that govern the in-vessel release of thermal boundary conditions imposed on the fission products and aerosols and their transport outer crust surface, determines the fraction of the and retention in the primary system, and the core total heat dissipation that is transferred through conditions for assessmg accident management the upper crust to the inside of the reactor vessel , strateg,es. i by radiative heat exchange, and the fraction that must be conducted through the wall of the reactor In FY 95, major accomplishments were achieved vessel lower head. in preparing the XR2-1 test: In August 1994, the NRC, in cooperation with 13 o design, development, and testing of a radiant countries and under the auspices of the cavity melt delivery system and wire-feeding Organization for Economic Cooperation and machinery that delivers wires at controlled Development's (OECD) Nuclear Energy Agency rates into the radiant cavity melter system (NEA), undertook an investigation of melt-vessel interactions to provide data on the internal o development and refinement of a real-time natural c(mvection flow and local heat flux : distribution mside the lower head of the reactor j x-ray imaging system pressure vessel for vanous melt compositions, This program involves large-scale integral o fabrication and assembly of the XR2-1 test
, experiments usmg molten UO 2 and ZrO2m, section representative reactor lower head geometries, analytical studies, and a number of small-scale '
o development of a process to control the separate effects experiments. This program, i needed thickness of oxide layers on the named OECD RASPLAV, is being performed at ! XR2-1 Zircaloy surfaces the Russian Research Center. During FY 95, tests were carried out to demonstrate the proposed o successful demonstration of a near full-scale heating methods (i.e., side wall heating and direct melt delivery system electrical heating) of the corium for conducting i
198 the integral experiments. Code development has or energetic steam explosions. These explosions been under way for pre- and post-test could challenge reactor vessel and containment calculations, and measurements of thermophysical integrity, as well as create a leakage path for properties of various corium compositions have radiological releases. It is in this context that the been performed. FCI is considered a severe accident issue of potential risk significance, and its resolution is In order to remove the fraction of heat conducted sought in the framework of severe accident through the vessel lower head, the concept of closure. flooding the reactor cavity to externally cool the reactor pressure vessel lower head and prevent its The Reactor Safety Study (WASH-1400) failure is being investigated. One major quantified the failure mode induced by in-vessel uncertainty involved in the external cooling of the steam explosion-generated missiles (identified in lower head is the critical heat flux distribution on the WASH-1400 study as the alpha-mode failure). , the bottom cmved surface of the reactor vessel. Since that time, significant progress has been l An experimental program is under way at the made in understanding the processes and ; Pennsylvania State University to address ex-vessel parameters that effectively limit the potential of ; flooding of the reactor cavity to prevent vessel missile-induced failure by an in-vessel steam failure. The program investigates boiling heat explosion. Most recently, in June 1995, the NRC transfer on downward facing surfaces in convened a second Steam Explosion Review hemispherical and toroidal geometries. The Group (SERG-2) workshop during which a panel results of this study include data on the critical of international experts reviewed the current heat flux (CHF) and the development of an understanding of the complete spectrum of FCI analytical model for the CHF on downward facing issues. (The first Steam Explosion Review Group surfaces. A series of transient and steady-state (SERG-1) workshop took place in 1985.) The experiments have been carried out to measure NRC is currently preparing a report CHF on a downward-facing hemispherical (NUREG-1529) summarizing the deliberations of surface. In addition, model development is under the experts on the alpha mode and other FCI way to predict CHF for the hemispherical surface, issues; this report will be published in FY 96. Further experiments and extension of the CHF model to toroidal-shaped surfaces will be The SERG-2 experts generally concluded that the performed in FY 96. alpha-mode failure issue was resolved or
" essentially" resolved, meaning that this mode of An experimental program is under development failure is of very low probability and of little or no at the Sandia National Laboratories to determine significance to the overall risk in a nuclear power the mode, mechanism, location, timing, and plant. The SERG-2 experts also noted that, with characteristics of the failure of a reactor pressure the essential resolution of the alpha-mode failure vessel lower head under the combined effects of issue, the em'phasis of FCI research shifted to thermal and pressure loads as a result of a core other issues. These issues include the mild meltdown accident. During FY 95, the scaling, quenching of core melt during non-explosive FCI, !
design, and construction of the experimental test and the shock loading of lower head and ex-vessel ! set-up were carried out. In FY 96, experiments structures arising from explosive localized FCI. will be performed on the scaled lower head test These issues are relevant with regard to sections, both with and without lower head tube determining certain accident management l penetrations. strategies for operating reactors, and the I adequacy of certain passive system design ) features of advanced light-water reactors ; FUEL-COOLANT INTERACTION In 1995, the NRC renewed its technical exchange Fuel-coolant interaction (FCI)is a process by arrangement for 4 years with the Safety which molten fuel transfers energy to the Technology Institute of the Joint Research Center surrounding coolant. Such energy transfer leads to (JRC) of the Commission of the European non-explosive breakup and quenching of melt, Communities at Ispra, Italy. The renewed with possible formation of a coolable debris bed arrangement will continue the melt quenching
199 experiments at the FARO facility, and the steam measurable augmentation. Additional experiments explosion experiments at the KROTOS facility, are planned in FY 96 with a larger quantity (1 kg) both at Ispra. In the FARO facility, large masses of both Zircaloy-water and Zr-ZrO 2-water (typically, up to 250 kg) of reactor prototypic melt systems to investigate their augmentation are generated and poured into a water pool of potential. varying depths at a range of system pressures. So far, five successful FARO tests have been carried out, and the results showed generally consistent melt quenchmg with no steam explosion. The next SEVERE ACCIDENT CODES FARO test is planned in FY 96. In the KROTOS . . facility, small masses (typically, up to 4 kg) of Because of the difficulty in performm.g prototypic both prototypic and simulant melts are generated experiments for a vanety of severe accident and poured into a water pool of varying depths at scenarios, substantial reliance must be placed on a low system pressure (0.1 MPa) to study steam the development, venfication, and validation of explosion potential and energetics. KROTOS system-level computer codes for analyzing severe experiments with prototypic melt (UO2 -ZrO2 ) a cident phenomena. Several system-level codes produced no steam explosion, even under (MELCOR, SCDAP/RELAP5, CONTAIN) have conditions of high water subcooling, high melt been developed for various stages in severe accidents, for both m-vessel and ex-vessel superheat, or presence of a trigger. On the other structures, and both BWRs and PWRs. hand, more recent KROTOS experiments, all performed in 1995 with a simulant melt, produced Additional codes a steam explosion in every case, with or without a developed and mam,(such tamed as VICTORIA) to perform speci are,ficbem, g trigger. These experiments indicate that the functions that require more detailed modelmg explosion potential of a melt may be influenced by than the system-level codes. material behavior or properties. MELCOR is an integrated computer code that models the progression of severe accidents in The ongoing FCI experimental program at the LWR power plants. The code can be used to University of Wisconsin is examining the effects evaluate the progression of severe accidents from of various fuel and coolant parameters on initiation through containment failure. It can also explosion energetics. Experiments performed in be used to estimate severe accident source terms, 1994 and 1995 with tin simulant considered the as well as their sensitivities and uncertainties, in a effects of melt superheat, water subcooling, water variety of applications. The NRC has been viscosity, system pressure, fuel / coolant mass ratio supporting the MELCOR development and (alternatively, volume ratio), and the presence of a assessment program for a number of years. The < trigger on energetics. Experiments in 1995 focus of the development efforts in FY 95 was to I concentrated on the effect of the fuel-to-coolant model downward and radial flows in the reactor I mass ratio (volume ratio) on energetics. Among core, the interactions of boron carbide with those selected, this parameter was found to be the steam, and incorporation of the Larson-Miller one that had the most influence on the energetics. vessel failure criterion. In addition, the code was improved to model the scrubbing of fission An experimental program was initiated in 1994 at product vapors through a suppression pool by the Argonne National Laboratory to determine incorporating into MELCOR the latest version of whether chemical augmentation of the energetics the SPARC code. New models are under can occur in Zircaloy-water and Zr-ZrO2-water development for fission product chemical steam explosions. Such chemical augmentation reactions with surfaces and in aqueous solutions. , important in assessing the shock loading of the A significant effort was made to develop new or I lower head and ex-vessel support structures, and revised models to perform calculations for a was observed in an aluminum-water system in potential severe accident involving the AP600 connection with the new production reactor plant design, which includes several features not (NPR) safety research. Several scoping tests with found in current operating nuclear power plants. 200 grams of molten Zircaloy interacting with a Another byproduct of this effort was the 1-meter-deep water pool were performed in 1995 incorporation of code enhancements that resulted with the preliminary results showing no in substantial improvements in code running time.
200 During FY 95, NRC contractors continued to chemical, and radiological conditions inside a assess MELCOR by applying the code to the reactor containment in the event of a severe analyses of various plant accident transients. A accident. The primary objective of the contain large number of code assessments were completed enhancements during FY 95 was to modify the in FY 95 by several U.S. and international user code to develop and validate models related to the organizations. Significant assessment efforts unique ALWR safety features that affect include exploration of improved treatment of containment performance for both design-basis Zircaloy oxidation during core damage, and and severe accident type calculations. The careful comparison of in-vessel accident CONTAIN code was also assessed against progression results as predicted by MELCOR to selected tests from the AP600 Passive Cooling results predicted by the SCDAP/RELAP5 code. System Large-Test Facility. Also during FY 95, the MELCOR Cooperative VICTORbt is a computer code designed to analyze Assessment Program, an international forum with fission product behavior within the reactor membership from 19 countries, continued the coolant system (RCS) during a severe accident. ongoing successful exchange of information on the The code provides detailed predictions of the applicability, limitations, and operational fission product release from the fuel and the experiences of MELCOR. Results of 18 highly transport in the RCS of radionuclides and useful assessment and application calculations non-radioactive materials during core with MELCOR were presented and discussed at degradation. During FY 95, pre-test analyses were the annual meeting in spring 1995. conducted for the Phebus FPT3 and FPT4 fission product release and transport experiments. SCDAP/RELAPS is a computer code that has the VICTORIA was also used to assess the boundary capability to perform detailed analyses of the conditions and consequences associated with in-vessel progression of LWR severe accidents, as steam generator tube rupture events. A peer well as detailed experiment analyses. Major review of VICTORIA also began in 1995. accomplishments in FY 95 include completing SCDAP/RELAP5/ MOD 3.1 full-plant calculations for resolving the direct containment heating issue, Reactor Conta.inment Structural as well as SCDAP/RELAP5/ MOD 3.1E updates Integrity and systematic assessments. (The key elements of . Durm.g 1995, important progress was made on these updates are debris oxidation model research projects myolvm, g model tests and improvements, the Ag-In-Cd control rod material studies of the effects of corrosion, as well as on interaction model, and BWR control blade / , channel box model improvements). Other major the rulemakmg endorsing sections of the ASME Code. Under the research topics, a model of a accomplishments in FY 95 include peer review of , steel containment was fabricated in Japan and proposed late-phase model improvements, completion of the Browns Ferry reference slupped to the United States as part of a cooperative research program of conta,mment calculations to support the ex-reactor (XR2-1) test at the Sandia National Laboratories, and model tests. A series of tests,was also completed to assess the failure of containment bellows, completion of general PWR/BWR upper plenum , , bringmg to a conclusion an mvestigation of the component model development. Ongoing work Potential containment failure modes involving continuing in FY 96 includes incorporating penetrat,ons. i proposed late-phase model improvements into SCDAP/RELAP5, performing additional code i assessment studies against experimental data, and l continuing to improve high-priority modeling CONTAINMENT MODEL TESTING ' deficiency items, as recommended by the SCDAP/RELAPS independent peer review The major effort in this program for the past few committee. years has been cooperation with the Ministry of International Trade and Industry (MITI) of Japan. CONTAIN is a detailed code for integrated Two areas of cooperative research are being analysis of containment phenomena. This code pursued-one dealing with steel containments provides the capability to predict the physical, using BWR designs in both the United States and
201 Japan-and the other relating to pre-stressed The pre-stressed concrete containment vessel concrete containments. The current generation of (PCCV) model is representative of U.S. Japanese PWR containments are of a pre-stressed containment designs, and will be a scaled concrete design. In the United States, there are 41 representation of an actual PCCV in Japan. The pre-stressed containments, compared to 20 actual PCCV, which was designed in accordance reinforced concrete containments. with the Japanese Concrete Containment Vessel Design Code, consists of a hemispherical dome, a A reinforced concrete model was chosen for the cylindrical wall, and a basemat. Two buttresses NRC-sponsored testing that was performed at the are used to anchor the horizontal or " hoop" Sandia National Laboratories (SNL)in 1987, tendons, and a " hairpin" tendon layout is Subsequent analyses of the results of that model employed in the vertical direction. The vertical test have shed light on how potential failure tendons extend from the basemat up through the modes develop in concrete containments. Some of cylinder wall, over the dome, and back to the the results also apply to pre-stressed concrete basemat on the opposite side of the containment. containments; however, there are two main They are anchored m, a tendon gallery that is reasons for performing an additional pre-stressed inside the basemat. A liner plate, which is made containment model test: of carbon steel, is placed on the mner surface of the concrete wall, dome, and basemat and forms
. . the containment pressure boundary in these areas.
o No test data exist with regard to the ultimate capacity available for a pre-stressed The basic design of the PCCV model was containment, that closely represents the completed in December 1994. Fabrication of the designs used in the United States. liner by hiitsubishi Heavy Industries in Kobe, Japan, began in April 1995, and will be completed o The margin between the ultimate capacity in 1996. The liner segments will be shipped to and the design pressure for pre-stressed SNL, where construction of the model will take containments is now thought to be somewhat place during 1996-1998. Instrumentation of the lower than that for reinforced concrete or model will be performed in 1998-1999, partly in steel containments. It is important to have parallel with the onsite model construction. accurate predictions of the ultimate behavior Testing of the PCCV model will then take place of pre-stressed containments for activities late in 1999. such as accident management, risk analysis, and confirmation of assumptions about the robustness of containments for the Severe Accident Policy Statement. CORROSION STUDIES The steel containment vessel test specimen is a Based on recent experience, corrosion effects can scale model representing some features of an significantly degrade containments. Numerous improved BWR hfark 11 containment wsselin examples of degradation caused by corrosion have Japan. A scale of 1:10 is used for the overall been found in hiark I BWR containments, ice geometry of the model, with 1:4-scaling of the wall condenser PWR containments, and the liners of thickness. This selection of scales allowed the concrete containments. The robustness of model to be small enough for transportation from undegraded containments was verified in tests Japan to SNI, while being thick enough to ensure performed at SNL showing their capacity to quality construction. sustain loads well beyond design level, and this robustness is a significant consideration in the The model, fabricated at the Hitachi Works in Commission's Severe Accident PoFev Statement. Japan, was completed in November 1994, and However, based on the degradaticr , arrived at SNL in hf arch 1995. It has since been containment found at operating plants, a better installed in the protective structure within which understanding of factors related to the occurrence the test will take place, and instrumentation of the of corrosion, efficacy of inspection, and model is in progress. The test is scheduled for fall containment capacity reduction is necessary to 1996. support regulatory activities.
202 In order to assess the reduction in containment near, the point of full axial compression, capacity caused by corrosion, the extent of the under those extreme conditions. corrosion must be determined, and an analysis must be performed to determine the reduction of (2) When the bellows were tested in a corroded capacity for k)calized and general corrosion. A or degraded condition, tests indicated that comparison of remaining thickness of significant reductions in performance were containment and containment liners with the caused by relatively small amounts of bellows minimum ASME Boiler and Pressure Vessel Code corrosion. This work has raised the requirements is the first step of an assessment. awareness of the industry for increased The clastic analysis methods used for design surveillance needs for bellows. The results of cannot be extrapolated to provide estimates of this program have been transmitted to the l actual failure. Methods are being sought that can ASME Section XI code group for possible i relate containment capacity to the amount and inclusion in future inspection activities. l location of degradation, using the results of I research on actual failure modes of containments. The structural aging (SAG) program addressed If this effort is successful, a basis can be found the aging management of safety-related concrete for judging the seriousness of a given degree of structe - in nuclear power plants to strengthen degradation at a particular location. the techmcal bases for their continued service. l The SAG program incibded activities in four l
. major technical task areas, including (1) program During FY 94, the Oak Ridge National management,(2) the materials property database, Laboratory imtiated a program to assess (3) structural component assessment / repair state-of-the-art nondestructive testmg techniques technologies, and (4) a quantitative methodology for examining steel containments and the lmers of for continued service determinations. The final concrete containments. As part of this program, program report is expected to be completed by l statistically based samphng plans will be early 1996' i developed to provide confidence limits on the detection of corrosion. One subtask scheduled to Regulatory applications of this research includ.
be completed in 1996 is a program assessing improved predictions of long-term material and nondestructive examination techniques that can structural performance, as well as available safety be used to determine if degradation has occurred margins. This research will also permit in inaccessible areas of the containment. SNL establishment of limits on exposure to initiated a related program during FY 94 to environmental stressors, and will increase the 4 investigate and develop analytical methods to capability to evaluate the integrity of structures. l account for the effects of corrosion on the In addition, this research will yield an improved ! capability of steel containments to withstand damage inspection methodology that could be j static internal overpressurization loads associated incorporated into national standards. l with severe accident conditions. Benchmarking of ' the containment models has been completed, and SNL is presently adding the individual elements RULEMAKING to model the effects of corrosion. l In order to ensure that containment inspection The containment bellows test program began in practices and procedures are effective, work 1990, and was completed in 1995. This program continued in 1995 on the rulemaking to was initiated as a result of concerns that bellows incorporate by reference Subsections IWE and could be a possible source of containment leakage IWL into 10 CFR 50.55a. Subsection IWE during a severe accident. As testing progressed, provides rules for the inservice inspection of the program was separated into two segments: metal containments and the liners of concrete containments. Subsection IWL provides rules for (1) Bellows were tested in a "like-new" condition, the inservice inspection of the reinforced concrete while subjected to extreme conditions of and the post-tensioning systems of concrete internal pressure and elevated temperature, containments. However, Subsections IWE and Tests indicated that bellows in like-new IWL address only the accessible areas of condition would remain leaktight up to, or containments. Consequently, a provision was
203 included in the proposed rule to address IPEEE submittals for alllicensed nuclear power inspection of inaccessible areas in containments. plants by the end of calendar year 1998. Some instances of containment degradation suggest the possibility that degradation may have In parallel with the staff review, the NRC initiated occurred in inaccessible areas. As noted in an an IPE/IPEEE Insights program. This program industry report on PWR containments, the state summarizes insights gained from the IPE and of practice for inspection of inaccessible areas will IPEEE reviews, particularly looking at safety have to be improved before resolution of this insights for the different reactor and containment issue is achieved. The final rulemaking is types and plant designs. As part of this program, scheduled to be published in 1996. a technology transfer effort was implemented to inform necessary personnel (e.g., plant resident inspectors) of the results of the staff review. Severe Accident Implementation In August 1985, the Commission issued a Severe Earth Sciences Accident Policy Statement (50 FR 32138), which . . . . Seismic hazard .is an 1mportant considerat. ion in concluded that existing plants posed no undue , nuclear power plant sitmg and design as it affects risk to public health and safety. However, the , the entire plant, simultaneously challengm, g the Commission recognized that systematic redundancy of safety systems. Because of the examinations of existing plants could identify , large uncertainties m estimatm, g seismic hazards, plant-specific vulnerabilities to severe accidents there is also a large uncertainty m, estimatmg the for which further safety improvements could be nuclear power plant risk associated with j justified. On November 23,1988, the Commission , , seismicity. In order to reduce these uncertaint,esi issued Generic Letter 88-20, requesting that l and provide background for regulations that will ) licensees perform a systematic examination "to ensure the safe operation of nuclear power plants identify any plant-specific vulnerabilities to severe , and other nuclear facilities, the NRC 1s contmumg accidents and report the results to the research into the causes and distribut,on i of Commission." seismicity. Research is also progressing in improved methods of converting the earth science information into estimates of ground motion levels for use in plant design. I INDIVIDUAL PLANT EXAMINATIONS 1 T he individual plant examination (IPE) process I involves two distinct efforts. The first is an SEISMOGRAPIIIC NETWORKS examination of existing plants for vulnerabilities to severe accidents resulting from initiating events The new National Seismographic Network (NSN) occurring within the plant (e.g., valve hardware was established through a cooperative agreement failure), including internal fk>oding, while the between the NRC and the U.S. Geological Survey plant is at full power. The second effort, referred (USGS). Including cooperative stations, the NSN to as the IPE for external events (IPEEE). now operates 39 broadband three-component considers vulnerabilities to severe accidents stations with satellite telemetry, providing caused by external events (e.g., earthquakes, fires, high-quality data on significant earthquakes winds), also while the plant is at full power. within minutes. These data are expected to provide new insights into the causes and All 77 IPE submittals have been received from distribution of seismicity, particularly in the licensees, and the staff review is expected to be central and eastern United States, concluded in calendar year 1996. The reviews of the IPEEE submittats will closely follow the A computer program completed during FY 95 approach used for the IPEs. To date, the staff has allows the NRC to read, archive, and analyze NSN received approximately half of the 75 expected data received via satellite. The program selects IPEEE submittals, and 24 are currently under data that exceed certain magnitude criteria, and review.The staff expects to receive and review sends an e-mail notice if high ground motion
204 levels are expected at nearby nuclear power to 4500 years ago was also found. In addition, plants. paleoseismic evidence for smaller earthquakes, separate from smaller events identified in Indiana, Several research contracts to analyze NSN data, were found in west-central Illinois. The estimated together with other seismological, geological, and times of occurrence of these carthquakes, based geophysical data, were started at the end of FY 94 on radiocarbon dating, are 20,000 to 25,000,7,000 and continued into FY 95. The new research to 8,000, less than 6,000, and 3,700 years ago. In includes analyzing detection capabilities of the south-central Illinois, strata with ages ranging NSN, modeling seismic source functions and from recent to 10,000 years were surveyed, and no ground motion attenuation, defining regional geological evidence of prehistoric carthquakes was seismicity and velocity models, and comparing found. Likewise, in northern Ohio, in the seismicity with tectonic data. The preliminary epicentral region of the 1986 Ashtabula results obtained from this research during FY 95 earthquake (magnitude 5.2), many miles of include indications that seismic source exposure of Quaternary soil that had the potential characteristics in the eastern United States may to liquefy were examined, but no paleoliquefaction be different from what was previously believed. features were identified. SOUTilEASTERN TECTONICS NEW MADRID SEISMIC ZONE Investigations continued in South Carolina to duermine whether there is a second source for a Paleoliquefaction investigations continued in the large earthquake in this region of the coastal New Madrid seismic zone, particularly at the plain, in addition to the source of the 1886 Wilkerson Ditch north of New Madrid, and at Charleston earthquake. This issue was identified Eaker Air Force Base in northern Arkansas. as a result of an earlier, NRC-supported Radiocarbon and archaeological data offer paleoliquefaction study that identified evidence of two large prehistoric events at these anomalously large, seismically induced two sites within the last 2000 years. All paleoliquefaction features that were formed in the paleoliquefaction data taken from the New vicinity of Georgetown, South Carolina, about Madrid region indicate four events during the 1800 years ago. However, no such paleolique. Past 2000 years, including one event less than 600 faction features were found in the Charleston years ago, and one cach approximately 900,1300, area. The present study, which has been ongoing and 1600 years ago. for 2 years, consists of locating and analyzing other 1800-year-old features in the Georgetown Based on the preliminary analysis of high-area, and re-investigating the Charleston resolution data acquired during FY 95 across the carthquake meiszoseismal area to identify southeast projection of the Recifoot fault,it is paleoliquefaction features of that age, if they exist. interpreted that the fault continues beyond the To date, other features of that age have been south side of Reelfoot Lake, and that the found near Georgetown but not at Charleston. cretaceous surface is uplifted 40 to 50 meters across the fault beyond the south side of the lake. Preliminary analysis of vibrioses data that were obtained from industry supports a previous PALEOSEISMICITY OF SOUTIIERN interpretation that there has been very little slip ILLINOIS,01110, AND INDIANA on the fault (about 100 m) since the late Cretaceous period. Paleoliquefaction investigations carried out in the Wabash Valley of southern Indiana and southern These investigations, along with several new Illinois during the past 2 fiscal years were studies that will continue during the next fiscal extended further into central and southern Illinois. year, are part of an ongoing effort to estimate the Paleoliquefaction evidence for the large Holocene recurrence of large-to-great earthquakes - carthquakes centered near Vincennes, Indiana, (magnitude 6-to-8)in this region, and to define and evidence for smaller events from about 4200 the causative faults. 1
l 205 GEOTECliNICAL INDICATIONS OF FAULT SEGMENTATION STUDIES i PALEOLIQUEFACTION FY 95 was the final year of investigating the fault segmentation that accompanied the 1992 earthquake in Landers, California. This study During the past 2 fiscal years, the NRC has , ndicates that, if all the fault segments within this conducted a project to identify alterations in fault system had been mvestigated before the i geotechnical properties that can be used to locate earthquake, with respect to geometry and past paleoliquefaction features. The first year's study , confirmed that during liquefaction, a stratum of behavior and usmg modern paleaseismic techniques, the segments that ruptured in 1992 water forms at the top of a liquefiable layer, just could have been predicted fairly closely. l below a relatively impermeable stratum, and this phenomenon plays a role in lateral spreading. The As part of this project, a reconnaissance was , second year s study addressed the question of
, made to an area in Mongolia that is believed to j whether h,quefaction causes changes in relative be analogous, in its intraplate setting, to the New density. Much time was spent studym, g the effects , Madrid area but with fault rupture at ground of the 1995 earthquake m, Kobe, Japan, where it
, surface rather than obscured by many hundreds was determmed that very large vertical strams of meters of sedimentary strata. Within the past caused densification. several decades, this region of Mongolia has experienced several earthquakes of magnitude 7 to nearly 8, all of which were accompanied by substantial ground rupture. The fault segments showed long periods of inactivity between ruptuic events, and instances where several segments were WEST-CENTRAL UNITED STATES ruptured during the same event. Based on obseivations of the effects of the 1957 Gobi Altai earthquake, it is believed that rupturing through several segments would not have been predicted ;
During FY 95, the NRC investigated three faults based on investigations before the earthquake. 1 showing quaternary displacements, including the Cheraw and Fowler faults on the Colorad These projects are part of an ongoing effort to Piedmont, and the IIarlan County fault in . estimate the magnitudes of future earthquakes Nebraska. Of these, only the Cheraw fault is through detailed studies of the characteristics of considered to be a tectome feature at this time, fault segments and their past behavior. The Fowler fault is probably of fluvial origm, and the liarlan County fault is currently thought to be a landslide. The Cheraw fault is 44 kilometers long, and apparently dips to the northeast at STRONG GROUND MOTION STUDIES about 50', with the hanging wall to the southeast and footwall to the northwest of the fault. It is The NRC continued to participate in several characterized at ground surface by a scarp that cost-sharing ground motion research programs in affects drainage. There is evidence of multiple cooperation with the U.S. Geological Survey. As offsets beginning about 100,000 years ago after a part of a project to estimate high-frequency long period of quiescence, with successive ground motion, an effort is being made to develop displacements about 25,000 years ago, between an improved technique to evaluate site subsurface 10,000 and 11,000 years ago, and most recently characteristics by analyzing shear waves generated approximately 8,000 years ago, based on at the surface instead of analyzing in-hole data. thermoluminescence and radiocarbon dating Another research project concentrated on methods. The calculated slip rate is 0.01 mm/yr. analyzing ground motion attenuation data in the Study of this fault illustrates temporal clustering southeastern Atlantic coastal plain, using ground and the low recurrence intervals that characterize motion data recorded by down-hole seismographs. faults in the central United States. These A third project used data recorded by the characteristics are very problematic in estimating National Seismographic Network to determine the seismic hazard of this region. attenuation characteristics in the Basin and
206 Range, southern California, and northern better results. Additional data can be expected in California. A fourth project experimented with the future from high-precision GPS networks techniques to determine a relationship between established by states and other entities. In ground motions recorded teleseismically, those addition, continuously operated GPS stations now recorded regionally, and those recorded locally. A being established by the Coast Guard and the fifth project studied the small-scale predictability Federal Aviation Administration are expected to of ground motion, based on data from the 1994 provide very detailed and accurate data in the Northridge earthquake. The sixth and final future. Information on strain distribution and research project investigated the relationship strain rates will provide a basis for refinements in among dynamic strains, site damage response, seismic hazard determinations. and ground failure using data from the l Northridge and plate interface carthquakes in i hiexico. PROBABILISTIC SEISMIC HAZARD ANALYSIS 1 GEOCHRONOLOGICAL STUDIES The Senior Seismic Hazard Assessment l Committee (SSHAC)is a panel of scientists l FY 95 was the second year of a project to assembled under the sponsorship of the NRC and ' I assemble state-of-the-scierice data on methods to the DOE. During FY 95 with input by the determine the age of geological m:iterials. Electric Power Research Institute, the SSHAC Geochronological analyses of faults, completed its final report documenting the results paleoliquefaction features, and other paleoseismic of a study of probabilistic seismic hazard analysis features are important factors in dormining the (PSHA) methodologies. The 3-year study began seismic and geological hazards of sites tu critical }v th an analysis of previous methodologies, and facilities. This year, field and laboratory ts goal was to derive guidelines for an improved experiments were conducted to validate certain methodology that is scientifically balanced and geochronological techniques and their application usable for regulatory decisions over the next i to a variety of field conditions, and a final report decade. The new guidehnes place particular was prepared. Sites tested included Hebgen Lake, weight on appropriate methods of eliciting expert Montana: Virginia Beach, Virginia: Georgetown, pimons and on rigorous treatment of South Carolina; and the Meers fault in uncertainty, both of which are of fundamental south-central Oklahoma. importance m PSijA. The study is in the final stage of a peer review by a panel convened by the National Academy of Sciences to ensure scientific objectivity. In addition, a limited test'and CRUSTAL STRAIN MEASUREMENTS implementation of the SSHAC guidelines was , started in FY 95 in order to exercise the i A 45-station crustal strain network for the central guidelines and ensure that they are sufficiently and eastern United States was established in 1987 complete to obtain the consistency sought in their and measured for the third time during FY 93. development. Calculations performed using these measurements have shown that strain rates in the central and eastern United States are low (approximately 1.5 x Plant Response to Seismic and Other 10-8). This is close to the noise level of the External Events measurements, and no differential strains have l been detected. A study of the Charleston, South l Carolina, area also determined a regional strain REPLACEMENT OF APPENDIX A TO rate of about 10-8 and a rate of about 104 in the 10 CFR PART 100 area of high seismicity around Charleston. This study concluded that triangulation data, even over Proposed geologic and seismic siting factors and a span of decades, are not sufficiently accurate to carthquake engineering criteria were published for produce valid crustal strain data, and Global public comment as Section 100.23 to 10 CFR Positioning System (GPS) measurements produce Part 100 and Appendix S to 10 CFR Part 50 on
207 October 17,1994 (59 FR 52255). When these modifications in the recommended scope of regulations become final, they will replace criteria seismic reviews. The methods and guidance in Appendix A," Seismic and Geologic Siting described in Supplement 4 to Generic Ixtter Criteria for Nuclear Power Plants," to 10 CFR 88-20 and NUREG-1407 are still acceptable (see Part 100, for new nuclear power plant the 1991 NRC Annual Report, p.174, and the applications. The notice of the availability of draft 1990 NRC Annual Report, pp.153 and 166). regulatory guides and standard review plan However, the results of the revised Lawrence sections providing methods acceptable to the Livermore National Laboratory seismic estimates NRC staff for implementing the proposed (NUREG-14SS) indicated that the perceived regulations was published on February 28,1995 seismic hazard has been reduced for most plant (60 FR 10880). The public comment period on sites in the central and eastern United States. both the proposed regulations and draft guidance Accordingly, reductions in the scope of the documents closed on May 12,1995. (See the 1994 seismic individual plant examinations of external NRC Annual Report, pp. 192-193). In general, events were identified. (For further information, most of the comments support the staff positions, see Severe Accident Implementation in this and many of the commenters provided editorial chapter.) and technical suggestions that would clarify the rulemaking. A few commenters provided more substantive comments requiring a careful COOPERATIVE INTERNATIONAL assessment of their implementation. SEISMIC PROGRAMS The NRC's participation in international seismic EXPERIENCE BASED SEISMIC test programs is beneficial both for sharing ) QUALIFICATION research resources and for gaining different perspectives on seismic design issues. Resource p ling all ws the development of large-scale In its Utilities Requirements Document for tests, which are an important element in ALWRs, the EPRI proposed the use of experience , i y lidating methods for predicting the seismic as a seismic qualification method as an applicable , response behavior of nuclear plant systems. substitute, on a case-by-case basis, for more traditional tests and evaluations (see the 1993 The Large-Scale Seismic Test (LSST) facility is NRC Annual Report, p.171). The Advanced one of ti?e largest in the world for soil / structure Reactor Corporation developed positions on the i interaction (SSI) research. The construction of a use of experience data for se,ismic qualification of 1:4-scale model of a reinforced concrete I equipment m ALWRs, as well as design-by rule containment,10.5 meters in diameter and 16.5 for cable tray and conduit systems and design meters high (1L1 meters above the ground) was concepts for IIVAC ductmg and supports. A completed in March 1993, and a formal panel of nationally recogmzed experts was
, dedication ceremony was held in Hualien, Taiwan, orgamzed by the Brookhaven National Laboratory
, , in April 1993. The LSST prc, gram at Hualien, to review and comment on this imtiative. Three Taiwan, is a follow-on to the SSI experiments at public meetings were held during FY 95 and a Lotung, Taiwan.
report documenting the panel's findmgs will be completed during FY 96. The LSST program was initiated in January 1990, and is expected to continue until 1998. The goal of this program is to collect real earthquake-induced INDIVIDUAL PLANT EXAMINATION FOR di S 1s nu lea p ver lan SEISMIC EVENTS structures. In the program, observations are made on the motions of the reactor building model and On September 8,1995, the NRC issued the surrounding ground during large-scale Supplement 5 to Generic Letter 88-20, " Individual carthquakes. The expectation is that the test Plant Examination of External Events for Severe model will be shaken by numerous earthquakes in Accident Vulnerabilities," to notify licensees of this seismically active area of Taiwan. To date, five
208 moderate earthquakes have been recorded at the to observe the damage and to discuss operational facility. Instrumentation located on the scale aspects. model and in the field along a three-dimensional strong ground motion array recorded the recent Both the Northridge and Hyogo-ken Nanbu earthquake data. earthquakes demonstrate the need to consider displacement limits as well as stress limits in EPRI has organized the Hualien LSST experiment structural members responding to earthquake and coordinated participation with the Taiwan ground motions. This is particularly true for Power Company, the NRC, the Central Research facilities within the near-field of fault rupture Institute of Electric Power Industry, the Tbkyo zones. The Nuclear Safety Commission of Japan Electric Power Company, the Commissariat a organized a special committee to review seismic l'I$nergie Atomique, Electricite de France, requirements for nuclear power plants after the Framatome, the Korea Power Engineering Co., earthquake. In a recently published report, this and Korea Electric Power Corp. In addition,in a committee concluded that there is no need to collaborative effort involving exchange of technical revise current seismic design criteria, but research information with the Ministry of International will be needed in several related areas. Trade and Industry (MITI) and the Nuclear Power Engineering Corporation (NUPEC) of Japan, the FUPEC completed seismic proving tests for a main steamline typical of PWR plants, and a SEISMIC DESIGN RULES FOR PIPING feedwater system typical of BWR plants. Tests were conducted at several levels of seismic In the 1994 Winter Addenda of Section III, ASME excitation, using both conventional and energy published revised rules for the seismic design of absorber supports for the pipmg systems. In th.is piping systems. One of the major changes in the collaborative effort, the NRC is conductmg addenda is to increase allowable stresses by 50 post-test analyses to assess the applicability of percent, which is significantly beyc,nd material currently available analytical models. Data are yield strength. Under a research program, the also bemg obtamed from NUPEC for seismic NRC has been reviewing the underlying technical provmg tests of a computer system and a reactor basis for these changes. Based on findings from shutdown coohng system. this program and participation of NRC staff members on code committees and working groups, the NRC informed ASME that it was unable to accept the revised rules pending further IIYOGO-KEN NANBU (KOBE) , , evaluation. On the basis of comments from the EARTIIQUAKE OF JANUARY 17,1995 NRC and other organizations, the ASME Section III Design Sub-Group has convened a Special An eight-member team composed of staff and Working Group on Seismic Rules (SWG-SR) to consultants representing the NRC and the DOE examine the revised rules. The SWG-SR expects visited Japan from February 11-19,1995, to gather to complete its assignment in a 2- or 3-year time data on the Ilyogo-ken Nanbu carthquake of period. January 17,1995. The team focused on evaluating the performance of industrial fa'cilities, with emphasis on power generating and distribution Generic Safety Issue Resolution facilities. Both NRC and DOE have made extensive use of experience-based data to evaluate in December 1983, the Commission approved a components and equipment in power plants and priority list of all generic safety issues (GSIs), other facilities. During the visit, the team met with including TMI-related issues. This list was " i Kansai Electric to discuss the overall performance prepared by the staff at the behest of the l of the power generating and distribution facilities, Commission, and was based on the potential I effects on the nuclear plants because of the grid safety significance of each issue and the cost of disturbances, design criteria used, steps necessary implementing a possible resolution for each. for recovery, and lessons learned. The team also Information and guidance on GSIs are reflected visited a thermal power station and a substation in the NRC's Five-Year Plan.
209 PRIORITIES OF GENERIC SAFETY been upiated semiannually with supplements in ISSUES June and December. The results of the NRC's continuing effort to identify, prioritize, and In prioritizing GSIs, the NRC continued to use resolve GLIs will be included in future risk and cost data in implementing the supplements to NUREG-0933. methodology originally described in the 1982 NRC Annual Report. In December 1983, a During FY 95, the NRC identified and prioritized comprehensive list of the issues was published in two new GSis (Table 1), and resolved one GSI "A Prioritization of Generic Safety Issues" (Table 2). Table 3 contains the sche'dules for (NUREG-0933). This list, which includes TMI resolving the 15 GSIs that remained unresolved at Action Plan (NUREG-0660) items, has generally the end of FY 95. Table 1. Issues Prioritized in FY 1995 Number Title Priority / Status 170 Reactivity Transients and Fuel Damage Criteria for Nearly Resolved l High Burnup Fuel 171 Engineered Safety Feature Failure from Loss of Offsite High Power Subsequent to a LOCA Table 2. Generic Safety Issue Resolved in FY 1995 Number Title 155.1 More Realistic Source Term Assumptions
210 Table 3. Generic Safety issues Scheduled for Resolution Scheduled Priority / Resolution Number Title Status Date 15 Radiation Effects on Reactor Vessel Supports High 12/95 23 Reactor Coolant Pump Seal Failures High 03/96 ; 165 Spring-Actuated Safety and Relief Valve High 06/98 Reliability 171 Engineered Safety Features Failure from High TBD Loss of Offsite Power Subsequent to a LOCA 24 Automatic Emergency Core Cooling System Medium 10/31/95 Switch to Recirculation 78 Monitoring of Fatigue Transient Limits for Medium 03/96 Reactor Coolant System 158 Performance of Safety-Related Power- Medium 04/96 Operated Valves Under Design-Basis Conditions B-17 Criteria for Safety-Related Operator Actions Medium 12/95 B-55 Improve Reliability of Target Rock Medium 08/97 B-61 Allowable ECCS Equipment Outage Periods Medium 83 Control Room Habitability Nearly 11/95 Resolved 145 Improved Surveillance and Startup Testing Nearly 01/96 Programs Resolved 166 Adequacy of Fatigue Life of Metal Nearly TBD Components Resolved 168 Environmental Qualification of Electrical Nearly TBD ! Equipment Resolved 170 Reactivity Transients and Fuel Damage Nearly TBD Criteria for High Burnup Resolved
l 211 PROGRESS ON GSI RESOLUTION Finally, the NRC participated in an international working group sponsored by the Organization for Economic Cooperation and Development / Nuclear As described in the 1994 Annual Report, studies Energy Agency, Committee for the Safety of and experiments continued during FY 95 related Nuclear Installations (OECD/NEA-CSNI), to the potential for BWR cmergency core cool.mg Principal Working Group 1. This international ' system stramer bk)ckage as a result of debris working group comprised participants from produced during a loss-of-coolant accident. A German, Swedish, Finnish, Japanese, and U.S. BWR6/MK1 reference plant was analyzed t?. regulatoiy authorities, the U.S. BWROG, and estimate the probability of a loss of net positive other U.S. companies, thereby enhancing the ; suction head margm, and the results were exchange of information and facilitating peer reported in NU, REG /CR-6224. The severe effects review. The charter of this working group was to of fibrous debris, coupled with filtration of other
, establish an internationally agreed-upon materials present in the suppression pool, such as knowledge base for assessing the reliability of sludge, have become more apparent from these emergency core cooling water recirculation studies and related exper,ments.
i As an example of systems. NRC-sponsored studies and experiments possible material present in the pool, this . were a major resource for developing of a draft photogiaph illustrates the resultm, g condition of a . report submitted to the OECD/NEA-CSNI in reflective metalh,e msulation assembly when September 1995. j subjected to a simulated steam line break at BWR operating conditions and, correspondingly, the ! severity of insulation destruction that can occur. Reactor Regulatory Standards ) RULEMAKING IMPROVEMENT PROGRAM QE%O g[ q ]NT ' [ g-h{NTN3
- J F 5 Mb '
In response to Executive Order 12866 (58 FR bj 1' h};;b; ? 51735) and the report of the National Performance
- ' l
* ^
1 Review, the NRC completed new procedures that i1 - , will make the rulemaking process more efficient. These procedures include the use of electronic gd7 aG . ' a] bulletin boards in rulemaking, a revised m+ - 1' concurrence process, procedures for early ) feedback from Agreement States on proposed i rules, and increased use of management steering l 3 groups. In January 1995, Management Directive !' 1 6.3, "The Rulemaking Process," containing the 4 " revised procedures was approved and published for staff use. In addition, NUREG/BR-0053,
& f j h. ~~~O~
' ~
" Regulations Handbook," was revised to
? kp > g ,, ; ,
,g implement Management Directive 6.3 in FY 95..
a w2 % u , <.c u .a M.id This handbook pmvides detailed guidance on the process used for developing regulations. The variability of U.S. BWR plant layouts and insulations employed precludes arriving at a REACTOR RULEMAKINGS singular generic solution to this safety issue. The staff and the U.S. BWR Owners' Group On September 26,1995 (60 FR 49495). the (BWROG) are continuing to exchange Commission issued a final rule on performance-experimental findings to identify resolution based primary reactor containment leakage options that are both appropriate and cost testing for water-cooled power reactors (10 CFR cffective. Part 50). The final rule amends the Commission's
212 regulations to provide a performance-based implementation and comments from the public option for leakage rate testing of LWR and industry, the final rule changes requirements containments. This option will be available for associated with controlling the access of personnel voluntary adoption by licensees, in lieu of and materials into reactor containment during compliance with the current prescriptive periods of high traffic (such as refueling and requirements contained in Appendix J to 10 CFR major maintenance). These changes relieve Part 50. This action is intended to improve the nuclear power plant licensees of the requirement focus of the body of regulations by eliminating to separately control access to reactor prescriptive requirements that are marginal to containments during these periods. Deletion of safety, and to give licensees greater flexibility for this requirement decreases the regulatory burden l cost-effective methods of implementing regulatory for the licensees without degrading physical l safety objectives. security. On September 19,1995 (60 FR 48369), the On March 14,1995 (60 FR 19002), the
. Commission issued a final rule on procurement of Commission issued for comment a proposed commercial grade items by nuclear power plant rulemaking on emergency planning and licensees (10 CFR Part 21). The final amendments Preparedness exercise requirements (10 CFR clarify and add flexibility to the process used by Part 50) for production and utilization facilities.
nuclear power plant licensees to proct:re The proposed rule would amend the regulations commercial-grade items for safety-related service. govermng domestic licensing of production and This final rule responds to a petition for utilization facilities, as necessary, to facilitate rulemaking (PRM-21-02) submitted by the greater flexibility in licensees' activities associated Nuclear Management and Resources Council with the annual "off-year" exercise. The (NUMARC), which is now incorporated into the rulemaking also preserves the existing Nuclear Energy Institute (NEI). requirement that each licensee, at each site, exercise biennially with participation by States On March 14,1995 (60 FR 13615), the and local governments within the plume exposure Commission issued a final rule to reduce pathway emergency planning zone (EPZ). In reporting requirements imposed on NRC licensees addition, the proposed rule would require for water-cooled nuclear power reactors, research licensees to continue enabling State and local an ' test reactors, and nuclear materials (10 CFR governments in plume exposure pathway EPZs to Parts 50,55, and 73). This action implements an participate in exercises and in drills during the NRC initiative to review its current regulations interval between exercises. This proposed rule with the intent of revising or eliminating responds to a petition for rulemaking submitted duplicative or unnecessary reporting by the Virginia Electric and Power Company requirements. (PRM-50-58). On March 6,1995 (60 FR 17902), the Commission During FY 95, the Commission withdrew six NRC issued for comment a proposed rulemaking on Policy statements that have been superseded by standard design certification for evolutionary subsequent NRC rulemaking actions: light-water reactors (10 CFR Part 52). The . e Nuclear Power Plant Access Authon.zation Commission anticipates that applications for design certification may be ready for such Program, March 9,1988 (53 FR 7534) j rulem combm,akings in the future. An applicant for a e Training and Qualification of Nuclear Power ed beense under 10 CFR Part 52 may use Plant Personnel, March 20,1985 (50 FR these certified designs without further m, depth review by the NRC. 71347) e Fitness-for-Duty of Nuclear Power Plant On September 7,1995 (60 FR 46497), the Personnel August 4,1986 (51 FR 27921) Commission issued a final rule on changes to nuclear power plant security requirements e Maintenance of Nuclear Power Plants, associated with containment access control December 8,1989 (54 FR 50611) (10 CFR Part 73). Based on staff review experience gained in security program o Information Flow, July 20,1982 (47 FR 31482)
213 c Planning Basis for Emergency Responses to the policy concepts included in the NRC Nuclear Power Reactor Accidents, guidelines, and translates the six steps in October 23,1979 (44 FR 61123), preparing regulatory analyses into implementable methodologies for the analysts. j A notice of withdrawal of these policy statements f 4 was published in the Fedeml Register on During this report period, the NRC also January 20,1995. The decision for withdrawal of completed or mitiated the development or review I these policy statements does not change reporting of about 18 safety-related regulatory impact , analyses to evaluate new regulatory regmrements requirements for licensees, and does not in any way reduce the protection of the public health and or actions for NRC licensees. safety. Reactor Radiation Protection and IIcaltli Effects REGULATORY ANAIXSIS GUIDELINES The NRC maintains a program of research and standards development in radiation protection The NRC performs regulatory analyses to support and health effects intended to ensure continued numerous regulatmy actions that affect nuclear protection of workers and the public from i I power reactor and nonpower reactor licensees. As radiation and radioactive materials in connection such, the related guidelines set forth a number of with licensed reactor activities. The program policy decisions that have broad implications for includes improving health physics measurements, the NRC and its licensees with regard to the identifying and disseminating cost-effective dose preparation and contents of regulatory analyses. reduction techniques, assessing health effects The revised guidelines reflect the NRC's consequences of postulated reactor accidents, and accumulated experience with implementing monitoring health effects research. Revision 1 of the guidelines, as well as changes in NRC regulations and procedures since 1984, especially the backfit rule (10 CFR 50.109) und REACTOR RADIATION PROTECTION the Policy Statement on Safety Goals for tLe RULEMAKINGS Operation of Nuclear Power Plants (51 FE 30028; August 21,1986). The revised guidelines aho On July 13,1995 (60 FR 36038), the Commission reflect advances and refinements m regulatory issued a final rule on radiation protection analysis techniques, and regulatory guidance for
, requirements to amend definitions and criteria Federal agenc,es i issued by President Clinton, the Adnum,strative Conference of the United States, (10 CFR Parts 19 and 20). The final rule amends the Commission's regulations in the following and the Office of Management and Budget. In ways:
addition, the revised guidelines incorporate procedural changes designed to enhance the e Deleted the definition " controlled area" to NRC's regulatory effectiveness. make it clear that any area to which access is restricted for the purpose of radiological The staff .is also m. the process of rev. .ismg protection is a restricted area as defined in NUREG/BR-0184," Regulatory Analysis the regulation Technical Evaluation Handbook," which was issued as a draft report in August 1993. This e Revised the definition of " occupational dose" handbook is to provide guidance and to delete reference to the " restricted area" standardized methods for reguletary analysts to use in preparing and presenting high quality e Revised the def'mition of " unrestricted area" regulatory analyses, including backfit and CRGR to be consistent with the deletion of regulatory analyses. The handbook also controlled area implements the policies of the " Regulatory Analysis Guidelines of the U.S. Nuclear e Revised the provision in 10 CFR Part 19 Regulatory Commission," NUREG/BR-0058, entitled " Instruction to Workers," so that ! Rev. 2. In addition, the handbook expands upon radiation protection training will be provided
214 to all persons with the potential to be continued publishing the newsletter, "ALARA occupationally exposed Notes," on about a quarterly schedule. e Restored a provision in 10 CFR Part 20 to BNL also published NUREG/CP-0143, provide that whenever licensees are required "Proceedm, gs of the Third International Workshop to report exposures of individual members of n the Implementation of ALARA at Nuclear the public to the NRC, those individuals are Power Plants," in hf arch 1995. The report includes to receive copies of the report p pers presented by nat,onali and international representatives of the nuclear mdustry on a wide range p sre se contml On February 10,1995 (60 FR 7900), the Commission issued a final rule on the frequency of medical examinations for use of respiratory protection equipment (10 CFR Part 20). The final CONTROL ROOM HABITABILITY rule amends the Commission's regulations concerning the required frequency of medical During FY 95, the NRC published two reports examinations to ensure the safe use of respiratory related to air quality and control room protection equipment. It also requires a habitability. PNL 10286, " Atmospheric Dispersion determination by a physician before the first field Estimates in the Vicinity of Buildings," published use of respirators (and periodically thereafter) in January 1995, provides validation of a model to that the individual user is medically fit to use the be used for predicting air quality at control room respiratory protection equipment. air intakes in the event of an accident. , NUREG/CR-6331, " Atmospheric Relative On hf arch 25,1995 (60 FR 20183), the Concentration in Building Wakes-ARCON 95 Commission issued a final rule clarifying the Code, prepared also by 1,NL, was published m, superseded 10 CFR Part 20 recordkeeping hiay 1995. This report provides a validated code requirements. This final rule reinstates certain for calculating accident-caused concentrations at record retention requirements not intended to be control room air mtakes when adjacent buildings removed that were inadvertently deleted. In so frect flow characteristics. doing, this rulemaking ensures that licensees s!> c sting p vis ons f a t 20 OCCUPATIONAL EXPOSURE DATA SYSTEh1S The NRC continued to collect and process data in l BROOKHAVEN NATIONAL L.ABORATORY the computerized Radiation Exposure ALARA CENTER Inf rmation Reporting System (REIRS), which provides a permanent record of worker exposures for reactors and several other categories of Funded by the NRC, the Brookhaven National licensees. A report on 1993 exposures, Laboratory (BNL) ALARA Center, continued its " Occupational Radiation Exposure at surveillance and dissemination of DOE and Commercial Nuclear Power Reactors and Other industry dose reduction and ALARA research. Facilities-1993" (NUREG-0713, Vol.15), was , This work includes abstracting national and issued in January 1995. Compilation of the ' international articles and books that discuss dose statistical reports indicated that approximately reduction in areas such as plant chemistry, stress 190,000 individuals were monitored during 1993, corrosion cracking, steam generator repair and and one-half received a measurable dose. The replacement, robotics, and decontamination. In average measurable dose remained steady at 0.31 hiay 1995, the NRC published NUREG/CR-3469 rem (cSv) for 1993. The collective dose obtained (Vol. 8), " Occupational Dose Reduction at NPPs: from summing all of the individual doses was Annotated Bibliography of Selected Readings in 29,045 person-rem (person-cSv). The database Radiation Dose Reduction and ALARA." This also includes exposure data on approximately information is particularly important to power 687,000 individuals who have terminated reactor facilities in the planning stage. BNL also employment with certain licensees, most of whom
r-l 215 worked at nuclear power plants. The NRC at the two sites, with the possibility of including continued to respond to requests for individual americium-beryllium neutron sources at a later exposure data from the system. The data also date, since the revised standard used for the assist in examining the doses incurred by NVLAP testing program, ANSI N13.11-1993, now transient workers as they move from plant to includes the americium-beryllium neutron ; plant. category. ! i In addition, a homepage for the Internet's I Worldwide Web was developed for NUREG-0713. ! This homepage includes how to submit an annual GAMMA-RAY DOSIMETER / 1 report of occupational radiation exposure, and the SPEGROMETER
- address to which the report is to be mailed. It also tells of upcoming meetings related,to Work under an ongoing Small Business Innovative occupational exposure reportmg, contams the Research (SBIR) Phase II contract involves the May 1991 issue of Part 20, cnd provides links to development of a pre-production prototype other related sites. Yttrium Aluminum Perovskite (YAP) plastic combination gamma-ray dosimeter spectrometer, In September 1994, the staff published Generic coupled to a miniaturized multichannel analyzer, Letter 94-04, " Voluntary Reporting of Additional and evaluation of its performance in extensive Occupational Radiation Exposure Data," as a field trials. YAP, a rugged inorganic scintillator mechanism to complete the available REIRS data used principally in the former Soviet Union, is a on occupational exposure. With the revision of much faster detector than the commonly used Nal 10 CFR Part 20, licensees are required to submit scintillator. As a result, YAP is expected to only data on the present year's activities. replace Nal in high-intensity radiation fields, and Previously, data were collected at the time an in areas of high humidity and temperature, where individual terminated employment. Thus, in order the Nal is more environmentally sensitive. Phase I to complete the database, data were requested for research established the feasibility of using YAP persons that were employed as of January 1,1994 phoswich-type detectors, and the present work is who were not already covered by termination expected to lead to commercially feasible YAP reports, dosimeters for use over a wide environmental range.
NATIONAL INSTITUTE OF STANDARDS AND TECIINOLOGY ELECTRONIC PERSONNEL DOSIMETERS Work is continuing at the National Institute of On August 16,1995, PNL published a notice of Standards and Technology (NIST), under availability for review and comment (60 FR 42629) Interagency Agreement RES-93-017, on an of NUREG/CR-6354, " Performance Testing of ongoing study aimed at developing protocols and Electronic Personnel Dosimeters." This report quality assurance and quality control procedures discusses the possible uses of electronic personnel needed for NIST to establish traceability of dosimeters (EPDs) as potential alternatives to neutron sources. The : vrees are used by Pacific conventional dosimeters (such as film badges or Northwest Laboratories (PNL)in their role as thermoluminescent Ssimeters), examines their testing laboratory for the NIST/NVLAP reliability, and suggests a set of performance tests accreditation program for dosimeter processors and implementing procedures to ensure their mandated by the NRC. Calculations of the fluence proper performance if used in lieu of conventional l and current of PNL and NIST sources has been dosimetry. Following an analysis of comments on ! completed, and the present work involves the subject report, it is expected that a series of i establishing protocols for intercomparison of side-by-side tests with conventional dosimeters measurements at the two sites, using transfer will be undertaken to establish the reliability of survey instruments. The current work also EPDs in various environments (such as electrical, involves comparing californium neutron sources magnetic, and electromagnetic fields).
216 SPENT FUEL HEAT Gk UERATION always be covered with either a single-phase liquid or a two-phase mixture. In Septembe mn ihe 6 x Ndge National A best-estimate computer code RELAP5/ Laboratory (r R "Techmcal Sm . ' ynur < NUREG/CR-6525, MOD 3.2, is being assessed against the test data
, 'roposed Decay H for validation and ultimate application to the Guide Using i V . uGEN-S Data." Tlu, seat AP600 plant' document improve. . daiabase for BWR and PWR sel decay heat generation by analyzing As reflected in ROSA and OSU facilities, the recent data to provide a basis for evaluating the AP600 safety systems appear to perform as adequacy of storage system heat removal designed, and there is no evidence of core heatup capability to limit fuel rod temperature. for a variety of accident conditions. Nonetheless, three phenomena have been identified as safety related, and are being examined to determine whether they are relevant to the AP600 design.
STANDARD REACTOR DESIGNS . . . The first phenomenon is the rapid condensation and potential for water hammer that may occur following the actuation of the automatic Systems Performance of Advanced depressurization system (ADS). The second is a Designs large thermal gradient in the cold leg where cooled water returned from the passive residual heat removal system forms a stratified thermal SUPPORT FOR AP600 DESIGN REVIEW l yer t We bottom. These two phenomena may affect structural integrity. Confirmatory testing and analysis of the The third phenomenon relates to the operation of ! Westinghouse AP600 reactor and plant systems the plant. Specifically the ROSA testing showed are being carried out to reinforce confidence in that, as the system depressurized as part of the the NRC's safety evaluation of the AP600 design. accident mitigation process,it exhibited an The testing is taking place in two different scaled oscillatory behavior. System-wide oscillations facilities, including the 1:30-scale Rig of Safety started following the ADS stage 4 actuation and Assessment (ROSA)in the Japan Atomic Energy persisted until the liquid in the pressurizer Research Institute (JAERI) and the 1:200-scale drained out and the steam generation in the core Oregon State University (OSU) facility, became insignificant. A large amount of liquid was previously carried over to the pressurizer The ROSA testing is being conducted under a during the ADS stage 1 to 3 operations. Following cooperative agreement between the NRC and ADS stage 4 actuation, the majority of the flow JAERI. So far,14 tests have been conducted in went out to the containment through ADS 4, and ROSA covering various accident scenarios such very little or no flow went out through ADS 1-3. as small-break loss-of-coolant accidents, steam Therefore, the liquid in the pressurizer could no generator tube rupture, main steam line break, longer be supported and must drain down to a and station blackout. Both design-basis accident level that can be supported by a new condition and beyond-design-basis accident scenarios were prevailing after ADS 4 actuation. However, this included. Since the ROSA facility is a full. draining process is not smooth because the vapor pressure facility, high-pressure phenomena are that must occupy the space created by the being investigated in ROSA, while low-pressure draining liquid must come from below through phenomena related to long-term cooling are being the surge line, which is too small for a stable mvesti3ated in OSU. In OSU,12 tests have been vaporliquid countercurrent flow. Osciliation is conducted covering both design-basis and probably also caused by the fact that the beyond-design-basis accident scenarios. preferential passage of steam in the ADS 4 line causes a periodic fill-up or plugging of liquid at a The results of both confirmatory testing programs certain location of the ADS 4 line. The liquid plug suggested that the core would be effectively cooled blocks steam venting and causes a pressure for a variety of accident conditions, and would buildup until the pressure is high enough to clear
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218 A new test program was initiated in FY 95 to IIUMAN RELIABILITY verify the performance of passive autocatalytic recombiners (PARS). PARS have been pioposed Efforts are continuing to develop methods for recently by Westinghouse as part of the AP600 assessing the impact on risk of changes in human design certification to control combustible gases performance due to the introduction of advanced in the containment following a design-basis digital displays and controls. These methods were loss-of-c(x)lant accident. Experiments will be tested on control stations representative of a performed in FY 96 to examine the startup retrofit, a hybrid, and an advanced control room characteristics, the hydrogen depletion rate, and configuration. The results were peer reviewed and the performance of PARS in the presence of the final report is in preparation. steam. The results will be used to develop an . independent audit capability to evaluate the Research to establish a techm. cal basis for performance of PARS. minimum operations shift staffing for advanced control room des,gnsi was m, itiated in Fiscal Year 1994 at the Halden Reactor Project. The research is based on workload and task allocation studies. Data were collected at the Loviisa plant simulator SUPPORT FOR SBWR DESIGN REVIEW
"' P h"on igui n and 'fl be co ec e tf e Halden Man-Machine Laboiatory simulator to represent To provide confirmatory testing and computer the advanced configuration. Loviisa plant code assessment for the General Electric Perators are serymg as subjects m, the Simplified Boiling Water Reactor (SBWR), the expenments. Thsk network modehng will also be NRC established a research program composed of used to estimate performance.
three elements. The first element is the Purdue University Multi-Dimensional Integral Test Regulatory Application of New Source Assembly (PUMA), a well-scaled integral test Terms facility for investigating a broad spectrum of loss-of-coolant accidents in the SBWR. For the The Commission's reactor site criteria (10 CFR second element, tests will be performed in the Part 100) require that an accidental fission PUMA facility to produce data for a broad product release from the core into containment be spectrum of loss-of-coolant accidents and assumed to occur, and that its radiological transients postulated for the SBWR. For the third consequences be evaluated. The criteria for the element, the PUMA data will be used to assess release into containment are derived from the the capabilities of the thermal-hydraulic RELAP5 1962 report, TID-14844. code for SBWR analysis, as well as the capabilities of the CONTAIN code for SBWR Since 1962, the NRC has gained a better contamment analysis. The PUMA data will als understanding of the timing and nature of fission be used to assess the mtegral performance of the product release. As a result, the staff has SBWR-unique safety systems that mamtam core identified a number of regulatory activities that and contamment cochng, and to identify and may benefit from changes introduced as a result understand the important phenomena observed in of source term and severe accident research. NRC the tests. research in this area is reflected in the updated version of TID-14844, which has been in use for three decades in connection with plant siting PUMA has a low-pressure (150-psi),1/4-height assessments. An extensive review of the updated facility with a volume 1/400 of the SBWR volume. TID-14844 has been completed; and the final Scaling analysis and facility design were NUREG-1465, " Accident Source Terms for completed in 1994, and facility construction was Light-Water Nuclear Power Plants," was completed at Purdue University in September published in February 1995. The revised source 1995. Shakedown tests were scheduled for terms are currently being used in the AP600 completion in November 1995, and a total of certification, and the NRC and the utilities are approximately 30 integral tests will be performed evaluating their use for current reactor licensing by December 1996. applications.
219
)
1 UPDATE OF SITING REGULATIONS The first volume of each set identifies human factors problems within each system, presents In FY 95, staff efforts continued to update 10 alternative approaches to solving these problems, CFR Part 100," Reactor Site Criteria." A and assesses these approaches with respect to proposed rule to revise Part 100 was first issued their relative ability to solve the system's human for comment in October 1992. That proposed rule factors problems. The remaining volumes of each climinated source term and dose calculations for set support the findings described in the first reactor siting by specifying a minimum exclusion volume, providing results of job and task analyses, area distance, and by stating population density as well as indepth studies of human-system criteria. An update of the seismic criteria would interface, procedures, training, and organizational incorporate probabilistic, as well as deterministic, practices and policies for each of the systems. methods. Extensive comments, both domestic and foreign, favoring the continued use of source term Materials Regulatory Standards and dose calculations for reactor siting were On December 2,1994, the Commission issued a received. As a result,in October 1995, the final rule (59 FR 61767) on the use and proposed rule was withdrawn, and a revised , Preparation of radiopharmaceuticals for proposed rule was published in the Federal , diagnosis, therapy, or medical research (10 CFR
- Register for public comment (59 FR 52255). This Parts 30,32, and 35). This action was taken m proposed rule incorporates basic reactor site response to a petition for rulemaking criteria, and continues the use of source term and (PRM-35-9). The final rule provides greater dose calculations for siting plants. The public flexibility by allowmg properly qualified nuclear comment period ended on May 12,1995. The Pharmacists and authon, zed physician users comments are currently being evaluated, and a , ,
greater discretion in preparmg radioactive drugs final rule is expected to be issued in 1996. contaimng byproduct material for medical use. ' This rule will also allow research involving human [ subjects using byproduct material, as well as i medical use of radiolabeled biologics. MATERIALS USERS On December 14,1994, the Commission issued a final rule (59 FR 64283) on notification of ; incidents (10 CFR Part 72). This rule amends the regulations to revise licensee reporting requirements regarding the noMcadon of mnts ; NUCLEAR MATERIALS RESEARCH related to radiation safety at independent spent ! AND REGULATION DEVELOPMENT fuel storage installations (ISFSIs) and monitored l retrievable storage (MRS) installations. l On August 15,1995, the Commission issued for Mater.ials Licensee Performance comment a proposed rulemaking for comment (60 FR 42079) on physical protection requirements for l Through its human factors regulatory research
, storage of spent fuel (10 CFR Parts 72 and 73). I program, the NRC seeks to improve its The proposed rule amends the regulations for the understand,mg and to maintain its requirements physical protection of spent fuel stored under a concernmg the effect of human performance on specific license. This action is necessary to clarify the safety procedures involving the medical and the physical protection requirements for ISFSIs industrial use of nuclear materials. During FY 95, and MRS installations owned by the Department comprehens,vei reports were completed on, the .of Energy. This proposed rule would not affect results of extensive human factors evaluations of spent fuel stored at power reactor sites under a medical systems that use nuclear byproduct generallicense, and would reduce the regulatory materials. NUREG/CR-6277 is a five-volume uncertainty regarding the physical protection report on the human factors evaluat,oni of requirements for ISFSIs.
teletherapy, and NUREG/CR-6125 is a three volume report on the human factors On December 22,1994, the Commission issued a evaluation of remote afterloading brachytherapy. final rule (59 FR 65898) on adding a standardized
I 1 220 l IIUHOMS cask to the list of approved spent fuel offsite consequences, and to decommission the storage casks (10 CFR 72.214). This rule will facility effectively to the new licensee. Similarly, increase the number of NRC-certified spent fuel the proposed rule would require a licensee to send storage casks from which the holders of power records, such as waste disposal and dose records, reactor operating licenses can choose to store to the NRC after the license is terminated. spent fuel under a general license. On January 4,1995, the Commission issued a Two petitions for rulemaking were granted during final rule (60 FR 322) on preparation, transfer for FY 95: PRM-21-02 from NUMARC was granted commercial distribution, and use of byproduct by publishing a final rulemaking anendment to material for medical use (10 CFR Part 32). The 10 CFR Part 21 on September 19,1995 (60 FR final rule will amend the regulations to provide 48369). PRM-35-09 from the American College of greater flexibility in these areas. Nuclear Physicians was granted by publishing a final rulemaking amendment to 10 CFR Part 35 The NRC is currently developing a final rule that on the use of radiopharmaceuticals on would amend the Commission's regulations to December 2,1995 (59 FR 61767). revise the radiography and radiation safety requirements for radiographic operations (10 CFR Part 34). 'Ihe final rule would amend the Materials Radiation Protection and regulations to clarify the requirements in Section IIcalth Effects 34.27 and to bring Part 34 into conformance with the approach developed by the Conference of Radiation Control Program Directors, Inc., and the State of Texas in Part 31 of the Texas MATERIALS RADIATION PROTECTION Regulations for Control of Radiation. Comments RULEMAKING and suggestions from regulatory groups, users, and manufacturers are considered in the final On September 20,1995, the Commission issued a revision. In December 1994, the NRC staff held a final rule (60 FR 48612) on administering 3-day public workshop with Agreement States and radiation and radioactive materials to patients the American Society for Nondestructive Testing (10 CFR Parts 20 and 35). The final rule will to discuss the issues and possible resolutions. amend the regulations to clarify that the This rulemaking will also respond to a petition for administration of radiation or radioactive rulemaking (PRM-34-4) from the International materials to any patient, even a patient not Union of Operating Engineers, Local No. 2. The supposed to receive an administration,is final rule will be published in FY 96. regulated by the NRC's provisions governing the medical use of byproduct material and is not The NRC is also developing a final rule that within the scope of regulations concerning NRC's would amend the Commission's regulations to standards for protection against radiation. This revise the patient release criteria contained in rule was necessary to indicate clearly that this has 10 CFR 35.75, and the applicability of the dose been the NRC's policy; it does not represent a limits for mernbers of the public in 10 CFR change in policy. 20.1301. This rulemaking will respond to the requests of three petitions for rulemaking. On December 28,1994, the Commission issued PRM-20-20 from Dr. Carol S. Marcus and for comment a proposed rulemaking (59 FR PRM-35-10/10a and PRM-35-11 from the 66814) on recordkeeping requirements regarding American College of Nuclear Medicine. These the termination or transfer of licensed activities requests expressed concern that the five-fold (10 CFR Parts 30,40,70, and 72). The proposed reduction in the public dose limit (5 to 1 mSv y-1) rule would amend the regulations pertaining to might lead to a five-fold reduction in the exposure l l the disposition of certain records when a licensee rate and activity criteria for patient release. terminates licensed activities, or when licensed Consequently, patients might have to remain in activities are transferred to another licensee. If hospitals for a longer period of time, and patients licensed activities will continue at the same now treated on an outpatient basis would have to c location, the proposed rule would require a be hospitalized. However, the new criteria for l licensee to transfer records necessary to evaluate patient release are dose based, rather than activity ;
221 based, and are consistent with the recom- The Commission also denied two petitions for mendations of the International Commission on rulemaking during FY 95. In PRM-20-23 from l Radiation Protection (ICRP) and the National Steve Gannis, dated March 13,1995 (60 FR Council on Radiation Protection and 13385), the petitioner requested that the Measurements (NCRP). Licensees may authorize Commission amend its regulations because he a patient's release if the total effective dose believed the requirements in 10 CFR Part 20 equivalent to any other individual from exposure should limit annual dose of radiation to the public to the released individual is not likely to exceed 5 to 1 mr. PRM-72-01 from the Maryland Safe millisieverts (0.5 rem). The final rule will be Energy Coalition dated July 26,1995 (60 FR published in FY 96. 38286), i& ntified generic issues related to dry cask storage (10 CFR Part 72). In support of this final rule and under a grant funded by the NRC, the NCRP published NCRP EMllRYO/ FETAL DOSE FROM Commentary No.11, " Dose Lumts for Individuals MATERNAL INTAKE Who Receive Exposure from Radionuclide Therapy Patients." This commentary addresses In FY 95, the NRC comp leted a study to improve , the risks to members of the pubhc exposed to understandm.g of the contribut. ion of maternal radiation from radionuclide therapy patients, , r dionuclide burdens to prenatal radiation discusses the societal costs and benefits of exp sure; the final report is scheduled to be controlling these risks, and recommends methods published in FY 96. The methods and data by which the radiation risks to the public can be developed under this project have been used by controlled in a manner that is as low as i reasonably achievable (ALARA) and acceptable !.he NRC m prepar,ng Regulatory Guide 8.36, Radiation Dose to Embryo / Fetus," which from the viewpoint of patient access to efficacious , describes acceptab'; methods of comphance with medical care' Section 20.1208 0110 :FR Part 20.This guide might have to be revised to incorporate the inf rm ti n that will be presented in the final , During FY 95, the Commission approved a rep rt. The methods developed under this project proposed rule that would amend the regulations , to constrain air emissions of radionuclides to .also useful in calculations of doses in cases of accidental releases of radioactive materials, 10 mrem /yr, similar to the program developed pursuant to Appendix I to 10 CFR Part 50 for power reactors. The proposed rulemaking will codify the regulatory basis for the Environmental CRITICALITY AND FUEL CYCLE SAFETY Protection Agency (EPA) to make a legal finding that the NRC program provides an ample margin During FY 95, the Oak Ridge National of safety to protect the public and the Laboratory continued to develop a slide rule for environment from air emissions of radionuclides. estimating nuclear criticality information. One Such a finding would permit the EPA to rescind goal of this project is to provide information 40 CFR Part 61 for NRC-licensed facilities other usef'.il in estimating potential fission yields for than power reactors.This proposed rule will homogeneous fissile material solutions. The demonstrate that the NRC program is sufficient second goal is to provide a readily available to protect the public and the environment from nuclear criticality accident emergency evaluation airborne radienuclide emissions from and response tool that will address the NRC-licensed lacilitis, and to eliminate the need preponderance of potential accidents at for dual regulation, thereby reducing the burden NRC-licensed nonreactor nuclear facilities that of compliance on licensees, process fissionable materials.
222 LOW-LEVEL WASTE AND MATERIALS AND ENGINEERING DECOMMISSIONING Engineered Enhancements and Alternatives to Shallow Land Burial Many States and State compacts are considering engineered enhancements for the disposal of LLW. These enhancements ialude particularly the use c neret engineered baniers to contain M DEVELOPMENT OF LOW-LEVEIs NRC research conducted at the National Institute ; WASTE REGULATION AND of Standards and Technology (NIST) has i GUIDANCE investigated the long-term performance of concrete for LLW applications. Tins research identified the degradation mechanisms affecting concrete for LLW disposal, and developed ! On March 27,1995, the Commission issued a final mathematical models of the major degradation l rule (60 FR 15649) on low-level waste (LLW) mechanisms. The researchers also made manifest information and reporting (10 CFR ) recommendations concerning the types of ' Parts 20 and 61). The final rule amends the aggregates to be used in concrete, analyzed regulations to improve information contained in laboratory data on sulfate and chloride ion < manifests accompanying shipment of waste to diffusivity in concrete, and developed a computer LLW disposal facilities licensed under Part 61. In model to estimate hydraulic conductivity of addition, the final rule develops a uniform concrete as a function of time for LLW facility ; manifest for national use. it also requires that performance assessment. Five reports of the NIST operators of these disposal facilities store work are being prepared as NUREG-series manifest information in electronic recordkeeping documents that address the following topics: systems, and require that operators be capable of submitting, on a computer readable medium, e a new method to determine chloride ion l reports of shipment manifest information. diffusion coefficients in concrete (NISTIR-5235) On July 18,1995, the Commission issued a notice e prediction of cracking in concrete of withdrawal (60 FR 36744) regarding land (NISTIR-5634) ownership requirements for LLW sites (10 CFR Part 61). An advance notice of proposed e evaluation of the effects of stresses caused by rulemaking (ANPRM) was published to request sulfate attack in concrete (NISTIR-5390) public comments on allowing a licensee to own land that is used for an LLW disposal site. The e sulfate diffusion in concrete (NISTIR-5361) Commission subsequently determined that this e 4 SIGHT a computer program for modeh.ng rulemaking is unnecessary, and withdrew the ANPRM. degradation of underground LLW concrete vaults (N1 STIR-5612). NRC research in support of regulatory activities The computer program for modeling the for LLW disposal facil ties is focused on making degradation of concrete for LLW performance , more realistic assessments of the overall assessment incorporates synergistic degradation performance of disposal systems. The results of mechanisms, the effects of cracks and joints, and NRC research are useful to the States regulating the precipitation of concrete dissolution products. LLW disposal and are made available to the States through NRC-sponsored workshops,
, , LLW Waste Forms participation by NRC contractors m forums sponsored by other agencies, as well as the In 1995, research at the Idaho National conventional method of publication in journals. Engineering Laboratory (INEL) on the stability of
l l 223 nuclear reactor decontamination waste was Infiltration of Water cxtended to examine samples from a full reactor decontamination at Indian Point. These studies were aimed at determining radionuclide and The University of California at Berkeley, in chelating agent releases, as well as the cooperation with the University of Maryland, compressive strength of the cement solidified continued to field test-at the Maryland waste. Test results are being summarized in Agricultural Experiment Station in Beltsville, papers that will be published in scientific Maryland-a variety of covers for use in LLW literature and in NUREG-series reports prepared disposal. In addition to any LLW disposal method by contractors. that includes an earthen cover, these cover,s can also apply to LLW, the Site Decomm,ssiomngi Management Plan (SDMP), Uranium Mill Tailings Remedial Action (UMTRA), and hazardous waste Plutonium 239 (Pu-239) activity levels in sites. Two designs are proving to be particularly decontamination wastes presented in effective. One, called bioengineering water NUREG/CR-6201 were used by the National management, shown in the following two Academy of Sciences in assessing potential photographs, reduced water infiltration to a Pu-239 inventory levels for the proposed Ward negligible amount, and dewatered the cells to Valley LLW disposal facility, which it was applied. Hence, this cover lends itself to remedial action Field lysimeter studies containing radioactive for sites susceptible to subsidence. In 1993, the ion-exchange resins solidified in cement and vinyl New York State Energy Research and ester-styrene continued at the Oak Ridge and Development Administration finished Argonne National Laboratories to determine constructing a bioengineering water management radionuclide release rates and transport in soils cover over such a trench at the West Valley LLW under environmental conditions. Recent disposal facility in New York. A second promising observations (NUREG/CR-5291) have indicated cover consists of a conductive layer barrier placed upward migration at the ORNL site, and a below a resistive layer barrier. This cover has preliminary investigation was completed on the functioned perfectly since its installation in presence of radio-colloids in leachate from the January 1990. Research results for 1995 were lysimeters. published in NUREG/CR-4918, Volume 8. In 1995, PNL completed a hydrologic evaluation Studies were also completed at INEL during methodology for estimating water movement FY 95 (NUREG/CR-6188) to investigate through the unsaturated zone at commercial LLW biodegradation of LLW by microorganisms to sites; this methodology is documented in ensure that the stability requirements of 10 CFR NUREG/CR-6346, which presents results from Part 61 are met, and to evaluate microbially two application studies for a hypothetical arid site enhanced release of radionuclides from LLW. and humid site. The report demonstrates the Studies continued at the Pacific National methodology, using actual site-specific data and Laboratories (PNL) to assess levels of long-lived realistic facility designs. It also demonstrates radionuclides in LLW and to determine scaling strategies for addressing the analytical difficulties factors for assessing hard-to-measure arising in any complex hydrogeologic evaluation of l radionuclides in LLW. Work at PNL examined the the unsaturated zone. PNL and its subcontractor, l effeca of chelating agents used in reactor New Mexico State University, have also developed decontamination on leaching and transport in the PolyRES code for solving transient, soils of radionuclides from LLW. Also a new two-dimensional water flow in unsaturated-research project was initiated to determine the saturated soils; this code is documented in solubility of radionuclides found in LLW and at NUREG/CR-6366, which provides example l contaminated sites for use in source terms used in problems demonstrating the versatility and ! performance assessments for license reviews. robustness of the PolyRES code. 1
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i 225 l HYDROLOGY AND National Academy of Science / DOE workshop on surf ce and subsurface barriers for long-term l GEOCHEMISTRY containment of radioactive waste. The USGS-NRC cooperative research program related to LLW continued in FY 95 and included a l l Radionuclide Migration in Soil workshop held in conjunction with the PNL technical briefing on the completed research Current models of radionuclide retardation in studies. soils introduce significant conservatism into current assessments of performance of an LLW disposal facility.This conservatism results from the quantitative uncertainty as to the degree of COMPLIANCE, ASSESSMENT, AND
- retardation in different soil types under various MODELING conditions.
To reduce this uncertainty, and permit more Performance Assessment realistic assessment of actual expected performance of an LLW disposal facility, the During FY 95, the NRC continued research to NRC is developing more realistic retardation develop a realistic, flexible, and computationally models based on field observations and tractable performance assessment methodology to laboratory experiments. At the Chalk River in suoport decontamination and decommissioning Canada, PNL collected air, water, soil, and activities for contaminated sites. These activities vegetation samples at a site contaminated by a include risk assessment, site characterization, ground-water plume containing C-14. Radio- remediation, and site monitoring, chemical analyses are under way to determine C-14 transfer and uptake coefficients in RW Source Term Modeling vegetation for the soil-to-plant and air-to-leaves pathways. Work also continued on the role of During FY 95, extensions were completed to the naturally produced organic complexes and existing breach, leach, and transport (BLT) LLW microparticulates m enhancmg migration. source term code developed by the Brookhaven National Laboratory to incorporate additional During FY 95, Sandia National Laboratories geochemistry and gaseous release. The (SNL) and the U.S. Geological Survey (USGS) background, theory, and description for the continued to examine the application of surface extended model were recently published in modeling to describe complex soil retardation NUREG/CR-6305, and the code documentation processes. The SNL work focused on theoretical and user's guide are currently being finalized. development of appropriate models and supporting laboratory experiments. The USGS work involved application to uranium transport at a uranium ore body in northern Australia. During DECOMMISSIONING AND 1995, a new NEA sponsored international study ENVIRONMENTAL PROTECTION (Analogue Studies in the Alligator Rivers Region) REGULATION of tlus uramum deposit was imtiated m which the NRC will participate and share the data and results from the USGS project. On July 26,1995, the Commission issued a final rule (60 FR 38235) to clarify decommissioning funding requirements (10 CFR Parts 30,40,70, l Hydrology and Contaminant 'Ransport and 72). The final rule amends the regulations for non-reactor licensees on the expiration and PNL has completed work in cooperation with the termination of licensees. This rule stipulates that USGS demonstrating its infiltration methodology financial assurance must be in place and updated I using the USGS research data from the LLW when the licensee decides to cease operation and l disposal facility in Beatty, Nevada. The USGS begin decommissioning. These amendments i and PNL investigators presented their work at a explicitly describe the implementation and timing j
l 226 requirements for licensees who have been in As previously noted, regulatory guidance is being timely renewal since the issuance of the 1988 prepared to assist licensees in irnplementing the decommissioning funding rules, as well as final rule. This supporting guidance will provide licensees who cease operations without adequate measurables in the form of surface and volume funding arrangements in place. radioactivity concentrations and site radioactivity inventory values. The staff held a special On July 20,1995, the Commission issued for workshop in September 1995, inviting public comment a proposed rulemaking (60 FR 37374) participation on the development of methods for on decommissioning nuclear power reactors surveys and dose methodology to be included in j (10 CFR Part 50). The proposed rule would the regulatory guidance. Also, the NRC published I amend the Commission's regulations on the three documents in August 1995 as draft reports i decommissioning procedures that lead to the for comment to support the regulatory guide termination of an operating license for a nuclear preparation. These are NUREG-1505, "A power plant and release of the property for Nonparametric Statistical Methodology for the unrestricted use. It would also clarify ambiguities Design and Analysis of Final Status that have arisen in the past, and would codify Decommissioning Surveys"; NUREG-1506, I practices that have been used for other licensees " Measurement Methods for Radiological Surveys i on a case-by-case basis, in Support of New Decommissioning Criteria"; and NUREG-1507, " Minimum Detectable The NRC is also developing a final rule that Concentrations with 'Iypical Radiation Survey would amend the Commission's regulations on Instruments for Various Contaminants and Field radiological criteria for license termination of Conditions.' nuclear facilities (10 CFR Parts 20,30,40,50,51, 70, and 72). The final rule would amend the Cadmium-Telluride Detector ; regulations to codify the basic principles and 1 radiological criteria that would allow Work is being carried out under a Small Business j decommissioned lands and structures to be Innovative Research (SBIR) contract to develop a released for public use. Regulatory guidance is high-resolution cadmium-telluride detector to be also being developed to assist licensees in used as a field tool for measuring contamination implementing the final rule. Together, these in soils. Use of this detector will decrease activities should benefit the public, the industry, decommissioning costs by allowing the conduct of and the NRC by providing a risk-based real-time surveys in the field, rather than the framework within which decommissioning sampling process currently used. activities and license terminations can be accomplished, T13e framework will ensure adequate protection of public health and safety, Decommissioning Cost Reassessment and will identify residual radioactivity criteria During FY 95, PNL completed NUREG/CR-upon which licensees can confidently develop 5884, " Revised Analyses of Decommissioning for reasonable and responsible decommissioning the Reference Pressurized Water Reactor Power plans. The fm' al rule will be published in FY 96. Station"(Vols.1 and 2), and NUREG/CR-6054,
" Estimating Pressurized Water Reactor In support of the rulemaking, the NRC completed Decommissioning Costs." The companion BWR two NUREG-series reports providing a record of reports, NUREG/ CR-6174, " Revised Analyses of comments received from the public on aspects of Decommissioning for the Reference Boiling Water the decommissioning rule. NUREG/CR-6307, Reactor Power Station" (Vols.1 and 2), and
" Summary of Comments Received at the NUREG/CR-6270, " Estimating Boiling Water l Workshop on Use of a Site-Specific Advisory Reactor Decommissioning Costs," are in the final i Beard (SSAB) to Facilitate Public Participation in stages of review. These final reports are scheduled l Decommissioning Cases," was published in June to be published in FY 96. Based on information i 1995. Draft NUREG/CR-6353, " Comments on already gathered, a proposed rule is being Proposed Rule on Radiological Criteria for developed to modify the financial assurance Decommissioning and Related Documents,"is requirements for decommissioning nuclear currently being prepared for publication. reactors and is scheduled to be issued in FY 96.
I 227 l Safety Issues Related to Permanently laboratory and field experiments. The objective of Shutdown Reactors this program is to develop an understanding of the physical processes that control and determine Brookhaven National Laboratory is evaluating the repository performance in the unsaturated I technical and safety criteria that should remain as volcanic tuff at the Yucca hiountain (Nevada) site ! part of the decommissioning regulations under currently under consideration by the DOE. A l 10 CFR Part 50 for permanently shutdown related goal of the NRC's HLW research is to ! nuclear reactors. Code development is under way provide models, methods, data, and technical to determine radiological consequences for mformation to support the staff's independent various spent fuel pool configurations during judgments as to the appropriateness and permanent shutdown. Financial assurance adequacy of DOE's demonstration of compliance requirements for offsite liability will be of the HLW repository with NRC requirements re-examined based on the technical assessments, specified in 10 CFR Part 60 and with the EPA's Technical criteria needed to support rulemaking HLW standard, incorporated by reference into for permanently shutdown reactors are also being 10 CFR Part 60. The program is divided into developed, and the proposed rulemaking is three parts. First, engineered systems research, scheduled to begin m FY 96, examines issues related to controlled release of l radionuclides, containment of waste, and the i engineering-geology interface in the repository. Second, geologic systems restarch examines issues related to the hydrology, geochemistry, and l HIGH-LEVEL WASTE geology of the repository site. Third, performance assessment research integrates mathematical models from the other research areas into the NRC's HLW performance assessment
'" ng IIIGII-LEVEL WASTE RULEMAKING ad ssfdlilhlei e ds t > as$eIs't e long-term performance of the packages containing On June 22,1995, the Commission issued a final the HLW, the potential for volcanic and seismic rule (60 FR 32430) on emergency planning for events, and flow and transport mechanisms in i independent spent fuel storage facilities (ISFSIs) unsaturated fractured rocks. )
and monitored retrievable storage (MRS) facilities , (10 CFR Part 72). As directed by the Nuclear hiost NRC HLW research is conducted by the ! Waste Policy Act of 1982, the final rule amends Center for Nuclear Waste Regulatory Analyses regulations regarding emergency planning (CNWRA), a division of the Southwest Research Institute m San Antomo, Texas. However, a licensing requirements for ISFSis and hiRS facilities. significant portion of the NRC's HLW research on hydrology is being conducted at the University of Arizona. IIIGII-LEVEL WASTE RESEARCII ENGINEERED SYSTEMS The Nuclear Waste Policy Act of 1982 requires the RESEARCII DOE to dispose of high-level radioactive waste (HLW), which can be spent reactor fuel or the byproduct of reprocessing spent fuel, in a deep Controlled Release geologic repository. The act further requires DOE to apply for a license from the NRC to dispose of The regulation,10 CFR Part 60, specifies a HLW. criterion for the maximum rate of release of radioactive material from the repository's As directed by the Congress in December 1987, engineered barrier system. Research on controlled
- the NRC maintains an active HLW research release is being conducted by CNWRA at the I program involving theoretical study and natural analogue site at Pelia Blanca, hiexico.
228 This site is h>cated in an unsaturated tuff GEOLOGIC SYSTEMS RESEARCII environment similar to that at Yucca Mountain. A uranium ore body is serving as a surrogate for disposed spent fuel, and limits on the expected Ilydrology range of spent fuel behavior in oxidizing chemical environments like those of Yucca Mountain are Because ground water transport is considered to being developed. be the most likely path for radionuclide transport from an HLW facility to the accessible environment, the NRC is actively studying Containment gr und w ter infiltration, recharge, flow, and transport processes. At the experimental Apache Part 60 also specifies a criterion for the minimum bap Tuff site operated by the University of lifetime of IlLW containment within waste An na in Partially saturated fractured rock simil r to that at the Yucca Mountam site, packages placed in the repository. CNWRA is , conducting confirmatory research on the behavior rpsearch continued in FY 95 on testmg hydrologic of waste package materials in the expected site charactenzation methods and scale effects m l repository environment. During FY 95, CNWRA fluid flow and radionuclide transport m l conducted research on stress-corrosion cracking, unsaturated media. Reports from this research repassivation potentials for long-term corrosion of Wcre issued on fingering instabilities, stainless steel, thermal stability of stainless steel, - a r-permeability tests, and observations of water and microbial corrosion. infiltration. In FY 95, the CNWRA examined conceptual and mathematical models of the Death Valley regional Engineering-Geology Interface ground-water system, which includes the Yucca Mountain ground-water system, and began a new Part 60 requires that the repdsitory's engineered project on subregion 0 hydrology. The new project and geologic systems function together, so as not began by examining ua in infiltration at Yucca to compromise repository safety. During FY 95, Mountain. Also, during FY 95, the University of CNWRA conducted two projects related to Arizona and the CNWRA cooperated in coupled processes deriving from the engineered conducting a workshop on flow and transport in system's interaction with its surrounding geologic unsaturated rocks. The NRC, DOE, and Nevada system. One project, on the redistribution of personnel and their contractors participated in liquid water by emplaced HLW, is using the workshop. laboratory-based similitude experiments and theoretical simulations to assess models of this redistribution. Wor!: en this project was Geochem. is try completed in FY 95 with a final report and papers Knowledge and application of the geochemical on the prediction of thermally driven fluid flows conditions at Yucca Mountain are important to at different scales in unsaturated fractured rock. understanding many aspects of repository I In the other project, on rock-mechamcal aspects performance, including waste package corrosion, ! of repository performance, CNWRA researchers radionuclide release and transport, and alteration . issued reports on the effect of mine seismicity on of ground-water flow paths. During FY 95, the ground-water hydrology and research on CNWRA began a new project on non-isothermal l rock joint characteristics. CNWRA also continued
,, geochemistry near emplaced HLW. The project's .
to support NRC participation in early efforts concerned thermodynamic data for l DECOVALEX-an international cooperative uranyl silicate minerals. ) l effort to test the validity of mathematical models ' l M Wennal-hydrological-mechanicalinteractions, A significant problem with addressing the by preparing several chapters in a book entitled geochemistry of radionuclide transport is that the "DECOVALEX-Mathematical and complexity of the chemistry makes calculations
- Experimental Studies of Coupled difficult and time consuming. Simplified Thermo-Hydro-Mechanical Processes in geochemical models have been developed to make Fractured Media." transport calculations tractable, but these models
l 229 1 i I oversimplify the chemistry to the point that even observed active volcanoes in Nicaragua and i so-called bounding calculations may not be truly Russia, and both volcanism research projects were I bounding. For this reason, the NRC initiated a subject to a rigorous peer review. l project at CNWRA to determine whether a model l could be developed that would be sufficiently The CNWRA is also conducting research on ! realistic to yield credible results and yet be tectonic processes in the Basin and Range calculationally tractable. During FY 95, the Province where Yucca Mountain is located. CNWRA tested models of radionuclide sorption During FY 95, the CNWRA issued reports and on certain kinds of clays, and issued reports and papers on faulting and stresses on faulted rock papers on uniform approaches to modeling masses in the Basin and Range. radionuclide sorption. Because there are no operating HLW repositories, the NRC studied several ancient man-made PERFORMANCE ASSESSMENT structures and natural are bodies around the world as archaeological and natural analogues to The NRC will assess the DOE demonstration of IILW disposal. The objective of these studies has compliance with both the NRC's requirements for . been to use the analogues as physical models to HLW disposal given in 10 CFR Part 60 and EPA's l test conceptual and mathematical models of HLW standard.The use of a performance radionuclide release and transport around HLW assessment methodology, independent of tha repositories. During FY 95, CNWRA finished DOE performance assessment methodology, is a i research on an archaeological analogue of HLW key element in NRC's strategy to review that I disposal near Akrotiri, Greece, and continued demonstration of compliance. To support work on a geochemical transport analogue at Pena implementation of that strategy, the NRC is ; l Blanca, Mexico. CNWRA also prepared a paper conducting research at the CNWRA on the 1 on a test of long-term predictive geochemical development of performance assessment tools. transport modeling at the Akrotiri site. Work at The tools are being used in their current state of l the Pelia Blanca site involved hydrogeologic development in the joint NRC-CNWRA HLW i studies and observations of the migration of Iterative Performance Assessment (IPA) effort, j naturally occurring radionuclides. which is providing insights as to the processes and phenomena that may be critical to repository performance. It is anticipated that as the Geology performance assessment tools become more robust, the IPA effort will also assist in setting Two CNWRA projects involve investigating (1) priorities for future HLW research. techniques to estimate the likelihood of the occurrence of volcanoes in the Yucca Mountain In FY 95, the CNWRA issued reports and papers area as an alternative to the method currently on multiphase transport theory, an improved used by the DOE, and (2) possible consequences method for solving the unsaturated zone's flow to HLW disposal of a volcano at Yucca Mountain. equation, an improved method for modeling During FY 95, CNWRA issued two archival radionuclide sorption during liquid-phase papers showing that other methods may suggest a transport, a new method for analyzing the output higher likelihood of a volcano at Yucca Mountain of performance assessments, and a stochastic l than the method currently used by DOE. To gain method for analyzing the effects of volcanism on l' i insight into the consequences of volcanism, the repository performance. The improved method for CNWRA has been examining active volcanoes in modeling radionuclide sorption predicts l l the United States, Mexico, Nicaragua, and Russia channeling of radionuclide transport caused by that may be analogous to possible volcanoes at the occupation of sorption sites by radionuclides Yucca Mountain. During FY 95, the CNWRA that arrived at the sites earlier. t
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CHAPTER 10 1 PROCEEDINGS AND LITIGATION This chapter covers significant activities, construction / operating licenses, amendments to proceedings and decisions of the NRC's Atomic reactor licenses, antitrust issues, enforcement Safety and Licensing Boards (ASLBPs), as well as actions, civil penalties, the licensing of nuclear noteworthy decisions of the Commission in its materials, Program Fraud Civil Remedy Act appellate review of ASLBP decisions. The chapter violations, and special matters the Commission includes a judicial survey of important litigation directs to be heard. The Act also requires that a involving the NRC during the fiscal year. hearing precede every issuance of a construction permit for a nuclear power plant or related facility. IIcarings provide individuals and organizations an opportunity to voice their concerns before an independent tribunal and OFFICE OF THE provide a means for NRC license holders and SECRETARY ff"d P "i'" '" '"" test Commission actions they dispute. The Secretary of the Commission manages the official adjudicatory dockets for the Commission. Adjudicatory hearings at the Nuclear Regulatory These dockets contain the filings of all parties to Commission are conducted by administrative the Commission's licensing and enforcement judges sitting alone or in three-member licensing proceedings; transcripts of the hearings held in boards. The judges are drawn from the Atomic each case; and all orders and decisions issued in Safety and Licensing lloard Panel ("the Panel") such proceedings by the Commission or its created by the Commission in 1962 under the Atomic Safety and Licensing Boards (ASLBs). authority'of Section 191 of the Atomic Energy The Secretary also serves Orders of the Act. The Panel's judges are lawyers or scientists Commission and ASLBs on parties to with expertise in a wide variety of disciplines, proceedings, and certifies docket indexes to the Their appointment to the Panel is based upon courts m agency litigations. recognized experience, achievement and independence in the appointee's field of expertise. The Chief Administrative Judge assigns individual judges to particular hearings where their legal or
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8 KrOMIC SAFETY AND the particular techmcal and legal matters at issue in the proceeding. During fiscal year 1995, the LICENSING BOARDS Panel was compnsed of 34 adnu,nistrative judges (13 full-time and 21 part-time). By profession, they The Atomic Energy Act and the Commission's included 11 lawyers,10 public health and environ-rules provide hearing opportunities for matters mental scientists,13 engineers or physicists, and 3 such as reactor operating licenses and combined medical doctors. (See Appendix 2 for the names
232 -- and disciplines of fiscal year 1995 Panel Rey do so by consolidating admissible members.) contentions whenever possible and fostering a free exchange of views among the parties conducive to possible settlement of disputed issues. RESPONSIBILITIES OF LICENSING 'Ib avoid licensing delays and litigation expenses BOARDS [ r the parties and the government, the Panel's Judges also actively encourage case settlement. The salutary effect of judge involvement in Licensing boards consist of three administrative settlement was demonstrated during 1995 in the judges, comprised of one legal member who settlement of several cases involving the Safety chairs the proceeding and two technical members. Light Corporation of Bloomsburg, Ohio. Three-judge boards are used primarily for Settlement was particularly important because proceedings involving commercial nuclear litigation expenses could have dissipated financial reactors and enforcement actions against resources for decontaminating the Bloomsburg licensees. Materials and reactor operators site. Due in part to the efforts of the Safety Light licensing proceedings are heard by a single licensing boards, settlement was reached prior to administrative judge from the Panel. Where one litigation for each proceeding, allowing $396.000 to judge presides, the Panel assigns a legal or be set aside for site characterization, technical administrative judge as an assistant to decontamination, and decommissioning. Safety the presiding administrative judge. That policy Light Corpomtion, LBP-94-41,40 NRC 340 (1994). assuits the availability of the necessary technical expertise. Paneljudges conduct both formal and informal TECIINOLOGY AND FACILITIES proceedings. Formal proceedings contain the traditional procedures utilized in litigation During the fiscal year, the Panel continued its including pretrial discovery between the parties leadership role in automating the hearing process. and formal trial-type procedures at the hearing. In A particularly important innovation was the informal proceedings (for example, proceedings inclusion, in large complex cases, of significant under 10 C.ER. Part 2, Subpart L), a hearing is documents (such as prefiled testimony and only conducted as to those issues that the hearing transcripts)into an electronic database administrative judge cannot resolve based on the for use by the judges. The system includes parties' written submissions and any additional indexing and companion search and retrieval mformation the administrative judge has deemed capabilities that considerably enhance and relevant. Informal proceedings rely heavily on the expedite document handling and information active involvement of the administrative judge in accessibility. In 1995, Personal Librarian software creating and shaping the record of the proceeding. (PLS) was utilized for the electronic database which is PC LAN based and can be accessed on The Panel employs a number of case management stand-alone personal computers. PLS is more techniques to make the adjudicatory process as efficient and less expensive than previous systems, efficient as possible. Licensing boards and affording potential savings of $30,000 to $40,000 presiding officers frequently structure their annually. hearing schedules into distinct phases, each dealing with discrete groupings of related issues. Also during the year, some Panel members In complex proceedings involving several topics participated in a project to draft electronic data and multiple issues, the Panel may create interchange (EDI) standards for the electronic separate, parallel licensing boards and assign one filing of adjudicatory documents in NRC hearings. or more discrete topics to each board. These These standards, to be developed under the parallel adjudications save time and enable Panel guidance of the American National Standards members' expertise to be more precisely matched Institute's X-12 group, are designed to expedite to the issues to be resolved. Proceedings are also delivery of adjudicatory documents and save made more efficient by the efforts of Panel judges resources by eliminating paper mail systems and to climinate or at least reduce issues for litigation. human handling. They have the potential to be
i 1 233 1 used as filing standards throughout the agency license amendment proceedings, and nuclear and by other administrative agencies. The project materials proceedings. Over the next several years, is expected to be . mpleted in Fiscal Year 1996. the Panel expects an infusion of new types of proceedings involving decommissioning, license In Fiscal Year 1995, the Panel began using its new extension of existing reactors, design certification hearing room in the 'Evo White Flint North of new reactors, and interim storage for high-level building in Rockville, Maryland. The new room, waste. which was designed specifically for conducting agency licensing and enforcement adjudications, Six of the Panel's 1995 proceedings were accommodates approximately 100 members of the particularly large and complex. These included a public with an essentially unobstructed view of construction permit application by Louisiana events within the "well of the court." The room Energy Services (LES) to build a gas centrifuge includes a speaker-phone system that allows uranium enrichment facility in Claiborne, outside parties to participate or " appear" in the Louisiana; a license recapture proceeding fa proceedmgs. Plans for the new hearing room Pacific Gas and Electric Company's Diablo include installation of a local area network that, Canyon Nuclear Reactor; an operating license using notebook computers, will allow the amendment application by Georgia Power presiding officer, counsel, and witnesses to locate Company to transfer operating control of its and view electronic text or imaged versions of Vogtle reactor to another corporate entity; a exhibits, perform word processing or spreadsheet license amendment application by Gulf States functions, and perform legal research using Utilities to transfer ownership and operating outside computer databases, control of its River Bend reactor to a new operator and owner; and an enforcement and license amendment proceeding involving the Sequoyah Fuels nuclear fuels facility in Gore, PERSONNEL CHANGES Oklahoma. The Diablo Canyon proceeding was completed in Deputy Chief Admm. is. trative Judge Robert M. FY 1995, but the other five cases were still Lazo died m office in May 1994. Judge Lazo had ongoing at year's end. In Diablo Canyon, the served the Panel for 22 years as a member, Act,ng i licensee had requested that the operating licenses Chairman, Executive Secretary, and Deputy Chief for the reactors be increased by 13 years for Unit Judge. He held a Ph.D. m Chemistry and a J.D. m 1 and 15 years for Unit 2 in order to " recapture" L3*- the period spent in constructing the plants. I"Cluded in the proceeding was a During the year, the Commission appointed . m ntenance/sedance program contentmn wim James M. Gleason Deputy Chief Administrative 43 distinct subparts and a contention deah,ng with Judge. Judge Gleason first became a part-time the h,eensee,s use of Thermo Lag as a fire barrier. Panel member in 1967 and took a full-time After conductmg full evident,ary i hearm, gs, the appointment in 1992. board held that the licensee's programs were adequate to allow the operating licenses for the Diablo Canyon units to be extended as requested. It did, however, order corrected some problems in PANEL CASELOAD the bcensee s mamtenance and surveillance programs. Pacific Gas and Electric Company l There were a total of 33 proceedings on the (Diablo Canyon Nuclear Power Plant, Units 1 and l Panel's docket during Fiscal Year 1995. Eight 2), LBP-94-35,40 NRC 180 (1994). involved nuclear power plants or related facilities, and 25 involved other Commission licensees. In the Louisiana Energy Service case, both the Fourteen cases were closed and 10 new cases were safety and environmental phases of the hearings docketed. were concluded during the year, and a licensmg board decision is now pending. The litigated The Panel's 1995 caseload primarily involved contentions pertained to emergency preparedness, enforcement actions against licensees, contested decommissioning, financial qualifications, the i
l ( 234 l 1 disposal of nuclear waste, and a novel National question whether a parent corporation is liable for Environmental Policy Act (NEPA) related issue decomm6sioning a contaminated site that is regarding " environmental justice" (i.e., the operated by a wholly-owned subsidiary. placement of potentially hazardous facilities in Evidentiary hearings are scheduled in Fiscal Year areas inhabited by minorities and economically 1996 for both proceedings. Sequoyah Fuels disadvantaged persons). Corporation (Source Materials License No. SUB-1010), October 14,1994 Slip Opinion: LBP-94-5, In Wgt/c, a whistleblower intervenor alleged that 39 NRC 54 (1994): LBP-94-8,39 NRC 116 (1994); individuals who would manage the plant after LBP-94-19,40 NRC 9 (1994). license transfer to a new corporate entity lacked . requisite character and integrity to operate the During Fiscal Year 1995, licensing boards and facility. The whistleblower claimed that in the past presiding officers also ruled on a number of these managers had engaged in a defacto transfer imPortant procedural issues mvolving docketed of facility operators prior to NRC approval and Panel cases. These issues meluded: intentionally misrepresented information to the NRC about the plant's diesel generators. This highly-contested proceeding has included Native American Tribe Participation in approximately 22 weeks of hearm, g during 1995, NRC Proceedings and additional hearing dates are expected in FY Native American Tribes and individuals 1996. representing the interests of these tribes intervened in three different NRC cases during In the River Bend proceeding, the facility's FY 1995. In each case, presiding officers co-owner claimed that a proposed change in recognized that while the tribes had to comply operators at the reactor could jeopardize safety. with the Commission's rules, they nonetheless According to the co-owner, the new operators enjoyed some special participant status and that might be underfunded because of legal actions recognition should be given to their tribal rights, pending against the reactor's present principal culture, and religious heritages. This occurred in owner and operator, Gulf States Utilities, that Hydro Resources, Inc., LBP-95-2,41 NRC 38 could result in the utility's bankruptcy. Gul/ States (1995), where the presiding officer granted a Utilitics Company (River Bend Station, Unit 1), Native American a second chance to cure LBP-94-3, 39 NRC 31 (1994). The prehearing procedural defects in his original petition and in phase of the proceeding has been highly Sequoyah Fuc/s Corporation, Slip Opinion at 2-3 contested, and an evidentiary hearing is expected (October 14,1994), when the presiding officer to begin in Fiscal Year 1996. granted standing to Native Americans based on alleged injury to tribal river beds on the Arkansas The Sequoyah Fuc/s litigation involved a materials River held in trust by the U.S. Government. license amendment proceeding and a related Similarly, in E." cry Fuels Nuclear, Inc., enforcement proceeding regarding a Gore, LBP-94-33,40 NRC 151 (1994), the presiding Oklahoma facility used for processing uranium officer recognized the importance of tribal grave hexafluoride and uranium tetrafluoride. In the sites, historical monuments, and Indian artifacts license amendment proceeding, intervening Indian as subjects of environmental concern. tribes and environmental groups oppose the licensee's curtailment of management and supervision at the site following cessation of Subpart L Hearing Requirements commercial operations. In the enforcement On several occasions during the year, presiding proceeding, these same intervenors contest an officers were asked to add new areas of concern NRC staff order holding Sequoyah Fuels in Subpart L informal proceedings after the time Corporation's parent company, General Atomics, for filing these concerns had expired. The jointly and severally responsible for providing presiding officer in Parks Township rejected these financial assurance for the facility's requests, explaining that late-filed concerns decommissioning. An important issue in both should not be accepted unless the delay is proceedings, as well as for future NRC excusable and granting the untimely request will decommissioning policy, is the jurisdictional not injure or prejudice other parties. He noted
l l 235 i i that in that case no attempt had been made to to intervene "without prior approval" of the explain the delay and none of the late-filed areas board. Georgia Institute of 7echnology (Georgia i of concern were founded upon information Tech Research Reactor), LBP-95-6,41 NRC 281 1 contained in the Hearing File. Babcock and Wilcar (1995). Company (Parks Township, PA), LBP-95-1,41 NRC 1 (1995). Employing similar standards, a l presiding officer in Sequoyah Fuels allowed a Intervenor Witness Requirements petitioner to add late-filed areas of concern because the additional concerns had involved In a proceeding involving the Diablo Canyon matters that arose after the filing of the original reactor, the licensee sought to prevent an petition and the licensee was not prejudiced intervenor from presenting technical arguments in because written presentations were still to be its post hearing findings of fact because the filed. Sequojah Fuels Corporation, June 9,1995 materials relied on by the intervenor had not been Slip Opinion- sponsored by the intervenor's own expert witnesses. In overruling the licensee, the board Another Subpart L issue concerned the held that NRC intervenors may utilize, as part of requirement for parties in their written their case, documents and testimony introduced submissions to presiding officers to submit through other party witnesses. The board organized presentations. In Parks 7bwnship, the reasoned that to do otherwise would abrogate the intervenors had submitted large volumes of right of intervenors to present their cases through i documents without analyzing them or identifying crossgxamination and might limit technical
, l how they related to the case. The presiding officer analysis and conclusions m NRC cases to '
ruled that parties are responsible for compre, statements made by licensee and staff expert hensively organizing and presenting their cases witnesses. The board, in this regard, pointed out and that presiding officers are not duty-bound to the value of opposing points of view and stressed consider disorganized and unstructured that the board had the technical expertise to presentations. He explained that, as an impartial evaluate (and not be prejudiced by) unsponsored judge, he could not construct a controversy on materials presented by the parties. Pacific Gas behalf of the intervenors from these papers "in and Electric Company (Diablo Canyon Nuclear bulk", nor for that matter, could he construct Power Plant, Units 1 and 2), LBP-94-35,40 NRC . their cases for them. Babcock and Wilcox 180 (1994). Company (Parks Township, PA), LBP-95-1,41 NRC 1 (1995). Access by OI and OIG to Confidential IIcaring Materials Organizational Standing In the Sequoyah Fuels case, NRJ staff had claimed that the NRC's Office of Investigations In a license renewal proceeding involving the and Office of the Inspector General should be Georgia Tech University research reactor in allowed unfettered access to confidential Atlanta, Georgia, a group titled Georgians against documents obtained during discovery. A majority Nuclear Energy (GANE) sought intervention on of the board ruled that access to these materials the basis that one of its members worked near the could not be obtained without the board's reactor site. The member had not officially joined permission and that the board would not grant GANE until after GANE had filed its initial permission absent a threat to health and safety. l petition to intervene. As one of the bases for The majority reasoned that courts tradit ioaaPy have not allowed discovery materials to : utilized accepting standing, the licensing board held that a person can establish standing on behalf of an by prosecutors and that protected infonJcn is organization if that person becomes a member generally only released when an agency's strute during the time when an amended petition to or rules specifically allow it to be. No such intervene can still be filed in the proceeding. This authorization existed in this case. Sequoyah Fuels l was proper, the board reasoned, because the Corp. (Gore, Oklahoma Site), LBP-95-5. 41 NRC l Rules of Practice permit amendment of a petition 253 (1995).
236 Cross-Examination quantities of neptunium-237, americium-241, i plutonium-239/240, and depleted uranium. l In the Diablo Canyon proceeding, staff had Scientists at the University's research reactor contended that the intervenor was required to give facility (MURR) are using these materials in staff notice prior to the hearing of all documents research known as the " TRUMP-S Project," the it intended to introduce into evidence at the purpose of which is to develop an inexpensive hearing. Advance notice would have forced the means to reduce the volume of high-level intervenor to reveal to opposing parties the radioactive waste. documents that it intended to utilize for cross-examination purposes at the hearing. The The presiding officer had concluded that the board held that requiring such notice would University's possession and use of the materials at undercut the utility of the cross-examination. As issue were consistent with the public health and I explained by the board, the parties had not been safety, did not harm the common defense and ' ! prejudiced by the lack of notice because they later security, and therefore satisfied the requirements had been offered additional time to examine these of the Atomic Energy Act (AEA). However,in i documents. Pacific Gas and Electric Company order to decrease further the risks associated with (Diablo Canyon Nuclear Power Plant, Units 1 and such possession and use, the presiding officer 2), LBP-94-35,40 NRC 180 (1994). imposed on the University certain additional conditions-mostly related to fire safety. LBP-91-31,34 NRC 29, clarified, LBP-91-34,34 NRC 159 (1991). SIGNIFICANT The university appealed to the Commission the presidmg officer s imposition of these additional COMMISSION DECISIONS conditions. The intervenors appealed the presiding officer's rulings that the license amendments satisfied the requirements of the The Commission exercises its appellate authority AEA; questioned his authority to issue his over adjudications when a party to a Nuclear clarifying order (LBP-91-34); challenged many of Regulatory Commission adjudicatory proceeding his procedural rulings; and appealed his decision is dissatisfied with an Atomic Safety and to exclude their areas of concern regarding waste Licensing Board decision and seeks Commission disposal, nuclear proliferation and review of that decision, or when the Commission decommissioning funding. on its own decides that review of a licensing board decision is necessary. The Commission also in addressing these two appeals, the Commission resolves adjudicatory matters raised for the first for the most part reached the same conclusions as time before the Commission. The Office of the presiding officer, although in some instances it Commission Appellate Adjudication and the followed a different line of reasoning. CLI-95-1, Office of the General Counsel assist the 41 NRC 71 (1995). The Commission affirmed the Commission in its adjudicatory role. Discussed presiding officer's two orders with certain briefly below are the more significant Commission modifications, and thereby approved the decisions in fiscal year 1994. These Commission University's license amendment applicatiori: (but decisions are published in their entirety in the subject to nine new conditions). More specifically,
" Nuclear Regulatory Commission Issuances," the Commission concluded that the presiding l NUREG-0750. officer had jurisdiction to issue his clarifying j order; affirmed his conclusions regarding all The Commission considered appeals from the procedural issues raised on appeal as well as his presiding officer's Initial Decision and decision to exclude three areas of concern; Reconsideration Order in Curators of the conducted an independent analysis and concluded University of Missouri, an informal hearing that the risk of dispersion of radioactive material proceeding that addressed two materials license from the TRUMP-S experiments is acceptably amendment applications filed by the University. small; and both modified and supplemented the Those amendments collectively authorized the fire safety conditions which the presiding officer i
University to possess and use certain specified had imposed upon the University.
237 i Following the issuance of CLI-95-1, the parties In Sequoyah Fuels Cmp., CLI-95-2,41 NRC 179 ! submitted an unprecedented three rounds of (1995), the Commission considered whether a ! petitions for reconsideration. In the first round, licensee that prematurely ceases operations, the University challenged one of the nine without sufficient time to prepare in advance final l conditions imposed by the Commission, and the decommissioning reports and surveys, must renew intervenors challenge numerous technical and its license before continuing limited legal underpinnings of CLI-95-1. decommissioning-oriented activities. Intervenors (the Native Americans for a Clean Environment and the Cherokee Nation) challenged a presiding g The Commission responded in CLI-95-8 by fficer's decision that permitted the Sequoyah l clarifying the wording of one fire-safety condition , Fuels Corporation (SFC) to withdraw a heense but otherwise declining to modify CLi-95-1. CLI-95-08,41 NRC 386 (1995). The University reng appHeatmn, and that termmated the admmistrative proceedmg then in progress on the then sought further reconsideration-this time applicatmn. SFC had notified the Commission m regarding the newly revised condition. The , July 1993 that all production activities had ceased University complained that the Commission's at its Gore, Oklahoma facility, and that any i revised condition did not specify that the contmumg activities would be limited to triggering conditions for a Site Area Emergency
-a potential 1-rem exposure or a "significant contromng yntry into restricted areas and decommissionmg the site. Argumg that it no release possibly approaching EPA PAG levels"-
I nger needed a license renewal, SFC moved ,to should be measured (or estimated) at the site , withdraw its renewal application and to termmate boundary. the proceeding then pending on that application.
- In LBP-93-25,38 NRC 304 (1993), the presiding :
In August 1995, the Commission issued officer granted both requests. I CL1-95-11,42 NRC 47, denying the University's l second petition on the ground that a reference to In challenging the presiding officer's decision, the < the site boundary was already implicit in the intervenors claimed that SFC's withdrawal of its revised " Site Area Emergency" condition. In license renewal application would deprive the addition, the Commission in CLI-95-11 sua company of its regulatory authorization to sponte required the University either (i) to require continue any activities, including non-production evacuation of all persons (except emergency activities, at its facility. The Commission personnel) to a point at least 150 meters from the concluded that 10 C.ER. G 40.42(e), an agency Alpha Lab if an alert is declared as a result of a license extension regulation existing at the time fire involving TRUMP-S materials or (ii) to. (but since superseded), maintained SFC's license provide the NRC staff sufficient information to in effect past its expiration date, as long as the determine that the existing Emergency Plan and licensee limited its actions involving source procedures (or any proposed modifications of the material to previously-approved actions related to Plan and procedures) adequately protect the decommissionmg and to the control of entry mto public within the site boundary in the case of a restricted areas. The Commission rejected as fire involving TRUMP-S materials. unsupported the intervenors' claim that the former section 40.42(e) was inapplicable to licensees whose sites still contained unused raw l In late August, the intervenors sought source material-in SFC's case, bulk yellowcake. reconsideration of CLI-95-11 on three grounds: the order was issued when the Commission lacked The Commission concluded moreover that even if a quorum and was therefore ultra vires; the section 40.42(e) could be read to exclude licensees Commission's acknowledgement in CLI-95-11 that had not yet disposed of unused source that the MURR site is open to the public material, a new provision-which became undermined the Commission's prior effective in August 1994, which superseded the , determination that the TRUMP-S Project is safe; former section 40.42(e), and which will be codified I and the sua sponte conditions were inadequate to at 10 C.F.R. S 40.42(c)-would unambiguously act ! protect the public. That petition for to extend SFC's license for limited decom-reconsideration remains under Commission missioning purposes, without need for a license review. renewal, regardless of the nature of the source
238 - - material onsite. The Commission emphasized. In Georgia Power Co. (Vogtle Electric Generating however, that the agency's license extension Plant, Units 1 and 2), CLI-95-9,41 NRC 404 regulation applicable to materials licensees (1995), the Commission denied a request by the l accords SFC only limited license authority. Georgia Power Company (GPC) to stay Because SFC has withdrawn its license renewal indefinitely inquiries being conducted by the application, SFC is no longer authorized to NRC's Office of Investigations (OI) into matters conduct the principal activities authorized by its that concerned GPC. According to GPC, the license, and SFC would still need to obtain a investigation was interfering with the Atomic license amendment before implementing any Safety and Licensing Board proceeding involving activity-decommissioning-oriented or not- similar issues. GPC further argued that the previously unauthorized urider its license. proceeding should be stayed because the 01 investigation could provide an avenue for the In Georgia Institute of Technology (Georgia Tech intervenor in the licensing board proceeding to Research Reactor, Atlanta, GA), the Georgians obtain affidavits that he had already been denied Against Nuclear Energy (GANE) challenged the in the adjudication and that the parallel application of Georgia Institute of Technology Proceeding interfered with GPC's ability to (Georgia Tech) to renew its license to operate the present its case before the licensing board. Georgia Tech Research Reactor (GTRR). The Atomic Safety and Licensing Board issued an The Commission declined to stay the proceeding mterlocutory order, LBI-95-6,41 NRC 281 because, as a general matter, it is not unusual for (1995), that both granted GANE,s request t an adjudicatory proceeding and an OI mtervene and admitted two of GANE's investigation on the same general subject matter contentions: one challenging the physical security to proceed simultaneously. Although the of the GTRR, particularly durmg the 1996 Commission has been willing to stay parallel proceedings in the past, the Commission declined Olympic Games m Atlanta, and the other alleging problems m the GTRR's management. GANE's to do so here, reasoning that GPC's objections physical security contention centered on an were mostly speculative and did not rise to the alleged , tempting target,, for terrorism posed by level of substantial prejudice required to enjoin an the G,I'RR's fuel. Georgia Tech and the NRC staff ongoing, customany agency activity. , l appealed this order and requested that the The Commission issued two decisions denying Commission stay discovery pending resolution of petitions for review (.f Initial Decisions. In the their appeal. In requesting the stay, Georgia Tech first, Babcock and Nicox Co. (Pennsylvania objected to divulging to GANE the details of Nuclear Service Operations, Parks Township, PA), security arrangements for the Olympic Games. intervenors questioned whether there has been, and under a license renewal whether there will be, In an unpublished order issued on June 9,1995, offsite radiation from Babcock and Wilcox's the Commission temporarily stayed discovery in (B&W) Parks Township facility which threatens order to permit the parties to brief the Com- the health and safety of the nearby population mission on the merits of a stay. Georgia Tech then and threatens radiological contamination of introduced new information to the Commission, nearby residential, agricultural and business indicating Georgia Tech's intention to remove the property. The presiding officer found that fuel from the research reactor, and to replace it radioactivity levels onsite at the Parks Township, only after the conclusion of the Olympics. In PA, facility were consistently below even the most CLI-95-10,42 NRC 1 (1995), the Commission conservatively applied maximum permissible lifted its June 9th temporary stay of discovery, concentrations permitted under the Commission's vacated the Licensing Board's original ruling on regulations and that no reportable releases in the security contention, and remanded that excess of NRC regulatory limits occurred during contention to the Board for reconsideration in the period 1976 through 1993. He also found that light of Georgia Tech's new intentions. In October B&W could be expected to keep exposure rates to 1995, the Commission upheld the Licensing members of the general public at very low levels. Board's rulings on GANE's standing and on its Based on these findings, he concluded that the management contention. CL1-95-12,42 NRC 111 licensee is fully qualified to maintain radioactive (1995). effluent releases within regulatory limits so that
i l 239 , 1 I l the public health and safety and the environment (1995); Louisiana Energy Services, CLI-95-7,41 are not threatened. The presiding officer also NRC 383 (1995); and Georgia Power Co., Docket rejected a number of subsidiary arguments raised Nos. 50-424-OLA-3 & 50-425-OLA-3 [no CLI by the intervenors. LUP-94-12,39 NRC 215 number, unpublished] (9/13/95). ! (1994). I On appeal, the intervenors raised factual, legal and public interest challenges to the presiding officer's order. The Commission found no obvious JUDICIAL REVIEW factual error, novel legal question, or important policy issue requiring appellate review under 10 The more significant litigatirn involving the C.ER. 6 2.786(b)(4). The Commission also Commission during fiscal year 1995 is declined to consider the mtervenors, late-filed and summarized below. unsupported assertion that the latest readings of concentration levels of uranium in ash samples taken from the Kiski Valley Water Pollution ; Control Authority's lagoon exceeded Commission I standards, but indicated that the intervenors were PENDING CASES l free to raise this issue directly with the NRC staff I and to provide supporting documentation. Genera / Atomics x NRC (S.D. Cal.1995)(9th Cir. l CLI-95-4,41 NRC 248 (1995). Appeal Pending) In the second case where the Commission denied General Atomics brought this lawsuit in federal review, Kenneth G. Pierce (Shorewood, IL), the district court in San Diego seeking to halt an Licensing Board had issued an Initial Decision ongoing NRC licensing board proceeding. In that overturning an enforcement order of NRC staff Proceeding the NRC staff seeks to establish the prohibiting Mr. Kenneth G. Pierce from agency's right to hold General Atomics financially involvement in NRC-licensed activities for three accountable for the cleanup of a facility owned by years, with an additional two-year reporting a General Atomics subsidiary, Sequoyah Fuels period. LDP-95-4,41 NRC 203 (1995). Corporation. General Atomics' suit claimed that the NRC has no authority to hold a corporate
.. . parent liable for its subsidiaries' actions. We filed i On appeal, the Commission granted a motion by a motion to dismiss arguing that the district court {
Commonwealth Edison Company (Comed) to file lacked jurisdiction. General Atomics opposed that I an amicus curiac brief, but then rejected the motion and asked that the district court enter a ' arguments of both C,omEd and the NRC staff that
, , preliminary injunction halting further NRC the Licensmg Board s Initial Decision contained proceedings. l " clearly erroneous" factual findings, i.e., that the ;
Board's findings were not " plausible in light,of the In a thorough opinion, the district court agreed record viewed m its entirety." The Commission with our position in full. The court found that concluded that Comed and the staff had instead
, federal district court was not the proper forum for demonstrated only that the record evidence m, th.is General Atomics' suit because the Hobbs Act case could be understood to support a view vests exclusive jurisdiction in the courts of sharply different from that of the Board. Such a
, , appeals over licensing-related suits like General )
showmg was insufficient to tngger discretionary Atomics. The court also ruled that, in the review by the Commission. CL1-95-6,41 NRC alternative, General Atomics was not free to go to l 381 (1995). court to challenge a Licensing Board proceeding in the middle of the proceeding. The court held In addition to the nine decisions summarized General Atomics to the usual doctrine that only above, the Commission also issued orders in final agency decisions are reviewable in court. Georgia Power Co., CLI-94-15,40 NRC 319 (1994): Dr. James E. Bauer, CLI-95-3,41 NRC 245 General Atomics has appealed the case to the l (1995); Georgia Power Co., CLI-95-5,41 NRC 321 Ninth Circuit. l
240 SIGNIFICANT JUDICIAL petitioners' argument as " essentially an attack on DECISIONS the policy choice made by the Congress" to encourage dry cask storage. 42 E 3d 1501,1521 (6th Cir.1995). In reaching this result, the court Citizens Awareness Network, Inc. v. MRC,59 E3d made a number of significant rulings: 284 (1st Cir.1995) First, the court held that "not every proposed Petitioner brought this lawsuit to challenge the action" calls for an adjudicatory hearing. Id. at Commission's rejection of a request for a hearing 1511." [Tjo prevail on a claim that the NRC is on the " component removal project"("CRP") bound to conduct its proceedings in a particular implemented by the Yankee Atomic Electric manner, a petitioner "must point to a statute Company in decommissioning its nuclear power specifically mandating that procedure.. " Id. at reactor at Rowe, Massachusetts. After protracted 1511 (citation omitted). See also id. at 1514 ("the settlement talks proved unsuccessful, the parties right to automatic participation applies only when filed briefs, and the court heard oral argument in the agency acts in a manner provided for in January 1995. On July 20 the court issued a 9189a"). decision setting aside the NRC's rejection of petitioner's hearing request. Second, the court held that "NRC decision-making, and in particular the procedure used by Using strong rhetoric, the court said that the the agency in the course of its decisionmaking, is NRC's " abrupt" shift in decommissioning policy entitled to substantial deference by this court."Id. in 1993 " appears utterly irrational" and is at 1513. Pointing to the NRC's consideration of
" inconsistent" with the Commission's statutoy public comments and to the agency's three-hour obligation to provide " notice and hearing" when public meeting, the court refused "to micro-modifying rules. 59 E3d 284,291-292 (1st Cir, manage NRC decisionmaking" and rejected 1995). The court also found that the NRC staff's " petitioners' assertion that the NRC attempted to various " grants of permission" to Yankee Atomic, shut them out of meaningful participation."Id. at especially the NRC's " approval" of CRP 1513. The court also suggested that an informal expenditures from the decommissioning trust public n,eeting might constitute the " hearing" fund, required an environmental review under required by statute, as "nothing in the applicable NEPA. Id. at 292-293. Finally, after brushing statutes or the relevant precedents compels the aside petitioner's claim under the Fifth NRC to hold a formal adjudicatory hearing."Id.
Amendment's Takins and Due Process Clauses at 1513. as too " bare" and " vague" (Id. at 293-294), the court held the Staff's " approval" of the CRP, as Third, the court rejected the argument that the well as the agency's shift in decommissioning agency's process for licensee safety evaluations policy, amounted to p'nting a license amendment under 10 C.ER. 6 50.59 amounted to "self-and triggered a right . hearing under 6 lo9a of regulation," finding the approach instead-the Atomic Energy .Act (id. at 294-295). " consistent with the NRC's historical method of regulation, which has long allowed licensees to Kelley u Selin,42 E 3d 1501 (6th Cir.1995), cert. make initial determinations about changes to their denied,115 S. Ct. 2611 (1995). facilities and has enabled the agency to retain its In this case a panel of the Sixth Circuit upheld an NRC rule approving the use of a VSC-24 concrete Fourth, the court found no NEPA problems in the cask for storage of spent nuclear fuel. The NRC's " tiering" of its environmental assessment Attorney General of Michigan, two citizens' for the VSC-24 on prior generic environmental l groups in Michigan, and several individuals had reviews and on prior environmental reviews for filed suit based on their concern over the use of individual reactor sites. Id. at 1516. the VSC-24 at the Palisades power reactor. l Finally, the court declined to consider petitioners' The court found the NRC's VSC-24 rule effort to challenge the NRC's 1990 rule setting up consistent with Congress' intent in enacting the a generic rulemaking process for dy cask storage Nuclear Waste Policy Act of 1982 and viewed approval, on the ground "that petitioners should i
241 have asserted such a claim within the 60-day any appeal by the government " frivolous." We period allowed by the Hobbs Act."Id. at 1515, nonetheless obtained authorization from the n.3. Solicitor General for an appeal. The Supreme Court denied certiorari on June 26, The court of appeals reversed the district court 1995.115 S. Ct. 2611 (1995). decision. The court of appeals held, as we had United States x Oncology Services Corp.,60 F. 3d argued, that the "me,re possibility of a new or conunued mvestigation from the NRC,s review of 1015 (3d Cir.1995) the disputed documents provided a sufficient to This is a longstanding subpoena enforcement suit seek judicial enforcement of the NRC subpoena." that a district court in Pennsylvania dismissed as 60 F. 3d 1015,1019 (3d Cir.1995). The court saw moot late in 1994. The subpoena was issued no sigmficance m Ol's admm, istrative " closing" of during an Office of Investigation inquiry into the its investigation in view of the agency's continued activities of a medicallicensee. It sought interest in the documents and its ongoing right documents bearing on the licensee's compliance "to assure that there were no violations of NRC with NRC regulations. regulations." Id. at 1019. l The district court initially took enforcement of the The court therefore remanded the case to the subpoena under advisement, and indicated it district court and advised that court to enforce would review the subpoened materialin camera. the NRC subpoena unless it were found plainly l Ultimately, because OI later " closed" its " irrelevant to any lawful purpose of the NRC."Id. I investigation and issued its report, the court at 1019. The court also stated that the "NRC is I found the enforcement of the subpoena moot, best able to determine what is relevant," and ) despite a pleading filed by the NRC indicating its expressed considerable skepticism about the continued interest in the subpoened materials, district court's in camera review approach. Id. at , The district court indicated that it would regard 1020. 1 l
F L . CHAPTER 11 p, 1 , 1 62 . m.
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u; > MANAGEMENT AND ADMINISTRATIVE SERVICES This chapter deals with internal events and permanent full-time employees, the latter figure activities of the Nuclear Regulatory Commission representing an attrition rate of 5.7 percent. The (NRC). These include initiatives in personnel NRC recruits new employees by conducting management; developments in the agency's recruitment trips to educational institutions, information resources program; activities in the participating in job fairs, and advertising in facilities, Freedom of Information, Local Public various news media (e.g., newspapers, trade , Document Room, security, and contracts journals, the Internet, etc.). Applications received management programs; audits and investigations by the agency are managed and controlled of the Office of the Inspector General, contracts through an automated applicant tracking system. awarded by the Office of Small Business and Civil Rights, and events sponsored by the Federal Women's Program at NRC. AWARDS AND RECOGNITION PERSONNEL MANAGEMENT In FY 95, the NRC continued to recognize and commend employees for excellen: performance. At its Annual Awards Ceremony on April 26, 1995, the NRC presented employees with 2 NRC , 1995 NRC STAFF-YEARS EXPENDED Distinguished Service Awards and 38 hieritorious Service Awards. During FY 95, NRC employees lso received 662 Performance Awards,559 ' During fiscal year 1995 (FY 95), the NRC expended a total of 3167 staff-years in carrying SPecial Act Awards, and 316 High Quality out its mission. This total included permanent Performance Salary Increases. Thirteen NRC full-time staff and part-time staff, temporary emp! yees and eight NRC offices were nominated workers, consultants, and cooperative education f r aw rds sponsored by other Federal agencies and " stay-in-school" employees. and national organizations. Three NRC employees received Presidential Distinguished Executive Rank Awards,11 received Presidential hieritorious Executive Rank Awards,89 received Senior Executive Service (SES) bonuses, and 12 RECRUITMENT , received SES pay-level increases. Eight senior level employees received performance-based cash During the report period, the NRC hired 59 awards, and seven received performance-based permanent full-time employees and lost 175 pay level increases.
244 BENEFITS and propose solutions. The agency has also provided training in methods of dispute Thrift Savings Plan open seasons were conducted resoludon, helping parties in a dispute to work from November 15,1994, to January 31,1995, and 8 rm anung PossMe resobtmns. from May 15,1995, to July 31,1995. A Health Benefits open season was conducted from November 14,1994, to December 12,1994. A IIealth Insurance Fair was conducted on NATIONAL PERFORMANCE November 15,1994, in conjunction with the open REVIEW season. Approximately 300 NRC employees i attended this fair. The Office of Personnel (OP) has been carefully l reviewing the human resources management l A limited open season for Federal Employees' Group Life Insurance was conducted from recommendations in the National Performance l Review (NPR) report, published in September l May 22,1995, to July 21,1995, allowing employees 1993 and the follow-on report, Reinventing Human l who were not currently enrolled to elect " basic Resources Management. While many NPR insurance". The open season was not a regularly recommendations require changes in the law or in scheduled event, but was provided by law to OPM regulations, others may be implemented ; establish "living benefits" for terminally ill without delay. OP has already begun to I employees and retirees. implement some of the suggested changes. Two of the changes that will have an impact on the The Voluntary Leave Transfer Program provides agency are (1) the reduction in staff size and the income protection to employees affected by a ratio of supervisors and managers to employees, medical condition through the voluntary donation and (2) the elimination or reduction of personnel of annual leave by other employees. Twelve directives and processes. While the former change employees qualified as leave recipients during this will affect the nature of supervisory relationships, I reporting period. the latter will provide management with more flexibility and fewer procedural barriers in To achieve its streamlining goals, the agency managing the NRC's human resources. During offered volmtary separation incentive payments FY 95, the ratio of supervisors and managers to (VSIPs) during FY 95. A total of 31 employees employees was decreased from 1:4.8 to 1:5.4 (a took advantage of this provision (14 carly-out decrease of 12.5 percent), and seven Management retirements and 17 optional retirements). During Directives were eliminated. ! FY 95, the NRC conducted eight group ' pre-retirement seminars, and a number of employees attended individual retirement counseling sessions. TRAINING AND DEVELOPMENT During FY 95, OP provided more than 100 LABOR RELATIONS different onsite courses in executive, management, supemsory, and admmistrative skills, as well as computer applications. The NRC also sponsored On October 1,1993, the President signed a wide variety of training and other developmental Executive Order 12871 dealing with Labor- programs conducted at colleges and universities, Management Partnerships in the Federal at other Government agencies, and in the private Government. The order expands the scope of sector. bargaining and calls for a more cooperative and less confrontational relationship between labor A new agency offering this year was a four-part and management. Pursuant to the order, the Planning for Retirement Program: (1) Beginning agency, and the union, have established an Federal Service for employees with less than one
" agency partnership committee," as well as office year of federal service (2) Mid-Career Retirement and regional partnership committees, to foster a Planning Seminar for employees in mid-career cooperative relationship and to identify problems status with ten to fifteen years of Federal service
245 (3) Planning for Retirement Seminar for personnel through contract providers. Seventy-two individuals within five to ten years of retirement percent of employees received training on (4) Retirement Planning Review targeting HIV/ AIDS in the workplace and approximately individuals within six months of retirement. 50 percent of employees received education concerning the EAP and the Drug-Free The computer applications curriculum continued Workplace. In addition, the agency provided to be revised so that employees could learn how information on a variety of substance abuse and to use the latest computer resources available at mental health topics. the NRC, and how to upgrade to a local-area An 11-room health center was constructed and network (LAN) environment based on Microsoft Windows. Examples of new or updated courses opened at the NRC headquarters during FY 95. include Wordperfect, Wordperfect Office for Hummer Associates operates the center, having Windows, Windows, and the Internet and been awarded a 1-year contract with 4 option Mosaic /Netscape. Offices using advanced years. The staff consists of a full-time medical computer technologies received instruction in officer, two full-time nurses, and a medical advanced office system capabilities and receptionist. Services provided include limited application training in UNIX, S-PLUS, and treatment and referral for on-the-job illness or EarthVision. injury; screening for diabetes, glaucoma, high blood pressure, and cancer; mammography The Individualized Learning Center continued to testing; immunizations; and health awareness provide employees with convenient access to programs on topics such as breast cancer, training through the latest in audio / video, prostate cancer, and smoking cessation. computer-based, and multimedia programming. In FY 95, NRC employees had access to more than 300 programs (an increase of 50 programs since FY 94)in project management, communica- INFORMATION tion, management and supervision, computer skills, secretarial skills, and employee assistance. RESOURCES The agency also sponsored a number of programs MANAGEMENT to help employees develop the skills necessary to meet the NRC's future clerical, administrative, technical, and management needs. Developmental programs sponsored bv the agency melude the NRC TECIINICAL LIBRARY Certified Professional Secretaries Program, the Administrative Skills Enhancement Program, the The NRC Technical Library was established in Computer Science Development Program, the 1975 with a unique collection of scientific and Women's Executive Leadership Program, the technical books' from the Library of the Atomic Graduate Fellowship Program, the Intern Energy Commission (AEC). Since its inception, Program, and the Senior Fellowship Program. the Library has continually expanded its collection and services for NRC Headquarters, Regional, and Technical Training Center staff (see the following photograph). The Library maintains over 22,000 books, and 800 journals and EMPLOYEE ASSISTANCE AND newsletters, in addition to the AEC's collection of IIEALTII PROGRAMS , foreign and domestic journals and unclassified researen reports. It also houses collections of During FY 95, the Employee Assistance Program references and International Atomic Energy (EAP) continued to give individual counseling and Agency (IAEA) publications, an archival collec-referral assistance to NRC personnel with such tion of NUREGs, and about 500,000 technical problems as chemical dependency, job stress, research reports dating back to the 1950s. In chronic illness, sexual harassment, and family addition, the Library's collection includes issues. The agency continued to make EAP historical and current industrial codes and services readily accessible to regional and field standards issued by a variety of Government and
246
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resources and services required by the NRC staff. p'7 8-
*g ! *Q The NRC Library continues to study the costs s
A i L. . W 9 and benefits of providing commercialinformation s } - . fg directly to NRC staff via the NRC local-area
% _~W i L. ...,, , network. These considerations include costs to acquire and maintain publications that are core to
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;[ the NRC mission, as contrasted with costs to 6
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' ' %( provide expanded access to a wider range of commercial and nonprofit electronic information.
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,, The broader emphasis on electronically available e
i V information will benefit the agency in many ways, b f a.q u - 'g including increased staff efficiency, reduced I clapsed time between a perceived information need and the provision of that information, and The NRC Technical Library, access to a larger body of knowledge. The NRC Library is positioned to provide these j professional societies, especially those standards information resources today, as well as into the that the NRC approves for incorporation by future. reference in its own regulations. While its primary mission is service to NRC staff, the Library has always made its unique resources accessible to all segments of the public for onsite use and via TIIE WASIIINGTON NATIONAL through to other libraries. RECORDS CENTER Electronic information resources continue to In addition to its own onsite and offsite records expand information available to the staff, either storage areas, the NRC makes use of other online to Internet and commercial resources or Federal facilities. As part of the National mhouse on compact disc / read-only memory Archives and Records Administration (NARA), (CD-ROM). Examples include the American the Federal Government has established a Society of Mechanical Engineers (ASME) Boiler nationwide system of Federal archives and and Pressure Vessel Code, civilian and Defense records centers operated by the NARA Office of research reports and databases, Department of Federal Records Centers. He system consists of Energy and IAEA nuclear-related databases, and 14 Federal records centers throughout the United over 400 other electrome information sources. States, including the Washington National These resources provide access to bibliographic Records Center (WNRC)in Suitland, Maryland, citations, full-text documents, and statistical data. for the economical, interim storage of noncurrent Some services allow onhne requests for Federal agency records pending transfer to the documents or borrowing materials from other National Archives or other disposition authorized libraries nationwide. by law. The WNRC has some 800,000 square feet of storage space and serves several hundred Since the NRC Library opened its new White Federal agencies and bureaus in Maryland, Flint location in June 1994, the number of onsite Virginia, West Virginia, and the Nation's Capital. users has risen. There is also a wider range of users and queries from the NRC offices, as The NRC is presently using the WNRC to store evidenced by dramatic increase in the number of 14,849 cubic feet of records that are no longer online database queries. Collocation with all needed for current business. The WNRC affords headquarters staff has allowed the Library to the NRC considerable economies in both space operate more economically by reducing the need and equipment. Based on an average annual cost to purchase multiple copies of printed media. of $43 per cubic foot for NRC office space and Given the increased costs of books, serials, and $1.62 per cubic foot for WNRC storage space, the electronic information, these efficiencies are WNRC saves taxpayers approximately $614,452.
247 Because the WNRC does not charge the NRC for adjudicatory proceedings and public comments record storage, the actual savings to the agency is on Commission rulemakings, approximately $638,507 per year (see the following photograph). On a daily basis, the DCD staff scans several hundred pieces of agency mail, identifies the documents that should be placed in the NRC's l central document search and retrieval system ) (NUDOCS), and assigns a distribution code to j e- . . . . g__ . 1 each document. The distribution code determines l l h- w-. g . j which persons and organizations internal and l I
- L- -- .w As s external to the NRC will receive copies of a g_ .-- '
- ** document. NRC documents are routinely l
7 t disseminated to selected technical staff within the
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! " agency program offices, the NRC Public . 1 , ) Document Room, national laboratories, and NRC j y contractors. i j . Documents created by NRC staff are also i forwarded to the DCD for placement in the j central document management system and the j appropriate official file location. In FY 95, the i DCD's document flow resulted in the addition of i j more than 90,000 unique records to the central , 9 document database and the distribution of over i l 16 million pages ofinformation to NRC staff and j others. The DCD personnel also support the NRC staff ) l by serving as the point of contact for those who l l - have questions about whether the NRC received a l
- particular submittal (see the following
! photograph). They also assist the NRC staff in
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- National itecords Center is NitC staff member Dave W ***".?
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l A_ .j NRC DOCUMENT CONTROL DESK 3'* ; r s l wdj m&T[ - -([ya L-f i The NRC's Document Control Desk (DCD) is the .
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- members of the public. A separate receipt and
{ control function is performed by the Office of the NitC staff membcr James McKnight reviews a document at l Secretary for legal filings relevant to NRC the NitC Document Control Desk. I i
248 Infected programs can be stopped, moved offline, developing new distribution patterns to fulfill specific program needs. The DCD also identifies or deleted. documents containing sensitive information The NRC staff is also made aware of the potential (proprietary, safeguards, or personal / privacy for virus problems through seminars, training information) that has been improperly marked, classes, articles published in the IRM newsletter, refers those documents to the appropriate contact Computer Security Day activities, and the j for resolution, and prevents the inadvertent development and distribution of a variety of mishandling of sensitive information. awareness materials. Although the NRC has l experienced some incidents of computer virus infection, the extensive awareness program and use of sophisticated detection and eradication NETWORK SOFTWARE UPGRADE tools have made such events increasingly rare and substantially less disruptive. The NRC initiated a program to upgrade the personal computer (PC) workstation software used to access the Agency Upgrade of Technology for Office Systems (AUTOS) office automation network. These upgrades were implemented in a ADMINISTRATIVE two-phased approach. g In the first phase, the Wordperfect Office character based menu system on each of the agency's approximately 3500 PC workstations was replaced with the Microsoft Windows graphical FACILITIES PROGRAM user interface configured for the AUTOS network [see Figure 4.] This interface permits the staff t During fiscal year 1995 (FY 95), several special efficiently aceess and move among current
, , hilities were completed on the plaza level of the applications; it also provides support needed for Two White Flint North (TWFN) complex in graphical appl cations. Rockville, Maryland. First, a newly renovated Health Unit opened in May 1995 in the One During the second phase, DOS versions of the White Flint North building for use of employees Wordperfect e-mail, calendar, and scheduler within the complex. Second, an 8000-square foot, software applications were replaced with 300-seat, full-service cafeteria capable of serving Wordperfect Office for Windows, an integrated approximately 1500 people daily, opened in June Windows-based application. 1995. A fitness center, opened in September 1995, offering a comprehensive wellness and fitness program to accommodate individual needs. Also, in SCPtember 1995, the Maryland Blind Industries COMPUTER VIRUSES opened a " Snack 'N Go" store, specifically to sell sundries such as cards, chips, and sodas.
S,mce the early 1990s, the NRC has taken a very aggressive approach to deal with both real and To enhance the safety and comfort of employees potential computer virus problems. A virus walking from one building to the other, the White incident team was established to quickly respond Flint Limited Partnership, Inc. awarded contracts to reported virtu incidents by eradicating the to design and construct an enclosed link between virus to keep it from spreading. A site license was Two White Flii? and One White Flint. obtained for virus scanning software, which was Construction is expected to be completed by the then installed on all AUTOS servers to scan each end of September 1996. user workstation at logon, and to give users the In March 1995, the NRC's Office of Adminis-capability to scan their own diskettes and hard drives on demand. The software constantly tration (ADM) published its policy concerning monitors file server and workstation activities by public use of the auditorium in Two White Flint checking incoming and outgoing files for viruses. North.
249 PROPERTY MANAGEMENT National Industrial Security Program PROGRAM On October 31,1994, the Deputy Secretary of Defense, acting as the Executive Agent for the National Industrial Security Program (NISP), Executive Order 12821, " Improving Mathematics atid Science Education in Support of the National approved the NISP Operatmg Manual (NISPOM). Education Goals," directs Federal agencies to the This manual establishes Government-wide requirements for protecting classified NSI and maximum extent possible to identify and transfer , restricted data at industrial facilities, meludmg excess education-related equipment to elementary NRC contractors, and to the extent feasible withm, and secondary schools. Under these guidelines, regulatory requirements, NRC licensees and the NRC has established an aggressive program certificate holders. The NRC was one of the four for donating computer equipment to school major agencies involved in this document. The systems nationwide. In FY 95, the NRC donated ther agencies were the Department of Defense, more than 4700 pieces of computer equipment, Department of Energy, and the Central including color monitors, system units, and Intelhgence Agency. printers with an acquisition value of about $5.4 million. ADP Personnel Screening Program During FY 95, the NRC's Division of Security (SEC) implemented Commission policy, which FREEDOM OF INFORMATION ACT provided for the SEC to assume responsibility for PROGRAM operating a Government-sponsored personnel screening program for computer-related contractors. This program will ensure that The NRC Freedom of Information Act (FOIA) contractor employees are eligible for access to the program operates under requirements established agency's sensitive automated data processing by statutory law 5 U.S.C. 552 and Department of (ADP) systems and data through the same type of Justice policy guidance. In FY 9,5, the NRC background investigation used for NRC received 528 initial requests for mformation and employees with comparable access. This screening 22 appeals related to initial decisions. During the program is based on the requirements in Office of same period, the NRC completed 559 initial Management and Budget (OMB) Circular A-130, requests and 22 appeals. " Management of FederalInformation Resources," and Public Law 100-235," Computer Security Act of 1987." In imp lementing this significant new area of SECURITY PROGRAM responsibility, the NRC conducted more than 200 face-to-face security assurance interviews and granted temporary access approval to more than 200 contractor employees. Executive Order 12958 On April 17,1995, President Clicton signed NRC Security Upgrade Efforts Executive Order 12958, " Classified National Security Information" (NSI), which revised the In October 1995, following the Oklahoma City Federal Government's system for protecting NSI bombing in April 1995, the Department of Justice to emphasize declassification of information. The (DoJ) issued a report, entitled " Vulnerability Administration's intent was to strike a balance Assessment of Federal Facilities," which between an open Government accessible to the established guidelines for Federal facilities to people, and the need to protect information. As a follow to enhance security. The NRC quickly result of Executive Order 12958, the NRC is conducted facility security surveys of NRC required to declassify NSI that is 25 years old or Headquarters, all regional offices, the Walnut older. Creek Field Office, and the Technical Training l
250 Center, using the DOJ guidance to formulate implemented in July 1994 as a means of recommendations for upgraded security at each streamlining the acquisition process for purchases facility. On the basis of these surveys, the NRC below $25,000. Most NRC offices now actively has initiated the following efforts: participate in the program, which resulted in a total of 1,707 BankCard transactions valued at
- procurement of x-ray package screening $1,143,451 in FY 95.
equipment for NRC facilities In addition, ADM acquired and tested electronic e procurement of walk-through metal detectors commerce software that will enable the agency to for use at various NRC meetings and gain access to the Gove:nment-wide Federal hearings Acquisition Computer Network (FACNET). This , capability will enable the NRC to electronically i e assessment of exterior lighting at NRC conduct simplified acquisitions. IIcadquarters, with recommendations for mereasing the lesel of lightmg Under pledges by the NRC's Senior Procurement l heutive, ADM participated in Government-
- planning for a security fence along a portion wide efforts to use past performance as a key of the NRC Headquarters' property line contractor selection enterion, to increase the use of performance-based semce contractmg. and to I e increased guard patrols use alternative dispute resolution procedures ;
where appropriate. ADM negotiated e increased control over vehicle access to NRC approximately $100 million in commercial Headquarters' property contracts for FY 95. l CONTRACT MANAGEMENT OFFICE OF THE During FY 95, ADM continued its efforts to INSPECTOR GENERAL streamline the acquisition process consistent with objectives of the National Performance Review. The NRC's Office of the Inspector General (OIG) Under the Agency's Procurement Remvention was established as a statuto:y entity on April 15, Laboratory, established in late 1993, the NRC has 1989, in accordance with the Inspector General
, Act of 1978, as amended in 1988. The OIG's improved procurement lead time and conserved staff effort through a variety of streamhmng primary mission is to assist the agency by imtiatives for contractmg with commercial firms, identifying ways to improve NRC's programs and non-profit organizations, and umversities. operations through the prevention and detection of fraud, waste, and abuse. The 01G Procurement innovations implemented under the ace mplished its mission by performing audits, Procurement Reinvention Laboratory include use special evaluations, mvestigations, event inqumes, of an oral proposal process, establishment of and regulatory reviews.
smaller source evaluation panels, increased The OIG's audit staff conducts performance and delegation of contractual authority, restrictions on financial audits, as well as special evaluations. written proposal content, and waivers of Performance audits focus on NRC's pre-award audits. The NRC also obtained a administrative and programmatic operations. waiver of the requirement to synopsize certain Through financial audits, OIG reviews NRC's technical assistance and research projects in the internal control systems, transaction processing, Commerce Business Daily. These innovations have and financial systems. Special evaluations are helped the NRC to reduce the processing time for conducted by the OIG to examine the each negotiated new procurement by an average implications of NRC's programs that affect of 1 month (compared to previous procurements). national issues. During FY 95, the NRC considerably expanded The OlG's investigative staff conducts tae BankCard program, which the Commission investigations and event inquiries. The staff
251 investigates violations of law or misconduct by procedural requirements that underlie the need NRC employees and contractors and allegations for complete and accurate financial information. of abuse or irregularities in NRC programs and l Toward the goal of helping the agency to improve operations. The event inquity is an investigative product documenting examination of events or its effectiveness, the OIG completed 16 audits of agency actions that do not focus specifically on NRC's programs and operations, analyzed 55 individual misconduct. These reports identify contract audit reports, and made 25 recom-institutional weaknesses that led to or allowed a mendations to NRC management. Also during FY problem to occur. 1995, the OIG received 434 allegations, initiated 82 new investigations, and closed 105 cases. In addition,91 referrals were made to NRC 4 In addit. ion, the OIG shares m. NRC's management. OIG also completed regulatory responsibility to provide adequate assurance for reviews of approximately 165 agency documents, the protection of public health and safety m the and forwarded more than a dozen regulatory commercial use of nuclear materials and in the
, commentaries to the agency with substantive operation of nuclear facilities. The OIG assists comments on their effect on agency programs and 1 the agency by assessing and reporting on NRC's operations.
efforts to ensure that its safety-related programs I are operating effectively. Of particular importance is the NRC's OIG FISCAL YEAR 1995 AUDITS l responsibility for ensuring that individuals who l identify nuclear safety concerns regarding the use The following are representative of the results of of nuclear materials do not suffer adverse job our audit work for the year: actions as a result of reporting these concerns. The OIG continually evaluates NRC's efforts to , combat this type of unlawful discrimination. Chief Financial Officers Act Audit i 4 The OIG also performs reviews of existing and The OIG audit of the NRC's principal statements l proposed legislation and regulations. These for the fiscal year ending September 30,1994, was issued on March 29,1995. This audit included an reviews are performed to provide the NRC with recommendations concerning their impact on the assessment of the agency's internal control l economy and efficiency of its programs and structure and its compliance with laws and operations. regulations. 1 OIG's independent auditor issued an unqualifiA > Some of OIG's accomplishments during FY 1995 opinion on the NRC's principal statements, included updating the publication entitled The IG including the statements of financial position, at the NRC. This revised edition provides, in operations and change in net position, cash flows, addition to information on the structure and and budget to actual for the fiscal year ending function of the NRC OIG, detailed policies and Sepember 30,1994. procedures for initiating and processing audits, investigations, and regulatory commentaries. It The independent auditor's Internal Control also defines the purpose and substance of the Report for FY 1994 contained no material OIG's documentary products and discusses the weaknesses. However, there were two reportable NRC employee's role in the 010 mission. The conditions that had previously been characterized OIG also published another pamphlet, Financial as material weaknesses. These concerned NRC Management at the U.S. Nuclear Regulatory funds spent at the DOE's national laboratories Commission and the Role of the Inspector General. and NRC's fallure to bill licensees for 10 CFR This publication provides an overview of financial Part 170 services in a timely manner. management initiatives at the NRC. In addition, it supplies information about NRC's financial The independent auditor's report on compliance management process and the statutory and with laws and regulations addressed the issue of
252 i l I implementing controls to ensure that licensees are license application schedule, personnel changes at billed correctly for services that directly benefit DOE and NRC, changes in program direction, them in accordance with the requirements in and funding discrepancies. Additional delays have 10 CFR Part 170. ensued from the lack of a clear definition and l agreement on the roles and responsibilities !' between DOE and NRC. As a result, only 6 years Federal Managers' Financial Integrity remain in which to develop and implement an Act Audit LSS before the scheduled repository license application date of 2001. In compliance with the Federal Manager's Financial Integrity Act (FMFIA), the OIG Because NRC is mandated to conduct a timely annually performs a review of the process used by licensing proceeding, the agency needs to take a the NRC to evaluate its internal controls and strong, agressive leadership role. The OIG financial management systems, believes it is crucial that the LSS not impede the license application process. Therefore, OIG In this 1994 review issued on December 19,1994, recommended that NRC work with DOE to OIG found that NRC complied with the develop a formal agreement on key issues, resolve requirements of the FMFIA during FY 1994. The principal internal management requirements, and OlG also found that changes were proposed in develop a contingency plan for resolving NRC's management control program during the important interagency issues that remain past year to anticipate OMB's revised Circular unresolved after a reasonable period. ! A-123. An Executive Committee for Management Controls was established to oversee changes to the program and to provide continuous attention Review of NRC's 2.206 Petition Process to efficiency and effectiveness through The OIG reviewed the NRC's petition process management controls. outlined in Section 2.206 of Part 2 of Title 10 of
. the Code of Federal Regulations (10 CFR 2.206)
The NRC completed corrective action for three to assess the receipt, handling, and tracking of previously reported material weakneses that were
, petitions. OIG also examined NRC's response to included in the 1993 review of the implementation several additional concerns raised by the public.
of FMFIA. These weaknesses related to NRC's Under NRC regulations, anyone may request the computer security program, management of NRC to initiate a proceeding against an NRC Department of Energy projects, and timely billm.g licensee to modify, suspend, or revoke a license, of NRC fees. or to request any other such action as may be appropriate. NRC Needs To Provide Strong In July 1993, the NRC staffinitiated a review of Direction for the Licensing Support the 2.206 petition process to assess its System effectiveness and credibility, as well as its comprehension by the general public. The staff The Nuclear Waste Policy Act of 1982 requires the found a need for improvement in areas that NRC to approve or disapprove the construction of included (1) tracking, handling, and processing a high-level waste repository within 3 to 4 years of petition evaluations; (2) the petitioners receiving a Department of Energy (DOE) involvement in the evaluation process;(3) the construction license application. To help meet this independent review of petitions by NRC staff; and deadline, NRC enacted a negotiated rule requiring (4) NRC's internal procedures for handling the development of an electronic information petitions. As a result, the staff developed several management system called the Licensing Support enhancements to improve the petitioner's System (LSS). The rule requires NRC to operate participation in the process and to foster j and maintain the system that DOE designs and communications between the petitioner and the develops. The OIG reviewed the status of the LSS. NRC. The LSS program has stalled over the past 5 years The 01G found that the staff's enhancements primarily resulting from delays in the DOE should result in an improved process for
253 petitioners.The OIG also noted that NRC and Chapter (MC) 1245. The NRC's reactor and the petitioners appear to interpret the 2.206 materials inspection programs are essential to the process differently. To further enhance the agency's mission of protecting public health and credibility and effectiveness of this process, OlG safety. The NRC established formal training recommended that the NRC initiate actions to requirements to ensure that the inspectors who familiarize the public with the best method of oversee the operating reactors and material bringing their concerns to the Commission and licensees meet minimum knowledge and that provisions be established to enable qualification standards for performing their petitioners to obtain a copy of NRC's Manage- duties. ment Directive 8.11. " Review Process for 10 CFR 2.206 Petitions." MC 1245 provides the training guidelines required for personnel to achieve initial certification as an NRC inspector and maintain knowledge through Review of NRC's Research Program post-qualification training. In 1989, NRC senior Management management conducted the Regulatory Impact Survey (RIS) to obtain industry and regulatory Research management is a joint responsibility staff opinions about the effect of NRC's activities shared by the NRC's Office of Nuclear Regulatory on the safe operation of nuclear power plants and Research (RES) and other NRC program offices, to assist the staff in determining if its regulatory principally the Office of Nuclear Materials Safety programs need modification. From the RIS, the and Safeguards (NMSS) and the Office of Nuclear staff identified three specific regulatory areas Reactor Regulation (NRR). The NRC's former needing improvement, which included the areas of Chairman asked 01G to assess the agency's " training, preparation, and management of overall management and oversight of its research inspectors." Because of the RIS, NRC revised MC program. 1245 in September 1991 to expand its formal The OIG previously recommended that the agency strengthen its research management by The OIG review found that the agency is developing criteria to more accurately measure complying with the initial qualification the performance of research programs and by requirements; however, our audit disclosed that supporting projects and establishing stronger the mandatory post-qualification training internal controls to periodically assess research requirements were not being fully met, and efforts. In response to OIG's report, RES agreed needed clarification. In addition, the agency's to implement several important changes to its database was deemed inadequate for tracking the research management process. training requirements and the inspectors' progression through required training. To improve The OlG review disclosed that the agency has the implementation of MC 1245, OIG recom-improved its research management process, but mended that the NRC's Executive Director for the linkage between the programs in other offices Operations institute steps to ensure that the and RES's support for these programs needed to post-qualification requirements are fully met, be strengthened in order for the agency to develop revise MC 1245 to clearly identify which a more focused institutional approach to research inspectors must meet current post-qualification management. The OIG recommended the use of a requirements, and ensure that the new training conceptual model consisting of " building blocks" and tracking system meets management needs. or essential elements to help accomplish this objective. Inspector 'IYaining Program: Improved Coordination and Communication Review of NRC's Implementation of Needed Inspection Manual Chapter 1245
'IYaining Requirements NRC has established training requirements to ensure that its inspectors meet mmimum The OIG reviewed the implementation of the knowledge and qualification standards. An training requirements in NRC Inspection Manual internal study has showr. the need to improve
254 inspector training, and the agency expanded its OIG FISCAL YEAR 1995 formal training requirements for inspectors. The objective of this review was to assess NRC s INVESTIGATIONS management of inspector training. Inadequate NRC Inspection of an The OIG noted that NRC generally achieved Accident at Sequoyah Fuels overall management objectives for the inspector Corporation training program. However, enhanced OIG conducted an investigation into allegations in coordination and communication of the planning a report generated by Native Americans for a and delivery processes was needed to improve the efficiency of the program. Breakdowns in Clean Environment (NACE) entitled " Silent Sirens." NACE's investigative report focused on a communication have caused inefficient resource usage, including revisions to inspection schedules November 1992 accident that occurred at
, Sequoyah Fuels Corporation (SFC), a uranium at some increased costs. To enhance trammg processing plant in Gore, Oklahoma. The accident cfficiency and effectiveness, OIG recommended l released toxic gases that caused injuries to a !
that the expectations of training coordinators be number of SFC employees and local tree farm I clarified, enrollment confirmation data be given to I workers. OIG investigated 12 of the allegations managers and participants on a more timely contained in NACE's report relating to the basis, and that managers ce held accountable for adequacy of NRC's examination of the accident developing training requirements and supporting and fully substantiated 3 of the allegations. scheduled training. OIG concluded that (1) SFC should have activated offsite sirens to alert the Gore community of the accident, (2) the NRC did not enforce SFC's commitment to seal its control Improvements Needed in NRC's room, and (3) the NRC regional office mistakenly Oversight of Parking Garage maintained an unapproved version of the SFC's Management Services Contingency Plan m Region IV's Incident Response Center. Headquarters parking garage management is one Alleged Falsification of Radiation of several functions NRC has contracted out. The OIG reviewed the agency's oversight of this Safety 'IYaining Records and the NRC's contract and the contractor s bilh,ngs for services Staff Failure to Ade9uatelYReEulate an during the first year of operations. Agreement . The OIG received information that an NRC Agreement State had failed to adequately i Our review disclosed that NRC did not investigate allegations regarding the validity of ' adequately review parkm, g fee collections or radiation safety training certificates issued to four l contractor charges for managing the garage. physicians by the Institute for Nuclear Medical These conditions led to unreported monthly Education (INME). Further, it was alleged that permit sales, inconsistent and uncollected daily the NRC failed to take any action even though the charges, and inaccurate contractor fees. The State did not conduct an adequate inve.stigation. review also disclosed that the contractor failed to ' establish adequate financial controls over parking The OIG investigation substantiated that the garage receipts that resulted in unreported State failed to thoroughly investigate an allegation ' monthly sales of $9,314. OlG recommended that about completion of a radiation safety training N'RC formally review and approve contractor program presented in 1988. The OIG investigation remittances for parking garage collections, update determined that records concerning the 1988 and clarify contract terms, and review prior daily training class were incomplete and interviewees parking logs to determine if additional monies are were unable to remember relevant details. due NRC. Because of the inadequate records and the
255 elapsed time before the allegation was appropriately addressed by the NRC,010 was Alleged NRC Coverup Involving Ward unable to determine whether the trainmg Valley Waste Site consisted of the required 200 hours or whether the physicians satisfactorily completed the trainmg The National Academy of Sciences (NAS) program. requested that the NRC review a dispute over the amount of plutonium projected for disposal at the proposed Low-Level Waste Repository (LLWR) situated at Ward Valley, California. The dispute OIG's investigation also revealed that the NRC was over a plutonium estimate submitted by the knew of the allegation but failed to ensure that the licensee and raised by opponents of the Ward State's investigation fully addressed the issues. As Valley site and a considerably lower estimate a result, the NRC did not detect the major projected by the State regulator. The NRC was shortcomings of the State's investigation, asked to determine which of these estimates was reasonable. In their initial response to NAS, the NRC staff concurred with the regulator's lower estimate. A l Fabrication of Friction Test Data second letter from the NRC advised NAS that the l Submitted to the NRC by an Idaho staff further examined the basis for the plutonium l National Eng.meermg Laboratory waste disposal amount projected by the beensee. 1 According to the staff, the licensee's higher I Employee plutonium estimate was based on an NRC document containing a typographical error. The Office of Nuclear Regulatory Research (RES) The OIG investigated several allegations that the notified the OIG of an allegation that an engmeer workm, g for INEL had submitted falsified friction NRC staff had failed to use NRC official guidance test results. OIG conducted an mvestigation for estimating radioactive waste and had provided which revealed tiiat as part of an NRC research misleading information to NAS. This allegedly ! contract, the engineer submitted to NRC allowed the NRC to assist the licensee in gaining numerous false and fictitious documents, which approval to operate the Ward Valley LLWR site. included friction test results. 01G referred the No evidence was found to indicate that any NRC matter to the United States Attorney for the staff member intentionally distorted information District of Idaho to consider for prosecution. to assist the licensing of the Ward Valley LLWR site. Further, OIG did not find evidence that the On June 14,1995, a seven-count indictment was returned against the former laboratory employee for violations of Title 18, United States Code, Theft of Computer Equipment Section 1001. On August 29,1995, the former employee pleaded guilty to one charge of making The OIG initiated an investigation when it a false statement in U.S. District Court. received a report that numerous computer memory chips were disappearing from individual computers throughout the NRC. During this As a result of the OIG investigation, the investigation, OIG identified an NRC contractor Commission asked the NRC staff to address the employee who stole at least $4,000 worth of NRC broader ramifications of this case, including such computer equipment over an 18-month period. issues as: (1) NRC confidence in the integrity of OIG was able to retrieve most of the stolen other data supplied by the contractor,(2) the property. OIG referred this case to the United NRC's management control process on this and States Attorney's Office for the District of other contractors, and (3) N1C assurance of Maryland. In November 1995, the contractor adequate management controls within the employee pleaded guilty to theft of government contractor organization, property. Since all the missing computer
256 equipment was not accounted for, OIG is continuing to investigate the possible theft of OFFICE OF SMALL other pieces of equipment. BUSINESS AND CIVIL RIGHTS Prosecution of NRC Advisory Committee Member The OIG issued an investigative report about a SMALL AND DISADVANTAGED former member of an NRC Advisory Committee IlUSINESS UTILIZATION in August 1994. In this report, OIG concluded PROGRAM that while with the Committee, the member received reimbursements as a result of 17 false The Small and Disadvantaged Business claims he submitted to the NRC for office rental Utilization Program annually establishes expenses and the cost of secretarial services Procurement preference goals, in conformance provided by his spouse. . with provisions of Public Law 95-507, amending OIG referred this matter to the U.S. Department the Small Business Investment Act of 1957. The of Justice, Public Integrity Section, to consider for following is a summary of estimated and actual contract awards during fiscal year 1995 (FY 95). criminal prosecution. On August 22,1995, the former member pleaded guilty to a one-count e The NRC estimated that $85,000,000 in total Informat,oni (filed in heu of an m, dictment), that prime contracts would be awarded during charged him with theft of public money in FY 95. The actual total for prime contract violation of Title 18, United States Code, Section wards was $91,008,000. 641. The former Advisory Committee member entered his plea in the United States District e The NRC estimated that small business Court for the District of Wyommg. The former prime contract awards would total member was sentenced to serve one-year of $40,000,000, or 47.06 percent of the estimated probation, fined $3,000, and ordered to pay total prime contract awards. The actual restitution of $4,280. achievement for small business prime contract awards was $46,908,000, or 51.54 percent of the actual awarded dollar amount Misuse of American ExIiress reflected above. Government ,fravel Card e The NRC estimated that awards to "8(a) The OIG initiated an investigation of a reactor firms" would total $22,000,000, or 25.88 inspector intern after receiving information from percent of FY 95 prime contracts. Awards to the Division of Accounting and Finance regarding "S(a) firms" actually totalled $28,003,000, or overdue and suspended credit cards. From the 30.77 percent of the actual dollar amount of investigatior, the OIG determined that the intern all prime contract awards, had used the government credit card on numerous occasions for personal use. It was further e The NRC goal for prime contract awards to determined that the employee's charge privileges small, disadvantaged business firms other had been suspended after submitting a check for than "8(a) firms" was $300,000, or 0.35 payment that was returned for insufficient funds. percent. The actual achievement was
$216,000, or 0.24 percent of the actual The NRC directive governing official travel awarded amount reflected above.
restricts use of the charge card to official travel purchases. Further, full payment by employees e The estimate fe NRC prime contract awards must be made upon receipt of the monthly to small business concerns owned and statement. operated by women was $2,000,000, or 2.35 percent. Awards to such firms came to As a result of this abuse, the employee was $872,000 or 0.96 percent of the total dollar terminated. amount of all prime contract awards.
257 1 1 o The NRC's total subcontract goal in FY 95 (PATCOB) positions and assessing their was $3,000,000. The NRC's actual subcontract promotions and career development. dollar awards were $1,983,000. On February 3,1995, the Chairman signed and o The NRC goal for small business subcontract forwarded to the EEOC the NRC's annual awards was $1,950,000, or 65 percent of the Multi-year Affirmative Action Program total estimated subcontract awards. Sub. Accomplishment Report. This report provided contract awards to small businesses actually statistical analyses comparing NRC's employment totalled $ U69,000, or 64 percent of the total accomplishments with census availability data in subcontract dollars awarded. the following major NRC occupations: o The NRC goal for subcontract awards to e GO-343, Management and Program Analysts J small, disadvantaged businesses was $375,000, o GG-801, General Engineers or 12.5 percent of the total estimated subcontract awards. Subcontract awards t e GG-840, Nuclear Engineers small, disadvantaged businesses actually totalled $221,000, or 11.14 percent of the total e GG-1301, General Physicists subcontract dollars awarded. o The NRC goal for the total dollar amount of subcontracts awarded by prime contractors The report also addressed actions taken to to small business concerns owned and achieve the following main affirmative action controlled by women was $100,000, or 3.33 objectives: percent of the total estimated subcontract dollars. Women-owned businesses actually
- Increase the representation of women and received subcontracts in the amount of minorities in professional occupations and in
$24,000, or 1.21 percent of the total supervisory, management, and executive subcontract dollars awarded. positions During FY 95,200 interviews were conducted with . Increase the number of Hispanic employees firms wanting to do business with the NRC, and in all occupations 30 followup meetings were arranged with NRC technical personnel. The staff of The Office Small
- Increase the number of disabled employees Business and Civil Rights (SBCR) also par- hired and retained.
ticipated in five major small business conferences. Most noteworthy among these were the Small The (SBCR) continues to hold meetings once Business Week in May 1995, and the Minority every other month with representatives from the Enterprise Development Week in October 1995. Equal Employment Opportunity (EEO) Advisory Committees and key staff members from the NRC Office of Personnel (OP). These meetings provide an opportunity for the EEO Advisory Committees CIVIL RIGIITS PROGRAl\1 to bring their concerns to tne attention of NRC management before the semiannual EEOC briefings. They also provide an opportunity for On January 19,1995, the Chairman signed and the SBCR and OP to apprise the EEO Advisory forwarded to the Equal Employment Opportunity Committees of management's accomplishments Commission (EEOC) the update to the NRC's regarding the EEO.
. Affirmative Action Program for hiring, placing, and advancing of individuals with disabilities. On April 19,1995, the Commission was briefed This update included an analysis of the NRC concerning the NRC's EEO and Affirmative workforce by grade level, identifying the number Employment Programs, goals, and accomplish-of individuals in professional; administrative; ments. The SBCR and OP jointly coordinated and technical; clerical, other white collar; supervisory; participated this briefing. Each of the following and leadership; and nonsupervisoty blue collar seven EEO Advisory Committees provided input
258 l for review and discussion, as part of the briefing In June 1995, the SBCR sponsored an advanced paper: training course for headquarters and regional EEO counselors at Hunt Valley, Maryland. This , (1) Advisory Committee for African Americans training, conducted by Delany, Siegel, Zorn & Associates, Inc., included the following areas: (2) . Affirmative Action Advisory Committee e common ground and communication-using (3) Asian / Pacific American Advisory Committee listening skills e setting the stage for effective information (4) Federal Women's Program Advisory Committee g therm, g-plannmg and listening (5) Hispanic Employment Program Advisory hfe"res"tg on resolubon-identifying common Committee e getting to resolution-addressing the (6) Joint Labor-Management Equal Employment underlying interests Opportunity Committee; and e positively managing conflict resolution (7) Committee on Age Discrimination. activities Committee Chairs participated in the briefing
- key counseling issues in the.90s-recent along with the Directors of SBCR, OP, the Office developments in Federal sector EEO for Analysis and Evaluation of Operational Data complaint processing (AEOD), and the Office of Administration (ADM); the General Counsel; and the Region I The most effective part of the training was the Administrator. videotaped role-playing exercises. The counselors had an opportunity to interact in roles as The briefing on April 19,1995, focus < d on complainants, supervisors, and counselors, and to accomplishments regarding the follcwing six receive feedback from these exercises. During the, affirmative action objectives: last day of trainmg, there was a panel discussion by James L Milhoan, Deputy Executive Director (1) Enhance opportunities for recruitin,, for Nuclear Reactor Regulation, Regional Hispanic employees in all occupations. Operations and Research, and representatives from OP and OGC.
(2) Enhance opportunities for recruiting women
, During FY 95, the SBCR also showed its and mm, orities in professional positions.
appreciation to the agency's EEO counselors by I
. updating the EEO display posters. The new (3) E,xpand the pool of women and mm.orit.ies
, posters include photos, telephone numbers, and cligible for semor-level supervisory, office abbreviations for the EEO counselors,in management, and executive positions. addition to the agency's EEO policy statement and a summary of the procedures for filing an (4) Enhance opportunities for attracting, EEO complaint. These new posters are displayed developing, and retaining disabled employees. in both the One White Flint North and Two White Flint North buildings. Similar posters provided to (5) Provide a dynamic training and . the regions display photos of regional EEO developmental program, meludm.g rotational counselors in their buildings.
opportunities, to enhance job performance and support affirmative action, training and The SBCR also published a four-page brochure developmental opportunities. outlining the procedures for Processing Complaints of Discrimination at the U.S. Nuclear Regulatory (6) Improve communication about EEO and Commission, NUREG/BR-0212. Copies were affirmative action objectives, heighten made available upon request to all interested awareness and evaluate progress. employees.
l 259 Only 18 of the 116 instances of persons consulting In coordination with OP and SBCR, the NRC's with an EEO counselor in FY 95 resulted in Offic'e of Nuclear Reactor Regulation (NRR), held formal discrimination complaints. Age was the a meeting with the NRR secretaries to discuss dominant basis on which complaints were filed, future career growth and potential career with promotion /non-selection dominating the opportunities for secretaries and administrative issues. staff. The discussion highlighted NRC's cnd NRR's strategic plans, along with information regarding NRC's developmental programs, and a review of the merit staffing process. Subsequently, AFFIRMATIVE ACTION AND a task force was established to address the issues FEDERAL WOMEN'S PROGRAM and develop recommendations to resolve problems. Some of the recommendations of this task force were implemented. During FY 95, SBCR implemented several affirmative action initiatives in support of th? FY 95 highlights included the second session of NRC s EEO objectives. Some of these imtiatives
, EEO Advisory Committee training, conducted by were conducted in conjunction with the vanous Ms. Delores Burton, President, DPI Associates.
EEO Advisory Committees and OP. The All EEO Advisory Committee members in summaries below highlight the activities Headquarters and the regions were invited to completed in FY 95. attend. This session covered the history of EEO, l the roles and responsibilities of advisory com-During November 1995, SBCR sponsored a video presentation entitled " Native Americans: The rmttees, program planmng, the identification of barners, and affirmative employment programs. History of a People " This video was shown twice The coverage of these top,ics was highly rated m during the day on television monitors in both n evaluation by the Committee members. White Flint One and %vo. This video presentation reflected upon the contributions and struggles of Native Americans both during the founding years In conjunction with the Federal Women's Program of the American culture, and also today. A related Advisory Committee (FWPAC), SBCR sponsored poster exhibit depicted Native American the annual Women's History Month Program in employees at the NRC, and provided a historical March 1995. The featured speaker was Dr. Adele summary of the life of Native Americans in North Scheele, nationally renowned author of several i America, books including Skillsfor Success. As a successful l columnist, Dr. Scheele also writes a monthly l In conjunction with Blacks In Government (BIG), column for li'orking II'oman magazine, and has ; SBCR sponsored the annual Black History Month appeared in Newswcck, 7he Reader's Digest, i Program on February 16,1995. The theme was AfcCalls, Vogue, and Afoney magazines. In
" Yesterday's Dream, Today's Reality, and addition, she is a television consultant for NBC's Tomorrow's Hope." The guest speaker was weekend "Today Show," and a noted change-Dr. Freeman A. Hrabowski, President, University management expert. The theme for the program of Maryland, Baltimore County. Dr. Hrabowski's was "Up, Up, and Away With Skills For Success."
message about educating our youth was a (See the following photograph.) Dr. Scheele's reminder and wake-up call for our sense of topics included developing women's self-esteem, 4 responsibility. The program also featured guest finding and keeping jobs, discovering innate choir director, Mr. Mitchell Fleming (nationally abilities, and turning obstacles into opportunities. known for his combined gospel choir), and gospel A wonderful poster exhibit featured during the vocalist, Mr. Steven Hurd. A 6-foot poster exhibit month of March highlighted the contributions of portrayed legendary African-American heroes of women in the arts, science, community action, and the past; names of all AfricanAmerican employees Politics. at the NRC, representing the present; and pictures of African-American babies and youth repre- A poster exhibit for Women's Equality Day was - senting the future. This exhibit was consistent displayed in August 1995. The theme of the with the theme that depicted passing a torch from exhibit was "200 Years of Women in the Military." one generation to the next. This exhibit depicted the role of women in World
260 I Wars I and II, the Korean War, the Vietnam War, In conjunction with the Hispanic Employment i and the Persian Gulf War. Program Advisory Committee (HEPAC), SBCR ! sponsored a poster exhibit in recognition of i National Hispanic Heritage Month. The theme of In conjunction with the Asian / Pacific American this exhibit was " Rising To The Top: Notable Advisory Committee (APAAC), the SBCR Hispanic Americans."This exhibit featured , sponsored the annual As,an/ i Pacific American Hispanic Medal of Honor recipients, as well as Hispanics in business, politics, community action, l Heritage Month Program on May 18,1995. The and science. l theme of the program was " Equality,
- Empowerment, Excellence." Dr. Narain G.
The Affirmative Action and Federal V* omen's l Hingorani, President of Hingorani Power Program Manager offered career development i Electronics, was the keynote speaker. Ms. Ginny counseling and assistance to employees upon l Gong, National President of the Organization of request. These sessions, conducted for i Chinese Americans (OCA), was the guest approximately 1 hour with each employee,
- speaker. Dr. Hingorani shared the story of his consisted of a background review of experiences j career, from its start as an engineer in India to his and skills, identification of goals and objectives, current position as president of Hingorani Power an outline of a strategy to achieve goals and
! Electronics. Ms. Gong described some of her objectives, and the identification of potential ! efforts through the organization to help ensure contacts needed. The Individual Development i ! and secure the rights of Chinese and other Asian Plan and the Mentoring Program were also l i Americans. reviewed in these sessions. l i t l l l i ,e - av 9 ,e j l kQipg p t 6 L[ f l l w,g
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QghWN-f I Y'f/p 3 b 1.XR l . l l (Qj d7 D : ' f - I } hhf&$W .. t i From left to right is the speaker for the Annual Women's IIistory Month Program, Dr. Adele Scheele, Commissioner de Planque, Commissioner Rogers, and Vandy 1. Miller, Director, Ofice of Small ilusiness and Civil Rights. i I (
261 Once every other month, the Affirmative Action Strategies,Inc. Both speakers have worked j and Federal Women's Program Manager, holds extensively in managing diversity in the private working meetings with the EEO Advisory and public sectors. Agencies represented at this Committee Chairpersons. During these meetings, meeting included the Office of the Secretary of the chairpersons strategize on ways to address Defense, Farm Credit Administration, issues of concern to their various constituencies. Department of Energy, Comptroller of the Currency, Defense Mapping Agency, International Two workshops on image and communication Trade Commission, U.S. Air Force, and were also presented during FY 95 by Ms. Lisa Montgomery County, Maryland, Government. Valenti, a trainer with National Seminars. The topics included Image (how others see you), self-esteem (how you see yourself), communication In conjunction with several EEO Advisory (words chosen and spoken, posture, and facial Committees, SBCR sponsored " brown-bag" and eye expressions), expression (between men workshops focusing on enhancing the career i and women and among cultures), self-promotion awareness and career development of employees. (projection), and networking (contacts and FWPAC sponsored the workshop, which featured mentoring). For each workshop, two sessions were as its guest presenter, Ms. Marilyn White, a held, one in the morning and one in the afternoon. career specialist. Ms. White's topics included Employees in all occupations and at all grade " Women in the Workplace, Visioning for the levels through SES attended the sessions. Future, and Metaforces Within." Employees rated Employees rated the sessions very highly, and this workshop highly, and requested a return visit requested a repeat performance, from Ms. White. The Asian / Pacific American Advisory Committee also sponsored a , On June 22,1995, SBCR sponsored a joint " brown-bag" awareness session with Asian meeting on managing diversity with other Federal American employees to inform them of the agencies and county government staff. Guest committee's role and their relationship with the l presenters for this meeting included SBCR to share career development information, Mr. Cleveland Clark, President AILC, Inc., and and to discuss specific concerns that affect Asian Dr. Vanessa Weaver, President of Alignment American employees. l l 1 l l l
263 Appendix 1 NRC Organization (As of December 31,1995) COMMISSIONERS
, Shirley Ann Jackson, Chairman Kenneth C. Rogers The Commission Staff OfDee of Commission Appellate Adjudication John E Cordes, Jr., Acting Director Office of Congressional Affairs, Dennis K. Rathbun, Director i General Counsel. Karen D. Cyr i Office of the Inspector General,Ixo J. Norton, Acting Inspector General 1 a
Office of International Programs, Carlton R. Stoiber, Director Office of Public Affairs, William M. Beecher, Director Secretary of the Commission, John C. Hoyle ' I Other Offices Advisory Committee on Nuclear Waste, Dr. Paul W. Pomeroy, Chairman i Advisory Committee on Reactor Safeguards, Dr. Thomas S. Kress, Chairman Atomic Safety & Licensing Board Panel, B. Paul Cotter, Jr., Chief Administrative Judge EXECUTIVE DIRECTOR FOR OPERATIONS Executive Director for Operations, James M. Taylor Deputy Executive Director for Nuclear Reactor Regulation, , Regional Operations and Research, James LMilhoan ] Deputy Executive Director for Nuclear Materials Safety, Safeguards and Operations Support, Hugh L Thompson, Jr. Assistant for Operations, James L Blaha Program Offices Office of Nuclear Material Safety and Safeguards, Carl J. Paperiello, Director j Office of Nuclear Reactor Regulation, William T. Russell, Director . Office of Nuclear Regulatory Research, David L Morrison, Director Staff Offices Office of Administration, Patricia G. Norry, Director Office for Analysis and Evaluation of Operahnal Data, Edward L Jordan, Director Office of the Controller, Ronald M. Jeroggins, Controller Office of Eniorcement, James Liebtemar, Oi,ector Office of Information Resources Management, Genud E Cranford, Director Office of Investigations, Guy P. Caputo, Director Office of Personnel, Paul E. Bird, Director Office of Small Business and Civil Rights Vandy L Miller, Director Office of State Programs, Richard L Bangart, Director Regional Offices Region I-Philadelphia, Pa., Thomas T. Martin, Regional Administrator Region II-Atlanta, Oa., Stewart D. Ebneter, Regional Administrator Region HI-Chicago,111., Ilubert J. Miller, Regional Administrator Region IV-Dallas, Tex.,Ixonard Joe Callan, Regional Administrator
264 The NRC is responsible for licensing and recommending research, standards and policy regulating nuclear facilities and materials and for options necessary for their successful operation. conducting research in support of the licensing and regulatory process, as mandated by the Atomic Energy Act of 1954, as amended; the The Office of Nuclear Reactor Regulation ensures Energy Reorganization Act of 1974, as amended; the public health and safety through licensing and the Nuclear Nonproliferation Act of 1978; and in inspection activities at all nuclear power reactor accordance with the National Environmental facilities in the United States. The Office oversees Policy Act of 1969, as amended, and other all aspects of licensing and inspection of applicable statutes. These responsibilities include manufacturing, production, and utilization protecting public health and safety, protecting the facilities (except for facilities reprocessing fuel environment, protecting and safeguarding and performing isotopic fuel enrichment), and . materials and plants in the interest of national receipt, possession and ownership of source, l security, and assuring conformity with antitrust byproduct, and special nuclear material used or laws. Agency functions are performed through Produced at facilities licensed under 10 CFR Part standards setting and rulemaking; technical 50. The Office develops policy and inspection l reviews and studies; conduct of public hearings; guidance for programs assigned to the Regional issuance of authorizations, permits and licenses; Offices, and assesses the effectiveness and inspection, investigation and enforcement; uniformity of the Regions' implementation of evaluation of operating experience; and those programs. The Office identifies and takes confirmatory research. The Commission itself is action in coordination with the Regional Offices composed of five members, appointed by the regarding conditions and licensee performance at President and confirmed by the Senate, one of such facilities that may adversely affect public whom is designated by the President as health and safety, the environment, or the Chairman. The Chairman is the principal safeguarding of nuclear facilities, and assesses executive officer and the official spokesman of the and recommends or takes action in response to Commission. incidents or accidents. The Office is responsible for licensing issues and regulatory policy The Executive Director for Operations is the conceyning reactor operators, including the initial chief operational, financial, and administrative licensmg cxaminat,on i and requalification officer of the Commission and is authorized and a min tions; emergency preparedness, meludm, g directed to discharge such licensing, regulatory, Participation m emergency drills with Federal, financial, and administrative functions of the State, and k) cal agencies; radiation protection; security and safeguards at such facilities, NRC and to take actions as are necessary for , day-to-day operations of the agency. The "icluding fitness for duty; and the mspection of Executive Director for Operations (EDO) nuclear supplier facilities. The Office also c nducts techm, cal review, certification, and supervises and coordinates policy development , licensing of advanced nuclear reactor facilities ; and operational activities of EDO staff and program offices, and implements Commission and renews current power reactor operatmg licenses. policy directives pertaining to these offices. i The Office of Nuclear Material Safety and The Office of Nuclear Regulatory Research plans, l Safeguards licenses, inspects, and regulates recommends, and implements programs of facilities and materials associated with processing, nuclear regulatory research, standards transporting and handling nuclear materials, as development, and resolution of safety issues for well as the disposing of nuclear waste, and nuclear power plants and other facilities regulated regulating uranium recovery facilities. The Office by the NRC. It develops and promulgates all also regulates related faciluy decommissioning. technical regulations; coordinates research l The safeguards staff of the Office reviews and activities within and outside the NRC, including ! assesses protection against potential threats, appointment of staff to committees and l thefts and sabotage for licensed facilities, working conferences; and coordinates national volunteer l closely with other NRC offices in coordinating standards efforts including appointment of staff l safety and safeguards programs and in to committees.
265 The Regional Offices are under the supervision activities with Congress; plans and develops and direction of the Executive Director for NRC's legislative program; and monitors Operations and carry out NRC regulatory legislative proposals, bills and hearings. programs originating in the various Headquarters Offices. The Office of the General Counsel directs matters I of law and legal policy, providing opinions, advice, and assistance to the Commission and staff with I respect to all activities of the agency. l The Commission Staff The Office of the Inspector General conducts investigations and audits directed principally The Office of the Secretary of the Commission toward improving program management, ensuring (SECY) provides executive management services the integrity of the NRC's regulatory programs, to support the Commission by planning and and preventing and identifying fraud, waste, and scheduling Commission business, preparing the abuse in the agency's programs and operations. Commission's meeting agenda, and codifying Commission decisions in memoranda directing The Office of International Programs provides staff action. The SECY also processes and advice and assistance to the Chairman, i controls Commission correspondence, maintains Commission and NRC staff on international ! the Commission's official records as well as issues. The office formulates and recommends I adjudicatory and rulemaking dockets, directs and policies concerning nuclear exports and imports, j administers the NRC Historical Program, and international safeguards, international physical operates and manages the NRC Public Document security, non-proliferation matters, and Room and its electronic systems for providing international cooperation and assistance in access to NRC's publicly available documents. In nuclear safety and radiation protection. The office i addition, SECY functions as the Federal Advisory plans, develops and implements programs to carry Committee Management Officer. out policies established in these areas; plans, develops and manages international nuclear safety The Office of Commission Appellate Adjudication information exchange programs; and coordinates is responsible for monitoring cases pending before international research agreements. The office presiding officers; for providing the Commission obtains, evaluates and uses pertinent information with an analysis of any adjudicatory matter from other NRC and U.S. Government offices in requiring a Commission decision (e.g., petitions processing nuclear expc rt and import license for review of Initial Licensing Board decisions, applications; establishes and maintains working certified questions, interlocutory referrals, stay relationships with individual countries and requests), including available options; for the international nuclear organizations, as well as drafting of any necessary decisions, pursuant to other U.S. Government agencies; and assures that the Commission's guidance, after presentation of all international activities carried out by the l options; and for consulting with the Office of the Commission and staff are properly coordinated General Counsel in identifying options to be internally and Government-wide and are , presented to the Commission and in drafting the consistent with NRC and U.S. policies. final decision to be presented to the Commission. The Office of Public Affairs develops policies, The Office of Congressional Affairs provides programs and procedures for informing the public advice and assistance to the Chairman, of NRC activities; prepares, clears and Commission and NRC staff on all NRC relations disseminates information to the public and the with Congress and views of Congress toward NRC news media concerning NRC polbies, programs policies, plans and activities; maintains liaison and activities; keeps NRC management informed with Congressional committees and members of on media coverage of activities ofinterest to the Congress on matters of interest to the NRC; agency; plans, directs and coordinates the serves as primary contact for all NRC activities of public information staffs located at communications with Congress, reviewing and the Regional Offices; conducts a cooperative concurring in all outgoing correspondence to program with the schools; and carries out members of Congress; coordinates NRC internal assigned activities in the area of consumer affairs.
266 The OfHee of the Secretary of the Commission experience and feeds back the lessons of that provides executive management services to experience to NRC licensing, standards and support the Commission and to implement inspections activities. The Office is also Commission decisions; advises and assists the responsible for the NRC incident response Commission and staff on planning, scheduling, program and the technical training center, as well and conducting Commission business; prepares as the tracking of licensee performance indicators. the Commission's meeting agenda; codifies Commission decisions in memoranda directing The OfGce of the Controller develops and staff action, monitors staff compliance of pending maintains NRC's financial management actions, and tracks commitments through the Programs, including policies, procedures and automated Commission tracking system; manages standards of accounting and financial the staff paper and COMSECY systems; initiates systems-such as payroll and travel and monitors the status of office automation expenses-and preparation of the agency budget. initiatives into the Commission's administrative system; processes and controls Commission The OfHce of Enforcement develops policies and correspondence; mamtams the Commission's programs for the enforcement of NRC official records and acts as Freedom of requirements, manages major enforcement Information coordinator for Commission records; actions, and assesses the effectiveness and maintams the official adjudicatory and uniformity of regional enforcement actions. rulemaking dockets of the Commission and serves The Office of Information Resources Commission and Atomic Safety and Licensmg Management develops, provides and administers Board issuances in all adjudicatory matters and information resources of the agency in the areas public proceedings; directs and administers the of computer, telecommunications, and NRC llistorical Program; operates and manages information services. These include data base the NRC Public Document Room and its management, ofUce automation, computer Bibliographic Retrieval System for providing hardware and software, systems development, access to members of the public and designated computer operations, timesharing, nation-wide foreign countries to NRC's publicly available telecommunications equipment, the Customer documents; and functions as the Federal Advisory Support Center, user training, document control Committee Management Officer. and management, central files, records management and services, library, graphics, and other information support services to the agency. Support Staff The Office of Investigations conducts, supervises and assures quality control ofinvestigations of nsees, applicants, contractors or vendors, The Office of Administration directs the agency's meluding the mvestigation of all allegations of programs for c,ontracting and procurement; document semces, meludmg preparation and wrongdoing by other than NRC employees and publication of the NRC's annual report to the contractors. The Office develops policy,
, , procedures and standards for these activities.
President and the Congress, and admmistration of the Freedom ofInformation Act and Privacy Act
, The OfHce of Personnel plans and implements requests; transportation services; secunty of NRC policies, programs, and services to provide personnel, facilities and information; for the effective organization, recruitment, administration of local public document rooms; placement, utilization and development of the rulemaking support; management of space and agency's human resources.
equipment, and other administrative services. The Ofnce of Small Business and Civil Rights develops and implements the NRC's program in The Office for Analysis and Evaluation of accordance with the Small Business Act, as Operational Data provides agency coordination amended, ensuring that appropriate consideration for the collection, storage, and retrieval of is given to small business firms, including operational data associated with licensed women-owned and minority businesses. The activities, analyzes and evaluates such operational Office develops and recommends NRC policy
l 1 I 267 1 providing for equal employment opportunity and persona services contracts. The committee I develops, monitors and evaluates the affirmative considers medical questions referred to it by the action program to ensure compliance with the NRC staff and gives expert opinions on the policy. The Office also serves as contact with local medical uses of radioisotopes. The Committee and national public and private organizations with also advises the NRC staff, as required, on related interests, and administers the Historically matters of policy. Black Colleges and Universities Program. The Advisory Committee on Reactor Safeguards 1 l The Office of State Programs is responsible for is a statutory committee established to advise the establishing and maintaining good community Commission on safety aspects of proposed and relations between the NRC, the States, local existing nuclear facilities and on the adequacy of governments, other Federal agencies, and Indian proposed reactor safety standards and performing Tribe organizations; serves as primary contact for such other duties as the Commission may request. policy matters between the NRC and these The committee conducts a continuing study of groups; keeps the agency apprised of activities of reactor safety research and submits an annual these groups, as they may affect NRC, and report to the Congress. The committee also conveys to NRC management the groups' views on administers a fellowship program. NRC policies, plans and activities; coordinates , liaison with other Federal Agencies through the The Atomic Safety and Licensing Board Panelis i Federal Liaison Program; administers the State a panel of lawyers and others with expertise in Agreements Program; provides training and various technical fields from which three-member technical assistance to Agreement States; Licensing Boards are drawn to conduct public integrates Federal regulatory activities with the hearings and make such intermediate or final States; and maintains cooperative and liaison decisions as the Commission may authorize in activities with the States. proceedings to grant, amend, suspend or revoke NRC licenses.
. The Licensing Support System Advisory Review NRC Adv.isory Comm.ttees i and L.icensmg Panel, established in 1989 advises the NRC's Panels Licensing Support System Administrator (LSSA) and the Department of Energy (DOE) on selected The Advisory Committee on Nuclear Waste was aspects of the design, development and operation of the support system.
established Commission inby thetoNuclear 1988 Regulatory advise the Com ' mission on nuclear waste disposal facilities, as directed by The Nuclear Safety Research Review Committee, the Commission. established in 1988 on the recommendation of the National Research Council, provides advice to the Advisory Committee on Medical Uses of Isotopes, Director of the Office of Nuclear Regulatory established in 1958, is composed of qualified Research regarding the direction of NRC's physicians and scientists, employed under yearly nuclear safety research programs. l l
l 269 J Appendix 2 Atomic Safety and Licensing Board Panel Full-Time Panel Members: JUDGE IVAN W. SMITH, Legal, U.S. Nuclear i Regulatory Commission, Rockville, Maryland ) CHIEF ADMINISTRATIVE JUDGE B. PAUL . Part-Time Panel Members: COTTER, JR., Legal, U.S. Nuclear Regulatory Commission, Rockville, Maryland JUDGE GEORGE C. ANDERSON, Marine DEPUTY CHIEF ADMINISTRATIVE Biologist (retired), University of Washington, JUDGE-EXECUTIVE JAMES P. GLEASON, Seattle, Washington Legal, U.S. Nuclear Regulatory Commission, JUDGE A. DIXON CALLIHAN, Physicist Rockville, Maryland (retired), Union Carbide Corporation, Davidson, North Carolina DEPUTY CHIEF ADMINISTRATIVE JUDGE JAMES H. CARPENTER, JUDGE-(TECHNICAL) FREDERICK J. SHON, Engineer, U.S. Nuclear Regulatory Environmental Scientist (retired), U.S. Nuclear Commission, Rockville, Maryland Regulatory Commission, Sunset Beach, North "I "* JUDGE CHARLES BECHHOEFER, Legal, U.S. JUDGE THOMAS S. ELLEMAN, Nuclear Nuclear Regulatory Commission, Rockville, Engineer, North Carolina State University, Maryland Raleigh, North Carolina JUDGE PETER B. BLOCH, Legal, U.S. Nuclear JUDGE GEORGE A. FERGUSON, Nuclear Regulatory Comm,ssion, i Rockville, Maryland Physicist (retired), Howard University, Shady JUDGE G. PAUL BOLLWERK, III, Legal, U.S. Side, Maryland Nuclear Regulato'ry Commission, Rockville, JUDGE HARRY FOREMAN, Medical Doctor Maryland (retired), University of Minnesota, St. Paul, JUDGE RICHARD E COLE, Environmental Minnesota l Scientist, U.S. Nuclear Regulatory Commission, JUDGE RICHARD E FOSTER, Environmental i Rockville, Maryland Scientist, Sunriver, Oregon l JUDGE CHARLES N. KELBER, Physicist, U.S. JUDGE DAVID L. HETRICK, Nuclear Engineer, Nuclear Regulatory Commission, Rockville, Un versity of Arizona, Tucson, Arizona Maryland JUDGE ERNEST E. HILL, Nuclear Engineer, Hill Associates, Danville' California JUDGE JERRY R. KLINE, Environmental Scientist, U.S. Nuclear Regulatory Commission, JUDGE FRANK E HOOPER, Marine Biologist Rockville, Maryland (retired), University of Michigan, Ann Arbor, Michigan JUDGE PETER S. LAM, Nuclear Engineer, U.S.
, JUDGE ELIZABETH B. JOHNSON, Nuclear Nuclear Regulatory Commission, Rockville, Engineer, Oak RiNe National Laboratory, Oak Maryland Ridge, Tennessa JUDGE THOMAS S. MOORE, Legal, U.S. JUDGE JAMES C. LAMB, III, Environmental Nuclear Regulatory Commission, Rockville, Engineer, George Washington University, . Maryland Charlottesville, Virginia JUDGE THOMAS D. MURPHY, Health JUDGE EMMETH A. LUEBKE, Physicist Physicist, U.S. Nuclear Regulatory Commission, (retired). U.S. Nuclear Regulatory Commission, Rockville, Maryland Chevy Chase, Maryland
270 JUDGE KENNETH A. McCOLLOM, Electrical JUDGE LESTER S. RUBENSTEIN, Nuclear Engineer (retired), Oklahoma State University, Engineer (retired), U.S. Nuclear Regulatory Stillwater, Oklahoma Commission, Oro Valley, Arizona JUDGE MARSHALL E. MILLER, Legal JUDGE DAVID R. SCHINK, Oceanographer, (retired), U.S. Nuclear Regulatory Commission, Texas A&M University, College Stat,on, i Texas Daytona Beach, Florida JUDGE GEORGE E TIDEY, Medical Doctor, University of Texas, Houston, Texas JUDGE PETER A. MORRIS, Physicist (retired), U.S. Nuclear Regulatory Commission, Potomac, Maryland ProfessionalStaff i JUDGE RICHARD R. PARIZEK, Geologist, LEE S. DEWEY, Chief Counsel, Legal Support , Pennsylvania State University, University Park, Staff, U.S. Nuclear Regulatory Comm,ssion, i j Pennsylvania Rockville, Maryland JACK G. WHETSTINE, Director, Program JUDGE HARRY REIN, Medical Doctor, Support and Analysis Staff, U.S. Nuclear ' i Longwood, Florida Regulatory Commission, Rockville, Maryland 1
271 Appendix 3 NRC Federal Advisory Committees Advisory Committee on Reactor MR. WILLIAM J. LINDBLAD, retired President, Portland General Electric, Portland, Oregon. Safeguards DR. DON W. MILLER, Professor and Chair, Nuclear Engineering, Department of Mechanical The Advisory Committee on Reactor Safeguards Engineering, The Ohio State University, (ACRS)is a statutory committee established to Columbus, Ohio. advise the Commission on the safety aspects of DR. DANA A. POWERS, Manager, Nuclear proposed and existmg nuclear facilit,es, i as well as Facilities Safety Department, Sandia National the adequacy of proposed reactor safety Laboratories, Albuquerque, New Mexico. standards, and to perform such other duties as the Conimission may request. DR. WILLIAM J. SHACK, Associate Director, Energy Technology Division, Argonne National Laboratory, Argonne, Illinois, As of January 1995, the ACRS included the following members: DR. CHARLES J. WYLIE, retired Chief Engineer, Electrical Division, Duke Power CHAIRMAN: DR. THOMAS S. KRESS, retired Head of Applied Systems Technology Section, Advisory Committee on Nuclear Waste ) Oak Ridge National Laboratory, Oak Ridge, Tennessee. The Advisory Committee on Nuclear Waste VICE-CHAIRMAN: DR. ROBERT L. SEALE, (ACNW) reports to and advises the NRC on nuclear waste disposal facilities. The committee Professor of Nuclear and Energy Engineering, of concern Department of Nuclear and Energy Engineering, examines and reports on th,ose areas,ts design referred to it by the Commission or i Co!!ege of Engineering and Mines, University of Arizona, Theson, Arizona. representatives, and undertakes other studies and activities related to those issues as directed by the . DR. GEORGE APOSTOLAKIS, Professor, Commission. l l Nuclear Engineering Department, Massachusetts Institute of Technology, As of January 1995, the ACNW included the J Cambridge, Massachusetts. following members: MR. JAMES C. CARROLL, retired Manager, CHAIRMAN: DR. PAUL W. POMEROY, Nuclear Operations Support Department, President, Rondout Associates Incorporated, Pacific Gas & Electric, San Francisco, Stone Ridge, New York. California. VICE-CHAIRMAN: DR. B. JOHN GARRICK, i i DR. IVAN CATTON, Professor, Department of President, PLG, Inc., Newport Beach, ) Mechanical, Aerospace, and Nuclear California. Engineering, School of Engineering and Applied DR. MARTIN J. STEINDLER, Senior Science, University of California, Los Angeles, Chemist / Senior Technical Advisor, Chemical California. Technology Division, Argonne National DR. MARIO FONTANA, Research Professor, Laboratory, Argonne, Illinois. Nuclear Engineering Department, University of DR. WILLIAM J. HINZE, Professor, Department Tennessee; and Retired from Oak Ridge of Earth and Atmospheric Sciences, Purdue National Laboratory, Oak Ridge, Tennessee, University, West Lafayette, Indiana.
272 Advisory Committee on Medical Uses Licensing Support System Advisory of Isotopes Review Panel The Advisory Committee on Medical Uses of The Licensing Support System Advisory Review Isotopes (ACMUI) was established in July 1958. Panel (LSSARP) was established in 1989 to advise Comprised of qualified physicians and scie'itists, the NRC and the Department of Energy (DOE) on selected aspects of the design, development, the ACMUI considers medical questions .eferred and operation of the Licensing Support System, to it by NRC staff, gives expert opinions on the medical uses of radioisotopes, and advises NRC currently administered by the Deputy Director of the NRC Office ofInformation Resources staff on matters of policy. Members are appointed Management. The panel consists of to serve 2-year terms, and are employed under representatives of the NRC, DOE, the State of yearly personal services contracts. Members may Nevada, the local government of Nye County serve a maximum of three terms. (Nevada), the National Congress of American Indians, a coalition of nuclear industry As of October 31,1995, the ACMUI included the organizations, and other Federal agencies having following appointed members: experience with large electronic document management systems. CHAIRMAN: DR. BARRY A. SIEGEL, Nuclear As of Nmemkr 12,1W, Ge qARP induM Medicine Physician, Mallinckrodt Institute of the following appointed members. Radie!cgy, St. Louis, Missouri. CHAIRMAN: MR. JOHN C. HOYLE, U.S. DR. DANIEL S. BERM NN, Cedar Sinai Medical Nuclear Regulatory Commission. Center, Los Angeb, California. MS. CLAUDIA NEWBURY, U.S. Department of MS. JUDITH I. BROWN, Patient Rights and Energy. Care Advocate, Washington, D.C. MR. KIRK BALCOM, State of Nevada. DR. DANIEL E FLYNN, Holy Family Hospital MR. STEVE FRISHMAN, State of Nevada. and Medical Center, Methuen, Massachusetts. MR. HARRY W. SWAINSTON, State of Nevada. MR. JOHN GRAHAM, Hospital Administrator, MR. ROBERT I. HOLDEN, Director, National St. Mary's Hospital, Livonia, Michigan. Congress of American Indians. DR. A. ERIC JONES, U.S. Food and Drug MS. LORETTA METOXEN, National Congress Administration, Rockville, Maryland. f American Indians.
. . MR. DENNIS BECHTEL, Clark County, Nevada.
DR. WIL B. NELP, University of Washington, University Hospital, Seattle, Washington. MS. EVE CULVERWELL, Commissioner, Lincoln City Board of Commissioners, MR. ROBERT M. QUILLIN, Agreement States Lincoln City, Nevada. Program, State of Colorado, Denver, Colorado. MR. WAYNE CAMERON, White Pine County, DR. JUDITH ANNE STITI, University of Nevada. Wisconsin Hospital, Department of Human MR. PETE J. GOICHOECHEA, Eureka County Oncology, Madison, Wisconsin. Commission, Nevada. l MR DENNIS P. SWANSON, University of MR. ARLO K. FUNK, Commissioner, Mineral l Pittsburgh School of Pharmacy, Pittsburgh, County Commission, Nevada. Pennsylvania. MR. FIDEL GOMEZ, Commissioner, Mineral DR. LOUIS K. WAGNER, Medical County Commission, Nevada. Physicist-Nuclear Medicine, University of Texas MR. VERNON POE, Director, Office of Nuclear Medical School, Houston, Texas. Projects, Mineral County, Nevada.
273 MR. JAMES REGAN, Churchill County DESIGNATED FEDERAL OFFICER: Commission, Nevada. DR. JOSE LUIS M. CORTEZ, Senior Research MS. HEATHER ESTES, Lander County Program Coordinator, Office of Nuclear Commission, Nevada. Regulatory Research, U.S. Nuclear Regulatory MS. JUANITA D. HOFFMAN, Esmeralda County, Nevada. DR. S. GEORGE BANKOFF, Chemical Engineering Department, Northwestern MR. BRAD METTAM, Inyo County, Nevada. MR. LES BRADSHAW, Nye County, Nevada. PROFESSOR ANTHONY J. BARATTA, MR. MALACHY MURPHY, Nye County, Nuclear Engineering Department, College of Nevada. Engineering, The Pennsylvania State University. MR. JAY SILBERG, Shaw, Pittman, Potts &
'Ibwbridge, Washington, D.C. PROFESSOR MICHAEL W. GOLAY, Professor, Nuclear Engineering. Department of Nuclear MR. CHRISTOPHER J. HENKEL, Nuclear Engmeermg, Massachusetts Institute of Energy Institute, Washington, D.C. Technology.
MR. DAVID COPENHAFER, U.S. Securities and Exchange Commission. PROFESSOR ROBERT D. HATCHER, JR., Distinguished Professor of Engineering, Department of Geological Sciences, University Nuclear Safety Research Review of Tennessee. Ccmmittee PROFESSOR CHARLES MAYO, Associate Professor of Nuclear Engineering, Department The Nuclear Safety Research Review Committee of Nuclear Engineering, North Carolina State (NSRRC) was established in 1988 on the University, recommendation of the National Research Council. The committee provides advice to the MR. FRED J. MOLZ, Westinghouse Professor, Director of the Office of Nuclear Regulatory Environmental Systems Engineering Research regarding the direction of the NRC's Department, Clemson Research Park. nuclear safety research programs. MR. JOHN TAYLOR, Retired, Electric Power As of November 1995, the NSRRC included the Research Institute. following members: DR. ROBERT VOGEL, Retired, Electric Power CHAIRMAN: DR. E. THOMAS BOULETTE, Senior Vice President, Nuclear, Pilgrim Station, DR. SUMIO YUKAWA, Retired, General Boston Edison Company. Electric Company.
275 l l Appendix 4 i i Local Public Document Rooms Copies of most documents originating in the NRC or submitted to it for review are placed in the Commission's Public Document Room (PDR)in the Gelman Building,2120 L Street, N.W., Washington, D.C., for public inspection. Other PDRs are maintained in the five Regional Offices (for documents related to nuclear material licenses, i.e., most byproduct and source material licenses). In addition, documents related to licensing proceedings or licensed operation of specific facilities are made available in local PDRs established in the vicinity of a proposed or existing nuclear facility. The locations of the local PDRs, the names of the persons to contact, and the names of the facilities for which documents are retained are listed below. (N.B., Updated listings of local PDRs may be obtained by writing to Freedom of Information Act/ local Public Document Room Branch, Division of Freedom of Information and Publications Services, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001.) ALABAMA CALIFORNIA o Ms. Susan Todd,IIcad Librarian e Mr. James Kirkendall Athens Public Ubrary Documents Ubrarian 405 E. South Street Humboldt County Library Athens, Ala.35611 1313 3rd Street Browns Ferry nuclear plant Eureka, Cal. 95501 Browns Ferry low-level waste llumboldt Bay nuclear plant ! storage o Ms. Bettye Forbus, Director l e Ms. Judy llorn, Department Ilead Ilouston Love Memorial LJbrary 212 W. Burdeshaw Street University of California l P.O. Box 1369 Main Ubrary Dothan, Ala. 36302 P.O. Box 19557 l ' Irvine, Cal. 92713 Joseph M. Farley nuclear plant San Onofre nuclear plant o Ms. Peggy McCutchen Scottsboro Public Library 1002 South Broad Street e Mr. Gerald Ward Scottsboro, Ala.35768 Central Library Bellefonte nuclear plant 8281 Street Sacramento, Cal. 95814 l Rancho Seco nuclear plant l ARIZONA e Ms. Johanna Brown, licad o Ms. Linda Rissecuw, Librarian 11 Government Documents and Maps Dept. Business and Science Division Robert E. Kennedy Library l Phoenix Public Ubrary California IVytechnic State University ! 1221 N. Central San Luis Obis [n, Cal. 93407 l Phoenix, Ariz. 85004 Diablo Canyou nuclear plant Palo Verde nuclear plant ARKANSAS COLORADO o Ms.Francesllager
'Ibmlinson ljbrary e Ms. Sue Safarik Arkansas Tech. University Weld Ubrary District, Lincoln Park Branch RusselMlle, Ark.72801 919 7th Street Arkansas Nuclear One nuclear Greeley, Colo. 80631 plant Fort St. Vrain nuclear plant
i 276 i CONNECTICUT ILLINOIS
- Ms. Marcella Kenney, Reference Librarian
- Mrs. Yvonne Jaycox, Assistant Librarian Russell Ubrary Byron Public Library District 123 Broad Street Middletown, Conn. 06457 109 N. Franklin Street Byron, Ill. 61010 lladdam Neck nuclear plant Byron nuclear plant e Mrs. Malinda Evans o Dr. Paul S. Price Vespasian Warner Public Library Director of learning Resources 310 N. Quincy Street Three Rivers Community Clinton, Ill. 61727 Technical College Clinton nuclear plant Thames Valley Campus 574 N,ew Imdon Turnpike Norwich, Conn. 06360 e Mrs. nancy Gillfillian Millstone nuc! car plant Library Director Dixon Public Ubrary 221IIennepin Avenue Dixon, Ill. 61021 Ouad Cities nuclear plant FLORIDA Sheffield low-level waste burial site O Ms. Joyce Shiver e Ms. Deborah Steffes Coastal Region Library Reference Assistant 8619 W. Crystal Street Morris Area Public Ubrary District Crystal River, Fla. 34428 604 Liberty Street Crystal River nuclear nt Morris, Ill. 60450 Dresden nuclear plant Morris spent fuel storage facility o Ms. Unda Smith, Librarian Charles S. Miley Ixarning Resources
- Ms. Evelyn Moyle, Documents Librarian Ctr. Jacobs Memorial Library Indian River Community College Illinois Valley Community Co!!cge 3209 South Virginia Avenue Rural Route 1 Ft. Pierce, Fla. 34981 Oglesby, Ill. 61348 St. Lucie '..uclear plant LaSalle nuclear plant e Ms. Mary Jane Anderson, Library Director o Ms. Sherry Mosley, Librarian Government Documents Collection Library Documents Department Wilmington Public Library Florida International University 201 South Kankakee Street University Park Wilmington, Ill. 60481 Miami, Fla. 33199 Braidwood nuclear plant
'Ihrkey Point nuclear plant e Ms. Tiffany Severns Reference Librarian Waukegan Public Library GEORGIA 128 N. County Street Waukegan, RI. 60085 Zion nuclect plant o Ms. Alice Coleman Appling County Public Ubrary 301 City IIall Drive Baxley, Ga. 31513 Edwin I. liatch nuc! car plant IOWA o Mrs. Gwen Jackson, librarian e Ms. Stephanic Schulte Burke County Ubrary Cedar Rapids Public Ubrary 412 4th Street 5001st Street, S.E.
Waynesboro, Ga. 30830 Cedar Rapids, Ia. 52401 Alvin W. Vogtle nuclear plant Duane Arnold nucicar plant
277 KANSAS MAINE I e Ms. Janet Morgan, Director ) o Ms. Nannette Martin, Documents Librarian Wiscasset Public Library ) Government Documents Dept. High Street ! William Allen White Library P.O. Box 367 Emporia State University Wiscasset, Me. 04578 1200 Commercial Street Maine Yankee nuclear plant Emporia, Kans. 66801 Wolf Creek Generating Station MARYLAND o Mr. Paul Arn.go NRC-LPDR Documents Collection Washburn University School of Law e Ms. Mildred Ward, Ubrary Assistant Topeka, Kans. 66621 Calvert County Public Library Wolf Creek Generating Station 30 Duke Street P.O. Box 405 Prince Frederick, Md. 20678 Calvert Cliffs nuclear plant KENTUCKY MASSACIIUSETTS o Ms. Vonnie Shelton e Mrs. Carolletson Ubrary/I. earning Resource Center Paducah Public Library Greenfield Lommunity College 555 Washington Street One College Drive Paducah, Ky. 42003 Greenfield, Mass. 01301 l Paducah Gaseous Diffusion Plant Yankee Rowe nuclear plant l e Ms. Grace E. Karbott, Reference Librariaa l Plymouth Public Library 132 South Street Mym uth, Mass. 023@ LOUISIANA Pilgnm nuclear plant o Ms. Rebecca Lubas Government Documents Department MICIIIGAN Troy H. Middleton Library louisiana State University e Mr. David O'Brien, Reference Librarian 11aton Rouge, La. 70803 River Bend nuclear plant Van Wylen Library Hope College 137 E.12th Street 11 Iland, Mich. 49423 o Mr. Kenneth E. Owen, Head Palisades nuclear plant Louisiana Collection Earl K. Iong Library University of New Orleans e Mr. Eric Grandstaff, Library Director Lakefront Drive North Central Michigan College New Orleans, La. 70148 1515 Howard Street Waterford nuclear plant Petoskey, Mich. 49770 Big Rock Point nuclear plant o Ms. Pam Suggs, Director e Mr. Carl Katafiasz Claiborne Parish Library Govanment Documents Librarian 901 Edgewood Drive Monroe County Library System Homer,IA 71040 3700 S. Custer Rd. 14uisiana Energy Services, Inc., Monroe, Mich. 48161 facility Enrico Fermi nuclear plant
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279 o Ms. Carolyn Johnson,llead OIIIO Business and Social Science Division Rochester Public Library e Ms. Sally Ondrejko 115 South Avenue Guernsey County District Public Library Rochester, N.Y.14610 800 Steubemille Ave. Robert Emmet Ginna nuclear Cambridge, Ohio 43725 plant Shieldalloy Metallurgical Corp. e Ms. Donnie Potelicki, Director o Mr. Erich Mayer, Assistant Librarian Garfield lieights Branch Library Buffalo and Erie County Public Library 5409 'Ibrney Road Lafayette Square Garfield lieights, Ohio 44125 Buffalo, N.Y.14203 Chemetron Corporation West Valley Demonstration Project e Ms. Ann Freed, Reference Librarian Perry Public Library 3753 Main Street o Ms. Laurie Strick Perry, Ohio 44081 Shoreham-Wading River Public Library Perry nuclear plant Route 25 A Shoreham, N.Y.11786 e Ms. Ann IIackman Shoreham nuclear plant Portsmouth Public Ubrary 1220 Gallia Street Portsmouth, Ohio 45662 o Mr. Oliver E Swift Portsmouth Gaseous Diffusion Municipal Reference Librarian Plant White Plains Public Ubrary 100 Martine Avenue e Mrs. Julia Baldwin, Documents Librarian White Plains, N.Y.10601 Government Documents Collection Indian Point nuclear plant William Carlson Library University of Toledo 2801 West Bancroft Avenue Toledo, Ohio 43606 Davis-Besse nuclear plant NORTII CAROLINA OKLAIIOMA e Ms. OJ. Grosclaude Stanley Tubbs Memorial Library o Ms. Dawn llubbs, Documents Librarian 101 E. Cherokee St. J. Murrey Atkins Library Sallisaw, Okla. 74955 University of North Carolina at Kerr-McGee Sequoyah Charlotte-UNCC Station Charlotte, N.C. 28223 William B. McGuire nuclear plant OREGON e Mr. Michael Bowman o Ms. Marsha Proctor,Ilead Branford E Millar Library Adult Services Portland State University Cameron Village Regional Ubrary P.O. Box 1151 1930 Clark Avenue 10th and liarrison Raleigh, N.C. 27605 Portland, Ore. 97207 Shearon liarris nuclear plant Trojan nuclear plant o Mrs. Eileen Brown PENNSYLVANIA Reference / Documents Ubrarian William Madison Randall Ubrary e Ms. Mary Ann Paulin, Reference Librarian University of North Carolina at Wilmington B.E Jones Memorial Library 601 S. College Road 663 Franklin Avenue Wilmington, N.C. 28/413-3297 Aliquippa, Pa.15001 Brunswick steam electric plant Beaver Valley nuclear plant
280 ~ o Ms. Judy Weinrauch SOUTH CAROLINA Government Publications Section State Library of Pennsylvania Walnut Street and Commonwealth Avenue e Mrs. Margaret ca.non, Director llox 1601 Barnwell County Public Library Harrisburg, Pa.17105 Hagood Avenue Three Mile Island nuclear plant Barnwell, S.C. 29812 Peach Ik>ttom nuclear plant Barnwell reprocessing plant Barnwell low-level waste burial site o Ms. VickiIIeld e Ms. Liz Watford, Librarian Apollo Memorialljbrary Nuclear Information Depository 219 N. Pennsylvania Avenue Ilartsville Memorial Library Apollo, Pa.15613 147 W. College Ave. Babcock & Wilcox Parks Township Hartsville, S.C. 29550 and B&W Apollo H.B. Robinson nuclear plant Robinson independent spent fuel o Mr. Scott Elmer E Pottstown Public Ubrary 500 liigh Street e Mrs. Mary Mallaney Pottstown. Ia.19464 Assistant Reference Librarian Limerick nuclear plant York County Library 138 East Black Street P.O. Ikn 10032 o Mr. Ernest Fuller Rock 11i11, S.C. 29730 NRC Materials Aide Catawba nuclear plant Saxton Community Library 911 Church Street e Ms. Joyce Lusk, Jbrarian Saxton, Pa.16678 Oconee County Library Saxton nuclear experimental facility 501 W. South Broad Street Walhalla, S.C. 29691 o Ms. Sandra Schimmel Reference Librarian Reference Department * . .s. Sarah D. McMaster, Director Osterhout Free Library Fairfield County library 71 South Franklin Street 300 Washington Street Wilkes-Barre, Pa.18701 Winnsboro, S.C. 29180 Susquehanna steam electric station Virgil C. Summer nuclear plant Susquehanna low-level waste storage TENNESSEE e Ms. Patricia Maroney, Ilead RilODE ISLAND Business, Science and Technology Dept. Chattanooga-Hamilton County library 1001 Broad Street o Ms. Ann Crawford, Director Chattanooga, Tenn. 37402 Cross Mill Public Library Sequoyah nuclear plant 4417 Old Post Road Watts Bar nuclear plant Charlestown, R.I. 02813 TVA Sequoyah low-level waste Wood River Junction' storage
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281 TEXAS WASIIINGTON o Mr. Thomas Lindsey Library-Documents
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283 Appendix 5 Regulations and Amendments-Fiscal Year 1995 REGULATIONS AND qualified nuclear pharmacists revise licensee reporting AMENDMENTS PUT INTO and authorized physicians to use requirements regarding the EFFECT-FY 1995 greater discretion in preparing notification of events related to radioactive drugs containing radiation safety at independent NRC Library; Address byproduct material for medical spent fuel storage installations Change-Parts 34,35,50,73, use. This action is in response to and a monitored retrievable end 110 a petition for rulemaking storage installation. This submitted by the American amendment, effective January 13, College of Nuclear Physicians 1995, is necessary to ensure that On October 5,1994 (59 FR and the Society of Nuclear sigmficant occurrences at these 506S8), the NRC published an h,eensed facilities are promptly amendment to regulations that Medicme (PRM-35-9). reported to the NRC. Such timely reference the availability of Statement of Organization and reportmg enables the materials that the Director of the , GeneralInformation; Agency Commission to evaluate whether Federal Register has approved Consolidation and Minor the licensee has taken j for incorporation by reference. , This amendment, effective Amendments-Part I appropriate actions to protect 1 immediately, gives the current the public health and safe,ty, and whether prompt NRC action is location where this materialis On December 12,1994 (59 FR necessary to address generic available for inspection. 63881), the NRC published an safety concerns. amendment to its regulations, Chinge in Organizational Title effective immediately, reflecting List of Approved Spent Fuel and Telephone Numbers-Part 2 the completion of the NRC Storage Casks: Addition-Part headquarters consolidation 72 On November 25,1994 (59 FR effort. Specifically, this 1 60551), the NRC published an consolidation included merger of On December 22,1994 (59 FR { the Office of Admimstration and amendment to its regulations, 56898), the NRC published an effective immediately, to provide the Office of Consolidation, and amendment to its regulations to the current title of the reconstitution of the Office of the add the standardized NUHOMS organization within the NRC and Licensmg Support System horizontal modular system to the the current telephone numbers Admimstrator as an list of approved spent fuel for a prospective petitioner to orgamzational unit of the Office storage casks. This amendment, contact before filing a petition of Information Resources effective January 23,1995, allows for rulemakmg. Management. The consolidat. ion the holders of power reactor i also transferred respons,bility for operating licenses to store spent Preparation, Transfer for admmistering the b,eensmg fuelin this approved cask under Ccmmercial Distribution, and support system from the a general license. Use of Byproduct Material for- Commission staff to the Office of M: dical Use-Parts 30,32, and the Executive Director for Preparation, Transfer for 35 Operations. Commercial Distribution, and Use of Byproduct Material for On December 2,1994 (59 FR Notification of Events-Part 72 Medical Use-Part 32 61767), the NRC published an amendment to its regulations. On December 14,1994 (59 FR On January 4,1995 (60 FR effective January 1,1995. This 64283), the NRC published an 322), the NRC published an amendment dlows properly amendment to its regulations to amendment to its regulations to
284 clarify the final rule, effective April 13,1995, to reduce would qualify as a small entity,
" Preparation, Transfer for the reporting requirements adjusts the receipts based Commercial Distribution, and currently imposed on licensees of standard to account for the Use of Byproduct Material for water-cooled nuclear power effects of inflation since 1985, Medical Use," published in the reactors, research and test and eliminates the separate $1 Fedeml Register on December 2, reactors, and nuclear materials. million size standard for private 1994. This amendment, effective practice physicians, applying the January 1,1995, reduces the Low-Level Waste Shipment revised receipts-based size requirements for the information Manifest Information and standard of $5 million to this to be included on labels for Reporting-Parts 20 and 61 class of licensees.
radioactive drugs to be transferred for commercial On March 27,1995 (60 FR Standards for hotecdon Against distribution. , Radiati n; Clarification-Part 20 15649), the NRC published an amendment to its regulations to Requirement To Report improve the quality and Transfers of Devices to Generally uniformity of information On A Eril 25* 1995 (60 FR Licensed Persons-Part 32 ) PuMed an contained in manifests that are , required to' control transfers of meng' ment to hs regulations, On January 19,1995 (60 FR low level waste (LLW) ultimately 3735), the NRC published an , mtended for disposal at a land nsta e equ e nts to retain amendment to its regulations disposal facility. Tlus records generated under the govermng the reportmg of device amendment, effective March 1, previously existing provisions of transfers to generally licensed 1998, will establish a set of forms Part 20 that were inadvertently persons. Tius amendment, to allow LLW to be tracked from omitted in a Federal Register effective December 31,1994, its ongin, and to serve as a notice published in the Fedemi reheves m, itial distributors of the Register on December 22,1993 national uniform low-level devices from the requirement to , , radioactive waste manifest to (58 FR 67657). provide copies of the transfer meet NRC, Department of Interim Storage of Spent Fuel in reports to each appropriate NRC Transportation, and State and regional office. an Independent Spent Fuel Compact information Storage Installation at a Reactor requirements. This amendment Frequency of Medical Site; Site Specific License to a also requires LLW disposal site Qualified Applicant- Parts 2 Exammations for Use of operators to electronically store Respiratory Protection and 72 container-specific manifest Equipment-Part 20 information, and requires the On April 28,1995 (60 FR disposal site operators to be 20879), the NRC published an On February 10,1995 (60 FR capable of reporting the stored 7900), the NRC published an amendment to its regulations to uniform mamfest information on permit the Director of Nuclear amendment to its regulations, a computer readable medium. effective March 13,1995,to Material Safety and Safeguards to issue a site-specific license to reduce the frequency at which NRC Size Standards; a qualified applicant. Such medical fitness determinations Revision-Part 2 are required to ensure the safe licenses permit interim storage of use of respiratory protection spent fuelin an independent
, On April 11,1995 (60 FR spent fuel storage installation egmpment. 18344), the NRC published an (ISFSI) at a reactor site following amendment to the size standards satisfactory completion of NRC Reduction of Reporting used to qualify an NRC licensee Requirements imposed on NRC safety and environmental reviews as a "small entity" under the and after any public hearing on Licensees-Parts 50,55, and 73 Regulatory Flexibility Act. This the application. This amendment, amendment, effective May 11, effective May 30,1995, eliminates On March 14,1995 (60 FR 1995, establishes a separate the need for express Commission 13615), the NRC published an standard to be used to determine authorization for each ISFSI amendment to its regulations, whether a manufacturing licensee license. However, the amendment
285 does not affect'the scope of NRC date for licensee "U" and "R" Emergency Planning Licensmg review of an ISFSIlicense special nuclear material access Requirements for Independent application, or the present authorizations and "Q" and "I" Spent Fuel Storage Facilities opportunity for public hearing access authorizations. This (ISFSI) and Monitored provided for in the NRC rules of amendment, effective June 16, Retrievable Storage Facilities practice. 1995, also requires the licensee to (MRS)-Part 72 submit NRC renewal application Nuclear Power Plant License paperwork only for an individual On June 22,1995 (60 FR Renewal; Revisions-Parts 2,51, who has not been reinvestigated 32430), in accordance with the
, and 54 by the Department of Energy or Nuclear Waste Policy Act of another Federal agency within 1982, the NRC published an On May 8,1995 (60 FR 22461), the 5- to 7-year span permitted in amendment to its regulations the NRC published an the regulations, regarding the emergency amendment to its regulations to Pl anning licensing requirements revise tl 3 requirements that an for independent spent fuel applicant must meet for Performance Requirements for storage facilities and monitored j obtaining the renewal of a Radiography Equipment-Part retrievable storage facilities. This , nuclear power plant operating 34 amendment, effective ;
September 20,1995, ensures that license. This amendment, effective June 7,1995, also local authorities will be notified clarifies the required information in the event of an accident so that must be submitted for On May 31,1995 (60 FR that they may take appropriate I review so that the NRC can 28323), the NRC published an action. j determine whether those mendment to its regulations
, , I pertammg to performance Radiat,on i Protection l requirements have been met and requirements for radiography Requirements: Amended changes the administrative e9mPment. This amendment, Definitions and Criteria-Parts requirements that a holder of a effectwe June 30,1995, permits a 19 and 20 renewed license must meet. l licensee to use an alternative torque value for the performance On Ju y 1 5 (60 FR 36038),
i Changes to NRC Addresses and , Telephone Numbers-Parts 2, testmg en cria. 19,20,30,32,40,50,51,60,61, revise the radiation protection 70,71,72,73,74,76, and 150 training requirement so that it Revision of Fee Schedules; 100% Fee Recovery, FY 1995-Parts ap e oa y On May 9,1995 (60 FR 24549), 170 and 171 the NRC published an in excess of 10 mrem (1 mSv)in a amendment to its regulations, year This amendment, effective effective immediately, to reflect August 14,1995, also revises the , the current addresses, telephone On June 20,1995 (60 FR definition of" member of the numbers, and organizational 32218), the NRC published an public" to clarify that a worker titles within the NRC, following amendment to its regulations to receiving an occupational dose is consolidation of Headquarters change the licensing, inspection, not included; revises the employees to Rockville, and annual fees charged to its definition of " occupational dose" Maryland, applicants and licensees. This to delete reference to location so amendment, effective July 20, that the occupational dose limit NRC Licensee 1995, is necessary to implement applies only to workers whose Renewal / Reinvestigation the Omnibus Budget assigned duties involve exposure Program-Parts 11 and 25 Reconciliation Act of 1990, which to radiation and not to members mandates that the NRC recover of the public; and revises the On May 17,1995 (60 FR approximately 100 percent of its definition of "public dose" to 26355), the NRC published an budget authority in fiscal year apply to dose received by amendment to its regulations to 1995, less amounts appropriated members of the public from climinate the 5-year expiration from the Nuclear Waste Fund. material released by a licensee or
286 from any other source of Clarification of October 19,1995, provides the radiation under the control of the Decommissioning Funding requirements for the licensee. In addition, the Requiremants-Parts 30,40,70, procurement of basic amendment ensures that prior and 72 components, which will be dose is determined for anyone procured initially as commercial subject to the monitoring On July 26,1995 (60 FR 38235)' gr de items with subsequent requirements in 10 CFR Part 20 dedication for safety-related , the NRC published an and retams a regturement that amendment to its regulations, service, m a manner that avoids knogvn overexposed individuals effective November 24,1995, unnmssary delay and expense receive copies of any reports of
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