ML20045E677
| ML20045E677 | |
| Person / Time | |
|---|---|
| Issue date: | 06/29/1993 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-93-185, WIR-930625, NUDOCS 9307020304 | |
| Download: ML20045E677 (36) | |
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i June 29, 1993 For:
The Commissioners frQG:
James L. Blaha, Assistant for Operations, Office of the EDO Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 25, 1993 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F
Information Resources Management G
Controller H*
Personnel 1-Small & Disadvantaged Business Utilization & Civil Rights J*
Enforcement K
Consolidation L
State Programs M
Policy P1anning N*
Public Affairs 0*
International Programs P
Congressional Affairs Q
Regional Offices R
Executive Director for Operations S*
Meeting Notices T
- No input this week.
.W ames L. Blaha Assistant for Operations, OEDO
Contact:
i 5b4 gV W !8=mge ah MEEKLYINFOREPT PDR i
Office of Nuclear Reactor Regulation Items of Interest Week Ending June 25, 1993 Meetina at FEMA The Emergency Preparedness Branch represented the NRC at an NRC/ FEMA Steering Committee meeting at FEMA Headquarters on June 22, 1993.
Issues. addressed at the meeting included implementation of the new EPA-400 protective action-guides, the status of FEMA responses to the issues raised in a 10 CFR 2.206 petition at THI, the forthcoming elimination of the Wellesley Reception Center for Pilgrim and Seabrook, the status of the proposed Supplement 3 to NUREG-0654 on protective action recommendations for severe accidents, the proposed standard for portal monitors used at offsite reception centers, and other site-specific items of concern such as the licensing of Watts Bar and the restart of Indian Point 3.
PROS Meetina P
On June 18, 1993, Bruce A. Boger, Director, Division of Reactor Controls and Human Factors, represented the NRC at the annual meeting of the Professional Reactor Operator Society (PROS). Major topics'of discussion were the recent changes to the examiner standards (Revision 7) and the proposed changes to 10 CFR 55. The group also expressed interest in the Augmented Inspection' Team results from the Palo Verde steam generator tube rupture event, the loss of overhead annunciators at Salem, the operator licensing recentralization study and shift staffing concerns raised at Sequoyah in view of the crew response to -
a dual unit trip from full power.
Generic Letter 93-04 Generic letter. 93-04 on the subject of rod control system failure and withdrawal of rod control cluster assemblies was issued on June 21, 1993. -It was sent for action to all holders of Operating Licenses or Construction Permits for Westinghouse designed nuclear power reactors except Haddam Neck, and for information to all holders of Operating Licenses'or Construction Permits for Combustion Engineering and Babcock and Wilcox designed nuclear power reactors and Haddam Neck. A failure mechanism whereby a single failure could cause an inadvertent withdrawal of one or more individual rod control cluster assemblies (RCCA) was discovered as a rt
.t of an event at Salem Unit 2 on May 27, 1993. An Augmented Inspection Team continues to investigate the Salem event and its implications. The staff activated the Westinghouse Regulatory Response Group on Tuesday, June 8, 1993. A meeting was held with the Westinghouse Owners Group on Monday, June 14, 1993, to discuss the safety implications of the Salem event. Although the staff believes that the safety significance of this issue is not high, it believes that compliance with plant-specific licensing bases is in question for holders of Operating Licenses or Construction Permits f.or Westinghouse designed nuclear power reactors. The generic letter required these licensees to answer questions to determine compliance with the licensing basis.
i JUNE 25, 1993 ENCLOSURE A i
4 BWR Water LAvel On June 17, 1993, the staff met with Commonwealth Edison to discuss the BWR water level instrumentation issue and implementation of Bulletin 93-03 for LaSalle Units 1 and 2.
During Unit 2 shutdown on June 1,1993, the "B" channel was declared inoperable due to 8" permanent level offset that occurred at very low reactor pressure. The Tech Spec was cleared upon entry into Cold Shutdown condition.
The operability criteria that they have established for LaSalle is a notch of f
>6" in magnitude and >2 minutes in duration.
By instrumenting their condensate pots, they have discovered that their pots consistently become gas saturated after approximately 2 months of operation. This was also evidenced by a slow drift upward in level during operation when small leaks from the leg are not replenished by condensation. When this occurs they backflush the-particular leg at power, and check for leakage, both external and internal.
Since the "B" leg performed the worst on both units during. plant shutdown, this leg will be backflushed at about 500 psi during shutdown. There is'a-convective neat source near the "B" legs that may aggravate the drawdown of gases into these legs. They also have two cold reference legs that are used only for post accident indication. These legs are backflushed monthly during operation to preserve the accuracy of the post accident level instrumentation.
Because preliminary work by General Electric has shown that the condensate pot vent modification may result in unacceptable fluctuations in the instrumentation, Commonwealth Edison has shifted the focus of their work to the constant backfill modification. At this point, they have not completed a plan for the engineering work that would be required to implement the backfill modification, and they are not sure that they can make the modification under 50.59. They discussed performir.g testing of the control rod drive system flow and pressure fluctuations during the September refueling outage for LaSalle-2.
It is unlikely that the licensee will meet the schedule for modifications contained in Bulletin 93-03.
Limerick Generatino Station. Units 1 and 2 Both Limerick units are operating at 100% power with no significant problems.
On June 23, 1993, Project Directorate I-2 (PDI-2) issued the license amendment authorizing the transfer of the Shoreham fuel to the Limerick facility. This license amendment allows PECo to receive, possess and use the Shoreham fuel at the Limerick site. This action completes our major activity on the action plan of March 24, 1993. The mode of shipment will involve transport by barge from the Shoreham site to a PECo facility along the Delaware river, Lfollowed by rail transport from there to the Limerick site. NMSS has approved the security plan for this mode of transport. The start of the. shipping of the fuel is now expected sometime in July 1993. The completion of the proposed 33 shipments, in the GE IF-300 shipping cask, is expected in the spring of 1994.
In accordance with the action plan, PDI-2 will continue to monitor, along with NMSS and Region I, the fuel transfer.
JUNE 25, 1993 ENCLOSURE A
3 Diablo Canyon Units 1 and 2.
On June 21, 1993, the licensee filed an initial identification of witnesses and a motion for schedule change with regard to the license recapture hearing-l before the ASLB. The hearing was requested by the Mothers for Peace who object to the licensee's amendment request to recover the construction period and extend the operating licenses 13 and 14 years for Units 1 and 2, respectively. The licensee proposed to forgo summary disposition motions on both admitted contentions which include concerns about the licensee's maintenance / surveillance program and Thermo-Lag compensatory measures. The 2
licensee also proposed to proceed directly to prefiled testimony and advance the schedule for hearing that was previously set for.0ctober. The ASLB has granted the licensee's request. As a result, the written direct testimony is due from all parties on August 2,1993, and the public hearings are scheduled to begin August 17, 1993, and continue for about two weeks in San Luis Obispo.
The staff is currently preparing a' witness list and written testimony.
I h
J"NE 25, 1993 ENCLOSURE A
)
Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending June 25, 1993 Meetina With Battelle-Columbus On Tuesday, June 22, 1993, Fuel Cycle Licensing Branch staff and a represen-tative of the Office of the General Counsel met with five Battelle-Columbus personnel to discuss the current status of their operations and future plans for the activities covered by License SNM-7. The principal current and planned activity is the decontamination and decommissioning of multiple-facilities which were involved in research and development (R&D) activities utilizing nuclear materials provided by the Department of Energy-(DOE) or-licensed by the Nuclear Regulatory Commission.
Since the' major portion of the
. R&D effort involved DOE materials, DOE has accepted responsibility' for 90 percent of the decommissioning costs.
Topics of discussion during the meeting included:
SNM-7 license renewal, decontamination / decommissioning activities and schedules, decommissioning financial' assurance requirements and ongoing activities planned for the site.
Regarding ongoing activities, Battelle plans to continue a low level effort in the areas of radiology'and tracer studies.
Nuclear Reaulatory Commission / Department of Enerav Safeauards Comparability On June 22, 1993, a Fuel Cycle Operations Branch staff member participated in a Department of Energy (DOE) meeting to initiate a review and revision of the current DOE threat policy.
Representatives of several Federal agencies concerned with counterterrorism also attended.
The Nuclear Regulatory Commission staff member briefed the group on current NRC activities relating to vehicle threats and the NRC design basis threat.
Gaseous Diffusion Plants - DOE Interest in Acolicable International Atomic Eneray Aaency (IAEA) Safequards Activities On June 21, 1993, Division of Fuel Cycle Safety and Safeguards (FCSS) staff met with a Los Alamos National Laboratory (LANL) employee, at his request, to discuss the IAEA safeguards activities conducted at Nuclear Regulatory Commission licensed facilities.
LANL is working with the. Department of Energy on safeguards for the Portsmouth and Paducah enrichment facilities, since the two enrichment facilities may be added to the Eligible facility List and may be selected by the IAEA for inspection.
The LANL representative was briefed on the methods and procedures used by the IAEA in safeguards activities, i.e.,
on 1) the submittal of the Design Information by the facility, 2) the procedure for adding a facility to the Eligible Facility List, 3) the selection of the facility by the IAEA for reporting and inspection or for reporting only under the US/IAEA Safeguards Agreement (INFCIRC/288), 4).the negotiation of a facility Attachment or a Transitional Facility Attachment, and 5) how the IAEA utilizes the data reported to them.
Final Safety Evaluation Report issued for Envirocare of Utah On June 18, 1993, the Nuclear Regulatory Commission staff issued the Final Safety Evaluation Report (FSER) on Envirocare of Utah, Inc.'s application'for a license to construct and operate a facility to receive, store, and dispose JUNE 25, 1993 ENCLOSURE B
-2 of Ile.(2) byproduct material near Clive, Utah._ In the FSER the staff has identifiea 13 open. issues in.the areas of geotechnical engineering, water resources protection, radon attenuation, financial assurance, and radiological.
safety. -The NRC will not issue a license for the proposed action until Envirocare adequately resolves these open issues. The NRC staff's documentation of the resolution of remaining open issues will-be by supplements to the FSER.
Resolution of Survey Error of North Portal location The Department of Energy Yucca Mountain Project Office _ (YMP) _has determined that there was an error in the location (latitude, longitude, altitude) of the starting point-for the exploratory studies facility-(ESF)..YMP's review of the problem indicated that the error was due to a contractor not having properly qualified personnel and procedures for conducting conventional leveling geodetic surveys. A new survey has been conducted.and drawings and geologic maps are being modified to reflect the adjusted location. The adjustment was approximately 0.1 ft. horizontal and.45 ft. vertical and had no significant effect on the ESF as constructed to date, The Nuclear Regulatory Commission On-Site Representatives (0Rs) are continuing to follow-related activities to gain a more complete understanding of the extent this problem may impact other quality affecting work. The '0Rs will-also review the documentation associated with the re-survey.
JUNE 25, 1993 ENCLOSURE B
.9 Office of Nuclear Regulatory Research Items.of Interest Week Ending June 25, 1993 Reaulatory Guide 1.160. "Monitorino the Effectiveness of Maintenance' at Nuclear Power Plants" The availability of Regulatory Guide 1.160, " Monitoring ~ the Effectiveness of Maintenance at Nuclear Power Plants" has been announced in the Federal Register and the document has been distributed to licensees of Power Reactors and Research and Test Reactors. The Regulatory Guide endorses NUMARC 93-01,
" Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," dated May 1993.
The Regulatory Guide also discusses the use of the Emergency Diesel Generator (EDG) triggers and monitoring methods described in Appendix D of.NUMARC 87-00, Revision 1.
The example used in NUMARC 93-01, which refers to optimizing EDG-reliability and availability, is cited as an acceptable means of establishing performance criteria and/or goals for EDGs. The Commission has selected the alternative of providing guidance in conjunction with the implementation of the Maintenance Rule (10 CFR 50.65) rather than modifying the Station Blackout-Rule (10 CFR 50.63) to more explicitly cover EDG reliability.
ASME Ooeration and Maintenance Committee Meetinos W. E. Campbell, Jr., participated as a member in meetings of the ASME OM
~
Committee Special Committee on Editorial Review (SCER) and Subcommittee on Vibration Monitoring (SCVM).
These meetings were held in.
Dearborn,
MI, on June 15 and 16, 1993..The SCER made considerable prcgress in resolving member comments on proposed standard OM 15, " Performance Testing of Emergency Core Cooling Systems in PWRs."
It was noted that the revision to RG 1.133 on loose parts monitoring has been stopped due to resource limitations.
Meetina at Johns Hopkins University / Applied Physics Laboratory (JHU/APL)
An introductory meeting between management and staffs from RES (DE & DSR) and the JHU/APL was recently held at the APL facility near Columbia, Maryland.
The purpose of the meeting was,to exchange information on the RES and APL missions and to learn of the technical skills, experiences, and capabilities available at the APL.
Specific areas where expertise has been demonstrated are:
development of " Intelligent Systems" including software for use in decision making in the areas of inspection, diagnostics, and human
- factors, development of safety systems to detect and mitigate electrical fires in high energy control systems aboard naval vessels, and development of non-destructive evaluation hardware and techniques using remote sensors to detect underground pipe breaks, flaws, anomalies, etc.
JUNE 25, 1993 ENCLOSURE C
1 2
Other areas where capabilities exist include heat transfer, materials and metallurgy, combustion, and' chemistry. Although the APL has been successful-in developing capabilities to solve many difficult' problems, there has been little experience dealing with nuclear equipment applications. -
The attendees agreed to exchange documents where particular interest was shown. The RES attendees also agreed to distribute the APL information to appropriate NRC staff for information and use, and for future assistance considerations.
Meetina with Eastern European Nuclear Experts on Aaina of Nuclear Power Plants.
On June 22, 1993, Satish Aggarwal of Electrical and Mechanical Engineering.
Branch met with J. Zlatnansky, Vice Chairman, Slovak Nuclear Regulatory Authority; K. Bohm, Director, State Office for Nuclear Safety, Prague; G. Mucskai, Deputy Director, National Atomic Energy Commission, Budapest; R. Ovtcharov, Head, Bu garian Committee on Use of Atomic Energy for Peaceful Purposes; and S. Rohar, Chief Inspector, Slovak Nuclear Regulatory Authority.
The highlights of the NRC aging research program were presented. The European nuclear experts expressed interest in obtaining copies of NUREG/CR-5643,
" Insights Gained from Aging Research" for their use.
(Copies will be supplied upon a request by the Office of International Programs).
Peer Review Meetina on Evaluation Criteria for ISLOCA On June 8, 1993, INEL presented the results of their work on component survival probability in low pressure piping exposed to an Interfacing' System Loss-of-Coolant Accident (ISLOCA) to an expert peer review panel comprised Lof D. F. Landers, E. C. Rodabaugh and D. A. Wesley.
Results had already been.
used in the Supplemental safety evaluation report for the Advanced Boiling.
Water Reactor and'are expected to be used'for other Advanced Light Water Reactors as well. A report from the peer review panel is expected in early August and will be used to justify use of the results before oversight bodies or in public hearings, or alternatively, to modify the course of the efforts.
The components covered include pumps, valves, heat exchanger tubes and tubesheets, flanges, tanks and vessels and piping elements.
Revision of ASCE Seismic Standard On June 17, 1993, an American Society of Civil Engineers (ASCE) Dynamic Analysis Committee Working Group met to discuss the revision of Standard ASCE 4-86, Seismic Analysis of Safety Related Nuclear Structures and i
Commentary on Standard for Seismic Analysis of Safety Related Nuclear Structures. Roger Kenneally (RES/SSEB) is the RES representative on the Working Group; other NRC representatives include T. Cheng and Y. Kim (NRR/ECGB). ASCE Standards are subject to a mandatory revision every 5 years.
In addition to revisions reflecting the state-of-the-art, two significant changes are being proposed.
The first is a broadening of the Standard to include all nuclear facilities (for instance, DOE. facilities).
JUNE 25, 1993 ENCLOSURE C
3 The second is an inclusion of. a nonmandatory appendix that. addresses the evaluation of facilities for seismic events beyond the design basis-(for instance, seismic probabilistic risk assessments or seismic margin evaluations).
't JuliE 25,1993 '
ENCLOSURE C-
t 7
Office for Analysis and Evaluation of Operational Data It ems of Interest-Week Ending June 25, 1993 Technical Trainina Center (TTC)
The first Technical Issue Training Bulletin (TITB), "BWR Level Instrumentation Noncondensable Gas Release," was issued on June 25, 1993.
The concept of the TITB was identified as a method for expedited development and distribution of' training on emerging technical issues.
It was developed by a project team at the TTC using the most current information available to the NRC.
The contents of the TITB were carefully reviewed by the management and subject matter experts in AE0D and NRR. The TITB was developed to convey the critical safety issues and the relevant engineering considerations and phenomena. The targeted NRC technical staff for this TITB included BWR resident inspectors, engineering support inspectors and BWR operator licensing examiners in the regions, headquarters operations officers and BWR instructors in AE00, BWR operator licensing examiners and project managers, engineering support inspectors, and technical reviewers in NRR and the supervisors of these staff members.
A contract (NRC-26-93-298), with an effective date of June 21, 1993, was awarded to Bishop Associates. This contract is in direct support of Ukrainian Priority 2 and Russian Priority 5, Establishment of Regulatory Training Programs iri Ukraine and Russia respectively.
The contract calls for the purchase, installation, burn-in, maintenance, and warranty service for eighteen microcomputer systems and associated peripherals and supplies. Half of the equipment will be delivered to Kiev, Ukraine for SCNRS use, and the other half to Moscow, Russia for GAN use.
The microcomputer equipment, although expected to be used for a variety of purposes, was acquired to support computer-based training in the RBMK-1000, VVER-440, and VVER-1000 designs. The microcomputer equipment is expected to be delivered in Kiev and Moscow in mid-July 1993.
The Subject Matter Expert Panel for the " Feasibility of a Human Factors Regulatory Research Facility" project, sponsored by the Office of Nuclear Regulatory Research, conducted a meeting at the TTC'on June 23-25, 1993. The TTC-specific part of the agenda included a tour of the TTC facility and simulator equipment, a short discussion of the capabilities of the simulators and simulation devices located at the TTC, and a scenario demonstration on the BWR/6 simulator.
Incident Response Branch (IRB)
The Director, D0A, and IRB staff participated in a meeting of the Catastrophic Disaster Review Group on June 21 at which FEMA presented the report of the Federal Response Task Force. This multi-agency task force has been in place for the past three months, developing new policies and procedures'for integrated federal response to emergencies.
FEMA Director Witt requested that agencies accept the task force as the starting point for the revised federal 1
response plan for "all hazard" responses.
JUNE 25, 1993 ENCLOSURE D
IRB staff conducted training on June 21 for members of the headquarters staff in preparation for the Fort Calhoun exercise. Additional training was scheduled for Monday, June 28.
During this week, an IRB staff member was in Region V to provide Emergency Response Data System (ERDS) training and familiarization to regional response team members.
NMSS conducted a training session for IRB staff on June 23 on Independent Spent Fuel Storage Facilities.
EGG provided emergency worker dosimeter training to the NRC'HQ Response Coordination Team on June 24. The procedures for radiation monitoring and control during the immediate response time frame of an accident were also reviewed.
Reactor Operations Analysis Branch (ROABl A hun.an performance study of an April 16th event at North Anna Unit 2 was issued on 6/23/93.
Following an automatic reactor trip, the. auxiliary feedwater (AFW) system was disabled by the secondary operator while a valid auto start signal msted. The secondary operator had received permission to
" secure AFW" and go on to main feedwater from the unit supervisor. The secondary operator placed the motor driven AFW pump control switches in
" pull-to-lock" and closed the steam supply valves to the turbine driven AFW pump.
Shift supervision intended for AFW to be shut down normally, i.e.
discharge valves throttled while the pumps continued running.
AFW was disabled for 18 minutes.
However, the normal method of shutting down AFW would have required manual operator action to restore AFW flow. The system misalignment was unknown to shift supervision until discovered by the procedure reader. Thc AFW system was then restored to a standby, operable configuration.
Major contributors to the disabling of AFW were operator uncertainty on how to respond to a cooldown that occurred after the emergency operating procedure step that checked for a cooldown had been completed, and terminology that was interpreted differently by the secondary operator and shift supervision.
Other important human performance aspects of the event included:
- command, control, and communications; teamwork; perceived stress; human machine interface; and training.
Preliminary Notifications a.
PN39332A, Quad Cities Unit 1, Quad Cities Unit 1 Shutdown Due to High Pressure Cooling Injection System Repairs - Update.
b.
PN39335, UCAR Carbon Co., Parma, OH, Contamination Found at Parma, Ohio Facility.
c.
PNO-II-93-026, Tennessee Valley Authority, Soddy-Daisy, TN, Fuel Assembly Tilted out of Position During Refueling (Unit 1 Cycle 7 Reload).
JUNE 25, 1993 ENCLOSURE D
y d.
FNI-9331, Construction Engineering consultants, Incorporated,-
Pittsburgh, PA, Construction Accident in Canonsburg,-Pennsylvania Involving a Portable Moisture Density Gauge.
e.
PN39334, Palisades.Nuc~ lear Power Plant, Covert, MI, Control Rod Pulled out of Core When Reactor Head Lifted.
f.
PN39333, University of Minnesota, Minneapolis, MN, Brachytherapy Misadministraticn.
t
-JUNE 25, 1993 ENCLOSURE D.
U
9 Office of Administration Items of Interest Week Ending June 25, 1993 Drua Testino Proaram The Department of Health and Human Services (HHS) Seml1 Annual report on NRC's Drug-Free Workplace Program for the period October 1, "1992 - March 31,1993, was signed by the Chairman and forwarded to HHS on June 22.
Items covered in-this report are analyzed by HHS and the Office of National Drug Control Policy to evaluate and compare agencies' programs.
Contract Award On June 21, a contract was awarded to Bishop Associates for 18 computers and peripherals to be used for the establishment of a technical training program in Russia and the Ukraine. This contract is part of the Agreement between the United States and the former Soviet Union known as the Lisbon Initiatives.
RFP Issues A Request for Proposal entitled " Incident Investigation Team Training" was issued on June 22.
The contractor shall furnish qualified personnel, materials and services to present-(l) an Incident Investigation Team Training Course, (2) an Incident Team Training Refresher Course, (3) a Root Cause/ Incident Investigation Workshop and (4) Human Performance-Investigation Process Training. The projected award date is September 30, 1993.
Whistleblower Protection for Nuclear Power Plant Employees A proposed rule that would amend the NRC regulations concerning the protection of employees who provide information to the NRC or their employers concerning safety issues was published in the Federal register on June 15, 1993 (58 FR 33042). The proposed rule would conform current regulations to reflect the new whistleblower protection provisions of the Energy Policy Act of 1992. The comment period for the proposed rule expires July 15, 1993.
Preparation. Transfer for Commercial Distribution. and Use of Byproduct Material for Medical Use A proposed rule that would amend the regulations applicable to the medical use of byproduct material was published in the Federal Register on June 17, 1993 (58 FR 33396). The proposed rule is intended to provide greater flexibility by allowing properly qualified authorized users who are physicians greater discretion to prepare radioactive drugs containing byproduct _ material for i
medical use. The proposed rule would also allow research involving human subjects using byproduct material and the medical use of radiolabeled biologics. The comment period for the proposed rule expires October 15, 1993.
JUNE 25, 1993 ENCLOSURE F
Radioloaical Criteria for Decommissionina of NRC-Licensed Facilities: Generic Environmental Impact Statement (GEIS) for Rulemakina. Notice of Intent To Prepare a GEIS and To Conduct a Scooina Process In a Federal Register notice published June 18, 1993 (58 FR 33570), the NRC announced that it is proposing to codify radiological criteria for termination of licenses and release of land and structures after levels of residual contamination have been appropriately reduced. The proposed action would provide a clear and consistent regulatory basis for determining the extent to which radioactive materials must be removed from-land and structures before.a site can be released. This document announces that the Commission intends to prepare a Generic Environmental Impact Statement for this action and to conduct a scoping process for this action that will include a series of public meetings.
Sionificant F0IA Reouests Received by the NRC For 5-Day Period of June 18 -
June 24. 1993 Request for records regarding Rutgers University since.1985.
(Joseph San Filippo, F01A-93-351)
Request for Parts 170 and 171 licensee fees paid by each operating power reactor unit for each quarter in FY 1990, 1991 and 1992.
(Tsege Redda, STS, F01A-93-352)
Request for the number of inspection hours per SALP functional area over the last three SALP periods for each plant and the corresponding SALP score in each functional area.over the same periods for each plant.
(Tsege Redda, STS, F01A-93-353)
Request for a copy of " Forensic Neutron Activation Analysis of Bullet-Lead Specimens", AEC Report GA-10141.
(Willette Page, AT&T Bell Laboratories, F01A-93-354)
Request for copies of 27 specified OI reports.
(Dave Davis, The Plain Dealer, F01A-93-355)
Request for copies of reports of discharges of cobalt-60-to the sanitary sewer in specified zip codes in the Ohio area.
(Thomas Lenhart, Northeast Ohio Regional Sewer District, FOIA-93-356)
Request for records to or from a named individual since January 1,.1985, and involving specified licensees and companies.
(Karen Unnerstall of Newman &
Holtzinger, P.C., F01A-93-357)
Request for copies of (1) procedures and/or guidelines used by the NRC and in place as of November,1992, relating to the severity level applied by the NRC for alleged violations by byproduct material licensees of 10 CFR _Part _19, 20 and/or 35, and (2) books and/or compilations of resolutions of actions between-the NRC and byproduct material licensees for alleged violations of 10 CFR Part 19, 20 and/or 35 for the period January 1, 1990, to the present.
(Marcy Colkitt, Oncology Services Corporation, F01A-93-358)
JUNE 25, 1993 ENCLOSURE F s
Office of Information Resources Management Items of Interests Week Ending June 25, 1993 WNRC Proposed Chanaes to the Disoosition of NRC Accessions The Washington National Records Center (WNRC) recently conducted a review of several NRC accessions containing permanent records that are located at the Federal Records Center (FRC) and are eligible for transfer to the National Archives. On June 8,1993, the WNRC issued a letter to the NRC identifying recommended changes in the disposition of five of these accessions..The Office of Information Resources Management (IRM) has completed its review of the WNRC proposed changes and has identified the actions required to address the proposed changes. The IRM is coordinating its findings with the FRC and will be preparing the material for transfer to the National Archives in accordance with the approved records disposition schedules contained in NUREG-0910, and established agency procedures.
Support for NMSS Eight Sun Sparc IPX computers were installed and connected to the server in.
the Office of Nuclear Materials Safety and Safeguards (NMSS). An additional 2.1 gigabytes of storage was added to their server. This storage is-accessible to all of the clients attached to the server. Additional work left to be accomplished includes installation of the Fortran software, fine-tuning individual configurations, and resolving problems with UNIX workstation connectivity to the AUTOS Local Area Network.
Computer Security Activities On June 23, 1993, at the request of Region I, Emily Robinson of the Codes and Standards Section presented a computer security awareness briefing to 50 Region I Resident Inspectors in the morning as part of their counterpart meeting, and presented similar training sessions twice in the afternoon to other Region I staff.
Reauest for NUDOCS Access An increased interest on the part of the media has been displayed through recent requests for NUDOCS access.
In'the last several weeks, ten new user accounts for access to NUDOCS have been requested. These requests.are being coordinated with the Office of Public Affairs and will provide the requesters with access to agency publicly available documents through NUDOCS The letter to the requesters granting access and providing necessary information to connect to the system also provides information regarding the agency's. Public Document Room services.
l 4
JUNE 25, 1993 ENCLOSURE G
Office of Personnel Items of Interest
' Week June 25, 1993 Meetina of Child Development Center's Board of Directors Conducted On June 23, the Board of Directors of the Child Development Center held its monthly meeting. During this meeting, the Board received information on how to select a management firm to operate the center.
Issues raised include staff salaries and benefits, staff _ qualifications and screening procedures, staff turnover, parent involvement, and insurance options. A Request for Proposal (RFP) to obtain the management firm will be released 'in early FY-1994.
Acency Represented at Maior National Conferences Jude Himmelberg, OP, represented the NRC. at the Society of Women Engineer's-(SWE's) annual conference the week of June 21, 1993.. Kristin O'Donnell, OP, attended the American Nuclear Society's (ANS's) annual conference the week of June 21, 1993.
Continued contact is maintained with ANS and SWE to ensure NRC has the name recognition needed to~ attract members to consider NRC for future employment opportunities.
New Manaaement Directive Published Management Directive (MD) 10.13, "Special Employment Programs," has just been published. This directive and handbook provides guidance on seven special-employment programs: stay-in-school, summer aid, graduate fellowship, student volunteer, employment of persons with disabilities, veterans readjustment appointments, and part-time career employment.
Arrivals Mathew, Roy OPERATIONS ENGINEER (PFT)
NRR Retirements FLEMING, Bessie L.
SUPPORT SERVICES ASSISTANT (OPFT)'
RV MESTRE, Jorge SR. PROGRAM ANALYST (PFT)
SBCR Departures None JUNE 25, 1993 ENCLOSURE I
Office of Enforcement l
Items of Interest Week Ending June 25, 1993 Sianificant Enforcement Actions A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $2,000 was issued on June 23, 1993, to Ponce I&M Engineering Lab. Inc.
This action was based on a Severity Level III violation that involved willful use of licensed material after an NRC license had expired and before a new license was issued. The base civil penalty for a Severity Level III violation is $500.
Escalation of 50 percent was applied for NRC identification and 50 percent for poor prior licensee performance. Neither escalation nor mitigrtion was warranted for corrective action.
In addition, the base civil penalty was escalated 200 percent because of the willful nature of the violation by a principal officer of the licensee. Six other violations'were cited and categorized at Severity Levels IV and V.
(EN 93-060)
An Order Imposing Civil Penalties in the amount of $200,000 was' issued on June 23, 1993, to Nebraska Public Power District (Cooper Nuclear Station).- The action was based on two violations, the first involved providing inaccurate information in response to an NRC Notice of Violation, and the second involved the failure to identify and correct a potentially significant condition adverse to quality involving startup strainers remaining in safety-related systems. The licensee responded to the Notice in a letter April 29, 1993.
After careful consideration of the licensee's response, the staff concluded that the violations did occur and an Order was issued.
(EN 93-024A)
A Order Imposing Civil Penalties in the amount of $10,000 was issued on June 23, 1993, to the U. S. Department of Agriculture (USDA). The action was based on violations in the management of the licensee's radiation safety program.
The licensee responded to the Notice in two letters dated April 22, 1993, and admitted the violations but protested the civil penalty. After consideration of the licensee's response, the staff concluded that the licensee did not provide an adequate basis for mitigation of the civil penalty and an Order was issued.
(EN 93-022A)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $500 was issued on June 24, 1993, to Hazelton Wisconsin, Inc., of Madison, Wisconsin. Hazelton Wisconsin is authorized to possess and use curie quantities of any byproduct material with atomic numbers 1-83 for use in research and development as defined by 10 CFR 30.4(q) and animal research.
In addition, the company is authorized to possess up to 1.2 curies of Ni-63 in gas chromatographs, each source not to exceed 15 millicuries.
In January 1992 the company accidently discarded one of these sources in the local landfill.
Because of ineffective corrective actions, it accidently discarded a second source in September 1992. These losses constitute a violation of 10 CFR 20.301. The base civil penalty is $500.
The base penalty was mitigated 50%
for identification and 100% for licensee performance, but it was also escalated 50% for ineffective corrective actions and for the two occurrences, resulting in no change to the base.
(EN 93-062) i l
JUNE 25, 1993 ENCLOSURE K t
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued on June 25, 1993, to the. Wolf Creek Nuclear 0perating Corporation. This action was based on the licensee's failure to ensure that the two motor-driven auxiliary feedwater pump control room hand switches were correctly aligned before entering mode 3 (Hot Standby) during startup following an outage. The base civil penalty was mitigated 50%'for licensee identification and 50% for the licensee's prompt and. thorough corrective action. However, the civil penalty amount was escalated 100% for the multiple opportunities the licensee had to identify the misalignment sooner through..-
shift turnover and control board walkdowns.
(EN 93-063)
Civil Penalties Paid GPU Nuclear Corporation (0yster Creek Nuclear Generating Station) paid the civil penalty in the amount of $50,000. The action was based on an' inadequate temporary procedure change that resulted in a plant heatup above 212 degrees F.
without certain Technical Specification requirements being met.
(EA 93-055)
Commonwealth Edison Company (Braidwood Unit 2) paid the civil penalty in the.
amount of $50,000. The action was based on the discovery by licensee personnel that contrary to the unit technical specifications, during the previous operating cycle the unit operated without an operable reactor vessel heat vent system. Both trains of the system were inoperable due to a closed common manual isolation valve which was not properly aligned to the open position following the previous refueling.
(EA 93-063) l The University of Michigan paid the civil penalty in the amount of $3,750.
The action was based on exceeding the licensed power level; by 15 percent for approximately 10 minutes.
(EA 93-069)
Gulf States Utilities (River Bend) paid the civil penalty in the amount of
$50,000. The action was based on three violations that occurred while the licensee was performing activities associated with the containment and drywell airlock interlock mechanisms.
(EA 93-060)
L JUNE 25, 1993 ENCLOSURE K
Office of Consolidation Items of Interest Week Ending June 25, 1993 Second Buildina Status During the week, KT Landscaping continued to place mulch, sod, shrubs, ground.
cover and annual and perennial flowering plants in the plaza pedestrian concourse planters and along the walks in front of TWFN. Sprinklers on the lawn area in front of TWFN were tested and were used on the newly placed sod.
Pavers were set on the ramp between OWFN and TWFN and around the auditorium entrance at the A-level entrance, and cracked pavers were replaced in front of OWFN and TWFN. Light posts were installed on the pedestrian concourse and the walkway was opened to pedestrian traffic during the week.
Insulation on the-upper floors along the perimeter walls was completely installed.. Metal garage doors connecting OWFN and TWFN were painted.
Lightening protection on cooling towers and on the perimeter of the roof was installed during the week.
On June 22, members of Commissioner Curtiss' staff toured TWFN with the Director, Office of Consolidation (CONS).
Also on June 22, CONS staff met with the NIST Indoor Air Quality. Group and Sigal's Site Superintendent to review drawings of ventilation systems for TWFH in preparation for air quality testing of the new building.
In the morning of June 23, Chairman Selin toured some of the public areas of the new building.
Commissioner de Planque and members of her staff toured the new building in the afternoon of June 23.
Also on June 23, the Director, CONS, and members of ADM's Facilities Management Branch and Division of Security met with the developer's representatives and Mr. Tim Sutter, a Vice President of Diplomat Parking Corp., to discuss the details of parking arrangements for NRC employees in the TWFN garage beginning in early July.
Diplomat will operate the garage for White Flint North Limited Partnership.
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JUNE 25, 1993 ENCLOSURE L
Office of State Programs Items of Interest Week Ending June 25, 1993 Anoalachian States low-level Radioactive Waste Annual Meetina-Marie Miller, Region I State Liaison Officer, attended the annual' meeting of the Appalachian States Low-Level Radioactive Waste Commission on June 24, 1993 in Harrisburg, Pennsylvania. Mr. Arthur Davis, Secretary, Pennsylvania Department of Environmental Resources and Chairman of this Commission, presided over the meeting, which included senior State representatives from Maryland, Delaware and West Virginia. Topics discussed included:
siting status, Low-Level Waste Forum activities, interregional access agreements for waste management, election of officers and other administrative topics. The selection of three candidate areas is expected by mid-1994.
JUNE 25, 1993 ENCLOSURE M
Office of-International Programs Items'of Interest Week Ending June 25, 1993 Assionees from Ukraine Two assignees from Ukraine, Mr. Nikolay Kurilchik and Mr. Valery Glygall will arrive at NRC on July 7th. They will be assigned to the Office of4 Nuclear Regulatory Research it..he Reactor and Plant Systems Branch, where Andy Szukiewicz will be their supervisor. They will study NRC management and practice in the development of regulatory research needs.
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JUNE 25, 1993 ENCLOSURE P
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Region I Items of Interest Week Ending June 25, 1993 1.
Visit of UK Official During the week of June 14-18, 1993, the Division of Radiation. Safety and Saftguards hosted Mr. Steven. Ebdon-Jackson,. Principal Scientific Officer from the United Kingdom. Mr. Ebdon-Jackson is. responsible for the UK's medical-regulatory program, and was interested in becoming familiar with the inspection and licensing program in the US. He accompanied Region I staff on inspections of the University.of Massachusetts Medical Center and Whidden Memorial Hospital in Massachusetts, and discussed regulatory issues' with NMSS staff'in the Division of Industrial and Medical Nuclear Safety and with Region I staff.
2.
Haddam Neck The licensee has four Model 27 steam generators with one 14" outer diameter feedwater (FW) nozzle per steam generator. During the 1993 outage, three of the four nozzles were found to have cracks on the nozzle inner surface within 1-1/2" of the weld between the nozzle and the inlet elbow. The cracking is close tolthe end of the thermal sleeve, although the end of the thermal sleeve was shown to have moved-relative to the nozzle to elbow weld during service.
Radiography (RT) is the licensee's primary method used to find cracks in accordance with the recommendation of IEB 79-13 titled " Cracking in Feedwater System Piping." The ultrasonic (UT) tip diffraction method was used to determine the depth of the cracks.
Nozzle I has had no previous problem with cracks and none were detected during this outage.
Nozzle 2 has one crack 18" long, 3/4" from the weld toe on the nozzle side. The depth of the crack is 1/4" 1/16".
Nozzle 3 has a 16" long crack 1-1/4" from the weld centerline on the nozzle side. The depth of the crack is 3/16" i 1/16".
Repairs were done and the elbow has been put back in place.
Nozzle 4 has two cracks and the thermal sleeve has moved toward the nozzle 1.25" since May 1980. The primary crack is a 25.5" long-circumferential crack in the bottom 180* of the nozzle. This crack is 1.5" from the weld centerline and appears to be 4" longer than in 1980.
The second crack is 1.75" long at the bottom of the nozzle. The depth of this crack is 1/8" i 1/16".
Examination of a sample of other FW pipe welds indicates that the cracking problem is limited to the FW nozzle area. The ISI program requires the examination of approximately 140 other FW' pipe welds as the JUNE 25, 1993 ENCLOSURE R
P F
sample expansion due to the identification of;the'.above cracking. - The-licensee is planning to request relief from the ASME Section XI Code that they are committed to regarding the extent of sample expansion in-the FW system.
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JUNE 25, 1993 ENCLOSURE R
I Region II Items of Interest Week Endinig June 25, 1993 1.
NRC/ Licensee Meetina at TVA Seauoyah Site The Regional Administrator conducted a public meeting on June 22, 1993, at the TVA Sequoyah site between the licensee and-NRC to discuss activities associated with the restart of Sequoyah Units 1 and 2.
2.
NRC/ Licensee Meetina at TVA Watts Bar Site The Regional Administrator conducted a public meeting on June 23,1993, at the TVA Watts Bar site between the licensee and NRC to discuss construction related topics.
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JUNE 25, 1993 ENCLOSURE R
Region III Items of Interest Week Ending June 25, 1993 1.
Chairman Selin Visits Ohio Contaminated Sites On June 21, 1993, Chairman Selin, accompanied by the Regional Administrator, Region III, visited the Southerly Waste Water Treatment Plant in Cuyahoga Heights, Ohio; the two Chemetron Corporation sites 'in Newburgh Heights and Cleveland, Ohio; and the Advanced Medical--Systems facility in Cleveland. All three sites are part of the Site Decommissioning Management Plan.
Senator Howard Metzenbaum and.
Congressman Martin Hoke also participated in the site visits. A news briefing was held by the Chairman at the conclusion of the visits.
2.
Dresden Nuclear Power Station On June 25, 1993, the Dresden Oversight Team exit meeting was held at the Dresden Station. The NRC was represented by the Deputy Regional Administrator; the Acting Director, Division of. Reactor Safety; the Assistant Director for Region III Reactors, NRR; and others. The licensee was represented by the Site Vice President and others. The meeting was open to the public and the media.
3.
Palisades Nuclear Plant On June 15, 1993, the licensee was lifting the reactor head in preparation for refueling when technicians observed that a control rod was also being lifted with the reactor head.
The head and control rod were lifted about 7 feet when the attached rod was noticed. All refueling activities were immediately halted and a recovery plan was -
developed. The head and control rod were subsequently lowered back into the vessel and the control rod was disengaged.
The resident inspector and region-based inspectors were on site at the time of the event and provided 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of the licensee's recovery actions, and interviewed involved personnel.
On June 18, 1993, during a telecon between Region III management and the licensee to discuss the results of their review of the event, the licensee agreed to document the results prior to continuing refueling activities.
On June 19, 1993, the licensee provided the documented review, the lessons learned, and their intended corrective actions.
Also, on that date, the Region III Projects Branch Chief and the Big Rock Point Senior Resident Inspector met with the licensee at the site to discuss the response and to interview personnel.
Subsequently, the Regional Administrator and the Vice President Nuclear Operations discussed the event and other i.ssues, and a management meeting in Region III was requested for June 28, 1993.
4.
Quad Cities Station On June 23, 1993, the Chief, Reactor Projects Branch 1, attended an exit meeting for a special team inspection led by the Division of Reactor JUNE 25, 1993 ENCLOSURE R
Safety to discuss the events and circumstances surrounding the. June 18, 1993, failure of the rupture disks on the high pressure coolant injection (HPCI) steam exhaust line for Quad Cities Unit 1.
The exit meeting emphasized weaknesses in' engineering, operations and quality assurance that led to the rupture disk failure.
5.
Former licensee Identified With Contamination Sites On June 22 through 24, 1993, Region III identified two contaminated sites that will require remediation. Oak Ridge under contract with the.
NRC is reviewing the docket files of former licensed activities that -
were terminated in the 1960's.
The purpose of the review is to _ identify licenses where sufficient information does not ' exist in the file to conclude that the facilities and surrounding environment were proptrly.
decontaminated on license termination. Two licenses identified as' having insufficient documentation describing _their decontamination activities were surveyed and determined to have low level contamination.
UCAR Carbon Corporation in Parma, Ohio (a suburb of. Cleveland) which formerly performed research on high enriched uranium fuel was identified.
as having isolated fixed low level surface contamination in one building. National Electric Carbon Company in Fostoria, Ohio which performed research on enriched uranium and thorium as well as manufactured graphite coated enriched uranium spheres was identified as having low level removable _ contamination in a large walk-in safe.
Contamination was also identified in storm sewers near other buildings on the site.
The sites were formerly owned by Union Carbide Corporation.
Union Carbide has committed to perform additional surveys to characterize the -
contamination and be responsible for any necessary remediation.
6.
Quad Cities Station On June 21, 1993, an enforcement conference was held between the Deputy Regional Administrator, Region III, members of the Region III staff, and Commonwealth Edison Company management and staff.. The purpose of the conference was to discuss apparent violations _involv'ing the fire protection program and safe shutdown equipment.
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I JUNE 25, 1993 ENCLOSURE R
Region IV-Items of Interest Week Ending June 25, 1993 1.
Cooper Nuclear Station The Deputy Regional Administrator _ and the Director, Division of Reactor' Projects visited the site on June 22, 1993, to participate in a meeting with Nebraska Public Power District management. The meeting was open to the public and addressed issues identified during the current outage.
The refueling outage _ began on March 7,1993, and was originally scheduled to last for_56 days.
2.
Inspector Dispatched'to South Dakota On June 23, 1993, Region IV received a call from the State Liaison Officer (SLO) for South Dakota. The SLO had.been notified that there were three 35 gallon drums on a ranch near Burbank South Dakota, each had a radiation sign on the side of the drum. An individual from the state geological survey laboratory had visited the site and stated that she had read 2 mr/H on the side of one drum-and 10s of mr/H over the opening of that drum (the plug to the drum was missing). The. SLO.
requested that Region IV assist the state in determining if the material in the drums was radioactive and help identify the contents _inside the drums. On June 24, 1993, the Region dispatched a region inspector to South Dakota. An inspector has been dispatched.to the site with a state representative. The samples will be sent to the Region IV Confirmatory Measurements Laboratory, which is at the Fort Calhoun Nuclear Station, Nebraska, for a routine inspection.
It is unknown at this time if the drums contain material that is under NRC jurisdiction.
Due to public interest in the area surrounding the ranch, South Dakota has issuea a press release.
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JUNE 25, 1993 ENCLOSURE R
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June 29,L1993 c.
NRR Meetina Notice E
Docket Attendees /
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Date/ Time Number location Purpose Applicant.
NRR Contact
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7/8/93
_50-331 One White Flint North To discuss proposed amendment NRC/IEL&P R. Pulsifer 8:00-12:00 Room 48-13 regarding Spent Fuel Pool Reracking at Duane Arnold.
7/9/93 50-302 USNRC To discuss Crystal River-3 NRC/ INDUSTRY
.C. Grimes 10:00-12:00 101 Marietta St., N.W.
Improved Technical Suite 2900, 29th Ft.
Specifications Implementation Conf. Room Issues.
Atlanta, Georgia 30323 7/15/93 None General Electric Office To discuss the Interim NRC/GE/BWROG/ORNL H. Richings 8:30-2:00 Suite 315 Corrective Actions and details 12300 Twinbrook Parkway of methodology for long term Rockville, MD 20852 solutions.
7/16/93 None One White Flint North To discuss Solution 1-0 NRC/BWROG/0RNL H. Richings-8:30-12:30 Room 4B-13 analyses.
'7/20/93 50-335 One White Flint North To discuss seismic qualification NRC/FP&L J. Norris 8:30 50-250
_ Room IF-19 of mechanical and electrical
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-equipment at.St. Lucie Unit I and Turkey Point Units 3 andL4.
2/3/93 50-220 One White Flint North To discuss proposed permanent NRC/NMPC D. Brinkman 10:00 Room 4B-11 repair methods for control rod drive stub tubes at Nine Mile
-Point Nuclear' Station'Unitul.
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NMSS Meetina Notices m
Docket Attendees /
G; Date/ Time Number Location Purpose Applicant NRC Contact S
6/29 N/A Rockville, MD To attend meeting with NRC N. Orlando Solid Waste Management Industry Representatives Industries' Representa-tives re: Development of pamphlet on-responding to radioactive material being detected in municipal solid waste 7/15 N/A Rockville, MD Discuss the NRC C. Gaskin implementation of the NFS Fitness for Duty Rule B&W-at Category i Fuel Facilities 7/20 N/A OWFN IF-5 NRC/ DOE Quality NRC P. Brooks 9:00a-2:45p Rockville, MD Assurance Meeting 00E-LState of Nevada and local governments 7/27-28
' N/A.
Las Vegas, NV Technical Exchange
- NRC C. Abrams TBD on Exploratory Studies DOE Facilities.(ESF) Title State of Nevada II Design-and Design' and local governments Control 7/29 N/A Rockville; M0 Staff to meet with NRC
- P. Lohaus Senior Vice President Law Environmental, Inc.
of Law Environmental, n,
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Inc. to discuss 10 CFR' E;
Part 61_and implementing h@
guidance
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jX RES Meetino Notices c;
Docket Attendees /
2' Date/ Time Number location Purpose Apolicant NRC Contact 7/6-9/93 N/A Boston, MA RELAPS International Users RELAP5 Users D.Solberg Seminar 7/7-8/93 N/A Holiday Inn Nuclear Safety Research Review NSRRC,.
G.Sege Bethesda, MD Committee meeting - General E'.Beckjord, review of NRC research programs other NRC staff, public 7/12-14/93 N/A Palo Alto, CA Meeting w/EPRI on Future MACE NRC, EPRI F.Eltawila Tests 10/20-22/93 N/A Boston, MA Conference on Achievements of NRC,OECD/NEA, A. Rubin the THI-2 Vessel Investigation-Utilities / Industry, Project, sponsored by OECD/NEA OECD members, and NRC Public p1 8
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June 25, 1993-Office of State Programs Meetina Notices Docket Attendees /
s Date/ Time Number location Purpose Applicant SP Contact U$
7/7/93 50-155 Glen Ellyn, IL
' Meet with Michigan Michigan PSC R. Lickus Public Service Commission staff on Big Rock Point 7/3/93 NA Jefferson City, M0 Meeting with Missouri EP Officials R. Lickus emergency planning officials 7/11-13/93 NA Madison, WI Midwest Legislative States R. Lickus Conference 7/12-13/93 50-220 Oswego, NY Nine Mile Point EP Officials M. Miller 50-410 Emergency Planning Exercise 7/12-15/93 NA Washington Washington Radiation State J. Hornor Control Program Visit 7/12-16/93 NA Montgomery, AL Alabama Radiation State R. Woodruff Control Program Review 7/13-15/93 50-395 Parr, SC Summer EP Exercise EP Officials R. Trojanowski 7/19-8/20/93 NA Oak Ridge, TN Health Physics Course States _
D. Sollenberger 7/21-23/93 NA Sante Fe, NM LLW Forum LLW Officials S. Salomon 7/25-29/93 NA
' San Francisco, CA NARUC Summer Meetings PUCs S. Droggitis og 7/26-28/93 NA Newhill, NC Harris' Emergency' EP Officials.
R.'Trojanowski fi Planning Exercise O
EE 7/26-30/93 NA Burlington, MA Industrial. Radiography States-J. Myers
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tg Reaion I Meetina Notices
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Docket Attendees /
Date/ Time Number location Purpose Applicant NRC Contact m
07/15/93 50-293 Region I To discuss Boston Edison Selected NRC Staff Kelly 11:00 a.m.
Organization Changes and Members and Licensee the Licensee Assessment of a recently completed Re-fueling Outage 07/16/93 50-244 Region I Enforcement Conference on Selected NRC Staff Lazarus 10:00 a.m.
Corrective Action for Members and Licensee Service Water Valve Failures 07/21/93 50-289 Region I 10 R Outage Briefing Selected NRC Staff Rogge 1:30 p.m.
50-320.
Members and Licensee 07/22/93 50-309 Region 1 Radiological Protection Selected NRC Staff.
Lazarus 10:30 a.m.
Program and Refueling Members and Licensee Activities P
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E Recion II Meetina Notice
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Docket Attendees /
l Date/ Time Number location Purpose Acolicant NRC Contact E
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w 06/28/93
'0ak Ridge, TN Com. Remick is touring Dir of DRSS, Stohr-Oak Ridge National Lab RII Staff and for site familiarization Licenrae 06/29/93 Oak Ridge, TN Com. Remick is touring Dir. of DRSS, Stohr Quadrex and Scientific RII Staff, and Ecology Group, Inc. for Licensee site familiarization 06/30/93 50-062 RII Office Enforcement Conference RA, RII Staff Ebneter.
9:00 a.m.
University of Virginia and Licensee l
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07/01/93 50-338 Mineral, VA SALP Presentation -
RA, RII Staff Ebneter 2:30 p.m.
50-339 VEPC0 - North Anna and Licensee 07/07-08/93 Colony Square Operability / Degraded RII and HQ Staff, Ebneter 8:00 a.m.
Hotel Equipment Conference and Utility Personnel Atlanta, GA 07/13/93 70-143 RII Office Enforcement Conference RA, RII Staff Stohr 10:00 a.m.
Nuclear Fuel. Services and Licensee l
07/15/93 50-269 Seneca, SC Presentation of Certs.
.Dir. of DRP,-
Herschoff l
6:00 p.m.
50-270 to Newly Licensed RII Staff, and 50-287 Operators at Oconee-Duke Power Co.
Managers and Operators l
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RIII Meetina Notice jg
-g Docket Attendees 23 Date/ Time Number Location Purpose Applicant NRC Contact 7/07/93 50-440 Site Cleveland Electric Director, Division of-Greenman Illuminating Co.
Reactor Projects Routine Management Meeting (Perry) 7/09/93 50-237 Site Commonwealth Edison Regional Administrator Greenman 50-249 Company (Dresden)
Selected Staff-Routine Management-Meeting 7/13/93 50-461 RIII Illinois Power Co.
Director, Division of Greenman Routine Management Reactor Projects Meeting (Clinton) 7/16/93 50-456 Site.
Commonwealth Edison Director, Division of Greenman 50-457 Company - (Braidwood)
Reactor Projects Management Meeting.
7/20/93 50-315 Site-Indiana Michigan:
Deputy Regional' Administrator Greenman Power Co.
Selected Staff (D. C. Cook) SALP.
Presentation l
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June 25, 1993 Es Reaion IV Meetina Notice G;
Docket Attendees /
NRC 3
23 Date/ Time Number location Purpose Applicant
[ontact 6/30/93 30-02392 RIV Enforcement Conference Columbus Hospital C.Cain 1:00 7/7/93 50-313;
.RIV ANO management discuss Entergy B. Beach 10:00 50-368 ANO performance 7/13/93 50-498; RIV FWIV Bypass-. Valve Oper-Houston L&P B. Beach 9:30 50-499 ability (South Texas)
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