ML20011F534
| ML20011F534 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1990 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-900223, NUDOCS 9003060227 | |
| Download: ML20011F534 (34) | |
Text
Fcdb2 j
I February 28, 1990 For:
The Commissioners 1
From:
James L. Blaha, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 23, 1990 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure A
Nuclear Reactor Regulation Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
Governmental & Public t.ffairs E
General Counsel F*
Administration G
Information Resources Management H
Controller I*
Personnel J
Small & Disadvantaged Business Utilization & Civil Rights K*
Enforcement L
Consolidation M
Regional Offices N
Executive Director for Operations 0*
Items Addressed by the Commission P*
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
I external distribution)
- No input this week.
ames L. Blaha, Assistant for Operations ffice of the Executive Director for Operations
Contact:
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James L. Blaha, OEDO 492-1703 I
9003060227 90022e WL 69%@N il
1 HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING FEBRUARY 23, 1990 1
Accelerated Corrosion of Oyster Creek Containment Structure Af ter the discovery of corrosion in tL sand cushion region of the steel drywell at Oyster Creek Plant in 1986, GPUN, the licensee, has comitted to conduct UT thickness measurements of the drywell shell at outages of oppor-tunity (whenever a drywell entry is planned or required). Such measurements were performed in September 1989 and again in the week of February 4,1990.
Onthebasisofthedatacollected,thelicenseecomputedthecorrosionrate and found the rate to be 9.5 to 10 mils per year which is twice the rate 6t drywell elevation 51' region established on the basis of previous UT measure-i ments. Based on the accelerated corrosion rate, the licensee has estimated that the drywell would meet the minimum thickness requirements for its con-taiurent structure until June 1991 instead of June 1992 as previously estab-lished. A conference call was made between the licensee, NRC Headquarters and Region I staff on February 14, 1990. The staff's basic concern is the uncer-tainty regardir.g the actual condition of the drywell. The licensee has been requested to provide detailed information on the recent UT measurements and an action plan that addresses the staff's concern.
NRC/ DOE Quality Assurance Meeting On February 15, 1990, representatives of the Division of High-Level Waste ManagementheldameetingwiththeDepartmentofEnergy(DOE)andtheState of flevada to discuss items of mutual interest related to the Quality Assurance (QA) progreu for the high-level waste repository. Among the items discussed were schedules and milestones resulting from the December 1989 DOE " Report to Congress on Reassessuent of the Civilian Radioactive Waste Management Program"
-and the pending reorganization of the DOE Office of Civilian Radioactive Waste tianagement. The staff and DOE representatives agreed upon the steps needed for tiRC to accept the DOE QA plans and procedures by September 1990. However, DOE and the staff aise need tc reach agreement on the specific actions needed to determine implementation of the programs to completely resolve NRC's Site Characterization Analysis QA objection and to complete NRC's acceptance of DOE's QA program. The process for the development of the QA programs for the DOE vitrification projects and the proposed NRC/ DOE workshop on QA was also discussed. The next QA meeting will be held on March 21, 1990.
Mitigation and Adaptation Technologies for Global Climate Change i.
The liRC was recently asked by the White House Science Advisor Dr. D. Allan k
Bromley, to participate in an interagency working group to coordinate research
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activities on Mtigation and Adaptation Technologies for Global Climate Change, l
This participation has been assigned to RES and Dr. R. Wayne Houston has at-tended the first two meetings of the group, on February 1st and February 22nd.
L A brief Comission paper is in preparation for transniittal in mid-March to make a recommendation on the future participation and role of the NRC in this activity.
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Office of Nuclear Reactor Regulation i
Items of Interest heek Ending February 23, 1990 l
Sta'ndard Technical Specifications A meeting will be held February 26-27, 1990 between the staff and the NSSS 0.ners Groups working on the development of new Standard Technical Specifica-i tions. The purpose of the meeting is to arovide clarification of NRC staff
-i coments on the chapters submitted by eac1 of the Owners Groups.
Seabrook Unit 1 On February 20, 1990. the licensee reported that all the tests scheduled to be performed during Mode 3 have been completed except the performance of the rod drop test. This test is expected to be completed by February 22, 1990.
The most significant Mode 3 testing activity was the successful demonstration of the operability of the emergency feedwater system.
At the present time, the licensee plans to remain in Mode 3 until it is known what the Commission decision is on the authorization to issue the full power license.
The Office of the Secretary of the Comission has prepared the Federal Register
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notice for a March 1,1990 Comission meeting.
In this meeting, there will be an uffirmation/ discussion and vote on:
Seabrook imediate effectiveness decision / full power license.
CommissionorderinSeabrookAppealBoarddecision(ALAB-922) certifying a question as to the " reasonable assurance standard".
River Bend Station i
TheAugmentedInspectionTeam(AIT)dispatchedtoRiverBendStationon february 12, 1990, concluded its investigation on February 16, 1990. A final report is to be issued in about 3 weeks.
Some of the conclusions discussed at the exit r:eeting on February 16,1990were(1)thelicenseehasstillnot-determined the cause of the event (i.e., what caused the battery charger spike and whether this spike is abnormal or whether the TOPAZ inverters acted ab-normally); (2) there is no load list for the TOPAZ inverters that will enable a determination of what loads will be lost u)on trip of these inverters; and (3) the LPCI injection valves, MOV-42 B&C whici opened for about 2 minutes, should be capable of closing against an intersystem LOCA differential pressure based on the torque switch settings.
Three hile' island Unit 2 1
l Examination of the " boat" sample taken from the E-6/E-7 core grid location L
revealed that there was no cracking of the carbon steel base metal.
The exami-E nation was conducted at the Argonne National Laboratory (ANL) by metallurgists from ANL and the NRC's Office of Nuclear ktgulatory Research. The previous L
' FEBRUARY 23, 1990 ENCLOSURE A
visual indications of 2 to 3 inch deep cracking in the end of the boat sample were apparently an artifact of the cutting process used to obtain the sample.
The microscopic. examination showed tearing of the 3/16 inch thick stainless steel clad and very minor melting / dissolution of the base metal. The melting /
dissolution was limited to a layer less than 1 mil in thickness.
'Thus far in the vessel inspection program, 8 boat samples have been obtained.
Additionally,14incoreinstrumentpenetrations(IIP)havebeencutoffap-proximately 2 inches above the reactor vessel cladding.
Instrument penetration R-7 had a glob of resolidified corium attached; the glob separated as they were placed in an inner shipping container. The next phase of tie vessel inspection l"
program is to obtain samples of the junction of the IIP bases and the reactor vessel ws11.
The planned sample locttions include core grid location E 7, where the most pronounced tearing (" cracking") of the stainless steel cladding hes been observed.
Accelerated Corrosion of Oyster Creek Containment Structure Af ter the discovery of corrosion in the sand cushion region of the steel drywell at Oyster Creek Plant in 1986, GPUN, the licensee, has comitted to conduct UT thickness measurements of the drywell shell at outages of oppor-tunity (whenever a drywell entry is planned or required). Such measurements were performed in September,1989 and again in the week of February 4,1990.
On the basis of the data collected, the licensee computed the corrosion rate ano four.d the rate to be 9.5 to 10 mils per year which is twice the rate at drywell elevation 51' region established on the basis of previous UT measure-ments. Based on the accclerated corrosion rate, the licensee has estimated that the drywell would meet the minimum thickness requirements for its con-tainment structure until June 1991 instead of June 1992 as previously estab-lished. A conference call was made between the licensee, NRC Headquarters and Region I staff on February 14, 1990. The staff's basic concern is the uncer-tainty regatding the actual condition of the drywell. The licensee has been requested to provide detailed information on the recent UT measurements and an action plan that addresses the staff's concern.
Assi.;ssment of Cooper-Dessemer Emergency Diesel Generators at Susquehanna i
Additional tests were conducted by Pennsylvania Power and Light Co. (PP&L) on the Susquehanna "E" diesel generator on February 16, 1990, to determine appro-priate actions which need to be taken to bring the combustion air temperature to within the manufacturers recommended limits.
Earlier tests on February 12 had indicated that lower enmbustion air temperatures does degrade engine per-formance which tends to support the vendor theory regarding root cause. Test data obtained during hot and cold tests on February 16 confirmed this trend, but the deviation between cylinders remained within the reccmmended range. The tests could not be conducted at the 30-40"F range due to the prevailing environ-mental cor.ditions. At these temperatures, engine performance is likely to degrade significantly. The data obtained to date, however, is sufficient to warrant implementation of permanent combustion air temperatures control measures. The staff recommended that the licensee move in that direction.
' FEBRUARY 23, 1990 ENCLOSURE A 1
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r NTOL AND RESTART SCHEDULE 2/23/90 I.
Schedule for NTOL plants:
INITIAL FULL PLANT LOW POWER CRITI-COMMISSION POWER AUTHORZTN CALITY BRIEFING AUTHORZTN COMANCHE PEAK 1 2/8/90C 3/28/90E 4/2/90E 4/11/90E i
SEABROOK 5/26/89C 6/13/89C 1/18/900 3/90E 1
II. Schedule for RESTART plants:
C0tNISSION STATUS PLANT SHUTDOWN BRIEFING PLANT RESTART BROWNS FERRY 2 9/15/84C
'8/90E 9/90E NIllE MILE POINT 1 12/19/87C 5/90E*
5/90E I
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- Staff hold restart decision
- FEBRUARY 23, 1990 ENCLOSURE A n
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Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending February 23, 1990 SAFEGUARDS AND TRANSPORTATION International j
International Safeguards Inspection at Babcock,and Wilcox (B&W) Fuel Company On February 19, 1990, the International Atomic Energy Agency conducted a
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routine safeguards inspection at the B&W Fuel Company in Lynchburg, Virginia.
The scope of the inspection included an audit of nuclear materials accounting ledgers, attribute measurements on uranium dioxide pellet receipts, and weighing and sampling of uranium dioxide pellets for destructive analysis at the Seibersdorf Analytical Laboratory in Austria.
Short Notice Random Inspection at General Electric (GE)
On February 21, 1990, the International Atomic Energy Agency initiated a short notice random inspection at GE Fuel Fabrication Plant in Wilmington, North Carolina. The inspection will entail an audit of the nuclear materials accounting ledgers, enrichment measurements on uranium hexafluoride cylinders using nondestructive assay, weighing and sampling uranium dioxide powder and pellets for destructive analysis at the Seibersdorf Analytical Laboratory in Austria.
Domestic Indeoendent Spent Fuel Storage Facility by Public Service Company of Colorado TFSCO) Fort St. Vrain Division of Safeguards and Transportation staff met with representatives of PSCC on February 15, 1990, to discuss the physical security measures to be employed at the proposed Independent Spent Fuel Storage Facility to be located
'near the Fort St. Vrain site. PSCC provided information concerning maintaining the spent fuel at a self-protecting level of radiation over an extended period.
They alsu reported on a study which, when finished, will provide offsite/onsite release projections in the event of a violent fuel disruption. The presen-tation also included specific physical security measures designed tu raeet the requirements of 10 CFR 73.50.
In a related matter, PSCC and Nuclear Fuel Services (NFS) are making preparations to ship the remaining unirradiated fuel segment to the NFS-Erwin site.
Package Supplier Inspection On February 13-14, 1990, a follow-up quality assurance inspection was conducted at the Pacific Nuclear Systems, Inc. (NUPAC).Trupact Assembly Facility in Carlsbad, New Mexico by an NRC staff member supported by a radiography specialist I
from Idaho National Engineering Laboratory. The inspection focused on the 1
I corrective actions implemented by NUPAC in response to the findings of an ear-y lierinspection(September 26-28,1989) concerning radiographic indications I
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FEBRUARY 23, 1990 ENCLOSURE B
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(cracks, porosity, slags) in the welds of. the Trupact !! containers. The inspection team noted that the grinding process used to remove certain weld defects had reduced the wall thicknesses to less than nominal values, and that NUPAC had accepted these repairs through Quality Discrepancy Reports (QDRs).
In a telephone conversation on February 16, 1990, NUPAC was advised that the use of QDRs to accept the repairs may be inappropriate. NUPAC stated that they i
would confirm in writing that the containers in question will not be released until the matter is resolved.
INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety Allied-Signal. Inc. - Exothermic Reaction in UF Cold Trap l
g On February 18, 1990, Allied-Signal reported an exothermic reaction in a heated cold trap containing uranium hexafluoride (UF ) at their UF conversion facility 6
g in Metropolis, Illinois. The reactidn caused an unusual increase in tempera-ture and pressure in the cold trao and an abnormal increase in weight and pres-sure in two distillation feed tanks. Cold traps are routinely heated to transfer 11 quid UF to the feed tanks. UF is held in these tanks prior to vaporization andpurif,icationinthedistillatkoncolumns.
The licensee suspects that the heating medium, ethylene glycol and water, leaked into the cold trap and caused the adverse teaction. The incident did not result in a release of uranium to l
the environment. However, some material was transferred through relief lines to the surge and dump tanks.
l On February 20, 1990, a Region !!! inspector was dispatched to the facility to review the incident. Next week, additional NHSS and Region III inspectors will be sent to the facility to monitor the licensee's recovery activities.
The licensee will confer with the NRC staff prior to taking safety-significant corrective actions.
HIGH-LEVEL WASTE MANAGEMENT NRC/ DOE Quality Assurance Meeting On February 15, 1990, representatives of the Division of High-Level Waste Management held a meeting with the Department of Energy (DOE) and the State of Nevada to discuss items of mutual interest related to the Quality Assurance (QA)programforthehigh-levelwasteiepository. Among the items discussed were schedules and milestcnes resulting from the December 1989, DOE " Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program" and the pending reorganization of the DOE Office of Civilian Radioactive Waste y
Management. The staff and DOE representatives agreed upon the steps needed for NRC to accept the DOE QA plans and procedures by September 1990. However, DOE and the staff also need to reach agreement on the. specific actions needed to determine implementation of the programs to completely resolve NRC's Site Characterization Analysis QA objection and to complete NRC's acceptance of DOE's QA program. The process for the development of the QA programs for the DOE vitrification projects and the proposed NRC/ DOE workshop on QA was also discussed. The next QA meeting will be held on March 21, 1990.
FEBRUARY 23, 1990 ENCLOSURE B
a Office of Nuclear Regulatory Research l
Items of Interest Week Ending February 23, 1990 Containment Performance and Protection from Radiation NationalCouncilon'RadiationProtectionandMeasurements(NCRP) Report on Hot Particles" On February 7, 1990, the National Council on Radiation Protection and Measure-ments (NCRP) provided the RES staff with a galley proof copy of a new report i
entitled:
" Limits for Exposure to ' Hot Particles' on the Skin," NCRP Report No. 106. The NCRP report should be printed and available in about 2 months.
Hot particles are small (usually microscopic) radioactive particles that can produce high' doses in small volumes of tissue, particularly if they come in contact with a worker's skin. The advent of increasingly sensitive radiation detectors at nuclear power plants since 1985 ircreased awareness of the poten-tial f0r worker exposure to these particles. The potential health effects af high',y nonuniform doses to very small volumes of skin tissue are quite dif-ferent in natt,ro from those caur.ed by the more unifem ('oses on which NRC regulaticns are based. A'; a result, RES requested the NCRP in March 1087 to provide guidance for the case of hot particles on the skin. This report responds to that request. The NCRP recommer.dation is that, for the special case of a particle in contact with the skin, the exposure be limited to tu t associated with ten billion beta particles emitted from the particle. Inis limit may also be expressed as 10 gigabecquerel-seconds or 75 microcurie-hours.
An exposure of 75 microcurie-hours to the skin from a point source fuel par-ticle would deliver 400 to 600 rads to a 1 square centimeter area of the skin's i
basal layer. The actual dose would depend on the age and composition of the particle.
The staff is currently preparing an Advance Notice of Proposed Rulemaking for the Hot Particle issue using the NCRP report as a basis. NRR has prepared an interim standard for exposure from hot particles on the skin which is currently before the Commission.
Mitigation and Adaptation Technologies for Global Climate Change The HRC was recently asked by the White House Science Advisor, Dr. D. Allan Bromley, to participate in an interagency working group to coordinate research activities on hitigation end Adaptation Technologies for Global Climate Change.
This participation has been assigned to RES and Dr. R. Wayne Houston has at-tended the first two meetings of the group, on February 1st and February 22nd.
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A brief Connission paper is in preparation for transmittal in mid-March to make a recommendation on the future participation and role of the NRC in this activity.
Scientific Integrity and Misconduct Policies and Procedures Meeting On February 22, 1990, the NRC Office of Nuclear Regulatory Research (RES) was invited to participate in the second meeting held by Office of Science and FEBRUARY 23, 1990 ENCLOSURE C
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Techno1cgy (OSTP) on the subject of scientific misconduct. Dr. Robert L.
Shepard, Senior Research Engineer, represented RES at the meeting which was l
held at the New Executive Office Building, 725 17th Street, NW, Washington, DC.
The initial meeting was held January 31, 1990, and consisted of participants from the National Institute of Health (NIH), the Public Health Service (PHS), ),
the Office of Scientific Integrity (OSI), the National Science Foundation (NSF the Veterans Administration (VA), the Department of Agriculture (USDA), the Department of Defense (D0D), and the Environmental Protection Agency (EPA).
This meeting involved the participants giving a description of their agency's policy or practice for handling allegations of scientific misconduct.
At the conclusion of the January 31, 1990 meeting, the group suggested that other agencies such as NOAA, NASA and USGS which did not attend thould be invited to participate in the next series of. meetings.
In the specific case of NRC, the group was informed that while to date no allegations of scientific misconduct have been raised on any of the NRC's Extramural research projr: cts, the Agency will pursue the questions of
-scientific mistoadur.t through the Office of the Inspector General if such t
questions should arise.
tiost participants agreed that setting government-wide guidelines for dealing
- with miscenduct in science may not be possible. On the other hand, all agreed 7
y the issue needs to be addressed and expect the outcome of the OSTP effort will produce positive and useful results.
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Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending february 23, 1990 Division of Operational Assessment (DOA)
On February 21-22, 1990, IRB staff participated in a nuclear plant analyzer exercise in Region I with Region I staff, INEL and COMEX. This was a tech-nica11y challenging drill involving a realistic plant response under severe reactor accident conditions for members of the Reactor Safety and Protective Measures teams in Region I.
The Director, Technical Training Center attended the Computerized Man-Machine Coramunication portion of the Enlarged Halden Program Group Meeting in Bolkesjo, i
Norway and visited the Halden Man-Machine Laboratory (HAMMLAB) in Halden, Norway c'uring the period of time 2/11-19/90.
The conference sessions on com-puterized man-machine communication featured presentations and some demonstra-tions on computerized operator support systems, experimeatal evaluation of operator support systems, verification end safety assessa,ent of computerized 1
systems and software development tools for process supervis bn and control.
Also featured was the i.ntegrated surnillance and control systems for advancsd l
control R0P.S Simulater (modeling the Loviisa plant ja Finland) operator intere face and capabilities, hardware and software configuration of the MAMMLAB equipment, corcpLteri2cc' operator support systeras not presented at the con-ference, methods of conducting research at the facility, and research subjects available to the Halden Reactor Project staff from the Halden Boiling Water Reector facility.
The Director, Office of Nuclear Reactor Regulation, Director, Office for Analy-sis and Evaluation of Operational Data, and De)uty Director for Research, Office of Nuclear Regulatory Research visited the Tecinical Training Center on 2/20/90 to provide senior management perspectives on plant risk and recognition of severe accident precursors to the TTC staff. The briefing for the TTC staff was held in conjunction with TTC staff training in PRA Applications and Lessons Learned and is part of an overall plan to bring a risk-based culture to the TTC in addition to the existing operationally oriented culture. While at the TTC, the senior managers were given a tour of ITC facilities and briefings on several ongoing TTC projects.
The second Encore 32/9780 computer has been delivered and is undergoing accep-tance testing in the computer room of the simulator for the GE vendor design.
The first Encore 32/9780 computer was previously delivered, tested, and ia-i L'
stalled as part of the permanent hardware configuration for the simulator for w
the B&W vendor design. The addition of these higher performance computers is l
necessary to establish a hardware platform which will support advanced thcrmal hydraulic modeling. This activity is part of an overall plan to upgrade NRC controlled simulators to state-of-the-art capabilities.
Division of Safety Programs (DSP)
In support of a case study on solenoid operated valve (S0V) problems, two AE0D members visited the Salem and Hope Creek plants on February 15-16, 1990.
4 FEBRUARY 23, 1990 ENCLOSURE D
2-Meetings at the plants focused upon the licensee's Reliablity-Centered Main-tenance (RCM) program as it pertained to SOVs. The licensee has undertaken an extensive effort (three calendar years, 220 man-years) to establish an RCH program for 14 systems at each of the Salem plants, and 12 systems at Hope Creek. The licensee's efforts include engineering analysis of industry-wide equipment failure data, in addition to specific failures at Salem and Hope Creek.
The 1988 Accident Sequence Precursor (ASP) report, HUREG/CR-4674, Vol. 9 & 10, was issued on 2/23/90. This report describes and evaluates significant opera-tional events reported by LERs during the calendar year 1988. This report provides t. risk significance perssective of operational data reported by com-mercial nuc1 car power plants in tie United States during the 1988 calendar year. The precursor events provide and highlight significant portions of acci-dent or incident sequences. The report indicatts that five of the seven highest core damap probability precursors (i.e., precursors having estimated condi-tional core damage probability greater than 1E-4) involved common mode failure.
These events illustrate the importance of comon mode failures and the need for con:nnued vigilance in the emas of maintenance, inspection, and testing.
As part of the maintenance Indicator trtal program, AEOD mnt with the manage-ment and staff of the Grand Gulf facility on February 20 21. Ameng the topiG discussed was the licensee's initiative to improve the quality of mainteuer.ce documentation. This initiative is of interest to the trial program partici-pants since accurate ard complete work order doct, mentation is essential to the trending and anclysis of component unavailabilities and the monitoring of maintenance effectiveness. A meeting is scheduled with Northeast Utilities this week that will be followed by a meeting in Chicago, March 8-9, with all trial program participants to summarize the results of the individual plant maintenance discussions.
Preliminary Notification The following Preliminary Notifications were issued during the past week, PH0-ADSP-90-02-A, Tb Electric (Comanche Peak Unit 1), Potential Intimi-n.
dation of Former QC Inspector, b.
PN0-1-90-12, Washington Hospital Center, Therapeutic Misadministration Involving a Cobalt-60 Teletherapy Unit, c.
PN0-I-90-13, Thomas Jefferson University, Diagnostic Misadministration l
withTechnetium-99m(Tc-99m) Involving 10 Patients, d.
PNO-11-90-11, Alabama Highway Department, Stolen Troxler Devices.
I PNO-Ill-90-09, Comonwealth Edison Co. (Quad Cities Units 1 and 2),
e.,
Accidental Discharge of Firearm.
f.
PNO-I!1-90-10, Allied-Signal, Inc., Unexpected Chemical Reaction.
g.
PNO-IV-90-C8A,GulfStatesUtilities(RiverBendStation), Augmented InspectionTeam(AIT) Update.
I FEBRUARY 23, 1990 ENCLOSURE D
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Office of Governmental and Public Affairs 4
Items of Interest Week Ending February 23, 1990 State Programs 4
New Hampshire Radiation Control Program Follow-up Review 4
A followup revitw of the New Hampshire Radiation Control Program was conducted
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i on February 19-22, 1990 in Concord, New Hampshire. The New Hampshire legis16-ture has approved additional staffing and resources for the State's radiation control program for fiscal year 1991 which begins in July. Governor Gregg i
l has indicated that he will sign such legislation. The Director of the New Hampshire radiation control program is authorized to hire the additional staff person prior to the beginning of the fiscal year. These actions by the State should go a long way toward addrcssing many nf the NRC concerns with the Nw l-Hampshire progrn,.
o Meeting with New Jersry 0'ficiais NRC staff rot with officitis from the New Jersey Department of Environmental Protection or, Febreary 22, 1990 in Trenton, New Jersey. The purpose of the meeting ws to discuss the full term operating license process for the Oyster Creek Nuclear Power Plant and other related utters.
North Carolina LLW Authority Chooses Two Sites For Characterization The Southeast LLW Compact has chosen two sites, located in Richmond and Wake /
Chatham counties in North Carolina, for site characterization. Upon completien of the site characterization process, a single site will be chosen.
Rocky Mountain LLW Board Meeting Dean Kunihiro, Region V State Liaison Officer, attended-the Rocky Mountain LLW Board meeting on February 23, 1990 in Las Vegas, Nevada. The Board. discussed the status of unsited States and Compacts 1990 milestone com)11ance, received an update on waste acceptance contracts and conducted other 30ard business.
International Programs International Visitors On Thursday, February 22, Commissioner Rogers met with the Honorable Adolfo Battaglia, Minister of Industry and Trade of the Government of Italy, several members of his staff, officials from the Embassy of Italy, and Dr. Raffaele di Menza, Director of the Washington Office, and North American Representative of the Italian Cortmission for Nuclear and Alternative Energy Sources (ENEA).
The purpose of the meeting was to exchunge views on current energy issues.
21, Dr. D. Bradley of the United Kingdom Nuclear Instal-On Wednesday, February (Nil) met with NRC staff members from the Materials and lations Inspectorate FEBRUARY 23, 1990 ENCLOSURE E
2 Chemical Engineering Branch, the NMSS technical branch, and International Programs.
The purpose of the meeting was to discuss the NRC activities and requirements in the area of water chemistry control, treatment, and effects relevant to waste management and stress-corrosion.
Visit of Korean Delegation A visit of representatives from the Korean Ministry of Science and Technology and the Korea Institute of Huclear' Safety (KINS), originally scheduled for February 20-22, will take place on March 20-22.
The visit was postponed while the Koreen Government determines whether, with the reorganization taking place because of the establishment of the KINS as an independent regulatory body, the appropriate people have been chosen to comprise the team.
I FEBRUARY 23, 1990 ENCLOSURE E
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, Congressional Affairs.
CONGRESSIONAL HEARINGS SCliEDULE (CA)
OCA hhASSIGNMENT DATE TIME WITNESS SUBJECT COMMITTEE COT 1ahan 02/28/90 9:00 Jim Taylor Advanced Eeactors Reps. Lloyd/Morrison Energy Research & Development House Science, Space & Technology
.to G$Gerke 02/28/90 10:30 Non-NRC Security Clearances Civil Service (Sikorski/Morella)
Due Process House Post Office & Civil Service E$
Procedures 00vi & Constl Rights (Edwards /Sensennbrenner 180use Judiciary Gerke 03/01/90 9:30 Non-NRC Equal Opportunity Civil Service (Sikorski/Morella)
Complaint Pro-Heuse Pc-t Offc & Civil Service-cessing Fmpi 07.eartunities (Martinez /Gunderson)
House e r; cation & Labor Combs 03/02/90 9:30 DOE DOE's Civilian Nuclear Senators Johnston/McClure Waste Progran Senate Energy & Natural Resources Combs 03/06/90 9:45 Bernero, Maisch Licensing of Reps. Udall/Hansen Urani'um Enrithment Energy and the Environment Facilities House Interior & insular Affairs Madden 03/21/90 10:00 Commission NRC's FY91 Budge' Reps. Bevill/Myers Subc on Energy & Water Development-House Appropriations Gerke 03/21/90 9:30 Non-NRC Civil Service Pay Senators Glenn/Roth 03/22/90 Reform Senate Governmental Affairs Combs 03/29/90 9:30 DOE DOE's Plan to Op(n Senators Johnston/McClure WIPP Senate Energy & Natural Resources E
P oEE NOTE: The advanced reactor hearing, previously scheduled for March 20, was resr.heduled for February 28.
E' Senate Energy's hearing on DOE's Nuclear Waste Program was postponed from 2/22 to 3/2/90.
Senate Energy's hearing on WIPP was postponed from 3/8 to 3/29/90.
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a Office of Administration Items of Interest Week Ending February 23, 1990 Significant FOIA Requests Received by the NRC For 4-day Period of February 16-- February 22, 1990 Referral from D0J of records relating to the River Bend nuclear power plant.
(Barry Spector of Gerst, Heffner, Carpenter & Podgorsky, F01A-90-71)
Request for a copy of the report regarding the last ins)ection of the close-out survey for Automation Industries (or its successor, Tec) Ops) for the facility locatect in Phoenixville, Pennsylvania. (Scott Baker, The West Company, 5
F0!A-90-72)
Request for copies of final rNc ts on radiatina safety program disperities for (1) Case Wet,terc Reserve Mc.iical Cent <tr and (2) Farris State College.
J (Rodger Manday, $siat Louis Univtr;ity FOIA ')0 73)
Request for records re17trJ to all allegations and HRC's investigation regarding H.A.F.A. Interrational, Inc. (Jeffrey Axelson of Van Grack,Axelson & Williamowsky, P.C.,F01A-90-75)
Request for records on the following matters related to the Rancho Seco nuclear power plant: (1) NRC's investigation of liquid radioactive discharges leading up to the determination to impose penalties upon SMUD, and (2) discharge of radioactive liquid effluent following the assessment of penalties in or about January 1989. (Barry Zimmerman of Friedman, Collard & Poswall, FOIA-90-76)
Request for seven categories of records related to NRC's. investigation of H.A.F.A.
International, Inc. (Jeffrey Axelson of Van Grack, Axelson & Williamowsky, P.C.,F01A-90-77)
Request for co)ies of eight specified records regarding the Shpack Landfill in Norton,Massac1usetts.(JohnCalhoun,TheTravelersCompanies,F01A-90-78) l Req)uest for copies of the following records for the period 1982 to the present (1 all agreements between NRC & OSHA regarding investigations of OSHA-related matters and claims, allegations, or concerns, and (2) any agreements, procedures or criteria to identify which agency has responsibility for such investigations.
(Linda Bauman of Robinson, Robinson, Peterson, Berk,Rudolph, Cross & Garde, F0!A-90-79)
Request for copics of seven specified records, including SECY-88-308, g-SECY-89-224, and SECY-89-369. (Karen Unnerstall of Newman & Holtzinger, F01A-90-80)
FEBRUARY 23, 1990 ENCLOSVRE G
E l
Office of Information Resources Management i
Items of Interest Week Ending February 23, 1990 1.
Code Distribution l
The Plot and Fit (PLOTNFIT) computer code, described in NUREG-1378, was submitted to the National Energy Software Center (NESC). The NESC has completed the process for making the code distributable and is now responding to thirty requests. The PLOTNFIT code is used for plotting and fitting curves to measured or observed data for both extrapolation and interpolation.
The Radiological Assessment System For Consequence Analysis (RASCAL) computer code, described in NUREG/CR-5E47, has completed the preparation process for distribution by the NESC. NESC is now responding to requests for the codes The RASCAL code is a new dose assessinent system for use
~
during responses to emerSencies.
2.
NIH Cost Red,uction A project was initiated to review all online storage costs at NIH exceeding $200.00 per month and to contact the users to determine if the datasets could be moved from public disk space to less expensive private disk packs.
3.
NUDOCS/AD Update The daily transaction update program has been successfully tested and installed on NUDOCS/AD. This will permit the NUDOCS staff to update the database with the previous day's transactions (new accessions and record' nodifications).
The processing transaction files from February 14-23 is expected to be completed by February 26. At this point the database will be current to the previous day of processing, i
FEBRUARY 23, 1990 ENCLOSURE H L
w t
Office of Personnel Items of Interest Week Ending February 23, 1990 Recruitment Efforts Continue NRC representatives traveled to several universities and job fairs during this week to recruit new talent for the Agency. On February 20, Brent Clayton (RIII), Doug Williams (RII),(and Dava Vire111 (RII) visited the University of Cincinnati. Chuck Robinson NMSS), Richard Freudenberger (RI), and Michael Markley (RI) met with students at the University of Lowell on February 21.
SandyJohnson(0P).ChuckRobinson(NMSS),RonBellarny(RI),andJohnJohnson (RI) represented NRC at a minority job fair at the Massachusotts Institute of Technology (MIT) on February 22 aad 23. Fred Shields (0P) and Tim Pollick (NRR) traveled to the University of Missouri at Rolla to discuss employment opportunities with students attending the American Nuclear Society Mid-Western Regional Student Conference on February 22-24.
Frank Elizondo (NRC Recruiting Of ficer), Sandy Johnson (OP), Antoinette Hassey (NRF.), P.K. Epen (RI), and Lester Tripp (RI) 3ttended the Black Engineers Job Fair in Baltimore, Maryland, on February 24, 1990.
Arrivals Jeffrey Main Technical Writer-Editor (PFT), ADM Nancy Campbell, Reactor Engineer (PFT) NRR Denise teach, Secretary (PFT),)NRRRamona Alzarez, Secretary (PFT, OGC SamuelHolland,CriminalInvestigator(PFT),O!G LisaHoston,CriminalInvestigator(OPFT)},OIG Rossana Raspa, Criminal Investigator (PFT 0!G Kevin Roughen, Computer Technician (OPFT), RII Departures Mark Flynn, Contract Negotiator (PFT), ADM DonaldMacKenzie,HealthPhysicist(PFT),GPA Vicki Dempsey, Secretary (PFT), NRR DennisKubicki,Sr.FireProf.ectionEngineer(PFT),NRR ThomasCollins,RadiationSpecialist(PFT),RII I
9 FEBRUARY 23, 1990 ENCLOSURE J
o Office of Enforcement Items of Interest Week Ending February 23, 1990 Significant Enforcement Actions, A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $75,000 was issued on February 20, 1990 toConsumersPowerCompany(Palisades).
The action was based on multiple examples of inadequate design control, failure to follow procedures, and inadequate corrective actions with respect to the design of piping and pipe supports. These deficiencies were considered collec-tively as an indication of a programmatic breakdown in the controls associated with the design of piping and pipe supports.
(EN90-019)-
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of
$2,500 was issued cn Febrtary 22, 1990, to stamford Hospital, Stanford, Connecticut. The action was based on, but not limited to license # s failures to:
secure or maintain surveillance over racioactive materials storc6 in an unrestricted area, perform or adequately perform certain dose calibrator teFts, perform leak tests on sealed reference sources, perform surveys in restricted and unrestricted areas contiguous to rooms containing brachytherapy implant patients, and retain records of daily surveys and properly complete daily and These violations are of concern as % the aggregato, weekly survey records.
they indicate a lack of management oversight of the radation safety program.
The raitigation/ escalation factors in the Enforcement Policy were considered and no adjustment to the base civil penalty was deemed appropriate. The mitigation of 50 percent warranted for prompt and extensive corrective action was balanced by the 50 percent escalation warranted for NRC's identification of the violations.
Application of the other factors in the Enforcement Policy were not deemed appropriate.
(EN90-021) l t
i l
FEBRUARY 23, 1990 ENCLOSURE L
i o
1 Office of Consolidation i
Items of Interest Week Ending February 23, 1990 1
Second Building Status GSA revised its offer to the WFN Partnership for the lease / purchase of Two l
White Flint North (TWFN) 6nd schedulc.1 a meeting for Monday, February 26, 1990, at the Partnership's offices to discuss it. The Director, Office of Consolidation, will attend the meeting.
The GSA Assistant Regional Administrator for Reel Estate indicated to the Director,' Office of Consolidation, that he was preparing a report to the i'
Regional Administrator on the progress of negotiations, the issues, and a schedsle of actions to bring tw process to closure in response to e telephone 1
call from Chairman Carr to Acting General Servie.s Ade1nistrator Austin on Febrtary 15.
The Director, Office cf Consolidatien, received a call f rotn a WFN Partnership at+orney on February 22 soliciting cost infonnation on the cour.ty transit subsidies for NRC employees.
He also requested other information about the 1
Mont90r:ery County Planning Board decisions on traffic n.itigation. These re-quests a)peared to be related to the developer's preparation for the negotia-tions scieduled on February 26.
Handicap Ramps Fabrication of the steel frame for the handicap ramps in the first floor lobby is scheduled to begin the first week of March with installation beginning in the south-side lobby around April 2 and finishing around April 12. The north ramp is scheduled for completion by April 19.
0WFN Cafeteria The Tower Company received revised design and cost proposals on installation of special ducting and exhaust fans for the kitchen grill and fryers from Sigal Construction on February 23. Although fire safety issues appear to
~,
have been resolved, cost issues between GSA and Tower remain.
Assuming these are resolved quickly, it is still possible the cafeteria could be open i
for business in April.
tieetings The Director, Office of Consolidation, attended meetings of the Transportation 1
Action Partnership Executive Committee and the North Bethesda-Garrett Park Citizens Advisory Committee on February 21. On February 20, the Director, Office of Consolidation, provided a tour and information to the new Federal Energy Regulatory Comission Director of Consolidation, Mr. Kenneth Plumb, and members of his staff.
l.
l FEBRUARY 23, 1990 ENCLOSURE M
,o Region !
Items of Interest Week Ending February 23, 1990 1.
CINTICHEM. TUXEDO NY As a result of licensee-identified radioactive contamination in an onsite retention pond, Region I dispatched a team to the Cintichem site on February 9 to monitor the licensee's corrective actions. The team confirmed that the reactor had been shut down, confirmed the licensee's measurements of radionuclides in water, and assured that, after the team's arrival on site, all liquid releases met regulatory limits. The team aise monitored the licensee's actions to identify the source of the contamina-tion leaks.
The licensee started non-deirtructive testing (NDT) of concrete walls in the reactor pool coolant and c6nal sybtems to identify any additional structurs) :leficiencies. 1he h!DT is scheduled to be complettd f a two weeks, at which time additional evaluttions will be conducted tr determine whether the conditions of the NRC Order have been met.
The NRC Team completed its on site activities on February 16. As e result of the reactor shutdown, no new production of radioisotopes is occurring, the needs of the medical community fer ifowever, for the time being,from Cintichem's inventory and by the Norcian radioisotoper are being met Corporation, which operates similar facilitics in Canada. On February 20, the company informed NRC Region I that it had made three discharges from the pond early on Friday, the 9th, that had not previously been called to the NRC's attention. The discharges were made after water samples had been taken for laboratory analysis, but the discharges were made before the analytical results were in hand. Later analysis showed these samples contained the radioactive isotopes iodine-131, iodine-133 and sodium-24.
These are characteristic products from the operation of Cintichem's reactor. Cintichem told the NRC it became aware of the results of its after the third discharge had been testing about 9 a.m. on February 9 completed. After beceraing dware of the presence of radioactivity in the water, the company halted discharges to the reservoir.
I FEBRUARY 23, 1990 ENCLOSURE N
,-o 5+
Region II Items of Interest Week Ending February 23, 1990 1.
Carolina Power and Light Company On February 20, the Regional Administrator, accompanied by selected Region 11 and NRR staff, was at the Harris Nuclear Power Station to present the SALP findings to representatives of Carolina Power and Light Company.
On February 21, the SALP Board Meeting for the Carolina Power and Light Company's Robinson Nuclear Power Station was conducted with representatives from NRR participating.
On February 22, Chairmar, Cerr, accompaniet by the Deputy Regional Adrair.is-trator, visited the Robinscn Nuclear Power Station.
1 1
2.
Virginia Electi_e and Power Conpany 1
On Febrary 21, representatives fiom tLe Virginia Electric and Power Company were in the Region 11 AffirA to discuss improvena ts in their Commitment Tracking Sys*ctr..
1 3.
Duke Pcwer Company a
On February 22, representatives of the Duke Power Company were in the l
Region II Office to attend an Enforcement Conference regarding the in-operability of the IB containment return fan and the circumstances sur-rounding the opening of the power lockout breaker to the fan.
j 4.
Florida Power and Light Company On February 20, the Turkey Point Unit 3, 3B spent fuel pool cooling pump for Turkey Point experienced a seal failure. Approximately 2000 gallons (3 inches on the floor) leaked into the building. All leakage was con-i tained within the spent fuel pool building. There has been extensive
,1 media interest because of a similar event which occurred in August 1988 where cooling water actually leaked out from the building. The August 3
1988 event was reported in the Abnormal Occurrence Report to Congress I
for that period under the classification of other items of interest due l
to extensive media coverage. Unit 3 is currently in a refueling outage and Unit 4 is operating at 100 percent power.
I l
I FEBRUARY 23. 1990 ENCLOSURE N L
j
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Region III l
Items of Interest Week Ending February 23, 1990 1.
Quad Cities _ Nuclear Power Station I
Dr. Carl J. Paperiello, Deputy Regional Administrator, members of the regional and Headquarters staffs, and the resident inspectors met on February 22, 1990, at the Quad Cities Nuclear Power Stetion with i
Assessment of Licensee Performance (SALP) pany to review the Systematic representatives of Coninonwealth Edison Comreport for the Quad Cities Station.
2.
Point Reach Nuclear Plant i
On February 20, 1990, Mr. H. J. Miller, Director, Division of Reacter Safety, and members of the Region III staff participated in a meeting at t
Headquarters with Wisconsin Electric Power Company to discuss engineering issues at the Point Beach Nuclear Plant. The meeting was sponsored by the Office of Nuclear Reactor Regulation for the purpose of understanding the licensee's method of work control, prioritizatico of major ongoing engineering issues, and plans for increasing engineering departme.t l
resources to address the backlog of outstanding actions.
3.
Allied Signal. Inc.
l On February 18, 1990, the licensee reported an unexpected chemical reaction in its uranium hexafluoride processing system resulting in abnormal temperature and pressure increases within the system. The systeu functioned es designed to contain the uranium hexafluoride by relieving to various process relief tanks. There was no' release of uranium hexafluoride outside of the processing system. On February 18, 1990, Region III in conjunction with the Office of Nuclear Material Safety and Safeguards (NMSS) received commitments from the licensee necessary to prevent recurrence before root causes have been identified.
A Region III inspector was on site February 20 and a materials section chief was on site February 21 to review this event and the licensee's recovery activities. An Augmented Inspection Team (AIT) headed by Region III is being dispatched on February 27 to review the sequence of events and causal factors contributing to equipment or processing problems which led to the unexpected chemical reaction.
The AIT will be supported by several representatives from the Office of Nuclear Material Safety and Safeguards. At this time, the processing system is being maintained in a stable condition while the licensee develops a plan to transfer the contaminated material.
4.
Fermi 2 Nuclear Plant The Division of Reactor Projects and the Division of Reactor Safety met with representatives of Detroit Edison Company on February 22, 1990, to discuss the licensee's corrective actions to weaknesses identified through the maintenance team inspection report and the licensee's Design Basis Task Force program.
FEBRUARY 23, 1990 ENCLOSURE N
,y? :,
n-4 Region IV Items of. Interest Week Ending February 23, 1990 1.
Sequoyah Fuels The licensee informed the Region IV office that on the afternoon of Friday, February 16, 1990, a fluoride sludge retention basin overflowed.
The licensee calculated that about 4200 gallons of treated waste water was released. The release flow by)assed the monitoring point. The licen-see' stated, however, that during t1e release the discharged waste water was-diluted with the runoff water from recent rains. Therefore, the licensee estimates that the pH of the waste water discharging to the Robert S. Kerr Reservoir was essentially neutral. The pH of the basin waste water is usually about 12.9. The licensee's measurements of the-pH along various points in the discharge path on the licensee's property ranged from 12.1 down to 7.5.
The licensee believes that the uranium content of the released water was less'than 0.01 mg/1.
(This content is significantly below the 10 CFR Part 20 limit for unrestricted MPC for naturaluranium.) The licensee expects no significant environmental im-pact as a result of the release.
licensee informed NRC of the event at about 4:00 p.m. on February 16, 40.
The licensee notified the EPA and the state of Oklahoma inasmuch the fluorido content of the release exceeded the state license require-cant!..
2.
Dz ango UMTRA Project The Director of URF0 and select members of his technical staff met on February 21, 1990, in Albuquerque, New Mexico, with representatives from the Department of Energy and the State of Colorado to discuss the status of the Durango UMTRA Project. Major topics included DOE's proposed approach to ground-water cleanup at the disposal site and the removal of trapped construction waters in the disposal cell.
- 3..
VA Medical Center, Houston, Texas An enforcement conference was held with representatives of the Veterans Administration Medical Center, Houston, Texas, on February 22, 1990, to review the findings related to an inspection conducted at the licensee's facility on December 11-13, 1989, and January 8-10, 1990. The inspection included a review of the broad nuclear medicine, research, and teletherapy _
programs at the institution. The conference focused on.the lack of manage-ment control of these programs which resulted in a relatively large number of identified violations. The most significant violations identified related-to the use of radioactive gas and volatile radioiodine.
' FEBRUARY 23, 1990 ENCLOSURE N
.p' y
Region V Items of Interest Week Ending February 23,1990 1.
Rancho Seco Nuclear Generating Station a.
On February 20, 1990 Region V was contacted by Federal Emergency ManagementAgency(FEMA),RegionIX regarding the need for offsite participationduringthenextannualemergencyexerciseatRancho Seco. The exercise, scheduled for December 1990, requires offsite participation. The FEMA representative stated that the local officials were in the process of preparing their budgets and that he had been contacted by the local officials regarding their need to budget for the December exercise. The FEMA representative wanted to discuss the NRC's position on this matter and the current status of the Rancho Seco Emergency Plan.
Region V stated that, based on the licensee's December 1989 Emergency Plan revision, an annual exercise would be required and that it would probably be appropriate for the offsite agencies to budget for their participation. This position was coordinated with the Nuclear Reactor Regulation staff. We expect FEMA and local officials will continue to question the staff on this matter, b.
The licensee has submitted exemption requests from the requirements of.10 CFR Part 50, Appendix J (leak rate testing of containment isolationvalves)and10CFR50.71(updateoftheFSAR)inletters dated October 20, 1989, and September 25, 1989, respectively. The NRC staff is reviewing the acceptability of these requests and actions necessary to resolve the issue of current compliance with these requirements. Other areas in which the licensee has or intends to request additional relief include: Inservice Inspections required by ASME Section XI, 10 CFR 50.49 for environmental qualification of electrical equipment, and simulator training and testing.
System layup efforts continue with the reactor coolant system and c.
secondary side of the steam generators being put in a wet layup condition. The control rod drive system layup has progressed to the point of disconnecting the power supply, d.
On February 16, 1990, high winds damaged the roof of the Interim Ra M ste Storage Building used to store low level contaminated waste and. equipment. Damage was done to approximately 80 percent of the waterproofing material and ventilation fans and ductwork mounted on the roof which allowed approximately 2,900 gallons of rainwater to collect in the building sump. Activity level of the collected water was below the maximum MPC for unrestricted use; however, no water was released outside the building during the event, e.
The SMUD Board / Rancho Seco Committee met on February 21, 1990, to discuss Rancho Seco issues including the status of the study to dispose of the spent fuel and options of converting Rancho Seco to FEBRUARY 23, 1990 ENCLUSURE N
t o=
utilize other fuels. Discussions concerning the disposal of spent fuel highlighted meetings to be held with DOE representatives on.
February 27,.1990, and with NRC representatives on February 28, 1990.
The conversion options discussed were gas fired boiler, combustion turbine / generator, and solar electric.
2.
Portland General Electric Company Portland General Electric Company notified Region V of a potential strike hy the International Brotherhood of Electrical Workers, whicn rey occur.
any time after March 5, 1990. The licensee is currently in negotiation with the Union. The licensee's contingency plans for the strike have been reviewed and follow-up will continue.
4 i
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FEBRUARY 23, 1990 ENCLOSURE N
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NRR MEETING NOTICES 5Q February 23, 1990 0
APPLICANT /
g DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/6/90 50-295/
White Flint _ Bldg.
' Discuss the. issues related to NRC/CE C. Patel 9:00-12:30 304 Room 88-11 reactor vessel integrity for Zion Units 1 and 2.
3/7/90 50-267 White Flint Bldg.
Discuss Fort St. Vrain status NRC/PSC P. Erickson 1:30-3:00 Room 10B-13 and plans for final defueling and decomissioning.
3/8/90 50-255 White Flint Bldg.
Discussion of Consumers Power-NRC/ Consumers A. DeAgazio.
9:00-5:00 Room 14B-11 Company program relating to Power Co.
pressurizer pilot operated' relief valves and block valves.
3/15/90 50-269/
McGuire Nuclear Plant Discuss the status of various NRC/GPCo L. Wiens 8:30-4:00 270 licensing activities and safety Duke Power Co.
initiatives at Duke Power Company's and Georgia Power Company's nuclear stations included in PDII-3 area of responsibility.
- Copies of sumaries of these meetings will be made publicly available and E
placed in the respective docket file (s)-in the NRC
'ocal public document
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rooms.
eny A listing of these meeting notices can be obtained y -
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APPLICANT /
.'y DATE/ TIME NUMBER LOCATION
-PURPOSE.
ATTENDEES NRR: CONTACT 3/21/90 50-382 White Flint Bldg._
' Discuss; licensees response to-NRC/LP&L D. Wigginton-9i00 Room 98-13 NRC questions transmitted by.
letter dated July 27,'1989,
'regarding proposed amendment-to revise the control room heating, ventilation and air conditioning technical speci-fications.
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. Attendees /
f Docket Date/ Time Number Location Purpose Applicant NRC Contact l
2/27 70-371 OWFN To discuss pre-licensing NMSS
- 5. Soong 9:30 a.m.
14-B-13 matters with UNC Naval RI
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Products Division-UNC-3/1 70-925 OWFN To discuss Cimarron NtiSS D. Hurt.
8:00 a.m.
6-B11 site investigation Kerr-McGee report with Kerr-McGee Division of High-Level Waste Management Attendees /
Docket Date/ Time Nunber Location Purpose Applicant NRC Contact-K.Stablein 3/6 DOE /Forrestal-Technical Exchange NMSS on Exploratory Shaft DOE siting issues-State of Nevada 9
3/21 Rm 6110 MNBB NRC/ DOE QA Meeting MSS M. Delligatti DOE P
State of Nevada 8
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. Division of Low-Level Waste Management and Decommissioning.
3 LDocket Attendees /
Date/ Time Number-Location-Purpose Applicant NRC Contact-
. p 2/25-3/1 Tucson,'AZ Was'te Management NMSS L. Pittiglio.
90 Conference 3/21-22 Palo Alto, CA To attend meeting with NMSS
- J. Sumeier.
DOE State' Technical i
Coordinating Committee
~ Division of Safeguards and Transpcrtation Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact-None
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' Number-Location Purpose-Applicant
, NRC Contact.-
ro Director's Office Nuclear Safety Research Review Committee (NSRRC) Meetings-3/19-20/90 San Antonic,'TX NSRRC. Waste Disposal R. Shepard Subcomittee meeting
- 492-3723.
Division of Engineering 3/20-21/90 Bethesda Ramada Inn Nuclear Plant Aging J. Vora Bethesda, MD-Research (NPAR): Research 492-3854 Review Group meeting Division of Systems Research 3/5/90 14-B-11, WFN Information meeting on NRC,NUMARC,1NPO,.
F. Coffman the Human Factors EPRI 492-3520-Regulatory Research
-Program 3/8-9/90 Washington, DC1 Attend NUREG-1150 Peer J. Murphy &:
M. Cunningham Area Review Committee Meeting M. Cunningham 492-3965 3/8-9/90 8-B-11,.WFN Human Factors Workshop T. Ryan,.RES for NRC Supervisors / Staff
.492-3554.
[ Workshop to be conducted R.'Eckenrode,NRR.
E by Lawrence Livermore 492-1105 P
' National Lab. Workshop 8
limited to 25 participants.
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.2 24 Docket'
. Attendees /
Date/ Time Number Location Purpose Applicant.
.MRC-Contact"
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03/06/90 50-244 RI Office
-Management Meeting Licensee.and Selected' McCabe o
9:00 am RG&EC - Ginna RI Staff Members O
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,,jj RII MEETING HOTICE si
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ATTENDEES /
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DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT
'NRC CONTACT.
M US 02/27/90 RII Office Enforcement Conference Licensee, RA and selected Ebneter 10:30 a.m.
VEPC0 - N. Anna facility RII staff members 03/01/90 Yankeetown, FL Operator Certficate Licensee, RA and resident Ebneter 6:30 p.m.
Presentation to the inspectors Crystal River Operators 03/15/90 New Hill, NC Commissioner Rogers at Commissioner, Tech. Asst.,
Milhoan Harris facility for and Deputy RA site familiarization 03/16/90 Southport, NC Commissioner Rogers at Commissioner, Tech. Asst.,
Milhoan 3runswick facility for and Deputy RA site familiarization-03/19/90 RII Office
.Surry Self-Assessment Licensee and selected Ebneter 1:00 p.m.
Meeting RII staff members 03/20-23/90 RII Office Resident Inspectors' Senior and Resident Reyes Meeting Inspectors and selected guest speakers E
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. Docket
' Attendees 3
Date/ Time Number Location Purpose Applicant-NRC Contact ~
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02/27/90 50-331' Region III Iowa Electric Light &
Licensee, Regional Greenman-m E
10:00 am Power, Duane Arnold -
Administrator and selected Management Meeting-members of RIII Staff 02/27/90
'50-315 Region III Indiana and Michigan Licensee,- Deputy Regional
~Greenman l
1:00 pm 50-316 Electric Company, Administrator and selected D. C. Cook -
members of RIII Staff
(
Enforcement Conference 02/27/90 50-483 Region III Union Electric Company, Licensee, Director, Division Norelius 1:00 pm Callaway
. Enforcement
.of Radiation Safety and Conference Safeguards and selected members of RIII Staff ~
03/8-9/90 Region III National 191SS -
Office Nuclear Materials Morelius Program Review Safety and Safeguards 03/15/90 50-315 D.C. Cook Plant Indiana and Michigan Licensee, Regional Greenman.
50-316 Electric Company, Administrator and selected D. C. Cook -
-members of RIII Staff Management Meeting 03/16/90 50-255 Palisades Plant Consumers Power Licensee, Regional Greenman Company, Palisades -
Administrator and selected Management. Meeting members of RIII Staff P
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'RIV Contact-
' Attendees /-
Date'
~ Number m
.E 2/28/90 50-298 RIV-NPPD. management visit to discuss HParris, NPPD; RMartin 9:30 follow up on SALP findings and other informational issues.
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