ML20062A899
| ML20062A899 | |
| Person / Time | |
|---|---|
| Issue date: | 10/17/1990 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-90-355, WIR-901012, NUDOCS 9010230211 | |
| Download: ML20062A899 (36) | |
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i October 17, 1990 For:
The Comissioners From:
James L. Blaha, Assistant for Operations, Office of the ED0 I
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 12, 1990 l
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A sumary of key events is included as a convenience to those Comissioners
'j who may prefer a condensed version of this report.
Contents Enclosure
]
Nuclear Reactor Regulation
-A Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data O
Governmental & Public Affairs E
i General Counsel F*
Administration G
Information Resources Management H
Controller I*
l Personnel J
- f Small & Disadvantaged Business Utilization & Civil Rights
- K*
Enforcement L
Consolidation M
Regional Offices N
Executive Director for Operations 0*
j Items Addressed by the Comission~
P*
-l Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
externaldistribution) j 1
- No input this week, ames L. Blaha- -
i Assistant for Operations, OED0
Contact:
James L. Blaha, OEDO h
d 492-1703
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9o1o230211 901017 PDR COMMS NRCC
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HIGHLIGHTS OF WEEKLY INFORMATION REPORT s
Week Ending October 12, 1990 Sequoyah Unit 1 On Monday, October 8, 1990, the licensee began a shutdown of Unit I due to an inoperable main steamline (MSL) check valve. The failure of the check valve could prevent closure of the MSL isolation valve, due to reverse flow, during a design basis MSL break. Following noises from the East MSL valve vault, the licensee had been investigating the possibility that the check valve disc had separated from the valve arm.
This had occurred in a MSL check valve in 1982.
This investigation culminated in x-rays made of the two check valves in the East valve on Sunday night. The licensee concluded that the disc had separated a'
from the arm in one valve, and shutdown the unit. After the shutdown, the licensee opened the four MSL check valves and found that the discs have separated from the arms in three of the valves. The three valves were modified during the Unit 1 Cycle 4 refueling outage that ended in May 1990.
The fourth valve was i
inspected in the outage but not repaired.
An AIT is being sent to the site.
R Notice of Possible Denial of Access to Current Low-level Waste Disposal Facilities On October 3, 1990, the States of Nevada, Washington, and South Carolina, jointly issued identical letters to the States of New York, New Jersey, Massachusetts, Maine, and Connecticut, indicating that these States may be denied access to disposal facilities within the currently sited States.
The letters cite the non-sited State's progress toward developing the capability to manage all low-level radioactive waste generated within their borders by January 1, 1993.
Michigan has previously been notified, by the sited States, that similar cir-cumstances in developing waste management capabilities may result in denial of access to currently sited facilities beginning November 11, 1990.
Notice of Withdrawal of Petition for Leave to Intervene in the Matter of Fort St. Vrain Independent Spent Fuel Storage Installation (15F51) Application On September 28, 1990, the Nuclear Regulatory Commission (NRC) received a peti-tion from the State of Colorado for leave to intervene in the matter of Public Service Company of Colcrado (PSC) regarding the Fort St. Vrain ISFSI application.
Following discussions between the NRC, the State and the PSC, a stipulation 1
agreement has been reached which provides the State with a forum for addressing issues related to the evaluation of the ISFSI application. As a result of the-agreement, on October 5, 1990, the Statn issued a Notice of Withdrawal for its p
Petition for Leave to Intervene.
l Small Agency Council Patricia G. Norry, Acting Director, Office of Information Resources Management, has been elected Vice Chairman for the Small Agency Council (SAC). The SAC is I
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2 the voluntary management association of sub-Cabinet Federal agencies.
Estab-lished in 1986, the SAC collectively represents the interests of approximately 70 small agencies with the various Federal management policy oversight agencies, sucF as the Office of Management and pidget and the Office of Personnel Manage-ment. The SAC also provides c 'erum tor the exchange of management experience among small agencies. Ms. Nort, kss been NRC's representative to the SAC since 1987, and has served as the Act:r,g Vice-Chairman for the past three months.
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Office of Nuclear Reactor Regulation items of Interest Week Ending October 12, 1990 l
Braidwood Station Unit 1 OnOctober4,1990,at1:22a.m.(CDT),threeCommonwealthEdisonCompany(CECO) individuals were sprayed with reactor coolant system (RCS) water during the performance of two separate surveillances on the Residual Heat Removal (RHR) system. One individual received a small (approximately 2-inch diameter) second degree burn on his left forearm. After successful decontamination of all three personnel, the individual with the burn was transported to the hospital, treated and released.
At the time of the event, the two surveillances, one an RCS pressure isolation valve leakage test and the other an RHR valve stroke timing test, were being performed concurrently. After the performance of the final leakage evaluation for the RCS isolation valve leakage surveillance on train "B" of the RHR system, the equipment attendant (EA) was requested by procedure to close a suction vent valve (1RH028-B). At the same time, a system engineer requested the Unit 1 NSO (reactor operator) to open the RHR hot leg suction valve, 1RH8702-B, for timing which aligned the RHR hot leg suction piping to the RCS. At the time of the event, the RCS was at 360 psig and 180'F. When 1RH8702-B started to open, the EA who was closing the RHR suction vent valve (1RH028-B) heard the rush due to the increased flow past the valve and attempted to hasten the closure of 1RH028-B.
- However, before the EA could close the valve completely, the tygon tubing attached to the vent valve broke and sprayed the EA and two engineers who were with the EA performing the tests. When the EA heard the increased flow, one of the engineers contacted the Unit 1 NSO in the control room to inquire what was happening since flow past the vent valve had increased and was spraying water over the surrounding area. The Unit 1 NSO checked pressurizer level and noticed a significant decrease. The Unit 1 NSO then went to close IRH028-B from breaking.
The total loss of RCS water was approximately 620 gallons which equates to a 5%
drop in pressurizer level.
An AIT team was formed and dispatched to the site Thursday evening, October 4, 1990. The initial assessment of the AIT concluded that the main contributors to the event were:
fatigue caused by excessive use of overtime by the technical staff, poor communications, and inadequate control over the testing activities by operations.
The team has completed its review and is in the process of writing its final report.
Sequoyah Unit 1 On Monday, October 8, 1990, the licensee began a shutdown of Unit I due to an inoperable main steamline (MSL) check valve. The failure of the check valve could prevent closure of the MSL isolation valve, due to reverse flow, during a design basis MSL break.
Following noises from the East MSL valve vault, the licensee had been investigating the possibility that-the check valve disc had separated from the valve arm. This had occurred in a MSL-check valve in 1982.
This investigation culminated in x-rays made of the two check valves in.the East valve on Sunday night. The licensee concluded that the disc had separated OCTOBER 12, 1990 ENCLOSURE A
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from the arm in one valve, and shutdown the unit. After the shutdown, the licensee opened the four MSL check valves and found that the discs have separated from the arms in three of the valves. The three valves were modified during the Unit 1 Cycle 4 refueling outage that ended in May 1990. The fourth valve was inspected in the outage but not repaired.
An AIT is being sent to the site.
Point Beach This morning a (non-reportable) event occurred at Point Beach Nuclear Plant j
involving the release of about 5 curies of noble gases, contamination of four individuals, and partial evacuation of the auxiliary building. At 7:46 a.m.
CDT a stack monitor " alert level" alarm occurred. This alarm indicates that releases are exceeding the normal level, the alert alarm setpoint is 2E-5.
(ThetechspecreleaseratelimitisSE-3).
The actual release rate reached a peak value of 6E-5.
Evacuation of the auxiliary building was initiated.
It was quickly determined that the release resulted from actions of technicians doing the daily sampling of the volume control tank (VCT). Apparently alignment of the sampling apparatus to the VCT was done in_a manner which permitted venting of the sample into the auxiliary building atmosphere.
Whole body counts were made of individuals evacuat;ng the building. Skin contamination was found on four individuals. The four had been involved in the VCT sampling. The highest nose smear was 700 counts.
The integrity of the VCT system was subsequently restored and access to the auxiliary building was reestablished by about 8:50 a.m. CDT.
It was estimated that 5 curies were released to the'outside atmosahere.
Relatively high winds, gusting to 25 miles per hour from the souti, were occurring at the time. Thus it is unlikely that releases were detectable at the site boundaries.
Although they determined that the event was not reportable, the licensee made a courtesy call to the NRC ops center. There has been some media interest in the event.
Computer Aided Design The Director, DRIS and a member of the Special Inspection Branch briefed Chairman Carr and Commissioner TAs on the planned and potential use of computer aided design (CAD) for the design and review of evolutionary and advanced reactor designs. There are basically two types of CAD systems. One is-essentially a drafting system, and the other is a stcte-of-the-art design system which goes well beyond drafting capability to visualization, animation, and optimization features. The advanced features included in~ CAD design systems are of value principally to design organizations, such as vendors for advanced nuclear plants. These systems will present.some new challenges and opportunities to both designers and the staff in terms of configuration control. These same features are not-as importar.t to the' staff in its safety reviews of material furnished in applications for advanced nuclear plants.
OCTOBER 12, 1990 ENCLOSURE A
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i However, the staff may at times find it useful to visit vendor facilities to make use of CAD representations of plant systems as a means of supplementing its reviews of application materials and of preparing for design and installa-tion inspections.
TRTR Annual Meeting The Director, Division of Licensee Performance and Quality Evaluation and representatives of the Operator Licensing Branch participated in the National.
Association of Test, Research and Training Reactors' (TRTR) Annual Meeting at Pennsylvania State University on October 9 - 10, 1990.
RESTART SCHEDULE 10/12/90 COMMISSION PLANT SHUTDOWN BRIEFING PLANT RESTART BROWNS FERRY 2 9/15/8dC 3/91 3/91*
- Commission decision prior to restart authorization, t
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OCTOBER 12, 1990 ENCLOSURE A-
a Office of Nuclear Material Safety and Safeguards.
Items of Interest Week Ending October 12, 1990 Domestic On October 10-11, 1990, the Department of Energy (DOE) held an interagency symposium on safeguards and security. The puraose of the symposium was i
to bring together various federal agencies wit 1 similar missions to share experiences in inspections and evaluations which could be of mutual benefit.
Papers presented at the symposium focused on safeguards and security inspections and addressed the control themes of inspection conduct / protocols, lessons learned and technologies, tools and methodologies.
Representatives of safeguards / security organizations from 12 federal agencies were present at the meeting. Nuclear Regulatory Commission (NRC) Safeguards personnel attended the meeting and made presentations on the agency's experience in Regulatory Effectiveness Review (RER) and regional safeguards inspections programs.
Meeting on NAC-CTC-Shipping Cask i
On October 3, 1990, Transportation Branch staff met with Nuclear Assurance Corporation (NAC) to discuss the NAC-CTC spent fuel shipping casks.
The i
NAC-CTC cask is one of a series of spent fuel shipping cask the Department of Energy (DOE) is designing for shipment of spent fuel under the Nuclear Waste Policy Act. The 100-ton rail / barge cask has a capacity of 52 boiling water reactor (BWR) assemblies or 26 pressurized water reactor (PWR) assemblies.
The meeting focused on the design of the NAC-CTC cask closure. The' cask lid I
is secured to the cask body by fif teen wedges which can be extended radially outward from the lid to engage in a groove machined in the cask body. NAC-CTC plans to conduct full-scale component reliability tests on the WEDGE-LOC cask closure and to conduct scale model drop tests of the cask which include the WEDGE-LOC closure. An application for NRC certification is expected in 1
January 1 G3, Notice of Withdrawal of Petition for Leave to Intervene in the Matter of Fort St. Vrain Independent Spent Fuel Storage Installation (ISFSI) Application l
On September 28, 1990, the Nuclear Regulatory Commission (NRC) received a I
petition from the State of Colorado for leave to intervene in the matter of Public Service Company of Colorado (PSC) regarding the Fort St. Vrain ISFSI application.
Following discussions between the NRC, the State and l
the PSC, a stipulation agreement has been reached which provides the State j
with a forum for addressing issues related to the evaluation of the ISFSI application. As a result of the agreement, on October 5, 1990, the State issued a Notice of Withdrawal for its Petition for Leave to Intervene.
i Notice of Possible Denial of Access to Current Low-Level Waste Disposal Facilities On October 3, 1990, the States of Nevada. Washington, and South Carolina, jointly issued identical letters to the States of New York, New Jersey, OCTOBER 12, 1990 ENCLOSURE B
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Massachusetts, Maine, and Connecticut, indicating that these States may be denied access to disposal facilities within the currently sited States. The letters cite the non-sited State's p* ogress toward developing the capability to manage all low-level radioactive weste generated within their borders by January 1,1993.
Michigan has previously been notified, by the sited States, that similar circumstances in developing waste management capabilities may result in denial of access to currently sited facilities beginning November 11, 1990.
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Office of Nuclear Regulatory Research items of Interest Week Ending October 12, 1990 Special Topic Workshop on Pressurized Thermal Shock Research A Special Topic Workshop on Pressurized Thermal Shock (PTS) research, organized by the RES Ma'.erials Engineering Branch, was held at the Rockville Crowne Plaza on September 26-28 with 15 Japanese industry representatives headed by JAPEIC (Japan Power Engineering and Inspection Corporation). The discussions revealed j
that the Japanese have a very low PTS risk due to -low copper-in their vessels, and because probability of transient occurrence is very low. It was also revealed that the lower shelf of fracture toughness K for Japanese steels is considerably curve!chisrevelationwasnotunderstood t
lower than the ASME Code reference KIc and must be explored further.
The meeting was especially notable because the Japanese presented much new.
information not previously opened to NRC; this is a clear break from previous interactions with the Japanese, signaling realistic expectations for continued more useful exchanges in the future. Towards that end, the Japanese agreed to exchange of their surveillance data bases with the US, although the data'must be kept proprietary to the NRC.
RES has agreed to analyze the data to see if there is any trending toward a flux rate effect; this will be done in connection with a larger but separate study of possible flux rate effects in US, French, and German data that was proposed at the GRS seminar held in Cologne Germany on
' September 3-6, 1990.
With completion of the Japanese PTS program in March 1992, they suggested we have a wrap-up meeting on this topic in Hawaii, in November 1991. To take further advantage of the availability of experts from the PTS workshop, we have discussed holding a Workshop on Materials Aspects of Aging for Normal and Extended Plant Operations at the same venue. The Japanese have a very large program on this topic; based on our recent experience, we would expect to learn much from their aging program at'this future meeting.
Division of Regulatory Applications.
l Draf t Regulatory Guide DG-3005, " Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities." Comments requested by November 30, 1990.
Contact:
C. M. Ferrell (301) 492-3944 OCTOBER 12', 1990' ENCLOSURE C
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l Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending October 12, 1990 Preliminery Notification The following Preliminary Notifications were issued during the past week.
PNO-1-90-89.WesternStress,Inc.,(Pensuaken,NewJersey), Radiography a.
Source Disconnect with Probable Whole Body and Extremity Overexposure.
b.
PNO-I-90-90, New York Power Authority, (James A. Fitzpatrick Nuclear Plant),
Presumptive Positive Drug Test on a Senior Reactor Operator.
c.
PNO-1-90-91,BostonEdisonCompany,(PilgrimNuclearPowerStation),
Summary of the Southeastern Massachusetts Health Study, d.
PNO-1-90-91A, Boston Edison Company,. (Pilgrim Nuclear Power Station),
Summary of the Southeastern Massachusetts Health Study, PN00-I-90-92, Nigeria Mohawk Power Corp., (Nine Mile Point 1), Condensate e.
Spill in Radwaste Building.
f.
PN0-II-90-60, Tennessee Valley Aitthority, (Sequoyah Unit 1), Forced Shutdown due to Steam Check Valve Failure.
g.
PNO-IV-90-37,NewmanMemorialHospital(Shattuck, Oklahoma), patient Provided Vital Containing Radiopharmaceutical and Dispatched to Another Hospital for Diagnostic Scan.
h.
PNO-II-90-523, SWVA, Inc (Huntington, WV), Melted Cesium-137 Gauge, 1.
PN0-IV-90-35A,OmahaPublicPowerDistrict,(FortCalhounStation), Plant i
Startup following a Shutdown Due to Design Deficiencies (Update),
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PNO-II-90-57, Florida Department of-Transportation, Stolen Moisture-Density
- Gauge, k.
PN0-11-90-56, StuartCircleHospital,(Richmond,VA),StolenLixiscope.
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PN0-1-90-88, New York Power Authority, (Indian Point Unit 3), Two Fuel
' Assemblies inadvertently Lifted From Core.
OCTOBER 12, 1990 ENCLOSURE D
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i Office of Governmental and Public Affairs Items of Interest Week Ending October 12, 1990 Oconee Emergency Planning Exercise Robert Trojanowski, ilegion 11 State Liaison Officer, participated in an emergency planning exercise for the Oconee Nuclear Plant on October 9-11, 1990 in Seneca, South Cartslina. Mr. Trojanowski participated as a member of the Regional Assistance Committee which evaluated the exercise. -The exercise included State and local government participation.
Meeting with Deputy to Governor of Tennessee Carlton Kammerer, Director, State Programs, and James Milhoan, Region 11 Deputy Administrator, met with Harland Mathews, Deputy to Tennessee Governor Ned McWherter, on October 12, 1990 in Nashville, Tennessee. The purpose of the meeting was to discuss the status of the Tennessee radiation control program.
Information Exchange with Visiting Japanese Technical Team On Tuesday an eight-member technical team from Japan, sponsored by the Washington Office of Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC), met in the morning with staff from RES and NRR to discuss human factor and severe accident issues.
Hong Kong Visit on Emergency Preparedness On Wednesday, Mr. K.W. Tong, from the Hong Kong government, accompanied by two engineers from Burns and Roe, met with Richard Van Niel, NRR/PEPB and Tom McKenna and Eric Weiss, AEOD/IRB, to discuss emergency preparedness and responding to radiological. emergencies. The Hong Kong government has requested from the Chinese safety authorities technical data on a plant's status in the event of an emergency in order to assess the event and advise the Hong Kong residents.
IAEA Vacancy Notices The following vacancy notices from the International Atomic Energy Agency in Vienna, Austria have been posted on.NRC bulletin boards:
P-5 Unit Head, Section 0A1, Division of Operations A. Department of Safeguards t
P-2 Editor, Publishing Section. Division of Publications, Department of Technical Cooperation P-3 Senior Reference Librarian, Reader Services Unit, VIC Library, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety P-5 Safety Standards Specialist, Safety Standards and Coordination Section, Division of Nuclear Safety, Department of Nuclear Energy and Safety OCTOBER 12, 1990 ENCLOSURE E-l
i P-5 Nuclear / Chemical Engineer, Waste Management Section, Division of Nuclear Fuel Cycle and Waste Management, Department of Nuclear Energy and Safety -
P-5 Head, Fellowships and Training Section, Division of Technical Cooperation Implementation, Department of Technical Cooperation i
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OCTOBER.12, 1990 ENCLOSURE E
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Office of Administration Items of Interest Week Ending October 12, 1990 Proposed Revision to Personnel Security Forms The Office of Personnel Management (OPM), due to recent court decisions re-i garding personal privacy and Constitutional rights, has published a Federal Register Notice requesting comments by October 29, 1990, on the pro)osed re-l vision of the SF-85, " Questionnaire for Non-Sensitive Positions"; t1e SF-86,
" Questionnaire for Sensitive Positions"; and a proposed new form, the SF-85P,
" Questionnaire for Public Trust Positions." These forms ask personal history questions and serve as the basir for personnel security investigations. SEC intends to provide comments on the SF-86, which NRC uses exclusively, and the SF-85P, if appropriate. The SF-85 is not used at NRC since all our positions are sensitive. Several questions on the SF-86 have been changed or eliminated based in part on previous comments solicited by OPM.
Review of Gilinsky Papers NRC has been notified by the Hoover Institution on War, Revolution and Peace.in Stanford, California, that they are now prepared to open the pa)ers of Dr.
Victor Gilinsky, consisting of 633 boxes, for scholarly researc1 During a I
recent trip to California, John Hoyle, Assistant Secretary of the Commission, reviewed some of the documents. Lynn Silvious, Chief, Information Security
' Branch, is scheduled to conduct a review during the week of October 22, 1990.
Ben Hayes, Director, Office of Investigation, while_on travel to California will review documents of interest to his office the week of October-16,1990.
A consolidated report of the review will be compiled upon comp ntion.
Headquarters Access Control System Work is scheduled to begin on October 15, 1990, to convert the Nicholson Lane card access system to the type used at OWFN and recently installed in the Bethesda area buildings. Once completed a single identification / access card will be used throughout Headquarters.
Significant FOIA Requests Received by the NRC l
For 4-Day Period of October 5, 1990 - October 11, 1990 l
Request for five categories of information relating to contracts awarded to j
Technassociates from January 1984 through December 1986. (Charles Leeper' of Spriggs & Hollingsworth, F01A-90-453)
Request for a copy of a February 14, 1986 memorandum from J. M. Taylor to _
l Regional Administrators entitled, "NRC Use of INPO Evaluation Reports." (Karen Unnerstall of Newman & Holtzinger, P.C., F01A-90-455)
Request for 27 categories of records regarding the West Lake Landfill in Bridgeton, Missouri. (John Herman of The Stolar Partnership, F01A-90-456) l i
DCTOBER 12, 1990 ENCLOSURE G
2 Request.for copies of environmental reports, inspection reports, and violations from October 1989 to the present on NDL Organization, Inc., of New York.
(Theresa Baylock, American Nuclear Insurers, F01A-90-459)
Request for a list of licenses for the use and handling of radioactive materials in humans in Puerto Rico in 1989 and-1990 and a list of applications not yet approved by NRC in Puerto Rico. (Jose M. Diaz, Sonumet, F01A-90-460)
Request for a specified letter to the NRC from Westinghouse concerning certain safety issues. (James Willis, F01A-90-461)
OCTOBER 12, 1990 ENCLOSURE G'
Office of Information Resources Management Items of Interest Week Ending October 12, 1990 1.
Patricia G. Norry, Acting Director, Office of Information Resources Management, has been elected Vice Chairman for the Small Agency Council (SAC). The SAC is the voluntary management association of sub-Cabinet Federal agencies.
Established in 1986,.the SAC collectively represents-the interests of approximately 70 small agencies with the various Federal.
management policy. oversight agencies, such as the Office of Management and Budget and the Office of Personnel Management. The SAC also provides a i
forum for the exchange of management experience among small agencies.
I Ms. Norry has been NRC's re)resentative to the SAC since 1987, and has served as the Acting Vice-C1 airman for the past three months.-
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Meeting rith Washington Interagency Telecommunications System (WITS)
Tom Kellam, Chief, Telecommunications Branch, Office of Information Resources Management met with members of the General Services Administra-tion's Washington Interagency Telecommunications Systems (WITS) cutover team on October 10, 1990. The purpose of the meeting was to discuss the i
changeover from commercial Centrex service to WITS' service at the NRC's convenience offices on F Street. The changeover is currently scheduled for late October.
Prior to the changeover, IRM will announce to NRC staff any changes in telephone numbers or dialing procedures.
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Office of Personnel I
Items of Interest Week Ending October 12, 1990 Combined Federal Camoaian Kicks Off at NRC NRC officially kicked.off the Combined Federal Campaign on Tuesday, October 2, 1990. Chairman Carr opened the kickoff meeting in the Commission Conference Room and presented awards to those offices who contributed significantly to last year's campaign.
EDO Jim Taylor remarked on the accomplishments of NRC offices as being the first year in which the highest award, the President's award, was presented to so many offices.
Guest speaker Judy Miller, Director of the Friendly Visitors Program, and special guests Bill Trumbull and Chris Core of WHAL radio spoke to those attending. Cheryl Nagle closed the meeting with a musical selection.
Recruitment Activities Continue The NRC staff continued to cover the various career days at universities and job fairs across the country.
A sample of the universities visited include Texas A&M University on October 9, Rutgers University on October 10, Texas A&1 University and Carnegie Mellon University on October 11, University of Pittsburgh on October 12, and the Massachusetts Institute of Technology on October 12 and 13. A roster of applications received will be available to NRC program offices when processing in the Office of Personnel is complete.
' Arrival s BARBELY, Edith Secretary (PFI)
NMSS DUBE, ROBERT Office Services Clerk (PFT)
RIV GOLDSMITH, Roxanne Reactor Intern Program Manager NRR HOOD, Katrina Clerk (SIS)(OPFT)
OP.
MILLER, Ilyne Secretary (PFT)
IRM SIKHINDRA, Mitra Electrical Engineer (PFT)
NRR SN0DDERLY, Mary Secretary (PFT)
NMSS YUROW, Judy Secretary (PFT)
OC-Deoartures MILLER, Jahr Senior Health Phy11cist (PFT)
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.ENCLOSURI J
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Office of Enforce'nent Items of Interest Week Ending October 12, 1990 Significant Enforcement Action L
A Notice o' Violation and Proposed Imposition of Civil Penalty in the amount of
$10,000 was issued on October 11, 1990 to Midwest Inspection Services, Ltd, Green Bay, Wisconsin. The action was based on seven violations that, con-sidered in the aggregate, are indicative of lack of management control. These violations include:
(1) exposure of an individual in excess of 1.25 rems in a 1
calendar quarter, (2) failure to report an exposure in excess of 10 CFR 20 limits, (3) failure to audit radiography personnel at the proper intervals, (4) failure to lock a sealed source assembly after completing a radiographic operation, (5) failure to calibrate a survey instrument at the proper intervals, (6) failure to check pocket dosimeters at the proper intervals, and (7) failure to properly mark or label a package or its outer packaging when transporting radioactive material. The base civil penalty was escalated because NRC identi-fied the violations and because the licensee's corrective actions were not promptly implemented and were only minimally acceptable.
(EN 90-089)
Civil penalties Paid 1.
Carolina Power & Light Company (Brunswick) paid the civil penalty in the amount of $62,500. The action was based on an event that occurred on July 5, 1990.
During work on the Unit 1 traversing incore probe (TIP) plant technicians received unplanned radiation exposures from an activated TIP having a radiation dose rate of approximately 1000 rem per hour on contact. While no regulatory radiation exposure limits were violated, it was determined that a substantial potential for overexposures existed.
The base civil penalty of $50,000 was escalated 25 percent after partially off-setting the escalation for prior notice of similar events by mitigation for identification and reporting as well as corrective actions.
(EA90-130) 2.
MQS Inspection, Inc., Elk Grove Village, Illinois, paid the civil penalty in the amount of $6,250. The action was based on an overexposure event which resulted in four violations of HRC requirements.
(EA90-046) l 1
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OCTOBER 12, 1990 ENCLOSURE L i
Office of Consolidation items of Interest Week Ending October 12, 1990 Second Building Status The WFN Partnership has indicated its intention to seek relief from some of the Montgomery County Planning Board's conditions related to approval of construction of Two White Flint North (TWFN). WFN's request for relief ~is based on current economic conditions in the real estate industry, which it describes as being in deep recession.
The relief WFN is seeking includes deferral of construction of the apartment building (behind One White Flint North for three years and elimination of the back-up Supplementary Program) to the WFN portion of the traffic mitigation program.
WFN has obtained an operating certificate and signed a contract with a shuttle bus carrier for operation of the White Flint Commuter Shuttle under the basic traffic mitigation program required by the County. The shuttle, which will replace the existing White Flint Shuttle to the Mall will go into service on or before October 29, 1990.
It will run from 7:00 a.m. to 6:00 p.m. and will connect office buildings on Woodglen, Security and Edson with the White Flint Metro Station and the Mall, completing a loop about every 71/2 minutes. The service will be free.
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Region I Items of Interest Week Ending October 12, 1990 1.
Western Stress Inc.
On October 5, 1990, at approximately 7:45 p.m., Western Stress Incorporated, a Region IV licensee, notified the Headquarters Operation Center of a radiographic source disconnect.
In an attempt to recover the source to its shielded position, the radiographer reported that he may have handled the guide tube near the source which may have caused significant radiation exposure to his hands and a whole body exposure above regulatory limits.
The incident occurred at a field location in Bordentown, New Jersey.
Activities were being conducted by Western Stress personnel from their field office in Pennsauken, New Jersey.
The radiographer reported the j
incident to the Corporate Radiation Safety Officer in Houston, Texas, who then contacted NRC Headquarters. Two NRC Region I inspectors were dispatched to the site to verify radiological controls and monitor source recovery operations.
Personnel from Amersham (the manufacturer of the camera) successfully recovered the source at 2:08 a.m. on October 6, 1990. Exposures to the two Amersham recovery personnel were 72 mrem and 2 mrem.
Initial licensee and NRC exposure estimates are that the radiographer received between 5 and 16 rem to the whole body and between 250 and 1000 rem to the hand.
The radiographer is receiving medical attention. The cause of the disconnect is being investigated by the manufacturer, 2.
Indian Point Unit 3 i
At Indian Point Unit 3, the New York Power Authority (NYPA) continues to evaluate the two fuel assemblies attached to the bottom of the upper core internals and suspended over the core. Underwater camera evaluations have determined that each of the assemblies is attached via one of the two l
fuel assembly alignment pins, which has been deformed. NYPA judges the attachment to be secure.
NYPA is planning to move the upper core internals and fuel assemblies to the refueling pool and to separate the assemblies after locating the assemblies in holding fixtures. Region I continues the l
24-hour coverage of activities and is being informed on all' activities-regarding the safety significant work.
3.
Millstone and Haddam Neck Commissioner James R. Curtiss will visit Millstone Station on October 11 and Haddam Neck Nuclear Power Station on October 12, 1990. The i
visits will include a tour of each site, and a briefing on ongoing activities and significant issues of concern.
t OCTOBER 12, 1990 ENCLOSURE'N l
~
Region II Items of Interest Week Ending October 12, 1990 i
l 1.
South Carolina Electric and Gas Company J
On October 9, the Regional Administrator met with the Vice President Nuclear Operations, South Carolina Electric and Gas Company, to discuss organizational changes pertaining to the Summer facility.
2.
Enforcement Conference On October 10, the Deputy Director, Division of Radiation Safety and Safeguards; the Director, Enforcement and Investigation Coordination Staff; and other members of the Regional staff conducted an Enforcement' Conference at the Cabell Huntington Hospital in Huntington, West Virginia regarding the findings of the NRC Inspection conducted on September 13, j
1990.
1 3.
Tennessee Valley Authority - Watts Bar On October 11, Chairman Carr, accompanied by the Regional Administrator, was at the Watts Bar facility to review-the status of the facility.
4.
Tennessee Valley Authority-Sequoyah i
On October 10 a special Augmented Inspection Team (AIT) was dispatched to the Sequoyah nuclear power plant to examine events associated with the failure of three main steam line check valves at Unit 1, to evaluate their significance with respect to system performance and safety, and to evaluate any damage the valve discs may have done after becoming dislodged. The problem was detected when plant personnel reported hearing an unusual noise in one of the steam lines. The unit was safely shut down and will remain so until the cause of the problem has been established'and correc-tive action has been completed.
f 5.
Hurricane / Tropical Storm Watch On October 10, 1990 Region II dispatched a region-based project inspector to Crystal River Power plant to aid the resident in preparing for tropical' storms in the area.
The Region is also monitoring tropical storm Lili and Marco, and has contacted nuclear power plants and fuel facilities in Region II where the storms may approach over the weekend of October 13-14,1990.
5.
Georgia Power Company - Vogtle On October 11, George Bockhold, the General Manager, Plant Vogtle (Site Manager), was reassigned to the position of Manager, Advanced Reactor.
OCTOBER 12, 1990 ENCLOSURE N-y l
l
.g.
Designs, effective immediately. This new position is with Gec gia Power Company's (GPC) parent organization, Southern Company Services.
Until a permanent replacement is identified, William (Bill) Shipman will act in the capacity of Vogtle General Manager. Mr. Shipman has been the Manager, Plant Support, Vogtle Project, in the GPC headquarters in Birmingham, Alabama.
On October 11, an alleger at Georgia Power Company's Yogtle Electric Generating Plant was terminated from employment with.GPC. The alleger's termination was due to his " surreptitious taping of conversations between GPC employees and NRC personnel, which was not in keeping with the GPC l
philosophy of mutual trust and open communications."
6.
Entergy Operations, Inc. (Grand Gulf)
On October 4, with the plant in mode 5. refueling, the steam dryer became lodged approximately five feet above its seated position, during lifting.
The dryer had rotated slightly out of alignment with its guide rods preventing further lifting of the dryer.
(Similarproblemswereencoun-tered while removing the dryer during the last refueling outage. A bent.
guide tab near the bottom of the dryer was believed to be the principal.
cause of that problem and was removed prior to reinstallation.) The dryer was successfully repositioned on October 7 and removed. Upon removal of the dryer, an inspection of the steam separator and guide rods was con-ducted. The guide rods had been bent and seven holddown bolts to the separator assembly were found damaged.
Special remote hand tools were fabricated and all but two holddown bolts were removed. A hydraulic-cutter and supporting hand tools have been fabricated to cut and remove.
the two remaining bolts. At present, removal of the separator (critical path steps) is about 115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> behind schedule. The licensee expects this operation to be completed on October 12. The vessel work is being per-formed by GE, and GE will be involved in the resolution of the problem.
The resident inspector will continue to follow licensee resolution of this' L
problem.
O 3
OCTOBER 12, 1990 ENCLOSURE N
t Region III Items of Interest Week Ending October 12, 1990 1.
North Detroit General Hospital On October 5,1990, C. J. Paperiello,. Deputy Regional Administrator, and selected regional staff conducted an Enforcement Conference to discuss the 10 violations identified during a recent inspection.
The licensee also described their corrective actions and plans to improve the management control of the program. The violations were apparently caused by a breakdown in management oversight of the_ program. The Region will recommend escalated enforcement.
2.
U. S. Army On October 10, 1990, W. L. Axelson, Deputy Director, Division of Radiation Safety and Safeguards, and. selected regional staff conducted a Management Meeting to discuss the licensee's proposed plan to decontaminate a burial site at Fort Bragg, North Carolina. ~The licensee also discussed the preliminary results of their internal investigation to determine why removable gun sights containing approximately 100 microcuries of promethium-147 were not removed from the weapons prior to disposal by burial.
It appears that 4,000 to 6,000 of these devices were buried during a nine month period.
3.
Chemtron Corporation A Radiation Specialist was dispatched.to the siteEto_ review the concerns reported to the Region regarding minors being observed in the restricted areas of the facility, a dump site located in Newburgh Heights, Ohio.
The site which was formerly used for the manufacture of products containing depleted uranium, is currently being decontaminated. The inspector found.
gaps and openings in the fence around the dump site. The licensee committed to erect new fencing and post additional site security staff to maintain closer security monitoring of the site. The City Council members and staff from Senator Metzenbaum's office were given a tour of the site by the site manager. The Region agreed to participate in'a public meeting on the issue if requested by the City Council.
4.
Zion Nuclear Power Station On October 10, 1990, the Director, Division of Reactor Projects and members of his staff accompanied Commissioner Kenneth Rogers on al tour of the Zion Station.
5.
Braidwood Nuclear Power Station l
On October 11, 1990, the Deputy Director, Division of Radiation Safety and Safeguards,'and members of the Region III staff accompanied Commissior.er Kenneth Rogers on a tour of the Braidwood facility.
OCTOBER 12, 1990 ENCLOSURE N s
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6.
LaSalle Nuclear Power Station The Director, Division of Reactor Safety and members of the Region III staff met with the licensee at the site on October 12, 1990, to discuss the status of the licensee's Engineering Program.
7.
Dresden Nuclear Power Station An Enforcement Conference with the licensee was held in the Region III office on October 12, 1990, to discuss a lack of a 10 CFR 50.59 review for a containment sampling system modification. The Deputy Regional Administrator and members of the Region III staff attended.
8.
Braidwood Nuclear Power Station On October 4, 1990, three individuals were spray d with Reactor Coolant System (RCS) water during the performance of two surveillances on the Residual Heat Removal (RHR) system. All three individuals were successfully decontaminated.
At the time of the event, two surveillances, one a RCS pressure isolation valve leakage surveillance and the other a RHR valve stroke test, were being performed concurrently on two isolation valves in series. After the completion of the RCS surveillance, the equipment attendant (EA) was required by procedure to close a suction vent' valve.. However, at the time, a system engineer requested the Unit 1 NSO to open the other RHR hot leg isolation valve to align the RHR hot leg suction piping to the,RCS. Before the EA_
could close the valve, the tygon tube attached to the vent valve broke and-sprayed the EA and two engineers. -After one of.the engineers contacted the NSO for Unit I to inquire what was happening, the Unit 1 NSO checked pressurizer level and noticed a significant decrease. The Unit 1 NSO then closed the hot leg isolation valve to stop the RCS inventory loss which had totaled 620 gallons.
Two senior resident inspectors (Dresden and Byron) were dispatched to the site to investigate the event. An Augmented Investigation Team (AIT) was formed to review the event.
9.
Fermi 2 Nuclear Plant Fermi started up from a seven day outage'on October 5,'1990. The outage focused primarily on B0P equipment feedwater heater system repairs.- The i
outage was observed by a Region III mini-maintenance followup team. The team noted improvement in licensee performance since the.1989 maintenance team inspection, especially in the areas of outage management, work planning, first line supervision of maintenance activities, and communications _among 1
maintenance and other plant staff.
On October 6, 1990, the reactor scrammed on low reactor water level due to level instrumentation discrepancies.
Preliminary ' licensee investigation results indicate that the reference legs of water level instrumentation _were not~ periodically backfilled as recommended by the vendor. The licensee'and resident inspectors investigations, into the_ root causes of the scram, continue.'
1 OCTOBER-12, 1990-ENCLOSURE N
Region IV.
Items of Interest Week Ending October 12, 1990 f
1.
South Texas Project Enforcement Conference On October 5, 1990, the Acting Director, Division of Reactor Projects and-other members of the Regional staff held an enforcement conference in the Region IV office with South Texas Project Generat'ng Station management personnel. The subject of the enforcement conference was the licensee's failure to restore a high head safety injection pump to operable as.
required during a Unit I heatup. The licensee was represented, in part, by the Vice President, Nuclear and Vice President,. Generation. The enforcement conference was beneficial in ascertaining the licensing perception of the event and their proposed corrective actions.
2.
Cooper Nuclear Station SALP Presentation On October 9, 1990, the Acting Director, Division of' Reactor Projects and other members of the Regional staff met at' Cooper Nuclear Station near Brownsville, Nebraska, to present the results of the most recent SALP review to the Nebraska Public Power District management and members of the public.
3.
Fort Calhoun Station Safety Enhancement Program Presentation-On October 10, 1990, the Acting Director, Division'of Reactor Projects and l
other members of the Regional staff met at the Fort Calhoun Station site to attend an Omaha Public Power District presentation on the completion of l
the Fort Calhoun Station safety enhancement program.
j l
4.
Wolf Creek Generating Station The Deputy Regional Administrator, accompanied.by select Region IV manage ment and technical staff, attended a public meeting on October 11, 1990, with the licensee's management to discuss the initial SALP report'at the
~
Wolf Creek Generating Station Training Facility in Burlington, Kansas.
5.
Reclamation Plan for Church Rock Uranium Mill On October 12, 1990, the President, United Nuclear Corporation and his consultant, Canonie Corp., met with the Director, Uranium Recovery Field I
Office and the Project Manager in the URF0 office. The meeting was held i
to discuss issues remaining before the NRC can. approve the Reclamation Plan for the Church Rock Uranium Mill in New Mexico.
6.
Waterford 3 i
On October 8, 1990, Waterford 3 was placed'in cold shutdown to repair-t the pressurizer safety valves that had been leaking. During the shutdown, the licensee performed a general area visual _. inspection inside.the contain-
{
ment and identified boric acid buildup on Reactor Coolant Pump.(RCP) 2-A.
f OCTOBER 12, 1990-ENCLOSURE N J
2 J
Further investigation revealed that a reactor coolant leak existed between the flanges that connect the RCP casing to the driver mount bottom flange.
The flange is designed with two concentric flexatallic gaskets and the l
leakage was through both gaskets. As a result, boric acid had accumulated around the flange studs, which are made of carbon steel.
1 Thelicenseehasperformedultrasonictesting(UT)ofthestudsandhas determined that no wastage has occurred due to boric acid corrosion.
NRR and Region IV personnel are currently in the process of reviewing '
the results of the UT of the studs.
The licensee does not plan to start up the plant until this issue is
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resolved.
I l
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r OCTOBER 12, 1990 ENCLOSURE N.
-i
Region V Items of Interest Week Ending October 12, 1990 1.
Diablo Canyon Nuclear Power Station A management meeting was held with Pacific Gas and Electric Staff at the.
Region V offices on October 10, 1990 to discuss recent plant events and initiatives taken by the licensee to improve their. operation.
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i OCTOBER 12, 1990 ENCLOSURE N I
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NRR MEETING NOTICES m"
October 12, 1990 C3 APPLICANT /
. DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 10/23-24/90 None ABB-CE Offices Meeting with ABB Combustion NRC/ABB-CE/
Y. Hsii 8:00-5:00-Building 24 -
Engineering to discuss sinall INEL Fuel Engineering break LOCA realistic evaluation Conference Room model.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500 10/25/90 None One White Flint North Meeting with Westinghouse to NRC/INEL/
Y. Hsii 8:30-4:30 Room 88-11 discuss WCOBRA/ TRAC code
-. Westinghouse /
modifications.
Northern States Power / Wisconsin Electric Power 10/25/90 50-413/
One White Flint North Meeting with Catawba Nuclear NRC/CNS K. Jabbour 1:30-4:00 414 Room 14B-11 Station to discuss operational safety and performance at Catawba Nuclear Station.
10/30/90.
None One White Flint North Meeting with.NUMARC to discuss NRC/NUMARC
.N. Markisohn 9:00 Room 6B-11.
the resolution of NRC staff conments'on the subject Industry Report.
o Copies of.. summaries of.'these meetings will be made publicly available and i
placed-int the respective docket file (s) in the NRC and local public-document
'_ mg.
rooms.
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A~ listing;of these meeting notices can be obtained by calling 492-7424.
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P. 2 C3 fl t!RR MEETING NOTICES h!
- =
October 12, 1990 APPLICANT /
[$'DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT o
11/15/90 50-458 One White Flint North Meeting with Gulf States Utilities NRC/GSU C. Abbate 9:00 Room 14B-13 to discuss the detailed data and benchmarks-used in the steady state physics and transient reports with will be submitted by the licensee in support of performing their own reload analyses.
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EI October 12, 1990
- o jfl NMSS Meeting Notices
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Division of Industrial and Medical Nuclear Safety Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact 10/17 70-08 OWFN 68-9 To discuss Battelle NRC P. Loysen 9:00 a.m.
decommissioning plans Battelle 10/17 08 OWFN 88-11 To review status NRC.
P. Loysen 11:00fa.m.
and responsibilities DOE of parties for Battelle decommissioning-RIII 10/23 10 Livermore, CA To meet with Northern NRC J. Schneider
. States Power, Lawrence NSP Livermore National Labs LLNL to discuss Prairie Island ISFSI Division of High-level Waste Management Docket Attendees /
- - Date/ Time Number Location Purpose Applicant.
NRC Contact None y,
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Docket Attendees /
y Date/ Time Number Location Purpose Applicant NRC Contact E
10/17
%TN 88-11 Attend Battelle NRC P. Loysen Columbus / DOE Decommissioning Meeting i
10/17-19 Miami, FL Attend LLW Forum NRC P. Lohaus Meeting 10/20-24 Albany & NYC, NY To review NYS LLW NRC P. Lohaus.
Program 10/21-22 Augusta, GA Attend ASLBP Annual NRC R. Bangart'
~
Panel Meeting 10/23-27 Las Vegas, NV Presentation _on NRC's NRC B. Lahs Below Regulatory. Concern-Policy to Department of Defense Joint Service
' Low-Level-Waste Generators Meeting 10/25-26
. Baltimore,- ND.
Participate _in Mixed NRC J.- Austin Wasto Workshop
.11/15 4 Washington, DC.
-Participate as a NRC J. Austin-
~
Commercial Generators Panel Member, at the ANS Mixed Waste W rkshop
~m-11/27-29 Tallahassee,fFL' Presenting'dsxed Waste NRC' N. Orlando Workshop zp tg
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Division of Safeguards and Transportation Docket Attendees /
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Date/ Time Number Location Purpose Applicant NRCConagg;,
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10/25 OWFN Room 68-11 Discuss Possible Credit NRC C. Withee.
for Fuel Birn-up DOE 11/4-9 Erwin, TN Inspect Nuclear Fuel NRC R. Castaneira Services, Erwin, TN 11/5-8
. Wilmington, NC Inspect GE Site
'NRC C. Haney 4
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RES Meeting Notices o
Attendees /
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Docket Purpose Applicant NRC Contact
-Date/ Time Number Location ro Director's Office h
'10/22-24/90 Holiday Inn Eighteenth Water Reactor Safety A. Burda Crowne Plaza Information Meeting 492-3714 Rockville, MD s'
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l i 6 October 12, 1990 l g Region I Meeting Notices
,p' Docket Attendees /
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Date/ Time Number Location Purpose Applicant NRC Contact G
10/16/90 50-354 Hancocks Bridge, NJ SALP Management Mtg.
Seleci.ed RI Staff Swetland 10:00 a.m.
50-272/311' Salem / Hope Creek Merbers & Licensee
. 10/16/90 50-293 Plymouth, MA SALP Management Mtg.
Selected RI Staff Rogge 1:00 p.m.
Pilgrim Members & Licensee 10/18/90 50-293
'RI Office Enforcement Conference Selected RI Staff Members McCabe 10iOO a.m.
Maine Yankee Members & Licensee-10/19/90 50-213 RI Office Enforcement Conference Selected RI Staff Members Haverkamp 1:30 p.m. 245/50-336/50-423 Millstone /Haddam Neck Members & Licensee
-To date there are no meetings scheduled for the period covering 10/22 thru 11/9/90.
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October 12, 1990 RII MEETING NOTICE
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DOCKET ATTENDEES /
~
h DATE/ TIME NilMBER LOCATION PURPOSE APPLICANT NRC CONTACT'
.y 10/16/90 York, SC Com. Curtiss at Catawba
- Commissioner, Tech. Asst.
Reyes j
facility for site and Regional Administrator
'o familiarization 10/16/90 RII Office Enforcement Conference Regional Administrator Reyes 10:00 a.m.
CP&L - Brunswick selected RII & NRR Staff,.
Licensee 10/18/90
' Seneca, SC SALP. Presentation -
Regional. Administrator.
Ebneter
'10iOO a.m.
DPC - Oconee selected RII 8'NRR Staff, Licensee.
~
10:00.a.m.
Memphis, TN.
Enforcement' Conference.
Selected RII Staff Mallett VA Hospital
' and Licensee 10/24/90 Columbia, AL Full Scale Emergency
. Regional Administrator, Ebneter-Exercise - APC
.Farley
. and~ selected RII Staff 10/31/90 RII Office Enforcement Conference' Selected RII Staff
.Reyes 1:00'p.m.
FPC - Crystal River.'
. and Licensee
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.N Date/ Time Number Location Purpow Applicant NRC Contact m
To
' West Shore Hospital -
Licensee, Deputy Regional Axelson E
10/22/90 30-10713 Region III
~1:00 p.m.
Enforcement Conference Administrator and selected
' merrbers of RIII Staff 10/23/90
' 50-341 Region III Detroit Edison Company, Licensee, Regional Greenman 10:00 a.m.
Fermi - Management
- Administrator and selected Meeting-members of RIII' Staff' 10/23/90, 50-254 Quad Cities Site Visit Chairman Carr and Deputy Greenman
~
- 50-265-Regional. Administrator 10/24/90 315^
D.-.C.
Cook ^
Indiana Michigan Power Licensee, Regional Miller:
10:00 a.m.
L50-316-
~
Company - Management Administrator and selected ~
Meeting-
. members of RIII Staff 10/24/90 331
-Duane! Arnold
- Site Visit Chairman Carr and Deputy.
Greenman Regional Administrator Point Beach-Wisconsin Electric
-Licensee,_ Regional -
Greenman 10/25/90
~ 50-266'
~
50-301-Power Company -
Administrator and selected-Management Meeting members. of RIII ~ Staff :
Licensee, Deputy Regional Greenman 10/30/90 50-440 Perry Cleveland Electric
. Administrator and selected 50-441'.
Illuminating Co. -
Systematic Assessment members of RIII Staff-of Licensee Performance Conference 11/06/90 254 Quad Cities-
. Site Visit Commissioner Rogers, Greenman g.
~ 50-265 Director,.. Division of.
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Duane Arnold Site Visit Commissioner Rogers',
- Greenman L
E 11/07/90' 50-331 w.
Director,. Division of,
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4 hS Region IV Meeting Notice
!g October 12, 1990
" E!
Docket Attendees /
y Date/ Time Number Location Purpose Applicant NRC Contact iG
- E.
10/18/90-50-267 RIV Enforcement conference with PSCO J.B.Baird 1:00 Fort St. Vrain 10/19/90 URF0 Discuss proposed modifications Total Minerals Corp.
R. Hall to Irigaray & Christensen Ranch in-situ license.
10/22/90 50-445 RIV Discuss actions associated with. TU Electric-D. Chamberlain.
. 1:00-secondary plant reliability problems.
URF0 Discuss ground-water corrective Petrotomics R. Hall
-10/25/90 action for Shirley Basin mill.
10/29 URF0' Discuss reclamation liability at. Western Nuclear R. Hall
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the nonoperating-Day Loma heap
-leach site in Wyoming.
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