ML20059D564
| ML20059D564 | |
| Person / Time | |
|---|---|
| Issue date: | 08/30/1990 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-900830, NUDOCS 9009070102 | |
| Download: ML20059D564 (38) | |
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August 30, 1990 For:
The Commissioners From:
James L. Blaha, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REP 0hT - WEEK ENDING AUGUST 24, 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 Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
Governmental & Public Affairs E
General Counsel F*
Administration G
Information Resources Management H
Controller 1*
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
external distribution)
- No input this week.
James L. Blaha Assistant for Operations, OEDO.~
Contact:
James L. 31aha, OED0 020m:2 gp 492-1703 l
9009070102 900830 i
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PDR COMMS NRCC I
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WEEKLYINFOREPT PNU-i.
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i HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING AUGUST 24, 1990 L
Brunswick Unit 2 l
On August 19, 1990, while performing the surveillance test for the Primary Containment Isolation System (PCIS), the 18C technician neglected to clear the partial scram signal in a " condenser pressure high" channel before proceeding to test the next channel, resulting in the generation of a full group 1 isolation signal. TheMainSteamIsolationValves(MSIV) closed, generating a scram signal. The reactor scrammed with all rods inserting properly.
In the course of controlling water level and reactor pressure, several problems were encountered. A number of safety valves did not lift at the required set points and several motor-operated valves in the RHR and RCIC tripped on thermal overload. An Augmented Inspection Team (AIT) was dispatched to the Brunswick site on August 21, 1990.
Status of Emergency Preparedness Around the Pilarim Nuclear Power Plant During the week of August 20, 1990, a member of PEPB, is participating with
. representatives of NRC Region I and FEMA Region I, in meetings with State and local officials responsible for radiological emergency planning around the Pilgrim Nuclear Power Plant. The meetings are being held to obtain the latest.
information on the status of offsite emergency preparedness.
This effort is in addition to the planned public meeting on current status of offsite emergency preparedness scheduled for September 6, 1990.
Dresden Nuclear Power Station On August 7 and 8, 1990, a human factors stuoy team was sent to the Dresden Nuclear Power Station site to review reactor operators res)onse to an event that occurred at Unit 2 on August 2, 1990, at 1:05 a.m.
T1at event involved the spurious opening of a Targn Ack Valve while the plant was at 87% power, a manual reactor scram, and th subsequent cooldown of the plant at an excessive rate. The report of the results of the study is in preparation. The Dresden review was the 4th conducted under the protocol developed thru RES by INEL.
An analysis will.be performed of the overall human factors lessons obtained after about 8 of these reviews to determine the' generic lessons that may be drawn from these events as a composite.
It is already established that current written LERs do not capture the human factors lessons very well.
Second Building Status The attorney for WFN Partnership indicated that he would propose language in the lease amendment during the week beginning August 27 to overcome the developer's concern about future financial liabilities should the Government-exercise its purchase option at the end of the fifth year.
On August 13 we reported that GSA had informed us that the appraisal update on TWFN would be completed on schedule, i.e., by August 26. However, late last week, the GSA Regional Office contracts staff reported that the appraisal update will not be delivered as promised. Further, GSA now says that only a verbal contract existed between the appraiser, Mr. Urghardt, who died before completion of the appraisal, and GSA. The GSA Regional Counsel's office is.
reviewing the situation to determine whether or not a valid contract still exists and how to proceed.
Office of Nuclear Reactor Regulation Items of Interest Week Ending August 24, 1990 Brunswick Unit 2 On August 19, 1990, while performing the surveillance test for the Primary Containment Isolation System (PCIS), the I&C technician neglected to clear the partial scram signal in a " condenser pressure high"' channel before proceeding to test the next channel, resulting in the generation of a full group 1 isolation signal. The Main Steam Isolation Valves (MSIV) closed,.
generating a scram signal. The reactor scrammed with all rods inserting properly.
In the course of controlling water level and reactor pressure, several problems were encountered.
A number of safety valves did not lift at the required set points and several motor-operated valves in the RHR and RCIC tripped on thermal overload. An Augmented Inspection Team (AIT) was dispatched to the Brunswick site on August 21, 1990.
s BWROG Meeting on ATWS/ Stability In an August 17 meeting the BWR Owners' Group (BWROG) provided a presentation of their current ATWS/ Stability program plans and a discussion of program implementation details including planned analyses, input assumptions and approach, and operator actions. The approach considers both "ATWS" and "Beyond ATWS" (e.g., no boron injection) events and operator actions via Emergency Procedure Guidelines (EPG). TRAC analyses for ATWS will be limited to (1) two (recirculation) pump trip (2) two pump trip with improved EPG, and (3) turbine trip with bypass..They will select a representative plant, use reasonably limiting parameters and initiate EPG actions, and compare results to
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ATWS acceptance criteria.
"Beyond ATWS" evaluations will rely primarily on qualitative analyses and will consider the possibility of new EPG actions. The presentation discussed the bases of the selected ATWS sequences and calculation input, and possible EPG improvements. The only specific EPG change which was indicated as currently under consideration was boron injection and water level
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control initiation based on suitable indication of oscillations above some threshold rather than waiting for su)pression pool temperature limits to be exceeded. The present goal is for tie analyses to be done by October, followed by BWROG review and a report to NRC in January 1991. The NRC staff response to the outline of the analyses program was generally favorable. The next meeting to discuss the program on ATWS as well as "long term solutions" is October 2 and 3, 1990.
L Standardized Plant Design Memberc of the Special Inspection Branch met with EBASCO personnel at their corporate offices on August 17. Discussions were held regarding the nuclear plant design process and level of design detail aspects for standardized plant design. A similar meeting was held with UE&C personnel on August 20 and Bechtel personnel on August 22.
ENCLOSURE A AUGUST 24, 1990
Status of Emergency Preparedness Around the Pilgrim Nuclear Power Plant During the week of August 20, 1990, a member of PEPB, is participating with representatives of NRC Region I and FEMA Region I, in meetings with State and local officials responsible for radiological emergency planning around the Pilgrim Nuclear Power Plant.
The meetings are being held to obtain the latest information on the status of offsite emergency preparedness.
This effort is in addition to the planned public meeting on current status of offsite emergency preparedness scheduled for September 6,1990.
RESTART SCHEDULE 8/24/90 COMMISSION PLANT SHUTDOWN BRIEFING PLANT RESTART BROWNS FERRY 2 9/15/84C 11/90E 12/90E*
- Commission decision prior to restart authorization.
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i AUGUST 24, 1990 ENCLOSURE A
4 Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending August 24, 1990 Physical Inventory Verification (PIV)- at General Electric-During the week of August 6,1990, ten inspectors from the International Atomic Energy' Agency (IAEA) performed a P1V at the General Electric Low Enriched Fuel Fabrication Plant in Wilmington, North Carolina.
The inspectors performed item counts, non-destructive assay measurements, weighings and sampling for destructive analysis.
Initial conclusions based on activities performed-on-site indicated a successful PIV; however, final conclusions will not be available until the IAEA completes their destructive assay measurements and i
statistically evaluates all of the data obtained. Typically, the IAEA final conclusions are communicated several months after the PIV.
Package Supplier Inspection On August 13-15, 1990, Transportation Branch staff conducted an inspection at Combustion Engineering, Inc., Windsor, Connecticut. The staff was supported by one quality assurance inspector from Idaho National Engineering Laboratory.-
The inspection focused on quality assurance in the fabrication, maintenance and use of transport containers for fuel pellets and fuel assemblies.
Preliminary findings were discussed with co:npany representatives at the exit meeting.
Consumers power Company - Palisades Nuclear Plant The NRC received a letter of August 17, 1990, from Consumers Power Company (CPCo) requesting that its license application, under 10 CFR Part 72, for an independent spent fuel storage installation (ISFSI) at the Palisades Nuclear Plant site be withdrawn. A number of petitions to intervene with respect to this licensing action have been filed.
CPCo indicated that it intends to provide additional onsite spent fuel storage under the provisions of new Subpart K, to 10 CFR Fart 72, which became effective on August 17, 1990.
The new amendment to 10 CFR Part 72 grants commercial power reactor licensees a general license to provide additional onsite storage of spent fuel in NRC-approved storage casks-provided certain conditions are met.
CPCo intended to use the ventilated concrete storage cask system designed by Pacific Sierra Nuclear Associates. A topical safety analysis report for this cask is currently under review by the NRC staff. The cask is not an approved cask design under the new rule change, I
but could be added to the list of approved casks by a' future rulemaking.
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i ENCLOSURE B AUGUST 24, 1990
Office of Nuclear ' Regulatory Research' Items of Interest l
Week Ending August 24, 1990 Denial of Requests to Extend Comment Period for License Renewal Rule Three requests to extend the 90-day comme'nt period for the proposed rule on nuclear power plant license renewal'by 60 days or more were denied.
(The comment period ends on October 15,1990.)- The prospective commer.ters requesting the extension were the Nuclear Information and Resource Service, the Ohio Citizens for Responsible Energy, and the Union of Concerned Scientists. The decision to deny was based on the required timing for complet?qn of this rulemaking and the sufficiency of the 90 days allowed, especially in view of extensive prior public participation opportunities. The denial, with its statement of considerations, is being published in the Federal Register. The prospective commenters who made the requests have been notified by individual letters, which assure them that the NRC would very much like to have their comments and explain the agency's need to have them within the required time frame.
t AUGUST 24, 1990 ENCLOSURE C
i Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending August 24, 1990 t
Director'sOffice(AEOD)
The schedule for industry workshops on backfitting and event reporting has been firmed up with the Regional Offices and letters are being dispatched to power reactor licensees. The workshops will be held in the following locations:
R11 September 27-28 Omni, CNN, Atlanta, GA RI October 1-2 Stouffer Valley Forge Hotel, King of Prussia PA Rill October 15-16 Ramada Hotel O' Hare, Ch;.ago, IL RIV & RV November 7-9 Sheraton CentrePark, Arlington, TX DivisionofOperationalAssessment(DOA)
A letter dated August 22, 1990 is being sent to reactor licensees advising them of the development of an International Nuclear Event Scale developed by 1AEA.
The letter is for information only and states NRC decision not to participate in the trial program.
Planning and preparation for the Oyster Creek Diagnostic Evaluation continued during the period August 20 - 24.
The Director, D0A, Chief DEIIB, and the designated Oyster Creek Diagnostic Evaluation Team Manager met with AE00, NRR and Region I senior management on August 20, 21, and 22 respectively to discuss the areas of focus for upcoming evaluation.
Division of Safety Programs (DSP)
A report of the results of a human factors review of a May 14, 1990 event at Nine Mile Point Unit 2 was issued August 24. The event involved a large number of operator actions in response to a loss of vacuum. The operator actions were timely and correct and served to limit the event to low safety significance.
On August 7 and 8, 1990, a human factors study team was sent to the Dresden Nuclear Power Station site to review reactor operators response to an event that occurred at Unit 2 on August 2, 1990, at 1:05 a.m.
That event involved the spurious opening of a Target Rock Valve while the plant was at 87% power, a manual reactor scram, and the subsequent cooldown of the plant at an excessive rate. The report of the results of the study is in preparation. The Dresden review was the 4th conducted under the protocol developed thru'RES by INEL.
An analysis will be performed of the overall human factors lessons obtained after'about 8 of these reviews to determine the generic lessons that may be drawn from these events as a composite.
It-is already established that current written LERs do not capture the human factors lessons very well.
AUGUST 24, 1990 ENCLOSURE D
The 1989 AE00 Annual Report has been provided to the EDO for transmittal to the Commission. The report is published in two separato parts.
NUREG-1272, Vol. 4, No. 1, covers power reactors and present an overview of the operating experience of the nuclear power industry. NUREG-1272, Vol 4, No. 2, covers nonreactors and presents an overview of the events and concerns during 1989 associated with the use of licensed rQterial in nonreactor applications.
Preliminary Notification The following Preliminary Notifications were issued during the past week.
a.
PN0-1-90-65, New York Power Authority (Indian Point 3), (Docket No.
50-286), Positive Fitness for Duty (FFD) Drug Test.
b.
PNO-I-90-66, Maine Yankee, (Docket No. 50-309), Unplanned Shutdown For Greater Than 48 Hours.
c.
PN0-1-90-67, New York Power Authority (FitzPatrick), (Docket No. 50-333),
Reactor Shutdown To Resolve Calculational Concerns In E0Ps.
d.
PN0-II-90-47, Carolina Power & Light (Brunswick Unit 2), (Docket No.
50-324), AIT Dispatched to Brunswick Steam Electric Plant, e.
PN0-Ill-90-56, North Detroit General Hospital, (License No. 21-10578-02),
Apparently Falsified Films For Diagnostic Nuclear Medicine Procedures, i
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AUGUST 24, 1990 ENCLOSURE D
Office of Governmental and Public Affairs Items of Interest Week Ending August 24, 1990 Midwest Low-Level Radioactive Waste Compact Comission Update The Detroit News reported August 16, 1990, that the Midwest Low-Level Radioactive Waste Compact Comission rejected Michigan's request for $1.9 milliontocontinutsearchingforalow-levelradioactivewaste(LLW) site.
The Comission recently voted to: urge Michigan to continue its search for a LLW site without giving it more money for the effort this fiscal year; provide
$400,000 in search money on October 1, 1990, if the Michigan Legislature eases a State law that imposes stringent environmental and health restrictions on the selection of a site; and reduce other money scheduled for Michigan unless it selects three possible sites by April 1, 1991. Also, the three existing LLW sites (Washington, South Carolina and Nevada) have already warn::d Michigan they-will shut off access to the State this fall if Michigan does not choose-specific sites for study or eese its siting criteria. The Michigan Authority tentatively had selected sites in Ontonagon, St. Clair and Lenawee counties for study, but dropped them from consideration because of the State's stringent siting criteria concerning water resource protection.
James Cleary, Comissioner of the Michigan Low-level Radioactive Waste Authority, stated he would not recomend withdrawal from the Midwest Low-Level Compact Comission until there is no chance of an agreement.
ASME Code Implementation Meeting l
Mindy Landau, State Programs, and Roland Lickus, Director, Region III State and' Government Affairs, participated in an.ASME Code implementation meeting on August 21, 1990, in Rockville, Maryland.
Representatives from EDO, NRR, RES t
Region III and SP discussed the Illinois Department of Nuclear Safety (IDNS),
proposed regulations and implementing procedures pertaining to the IDNS subagreement with NRC on ASME code activities.
Meeting on Safety of the VVER/230 Reactors H. Denton and H. Faulkner attended a meeting at DOE on August 23 to discuss instructions for the u) coming IAEA Consultants Meeting on the Safety cf VVER Model 230 Plants. Alt 1ough NRC is not participating in the meeting, Bill Horak, a DOE contractor at BNL, will attend for the United States. Mr. Horak will limit his presentation and discussion to the scope and results of the BNL evaluation. Discussion of future IAEA activities on the Model 230's should be reserved for the upcoming Advisors Group Meeting in September.
Physical Protection Bilateral to Argentina and Brazil A team of physical protection experts from NRC (GPA/IP and NMSS/SGIB).
DepartmentofEnergy(DOE)andDepartmentofDefense/DefenseNuclurAgency (D0D/DNA) met with government and private sector nuclear officials and visited installations in Argentina and Brazil from August 7-17, 1990. In addition to-presentations on physical protection programs in the_U.S. and host countries, AUGUST 24, 1990 ENCLOSURE E
the team toured the Ezeiza (CONUAR fuel fabrication >lant and RA-3 research reactor) and Constituyentes (Alpha facility) researci centers, and the Embalse nuclear power plar.t in Argentina, and the NUCLEP heavy components facility, Angra I nuclear power plant, and IPEN (IEA-R1 research reactor) research center in Brazil.
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 for Data Processing Development Division of Safeguards Information Treatment, Department of Safeguards P-5 Systems Analyst, INIS Section, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety P-3 Reactor Engineer, INIS Section, Division of Scientific and Technical Information, Department of Nuclear Energy end Safety P-2 Database Programmer, Computer Users Support Section, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety P-5 Head, Office of Management Services, Department of Administration, Office of Management Services P-4 Nuclear Medicine Instrumentation Specialist, Nuclear, Medicine Section, Division of Life Sciences, Department of Research and Isotopes P-5 Section Head, Section for Instruments and Equipment Provision and Management, Division of Development and Technical Support, Department of Safeguards P-3 Translator (2 posts),EnglishTranslationSection, Division of Languages, Department of Administration AUGUST 24, 1990 ENCLOSURE E
B' Office of Administration Items of Interest Week Ending August 24, 1990 Significant FOIA Requests Received by the NRC for 5 Day Period August 17 - August 23, 1990 Request for four categories of records regarding NRC systems for tracking data of staffing time by NRC employees. (Susan Long, Transactional Records Access Clearinghouse,SyracuseUniversity,F01A-90-370)
Request for the results of air sampling at the Beryllium Corporation located in Ashmore, Pennsylvania. (Richard Frey, F01A-90-373)
Request for copies of contracts recently awarded to U.S.' Testing, IT Corporation for radiological analysis of low-level mixed waste. (Michael Paessun, Wadsworth Laboratories,Inc.,F0!A-90-374)
Request for 12 categories _of records concerning AEC's licensing of Union Carbide Corporation to mine uranium oxide in or around the areas of Uravan, Rifle, and Maybell, Colorado between the years 1946 and 1975. (Andrew KochanowskiofLord,Bissell'& Brook,F01A-90-375)
Request for two categories c.f records regarding Below Regulatory Concern Policy. (Michael Veiluva, Western States Legal Foundation, F01A-90-376) l AUGUST 24, 1990 ENCLOSURE G
Office of Information Resources Management Items of Interest Week Ending August 24, 1990 -
Emergency Notification System (ENS)
NRC staff from the Office of Information Resources Management, Telecommuni-cations Branch, visited Calvert Cliffs Nuclear Plant on August 23, and visited the North Anna Nuclear Plant on August 24 to finalize the checkoff sheet that will be used at all nuclear plants to verify Emergency Notification System (ENS) installations. These surveys will be used to determine present con-figurations, o)erational status, quantities of spare-equipment, and require-ments for purciase of new equipment.
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AUGUST 24, 1990 ENCLOSURE H
Office of Personnel I
Items' of Interest Week Ending August 24, 1990 i
Pilot Career Develooment Initiative Proaram Staff from the Offices of Personnel and Small and Disadvantaged Business Utilization and Civil Rights conducted a series of meetings on August 22 and 23 to explain the Pilot Career Development Initiative Program to implementing team members and supervisors from NRR and NMSS.
This program is designed to help employees improve their Individual Development Plans. About 35 individuals attended the meetings.
Recruitment Staff Focus on Hirina Continues Several NRC employees attended a Blacks in Government, Inc. training conference in Kansas City, M0 on August 22-25.
Participants at the conference were encouraged to consider employment with the NRC.
Representatives were Cordell Williams, NRR, Reggie Mitchell, OP and Duane Potter, OP.
Fifty applicants expressed interest, of whom six were interviewed.
Four are of interest to the NRC.
NRC staff also participated in the Women in Energy Conference and held an open house / job fair in Chicago, IL on August 24-25.
Representatives were Frank l'
Elizondo, OP, Peggy Shaw, R II, John Surmeier, NMSS, Cindy Pederson, R-III, Evelyn Matson, R-III, and Brenda Mozafari, NRR.
Thirty-four applicants were interviewed with interest in 16.
NRC participated at the Nuclear Ventures Job Fair at-Groton, CT on August 25.
Representatives were Jude Himmelberg, OP, Peter Prescott, NRR, and William Raymond, R-I.
Twenty-five applicants were interviewed with interest in five.
Comouter-Based Trainina Featured at Conferenc.g Carolyn Bassin (Training, Development and Employee Assistance),' attended the i
Society for Applied Learning Technology (SALT) Conference held at the Washington, D.C., Marriott August 22-24. The exhibit included vendors of interactive videodisc and computer-based training software.
Arrivals TAYLOR, Susan Contracts Negotiator (PFT)
ADM GREENE, Susan Health Physicist (PFT)
NMSS JOHNSON, Ima Secretary (PFT)
NMSS ROBINSON, Debra Secretary (PFT)
NMSS HERB, Isabel Technical Intern (PFT)
NRR IBARRA, Jose Electrical Engineer (PFT)
NRR ST0KES, Catherine Technical Intern (PFT)
NRR AUGUST 24, 1990 ENCLOSURE J
2-WILLIAMS, Joseph Project Manager (PFT)
NRR-FUTOMA, David Legal Intern (PFT)
OGC HOOD,' Sandra Secretary (PFT)
OGC RINER, Joyce Personnel Assistant (Typing) (PFT)
OP BAER, Edith Technical Reader (0PFT)
RES MINNICK, Sherri Health Physicist (PFT)
RI ROUGHEN,-Kevin Radiation Specialist (PFT)-
RII SALEHI, Kombiz ReactorInspector(PFT)
RIII YOUNGS, Ann Office Resident Assistant (OPFT)
RIV' Departures MOORE, Johnny Public Affairs Officer (PFT)
GPA PETERSON, Marvin A/D for International-Security (PFT)
GPA ROLES, Gary Systems Performance Analyst (PFT)
NMSS HOLDER, Ann Secretary (PFT)
NRP.
KUBIAK, Georgann Secretary (PFT)
NRR PEAC0CK, Karen Office Resident Assistant (OPFT)
RI Summer losses WILLIAMS, Cheryl Clerk (0PFT)
GPA HEDGC0CK, John Technical Intern (0PFT)
NRR NAMATH, Lisa Clerk (OPFT)
NRR PRICE, Richard Technical Intern. (OPFT)
-JOHNSON, James Clerk (OPFT)
SECY SCHLEIN, Emily Clerk (0PFT)
SECY BORBIDGE, Hugh Technical Intern (0PFT)
RI DAUBULIS, Jeffrey Clerk (0PFT)
RI l
GAGNIER, James Technical Intern (OPFT)
RI l
JAVERY, Mark Technical Intern (0PFT) ~
RII
'DUBORD, Rene Technical Intern (OPFT)
RIII DUEN0, David lechnical Intern (OPFT)
RIII JUDKINS, Tiffany C1erk (OPFT)
RIII Retirement SHEETS, Margaret Voucher Examiner (PFT)
LRI AUGUST-24, 1990 ENCLOSURE _J
l Office of Small and Disadvantaged Business Utilization and Civil Rights Items of Interest Week Ending August 24, 1990 Federal Women's Program In commemoration of the ratification.of the Nineteenth Amendnent to the U.S.
Constitution granting women the right-to vote, on August 26, 1920, the Federal Women's Program Manager developed an All Employee Announcement, signed by Chairman Carr, concerning this historic event; developed and displayed posters depicting historical women leaders and their accomplishments; and on August 23, 1990, presented two showings of the award winning video "How We Got the Vote" in the One White Flint North second floor conference rooms. Among the viewers at the first shcuing was Dr. Katharine M. Rogers, the wife of Commissioner Kenenth C. Rogers.
AUGUST 24, 1990 ENCLOSURE K, L
Office of Enforcement items of Interest Week Ending August 24, 1990 Significant Enforcement Actions 1.
An Order Imposing Civil Penalty in the amount of $450,000 was issued on August 21, 1990 to Alabama Power Company (Farley Units 1 & 2). The action was based on violations of the environmental qualification requirements of 10 CFR 50.49 and was taken under the " Modified Enforcement Policy Relating-to 10 CFR 50.49."
(EN 88-66A) 2.
A Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $20,000 was issued on August 24, 1990 to Syncor International, Chatsworth, California.
The action was based on the willful failure to follow NRC requirements concerning the preparation of radiopharmaceuticals and falsification of an NRC-required record at the Blue Ash, Ohio facility.
The staff submitted this action for Commission review in SECY 90-274, and the staff was directed to issue the action via SRM dated August 22, 1990.
(EN90-081)
Civil Penalties Paid 1.
Philadelphia Electric Company (Peach Bottom Units 2 & 3) paid the civil penalty in the amount of $75,000. The action was based on three violations identified with the design and operation of the emergency service water system. The base civil penalty of $50,000 was escalated a total of 100%
based on NRC identification of the violations and prior notice of one.of the violations. The escalation was partially offset by 50% mitigation for the licensee's prompt and extensive corrective actions resulting in a proposed civil penalty of $75,000.
(EA90-105) 2.
Northeast Nuclear Energy Company (Millstone) paid the civil. penalty in I
the amount of $25,000. The action was based on the' licensee's failure to meet a technical specification limiting condition for operations l
involving the main steam line high flow set point, as well as the failure to perform an adequate monthly surveillance test of the gas turbine generator. Though the safety significance of each item was limited, the violation was categorized at a Severity Level III due to the duration of the deficiencies and the prior opportunities'to identify and correct them.
The proposed civil penalty was mitigated by 100% due to the licensee good past performance. However, that mitigation was offset by 50% escalation of the base civil penalty for prior notice.
No further escalation or mitigation based on the other-factors is warranted.
(EA 90-084) 3.
Davis Memorial Hospital, Elkins, West Virginia paid the civil penalty in the amount of $10,000. The action was based on 24 violations including, but~not limited to, failures to:
conduct Radiation Safety Committee meetings'five separate calendar quarters, perform annual reviews of the.
entire radiation safety program, train individuals frequenting restricted AUGUST 24, 1990 ENCLOSURE L
2 areas, assay iodine-131 doses prior to administering to patients, mathe-matica11y calculate activities of radiopharmaceutical doses that were administered to patients, properly determine molynbdenum-99 breakthrough i
contamination, decontaminate, and limit radiation levels in unrestricted-areas. The violations are of very significant concern as.they indicate a lack of management oversight brought about by the careless disregard of the Radiation Safety Officer (RS0) for his duties and responsibilities as RSO and chair of the Radiation Safety Committee, (EA90-101) l l
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Office of Consolidation Items of Interest Week Ending August 24, 1990 Second Building Status The attorney for WFN Partnership indicated that he would propose language in the lease amendment during the week beginning August 27 to overcome the developer's concern about future financial liabilities should the Government 1 exercise its purchase option at the end of the fifth year.
On August 13 we reported that GSA had informed us that the appraisal update on TWFN would be completed on schedule, i.e., by August 26.
However, late.
last week, the GSA Regional Office contracts staff reported that the appraisal update will not be deliverea as promised.
Further, GSA now says that only a verbal contract existed between the appraiser, Mr. Urghardt, who died before completion of the appraisal, and GSA. The GSA Regional Counsel's office is reviewing the situation to determine whether or not a valid contract still exists and how to proceed.
0WFN - New Reg Cafe Nine outdoor tables with benches and umbrellas were delivered and installed on the south veranda of OWFN just outside the New Reg Cafe for the use of cafe patrons. The outdoor tables will accommodate 40 to 50 people.
1 AUGUST-24, 1990 ENCLOSURE M
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Region I Items-of Interest Week Ending August 24, 1990 1.
Safety System Functional Inspection at the Vermont Yankee Facility
(.
A Safety System functional Inspection was performed at the Vermont Yankee facility during the period of August 6 through 17, 1990, of the RHR service water and core spray systems. The significant findings of the inspection included the following:
1)
The licensee had performed an intarnal SSFI and determined that a current load study should be performed for the emergency diesel generators. The licensee completed the load study in April 1990 but had failed to note that the maximum loadings determined by the analysis exceeded the values specified in the monthly Technical Specification surveillance test. The analysis indicated a maximum load value of 2751 kW at a.8 power factor versus the Technical Specification value of 2500 kW at a unity power factor.
Subsequent to the Nid' identifi-cation of the discrepancy, the licensee successfully load tested.the diesels to the higher values.
l 2)
The team identified that the safety-related 480 volt motor control center (MCC) 8A did not have sufficient capacity to support the anticipated loads. The MCC'is rated at 600 amperes but the supply l
l breaker and cables to the MCC are rated at 400 amperes. The l
anticipated loads on the MCC are calculated to be 480 amperes.
s 3)
The RHR service water pump motor coolers for all four pumps' drain into a common discharge pipe that has a: shutoff valve installed.
Any inadvertent blockage of the. pipe or accidental closure of the -
valve will disable the RHR service water pumps for both trains.
2.
Meeting With Greenpeace, August 21 in Philadelphia At the request of Greenpeace, Jim Prell and Malcolm Knapp of Region I met with approximately 25 members of Greenpeace at the Greenpeace office in l
downtown Philadelphia on August 21. Mr. Prell and Dr. Knapp answered a L
number of. questions concerning releases of radioactivity from nuclear I
plants, actions NRC has taken since Three Mile Island to update reactor safety, and recent NRC actions on wastes below regulatory concern.
The audience was courteous and the meeting was positive.
3.
Nine Mile Point Unit 1 l
At 6:45 p.m., 8/19, Nine Mile Point Unit 1 operators inserted a mar.ual scram from 20% power in response to high vibrations during main turbine torsional testing. When turbine vibrations exceeded 10 mils, the turbine was-tripped and condenser vacuum broken to rapidly decelerate the turbine. As an auto-
.matic reactor scram would have occurred,due to11oss of condenser vacuum, AUGUST 24, 1990 ENCLOSURE N rwgq w
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the operators manually scrammed the reactor. Later examinations of turbine bearings found them to bo acceptable.
Niagara Mohawk has been advised by GE that slight rubbing of the turbine rotor at the low speed (100 rpm) could have caused the observed vibrations.
Following repair of a turbine bearing on 8/10, the turbine had performed acceptably for six days prior to the turbine overspeed trip test on 8/17.
4.
Fitzpatrick.' Reactor Shutdown to Resolve Calculational Concerns in E0PS On August 21, 1990, the New York Power Authority (NYPA) initiated a voluntary shutdown while resolving calculation concerns in the emergency operating procedures (EOPs).
Fitzpatrick is a BWR-4 with a Mark I contain-ment. Previous analyses of the drywell vent valves had used assumptions for severe accident performance determination that NYPA recently found to be incorrect.
NYPA concluded that the incorrect assumptions could impact the operator's ability to vent the drywell under some very low probability severe accident scenarios. The acceptability of the drywell vent valves under all design basis conditions is not affected.
Since NYPA was unable to establish conservative guidance to the operators until revised calculations are completed, NYPA decided that a reactor shutdown was appropriate.
AUGUST 24, 1990 ENCLOSURE N
7 _ _ _
Region II Items of Interest Week Ending August 24, 1990 1.
Virginia Electric & Power Company On August 20, with North Anna 2 at 50 percent power, in coast down for a December 7 refueling outage, and a known problem concerning primary to i
secondary leakage, the leakage frca "B" steam generator increased to approximately 39 gpd. At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, power was reduced to 30 percent and leakage decreased to 7 gpd.
At 0323 hours0.00374 days <br />0.0897 hours <br />5.340608e-4 weeks <br />1.229015e-4 months <br /> on August 21, 1990, as a conservative measure and since it was not considered economical to operate at this power level before starting the scheduled outage, the licensee management made the decision to start their outage three weeks early and the unit was shutdown.
No Technical Specifications limits were exceeded during this event. Currently, the unit is in Hot Standby with very litt.el primary to secondary leakage.
With this current run, Norti Anna Unit 2 set a new record for all Westinghouse units with 47J days of continuous operation. At shutdown, they were seven days short of the '.ight-water reactor world record of continuous operation without a shutdown.
2.
Georgia Power Company On August 21 and August 22, Commissioner Curtiss and his Technical Assis-tant were on a site familiarization visits of Georgia Power Company's Plant Vogtle and Plant Hatch. They were accompanied by the Regional Administrator at the.Vogtle site and.the Projects Division Director at the Hatch site, 3.
Carolina Power and Light Company On August 20,-1990, anAugmentedInspectionTeam(AIT)wasdispatchedto the Brunswick Steam Electric Plant to investigate the circumstances surrounding a Unit 2 reactor trip-that occurred on August 19. 1990, at 9:54 p.m.
The unit tripped from _100 percent power when the main steam isolation valves went closed due to an inadequately performed / controlled I
surveillance test. Several safety relief valves failed to open on in-creasing reactor pressure and reactor core isolation cooling system tripped on what appeared to be related to valve thermal overload.
In addition, other equipment failures also occurred. The unit has been taken to cold shutdown in order to effect repairs. Preliminary Notification (PNO-II-90-47 and 47A) discusses the event in great' detail.
On August 23, the Regional Administrator, accompanied by selected Regional staff members, met at the Carolina Power & Light Company's Brunswick facility to discuss their Integrated Action Plan.
l AUGUST 24, 1990 ENCLOSURE N
4.
bpscock and Wilcox-NNFD Facility On August 20-24 a nuclear criticality safety appraisal was conducted at the Babcock & Wilcox - NNFD facility in Lynchburg, VA. The appraisal team consisted of specialists from the Region II office and headquarters NMSS.
The licensees nuclear criticality program was found to be adequately implemented and the licensee was responsive to NRC team recommendation, j
The Chief, HMSS Fuel Cycle Safety Branch and the Region II, Director of i
the Division of Radiation Safety and Safeguards attended the closecut meeting.
5.
Southeast Utility Manager's Meeting On August 24, the Regional Administrator and the Acting Director, Division of Reactor Safety, attended the Southeast Utility Managers Meeting in Raleigh, North Carolina.
6.
River Bend Tabletop Exercise On August 28, 1990, two representatives from the Division of Radiation Safety and Safeguards will be attending the River Bend Tabletop Exercise in Baton Rouge, Louisana. The purpose of the Tabletop is to examine selected issues related to utility, local, State, and Federal offsite response activities in the post-emergency time frame.
Participants and observers will be present from numerous utility and governmental organi-zations.
4 AUGUST 24, 1990 ENCLOSURE N
4 Region III Items of Interest Week Ending August 24, 1990 i
l 1.
LaSalle, Units 1 and 2 Dr. Carl J. Paperiello, Deputy Regional Administrator, and members of his staff met with the Commonwealth Edison Company corporate and LaSalle site health-physics organizations to discuss the licensee's. followup actions to the NRC's special ALARA Team inspection report of June 6, 1990. =The licensee's presentation focussed on short and long term commitments to improve its ALARA program including training and staffing-improvements, ALARA integration into maintenance and engineering cobalt reduction program, and participation on the GE Owners Group ALARA Committee.
j 2.
Kerr-McGee, West Chicago On August 23, 1990, Thomas Combs, Office of Congressional Affairs, aeraepenied by D. J. Sreniawski and R. M. Lickus from Region-III toured the Kerr-McGee Chemical Corporation, West Chicago Rare Earth TAG) pproximately 15.to 20 members of the Thorium Actionrequested t facilit A
Group (y.
at the entrance to the site. TAG representatives expressed their views relative to the disposal of wastes-in West Chicago-and on the issue of Illinois obtaining regulatory jurisdiction from.the NRC over the material in question.
3.
Zion Nuclear Power Station 1
Mr. A. Bert Davis, Regional Administrator, Region III, and other members of.
the Region III staff met with licensee management at the site on August 21, 1990, to discuss progress of the licensee's Performance Improvement Program and recent DET findings. The licensee has identified areas requiring improvement and is formulating the organization and-staffing plans to deal with the issues. The licensee will present their. plans to Region III management on September 17, 1990. A concern regarding the excessive use of overtime was pursued.
As a result,.the Senior Vice President has requested a meeting on August 27, 1990, with the Regional Administrator to pursue the matter further, 4
4.
Prairie Island Nuclear Generating Station On August 23, 1990, at 3:00 p.m. CST,.the licensee declared an unusual event based on s loss of the NSSS annunciator system in the. control room.
The annunciator system was lost for 17 minutes but the plant process computer system which duplicated the panel alarms remained _ operable and ESF initiation systems were unaffected. The unusual event was terminated at 5:45 p.m. following repair and testing of the annunciator system. The cause was the failure of the K-1 relay in the power supply logic for the Unit 1 NSSS annunciator system. The SRI observed the troubleshooting, repair, and testing activities. The K-1 relay for Unit 2 was inspected and found to be without problems.
1 AUGUST 24, 1990 ENCLOSURE N
5.
D. C. Cook Nuclear Plant A supplemental maintenance inspection effort'that' spanned 5 months was concluded this week. This inspection was conducted by the Region III DRP personnel with increased support from the resident staff as well as some involvement of DRS. Many improvements in maintenance support systems have been developed and implementation will-begin in the near future.
Implementation was delayed due to the need to have a stable organization during a recent outage.
6.
Clinton Nuclear Power Station On August 23, 1990, Commissioner Rogers visited the Clinton Power Station.
He was accompanied by Edward Greenman, Director, DRP; John Hickman, NRR, and the resident inspectors.
7.
Fermi 2 Nuclear Plant A Senior Management meeting was conducted in Region III between Detroit Edison Company personnel, A. Bert Davis, Regional Administrator, and
' Edward Greenman, Director, Division of Reactor Projects.
Recent organizational changes and the licensee's performance indicators were discussed. Licensee performance has been and continues to be good.
8.
Self-Assessment Workshop On August 23, 1990, A. Bert Davis, Regional Administrator, addressed a Self-Assessment Workshop sponsored by the Cleveland Electric Illuminating Company on the subject of self-assessments.
The meeting was attended by about 50 people representing utilities nationwide.
AUGUST 24, 1990 ENCLOSURE N
Region IV Items of Interest August 24, 1990 1.
Western Nuclear, Inc. Meeting with URF0 At the request of Western Nuclear, Inc. (WNI), the Acting Director of URF0 and select members of the technical staff will meet on August 27, 1990, with WNI to discuss air monitoring requirements at their Split Rock Mill near Jeffrey City, Wyoming. WN! is currently decommissioning the facility and is encountering difficulties maintaining power to the remote. air monitoring locations. They are therefore requesting that alternative monitoring requirements be evaluated, such as a-24-hour sample period l
rather than continuous sampling.
2.
Fort Calhoun Station On August 24, 1990, at 4:19 p.m., the Fort Calhoun Station commenced a controlled shutdown from 100 percent power. The shutdown was ordered due to a suspected blockage of the Reactor Coolant Pump RC-3A pressure breakdown orifice between the lower and middle seals. The licensee will replace the seal cartridge on RC-3A, and perform other maintenance during this mini outage which is expected to last approximately 7 days.
l l
l AUGUST 24, 1990 ENCLOSURE N
ITEMS ADDREhiD BY THE COMMISSION - WEEK ENDING AUGUST 24, 1990 A.
STAFF REQUIREMENTS - BRIEFING ON ESSENTIALLY COMPLETE DESIGN ISSUE 'FOR FART 52 SUBMITTALS (SECY-90-241), 2:00 P.M., WEDNESDAY, JULY 18, 1990, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to James M. Taylor, EDO and.
William C. Parler, GC dated 8/22/90 The Commission was briefed by the NRC staff on the implementation of Part 52 with respect to an essentially complete design.
The Commission-requested the staff to provide a paper in advance of each semi-annual briefing addressing current 2= sues pending resolution, any changes in schedule, specific accomplishments in the six months preceding the briefing,'the current critical path, and projected personnel resource needs for the next six mor.ths, including any anticipated personnel resource shortages.
The' staff is already committed to provide a semi-annual briefing on the progress of design certification reviews (SRM M900427' dated 6/18/90).
In addition, the Commission requested a paper describing the advantages and disadvantages of the two-tier approach proposed by industry for design certification.
The Commission also requested staff's recommendations on those structures, systems and components for which it may not be feasible or practical to achieve a level of design detail in the application consistent with levels 1 and 2 described by the staff in SECY-90-241 and why it is not feasible or practical to supply such design detail.
Staff should also advise the Commission of those l
i structures, systems and components for which level 1 design detail is not necessary to achieve standardization.
Commissioner Remick, while strongly supporting the=need for-standardization, believes that there is a need for some controlled flexibility, beyond what Section 50.12 permits, to.
provide for technological advancement, component unavail-ability, and construction deviations.
Commissioner.Remick requested the staff to consider the pros and cons of incorporating an "ASARA" principle (As Standard As Reasonably Achievable) into a two-tier approach to provide such flexibility while preserving standardization throughout the life of a certified plant.
The-staff should provide the Commission an analysis of the public comments received on SECY-90-241.
The staff should provide the Commission a description of what, specifically, is envisioned.in the " standardization portion" of the review, as that term is used in SECY-90-241, including a description of the process that the staff will use for collating the experience gained from existing reactors and applying those lessons in the review of future designe.
AUGUST 24, 1990 ENCLOSURE P
B, STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 9:30 A.M., THURSDAY, AUGU5T 16, 1990, COMMISSIONERS' CONFERTR f ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTfhFMCE) - SECY to James M. Taylor, M and William C. Parler, GC dated 8/22/00 "
1.
SECY-90-255 - Pittal Rule on Informal Procedures for Reactor Operator and Senior Reactor Operator Licensino Adiudications l
The Commission, by a 4-0 vote, approved a final rule which provides procedures for the use of informal adjudication l
procedures in nonenforcerent operator licensing proceedings.
The rule also includes express permission for an applicant to l
include within the request for a honring a request that the l
presiding officer recommend to the (ommission that procedures other than those specified in Subpare. L be used in the proceeding.
The Federal Register Notice should be revised to incorporate the attached changes (Attachment 1), reviewed by the Regulatory Procedures Branch ADM, for consistency with Federal Register requirements, and forward to SECY for signature and publication.
II.
SECY-90-209 - Final 1990 Waste Confidence Decisions and Amenoments to 10 CFR Parts 1 l
The Commission, by a 4-0 vote, approved issuance of the final
" Waste Confidence Decision Review" and final conforming aMGndments to 10 CFR Part 51 subject to the attached tredificotiO60 (Attachment 2).
The Federal Register Notice should be revised as noted, and forwarded for r
.tre and publication.
l l
Attachments:
Not included l
l AUGUST 24, 1990 ENCLOSURE P
M8 NRT MEETING NOTICES August 24, 1990 m?
APPLICANT /
NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT g DATE/ TIME 9/5/90 50-416 One White Flint North Meeting with Entergy Operations NRC/SERI L. Kintner 9:00 Room 108-13 to discuss program for testing motor operated valves per Generic Letter 88-10.
9/5/90 50-266/
One White Flint North Meeting with Wisconsin Electric NRC/WEPCO R. Samworth 1:00-4:00 301 Room 14B-11 Power Company plans for the installation of the additional emergency diesel generators and extra station batteries.
9/12/90 50-382 One White Flint North Meeting with Entergy Operations, NRC/EO,Inc.
D. Wigginton 10:00 Room 98-13 Inc. to discuss proposed security changes to vital areas and to l
the personnel access.
9/19/90 50-219 One White Flint North Meeting with GPU Nuclear NRC/GPUN A. Dromerick 10:00-5:00 Room 14B-11 Corporation to discuss matters related to the Oyster Creek Drys. ell Corrosion problem.
- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document l
Q rooms.
C 492-7424.
S A listing of these meeting notices can be obtained by calling c
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August 24, 1990
' g NMSS Meeting Notices
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Division of Industrial and Medical Nuclear Safety
-*w Docket Attendees /
Date/ Time Musber Location Purpose Applicant NRC Contact 8/27-29 Irving, TX To attend all Agreement NRC G. Sjoblom (RIV)
States 1990 Special Topics Workshop 8/28 70-143 OWFN 2F-17 To discuss Nuclear Fuel NRC G. Bidinger 9-12:00 p.m.
Services, Inc. (NFS)
NFS Nuclear Criticality Safety Program 8/28 Chicago, IL Public Meeting on BRC MRC J. Glenn Policy 8/28 72-9 Ft. St. Vrain Meeting with Public NRC
- 5. Ruffin site Service Company (PSC)
PSC of Colorado re: ISFSI 9/18 OWFN 88-11 Presentation by Elekta MRC J. Schlueter Instruments, Inc.
Elekta Instruments, Inc.
FDA CRCPD 9/18 King of Prussia, PA Public Meeting on BRC NRC J. Hickey 9/20 Atlanta, GA Public Meeting on BRC MRC J. Hickey 9/25 Arlington, TX Public Meeting on BRC NRC J. Hickey 9/27 Dakland, CA Public Meeting on BRC NRC J. Hickey n
Division of Low-level Waste Management and Decommissioning Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact 7
_., 8/28-29 Chicago, IL DOE National LLW NRC J. Surmeier Conference o
9/4-8 Oakland, CA NRC/ EPA Mixed Waste NRC R. Boyle Workshop 9/11-14 Omaha, Nebraska To conduct training for NRC J. Shaffner the State of Nebraska licensing LLW facilities 9/19 OWFN 2F-21 Full System Chemical NRC T. C. Johnson 4
Decontamination Program General Electric Meeting Division of Safeguards and Transportation Docket Attendees /
Date/ Time Number Location Purpose Applicant _
NRC Contact 09/06 71-9231 OWFN 6B-11 Meeting on MAC-CTC MC E. Easton Spent Fuel Transport D0t.
Cask, Structural NAC Analysis Division of High-level Waste Management Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact E 8/30 OWFN Monthly management NRC J. Holonich P
Meeting with DOE DOE 8
State of Nevada C
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ro RES Meeting Notices Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact Division of Safety Issue Resolution 9/11-13/90 Pittsburgh Hilton The NRC plans to conduct a J. Chen Pittsburgh, PA workshop to discuss the IPEEE 492-3919 objectives and solicit questions and points for clarification on the draft Supplement and on the draft guidance docunent, MUREG-1407,
" Procedural and Submittal Guidance for Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities."
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30 RES Meeting Notices kh Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact C'
FIVE PUBLIC MEETINGS ON BELOW REGULATORY CONCERN The NRC will hold five public meetings in August and September to discuss its recently published Below Regulatory Concern (BRC) Policy Statement 8/28/90 Chicago, IL Charles Morelius 1:00 PM Holiday Inn - O' Hare Airport Region III 708/790-5500 9/18/90 King of Prussia, PA Marie Miller 9:00 AM Sheraton Valley Forge Convention Center Region I 215/337-50P' 9/20/90 Atlanta, GA J. Philip Stohr 1:00 PM Westin Peachtree Plaza Hotel Region II 404/331-4503 9/25/90 Arlington, TX A. Bill Beach 1:00 PM 7,rlington Convention Center Region IV 817/860-8100 4
9/27/90 Oakland, CA Ross A. Scarano 9:00 AM Holiday Inn - Oakland Airport Region V 415/943-3700 i
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Office for Analysis and Evaluation of Operational Data
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Docket Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact E
08/27/90 DOT Meeting of NRT Response Committee AE00, DOT, Other R. Hogan to develop agency responsibilities Federal Agencies for a catastrophic spill 08/27-28 Forked River, Trip to Oyster freek Nuclear C. Grimes (MRR)
New Jersey Generating Plant as preparation for S. Rubin Diagnostic Evaluation 08/27-28 TTC NRC Inspection Manual Chapter NRR, AEOD and K. Raglin Chattanooga, 1245 (Inspector Qualifications)
Regions I-V E. Butcher (NRR)
TN Review Group Meeting 08/28 and Baton Rouge, Post-Emergency Table Top Exercise AE00, States E. Weinstein 09/18 LA at the River Bend Facility local Parishes, Federal Agencies 08/29 TTC Training Advisory Group (TAG)
NRR, MMSS, RES, GPA, AE00, K. Raglin Chattanooga, Meeting OP, Regions I-V TN 08/30 DOT National Response Team Meeting AE00, EPA, Coast Guard, R. Hogan Other Federal Agencies 4
i 09/06 Operations Exercise with CE Facility.in AE00, RIII, Licensee E. Weinstein Center, RII Hematite, M0 E2 5:
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E July 20, 1990 Region I Meeting Notices Docket Attendees /
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Date/ Time Nu4 er Location Purpose Applicant NRC Con +.act S
09/05/90 070 15125 RI Office Enforcement Conf.
Selected NRC Staff Shanbaky 9:30 a.m.
Members & Licensee 09/06/90 50-293 Plymouth, MA Pilgrim - Status of MRC Staff and the Rogge 7:00 p.m.
Emergency Preparedness Public 09/19/90 50-354 RI Office SALP Board Meeting Selected NRC Staff Swetland 9:00 a.m.
Hope Creek - SE&G Meders 09/20/90 50-272/
RI Office SALP Board Meeting Selected NRC Staff Swetland 9:00 a.m.
50-311 Salem - PSE&G Members 09/21/90 030-08572 RI Office Enforcement Conf.
Selected RI Staff Kinneman 11:00 a.m.
Meders & Licensee G
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A: gust 24, 1990 RII MEETING NOTICE 8
00CKET 1
ATTENDEES /
.DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 08/27/90 RII Office 3
1:30 p.m.
Enforcement Conference Licensee, DRA, and M11hoan General Electric Company selected RII staff members 08/29/90 Jackson, MS Meeting with Entergy Licensee, RII and Ebneter 9:00 a.m.
64 rations to discuss RIV Administrators corpo ?te philosophy 08/30/50 Woodbridge, Enforcement Conference Licensee and selected Stohr 1:00 p.m.
Virginia Tri-State Associates, Inc.
RII staff members 09/05/90 RII Office Enforcement Conference Licensee, RA, and Ebneter 10:00 a.m.
Georgia Power Co. - Vogtle selected RII staff members f
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Region III Meeting Notices c$
Docket Attendees Date/ Time Number Location Purpose Applicant MRC Contact my 08/28/90 50-483 Region III Union Electric Co.,
Licensee. Director, Division Greenman 9:00 a.m.
Callaway - Management of Reactor Projects and Meeting selected members of RIII Staff Holiday Inn O' Hare Below Regulatory Deputy Regional Paperiello 08/28/90 1:00 p.m.
Chicago, IL Concern Workshop Administrator, selected members of RIII Staff, Licensees and General Public 08/29/90 Region III Alt & Witzig -
Licensee, Deputy Regional Morelius 10:00 a.m.
Enforcement Conference Administrator and selected members of RIII Staff 09/05/90 50-254 Region III Commonwealth Edison Licensee, Regional Greenman 10:00 a.m.
50-265 Co., Quad Cities -
Administrator and selected Enforcement Conference members of RIII Staff Region III Materials Accident Licensee, Deputy Regional Morelius 09/06/90 Exercisc - Combustion Administrator and selected Engineering members of RIII Staff 09/11/90 50-?'TJ Monticello Northern States Poe r Licensee, Regional Greenman 1
9:00 a.m.
Company, Monticello -
Administrator and selected Systematic Assessment members of RIII Staff of Licensee Perforrance E
P S
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_. -, -. - _ - _ _ - - _. _ - _ _ _ _ _ _ _ _ - _ ~ _
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Regios IV Meeting Ilotice 5 August 24,1990
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Attemlees/
u" Docket Npt Contact l
,.2 Dst;/ Time Humber Location Purpose Applicant 9
M Jackson, MS Meeting with Entergy W. Cavanaugh R.ftertin e
. E C/29/90 j
Executive Staff 3
(9:00) 9/12/90 50-298 Region IV At NPPO's regeest to introduce NPPD management G. Constable t
new CWS plant management and status of NPPD training program.
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h Region V Meeting Notice
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Docket.
Attendees /
Date/ Time Number Location Purpose Applicant NRC Contact o
l 9/24/90 50-206 San Clemente Southern California Edison J. Martin P. Johnson 50-361 CA Management Meeting on SONGS R. Zinenerman 50-362 Facility.
R. Scarano i
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