ML20205Q982
| ML20205Q982 | |
| Person / Time | |
|---|---|
| Issue date: | 04/01/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-870327, NUDOCS 8704060154 | |
| Download: ML20205Q982 (31) | |
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For P b f.
April 1, 1987 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 27, 1987 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
General Counsel F*
International Programs G
State Programs H
Resource Management I*
Analysis and Evaluation of Operational Data J
Small & Disadvantaged Business Utilization & Civil Rights K*
Special Projects L*
Regional Offices M*
CRGR Monthly Reports N*
Executive Director for Operations 0*
Items Addressed by the Commission P
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
externaldistribution)
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- No input this week.
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t for Operations WEEKLYINFOREPT PDR Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING MARCH 27, 1987 Fort Calhoun Station, Unit No. 1 Fort Calhoun Station lost offsite power at 7:54am on March 21, 1987.
The plant is shutdown for refueling. The 345K line was isolated at the time. Power being supplied by the 161K line was lost when the oil fault pressure relay was inadvertently stepped on causing it to trip. The plant went on batteries for 5 minutes; diesel generator DG 1 was started manually and supplied power for 40 minutes until offsite power was restored. Diesel generator DG 2 was inoperable at the time because a new turbocharger was being installed.
D.C. Cook Nuclear Plant The licensee has informed NRR that the 6th District Criminal Court has dismissed the criminal proceedings against the Indiana and Michigan Electric Company and one individual in the material false statement on meeting the fire protection requirements.
It is our understanding that the statue of limitations had run out and could not be extended for criminal proceedings even though IMEC and the individual had agreed to extending the statue.
The civil penalty case is continuing with the licensee agreeing to l
an extension in that case until September.
FBI Visit to North Anna Facility On March 19, 1987, 22 agents of the FBI were provided with a familiarization tour of the North Anna nuclear facility by the staff of the Virginia Power Company. This tour was the result of the combined efforts of the FBI, Virginia Power and NMSS staff to improve certain aspects of contingency planning and incident response. The tour included presentations, displays and visits to key areas of the facility. This activity appears to have met its goal of providing initial familiarization with a commercial nuclear facility.
Arrangements are being made to conduct tours on an annual basis for selected FBI agents.
Mixed Low-Level Waste On Friday, March 13, 1987, Hugh Thompson (NRC) and Winston Porter (EPA) signed a Generic Letter to the states and compact regions on Combined NRC-EPA Siting Guidelines for Disposal of Mixed Low-Level Radioactive and Hazardous Waste.
This letter eliminates the possibility of states and compacts not meeting the Low-Level Radioactive Waste Policy Amendments Act obligations because of the absence of final Resource Conservation and Recovery Act location standards.
Western Low-Level Waste Disposal Compact Senator Larry Pressler, South Dakota, introduced on March 11, 1987, the Western Low-Level Waste Disposal Compact (S. 717). The House version (H. R. 1530) was introduced on March 10 by Representative Udall of Arizona.
In this compact, Arizona is the host State and South Dakota and North Dakota are the other initially eligible party States.
I
0FFICE OF ADMINISTRATION Week Ending March 27, 1987 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1986 170 53 Received, 1987 169 14 Granted 126 6
Der.ied 43 11 Pending 170 50 ACTIONS THIS WEEK Received Marjorie Aamodt Requests attachments Q through W to an OIA report.
(87-163) dated January 7, 1981, entitled, "IE Inspectors Alleged Failure to Report Information re: March 28, 1979 Hydrogen Explosion at TMI-2."
P.G. Wist, Requests copies of the bid abstract and winning proposal Shaw/ Walker for RFQ #610257.
(87-164)
Kennedy Maize, Requests all records relating to Apollo and Parks Township Union of Concerned in Pennsylvania.
Scientists (87-165)
James Flasch, Requests records regarding an incident involving a breach i
The Post-Crescent of security in July 1986 at the Point Beach nuclear power J
(87-166) plant.
Charles Openchowski Requests copies of job descriptions for attorney positions (87-167) at GS/GM levels 14-18, SES, and political appointee ranks
)
which involve full or part-time responsibility for matters concerning federal environmental laws and regulations.
Phil Jay, Requests copies of (1) NUREG-0020 from 1975 to 1987; (2)
Matthew C. Jay a list of the stainless steel pipe manufacturers for the and Associates cooling water systems at the Surry nuclear power plant; (87-168) and (3) a list of each plant corresponding to those stainless steel pipe manufacturers for the Surry plant.
CONTACT: Donnie H. Grimsley 492-7211 MARCH 27, 1987 i
ENCLOSURE A a
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Received, Cont'd Dave Airozo, Requests copies of the draft comments from FEMA concerning McGraw-Hill the NRC's proposed change in its emergency planning (87-169) rules (10 CFR Part 50).
Linda Bauman, APPEAL TO THE EDO for the release of the records denied Government in a request for records regarding the work of the Accountability Management Review Comittee of OIA Report No. 86-10.
Project (87-A-14-87-87)
Granted George Walker, In response to a request for a copy of the technical Opportunity proposal for NRC-10-86-251 which was awarded to Technical 1
Systems, Inc.
Associates, made available a copy of the nonproprietary (86-877) version of the proposal.
Frank Constantino, In response to a request for a printout containing certain General Electric infonnation on uranium shipments for the period Company January 1986 through December 1986, made available the (87-85) requested printout.
Robert Gonsky, In response to a request for copies of (1) a current ADP Businessland, list of hardware contracts for four specified items and Inc.
(2) the current ADP maintenance agreements naming the prime (87-100) contractor, made available two records.
Informed the requester that two additional records subject to this request are already available at the PDR.
Informed the requester that no agency records were located for category one of his request.
Patricia Stevenson, In response to a request for copies of all bids submitted Infonnation for solicitation number RS-ADM-87-206, made available Control Systems three records.
Corp.
(87-135) l 4
Cecilia Staudt, In response to a request for a copy of the technical j
The Information proposal submitted by Keyboard Comunications, Inc., for i
People contract NRC-10-87-174, made available a copy of the (87-155)
Abstract of Offers.
Informed the requester that solicitation RFP-RS-ADM-87-174 was issued as an Invitation for Bid, for which a technical proposal is not required.
Marjorie Aamodt In response to a request for attachments Q through W to (87-163) a January 7, 1981 OIA report entitleo, "IE Inspectors Alleged Failure to Report Information re: March 28, 1979 Hydrogen Explosion at TMI-2," informed the requester that these attachments are already available at the PDR in file F01A-84-921.
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. MARCH 27, 1987 ENCLOSURE A
3 Denied Mozart Ratner, In response to an APPEAL TO THE EDO for the release of Mozart G. Ratner, the denied portior.s of 17 records regarding a request P.C.
for records concerning General Electric's facility (87-A-2-86-704) in Wilmington, North Carolina, continued to deny these withheld portions identifyirig procedures for safeguarding licensed special nuclear material.
4 MARCH 27, 1987 ENCLOSURE-A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MARCH 27, 1987 CONTRACTS AWARDED RFP No.: RS-01E-87-121
Title:
" Training Course in Medical Uses of By-Product Material"
==
Description:==
Provide NRC materials inspectors with hands-on experience and classroom presentations in three general safety areas for the use of by-product material:
radiological health and safety procedures, personnel training and experience, and facilities and equipment.
Period of Performance: Four years Sponsor: Office of Inspection & Enforcement Status: A fixed price indefinite quantity type Contract No. NRC-05-87-121 was awarded to The University of Texas Health Science Center at San Antonio in the amount of $42,240.00 effective March 30, 1987.
RFP No.: RS-SECY-86-203
Title:
"Public Document Room Branch Long Range Plan"
==
Description:==
Develop a comprehensive five year working plan for the NRC's Public Document Room to insure that procedures, systems and services are maintained at a high level of efficiency.
Period of Performance: Five months Sponsor: Office of the Secretary Status: A firm fixed price type Contract No. NRC-17-87-157 was awarded to Joel L. Lipkin, Inc., in the amount of $19,762.00 effective April 1, 1987.
CONTRACT CLOSED OUT NRC-10-83-331 Metrocom, Inc.
ADMINISTRATIVE MATTER On March 18, 1987, Functional Management International filed a protest with the Contracting Officer under Solicitation No. RS-0RM-87-223 for
" Cost Analyses of Proposed Changes in NRC Requirements Having Economic Impact." The protest disputes the basis for excluding Functional Management International from the competitive range. The protester requests that its proposal be reconsidered. Award is being withheld pending disposition of the protest.
4 MARCH 27, 1987 ENCLOSURE A
-4 0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST '
Week Ending March 27, 1987
'Palo Verde Unit 3 The NRC anticipates issuing a low power license for Palo Verde Unit 3 -
during the week of March 23, 1987.
Fort Calhoun Station, Unit No. 1 Fort Calhoun Station lost offsite power at 7:54am on March 21, 1987.
The plant is shutdown for refueling. The 345K line.was isolated at the time. Power being supplied by the 161K line was lost when the oil fault pressure relay was inadvertently stepped on causing it to trip. The plant went on batteries for 5 minutes; diesel generator DG 1 was started manually and supplied power for 40 minutes until offsite power was restored. Diesel generator DG 2 was inoperable at the time because a new turbocharger was being installed.
j D.C. Cook Nuclear Plant The licensee has informed NRR that the 6th District Criminal Court has dismissed the criminal proceedings against the Indiana and Michigan Electric Company and one individual in the material false statement on meeting the fire protection requirements.
It is our understanding that the statue of limitations had run out and could not be extended for criminal proceedings even though IMEC and the individual had.
agreed to extending the statue.
The civil penalty case is continuing with the licensee agreeingLtc an extension in that case until September.
Palo Verde Requalification Examinations On January 27, 1987, NRC Region V administered requalification examinations to Reactor Operators and Senior Reactor Operators (SRO) at the Palo Verde NPS, Palo Verde NPS requalification training program had not previously been evaluated. During NRR's review of the operator licensing program in Region V on March 3 - 5, 1987, it was discovered that the SRO written examination was essentially identical to an SR0 examination previously administered at Palo Verde on September 23, 1986 (32 of 37 questions were duplicated). Since the licensee had been provided the September 1986 examination and answer key, the Regional Administrator concluded the SRO written portion of January 1987 examination had been invalidated. The 1
MARCH 27, 1987 ENCLOSURE B w
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examination grading and requalification program evaluation has not been completed. The remainder of the overall recualification examination activity was evaluated to be satisfactory (i.e., the RO written, the R0 and SR0 simulator and the R0 and SR0 oral exaninations).
Region V is preparing a new SR0 written requalification examiration to be administered to a randomly selected sample of Senior Operators prior to the Commission review for full power licensing of PVNGS-3.
Region V is reviewing this event and has implemented corrective action to prevent its reoccurrence.
Information regarding this event has become known to other licensees and INP0.
INPO notified W. Russell that they had received several inquiries regarding the Palo Verde requalification examination.
Palo Verde Unit 3 A low power license for Palo Verde Unit 3 was issued on March 25, 1987.
Fuel loading is expected to begin over the weekend.
MARCH 27, 1987 ENCLOSURE B
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i NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS i
REPORT FOR MARCH 23 - 29, 1987 1.
DEFUELING Attempts to remove additional partial-length fuel assemblies using the hydraulic cam clamp tool and the pole snare were unsuccessful.
Defueling teams cut fuel pins at the core drilling test pattern area i
and partially loaded two fuel canisters using the heavy duty spade bucket.
2.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results i
show that TMI site liquid effluents are in accordance with i
regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water effluents are sampled from the station (Units 1 and 2) discharge and analyzed by EPA. Gamma spectrum analyses of the seven daily composited samples for March 7 - 14, 1987 indicated no TMI-2 related radioactivity.
EPA's gamma spectrum analysis of the NRC's TMI outdoor air sample j
for the period March 19 - 27, 1987 showed no reactor related radioactivity. The EPA laboratory's lower level of detection for 1
iodine-131 and cesium-137 is about 6 E-14 uCi/cc.
The water works for the City of Lancaster composited seven daily e
samples from March 8 - 14, 1987. The gamma spectrum analysis for the composited sample performed by EPA showed no reactor related radioactivity.
3.
DECONTAMINATION ACTIVITIES Scabbling of the floor beneath the B and C bleed tanks continued.
j Desludging of the auxiliary building sump continued.
Final preparations are being made to pump sludge from the reactor j
i building basement to the auxiliary building.
4.
NRC EVALUATIONS 1
a.
Completed Revision 2 to. the Sediment Transfer and Processing Safety Evaluation Report was approved on March 26, 1987.
Coagulant Criticality Safety Evaluation Report was approved on March 27, 1987.
b.
In Progress Technical Specification Change Request numbers 49 and 51 and the associated Recovery Operations Plan Change Requests 31 and j
33.
MARCH 27, 1987 ENCLOSURE B
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Technical Specification Change Requests 52, 55 and 56.
Solid Waste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Processed Water Disposition Proposal.
Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 3.
Pressurizer Defueling Safety Evaluation Report.
Safety Evaluation Report for Defueling of the Core Support Assembly.
Seismic Evaluation for Modified Containment Penetration.
5.
MEETING On the evening of March 25, 1987, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a'public meeting at the Holiday Inn, Harrisburg, PA. At this meeting the Panel received presentations on the issue of Accident-Generated Water Disposal from Drs.
R. Piccioni and E. Sternglass. Statements from Drs. M. Kaku and C.
Johnson were read at the meeting by members of the Susquehanna Valley Alliance. The Panel alsc received a number of public comments on the licensee's proposal for the disposal of accident-generated water.
The Panel voted 8 - 2 finding the NRC staff's draft supplement to the PEIS an acceptable evaluation of alternatives and environmental impact.
The Panel voted 5 - 4, with one abstention to not endorse the licensee's proposed eva'poration option for water disposal. The Panel also voted 10 - O against any discharge of the water to the Susquehanna River.
The next meeting of the Advisory Panel is scheduled for April 16, 1987 in Washington, DC, before the NRC Commissioners. The meeting will be open to the public and will address processed accident-generated water disposal.
Persons desiring to speak before the Panel are requested to contact Mr.
Thomas Smithgall at 717-291-1042, or write to him at 2123 Marietta Avenue, Lancaster, PA 17603, so that they may be placed on the meeting agenda.
MARCH 27, 1987 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest 4
Week Ending March 27, 1987 Advanced Nuclear Fuel Corporation On March 17-18, 1987, M. Horn and E. Shum visited the Advanced Nuclear Fuel (ANF) facility in Richland, Washington.
The purpose of the visit was site familiarization and to discuss additional information to conduct the environmental assessment related to ANF's license renewal and incinerator operation.
Staff was given a complete tour of the facility while there.
Sequoyah Fuels UF To UF Facility g
4 On March 25, 1987, the Division of Fuel Cycle and Material Safety (FC) staff issued a license amendment to Sequoyah Fuels Corporation (SFC) authorizing the conversion of depleted uranium hexafluoride to depleted uranium tetrafluoride.
The SFC amendment request transmitted by letter dated January 24, 1985, was the subject of an informal hearing held in Sallisaw, Oklahoma, the week of January 11, 1987.
Judge J. H. Frye, III, the presiding officer, ruled that the l
i amendment authorizing the conversion of UF to UF could be issued by staff 6
4 subject to the following conditions:
1.
Within one month following issuance of the license amendment, SFC is to ascertain whether all residences within a two mile radius of the facility have telephones and make provisions acceptable to Staff to notify any that do not; 2.
SFC is to verify that all telephone numbers listed in its emergency response plan are accurate at each major exercise of the plan; 3.
SFC is to maintain the level of staffing outlined at Tr. 556-61 unless a 4
change is authorized by Staff, and SFC is to promptly report to the staff any significant changes in the duties as described on those transcript pages; and 4.
SFC's President and its General Manager each are to spend at least one full workday each month at the UF4 production facility while it is in operation.
NMSS and Region IV staff have incorporated 11 additional conditions related to health and safety into the license amendment.
MARCH 27, 1987 ENCLOSURE C
2 Meeting With Member of Italian Nuclear Regulatory Authority At the request of IP, an NMSS staff member met on March 23, 1987, with Mr. T.
Ciancolo, a member of the Italian nuclear regulatory authority.
Mr. Ciancolo explained that the Italian authority is expecting an application for at-reactor-site dry spent fuel storage.
Such storage would be in GNS CASTOR type casks. NRC dry storage licensing experience under 10 CFR Part 72 and CASTOR V/21 cask design approval were discussed.
At Mr. Ciancolo's request, copies of the Part 72 license for the Surry dry cask Independent Spent Fuel Storage Installation with SER and the SER for the CASTOR V/21 cask have been mailed to him.
Policy Statement and NUMARC Guidelines on Access Authorization Staff has analyzed the NUMARC response to questions concerning the screening of temporary workers.
A memorandum is in preparation to the EDO recommending approval of a Commission Paper transmitting the Policy Statement and Guidelines to the Commission.
73.71 Safeguards Reporting Requirements With the exception of one item, all CRGR suggestions have been accommodated in the final rule package.
SG, CRGR and IE staff are working to resolve the remaining issue so that the package can be submitted to the EDO for approval and publication.
FBI Visit to North Anna Facility On March 19, 1987, 22 agents of the FBI were provided with a familiarization tour of the North Anna nuclear facility by the staff of the Virginia Power Company.
This tour was the result of the combined efforts of the FBI, Virginia Power and NMSS staff to improve certain aspects of contingency planning and incident response.
The tour included presentations, displays and visits to key areas of the facility.
This activity appears to have met its goal of providing initial familiarization with a commercial nuclear facility.
Arrangements are being made to conduct tours on an annual basis for selected FBI agents.
Low-Level Radioactive Waste Disposal Issues On March 27, 1987, G. C. Pangburn will make a presentation on "LLW Disposal:
The Role of the U.S. Nuclear Regulatory Commission" at a roundtable program on Low-Level Radioactive Waste Disposal Issues in Wisconsin.
The program will be held at the University of Wisconsin and is sponsored by the Wisconsin Public Utility Institute and the Institute for Environmental Studies. Mr. Pangburn's presentation will address the development and structure of 10 CFR 61 and the licensing process for a new low-level waste disposal facility in a non-Agreement State.
I MARCH 27, 1987 ENCLOSURE C
3 Mixed Low-Level Waste On Friday, March 13, 1987, Hugh Thompson (NRC) and Winston Porter (EPA) signed a Generic Letter to the states and compact regions on Combined NRC-EPA Siting Guidelines for Disposal of Mixed Low-Level Radioactive and Hazardous Waste.
This letter eliminates the possibility of states and compacts not meeting the Low-Level Radioactive Waste Policy Amendments Act obligations because of the absence of final Resource Conservation and Recovery Act location standards.
On Monday, March 16, 1987, Sher Bahadur presented an overview of NRC's perspective on mixed low-level waste at the Atomic Industrial Forum Fuel Cycle Conference '87 held in Boston.
He represented NRC on a mixed low-level waste panel at the conference.
1 I,
MARCH 27, 1987 ENCLOSURE C
Office of Inspection and Enforcement Items of Interest Week Ending March 27, 1987 1.
Items of Interest None.
2.
Civil Penalties Paid 1.
Professional Consultants (Missoula, MT) in the amount of $1,000 based on violations involving failure to control licensed material, failure to provide shipping labels, and failure to maintain exposure records.
(EA86-140) 2.
Marcus Daly Hospital (Hamiltion, MT) in the amount of $1,250 based on a violation involving an unauthorized user.
(EA 87-06) 3.
The following Significant Enforcement Actions were taken during the past j
week:
i 1.
A Notice of Violation and Proposed Imposition of Civil Penalty was 4
issued to Cintichem, Inc. (Tuxedo NY) in the amount of $12,500.
This action was based on numerous health physics violations indica-l tive of a lack of attention to and control of the radiation safety program.
(EN 87-22) 2.
A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Commonwealth Edison Company (Byron) in the amount of
$50,000. This action is based on the failure to obtain prior NRC approval of a change in acceptance criteria for a reactor coolant flow coastdown test from that described in the Byron FSAR.
(EN 87-23) 4.
The following IE Information Notices and Bulletins were issued during the past week 1.
IE Information Notice No. 87-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment, was issued to all nuclear-power reactor facilities holding an operating license or a construction permit.
2.
IE Information Notice No. 87-15, Compliance with the Posting Require-ments of Subsection 223B of the Atomic Energy Act of 1954, as amended, was issued to all nuclear power reactors holding a construction per-mit and all fines supplying components or services to such facili-ties.
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MARCH 27, 1987 ENCLOSURE D
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5.
The following IE Preliminary Notifications were issued during the past week:
'1 1.
PNS-I-87-04, Philadelphia Electric Company (Limerick), et. al., YOH
' Security, Inc., pleads guilty to Federal charges; agrees to $100,000 fine.
2.
PNO-I-87-23, GPU Nuclear' Corp. (Three Mile Island 1), TMI-1 Restart from Extended Outage.
i 3.
PNO-I-87-24, Philadelphia Electric Co., (Peach Bottom 3), Unplanned Shutdown in Excess of 48 Hours.
4.
PNO-II-87-19A, Florida Power & Light Company (Turkey Point 4), AIT Dispatched to Turkey Point (Update).
5.
PNO-II-87-20, Virginia Electric & Power Company (Surry Unit 2) - Unit Returning to Service.
6.
PNO-II-87-21, Soil Consultants, Inc., (Chantilly, VA); Moisture Density Gauges Damaged.
I 7.
PNO-III-87-41, Commonwealth Edison Company (LaSalle Unit 1) - Reactor Trip; Arcing in Buss Bars from Unit Auxiliary Transformer.
8.
PNO-III-87-42, Illinois Power Company (Clinton), Maintenance Outage Following Manual Scram.
I 9.
PNO-IV-87-13, Sequoyah Fuels Corporation (Gore, OK), Stiffening Ring Material of Certain UF Shipping Cylinders..
6
- 10. PNO-V-87-22, Washington Public Power Supply System (WNP-2) - ECCS System Partially Disabled.
- 11. PN0-V-87-23, Arizona Nuclear Power Project (Palo Verde 3), Palo Verde Unit 3 Low Power License.
- 12. PNO-V-87-24.WashingtonPublicPowerSupplySystem(WNP-2), Reactor Manually Tripped Due to loss of Feedwater.f {
Manually Tripped Due to Loss of Feedwater (y System, (NP-2), Reactor 13.
PNO-V-87-24A, Washir.gton Public Power Suppl Update).
- 14. PNO-V-87-25, Pacific Gas and Electric Company (Diablo Canyon 2),
Reactor Trip and Safety Injection.
- 15. PNO-V-87-26, Sacramento Municipal Utility District (Rancho Seco),
Limited Stop Work at Rancho Seco.
1 MARCH 27, 1987 ENCLOSURE D l-
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending March 27, 1987
/
i Release of the CONTAIN. Code Version 1.06 A new version of the containment system code for severe accident analysis, CONTAIN 1.06 developed at Sandia National Laboratory, has been released.
This is a major revision to the CONTAIN code, incorporating 30,000 new lines of Fortran. Users have been provided with code update and changes to the User's Manual.
s CONTAIN 1.06.is a major advance in severe accident computational analysis, mainly because it ' includes an integrated implementation of the CORCON-Mod 2 model for Molten Core Concrete Interactions (MCCI). Also coupled in is the l
Vanesa code for aerosol generation and radioisotope release from MCCI's.
With CONTAIN's integrated treatment of aerosol behavior and i
thermal-hydraulics these new features should provide for significantly improved severe accident containment analysis.
The new version also includes,significantly improved models for radiant heat i
exchange. Users now have a number of choices for the level of detail desired in calculations-involving hot surfaces and/or hot gases.
- Finally, there are a number.of minor improvements. These include a new option for removing liquid water from the atmosphere in the absence of aerosol modeling, a model for gravitational settling through flow paths (not just onto structures), replacement of the.old semi-implicit boiling calculations with full implicit coupling to thermodynamics and flows, and other improvements to the implicit flow calculations, i
ICEDF Computer Code Validation A panel peer review of thie planned ICEDF computer code validation tests was held at PNL on March 17, 1987. The ICEDF code was developed by PNL for the DES Materials Branch as part of the source term reassessment effort, i
specifically to estimate the extent of aerosol particle retention in the ice i
compartments of PWR ice condenser containment systems. The test program is to obtain particle retention data for model-data comparisons. The comparisons will be based on data from and code calculations for the PNL.
test facility that consists of a full-length (48 feet) arrangement of four i
equivalent ice columns (one control column surrounded by four half / side columns and four quarter / corner columns, square 2 ft.-6 in. side).
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MARCH 27, 1987 ENCLOSURE'E' l
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1 The review focused on planned test procedures, i.e., how tests will be per-formed and what and how data will be taken.
(Facility design was the subject of a prior peer review.) The peer panel was positive during the review that the test program appears to be a best effort toward accomplishing the task and provided several constructive suggestions which will be implemented. Test runs are scheduled to begin in April.
NRC Research on Robotics Highly Successful - Significant Worker Dose Reduction Reported - Plant Safety Enhanced NUREG/CR-4815, " Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant - Analysis of Costs and Benefits" was published by.
RES/NRC in March. The NUREG is the final report on an NRC/SBIR contract with Remote Technology Corporation in Oak Ridge, to design, construct and demonstrate a remote controlled vehicle for inspection and surveillance in radiologically controlled areas of NPPs.
The device, called SURBOT (surveillance robot), was constructed almost entirely from commercially available components.
It is equipped with high resolution TV and illumination, two-way sound communication, radiation level detectors, air sampler and a remote controlled arm capable of surface contamination sampling and light maintenance tasks. The robot can be decontaminated by high pressure spraying and can be moved between-contamination areas in a sealed transport container.
The portable control console is equipped with joystick operation of the 1
robot and arm, a TV screen for high resolution inspection, a split screen for front and rear viewing caneras, recording devices to make permanent records of inspections and con.puters for preprograming operations. Other features include location mapping of the robot in specific rooms, 3-dimensional dose-rate mapping and programmed trend comparisons, and a schematic representation of the location and orientation of the inspection camera.
The system was operated.for 5 months at the Browns Ferry Nuclear Power Plant by trained TVA personnel in real job situations. Data collected by the TVA evaluators indicate that the device can save over 100 man-rem per year at a NPP and permit more frequent and better inspections of safety related components. Other benefits include labor and protective clothing cost 4
savings, more complete surveillance data on components during power operation, improved worker safety and' decreased liability of plant operators for worker injury claims. The cost-benefit analysis concluded that the
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initial cost of approximately $160,000 will be recovered in 2 years of l
operation and the system has an estimated useful life of 10 years, MARCH 27, 1987 ENCLOSURE E
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As a result of this work for the NRC, and several other related projects.
REMOTEC was nominated for the SBA Small Business Subcontractor of the Year Award for 1987.
REMOTEC was selected es the winner of the South-East Regional award and is now contending for the national honor.
REMOTEC has begun Phase III of the SB/ program with commercialization and marketing of the device. This phase is not supported by government funds and is one indication of the success of Phase I and II. REMOTEC is marketing four optional concepts featuring SURBOT in wheeled and tracked models with combinations of inspection equipnent and operational arms.
Considerable interest is evidenced in the nuclear, defense and security markets.
In addition, REMOTEC, partly due to its success on the NRC contract, has been selected to conduct three new SBIR demonstration projects for D0D and DOE.
Recently Issued Publications Regulatory Guide 3.59, " Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations" Task WM 407-4.
Contact:
JohnStewart(301)443-7987 Regulatory Guide 3.60, " Design of an Independent Spent Fuel Storage Installation (Dry Storage)", Task CE 410-4.
Contact:
Frank Cardile (301) 443-7946 Publication to be Issued in the Near Future
Title:
Environmental Qualification of Connection Assemblies for Nuclear l
Power Plants (Draft Regulatory Guide)
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Description:==
This regulatory guide, which endorses IEEE Std 572-1985 without exceptions, provides specific guidance to comply with Section 50.49 to 10 CFR Part 50 with respect to the environmental qualification of quick disconnect connection assemblies and environmental seals.
Contact:
S. K. Aggarwal, RES 443-7840 ftARCH 27, 1987 ENCLOSURE E
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ITEMS OF INTEREST 1
OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MARCH 27, 1987 International Agency Meeting Notices The following international meeting notices supplement those announced previously:
IAEA Consultants Meeting to Review Technical Aspects of Reactivity Initiated Accidents (RIA) for All Types of Nuclear Power Reactors, April 27-30, 1987, Vienna, Austria IAEA Consultants Meeting to Review Agency Regulations for the Safe Transport of Radioactive Material, May 5-8, 1987, Vienna, Austria IAEA Technical Committee / Workshop of National Coordinators'to Improve i
the Ouality of Incident Reporting System (IRS) Reports, May 18-22, 1987, Vienna, Austria IAEA Advisory Group Meeting to Review Methodology for Assessment of Individual and Collective Radiation Doses from Radionuclides in the Environment, June 1-5, 1987, Vienna, Austria IAEA Consultants Meeting on Probabilistic Safety Assessment (PSA) for Safety Decisions, June 15-19, 1987, Vienna, Austria IAEA Technical Committee Meeting on Evaluation of Impact on Marine Biota by Dumping of Radioactive Wastes, June 22-26, 1987, Vienna, Austria IAEA Technical Committee Meeting on In-Service Inspection for Nuclear Power Plants, August 31-September 4, 1987, Prague, Czechoslovakia International Agency Vacancy Notices i
The following vacancy notices from the International Atomic Energy Agency have been posted on NRC bulletin boards:
P-4 Statistician, Section for Data Evaluation, Division of Safeguards Evaluation, Department of Safeguards P-4 Liaison Officer, Inter-Agency Affairs Section, Division of External Relations, Department of Administration P-5 Senior Radiation Protection Officer, P.adiation Protection Section, i
Division of Nuclear Safety, Department of Nuclear Energy and Safety P-5 Senior Radiation Protection Officer, Radiation Protection Section, Division of Nuclear Safety, Department of Nuclear Energy'and Safety MARCH 27, 1987 ENCLOSURE G 1
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International Agency Vacancy Notices continued P-5 Emergency Response Specialist, Radiation Protection Section, Division of Nuclear Safety, Department of Nuclear Energy and Safety P-4 Operational Safety Officer, Safety of Nuclear Installations Section, ~ Division of Nuclear Safety, Department of Nuclear Energy and Safety P-5 Senior Operational Safety Officer, Safety of Nuclear Installations Section, Division of Nuclear Safety, Departrent of Nuclear Energy and Safety P-4 Safeguards Analyst, System Studies Section, Division of Development and Technical Support, Department of Safeguards P-5 Programme Evaluator / Analyst, Office of the Director General I
i Foreign Visitors On Monday four representatives of the Italian National Connittee for Research and Development of Nuclear Energy and Alternative Energy met with representatives of NRR.and NMSS to discuss a variety of technical issues related to the licensing of U.S. facilities which are reference plants for the Italian nuclear power plants. The visitors had held i
preliminary discussions at NRC on Tuesday, March 17.
On Tuesday Peter Fraser, Staff Scientist, Ontario Nuclear Safety Review, met with Harold Denton, Jim Sniezek, Frank Miraglia and Karl Kniel of NRR and Kevin Burke of IP to identify what assistance NRC can provide i
the Ontario provincial government's review of the safety of the design, operating procedures and emergency plans associated with Ontario Hydro's CANDU nuclear power plants. Twelve technical topics were identified and ranked in order of priority for discussion. Meetings with the technical staff were scheduled for the afternoon, and follow-up discussions will be held in April when Mr. Fraser returns to Washington.
On Thursday Mr. Shin-ichi Nakagawa, the Washington Office representative of the Kansai Electric Power Company in Japan, met with Howard Faulkner and Kevin Burke of IP to discuss arrangements for Commissioner Carr's April 17 visit to the Takahama Nuclear Power Station and Maintenance Training Facility.
l On Thursday George'Liu, Director of the Science Division of the' Washinoton Office of the Coordination Council for North American Affairs (CCNAA), and Mr. Charles Peng visited the IP staff. Mr. Peng is the new Deputy Director of the Washington Office of the CCNAA Science Division.
The participar.ts discussed the American Institute in Taiwan's proposed participation in NRC's International Piping Integrity Research Group and i
the upcoming Joint Committee Meeting on Civil Nuclear Cooperation to be i
held in Taiwan.
MARCH 27,-1987 ENCLOSURE G
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK FNDING MARCH 27, 1987 2
Western Low-Level Waste Disposal Compact Senator Larry Pressler, South Dakota, introduced on March 11, 1987, the Western Low-Level Waste Disposal Compact (S. 717). The House version (H. R. 1530) was introduced on March 10 by Representative Udall of Arizona.
In this compact, Arizona is the host State and South Dakota and North Dakota are the other initially eligible party States.
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0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST i
Week Ending March 27, 1987 1.
An Engineering Evaluation report, AEOD/E703, " Loss of Offsite Power Due to Unneeded Actuation of Startup Transformer Protective Differential Relays," was issued on March 23, 1987. The study was performed to review and assess information concerning loss of offsite power for auxiliary power system designs which transfer emergency buses from a unit auxiliary transformer to a startup or reserve transfomer following a turbine generator trip. The review was initiated due to the loss of offsite power event which occurred in such an auxiliary power system design at H. B. Robinson Unit 2 on January 28, 1986. The related safety concern is that in these auxiliary power system designs the preferred power source i
1 (offsite power) to the emergency buses may be lost at a time when needed to operate safety-related electrical equipment due to direct current l
(DC) saturation of a current transformer (CT) associated with a startup or reserve transformer protective differential relay.
IE has issued an information notice (IE IN 86-87) addressing the Robinson event and DC saturation of cts associated with power transformer protective differen-tial relays.
j The report has been forwarded to NRR for their consideration in ongoing licensing reviews, and for incorporating the lessons learned from this j
event into the next revision of Standard Review Plan Section 8.2.
2.
An Engineering Evaluation report discussing the inadvertent discharge of I
coolant outside of containment at PWRs while on RHR cooling was issued on 3
March 26,1987(AEOD/E704). A total of seven operating events which occurred at different PWRs in the last nine years were identified and evaluated. The major causes of these operating events were operating procedures and personnel errors. During shutdown, while on RHR cooling, maintenance, test and other activities can create a busy working environ-ment that is conducive to personnel errors if procedures are not carefully written or followed to preclude inappropriate sequential valve operations, or if the operators are not attentive to the various evolutions in progress.
If not terminated, these operating events, involving the inadvertent discharge of primary coolant outside of containment, could progress into loss of RHR cooling events, i
These operating events were judged to have a low core damage likelihood.
However, there is a potential for offsite releases if the event and/or the pathway outside of containment is not isolated in a timely fashion, Consequently, IE was requested to consider an information notice to alert licensees to the occurrences of these events and to reduce the likelihood and severity of these events.
3.
On March 23, 1987, AEOD issued a report on medical misadministrations J
reported to NRC for the period January 1986 through December 1986. For this period, 369 of the PM0 NRC licensees authorized to perfom nuclear 1
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MARCH 27, 1987 ENCLOSURE J
medicine studies on radiation therapy reported one or more misadministra-tions. A total of 446 reports of misadministrations were reported: 438 (98%) were diagnostic misadministrations and 8 (2%) were therapy misadmini-strations. This is about the same number of diagnostic and therapy misadministrations as were reported annually for the previous five years.
Of the eight therapy misadministrations reported in 1986, four involved teletherapy, two involved brachytherapy and two involved radiopharmaceuti-cal therapy. Both the teletherapy and brachytherapy misadministrations that occurred might have been prevented by quality assurance procedures directed to verifying dose calculations, type of treatment and patient identification.
l Essentially all of the diagnostic misadministrations for 1986 involved i
either the administration of the wrong technetium-99m compound to a-patient or the administration of a technetium compound to the wrong patient. However, five diagnostic misadministrations involved the admini-stration of near therapy dosages of iodine-131 to patients. These misadmi-nistrations typically involved events in which the technologist performed a whole body iodine scan on a patient when the referring physician had ordered a thyroid scan.
4.
On March 27, 1987 AEOD issued a report on nonreactor events reported to NRC for 1986. The type of events included events on radiation exposure; lost, abandoned, and stolen material; leaking and contaminated sources; releases of radioactive material; and events involving industrial radio-graphy, manufacturing and distribution of radioactive materials and fuel cycle events (except fuel cycle events related to routine effluent'
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releases).
The report documents the review of 202 events. While most of the non-reactor events involved modest overexposures, lost or abandoned sources, j
or leaking sources, six events at NRC licensees and six events at Agree-ment State licensees were included in the Report to Congress on Abnormal Occurrences (first half of 1986).
4 The UF, cylinder rupture in January 1986 at Sequoyah Fuels was the most signifYcant event reported by fuel cycle or material licensees and has resulted in a substantial effort by NRC to review its licensing and' inspection activities in the nonreactor areas, and to address the lessons
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taught by the event. The contamination of a building at Wright-Patterson j
Air Force Base was also significant.
In that event opening and dumping an i
unlabeled waste drum to identify its origin resulted in contamination of a building. Costs of recovering from the event are estimated at $500,000.
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MARCH 27, 1987 ENCLOSURE J
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i ITEMS ADDRESSED BY THE COP 91ISSION - Week Ending March 27, 1987 i
A.
STAFF REQUIREMENTS - BRIEFING ON STATUS OF TVA, 2:00 P.M., MONDAY, MARCH 16, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE)
SECY for the Record dated 3/24/87 The Commission was briefed by TVA management on the status of its nuclear operations programs, including its handling of employee concerns.
Presentations to the Commission were made by the following TVA representatives:
- S. White
- C.H. Dean
- J. Waters
- J.E. Huston
- E. Kirkebo
- W. Brown
- E. Sliger 2
- T. Jenkins
- H. Abecrombie Chairman Zech observed that NRC concerns with TVA were shared by TVA management; he emphasized the importance of good communi-cations between TVA and the NRC and stated that the NRC relies on licensees to inform us of problems at their plants; he-observed that design issues could be the controlling factor in the restart readiness of TVA plants; and he emphasized the importance of factoring required NRC reviews into TVA schedules.
There were no requirements placed on the staff at this meeting.
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B.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 4:00 P.M., THURSDAY, MARCH 19, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. 0FFICE (OPEN TO PUBLIC l
ATTENDANCE) - SECY to W. Parler, GC dated 3/27/87 I.
SECY-87 Commission Review of ASLBP-815-511-01-ML (In the Matter of Babcock & Wilcox, Parks Township Volume l
Reduction Services Facility)
The Commission, by a 5-0 vote, approved an order in response to new information received on March 2, 1987 in connection with the Babcock & Wilcox Parks Township Volume Reduction Services Facility.
The order returns ASLBP-815-Sil-01-ML to Administrative Judge Paris for reconsideration of license condition number 2 in light of the information received from Pennsylvania and the licensee.
1 MARCH 27, 1987 ENCLOSURE P
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NRR MEETING NOTICES
- MARCH 27, 1987 O!
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APPLICANT /
ES DOCKET DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/30/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-I mance.
I 3/30/87 50-498/
Room P-To discuss the South Texas sub-NRC/HL&P N. P. Kadambi 9:00 a.m.
499 Phillips Building mittal regarding changes to methodology with respect to struc-tural analysis.
3/31/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the.confor-i mance.
3/31/87 50-155' Room P-110 To discuss resolution of the NRC/ Licensee C. S. Hinson 1
1:30 p.m.
,Phillips Building staff's concern on environmental qualification of cables in the plant.
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- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) 1
- 5 in the NRC and local public document rooms E!
A sumary of these meeting notices can be obtained by callfog 492-7424 4
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, E5 NRR MEETING NOTICES
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MARCH 27, 1987 cn DOCKET APPLICANT /
'd DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/1/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
4/1/87 50-412 Room P-110 To discuss the applicant personnel NRC/0LC P. S. Tam 10:00 a.m.
Phillips Building issues uncovered by the Seismic Qualification Review Team and the Pump and Valve Operability Review Team.
4/1/87 50-331/
Room P-118 GPC appeal meeting with NRR Mgmt. NRC/GPC G. W. Rivenbank 2:00 p.m.
366 Phillips Building GPC appealing staff position that hydrostatic pressure tests be per-formed with the reactor non-critical.
4/2/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
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- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s)
Es in the NRC and local public document rooms E
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A summary of these meeting notices can be obtained by calling 492-7424 o
3 NRR MEETING NOTICES
- 4 MARCH 27, 1987 3
0 h 7o' APPLICANT /
O DOCKET d
. DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4
4/2/87 50-334 Roem P-114 To discuss removal of control NRC/DLC P. S. Tam i.
10:00 a.m.
Phillips Building room partition and modificatiens to the control room habitability systers.
4/2/87 50-445/
Room P-110 To discuss Comanche Peak Response NRC/ Applicant A. Vietti-Cook 1:30 p.m.
446 Phillips Building Team (CPRT) Program Plan effort and corrective action programs.
4/3/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 1
8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
4/7/87 50-247 Room P-110 To discuss the upcoming Reactor NRC/ CECO M. M. Slosson 10:00 a.m.
Phillips Building Vessel Augmented Inspection.
Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) 1 in the NRC and local public document rooms A summary of these meeting notices can be obtained by calling 492-7424 9
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- =9 NRR MEETING NOTICES
- MARCH 27, 1987
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cn DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT R.B. Russell Fed.
To provide information about the NRC/0LB/
W. T. Russell 4/9/87 8:00 a.m.
Build. Atlanta, GA final revisions to 10 CFR Part 55 Reg. Reps./
" Operators' Licenses," and their Utility Reps./
implementation.
Public Members Stouffer Concourse To provide information about the NRC/0LB/
W. T. Russell 4/14/87 8:00 a.m.
Hotel Denver, C0 final revisions to 10 CFR Part 55 Reg. Reps./
" Operators' Licenses," and their Utility Reps./
l implementation.
Public Members i
Ramada Hotel O' Hare To provide information about the NRC/0LB/
W. T. Russell 4/16/87 8:00 a.m.
Rosemont, IL final revisions to 10 CFR Part 55 Reg. Reps./
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" Operators' Licenses," and their Utility Reps./
implementation.
Public Members 4/20/87 Hilton Hotel Valley To provide information about the NRC/0LB/
W. T. Russell 8:00 a.m.
Force final revisions to 10 CFR Part 55 Reg. Reps./
King of Prussia, PA
" Operators' Licenses," and their Utility Reps./
implementation.
Public Members l
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 rooms m
!M l 5 A sussuary of these meeting notices can be obtained by calling 492-7424 j
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NHSS MEETING NOTICES g
FOR WEEK ENDING: 3/27/86 g
Division of Fuel Cycle and Material Safety x
0 DOCKET ATTENDEES /
DATE/ TIE NUPEER LOCATION PURPOSE APPLICANT NRC CONTACT In$
3/26/87 Willste, 9th To meet with Sequoyah Fuels Corp.
H. Thompson (NMSS)
Crow floor conf to discuss SFC's waste management R. Cunningham (FC) room practices.
W. Crow (FC)
L. Rouse (FC)
D. Cool (FC)
J. Randolph and J. Stauter (SFC) 3/29-4/1/87 Tucson, AZ Ts attend ANS meeting.
B. Bidinger (FC)
Bidinger 3/30/87 Willste, 5th To discuss new model (M-140)
R. Odegaarden (FC)
Odegaarden DATE CHANGE floor conf spent fuel cask for shipping D. Huang, H. Lee, 9:00-Noon room Naval. reactor fuel assemblies.
W. Lake, R. Chappell, E. Easton, C. Williams, and C. Marotta (FC) l Reps fm Naval Reactors 3/31/87 Willste Meeting with Attorney from Shaw R.Cunningham(FC)
Cunningham 1:30 and Pittman and Jack McKay, L. Rouse (FC) purchaser of NFS.
R. Fonner (OGC) 4/8/87 Washington, To attend 33rd Meeting of the R. Cunningham (FC)
Cunningham l
D.C.
National Council on Radiation Protection.
4/9/97 Willste, 2nd To discuss structural analysis R. Odegaarden (FC)
Odegaarden 9:00-Noon floor conf of several packages.
C. Williams, D. Huang, m
room H. Lee, R. Chappell (FC) 3 Bill House (Chem-Nuclear) o c
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j Division of W7ste Management
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,0 DATE LOCATION PURPOSE ATTENDEES CONTACT G
4/7-9 Stockholm, Sweden GE0 VAL-87 Symposium on verification P8 rooks SCoplan and validation of geosphere 4/7-9 Somerset, New Jersey Conference sponsored by National Water MWeber MWeber Well Association on " Radon, Radium and Other Radioactivity in Groundwater:
Hydrogeologic Impact & Application to Indoor Airborne Contamination" 4/6-10 Richland, WA Meeting on BWIP Hydrologic Testing Program REBrowning JLinehan JLinehan RJohnson i
TVerma NColeman.
Division of Safeguards None m
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h March 27, 1987 P.II MEETING NOTICE g
- n9 DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT p.m.
Wilmington, NC Operator Certificate Licensee management and Grace Presentation - Brunswick Operators, and Regional Administrator 3/31-4/2/86 RII Office Fundamentals of Inspection Selected RII Staff Members Crlenjak Course 4/6/87 Baxley, GA Georgia Power Company -
Licensee representatives Ernst SALP Meeting peputy Regional Administrator and Selected RII Staff Members 4/13/87 New Hill, NC Operator Certificate Licensee management and Ernst Presentation at Harris operators, and Deputy Regional Administrator 4/16/87 RII Office Enforcement Conference Licensee, Regional Admini-Grace 3:00 p.m.
Duke Power Company -
strator, and selected RII McGuire and Catawba Staff Members 4/22/87 Huntersville, NC SALP Meeting with Duke Licensee, Deputy Regional Ernst 9:30 a.n.
Power Company - McGuire Administrator and selected RII Staff Members E
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