ML20199L076
| ML20199L076 | |
| Person / Time | |
|---|---|
| Issue date: | 07/03/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860627, NUDOCS 8607090304 | |
| Download: ML20199L076 (33) | |
Text
b( DR 8
July 3,1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 27, 1986 A summary of key events is included as a convenience to those Commissioners 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
Executive Legal Director F*
International Programs G
State Programs H
Resource Management I*
Analysis and Evaluation of Operational Data J
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L*
CRGR Monthly Reports M*
Executive Director for Operations N*
Items Addressed by the Commission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution) f
- No input this week.
/
p
//
T. A. Rehm, Assistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, E00 8607090304 e60703 492-7781 ggggc
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JUNE 27, 1986 Midland 1 & 2 On June 19, 1986 Consumer's Power notified the staff via telephone that they intend to femally request NRC to withdraw their Construction Permit. The two units are permanently cancelled for the nuclear option. The ultimate disposition cf the facility remains undecided at this date.
Materials Safety Regulation Review Study Group The Materials Safety Regulation Review Study Group (MSRR5G) is a group of independent consultants charged to take a broad overview look at NRC activities in licensing and inspection of mat'erials facilities from a number of different backgrounds and expertise. The group visited Regions III and IV during the week of June 16-20, 1986, to discuss these Regions' activities.
The group also visited with the Oklahoma State Department of Health and with officials of Sequoyah Fuels Corporation.
Sequoyah Fuels Corporation, Status of Restart By letter dated May 7, 1986, Sequoyah Fuels Corporation requested authorization to resume uranium conversion operations at their facility near Gore, Oklahoma.
The staff expects to receive a response to its request for additional information on June 26, 1986.
The staff already has under review modifications to the Radiological Contingency Plan.
The staff has prepared a plan to review the restart request which includes a restart inspection, public meeting, and Commission briefing.
Sequoyah Fuels Corporation Public Meeting The Nuclear Regulatory Commission (NRC) is considering a proposal from Sequoyah Fuels Corporation to resume uranium hexafluoride (UF ) production at its g
facility near Gore, Oklahoma.
Production has been dTscontinued since the January 4, 1986 accident.
As an adjunct to its review of the Sequoyah Fuels Corporation proposal, the NRC will hold two meeting to solicit comments from members of the public about issues related to production restart.
The meetings will be held in the Brooks-Cawhorne Gymnasium adjacent to the Gore Elementary School in Gore, Oklahoma, on July 8,1986, from 7 to 10:00 p.m. and on July 9, 1986, from 10 a.m. to 12 noon.
JUNE 27, 1986
OFFICE OF ADMINISTRATION Week Ending June 27, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 198F 478 96 Granted 309 31 Denied 80 18 Pending 270 62 ACTIONS THIS WEEK Received Catherine H. Madden, Requests copies of contracts NRC-05-86-156 and NRC Information 86-158.
Handl;ng Services (86-457)
(NRCemployee)
Requests records regarding an 0IA investigation generated (86-458) or obtained by OIA since June 2, 1968.
Don Weinstein, Requests copies of the distribution licenses for Citizen World Time Watch Company of America, Inc. and Seiko Time Corporation.
Corporation of America (86-459)
Christine Herbert, Requests a copy of a list of form codes to interpret Medi+ Physics certain information contained on the printouts provided to (86-460) her under F01A-86-401.
(An individual Requests a copy of the investigation report concerning Allegation RI-84-A-0086 relating to hine Mile Point and requesting )
a copy of the transcript of his testimony concerning the information (86-461) allegation.
Larry C. Lowe, Requests two categories of records regarding an accident Morgenstein, Ladd at the SL-1 nuclear reactor in Idaho in 1961.
& Jubelirer (86-462)
CONTACT:
Donnie H. Grimsley 492-7211 JUNE 27, 1986 ENCLOSURE A
2 Received, Cont'd Lyle Graber, Requests copies of SECY-86-119 and SECY-86-123.
NUS Corporation (86-463)
Ernest C. Hadley, Requests copies of records related to granting, denial Passman and Broida or revocation of security clearances, adjudication and (86-464) investigation of security cases, and NRC's written decisions granting, denying, or revoking security clearances.
Andrea Fell-Moody, Requests copies of the compliance records of ADC0 Molecular Genetics Services, Inc., located in Tinley Park, Illinois.
Inc.
(86-465)
Tom Dubocq, Requests copies of all reports provided to the NRC The Miami News during 1986 by INP0 regarding the Turkey Point nuclear (86-466) power plant, including a recent study on safety systems.
James E. Foster, Requests five categories of records regarding Vacancy NTEU Vice Announcement No. RIII-86-0027.
President (86-467)
Bruce E. Gellerman, Requests copies of all records within the past two years Center for regarding the production of a " Radiation Monitor Alarm" Investigative by the Radio Shack Division of the Tandy Corporation of Reporting, Inc.
Fort Worth, Texas.
(86-468)
Jay E. Silberg, Requests records regarding (1) Section 7601 of the Shaw, Pittman, Consolidated 0 minibus Budget Reconcilation Act of 1978; Potts & Trowbridge (2) identifying those costs incurred by the Commission (86-469) which are " reasonably related to the regulatory service provided by the Commission;" and (3) allocating among different classes and categories of licensees those costs incurred by the Commission which are " reasonably related to the rgulatory service provided by the Commission."
Rules," (2) pies of (1) SECY-85-381, " Insider Safeguards Alfred B. Robinson, Requests co notation sheets and comments by Commissioners Thompson, Mann and Hutson who voted on SECY-85-381 and (3) other records related (86-470) to the affirmation or modification of SECY-85-381.
Pat Costner, Requests records regarding the Sequoyah Fuels Corporation National Water proposed restart of UF6 production after the January Center accident.
(86-471)
Larry C. Lowe, Requests two categories of records regarding an accident Morgenstein, in the late 1950's in Santa Susana, California.
Ladd & Jubelirer (86-472)
JUNE 27, 1986 ENCLOSURE A
3 Received, Cont'd Anthony I. Kimery Requests copies of the specific safety regulations and/or (86-473) the NRC policy with respect to personal protection for workers in that area of UF6 processing that entails final loading.
Elizabeth H. Temkin, Referral from the 00J of three records for NRC's review Davis, Graham &
regarding the Canonsburg, Pennsylvania, Uranium Processing Stubbs Site.
(86-474) and Gene Stilp, Essential Information (86-475)
Jill C. Grice Requests two categories of records related to Harvard (86-476)
University license 20-00297-53.
Cindee Virostek, Requests copies of AEC Access Permit No.1410 and reports Kiski Valley submitted pursuant to specified part of 10 CFR for all Coalition licenses issued to the B&W facilities in Apollo and Parks (86-477)
Township, Pennsylvania.
Irwin Feerst, Requests three categories of records regarding meetings Committee of held from January 1, 1985, to the present between the NRC Concerned E.E.s.
and the Institute of Electrical and Electronics Engineers (86-478)
(IEEE).
(NRCemployee)
APPEAL TO THE COMMISSION for the release of denied records (86-A-95-86-316) regarding an OIA investigation.
(86-A-96-86-357)
Granted f
Billie P. Garde, In response to a request for records for the time period Government of March 6, 1984, through March 24, 1986, pertaining to Accountability plans and proposals for 01 and 0IA to be combined, informed Project the requester that the NRC has no records subject to this (86-212) request.
Stephanie Murphy, In response to a request for four categories of records Nuclear Information regarding NRC contacts with licensees and Automatic and Resource Sprinkler Corporation of America about operability of Service 6-inch deluge and pre-action fire protection water control 4
(86-262) valves, made available 26 records.
Informed the requester that four additional records subject to this request are already available at the PDR.
Billie P. Garde, In response to a request for records relating to Government Inspection Report 50-445/50-446, 86-04/86-03 regarding the Accountability Comanche Peak nuclear power plant, made available 21 Project records.
Informed the requester that two additional (86-270) records subject to this request are already available at the PDR.
JUNE 27, 1986 ENCLOSURE A
4 Granted, Cont'd 811119 P. Garde, In response to a request for records related to Government Commissioner Bernthal's presentation to the Atomic Accountability Industrial Forum on May 20, 1985, in Dallas Texas, Project informed the requester that the NRC has no additional (86-376) records since NRC's response to her previous FOIA request, F01A-85-487.
William J. Hagerty, In response to a request for records related to the Inventive report, " Uranium Production Technology" prepared under Processing Company, contract with the AEC, informed the requester that the USA NRC has no records subject to this request.
Informed him (86-415) that DOE may have records in which he is interested.
Steven Aftergood, In response to a request for copies of six reports by Committee to the Safeguards Interoffice Review Group, which are Bridge the Gap referenced in NRC's Weekly information Report for the (86-432) week ending May 2, 1986, made available seven records.
Billie P. Garde, In response to a request for records regarding Inspection Government Report No. 85-10/85-15 dated May 12, 1986, regarding the Accountability Comanche Peak nuclear power plant, informed the requester Project that there is no Inspection Report No. 85-10/35-15 dated (86-452)
May 12,1986.
Christine Herbert, In response to a request for a copy of a list of form Medi+ Physics codes to interpret information contained on the (86-460) printouts provided to her under F01A-86-401, made available two records.
Denied Stephanie Murphy, In response to a request for records relating to Information Nuclear Information Notice 86-05 and five categories of records related to and Resource main steam safety valves, made available 98 records.
Service Informed the requester that additional records subject (86-266) to this request are already available at the PDR. Denied two records in their entirety, release of which would I
tend to inhibit the frank and candid exchange of information in future deliberations.
l l
(NRCemployee)
In response to a request for a copy of an OIA report, l
(86-450) denied this record in its entirety, release of which would j
interfere with an ongoing investigation.
Billie P. Garde, In response to APPEAL TO THE COMMISSION for the release l
Government of three denied records regarding a request for records l
Accountability generated or prepared by Victor Stello beginning with his Project appointment as Acting Executive Director for Operations, i
I (86-A-34-86-53) continued to deny these records, release of which would (86-A-35-86-54) tend to inhibit the frank and candid exchange of information (86-A-36-86-55) in future deliberations and would interfere with an ongoing enforcement proceeding.
JUNE 27, 1986 ENCLOSURE A
5 Denied, Cont'd (NRCemployee)
In response to an APPEAL TO THE COMMISSION for the (86-A-72-86-229) release of denied records regarding an 0IA investigation, continued to deny these records because they pertain to an ongoing investigation.
Billie P. Garde, In response to an APPEAL TO THE COMMISSION for the release Government of 13 denied records and portions of one denied record, Accountability regarding a request for records generated in connection Project with SECY-85-404, " Unauthorized Disclosures of Sensitive (86-A-77-86-40)
Information - Availability of Administrative Sanctions Against NRC Employees and Special Government Employees,"
continued to deny these records, disclosure of which would be likely to stifle honest and frank communication within the agency.
JUNE 27, 1986 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JUNE 27, 1986 PROPOSALS UNDER EVALUATION RFP No.: RS-0IE-86-168
Title:
" Independent Assessment and Analysis"
==
Description:==
Perform independent assessments of materials and components for reactor construction and operation including fabrication and installation to ensure licensee compliance with applicable codes, standards and federal regulatory requirements.
Period of Performance:
36 months Sponsor: Office of Inspection and Enforcement Status: RFP closed on June 6, 1986. Proposals forwarded to Source Evaluators for review on June 9, 1986. Competitive range to be established on July 3, 1986.
RFP No.: RS-RES-86-117
Title:
"Paleoliquefaction Features on the Atlantic Seaboard"
==
Description:==
The objective of this project is to catalogue the characteristics of seismicity induced liquefaction and paleoliquefaction features identified in the Charleston Earthquake area.
Those characteristics will then be used to design and carry out an investigation program in selected areas of the Atlantic Coastal Plain that have a history of relatively high seismicity (by Eastern U.S. standards), and at least one area that is relatively aseismic.
Period of Performance:
24 months Sponsor: Office of Nuclear Regulatory Research Status: The competitive range has been established and negotiations are scheduled for July 9, 1986.
RFP No.: RS-01E-86-154
Title:
" Continuity of Government Programs"
==
Description:==
The objective of this project is to identify and select a contractor to provide logistical and administrative support for the maintenance and functioning of the NRC Continuity of Government (COG) Program.
The contractor will assist in the development of the essential documents and guidance necessary to establish the revised NRC COG Program at both Headquarters and the Regional Offices; and provide support to the NRC for the implementation of the revised COG program and training of NRC staff.
Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: Best and Final offers are due on June 27, 1986.
RFP No.: RS-01E-86-155
Title:
" Technical Assistance for Design Inspections"
==
Description:==
The design inspections are intended to provide a close examination of the design process and design implementation for a limited sample of structures, systems or components for a specific facility and any of its associated design organizations.
Period of Performance:
36 months Sponsor: Office of Inspection and Enforcement Status: Best and Final offers received and forwarded to Source Evaluators for review on June 20, 1986.
JUNE 27, 1986 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending June 27, 1986
@l_and1&2 On June 19, 1986, Consumer's Power notified the staff via telephone that they intend to fonnally request NRC to withdraw their Construction Permit. The two units are permanently cancelled for the nuclear option. The ultimate disposition of the facility remains undecided at this date.
River Band Station On June 20, 1986, Gulf State Utilities filed its position with the Texas Public Utility Comission that River Bend Station be considered in comercial operation. On May 7, 1986, Gulf States Utilities raised the level of River Bend Station to 100% of rated power for the first time. River Bend Station serves customers in both Louisiana and eastern Texas.
Crystal River 3 Subsequent to repair of the reactor coolant pumps at Crystal River Unit 3, the plant entered Mode 2 at 21:35 hours on June 19, 1986, and reached essentially 100% power in the early merning of June 22, 1986. The plant had been shut down since January 1,1986.
l l
JUNE 27, 1986 ENCLOSURE B
o NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JUNE 23 - JUNE 29,1986 1.
DEFUELING The first rail-mounted shipping cask was loaded with seven defueling canisters leaving 36 canisters stored in the fuel pool.
The total weight of the debris contained in the seven canisters is 2400 lbs.
Approximately 51,670 lbs. of debris have been loaded into canisters and transferred to the fuel storage pool to date.
The shielded work platform on top of the reactor vessel is currently dedicated to core stratification sample acquisition (core bore) activities. The core boring rig was being aligned as of Monday, June 30, 1986. The core bore is designed to obtain full length samples of the reactor core from the debris bed to the elliptical flow distributor plate.
Information gained from drilling regarding the hardness, ductility, and friability of the core material will be used to aid future defueling activities. The information will be useful to defueling tool development and defueling strategy. The core bore samples (approximately 21" in diameter and 8 ft. long) will be shipped to the Idaho National Engineering Laboratory for examination.
Core bore activities are currently planned to continue for approximately four weeks.
On June 21 - 26, 1986, NRC's Vendor Inspection Branch performed a special inspection at Nuclear Pacific Corporation, Federal Way, Washington, of activities and records pertaining to non-destructive examination and testing of the two NUPAC 125-B fuel debris shipping containers. A representative of the TMI-2 Cleanup Project Directorate participated in this effort. Areas reviewed included leak testing, radiography, ultrasonic testing, penetrant testing, and pressure testing of the containers. Vendor Inspection Branch will publish a report of the details of the inspection in approximately three weeks.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 78 F.
The airborne radioactivity on the defueling platform is about 3 E-7 uCi/cc Tritium and 1.1 E-11 uCi/cc particulates, predominately Cesium-137 and Strontium-90. The platform is mounted above the modified internals indexing fixture which is mounted over the reactor vessel. These provide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.
JUNE 27, 1986 ENCLOSURE B
2 3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) completed processing batch S-133. SDS processing to date has been 4,098,333 gallons.
EPICOR II completed processing batch 293, 294, 295, and 296. The system has processed 3,002,840 gallons to date.
4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.
The Lancaster water sample taken at the water works river intake and analyzed by EPA consisted of a seven day composite sample taken June 8 - 14, 1986. A gamma scan detected no reactor related activity.
TMI water samples taken by EPA at the plant discharge (includes Units
. I and 2) to the river consisted of seven daily composite samples taken from June 7 - 14, 1986. A gamma scan detected no reactor related activity.
The EPA analysis of the NRC outdoor air sample for the period June 19
- 26, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Assembly of the desludging system continued.
Hands-on decontamination was conducted in the Westinghouse Valve Room at the 281 ft. elevation of the Fuel Handling Building.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31 and 36.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Extended Core Stratification Sample Acquisition Activity.
Heavy Load Safety Evaluation Report, Revision 3.
Defueling Safety Evaluation Report, Revision 10.
l JUNE 27, 1986 ENCLOSURE B l
1
e OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending June 27, 1986 Near-Term NRC Actio'ns Under the NWPA Section:
114(e)(2) of NWPA:
Federal Agency Reporting Requirements Status:
With the issuance of the DOE final PDS on April 3, 1986, the reporting requirements of Section 114(e)(2) are now effective.
Any Federal agency that determines that it cannot comply with any deadline in the final PDS, or fails to so comply, is required to submit a report to the Secretary of Energy and to Congress explaining the reason for such actual or potential noncompliance.
Action:
In the final PDS, NRC was scheduled to " Issue Proposed Amendment to conform 10 CFR Part 60 to EPA Standards" in March, 1986. The proposed revisions were published June 19, 1986.
Section:
141 of NWPA:
Monitored Retrievable Storage (MRS)
Status:
DOE had planned on submitting the MRS proposal and NRC comments to Congress in early February, 1986.
However, an injunction on behalf of the State of Tennessee has delayed the submittal of the proposal indefinitely.
Action:
DOE has filed an appeal to expedite a decision on the injunction in the Sixth Circuit Court of Appeals in Cincinnati, Ohio, and oral arguments are seneduled to begin on Monday, July 21, 1986.
Section:
306 of NWPA:
Regulations for Training Power Plant Personnel Status:
The final rulemaking on Part 55 and three associated regulatory guides concerning regulations for Training of Power Plant personnel was submitted to the Commission on April 18, 1986 (SECY-86-123) and is currently awaiting Commission approval, pending OGC analysis of the package.
JUNE 27,1986 ENCLOSURE C
. International Symposium for Packaging and Transportation of Radioactive Material (PATRAM 86)
On June 16-20, 1986 representatives of NMSS participated in PATRAM 86 jointly sponsored by the International Atomic Energy Agency, the Government of Switzerland, and the Department of Energy.
Approximately 168 papers were presented during 21 sessions by persons representing 19 countries.
Thirty-six (36) countries and several international organizations were represented at the symposium.
International symposiums are held approximately every three years and continue to be an important forum for exchange of experience, research and development in packaging and transporta-tion of radioactive material.
Malfunctions of Therac 25 Therapy Units On June 20, 1986, OPA informed us of a report by the Associated Press that three patients had been injured because of malfunctions of Therac 25 therapy units manufactured by Atomic Energy of Canada, Limited (AECL).
One injured patient later died.
FCML staff has obtained the following additional information.
Therac 25 units are accelerators, thus not regulated by NRC. Therac 25 units use a computer to program the unit for each patient's treatment.
The malfunctions involved a
" miscue" in the computer software that allowed the unit to be activated for 330 milliseconds before it shut down.
In that brief time the unit delivered an estimated 16,000 rads to a portion of the patient's body.
AECL became aware of this problem on April 11, 1986, determined the cause and a temporary "fix" over that weekend.
Before patient treatments began on April 14, 1986, AECL notified the medical institutions that have Therac 25 units of the problem and temporary solution.
(There are 5 Therac 25 units in the U.S. and 7 in Canada.) The U.S.
Food and Drug Administration (FDC) is investigating these events and is evaluating the permanent "fix" proposed by AECL.
Review of Transportation Sections of Final Environmental Assessments The Division of Fuel Cycle and Material Safety is proceeding with their review of those sections of DOE's Final Environmental Assessments that pertain to transportation.
The reviews are directed toward determining the manner in which comments on the draft environmental assessments have been addressed.
The i
reviews are scheduled for completion by mid-July 1986.
JUNE 27, 1986 ENCLOSURE C
Materials Safety Regulation Review Study Group The Materials Safety Regulation Review Study Group (MSRRSG) is a group of independent consultants charged to take a broad overview look at NRC activities in licensing and inspection of materials facilities from a number of different backgrounds and expertise.
The group visited Regions III and IV during the week of June 16-20, 1986, to discuss these Regions' activities.
The group also visited with the Oklahoma State Department of Health and with officials of Sequoyah Fuels Corporation.
Sequoyah Fuels Corporation, Status of Restart By letter dated May 7, 1986, Sequoyah Fuels Corporation requested authorization to resume uranium conversion operations at their facility near Gore, Oklahoma.
The staff expects to receive a response to its request for additional information on June 26, 1986.
The staff already has under review modifications to the Radiological Contingency Plan.
The staff has prepared a plan to review the rt. tart request which includes a restart inspection, public meeting, and Commission briefing.
Sequoyah Fuels Corporation Public Meeting The Nuclear Regulatory Commission (NRC) is considering a proposal from Sequoyah Fuels Corporation to resume uranium hexafluoride (UF ) production at its g
facility near Gore, Oklahoma.
Production has been dTscontinued since the January 4, 1986 accident.
As an adjunct to its review of the Sequoyah Fuels Corporation proposal, the NRC will hold two meeting to solicit comments from members of the public about issues related to production restart.
The meetings will be held in the Brooks-Cawhorne Gymnasium adjacent to the Gore Elementary School in Gore, Oklahoma, on July 8,1986, from 7 to 10:00 p.m. and on July 9, 1986, from 10 a.m. to 12 noon.
Battelle Columbus Incinerator An Environmental Assessment and Finding of No Significant Impact has been issued regarding the proposed operation of a low-level radioactive waste (LLW) incinarator by Battelle Columbus Laboratories (BCL) at its West Jefferson, Ohio site.
BCL proposes to receive and incinerate Class A LLW from utility, academic and institutional generators who contract to participate in a planned five year program to demonstrate the safety, technical and cost effectiveness of incineration as a method of LLW management.
The incinerator proposed for installation is a larger scale version of a prototype unit developed and in use in West Germany.
The developing firm is represented in the U.S. by ATCOR Engineered Systems.
The staff's safety evaluation is essentially complete.
If approved, licensing action would be an amendment of Materials License No.
$NM-7 held by BCL.
Although possible licensing action is near-term, timing JUNE 27, 1986 ENCLOSURE C Battelle Columbus Incinerator (Continued) for installation and operation of the incinerator remains uncertain because of the need to obtain an air quality permit from Ohio EPA and to complete customer contractual arrangements for the demonstration project.
Spent Fuel Rule Division of Safeguards staff, responding to concerns expressed by Division of Fuel Cycle staff regarding the response of nodular cast iron casks to mechani-cal shock loading, is seeking to determine whether these concerns have explo-sive sabotage implications.
They have: (1) requested explosive test data, understood to be available from West Germany, and (2) requested Sandia to study the question and report back.
NRC-D0E Physical Security Comparability Study The second meeting of the NRC-DOE Physical Security Comparability Study Team is scheduled to be held on July 2,1986, in Germantown, MD.
The purpose of the meeting is to finalize the list of DOE facilities to be studied and the criteria to be used for data gathering.
Tentative plans have been made to visit a DOE facility during the week of July 7.
l JUNE 27, 1986 ENCLOSURE C
Office of Inspection and Enforcement Items of Interest Week Ending June 27, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
a.
An Order Suspending License (Effective Immediately) was issued to Radiation Technology, Inc. (Rockaway, NJ).
This Order was based on:
(1) willful violations of Comission requirements by defeating interlocks on numerous occasions, (2) senior management knew or should have known that personnel violated license requirements, and (3) in response to NRC inspection and investigation provided false information regarding circumstances surrounding the alteration and operation of the interlock system.
(EN-86-11B) b.
A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Commonwealth Edison Company (Byron) in the amount of
$25,000. This action was based on the discharge of a subcontractor employee for reporting to the NRC inadequate inspection procedures of the subcontractor and inappropriate supplies installed by the sub-contractor; this is a violation of 10 CFR 50.7.
(EN-86-41) c.
A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Florida Power and Light Company (Turkey Point 3) in the amount of $50,000. This action was based on the misrepresentation of the operability of neutron flux detectors.
(EN-86-44) 2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-I-86-44, International Nutronics, Inc. (Dover, NJ), Grand Jury Indictment of International Nuctronics, Inc. and Two of Its Employees.
b.
PNS-I-86-09, Public Service of New Hampshire (Seabrook), Threat Against Facility.
c.
PN0-II-86-44, General Information, Hurricane Bonnie, d.
PNO-III-86-57, Northern 5tates Power Company (Monticello), Loss of Intermediate Range Monitor Trip Function Without Annunciation.
e.
PN0-III-86-58, Commonwealth Edison Company (LaSalle), Municipality Withdraws From Emergency Planning For LaSalle Nuclear Plant.
f.
PN0-III-86-59, Cleveland Electric Illuminating (Perry 1), Charcoal Filter Fire.
g.
PN0-III-86-59A, Cleveland Electric Illuminating (Perry), Charcoal Filter Fire (First Update),
h.
PNO-III-86-60, Union Electric Company (Callaway), Reactor Trip--
Closure of Feedwater Isolation Valve.
JUNE 27, 1986 ENCLOSURE D
2 1.
PNO-III-86-61, Dairyland Power Cooperative (LACBWR), Reactor Trip and Water Level Instrumentation Problem.
j.
PNO-IV-86-21, Multiple Facilities, Hurricane Bonnie.
k.
PNS-V-86-05A, Arizona Nuclear Power Project (Palo Verde 3), Suspected Attempted Sabotage / Vandalism (Update).
1.
PNO-V-86-34, Washington Public Power Supply System (WNP 2), Shutdown Greater Than 48 Hours.
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
a.
IE Information Notice No. 86-52, Conductor Insulation Degradation on Foxboro Model E Controllers was issued to all nuclear power reactor facilities holding an operating license or a construction permit.
b.
IE Information Notice No. 86-53, Improper Installation of Heat Shrinkable Tubing was issued to all nuclear power reactor facilities holding an operating license or a construction permit.
4.
Other Items a.
Senior Management Meetings (1) The Director, IE participated with the ED0 and DEDR0GR at a senior staff meeting in Region II.
(2) The Director, IE participated with the EDO, DEDR0GR, Deputy Director, NRR, and Regional Administrators of Regions I and II with INP0 to discuss INP0 programs.
b.
Civil Penalties Paid (1) Washington Hospital Center (Washington, DC) in the amount of
$5,000 based on violations involving inoperable interlocks.
(EA-86-43)
(2) Detroit Edison (Fermi) in the amount of $50,000 based on security violations.
(EA-86-66) c.
Operations Center (1) On June 23, 1986, the Director, Division of Emergency Pre-paredness and Engineering Response, and the Incident Response Branch Chief and staff members, along with the ED0 and the Office Directors from IE and NRR, met with Representative Huckaby and staff to discuss:
NRC incident response; the proposed Emergency Response Data System (ERDS); and the Nuclear Data Link concept.
(2) Two members of the Incident Response Branch participated with contractor personnel in ERDS site surveys this week. The surveys were conducted at the Crystal River and Trojan nuclear power plants.
JUNE 27, 1986 ENCLOSURE D
3 d.
Vendor Program The following Vendor Program Branch inspections were conducted this week:
(1) Sequoyah 1 and 2, Daisy, TN - to complete the final phase of the pre-startup EQ program inspection initiated January 1986.
(2) Henze, Mobile, AL - to review North Anna main steam relief valve drift problem.
(3) Farwell and Hendricks, Milford, OH - to review procurement process of commercial grade as Class IE electrical equipment.
(4) Control Products Corporation, Grafton, WI - to review manu-facturing process of Amerace relays.
(5) Babcock & Wilcox, Lynchburg, VA - to review implementation of QA program.
(6) Combustion Engineering, Windsor, CT - to review implementation of QA program.
Vendor Inspection followup:
(7) As part of a trial program to inspect the fabrication, main-tenance and repair of type B transportation casks, and at the request of NMSS, the Vendor Branch conducted an inspection of Nuclear Packaging Incorporated (NUPAC) in May 1986. This inspection identified several potential problems in the areas of leak testing, nondestructive testing records and personnel qualifications.
In response to these issues, NMSS, the TMI Project Directorate, the Vendor Branch, and representa-tives of DOE discussed the problems. A second inspection, to review additional information related to the questionable areas, commenced on Saturday, June 21 at the NUPAC facility in Federal Way, Washington. This inspection was expedited to avoid or minimize delay in use of the cask.
The inspection, through review of radiographs, has identified a lack of penetration in a weld located in the outer steel shell which is a structural member of the cask.
The defective weld is not accessible in the as-built condition of the cask.
The design is proposing to accept the weld as is and will pro-vide justification to NMSS.
l JUNE 27, 1986 ENCLOSURE D
4 e.
Incident Response A member of the Incident Response Branch chaired a meeting of the Federal Field Exercise (FFE) '87 Scenario Development Work Group in Chicago, IL. Representatives from Region III, Commomwealth Edison, the States of Illinois and Wisconsin, and other federal agencies (FEMA, DOE, EPA, NOAA, HHS, and USDA) participated.
f.
Emergency Preparedness (1) A FEMA emergency preparedness exercise report for Seabrook was forwarded to the region for appropriate action.
FEMA identified several deficiencies and other areas requiring corrective action. A number of communities in New Hanpshire and Massachusetts and the Commomwealth of Massachusetts did not participate in the exercise.
(2) An Emergency Preparedness Branch member is participating in the Region III evaluation of the annual exercise at Fort Calhoun.
(3)
FEMA has reported (in accordance with their rule 44 CFR 350) that the state and local plans for radiological emergencies for the State of Delaware related to Salem / Hope Creek were found acceptable.
g.
Interagency Activities Representatives of IE and NMSS met with representatives of the OSHA intergovernmental relations and field coordination staffs to hold an initial discussion concerning the planned Memorandum of Understanding between the two agencies.
h.
Meetings - Conferences of Note (1) A member of the Enegineering and Generic Comunications Branch (EGCB) was at the EPRI-NDE Center, Charlotte, NC on June 25-27 to participate in the training and qualifica-tion testing of TVA NDE personnel in the use of "MINAC" Radiography for inservice inspection.
(2) On June 27, a member of the EGCB made a presentation to a joint meeting of the ACRS Subcommittee on Occupational and Environmental Protection Systems and the Subcommittee on Auxiliary Systems.
JUNE 27, 1986 ENCLOSURE D
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending June 27, 1986 Test FLHT-4 The instrumented, unirradiated test fuel rods and hardware for test FLHT-4 were delivered to Chalk River National Laboratories (CRNL), Canada on 6/24/86. Test FLHT-4 is scheduled to be run in the NRU reactor at CRNL in late August. Test FLHT-4 is a coolant boilway test in which an assembly of ten fresh and one 20 GWD/MT full length, commercial enrichment fuel rods will be nuclear heated to peak cladding temperatures (PCT's) of 2400K-2600K. The test is then to be held at power for twenty minutes after reaching the PCT's in order to collect data on hydrogen release during and after cladding and fuel relocation.
Fission product release and transport will also be monitored.
j Occupational Collective Dose at Power Reactor Decreases Again in 1985 Preliminary compilations of 1985 annual radiation exposure data reported for 83 operating nuclear power reactors indicate that the collective dose for the approximately 93.000 workers that received a measurable dose is 43,650 person-rems. This is a 20% decrease from last year's value of 54,745 person-rems and is the lowest collective dose reported since 1979, when about 40,000 person-rems were incurred by 64,000 workers. The sharpest decline in collective dose was experienced by BWRs with a 25% decrease from last year's value; the collective dose at PWRs declined by 17%. This resulted in the lowest average measurable doses ever reported, 0.53 rems for workers at BWRs, 0.42 rems for PWRs, and 0.47 rems for all LWRs. These decreases are probably due to several factors such as greater efforts by the nuclear utilities to reduce the collective doses received during various tasks, better worker training, and the completion of modifications required by the NRC following the Three Mile Island accident.
JUNE 27, 1986 ENCLOSURE E
+
2 EPA Advance Notice of Proposed Rulemaking on Residual Radioactivity Limits for Decommissioning On June 18, 1986, the Environmental Protection Agency (EPA) published for public comment an advance notice of proposed rulemaking in the FEDERAL REGISTER on " Radiation Protection Criteria For Cleanup of Land and Facilities Contaminated with Residual Radioactive Material."
In this regard, EPA has established an Interagency Working Group on Residual Radioactivity (NRC is represented on this group by Robert E. Alexander) for the purpose of updating the 1960 Federal Guidance on public exposures issued by the former Federal Radition Council. EPA's advance notice relative to land and facilities is the first step by EPA in updating the 1960 Federal guidance.
EPA is planning to subsequently develop additional guidance relative to the unrestricted release and recycling of materials and equipment contaminated with trace quantities of residual radioactivity.
Federal guidance would apply to NRC and Agreement State licensees, to sites owned or used by the Department of Energy, the Department of Defense, the former Atomic Energy Commission, and to sites where naturally occurring or accelerator-produced radioactive materials have been used. Advice and comments are requested on such issues as:
basis for the guidance; form of guidance; guidance versus standards; assessment needs; institutional controls; and recycling equipment and materials, etc.
Recently Issued Publications Draft Regulatory Guide and Value/ Impact Statement: Fracture Toughness Criteria for Ferritic Steel Shipping Containers with a Wall Thickness Greater than Four Inches (0.1 m), Task MS 501-4. Connents requested by August 29, 1986.
Contact:
H. Graves '301) 443-7709.
Reg. Guide 1.84, Rev. 24, Design and Fabrication Code Case Acceptability ASME Section III Division I Reg. Guide 1.85, Rev. 24, Materials Code Case Acceptability ASME Section III Division I JUNE 27, 1986 ENCLOSURE E
3 RES RULEMAKING ACTIVITIES AND OTHER RELATED ISSUES Operational Safety Reliability Research The Operational Safety Reliability Research project includes case studies of five utilities to help identify reliability techniques that utilities have found to be effective and to identify attributes of successful reliability programs.
Ir. a memorandum dated February 26, 1986, the ED0 directed RES to:
(1) complete by April 30, 1986, a draft technical report evaluating the effectiveness of a reliability program applicable to light-water reactor safety, and (2) in coordination with NRR and IE, submit by June 30, 1986, an evaluation of current and potential needs for implementation of reliability assurance in the regulatory program.
The status of these two reports is as follows:
On April 30, Brookhaven National Laboratory (BNL) completed the draft technical report.
Following RES review and comments, BNL issued a revised draft.
On June 19, 1986, RES circulated the revised draft to interested divisions in NRR, IE, and AE0D for comment.
The second report, a staff evaluation of current and potential needs for reliability technology in the regulatory program, is being drafted by RES. A draft will be circulated in a few days for division-level comment by NRR, IE and AE0D, prior to forwarding it for office concurrence in July.
RES will brief NRR, IE, and AE0D staff on the contents of both reports (i.e.,
the BNL draft technology assessment and the RES draft assessment of regulatory needs) in early July.
JUNE 27, 1986 ENCLOSURE E
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 27, 1986 U.S.-Taiwan Meeting on Cooperation On Monday and Tuesday RES and IP staff participated in the second annual AIT-CCNAA Joint Committee Meeting on Civil Nuclear Cooperation that was held at the Brookhaven National Laboratory. Following a brief discussion of the Chernobyl accident, RES provided a briefing on several NRC research programs and invited Taiwan's participation. Taiwan expressed interest in the piping integrity and aging programs. The meeting closed with a review of the status of existing joint projects.
U.S.-Korea Meeting on Cooperation On Tuesday, Wednesday and Thursday IP staff participated in the tenth annual meeting of the U.S.-Korea Joint Standing Committee on Nuclear and Other Energy Technology. The status of cooperative projects between NRC and Korea was reviewed and future plans described.
B. Sheron, RES, gave a briefing on Chernobyl to the group at the Thursday session.
International Agency Vacancy Notices Vacancy notices for the following five positions at the International Atomic Energy Agency in Vienna, Austria have been posted on NRC bulletin boards:
l l
P-2 Systems Programmer, Computer Section, Division of Scientific and l
Technical Infonnation, Department of Nuclear Energy and Safety P-2 Associate Area Officer, Latin America Section, Division of Technical Assistance and Cooperation, Department of Technical Cooperation P-2 Data Service Coordinator, Nuclear Data Section, Division of Research and Laboratories, Department of Research and Isotopes l
l P-4 Senior Translator, French Translation Section, Division of Languages, Department of Administration P-4 Containment / Surveillance Engineer, Section for Technical Services, Division of Development and Technical Support, Department of Safeguards Foreign Visitors On Friday, June 20, Syh-Tsong CHIOU from the Taiwan Atomic Energy Council met with AE0D for an overview of their program.
JUNE 27, 1986 ENCLOSURE G l
2 Foreign Visitors continued On Wednesday Minister Chon Hakze, Korean Minister of Science and Technology, accompanied by three other Korean nuclear officials, met with Chaiman Palladino, Comissioners Zech and Asselstine, and IP Director Shea to discuss NRC's very active program of cooperation with Korea.
JUNE 27, 1986 ENCLOSURE G
0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JUNE 27, 1986 National Congress of American Indians 1986 Annual Mid-Year Conference OSP attended National Congress of American Indians 1986 Annual Mid-Year Conference held June 17-20 in Albuquerque, NM.
G. Wayne Kerr, Director, OSP presented a paper addressing Transportation of Nuclear Material before the Nuclear Waste Policy Committee on Wednesday, June 18.
State Liaison Officers' Meeting OSP and Region IV held a State Liaison Officers' Meeting in Arlington, TX for the States of Arkansas, Colorado, Idaho, Kansas, Louisiana, Montana, Nebraska, New Mexico, North Dakota, Oklahoma, South Dakota, Texas, Utah, and Wyoming on June 19-20. Topics of discussion included the status of the uranium mill industry in the States, detecting radon in the environment, low-level waste compacts, the Sequoyah Fuels incident and high-level waste.
4 JUNE 27, 1986 ENCLOSURE H
- - - = -
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST Week Ending June 27, 1986 AE0D/N602, Medical Misadministration Report, was issued on June 25, 1986. The report compiles data for therapy and diagnostic misadministration reports for 1985, and contains a discussion of these reports and similar reports for the 1981-1985 time period. The report found that: four therapy misadministrations were reported in 1985; there were 380 reports of diagnostic misadministrations for 1985; and there were three reports of diagnostic misadministrations involving millicurie doses of iodine-131, a therapy dose. A review of the 1981-1985 data showed that the overall misadministration rate for diagnostic misadministrations was about 0.01%, and has not varied much over time.
JUNE 27, 1986 ENCLOSURE J
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 27, 1986 A.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 11:30 A.M., THURSDAY, MAY 1,1986, COPfiISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to Stello and Zerbe dated 6/23/86 I.
SECY-85-279 - Revised Advanced Reactor Policy Statement The Commission, by a 4-l* vote, approved the issuance of the attached Advanced Reactor Policy Statement for the Regulation of Advanced Nuclear Power Plants.
The Advanced Reactor Policy Statement's primary objectives are to (1)
Encourage earliest possible interactions of' applicant, vendors, and government agencies, with the NRC; (2)
Provide all interested parties, including the public, with the Commission's views concerning the desired characteristics of advanced reactor designs; and (3)
Express the Commission's intent to issue timely comment on the implications of such designs for safety and the regu-latory process.
Commissioner Roberts, while approving, noted his deep concern about the statement (on page 6) whereby the Commission commits advanced reactor designs to comply with the forthcoming safety goals policy statement before the safety goals statement is i
finalized and while the final wording is still fluid.
Commissioner Asselstine disapproved and provided separate views which will be published with the Policy Statement.
The addi-tional views of Commissioner Bernthal are also attached, i
The Federal Register Notice will be forwarded for publication.
The Final Advanced Reactor Policy Statement also commits the NRC to an advanced reactor group which will act as a focal point and I
will maintain knowledge of advanced reactor developments.
This group should keep the Commission informed regarding contemplated major changes to licensing procedures, to general design criteria or to functional requirements.
The Commission expects to be able to render timely final decision on significant departures from present practice consistent with the orderly processing of applications or inquiries.
- Section 201 of the Energy Reorganization Act, 42 USC S 5841, provides that action of the Commission shall be determined by a
" majority vote of the metabers present."
Commissioner Asselstine was not present when this item was affirmed.
Accordingly, the j
formal vote of the Commission was 4-0 in favor of the decision.
Commissioner Asselstine, however had previously indicated that he would disapprove this paper and had he been present he would have affirmed his prior vote.
ENCLOSURE 0 JUNE 27, 1986 l
m
- ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 27, 1986 B.
STAFF REQUIREMENTS - MEETING WITH ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) ON GESSAR-II, 2:00 P.M., THURSDAY, JUNE 5, 1986: COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY for the Record dated 6/24/86 The Connissilon met with the Advisory Committee on Reactor Safeguards (ACRS) to discuss ACRS views, which were expressed in a January 14, 1986 letter to the Commission on the GESSAR-II BWR/6 Nuclear Island Design for future plants.
The Chairman indicated his intention to circulate a memorandum to Commissioners on approaches for Commission involvement in approval of standard plant designs.
There were no requirements for the ACRS at this meeting.
C.
STAFF REQUIREMENTS - PERIODIC MEETING WITH ADVISORY PANEL FOR THE DECONTAMI-NATION OF TMI-2, 11:00 A.M., WEDNESDAY, JUNE 11, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to Stello dated 6/24/86 The Commission met with the Advisory Panel for the Decontamination of TMI-2 to receive local community input on the efforts of decontaminating TMI-2.
The Panel was represented by:
- Arthur Morris, Chairman
- Kenneth L. Miller
- Frederick S. Rice
- Joel Roth
- Thomas Smithgall
- Niel Wald
- John Luetzelschwab The Commission requested the staff to review the remaining tasks and major milestones required to complete TMI-2. cleanup and identify the issues which require input of the Panel.
The staff is to discuss the issues with the Panel and then submit a paper i
for Commission consideration to determine an end point for the activities of the Panel.
j The Panel recommended that the next meeting with the Commission be scheduled for September or October to discuss GPU's plans for water disposition and defueling of the plant.
1 Chairman Palladino requested the staff to examine ways to help increase the credibility of various studies dealing with cancer, pregnancy, and psychiatric problems.
JUNE 27, 1986 ENCLOSURE 0
--. D.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND V0TE, 3:30 P.M., WEDNESDAY, JUNE 18, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (CPEN TO PUBLIC i
ATTENDANCE) Memo SECY to Stello dated 6/25/86 I.
SECY-85-381 - Insider Safeguards Rules The Commission, by a vote of 5-0, has approved the staff's proposed rules on Search Requirements and Miscellaneous Safeguards-Related Amendments.
The statements of consideration should be modified as suggested in the OGC memorandum to Chairman Palladino dated April 14, 1986, to state that the costs of the rule are justified by a substantial increase in safety and the justification of the conclusions.
The Federal Register Notices should be forwarded for signature and publication and the appropriate public and Congressional announcements made.
Additionally, the Commission, by a vote of 3-2 (with Commis-sioners Roberts, Bernthal, and Zech agreeing), has disapproved issuing an Access Authorization Rule in favor of a policy statement.
The staff is directed to develop and submit for Commission approval, a policy statement, in cooperation with NUMARC, which endorses the NUMARC Guidelines for Nuclear Power Plant Access Authorization.
The policy statement should address the NUMARC commitment for the licensees to voluntarily incorporate the NUMARC Guidelines as part of their security plans.
The policy should also recognize the NRC position that an appeal procedure is an important element of this process.
Chairman Palladino and Commissioner Asselstine approved issuance of the access authorization rule and do not believe it should be a policy statement.
E.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND V0TE, 2:15 P.M., THURSDAY, JUNE 19, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to Malsch dated 6/25/86 I.
Diablo Canyon Stay Request The Commission, by a 5-0 vote,* approved an order responding to an application from the Sierra Club and the San Luis Obispo Mothers for Peace for a stay of the effectiveness of a staff issued license amendment allowing the licensee to rerack the spent fuel storage pools at Diablo Canyon.
- Section 201 of the Energy Reorganization Act, 42 U.S.C.
S 5841, provides that action of the Commission shall be determined by a " majority vote of the members present."
Commissioner Asselstine was not present when this item was affirmed.
Accord-ingly, the formal vote of the Commission was 4-0 in favor of the decision.
Commissioner Asselstine, however, had previously indicated that he would approve this paper and had he been present he would have affirmed his prior vote.
JUNE 27, 1986 ENCLOSURE 0 i
_a_
The Order denied the request for action on a stay by c.o.b.
Tuesday, June 18, 1986, and granted an expedited consideration of the matter by providing other parties an opportunity to respond to the stay request.
The licensee and the NRC staff were directed to have responses to the intervenors' application for a stay in the hands of the Secretary of the Commission on or before the c.o.b. Wednesday, June 25, 1986, copies to be served on intervenors' counsel by next-day express mail or courier.
(Subsequently, on June 19, 1986 the Secretary signed the Order.)
JUNE 27, 1986 ENCLOSURE 0
NRR MEETING NOTICES
- JUNE 20, 1986
?
C S
DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 7/1/86 50-412 Room P-110 Discuss with DLC technical NRC/DLC P. S. Tam 9:00 a.m.
Phillips Building issues raised by the staff regarding DLC's Equipment Qualification Report (sub-mitted May 23,1986) 7/1/86 50-272 Room 6110 Discuss DCRDR NRC/PSE&G D. C. Fischer 9:00 a.m.
50-311 Maryland National i
Bank Building 7/788/86 50-327 TVA Corporate Office Discuss NRC comments on NRC/0THER T. J. Kenyon 1:00 p.m.
328/390 Southwest Building Revision 9 of TVA's Topical 391/438 Chattanooga, TN Report TVA-TR75-1A 7/8/86 50-601 Westinghouse Licensing Outline the content and NRC/ Westinghouse S. Long 9:00 a.m.
Operations Center discuss the format for Module Bethesda, MD 15 of RESAR - SP/90 7/8/86 50-294 Room P-234C Discussion of Decommissioning NRC/MSU J. Dosa 1:00 p.m.
Phillips Building Requirements or Alternatives for the Michigan State Univ.
TRIGA Facility 7/889/86 50-454 Room P-118 Disciass Byron's Inservice NRC/ COP 990NWEALTH L. N. 01shan g
8:30 a.m.
Phillips Building Testing Program EDISON /EG&G 1 p l
8 C
- A u
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
E!
Ei NRR MEETING NOTICES
- JUNE 13, 1986 0
DOCKET APPLICANT /
y DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 7/9-10/86 50-461 Clinton Power Station To pemit NRC management to NRC/ Illinois Power B. L. Siegel 3:00 p.m.
Nuclear Training assess the operational Company Facility readiness of Clinton Unit 1 Clinton, Illinois E
P o
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
l NMSS MEETING NOTICES FOR WEEK ENDING:
6/27/86 i
Divis1*on of Fuel Cycle and Material Safety c,
C i
Ni DOCKET ATTENDEES /
t3 DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT G
8' 6/30-7/3/86 Pittsburgh, To attend the Health Physics V. Miller (FC)
McElroy PA Society meeting; attend N. McElroy (FC) subcommittee meeting; discuss material licensing with licensees / consultants.
7/1/86 M-32 Willste To discuss LLW disposal with West Reps fm NRC and Clark 9:30-4:40 5th floor Valley Demonstration Project staff.
DOE 4
conf room 7/8-9/86 40-8027 Gore, OK Public Meeting regarding Sequoyah Reps fm NMSS, ELD, Mausshardt Fuels Corporation.
IE, RIV Members of the public 7/8-11/86 M-32 West Valley, To review HLW treatment with Reps fm NRC and DOE Clark NY West Valley Demonstration Project staff.
DIVISION OF WASTE MANAGEMENT None DIVISION OF SAFEGUARDS None n,
h5 g
Ea M
.