ML20140C336
| ML20140C336 | |
| Person / Time | |
|---|---|
| Issue date: | 01/22/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860117, NUDOCS 8601270326 | |
| Download: ML20140C336 (33) | |
Text
.
9Chk x
January 22, 1986 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 17, 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)
~ ~y
~ _ -
- No input this week.
j l j !vg p s w.-
T. A. Rehm,' Assistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781 8601270326 860122 PDR CENW1S NRCC WEEKLYINFOREPT PDR
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JANUARY.17, 1986 j
B&W Regulatory Response Group On January 8, 1986, the staff met with the B&W Regulatory Response Group to discuss the generic implications of the December 26, 1985 Rancho Seco loss of integrated control system (ICS) power event. The Regulatory Response Group (RRG) presented information to demonstrate that the other B&W plants'are sufficiently different such that the transient that occurred at Rancho Seco would not be as severe at the other plants. Accordingly, they concluded that no imediate action at other B&W facilities was required. The RRG also concluded that due to i
similiarities, additional review of the Rancho Seco event should be undertaken to identify actions to reduce the frequency and magnitude of transients.
In addition, special training will be conducted to familiarize operations with the Rancho Seco event. A B&W Owners Group i
Executive Committee meeting scheduled for January 16, 1986 will finalize the actions to be taken. The B&W Owners Group Program and 1
Plans, will be reported to the staff at a meeting scheduled for
~
February 5, 1986. Based on the information presented at the meeting, i
I the staff concluded that no immediate action is required for the other B&W plants.
Shoreham Emergency Planning Drill i
Suffolk County Executive Peter Cohalan, on January 15, 1986, signed a new law which makes it a misdemeanor, punishable by one year in prison.
to conduct or participate in a test or exercise of a natural or man-made emergency situation, unless the County legislature has previously approved the exercise. The law also prohibits the j
simulation of the roles or governmental functions of any Suffolk County official during such an exercise without the prior approval of the i
legislature. The new law appears to be aimed at preventing the conduct i
of an emergency planning drill next month for Shoreham.
j Sequoyah Fuels On January 14, 1986, the NMSS staff held a meeting to establish a task force j
to evaluate the public health impact associated with the accidental release l
of UF which occurred at the Sequoyah Fuels Facility, Gore, Oklahoma.
The attenbeesincludedmembersfromEPA,CenterofDiseaseControl(HEW),OakRidge National Laboratory (0RNL), Lawrence Livermore Laboratory (LLL), Dr. Paul Morrow (University of Rochester), and the State of Oklahoma.
At the meeting, an out-line of the proposed NRC technical report was presented. There will be another meeting to brief the group after all the data are collected. The data will be
)
tabulated and provided to individual members of the task force and will be used j
for impact analysis.
g l
l JAN 171986 I
A
__._-.._.,--_..-_,_---_-__n
.n,
0FFICE OF ADMINISTRATION Week Ending January 17, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1985 181 15 Received, 1986 34 3
Granted 33 0
Denied 7
0 Pending 175 18 ACTIONS THIS WEEK Received (NRC employee)
Requests two categories of records regarding Vacancy (86-18)
Announcement No. 86-0336-5.
Mary Ann Mathews, Requests a computer tape updating information, since General Electric December 1984, on uranium shipments provided in response (86-19) to her previous F0IA request.
Zinovy Reytblatt, Requests a list of the records related to DD-85-10 and Illinois Institute the NRC meeting with the requester on October 17, 1985, of Technology as well as Mr. Bernero's review of the transcript of the (86-20)
October 17 meeting.
Zinovy Reytblatt, Requests a list of records related to review of the Palo Illinois Institute Verde Unit 1 leak rate test report and unofficial leak rate of Technology test curves.
(86-21)
Zinovy Reytblatt, Requests three categories of records regarding the OIA Illinois Institute investigation involving an interview with the requester.
of Technology (86-22)
Ophelia Williams, Requests copies of any correspondence from W. Dircks J/R/A Associates responding to INP0's October 16, 1985, letter regarding (86-23)
INP0's involvement in utility training and maintenance programs.
Kathleen M. Tucker, Referrral from the 00J for records regarding claims Health & Energy against the Government relating to radiation exposure.
Institute (86-24) 1 CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A I
JAN 171986
2 Received, Cont'd Cindee Virostek, Requests a copy of a report identified as ORNL-NSIC-69.
Kiski Valley Coalition (86-25)
William Patterson, Requests records since January 1, 1984, relating to Morgan, Lewis refueling outages at Oyster Creek.
& Bockius (86-26)
Gene Stilp, Requests records regarding radium dial workers, the Essential Ottawa, Illinois, radium dial painting plant, health of Information the workers, locations where radium instrument painting (86-27) was or is practiced, etc.
(NRCemployee)
Requests information regarding herself.
(86-28)
William J. Manning Requests a copy of a July 11, 1980, memo to R. Vollmer (86-29) from R. Jackson entitled, "Diablo Canyon Hearing Reopening and San Onofre Review Status."
(NRCemployee)
Requests records regarding herself.
(86-30)
(An individual Requests records in the NRC on himself.
requesting information about himself)
(86-31)
Howard Irwin, Requests three categories of records regarding AEC Advanced Medical license 34-7225-12 issued to Picker Corporation.
Systems, Inc.
(86-32)
Don J. Waters Requests a copy of the radiation limits published in the (86-33)
Federal Register.
(Anindividual Requests records in the NRC on himself; National requesting )
Workers Party; National Workers Committee; and Awareness information Research Incorporated.
(86-34)
Albert V. Carr, APPEAL TO THE COMMISSION for the release of 12 denied Duke Power records regarding a request for records regarding Company Enforcement Action No. EA-84-93 on the Catawba nuclear (86-A-1-85-584) power plant.
Steven Aftergood, APPEAL TO THE COMMISSION for the release of two denied Committee to regarding NRC's reactor safeguards program.
Bridge the Gap (86-A-2-85-577)
ENCLOSURE A JAh I '.1986
3 I
Received, Cont'd Diane Curran, APPEAL TO THE COMMISSION for the lack of response to Harmon, Weiss &
a request for three categories of records regarding the Jordan backfit rule.
(86-A-3-85-759)
~
Granted Don L. Schlemmer, In response to a request for seven categories of records Government dated from September 1984 concerning the merger of the Accountability Cleveland Electric Illuminating Company and Toledo Edison, Project made available one record.
Informed the requester that (85-642) seven additional records subject to this request are already available at the PDR.
Dinah Wisenberg, In response to a request for a record of all meetings in Inside NRC the last year between representatives of the Nuclear (85-662)
Utility Management and Human Resources Comittee and members of the NRC, made available one record.
Informed the requester that transcripts of three meetings are already available at the PDR.
Patty Day, In response to a request for a copy of SECY-85-288, made NUS Corporation available a copy of the requested record in the PDR.
(85-756)
(An individual In response to a request for copies of records regarding requesting himself, made available four records.
information about himself)
(85-818)
Ellyn R. Weiss, In response to a request for a copy of all GPU Nuclear Harmon & Weiss Corporation responses to questions attached to NRC (85-844)
Inspection Report No. 50-289/85-26, informed the requester that GPU was given 60 days from the date of the Inspection Report, December 12, 1985, to respond to the NRC questions. Therefore, the NRC has no records subject to this request.
Lindsay Audin In response to a request for records received by the NRC (85-835) in response to its February 24, 1984, inquiry to the Central Electricity Generating Board, made available four records.
Robert Todd in response to a request for all records pertaining to (85-848)
" unusual events", possible security threats, and violations of the airspace at the Indian Point nuclear power plant on or about July 24, 1984, informed the requester that the NRC has no records subject to this
- request, ENCLOSURE A g
7g
4 Granted, Cont'd John W. Flora, In response to a fequest for a ' copy of the Open Items Nuclear Consultant that were registered during 1984 and 1985 in Region III, (86-6) made available a computer printout.
Lynn Connor, In response to a request far copiis of the construction Doc-Search status reports for 1985, made available 13 records.
Associates Informed the requester that three additional records (86-11) subject to this request are alrerdy available at the PDR.
Cindee Virostek, In response to a request for a copy of a report identified Kiski Valley as ORNL-NSIC-69, informed the requester that we have Coalition referred her request to the DOE for response to her.
(86-25)
Denied Diane Curran, In response to a request for five categories of records Harmon, Weiss &
and infomation related to NUREG/CR-3597, SAND 84-0138, Jordan RV; NUREG/CR-3418, SAND 83-1617, RV; and Board (84-863)
Notification 84-032, made available 144 records.
Informed the requester that additional records subject to this request are already available at the PDR. Denied four records in their entirety and portions of four records containing confidential business (proprietary) information.
Steven C. Sholly, In response to a request for copies of (1) J.D. Harris MHB Technical (ORNL)andJ.W.Minarick(SAIC),"AnEvaluationofBWR Associates Over-Presure Incidents in Low Pressure Systems," May 1985, (85-804) as well as any subsequent versions; (2) N. Hanan, et al.,
"A Review of BWR/6 Standard Plant Probabilistic Risk Assessment, Vol. 1, Internal Events and Core Damage Frequency," BNL, NUREG/CR-4135, May 1985; and (3) all technical reports prepared by Sandia National Laboratories pursuant to FIN A-1227, "High Temperature Fission Product Chemistry Program," made available copies of items 1 and 3.
Denied portions of item 2 containing confidential business (proprietary) information.
Patty Day, In response to a request for copies of (1) April 25, NUS Corporation 1974, Staff Evaluation of Tests Conducted to Demonstrate (85-805) the Functional Adequacy of the Ice Condensor Design; (2)
November 21, 1974, letter from Vassallo (NRC) to Salvatori (Westinghouse) with the enclosed requested Topical Report Evaluation; (3) November 3, 1975, letter from Vassallo to Eicheldinger (Westinghouse) with the enclosed Topical Report Evaluation; (4) May 1974 WCAP-8282-Addendum 1
" Answers to AEC Questions on Report WCAP-8282;" and (5)
December 1974, MXA-0-402, "The Marviken Full Scale Containment Experiments " made available copies of items 1 through 3.
Informed the requester that the NRC is not in possession of item 5.
Denied portions of item 4 containing confidential business (proprietary) information.
- I ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JANUARY 17, 1986 PFP ISSUED RFP issued under Small Business Innovation Research Program
Title:
"Small Business Innovation Research Program Solicitation"
==
Description:==
Objectives of the solicitation are to: stimulate technological innovation in the private sector; strengthen the role of small business in meeting federal research and development needs; increase the commercial application of NRC-supported research results; and improve the return on investment from federally-funded research for economic and social benefits to the nation.
Period of Performance: Phase I - 6 months Sponsor: Office of Nuclear Regulatory Research Status: RFP issued on January 13, l'S6.
Proposals due March 28, 1986.
RFP No.: RS-ORM-86-264
Title:
" Development of the Corporate Data Network"
==
Description:==
The contractor will develop shared data bases utilizing the Data Base Management System package IDMS/R and strategic data planning and information engineering methodologies.
Period of Performance: Three years Sponsor: Office of Resource Management Status:
RFP issued on January 16, 1986.
Proposals due February 28, 1986.
PROPOSALS UNDER EVALUATION RFP No.: RS-ADM-86-216
Title:
"The Regulatory Process"
==
Description:==
Presentation of two-day course entitled, "The Regulatory Process" Period of Performance: 24 months Sponsor: Office of Administration Status: RFP closed on January 16, 1986. Proposals forwarded to Source Evaluation Panel for review on January 16, 1986.
RFP No.: RS-NRR-86-055 Titie: " Assessment and i.pplication of Thermal-Hydraulic Phenomena for Severe Accident Decisions"
==
Description:==
Generic Assessmen; of thermal hydraulic issues associated with severe accidents, revie's all LWR designs to determine the specific applicability of results of tre generic assessment of thermal-hydraulic issues, and provide support for implementation of NRC's severc accident policy, review of probi.blistic risk assessments and prioritization of generic issues.
1 Period of Performance:
30 months Sponsor: Office of Nuclear Reactor Regulation Status: RFP closed on January 13, 1986.
Proposals forwarded to Source Evaluators for review on January 13, 1986.
ENCLOSURE A JAN 171996
i
?
Weekly Information Report
~'
Division of Contracts
' PROPOSALS UNDER EVALUATION (cont'd)
F 2
RS-ORM 85-335 RFP No.:
Title:
" Integrated Library System"
==
Description:==
Sof tware maintenance, support and timesharing services for the Integrated Library System.
Period of Performance: Two years with one option year Sponsor: Office of Resource Management Status: Best and Final offers received on January 10, 1986 and forwarded to Source Evaluation panel for review on January 10, 1986.
CANCELLATION RFP No.: RS-NMS-86-002
Title:
"The Need for Spent Fuel Storage Capability"
==
Description:==
Technical assistance in determining spent fuel inventory and storage capability through calendar year 2000.
Period of Performance: 21 months Sponsor: Office of Nuclear Material Safety & Safeguards Status: RFP cancelled on January 15, 1986-
=
ENCLOSURE A JAN 171986
t OFFICE OF NUCLEAR REACTOR REGULATION i
ITEMS OF INTEREST Week Ending January 17, 1986 l
Big Rock Point Nuclear Power Plant On January 8, 1986, the NRC issued to Consumers Power Company an exemption from certain requirements of Appendix J to 10 CFR Part 50.
The exemption pertains to the requirements to leak test the containment airlocks within 3 days after each opening.
l t
Due to the unique plant design, the personnel airlock is used daily for safe operation of the plant. Since the airlocks are all of the single i
seal design, an entire airlock must be pressurized to perform the required leak rate test.
t Palo Verde Unit 1 The Arizona Public Service Company (licensee) informed us (Friday, January 10,1986) that on the afternoon of January 9, 1986 the plant experienced an unexpected type of trip. The trip occurred during the test Derformance of a turbine trip from 100% and was caused when a i
failure of auto transfer of house loads to offsite power resulted in a projected low DNBR trip when the RCS pumpt started to coast down.
The licensee is currently evaluating the event to determine the root i
causes. A reactor trip was anticipated for this test (via a high nressurizer pressure signal) but the lack of auto transfer was not expected.
Palo Verde Unit 1 is in the last stages of the power ascension test program.
In addition to the unsuccessful turbine trip from 100% power, j
the only other test remaining is the natural circulation cooldown test.
B&W Regulatory Response Group i
On January 8,1986, the staff met with the B&W Regulatory Response Group to discuss the generic implications of the December 26, 1985 Rancho Seco loss of integrated control system (ICS) power event. The Regulatory Response Group (RRG) presented information to demonstrate that the other B&W plants are sufficiently different such that the transient that occurred at Rancho Seco would not be as severe at the other plants. Accordingly, they concluded that no immediate action at other B&W facilities was required. The RRG also concluded that due to similiarities, additional review of the Rancho Seco event should be undertaken to identify actions to reduce the frequency and magnitude of transients.
In addition, special training will be conducted to familiarize operations with the Rancho Seco event. A B&W Owners Group Executive Committee meeting scheduled for January 16, 1986 will finalize the actions to be taken. The B&W Owners Group Program and ENCLOSURE B JAN 171980 i
i y-. -,,
m._
-...m__._
-w.-
-_mm.,_m
.-_._m.,
__,r..m,.-__-._r_+,.,_~.,
-.,r v
Plans, will be reported to the staff at a meeting scheduled for February 5,1986. Based on the information presented at the meeting, the staff concluded that no immediate action is required for the other B&W plants.
River Bend On January 8,1986, while repairing a damaged feedwater valve operator, a Limitorque technical representative raised questions on the environmental qualification of certain wiring in the valve operator.
Subsequently, the licensee found seven other valve operators with identical procurement histories (GE/Velan) to have similar questionable wiring. These seven valves are on the HPCS system. The licensee declared the HPCS system inoperable.
River Bend Station has been shutdown since January 7,1986. The licensee previously verified wiring on all valves within containment and is currently inspecting other valves outside containment. The licensee replaced the wiring in these eight valves by January 12, 1986, and expects to restart and be operating at 35% rated power a week later.
Region IV is following up on valve inspections and has reported this situation to the Vendor Inspection Branch.
Crystal River Unit 3 - Industrial Accident Involving 2 Divers During the afternoon of January 10, 1986, while cleaning trash from the circulating water / nuclear services cooling water intake area, two contract divers drowned. Complete information is not yet available, but the circumstances appear to be as follows.
The plant was shutdown for repairs to a failed reactor coolant pump.
Circulating water pumps were secured, but two service water pumps were operating, taking suction from a sump fed by a 48" line from the intake structure. One divar was found in the sump having presumably been drawn into the 48" line, flow in which had a calculated velocity of about 4 fps. The other, who had entered the intake area to check on the first, was pulled back when his tether went taut.
In order to remove the body of the first diver, all pumps drawing water froro the sumps, including the decay heat service water, were secured.
In a planned evolution, an industrial cooling line was cross connected to the decay heat cooling system, allowing a decay heat temperature rise of 30*/hr. from an initial temperature of 95 F.
Train B of the decay heat service water system, taking suction from an adjacent inter-connected sump, was also available if necessary, as well as the capability to add water to the RCS. Reactor core thermocouples were closely monitored. When the decay heat pump suction temperature reached 175*F, in about three hours, the B train was started and left on. No other nuclear concern arose during this accident.
ENCLOSURE B JAN 171986
TMI-E Leak Rate Testing On January 9,1986, GPU Nuclear Corporation provided the report of the GPU Assessment Panel for Individuals Involved in TMI-2 Leak Rate Testing to the NRC and simultaneously released it to the public. The Assessment Panel was established by the Chairman of GPU and is comprised of the Presidents of GPU Nuclear Corporation, Pennsylvania Electric Company, Metropolitan Edison Company and Jersey Central Power and Light Company.
The subject of the report involves an investigation of irregularities in the conduct of tests designed to determine leakage from the primary coolant at TMI-2 during late 1978 and early 1979.
In its determination, the Panel reviewed the report (dated September 5, 1985) of an independent investigation of the leak rate testing by Edwin H. Stier, a New Jersey attorney and former director of the New Jersey Division of Criminal Justice, to determine what disciplinary action, if any, should be taken with respect to those individuals involved in improper TMI-2 leak rate testing and who are still employed by GPU. The Panel concluded that of 24 current GPU system employees considered for possible disciplinary action, 17 employees acted improperly in conducting the tests and disciplinary actions are being taken against those individuals. The other 7 employees were found to have acted properly and no disciplinary action was taken against these individuals.
NRC hearings on individual employee involvement in improper leak rate testing are scheduled for later this year. Since those hearings could develop information not available to the Assessment Panel, some actions taken were made subject to review following the NRC proceeding.
Three Mile Island-Unit 2 On Sunday, January 12, 1986, GPU Nuclear began the removal of accident-generated core debris from the TMI-2 reactor vesu I.
Three fuel canisters, each containing from 300 to 350 pounds (f material, were transferred from the reactor vessel to submerged storage racks in the "A" Spent Fuel Pool located in the fuel handling building. These canisters were loaded with partial fuel assemblies, end fittings, control rod spiders and other large debris by defueling operators using long-handled tools.
Prior to transfer, each canister was sealed, dewatered, and weighed. Normal fuel handling eouipment has been modified to handle the specially designed canisters and to provide shielding as canisters are transported through air between the reactor vessel and the flooded end of the fuel transfer canal.
Radiation surveys conducted during the initial transfers indicated a maximum radiation level of 20 mR/hr at the surface of the canister transfer shield.
ENCLOSURE B JAN 171986
o e,
l On Monday, January 13,1>86, a knockout canister was also successfully transferred to a storage location in Spent Fuel Pool "A".
The knockout canister was filled with 1100 pounds of loose granular debris removed from the debris bed using a vacuum system. The maximum radiation level measured during knockout canister transfer was 40 mR/hr. Loading and storage of defueling canisters will continue. Off-site shipment of canisters to a Department of Energy facility is expected to commence in late spring of 1986.
Catawba Unit 2 The staff was informed by Duke Power Company that Catawba Unit 2 current schedule for fuel load is March 1,1986. This date is predicated upon the TDI Diesel Generator 2B being operational, by early February, to complete the ESF testing.
Presently, the licensee has completed flushing the lube oil system and is about to complete the reassembly of the 2B engine to perform the break-in runs.
Shoreham Emergency Planning Drill Suffolk County Executive Peter Cohalan, on January 15, 1986, signed a new law which makes it a misdemeanor, punishable by one year in prison, to conduct or participate in a test or exercise of a natural or man-nede emergency situation, unless the County legislature has previously approved the exercise. The law also prohibits the simulation of the roles or governmental functions of any Suffolk County official during such an exercise without the prior approval of the legislature. The new law appears to be aimed at preventing the conduct of an emergency planning drill next month for Shoreham.
J f
ENCLOSURE B JAk 171986
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING JANUARY 17, 1986 1.
DEFUELING On January 13, 1986, the first knock-out (K0) canister was transferred successfully from the reactor vessel to the canister storage rack in the spent fuel pool (SFP) of the Fuel Building.
This K0 canister has been loaded with 1,050 lbs. of fuel debris.
Along with the three fuel canisters transferred from the Reactor Building to the SFP on January 12, 1986, a total of approximately 2,200 lbs. of fuel debris and damaged fuel assembly structural materials have been transferred to the Fuel Building.
Prior to defueling, the total weight of damaged fuel and structural materials in the reactor vessel is estimated to be about 308,000 lbs.
Three empty fuel canisters have been installed in the Canister Positioning System and defueling by pick-and-place is in progress.
By January 1., 1986, the defueling workers had almost filled one fuel canister with end-fittings and control rod spiders. Using a slide-hammer tool, some success was achieved in breaking fused end-fittings such that they can be loading into the fuel canister.
During the transfer of the first fuel canister and the first K0 canister, radiation control technicians performed a radiation profile survey on the surface of the canister transfer shield. The highest dose rate was 22 mrem /hr for the fuel canister and 35 mrem /hr for the K0 canister.
These dose rates are relatively very low, especially considering the loading of the K0 canister with over 1,000 lbs. of fuel debris.
2.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel.
The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel. transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the internals indexing fixture.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 67*F to 95 F with an average of 82 F.
JAN 171986 ENCLOSURE B
The average reactor building temperature is 57 F.
The reactor building airborne activity at the Westinghouse platform is 8.3 E-8 uCi/cc Tritium and 1.3 E-10 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded tc e depth of 20 feet. About 6 feet of water is over the fuel canister storage racks.
3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) remained shutdown this week.
EPICOR II commenced processing of Batch 275, which consists of 2,678 gallons of water in CC-T-2 to be recycled through the system and returned to CC-T-2.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,779,214 gallons.
4.
DOSE REDUCTION / DECONTAMINATION Decontamination activities are continuing on the 281' level of the auxiliary building.
Kelly-vac cleaning of the decay heat vaults is in progress.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
5.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from December 28 through January 4, 1986. A gamma scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from December 29 through January 4, 1986. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI site collected a sample between January 8, and January 15, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
6.
REACTOR BUILDING ACTIVITIES Initial vacuum defueling of the reactor core is in progress.
The pressurizer manway cover has been removed and the access port shielded. Sludge samples have been removed from the pressurizer and further examination is in progress.
JAN 171986
0 3-7.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.
Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
8.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
9.
PUBLIC MEETINGS The next meeting of the Advisory Panel is scheduled for February 12, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.
Persons desiring the opportunity to speak before the panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
JAN 171956 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending January 17, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Section:
141(b) of NWPA:
Comments on MRS Proposal Status:
DOE submitted to the Commission the Monitored Retrievable Storage facility proposal on December 24, 1985.
Staff comments were transmitted to the Commission for approval on January 7, 1986 (SECY-86-9).
Action:
The Commission will be briefed by Mr. Ben Rusche, Director of OCRWM, concerning the MRS proposal on Thursday, January 23, 1986 at 2:00 p.m.
NRC comments are to be submitted with the proposal to Congress in early February 1986.
Section:
141(d) of NWPA:
Licensing of MRS Status:
NRC has developed revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress.
Action:
The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1985, for approval, which is expected in late January 1986, after the Commission briefing by Ben Rusche on January 23, 1986.
Section:
121(a) of NWPA:
EPA final High Level Waste Standards Status:
EPA final HLW Standards became effective on November 18, 1985.
' A lawsuit has been filed by States and environmental groups challenging the EPA rulemaking (40 CFR Part 191, Paragraph 16).
Action:
Staff is currently preparing revisions to 10 CFR Part 60 for conformance with EPA standards. The ACRS was briefed on this subject on January 15, 1986.
The proposed revisions are scheduled to be submitted to the Commission on February 14, 1986.
ENCLOSURE C JAN 171986
Section:
306 of NWPA:
Regulations for Training of Power Plant Personnel Status:
The final rulemaking package on Part 55 dealing with simulation training requirements and three associated regulatory guides has received office concurrence and ACRS approval.
Action:
The final rule will be submitted to the CRGR for review on February 12, 1986, and then to the Commission for approval.
Section:
113(b)(1)(B) of NWPA: Waste Package / Form Description Status:
"Before proceeding to sink shafts at any candidate site, the Secretary shall submit... a description of the possible form or packaging for the" HLW or SNF.
This will be issued along with the Site Characterization Plans [113(b)(1)(A)].
Action:
DOE and NRC will be conducting a joint Salt Waste Package Workshop on January 22-24, 1986 in Columbus, Ohio, to discuss DOE salt waste package design and its relationship to 10 CFR Pr.rt 60 requirements, and other waste package technical issues.
Sequoyah Fuels On January 14, 1986, the NMSS staff held a meeting to establish a task force to evaluate the public health impact associated with the accidental release of UF which occurred at the Sequoyah Fuels Facility, Gore, Oklahoma.
The g
attendees included members from EPA, Center of Disease Control (HEW), Oak Ridge National Laboratory (0RNL), Lawrence Livermore Laboratory (LLL), Dr. Paul Morrow (University of Rochester), and the State of Oklahoma.
At the meeting, an out-line of the proposed NRC technical report was presented.
There will be another meeting to brief the group after all the data are collected.
The data will be tabulated and provided to individual members of the task force and will be used for impact analysis.
NFS-Erwin Strike by OCAW members continues.
There has been essentially no negotiating between the Union and NFS within the last couple of months, so resolution of the differences between the parties is not expected in the near term.
NFS continues to conduct limited operations of the HEU production, scrap recovery, and R&D facilities.
ENCLOSURE C JAh 171986
Office of Inspection and Enforcement Items of Interest Week Ending January 17, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
EA 85-50 issued January 14, 1986 to Florida Power and Light Company (Turkey Point), $100,000.
2.
The following IE Preliminary Notifications were issued during the past week:
PNO-I-86-01, Washington Hospital Center (Washington, DC), Entry Into a.
High Radiation Area with Teletherapy Interlocks Inoperable, b.
PNO-II-86-05, Georgia Power Company (Vogtle Units 1 & 2), Bomb Threat.
PN0-II-86-06, Florida Power Corporation (Crystal River Unit 3), Two c.
Divers Drown While Working in Water Intake Area.
d.
PNO-TMI-86-01, GPU Nuclear Corporation (Three Mile Island Unit 2),
First Core Debris Removed From TMI-2 Reactor Vessel.
PN0-IV-86-02C, Sequoyah Fuels Corporation (Gore, OK), Ruptured e.
Uranium Hexafluoride Cylinder (Update).
f.
PN0-IV-86-02D, Sequoyah Fuels Corporation (Gore, OK), Ruptured Uranium Hexafluoride Cylinder (Update).
g.
PN0-IV-86-02E, Sequoyah Fuels Corporation (Gore, OK), Reptured Uranium Hexafluoride Cylinder (Final Update).
h.
PNO-IV-86-04, PA Incorporated (Houston, TX), Truck Accident Involving Cs-137 Sources.
i.
PN0-IV-86-05, Arkansas Power and Light Company (Arkansas Nuclear One, Unit 1), Outage Greater than Two Days.
j.
PN0-V-86-03, Arizona Nuclear Power Project (Palo Verde Unit 1), Loss of Forced Reactor Coolant System Circulation Following Full Power Trip Test.
3.
The following IE Information Notice was issued during the past week:
IE Information Notice 86-03, Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Wiring was issued January 14, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.
ENCLOSURE D JAN 171986
4.
Other Items a.
Civil Penalties Paid (1) EA 85-52 issued December 9,1985 to Commonwealth Edison Company (Byron),$25,000.
b.
Visit to Davis-Besse IE Director and RIII Administrator met with Davis-Besse staff and toured the facility on January 14, 1986.
c.
IE Inspections (1) Representatives of the Reactor Construction Programs Branch, Division of Inspection Programs began site effort on a construction appraisal team inspection at Palo Verde. Site visit is scheduled for January 13 thru 24 and February 3 thru 14.
(2) Representatives of the Vendor Programs Branch, Division of Quality Assurance, Vendor, Technical Training Programs conducted site efforts this week at TVA's Sequoyah Power Facility, Joseph Oat Corp. (Camden, NJ) and Westinghouse (Monroeville, PA).
(3) Representatives of the Operational Reactor Programs Branch, Division of Inspection Programs and Region II and IV inspectors began site effort and safety system functional inspection at Arkansas Nuclear One. Site visit is scheduled for January 13 thru 17 and 27 thru 31.
d.
Accompanying Regional Inspections A representative of the Operating Reactors Programs Branch, Division of Inspection Programs accompanied Region I inspection of Pilgrim from January 13 thru 17, 1986.
e.
Meetings (1) Representatives of the Operating Reactor Programs Branch, Division of Inspection Programs attended Region II's quality assurance inspection program meeting on January 14, 1986.
(2) A representative of the Safeguards & Materials Programs Branch, Division of Inspection Programs attended a radiography steering t
committee meeting in Austin, Texas on January 15-16, 1986.
i f.
Shoreham Update (1) On January 9, 1986, the Director Division of Emergency Preparedness and Engineering Response, the Incident Response Branch Chief and staff met with FEMA Associate Director, State and Local Programs Support and staff to review the staff ENCLOSURE D
]
JAh 1.i 1986
- planning for the control of the offsite portion of the Shoreham exercise.
In the meeting, there was a determination as to wr.ich controller positions NRC would prnvide an individual.
Final decisions regarding the specific assignment of individual controllers were to be determined after review of the control plan with the FEMA RAC Chairman.
(2) On January 14-15, 1986, Incident Response Branch staff met with the FEMA RAC Chairman and other FEMA support to review and finalize the draft Control Plan and make assignments for the remaining tasks to implement the Control Plan and assure that all logistic matters have been addressed.
(3) On January 15, 1986, Incident Response Branch staff, the FEMA RAC Chairman and other FEMA support met with the LILC0 exercise planning staff to assure that FEMA adequately understands the LILC0 control plan so that the FEMA offsite Control Plan is designed appropriately and will not adversely impact on the LILC0 offsite scenario, g.
Operations Center Briefing (1) On January 13, 1986, the Incident Response Branch, Division of Emergency Preparedness and Engineering Response, sponsored a briefing by the Federal Bureau of Investigation which was held in the Operations Center.
(2) DOE contractors visited the Operations Center on January 16, 1986, for discussions on lessons learned on Operations Center design.
ENCLOSURE D JAN 171986
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending January 17, 1986 Multiloop Integral System Test (MIST) Program Congressman R. Reg;1a (Ohio 16th District) toured the Babcock and Wilcox (B&W) research facilitiet in Alliance, Ohio on Thursday afternoon, January 9,1986. This tour included the MIST facility which is jointly sponsored by the NRC, B&W's Owner's Group, B&W, and the Electric Power Research Institute. The MIST facility is an integral test facility designed to simulate thermal hydraulic aspects of transients in reactors of the B&W design. The facility is currently in shakedown testino.
Regulatory Guide Supporting..;;pendix K Revision RES has proposed, and forwarded to NRR, a draft regulatory guide providing guidance on acceptable methods of compliance with the proposed revision to 10 CFR 50.46 and Appendix K.
In an effort to maintain consistency with the current Appendix K, the RES staff has identified a number of specific models and correlations, which are supported by an adequate experimental data base, which would be acceptable for use in a best-estimate emergency core cooling system (ECCS) performance calculation methodology. The regulatory guide clearly specifies that the models and correlations are referenced for guidance only and that their acceptability will be determined in the context of the evaluation methodology submitted by the licensee. Supporting documentation of the methods and models have been forwarded in advance to NRR to facilitate office review.
ROSA-IV International Cooperative Program Between NRC and the Japanese Atomic Energy Research Institute (JAERI)
The ROSA-IV Program conducts large-scale thermal hydraulic tests under a cooperative program between NRC and JAERI. JAERI conducts small-break and secondary transient tests and provides these test results to NRC for assessnent and improvement of the NRC regulatory safety analysis codes. Since October 1985, Tests SB-PR-01 (loss-of-coolant accident with PORV stuck-open), ST-NC-01 (natural circulation cooling-high core power),
ST-NC-02 (natural circulation cooling-low core power), ST-SG-01 (heat transfer in steam generator-high core power), and ST-SG-02 (heat transfer in steam generator-low core power) were completed in the Large-Scale Test Facility at JAERI on schedule. The test data will be processed and delivered to INEL on a best-effort basis.
A FACOM (vectorized) version of RELAP5/M002 Cycle 36 has been developed by JAERI and will be transferred to INEL. This version can be used in t' International Code Assessment Program, if a participant possesses a FAc0M computer.
ENCLOSURE E JAN 171986 i
Direct Containment Heating On January 13, 1986, the vessel was delivered to Sandia National Laboratories for the facility in which the USNRC is planning tests on high pressure melt ejection to quantify its effect on direct heating of containment by dispersing core debris.
The vessel is approximately 40 feet high, has an outside diameter of 12 feet and has enough volume to simulate 1/10 linear scale of large pressurized water reactor (PWR) dry containments.
Ins 0111ation of the facility is continuing and acceptance and shakedown tests are expected to be completed by the end of January,1986.
The first test in this facility is currently projected to be conducted at the end of February,1986.
Safety issues relating to high pressure melt ejection sequences have been identified as requiring further research by the American Physical Society review of NUREG-0956 and remain an important cause for uncertainty in the forthcoming NUREG-ll50.
Boiling Water Reactor (BWR) Core Power Variation With Pressure,and Water Level The rebaselining studies of risk for the reference plants include anticipated transient without scram (ATWS) analyses that require knowledge of the core power at various pressure.
The Oak Ridge National Laboratory Severe Accident Sequence Analysis (SASA) group has completed the calculation and issued a letter report that provides core power during a main steam line isolation valve (MSIV)-closure-
-initiated ATWS as a function of reactor vessel pressure and water level.
The major parameters affecting the power level, in addition to the void coefficient, are the saturated liquid moderation density and the dc@ler.coefficienct.
Battelle Columbus Laboratory (BCL) has reviewed th" ;;aults and verified that this information is sufficient for the NUREG-ll50 calculations.
These calcula-tions will provide a more realistic estimate of the reactor power during ATWS.
SEVERE CORE DAf' AGE ACCIDENT PROGRAM (SCDAP) Code Application The Severe Core Damage Accident Prngram code is a detailed mechanistic code for degraded core analysis.
It predicts fission product release and hydrogen generation in a reactor during recovered severe accidents.
A SCDAP calculation has been performed for NRR to estimate hydrogen generation in a degraded fuel assembly to provide information for NRR to address issues with the Hydrogen Control Owners Group (HCOG). Additionel SCDAP applications are anticipated to meet NRR needs.
i l
5 JAN 171986 ENCLOSURE E s
. Presence of Cesium Iodide in PSF Test Cesium iodide was tentatively identified in the PBF SFD 1-3 test from a sample collected on a deposition rod located 5-feet Samples from the top of the fuel bundle in the test train.
collected up to the 5-foot elevation have not shown any cesium So far, identification of cesium iodide has been made Analysis of additional iodide.
in only one sample from the PBF 1-3 test.
samples for the presence of cesium iodide is continuing.
Unsaturated Rock / Contaminant Transport Workshop III During the week of January 6, 1986, RES sponsored a workshop at the University This workshop, entitled " Unsaturated Rock and Containment Transport Workshop III," was the third workshop over a 5-year period to review RES-spon of Arizona.
work and findings on unsaturated ground water flow and transport in fractured rocks.
Tom Nicholson, the NRC Project Manager for this project, explained in the opening session that the purpose of this research is to support NMSS in their assessment and licensing of high-level nuclear waste repositories that conform to NRC and EPA regulations.
First, there and those discussions led to the following general conclusions.
is still debate as to whether the primary flow path of water in unsaturated
- Second, fractured rocks is through the fractures or through the rock matrix.
while bore hole instrumentation developed to date is useful, the field work now being done indicates clearly that further refinements in instrumentation are needed to provide reliable and consistent measurements of r the unsaturated zone.
Third, there was a properties in fractured rock appears to be promising.
gereral consensus that much more field data are needed for validation of of unsaturated fracture flow, and finally, considerable interest was expressed in the continued study of natural analogs as a possible source of real-world data for model validation, t
i JAN 171986 ENCLOSURE E
4-RES RULEMAKING ACTIVITIES Emergercy Core Cooling Systems; Revisions to Acceptance Criteria (Part 50)
(Appendix K).
The proposed rule would amend regulations concerning acceptance criteria for emergency core cooling systems (ECCS) by changing the methods used to demon-strate that an ECCS would protect the nuclear reactor core during a loss-of-coolant accident. Because the proposed rule represents a significant change in a regulatory requirement, the staff is currently preparing a summary of ECCS research perforned over the last 10 years which will serve as the technical basis for the proposed rule and a regulatory guide which will provide defini-tion of what constitutes an acceptable best estinate model and acceptable methods of performing the uncertainty evaluation.
A revised Federal Register notice and Commission paper has been prepared considering the unofficial NRR comments.
By memorandum dated December 6, 1985, DAE requested NRR and ELD to review and comment on the paper by January 31, 1986.
Techr..ual documents that describe in detail the codes, models and methods that are to be referenced in the regulatory guide accompanying the rule have been informally sent to NRR for review and evaluation. A revised draft of the regulatory guide and a formal request for review and comment of the guide and models is being transmitted this week.
Standards for Protection Against Radiation (Part 20)
Radiation protection philosophy and technology have changed markedly since the present Part 20 was promulgated nearly 30 years ago.
Because the present Part 20 has become outdated, most radiation protection actions occur through licensing actions independent of Part 20. A complete revision is necessary to provide better assurance of protection against radiation; establish a clear health protection basis for the limits; reflect current information on health risk, dcsimetry, and radiation protection practices and experience; provide NRC with a health protection base from which it may consider other regulatory acticns taken to protect public health; be consistent with recommendations of world authorities (ICRP); and apply to all licensees in a consistent manner.
The Federal Register notice of proposed rulemaking for 10 CFR Part 20 was published in the Federal Register on December 20,1985, for a 120-day public comment period.
Due to an unusually large number of typesetting errors, it was decided to reprint the entire Federal Register notice.
Republication of the Federal Register notice occurred on Thursday, January 9,1986, and the comment period has been extended to May 12, 1986.
Distribution of the corrected Federal Register notice to licensees and other interested parties began on Janua ry 13, 1986.
ENCLOSUPE E g
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JANUARY 17, 1986 Foreign Trip Reports J. E. Hardy and R. A. Hess, ORNL November 4-15, 1985; Visited Japan:
The purpose of this trip was to check out and calibrate the ORNL-supplied electronics for the Slab Core Test Facility Core III (SCTF-III) and participate in the force calibration tests, the high-temperature calibration test, and the wet and dry calibration runs.
C. Z. Serpan, Jr., Chief, MEBR/DET/RES November 19-25, 1985; Visited France and the FRG:
Mr. Serpan attended the OECD/NEA Committee on the Safety of Nuclear Installations meeting in Paris on November 20-21, 1985 and presented the PWG-3 program.
In Germany, he visited with representatives of GRS, KWU and MPA-Stuttgart to discuss the flow of information between the U.S.
and the FRG.
JAN 1719S6 ENCLOSURE G
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JANUARY 17, 1986 State Program Reviews The Idaho and Washington radiation control programs will be reviewed beginning the week of January 27, 1986. Waste Management staff will assist in the review of the uranium mill portion of the Washington program.
4 l
l ENCLOSURE H JAN 171986 l
REGION III STATUS REPORT
. DAVIS-BESSE LOSS OF FEEDWATER EVENT JANUARY 17, 1986 Plant Status The plant remains in cold shutdown. The licensee is continuing to investigate the cause of the restricted flow of water from Lake Erie to the plant that occurred in December, 1985. The investigation is being hampered by lake ice conditions. The flow has returned to normal.
Restart Activities Region III staff actions, as assigned by Mr. W. Dircks memo of August 5,1985, relating to monitoring of troubleshooting and root.cause determinations, are completed and documented in Inspection Reports 85021, 85022 and 85025.
Verification of cuxiliary feedwater system (AFW) testing to confirm system configuration and training of operators in resetting the AFW trip throttle valve will be completed during plant restart.
A NRR maintenance survey inspection is planned for late February to followup on previous findings and to evaluate the licensee's actions concerning management practices as they relate to the maintenance area.
Other Activities Installation of the new electric motor driven startup feedwater pump is complete. The licensee is now testing the new system.
Inspections of safety system piping supports in the auxiliary building are ++
continuing.
Evaluation of the nonconformances (NCR) found on supports in containment is in progress. Of the supports requiring disposition prior to restart, eighteen remain to be dispositioned.
M0 VATS testing, environmental qualification work and other maintenance
++
activities continue on the 167 safety-related motor-operated valves onsite.
The licensee has completed all work on twenty seven valves and returned them to service. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The licensee has begun modifications required to make the control room
++
emergency ventilation system operable. The time required to complete this work has expanded due to difficulties in identifying required materials.
ENCLOSURE L JAN 171986
The licensee's inspection and review of items raquiring environmental
++
qualification continues to identify components that require repair, replacement, or further engineering evaluation.
The NRC test review team continues to provide weekly coverage of licensee
++
testing activities. Recirc and full flow testing of the newly installed feedwater pump has been completed. System flushing is scheduled to start January 18, 1986 along with Emergency Diesel Generator and Containment Air Cooler Damper testing.
Incore monitoring testing has been in progress since January 10, 1986 with seven of thirty-six strings tested found failed.
Licensee Organizational Changes M Schefers has assumed the recently created position of Information Management Director.
L. Ramsett has been appointed Quality Assurance Director.
E. Salowitz has been appointed Planning Superintendent.
C. Daft has been appointed Qualily Assurance Engineering Manager.
Meetings The Maintenance Assessment Team will hold a working meeting on January 23,1986 in Washington, D. C..
Members from Divisions of Reactor Safety and Reactor Projects, Region III and the Senior Resident Inspector will attend.
ENCLOSURE L JAN 171986 2
ITEMS ADDRESSED BY THE COPNISSION - WEEK ENDING JANUARY 27, 1986 A.
STAFF REQUIREMENTS - BRIEFING BY STAFF ON TVA CORPORATE PLAN. 10:00 A.M..
TUESDAY, JANUARY 7, 1986, COMMISSIONERS' CONFERENCE ROOM. D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD 1/17/86 The Commission met with staff to be briefed on TVA's program for improvement, and the current status of the staff's review and evaluation of the TVA program.
Chairman Palladino indicated that a follow-on briefing would be scheduled at a future agenda plannir.; ression.
I JAN 171986 ENCLOSURE 0 4
E NRR MEETING NOTICES *
[l JANUARY 17, 1986 c3 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 1/21/86 50-295 P-110 Discuss CECO proposed usage of Commonwealth Edison J. Norris 9:00 a.m.
50-304 Phillips Bldg.
Reactor Vessel Level Indication Company System (RVLIS) in the Emergency Response Guidelines (ERG), and to address the treatment of RVLIS inaccuracies in the ERG application.
1/22/86 50-206 Room 508 To discuss schedule for review of Southern California R. Dudley 2:00 p.m.
Phillips Bldg.
seismic analyses with San Onofre Edison Company Nuclear Generating Station, Unit 1.
1/23/86 50-029 P-114 To discuss actions necessary to Yankee Atomic J. Clifford 10:00 a.m.
Phillips Bldg.
complete seismic analysis for the Electric Company systematic evaluation program.
1/28/86 50-424 P-114 Discuss streamlining (i.e.,
Georgia Power Company M. Miller 9:00 a.m.
50-425 Phillips Bldg.
elimination of redundant or unnecessary portions) of the Vogtle - specific Technical Specifications.
1/29/86 P-114 Discuss development of a Commission Region I, III, IV, V, T. Michaels 9:00 a.m.
Phillips Bldg.
Policy Statement on deferred and IE, OELD and RES cancelled plants.
1/30/86 50-295 P-114 Meeting with Commonwealth Edison Commonwealth Edison J. Norris 9:00 a.m. 9 50-304 Phillips Bldg.
Company (CECO) regarding reload Company F2 methodology for Zion 1 and 2.
!5 m
Copies BY summaries of these meetings will be made publicly available and placed in the respective docket file (s) o in the NRC and local public document rooms s
NMSS MEETING NOTICES Division of Fuel Cycle and Material Safety b
DOCKET ATTENDEES /
- DATE/ TIME NUPEER LOCATION PURPOSE APPLICANT NRC CONTACT o
h 1/22/86 Willste Meeting of the Interoffice Working Reps fm RI, II, Miller 1:15 pm 8th floor Group.
III, IV & V, conf room NMSS, SP IE, AE00, RES, ED0 1/24/86 71-9201 Willste Discuss shipping packaging for D. Haelsig, etc. (NPI) Odegaarden 1:00-4:00 2nd floor radiation (therapy) unit with H. Lee (FC) conf room Nuclear Packaging, Inc. (NPI).
R. Odegaarden (FC) 1/24/86 Washington, To present paper at the INPM F. Sturz (FC)
Sturz DC Seminar on Spent Fuel Storage L. Rouse (FC)
Technology re: Licensing of Dry ISFSI and MRS.
Paper to be presented by Fritz Sturz.
1/28/86
- DOE, Resolution of observed discrepan-G. Bidinger (FC)
Bidinger Germantown cies between critical mass experiments and calculations.
1/31/86 Washington, final Advisory Panel meeting for R. Cunningham (FC) Cunningham 8:30-4:30 DC the Office of Technology Assessment Transportation of Hazardous Materials Assessment.
Division of Safeguards None
{
Division of Waste Management r-None
h RES MEETING NOTICES January 17, 1986 w
Docket Attendees /
g Date/ Time Number Location Purpose Applicant NRC Contact 1/22-24/86 L' Enfant Plaza INPN Workshop on the Propagation of Abramson Abramson Wash.,0C Error for Nuclear Materials Frattali Accounting 1/28/86 Nicholson Lane Resolve Peer Review Comments on Frattali Fra ttali NRC Office Chapters 1-12 of the Statistical Abramson Handbook for NHS Lane Telford N
O EM A
b January 17, 1986 z
W RII MEETING NOTICE e
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 01/21/86 Region II Enforcement Conference Licensee, Regional Walker 10:00 am Georgia Power Company -
Administrator, and Hatch Selected RII Staff Members 01/21/86 Region II Enforcement Conference -
Licensee, Regional Stohr 1:00 pm Nuclear Fuel Services Administrator, and selected RII Staff Members 01/23/86 Raleigh, NC CP&L SALP Presentation Licensee, Regional Walker (Shearon Harris, Administrator, and Brunswick & Robinson) selected RII Staff Members 1
P8 E
m T
.