ML20137P288
| ML20137P288 | |
| Person / Time | |
|---|---|
| Issue date: | 01/29/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860124, NUDOCS 8602050004 | |
| Download: ML20137P288 (37) | |
Text
9k January 29, 1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 24, 1986 A sumary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement 0
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 Comission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
/
/
~ 2 8602050004 86o T. A.
eh,
istant for Op h dons '
9
[EEDINFOREPTPDn DR coMMS NRcc Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781 1
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JANUARY 24, 1986 Three Mile Island, Unit 1 (TMI-1)
GPUN decided not to shut down TMI-1 last Friday, January 17, 1986, to correct a defective bellows in their extraction steam system. The most notable effect of their problem is a loss of about 20 MWe. The plant would have to be shut down about a week to replace the bellows in question. General Electric notified the licensee that extended operation in this condition may cause adverse loading problems on the turbine.
After data indicated a positive pressure existed across each turbine rotor, GPUN elected not to shut down this last weekend. The licensee intends to closely monitor turbine perfanance and maintain power operation until a schedule outage in late Mardch 1986. However, if the data indicates a more serious problem is developing, the licensee will shut down. Such operation is not without precedent. Peach Bottom had operated, apparently 'or an extended period, with a similar bellow ruptured with no adveue effect on turbine performance.
Crystal River Unit 3 Reactor Coolant Pump Shaft Separation The Daily Highlight dated January 3, 1986 discussed a reactor trip because of a, flux-flow mismatch resulting from a problem with the RCP.
Preliminary external testing and examination, damage to the pump and motor, and other events at the plant, delayed disassembly of the pump (manufactured by Byron Jackson). This has now been accomplished to the extent that it is known that the shaft failed completely near the top of the pump hydrostatic bearing. Difficulties due to apparent damage still remain in removing the impeller from the pump casing and the motor shaft from the motor. The nature of the failure and its probable cause is not yet known.
Arkansas Nuclear One. Unit No.1 (ANO-1)
On Monday, January 13, 1986, while load testing the "A" Diesel
~
Generator, the diesel generator failed on high crank case pressure. A preliminary inspection found babbitt filings in the oil reservior.
i Also, the licensee has found excessive clearance in the wrist pins on I
the connecting rods to the pistons. The licensee will shut down the plant by the end of the day of January 15, 1986, to make repairs and possibly to inspect "B" Diesel Generator. The licensee will also replace the seal of "C" Reactor Coolant Pump which has shown indications of leaking in the third stage.
If no other problems are l
found, the licensee should be able to restart within seven to eight days.
(
Action of Southeast Compact on Low-level Radioactive Waste l
In a meeting on January 17, the Southeast Low-Level Radioactive Wasth 1
Compact Conunission established March 1,1986 as the date when it will impose a ban on all export of low-level radioactive waste from the region. This ban is authorized under the Low-Level Radioactive Waste j
Policy Amendment Act of 1985 (PL 99-240).
l l
JAN 2 41966 1
l
OFFICE OF ADMINISTRATION Week Ending January 24, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 47 4
Granted 45 1
Denied 9
0 Pending 174 18 ACTIONS THIS WEEK Received Billie P. Garde, Requests all records related to NRC Announcement No.110, Government
" Proper Use and Control of Telephone Services."
Accountability Project (86-35)
Billie P. Garde, Requests all records related to Inspection Report 50-Government 445/85-13 and 50-446/85-09 on the Comanche Peak nuclear Accountability power plant.
Project (86-36)
Billie P. Garde, Requests copies of all records regarding IE Infonnation Government Notice 85-101 " Applicability of 10 CFR 21 to Consulting Accountability Firms Providing Training," specifically all information Project concerning the vendor inspection of "a company that (86-37) supplies consulting services, including training, to the nuclear industry."
Billie P. Garde, Requests all records related to the Quality Assurance Government Branch visit of TERA offices in Bethesda, Maryland, on
(
Accountability October 28 through November 1, 1985.
(86-38)
Cindee Virostek, Requests copies of NUREG-0627, Executive Summary, Main Kiski Valley Report and Appendix B.
Coalition (86-39)
CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A JAN 2.: ; egg l-
2 Received, Cont'd Billie P. Garde, Requests all records related to SECY-85-404, Government
" Unauthorized Disclosures of Sensitive Information -
Accountability Availability of Administrative Sanctions Against NRC Project Employees and Special Government Employees."
(86-40)
Melody Johnson Requests a copy of Form 742, Material Status Reports for (86-41) the period June 1974 through February 1975 from the Kerr-McGee Cimarron facility in Crescent, Oklahoma.
Lauris Fowler, Requests all records related to NRC's investigation Law Offices of initiated in May 1983 regarding allegations that Pullman Brian Spears Power Products employees intimidated and harassed (86-42) quality control inspectors at nuclear facilities.
Laurie Fowler, Requests all records related to NRC's investigations into Law Offices of allegations in January 1985 of illegal and improper Brian Spears procedures and practices at the Vogtle nuclear power (86-43) plant.
Kathryn H. Urban, Requests a list of licensees for Iodine 125 and Medi+ Physics Gadolinium 153 sealed sources.
(86-44)
Myron L. Scott, Requests records related to ACRS meetings and other Coalition for discussions regarding difficulties pertaining to the Responsible Energy Combustion Engineering auxiliary pressurizer spray Education system at Palo Verde and other plants using the same (86-45) system.
Myron L. Scott, Requests all records related to allegations reported to Coalition for NRC in October 1985 concerning pressure by superiors on Responsible Energy employees to speed up or improperly complete work Education activities at the Palo Verde nuclear power plant.
(86-46)
T.J. Vukovich, Requests a copy of draft NUREG-4380.
C.R. Steinhardt, Wisconsin Public Service Corp.
(86-47)
Laurie Fowler, APPEAL TO THE COMfilSSION AND THE E00 for lack of response Law Offices of to a request for all records regarding NRC's internal Brian Spears investigation by OIA or others of Region II investigator, (86-A-4-85-766)
Bruno Uryc.
Granted Steven Aftergood, In response to a request for copies of all papers Committee to delivered at the International Meeting on Reduced Bridge the Gap Enrichment for Research and Test Reactors held (85-745)
October 14-16, 1985, in Petten, The Netherlands, made available 33 records.
ENCLOSURE A Jpft 2
'SC6
i Garth L. Wilson, Ir.esponse to a request for access to certain NRC The Argee Corp.
records concerning the Vitro UMTRA Project, made available (85-843) six records.
Informed the requester that 90 records subject to this request are already available at the PDR.
Teresa S. Barnhart, In response to a request for specified records NTEU Steward regarding Vacancy Announcement No. 86-0336-5, made (85-846) available five records.
(NRC employee)
In response to a request for copies of all records that (86-847) are maintained in her security investigation file, made available 38 records.
Michael O'Mealia, In response to a request for all correspondence concerning Doc-Search EAD Metallurgical, Inc., from August 7, 1985, to the Associates present, informed the requester that the NRC has no (86-2) records subject to this request.
Lynn Connor, In response to a request for a copy of the nonproprietary Doc-Search version of the April 19, 1985, submittal by Westinghouse Associates on the 1000 MWe NSSS design, informed the requester (86-10) that there is no nonproprietary version of this record.
Michael O'Mealia, In response to a request for copies of the transcripts or Doc-Search summaries of the NRC/Framatome meeting in October 1985 Associates and any other meetings, made available two records.
(86-16)
Ophelia G. Williams, In response to a request for any correspondence from J/R/A Associates W. Dircks responding to INP0's October 16, 1985, letter (86-23) regarding INP0's involvement in utility training and maintenance programs, made available two records.
William J. Manning In response to a request for a copy 0f the July ll, (86-29) 1980, memorandum to Richard Vollmer from Robert Jackson entitled, "Diablo Canyon Hearing Reopening and San Onofre Review Status," made available a copy of the requested record.
(An individual In response to a request for records in the NRC on requesting himself or listed organizations, informed the requester information) that the NRC has no records subject to this request.
(86-34)
Cindee Virostek, In response to a request for a copy of NUREG-0627, Kiski Valley Executive Summary, Main Report and Appendix B, informed Coalition the requester that these records are already available (86-39) at the PDR.
Denied Billie P. Garde,.
In response to a request for all records developed by the Government License Fee Management Staff of the Office of Administration Accountability concerning the cost of the operating license review for Project the Comanche Peak nuclear power plant from June P4, 1984, (85-794) made available 15 records. Denied portions of two records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
ENCLOSURE A M2 E
. =. -
4 l
i Denied, Cont'd Lynn Connor, In response to a request for a copy of WCAP-10858, Doc-Search denied this record in its entirety containing Associates confidential business (proprietary) information.
(86-8) r t
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ENCLOSURE A i
i JAN 2 '.1986 a
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WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JANUARY 24, 1986 IFB ISSUED IFB No.: RS-ADM-86-256
Title:
" Archival Storage"
==
Description:==
The contractor shall provide an environmentally controlled and protected storage area for archival material.
Period of Performance: Two years with an option to extend one additional year.
Sponsor: TIDC/ Office of Administration Status: Closing date has been extended to January 24, 1986.
PROPOSALS UNDER EVALUATION RFP No.: OIE-86-170
Title:
" Assistance for Emergency Response"
==
Description:==
Provide technical, logistical and administrative assistance for the maintenance and functioning of the NRC Headquarters Operations Center.
Period of Perfermance:
12 months Sponsor: Office of Inspection & Enforcement Status: Best and Final of fers received on January 14, 1986 and forwarded to Source Evaluators for review on January 14, 1986.
RFP No.: RS-0IE-85-158
Title:
" Technical Assistance in Developing and Implementing Frograms and Procedures for Inspection of Operating Reactors During Major Outages"
==
Description:==
The objective of this project is to provide technical as_sistance to the NRC for activities pertaining to planned outages of operating reactors. This includes the development of standardized inspection procedures as well as providing assistance to the regional offices for conducting inspections.
Period of Performance: Three years Sponsor: Office of Inspection & Enforcement Status: Final Evaluation Report received on January 16, 1986.
CONTRACT AWARDED RFP No.:
RS-ADM-86-253
Title:
" Reorganization of Materials Stored at a Commercial Environmental Facility"
==
Description:==
Contractor shall provide services to inventory, index, interfile and reorganize NRC archival data and records stored in a commercial environmental facility.
Period of Performance: Six months (January 15, 1986 - July 14, 1986)
Sponsor: TIDC/ Office of Administration Status: Cost-Plus-Fixed-Fee contract (NRC-10-86-253) awarded to SBA/TIPCO, Inc.,
in the amount of $82,902 effective January 15, 1986. This firm has been certified by the Small Business Administration as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.
l ENCLOSURE A JAN 2
'" $ 1
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending January 24, 1986 Arkansas Nuclear One, Unit No.1 (AN0-1)
On Monday, January 13, 1986, while load testing the "A" Diesel Generator, the diesel generator failed on high crank case pressure. A preliminary inspection found babbitt filings in the oil reservior.
Also, the licensee has found excessive clearance in the wrist pins on the connecting rods to the pistons. The licensee will shut down the plant by the end of the day of January 15, 1986, to make repairs and possibly to inspect "B" Diesel Generator.
The licensee will also replace the seal of "C" Reactor Coolant Pump which has shown indications of leaking in the third stage.
If no other problems are found, the licensee should be able to restart within seven to eight days.
River Bend Station At 3:30 a.m. on 1/15/86 CST, River Bend Station, Unit 1 scrammed on a reactor high water level trip. At the time, River Bend Station was operating at 17% of rated power, in the process of switching from the startup feedwater system to the noram feedwater system.
This high water level scram incident was caused by a feedwater control valve that was stuck in an open position. At the time, the licensee was attempting to use a feedwater line which had not previously been used in service.
As part of the switch over to the main feedwater system, the operator set the demand for feedwater to zero, which presumably would have closed the control valve.
(There is no indication of feedwater valve position in the control room). The operator then opened a block valve in preparation to admit water through the presumably closed feedwater valve. Since the feedwater valve was stuck open, the full flow of main feedwater entered the reactor vessel. Apparently the reactor water level rose rapidly, precluding manual control of water level by the operators. Region IV is following up on this event.
NRR has informed the licensee that an NRC team will arrive on site beginning January 29 for a closer look at this and other recent events at River Bend. The team will be headed by the NRC Project Manager (Steve Stern) and will consist of NRR, IE, and Region IV staff.
ENCLOSURE B JAN 2 6 E86
_2 Arkansas Nuclear One, Unit No.1 (ANO-1)
The scenario involves a postulated break 17 the steam line from the "A" 0TSG to the turbine driven EFW pump supply header concurrent with the loss of power from the red bus which supplies power to, among other equipment, the motor driven EFW pump and the isolation valve in the "A" 0TSG supply line to the turbine driven EFW pump. Since the turbine driven EFW pump supply header is connected to both OTSGs would blow down through the break rendering the turbine driven EFW pump inoperable and thus rendering the whole EFW system inoperable.
Waterford 3 On January 15, 1986, Louisiana Power & Light Company announced that R. S. (Mike) Leddick, Senior Vice President for Nuclear Operations, will be resigning in the near future and returning to his home in Minneapolis. Leddick, who provided senior-level nuclear management experience during the final construction and licensing of Waterford 3, will be assuming a managemert position with the city of Minneapolis to oversee construction of a large convention center. LP&L hopes to select a successor to Leddick prior to his leaving.
Oyster Creek Nuclear Generating Station On November 30, 1985, the staff issued its Safety Evaluation on the emergency technical specification change to delete the daily channel check for the low-low and low reactor water level instrumentation.
This change was effective to the restart from the Cycle 11 Refueling outage which begins in April 1986.
Before the commencement of the outage, the licensee was requested to provide a justification of the existing instrumentation channels addressing the staff's concerns about the checks for operability of these channels commensurate to its safety function or to install in the outage appropriate means for a channel check.
A meeting will be held with the licensee on January 23, 1986, Thursday, in P-1123E of the Phillips Building to discuss the licensee's response to the staff's Safety Evaluation. Reviewers from EICSB and RSB of DBL will be attending in addition to the contributors to the staff's Safety Evaluation.
ENCLOSURE B JAN 2 41986
Three Mile Island, Unit 1 (TMI-1)
GPUN decided not to shut down TMI-1 last Friday, January 17, 1986, to correct a defective bellows in their extraction steam system. The most notable effect of their problem is a loss of about 20 MWe. The plant would have to be shut down about a week-to replace the bellows in question. General Electric notified the licensee that extended operation in this condition may cause adverse loading problems on the turbine.
After data indicated a positive pressure existed across each turbine rotor, GPUN elected not to shut down this last weekend. The licensee intends to closely monitor turbine performance and maintain power operation until a schedule outage in late Mardch 1986. However, if the data indicates a more serious problem is developing, the licensee will shut down. Such operation is not without precedent.
Peach Bottom had operated, apparently for an extended period, with a similar bellow ruptured with no adverse effect on turbine performance.
Nine Mile Point 2 In a telephone call on Tuesday, January 21, 1986, Mr. Anthony Zallnick, Niagara Mohawk Power Corporation (MNPC), Licensing Manager for Nine. Mile Point 2, stated that MNPC is revising their estimated construction completion date (and readiness for fuel load date) from the presently scheduled date of February 24, 1986. The revised schedule will state that Nine Mile Point 2 will be ready for fuel load "within 10 weeks" of the February 24, 1986, date.
The NRC Project Manager requested, and it is expected, that MNPC will be submitting this revised schedule date formally, although no schedule for formal submittal was available. Mr. Zallnick also indicated that he believed a press release on the new date is being prepared.
Limerick On January 16, 1986, the Appeal Board affirmed a Licensing Board decision, which denied a request by intervenors Robert L. Anthony and Friends of the Earth to reopen the hearing record in the Limerick operating license proceeding. The intervenors had filed on April 30, 1985, a petition concerning:
(1) the use of plant site boundaries in determining public exposure to routine releases; (2) the estimation of public exposure considering the fish ingesticn pathway; and (3) degradation of protection of the public due to revisions in the Offsite Dose Calculation Manual.
Limerick, Unit 1 is currently operating at 96.4% of rated power and is in the latter stages of its start-up test program.
ENCLOSURE B d.; 2 41936
_4-Crystal River Unit 3 Reactor Coolant Pump Shaft Separation The Daily Highlight dated January 3, 1986 discussed a reactor trip because of a flux-flow mismatch resulting from a problem with the RCP.
Preliminary external testing and examination, damage to the pump and motor, and other events at the plant, delayed disassembly of the pump (manufactured by Byron Jackson). This has now been accomplished to the extent that it is known that the shaft failed completely near the top of the pump hydrostatic bearing. Difficulties due to apparent damage still remain in removing the impeller from the pump casing and the motor shaft from the motor. The nature of the failure and its probable cause is not yet known.
O ENCLOSURE B JAtt 2 41986
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING JANUARY 24, 1986 1.
DEFUELING Defueling during the week consisted of pick-and-place loading of fuel canisters. By January 23, 1986, all five fuel canisters in the Canister Positioning System were filled. Since last week, the number of single end-fittings that can be easily loaded into fuel canisters has been depleted. There was some success in separating fused end-fittings with a slide-hammer tool. On January 25, 1986, four of the five filled canisters were transferred from the Reactor Building to the storage racks in the Spent Fuel Pool (SFP). One of those four canisters had not been dewatered prior to the transfer and the total net weight of fuel debris transferred is not yet available. On January 26, 1986, two empty fuel canisters and an end fitting temporary storage container (EFTSC) were loaded into the Canister Positioning System in the reactor vessel. The function of the EFTSC is to provide storage for the fused end-fittings which cannot be easily loaded into the fuel canisters. Loading of the EFTSC is procedurally limited to end-fittings or other structural material with minimal amounts of attached fuel pins. The staff has reviewed the safety evaluation, as well as the procedure for loading the EFTSC to ensure the safety of temporary storage of the loaded EFTSC in the storage racks in the SFP.
On January 23, 1986, a filter canister from the Defueling Water Cleanup System (DWCS) was transferred from the Fuel Transfer Canal to the canister storage racks in the "A" Spent Fuel Pool. This canister has experienced plugging problems after only a short operating time in the DWCS. The licensee will attempt to clean this filter with boric acid solution. A boroscopic examination of another fouled filter canister revealed extensive plugging by an algae growth. This is being studied by the licensee with assistance by Oak Ridge National Laboratory.
On January 20, 1986, a fuel assembly at the core periphery (assembly P-4) was toppled with a hook tool. The broken-off portion of the assembly weighs about 800 pounds underwater and is about 8 feet in length. A video inspection of this assembly was performed on January 21, 1986 and by January 23, 1986, the broken-off portion of the assembly had been sectioned with a shear tool and loaded into a fuel canister. The void remaining after removal of this assembly will be examined to collect information on the core conditions below the loose rubble.
JAN 2 41986 ENCLOSURE B
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 (15}
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.
The average reactor building temperature is 56 F.
The reactor building airborne activity at the Westinghouse platform is 6.2 E-8 uCi/cc Tritium and 6.7 E-11 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a 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 completed processing of Batch 275, which consisted of about 46,000 gallons of water recycled through the system.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,822,963 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.
A temporary ventilation system has been installed in the annulus area between the reactor building and fuel handling building. This was done in preparatien for water spray decontamination of the 281' level of the annulus and will prevent spread of contamination during the evolution.
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.
JAN 2 41986 ENCLOSURE B
. 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 sanples taken from January 4 through January 11, 1986. A gama 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 January 5 through January 11, 1986. A ganina scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI site collected a sample between January 15, and January 22, 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.
7.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.
One auxiliary building sump pump has been removed as part of the preparations for sump desludging.
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.
Reactor Building Sump Criticality Safety 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.
ENCLOSURE B 2=g
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending January 24, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
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 conduct a joint Salt Waste Package Workshop on January 22-24, 1986 in Columbus, Ohio, to discuss 00E salt waste package design and its relationship to 10 CFR Part 60 requirements, and other waste package technical issues.
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.
ENCLOSURE C JAN 2j Leeg
-2_
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.
Near-Term DOE Actions of Interest Late January 1986 - DOE to issue Final Transportation Business Plan Late January 1986 - DOE to issue draft Request for Proposals (RFP) for the reactor fuel transportation cask February 1986
- DOE submits MRS proposal to Congress Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit No. 3 On January 22, 1986, Arizona Public Service Company, on its own behalf and as agent for 5 other utilities, was issued Special Nuclear Material License number SNM-1956 for Palo Verde Nuclear Generating Station, Unit No. 3.
This license authorizes the receipt, possession, inspection and storage of uranium enriched in the U-235 isotope contained in fuel assemblies, fission counters, and in excore and incore detectors, as well as the receipt, possession, and use of Pu-Be sources for eventual use at the Palo Verde Nuclear Generating Station, Unit No. 3.
i JAN 2 4 ESS ENCLOSURE C
Office of Inspection and Enforcement Items of Interest Week Ending January 24, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
None.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PN0-I-86-02, Vermont Yankee Nuclear Power Corporation (Vermont Yankee Nuclear Power Station), Probable Tampering With Fire Deluge System.
b.
PNO-I-86-03, Pennsylvania Power and Light Company (Susquehanna Steam Electric Station Unit 2), Reactor Shutdown.
c.
PNO-I-86-04, GPU Nuclear Corporation (0yster Creek Nuclear Generating Station), Contamination of Workers With Short-Lived Rubidium-88 and Cesium-138.
d.
PNO-I-86-05, Niagara Mohawk Power Corporation (Nine Mine Point Unit 1), Reactor Shutdown Due to Potential Degradation of Primary Con-tainment Integrity.
e.
PNO-II-86-07, Tennessee Valley Authority (Sequoyah Units 1 & 2),
Local Media Interest in Contamination on Outside of Building.
f.
PN0-II-86-08, Duke Power Company (McGuire Unit 2), Unscheduled Shutdown Longer Than 48 Hours.
g.
PN0-III-86-02, Northern States Power Company (Monticello Nuclear Plant),BombThreat.
h.
PN0-III-86-04, Detroit Edison Company (Fermi 2 Nuclear Power Plant),
Possible Problem With RHR Pump Motors.
1.
PN0-III-86-05, Commonwealth Edison Company (LaSalle Unit 1), Cracks in Recirculation System Piping.
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
None.
ENCLOSURE D
, TAN 2 L 1536
. 4.
Other Items a.
Civil Penalties Paid (1) EA 85-129 issued December 12, 1985 to Quality Assurance Labs, Inc. (South Portland, ME), $5,000.
(2) EA 85-68 issued December 13, 1985 to Virginia Electric and Power Company (North Anna), $20,000.
(3) EA 85-128 issued December 18, 1985 to Southern California Edison (San Onofre), $50,000.
b.
Inspections Representatives of the Vendor Programs Branch, Division of Quality Assurance, Vendor, and Technical Center Training Programs, con-ducted site inspection efforts this week at Bechtel Company (San Francisco, CA), Rockbestos Company (New Haven, CT), and Commonwealth Edison's Dresden Plant.
c.
Accompanying Regional Inspections A representative of Division of Emergency Preparedness and Engineering Response participated in a welding re-examination assessment at TVA's Sequoyah plant January 21-24, 1986.
d.
Part 21 Notification General Electric Company submitted a Part 21 notification on January 17 based on the July 13, 1985 failure of Grand Gulf l's high pressure core spray diesel generator. This generator is manufactured by Northern Electric Industries Parson Peebles-Electric Products Inc.
e.
Kerr-McGee Followup A representative of the Incident Response Branch, Division of Emer-gency Preparedness and Engineering Response met with EPA and OSHA on January 22 to discuss followup on the Kerr-McGee accident relating to nonradiological hazards.
f.
NRC/ FEMA Steering Committee The Director, Division of Emergency Preparedness and Engineering Response and staff from this Division attended the NRC/ FEMA Steering Committee meeting on January 21.
g.
Davis-Besse Visit Representatives of the Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response, and AE0D met with Davis-Besse staff on January 24 to discuss valve testing program data.
ENCLOSURE D g 21 E6
. h.
ANSI Meeting A representative of the Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response, attended the ANSI meeting on respiratory protection January 20-24.
1.
Operations Center Visit Sandia Labs representatives visited the Operations Center on January 21.
j.
Relocation Tabletop Exercise A representative of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response attended the Reloca-tion Tabletop Exercise meeting on January 22.
1 i
l l
[
l JAN 2 41986 ENCLOSURE D l
[
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending January 24, 1986 Semiscale Test S-NH-3 was successfully completed on January 15, 1986. This is a simulated 0.5% cold leg break in which high pressure coolant injection is inoperative. During the test, system liquid inventory decreased until peak cladding temperature reached 1000*F. At that time the intact loop coolant pump was restarted with the result that the cladding temperature rapidly decreased to near saturation. At 600 psig accumulator flow was initiated but this coolant did not appear to reach the core. Core temperature rose throughout accumulator injection which was completed at about 220 psi.
Thereafter the cladding temperature rose rapidly to 1250*F at which time secondary feed and steam was initiated. Shortly thereafter the low pressure injection set point was reached and the test was terminated. The results are tentative since the data have not been qualified. The data will be used to validate code capabilities for this accident scenario which represents an instrument line break.
RELAP5/M002 Code The RELAP5/M002 Code is used to analyze thermal hydraulic phenomena in a reactor system when a system transient occurs in a plant.
The Idaho National Engineering Laboratory (INEL) has published a draft report entitled "RELAP5/ MOD 2 Code Assessment at the Idaho National Engineering Laboratory" The report presents an overview of the assessment work at (N'JREG/CR-4754).
INEL.
It will be published after the review is completed and available to NRR, NRC contractors, and International partners under the International Code Assessment Program and all other U.S. users.
ENCLOSURE E JAN 2 41336 i
k
. STAR Experiment in ACRR.
The STAR-7 experiment has been successfully performed in the ACRR test reactor completing NRC participation in the joint program of fast-reactor safety experiments in ACCR. The Sandia Transient Axial Relocation (STAR) experiments with corollary analysis and model development have been a joint LMFBR safety research program among NRC, Kernforschungszentrum Karlsruhe (KfK) of the Federal Republic of Germany, and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. Of the FY1985 funds for orderly completion of this program, the majority were furnished by the foreign program partners.
The STAR experiments are unique in-pile separate-effects experiments on the upward relocation of clad and fuel material and on blockage formulation during the initiation phase of an LMFBR Loss-of-Flow (LOF) accident. This fuel relocation, along with molten fuel removal from the core during the later transition-phase of the accident, limits the energetics of possible fuel recriticalities during the accident and the resultant threat to the integrity of the reactor primary system and the containment. This was a major issue in the CRBR licensing review and is one of the most important generic LMFBR safety uncertainties.
In the STAR experiments, irradiated LMFBR fuel pins with simulated upper-blanket structure are melted by exposure to Loss-of-Flow (LOF) Power histories in ACRR in the presence of high velocity argon gas that simulates sodium vapor. High-speed cinematography records the detailed motion of the fuel and clad materials, and also measures surface temperatures by pyrometry. The STAR-7 experiment used 4 irradiated fuel pins and simulated upper-blanket structure. A specific LOF-accident power history was used in the STAR-7 experiment that tested the hypothesis that rapid vaporization of
~
molten stainless steel clad entrained in molten fuel can produce rapid upward expulsion of the molten fuel from the core, so that the potential for recriticality is substantially reduced. A nearly explosive ejection of the -
molten fuel was observed in STAR-7 as predicted. This experiment has produced the only data to confirm the hypothesis of molten-fuel ejection by vaporization of entrained molten cladding, a result that is of significant importance in fast-reactor safety assessment and to our German and Japanese program partners.
i I
ENCLOSURE E si::,.Au
(
. RES-Rulemaking Activities Emergency Preparedness for Fuel Cycle and Other Radioactive Materials -
Licensees (Parts 30, 40, 70)
In 1981 the NRC issued orders to certain fuel cycle and other radioactive material licensees requiring them to submit comprehensive onsite radiological emergency plans. Subsequently, rulemaking was initiated to place a requirement for emergency plans in the regulations.
The current draft SECY paper is being revised slightly to characterize the intent of the rule regarding onsite and offsite responses to chemical and radiological threats from accidents involving licensed materials and to include a comparison of predicted consequences of a UF release with the consequences g
from the Kerr McGee accident. The Director, DTvision of Inspection Programs, IE, has scheduled a meeting for January 22, 1986, with the Occupational Safety and Health Administration (OSHA), the Environmental Protection Agency (EPA) and NRC staff to discuss agency jurisdiction. The Commission paper will be revised, if necessary, to be consistent with agreements reached.
Risk Effectiveness of LWR Regulatory Requirements In 1985 Policy and Planning Guidance on improving regulation of the nuclear industry the Commission directed the staff to review existing regulatory requirements to see if some could be eliminated without compromising safety.
In response to this guidance, RES is continuing a 1985 program to select existing rules for reexamination based on a comprehensive evaluation of their risk significance.
Rules that have marginal importance to safety or that have becore obsolete by implementation of other approved staff practices will be reconmended for elimination or modification.
In 1985 the contractor performed a survey to identify those regulatory areas that were thought to be least effective on the basis of risk / safety considera-tions.
Also, the contractor studied the risk effectiveness of two regulations,'
one of these being the containment leakage rate requirements and testing and the other being new fuel design review requirements. The staff is preparing recommendations to the E00 regarding these existing requirements.
In 1986 the contractor will prepare detailed work plans and begin work on four new tasks:
(1) combustible gas control; (2) post accident sanpling system; (3) impregnated charcoal filters; and (4) turbine missiles. The detailed work plans for each task are currently scheduled for NRC review by mid February 1986.
ENCLOSURE E yn 2 41966
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JANUARY 24, 1986 International Meetings The following international meeting notices supplement those previously announced:
January 27-31, 1986, Vienna, Austria - IAEA Working Group Meeting on
" Coastal Modeling" for Joint Group of Experts on the Scientific Aspects of Marine Pollution February 10-14, 1986, Vienna, Austria - IAEA Consultants' Meeting to Update the IAEA Incident Reporting System (IRS) Guidelines and Examine the Necessity of Developing New Guidelines
~ ~
Feb rua ry' 17-20, 1986, Barnwood, UK - IAEA Consultants' Meeting on Spent Fuel Management March 3-7, 1986, Vienna, Austria - IAEA Advisory Group Meeting to Prepare a Document on the Application of the Principles for Limiting i
Releases of Radioactive Effluents in the Case of Mining and Milling Radioactive Ores March 11-13, 1986, Vienna, Austria - IAEA Advisory Group Meeting on Spent Fuel Managenent March 17-21, 1986, Toronto, Canada - IAEA Consultants' Meeting to Prepare a Technical Report on Handling and Treatment of Radioactive Waste from Unplanned Events at Nuclear Power Plants March 25-27, 1986, Vienna, Austria - IAEA Standing Advisory Group on the Safe Transport of Radioactive Materials (SAGSTRAM)
April 21-25, 1986, Vienna, Austria - IAEA Technical Committee Meeting on the Factors Relevant to the Pecycling and Reuse of Components Arising from the Decommissioning of Nuclear Installations May 26-June 13, 1986, Canada - Interregional Training Course on Management and Disposal of Radioactive Wastes June 23-27, 1986, Vienna, Austria - IAEA Consultants' Meeting to Review the Need for the Development of International Recommendations Regarding the Notification of National Autnorities in Recipient Countries When Certain Categories of Radioactive Material are Exported October 5-10, 1986, Budapest, Hungary - World Conference on Hazardous Waste ENCLOSURE G
2 International Organization Vacancy Notices The following vacancy notices from the International Atomic Energy Agency located in Vienna, Austria have been posted on NPC bulletin boards:
P-3 Experts Recruitment Officer, Experts Section, Department of Technical Cooperation P-1 Soil Scientist, Soil Science Unit, Seibersdorf Laboratory, Department of Research and Isotopes P-3 Personnel Management Analyst, Division of Personnel, Department of Administration P-5 Legal Officer, Legal Division, Department of Administration Foreign Trip Report P. N. Randall, MEBR/RES November 1-9, 1985; Visited South Korea:
This trip was arranged through the Office of International Programs at the request of the Korean Advanced Energy Research Institute's Nuclear Safety Center (NSC). The purpose was to discuss how the NSC should regulate fracture control of nuclear reactor vessels that are sensitive to radiation damage. The report is Official Use Only.
J,,,-,,,,,3 ENCLOSURE G
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JANUARY 24, 1986 Action of Southeast Compact on Low-Level Radioactive Waste In a meeting on January 17, the Southeast Low-level Radioactive Waste Compact Commission established March 1, 1986 as the date when it will impose a ban on all export of low-level radioactive waste from the region. This ban is authorized under the Low-Level Radioactive Waste Policy Amendment Act of 1985 (PL 99-240).
State Program Reviews
.The radiation control program of Louisiana will be reviewed during the week of February 3-7, 1986.
ENCLOSURE H 4
.'AN 2 41986 L
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING JANUARY 24, 1986 1.
San Onofre Nuclear Generating Station, Unit 1 The IIT investigation into the causes of the November 21, 1985 loss of power and water hammer event has been completed, and the Team's report (NUREG-1190) has been issued. The IIT briefed the Commission on January 22, 1986 concerning the findings and conclusions resulting from its activities. The most significant aspect of the event involved the failure of five safety-related check valves in the feedwater system.
Their failures occurred in less than a year, without detection, and contributed to an incidence of a severe water hammer that challenged the integrity of safety systems. The Team identified a number of equipment, personnel and procedural deficiencies that contributed to the event.
The Team is scheduled to brief the ACRS Subcommittee on Westinghouse Water Reactors on February 12, 1986.
2.
AE0D Engineering Evaluation Report E601 entitled " Deficient Operator Actions Following Dual Function Valve Failures," was issued. The study evaluated events involving dual function valve failures at Dresden 3, Brunswick 1 and 2 and Peach Bottom 3.
The study found that light water reactors are generally equipped with a number of valves which perform both on emergency core cooling (or safety-related) function and a containment isolation function. However, operating experience shows that the proper and conservative operator action for a failure of one of these valves has not always been taken by the operating staff in a manner which is fully consistent with plant technical specifications.
In each of the events reviewed, the operator's actions preserved one function of the valve but
~
disabled the valve's alternate function.
Furthermore, the operator's actions were taken without declaring the adversely affected function of the valve to be inoperable as required by the plant technical specifications. At Dresden 3, operability of an ECCS loop was preserved, but containment isolation capability was disabled. At Brunswick and Peach Bottom 3 containment integrity was maintained, but a safeguards train was disabled.
The study also found that the affected valves were not included in the plant technical specification table of containment isolation valves.
The report contains some suggestions for action by IE and NRR.
ENCLOSURE J JA.'i 2 41986
REGION III STATUS REPORT i
~
DAVIS-BESSE LOSS OF FEEDWATER EVENT January 24, 1986 Plant Status The plant remains in cold shutdown. On January 8,1986, the safety features ++
actuation system was actuated due to an operator error during maintenance activities. The licensee is completing troubleshooting to determine the cause of anomalies in valve functions noted following the actuation. On January 21, 1986, the licensee made a Part 21 report on inadequate control of wire wrap terminations made in the steam and feedwater line rupture control system.
Restart Activities 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.
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 thirty nine valves and returned them to service. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The NRC test review team continues to provide weekly coverage of licensee
++
testing activities. System flushing and recirculation testing of the motor driven startup feedwater pump is scheduled to start today along with Emergency Diesel Generator (EDG-1) and Containment Air Cooler troubleshooting testing.
EDG-2 modifications and testing have been completed. Testing of the component cooling water pump room ventilation system showed that the Hydromotor actuators did not properly function.
Other Activities 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, fourteen remain to be dispositioned.
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.
The licensee is continuing work on modifications required to make the control room emergency ventilation system operable.
ENCLOSURE L JAN 2 /. $??6
The licensee's inspection and review of items requiring environmental
++
qualification continues to identify components that require repair, replacement, or further engineering evaluation. The licensee determined that the post-accident containment radiation monitoring instruments were not environmentally qualified. These instruments are required by the Technical Specifications.
Meetings On February 5, 1986, the Babcock and Wilcox owners group will meet with the NRC in Washington to discuss their activities in response to the December event at Rancho Seco and the June event at Davis-Besse.
On February 6,1986, the ACRS will meet with the NRC staff and Toledo Edison in Washington to discuss the safety evaluation report on and the status of activities being conducted in response to the June event.
JAN 2 41966 ENCLOSURE L 2
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JANUARY 24, 1986 A.
STAFF REQUIREMENTS - EE0 PROGRAM PLAN - PROGRESS REPORT, 2:00 P.M.,
THURSDAY, DECEMBER 12, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C.
0FFICE (OPEN TO PUBLIC ATTENDANCE) AND COMJA-85 Memo SECY to V. Stello dated 1/21/86 The Commission was briefed by staff and by representatives of EEO advisory committees on the NRC Equal Employment Opportunity (EEO) program.
The Commission, at the meeting and in response to COMJA-85-17, directs the staff to develop and/or implement the following:
(1)
The staff should present to the Commission a conceptual plan and an operational program to increase the hiring and promotion of women and minorities in the upper grades (13-18) and in the SES.
(ADM/SDBU/CR)
(SECY SUSPENSE: 4/15/86) l (2)
The staff should include in the five year plan (possibly under the section " Manage and Support the Other Mission Areas") :
(a)
A plan for dealing with the NRC's human resources which will include a projection of what the workforce will look like over the next five years.
The plan should also i
include a provision for resolving anticipated overages by way of retraining or lateral transfers.
The retraining plan should be fleshed out with an operational plan.
l (b)
The results of an evaluation by staff of the findings of the Age Discrimination Committee's proposed study of the recent reduction in force exercise (RIF). The Commission is in favor of the Age Discrimination Committee conducting this study.
Upon its completion the staff is to develop " lessons learned" to be used in future RIF's.
The staff should address the issue of how to avoid RIF's that are, or that appear to be, discriminatory against a particular EEO protected group - i.e. women, minorities, or more senior employees.
t (ADM) (SECY SUSPENSE: 1/31/86 or an appro-priate time to be included in the five year plan, an initial draft which is due l
1/31) l ENCLOSURE 0 JAW 2 41555
2 i
A.
CONTINUED 3.
The staff is directed to ensure that appraisal forms for all supervisory personnel, deputy to branch chief and above, include an EEO performance element.
Additionally, the staff is to develop a set of criteria for judging EEO performance of managers that will provide a more sensitive evaluation process than a mere calculation of hires and promotions.
The OSDBU/CR office should be intimately involved in the development of these criteria.
(ADM/OSDBU/CR)
(SECY SUSPENSE: 6/86) 4.
The staff is to look into the issue of the appearance of racial bias in the preparation of performance appraisals.
The staff should be prepared to discuss their findings at the next EEO briefing.
(EDO)
(SECY SUSPENSE: 6/86) 1 5,.
The staff is to provide a report on how the Executive Leadership Program offered by OPM functions and what assistance the agency provided to the NRC candidate to make her participation more useful to both her and to the agency.
The staff is further to provide a report en the agency's plans for an in-house program which are mentioned at page 37 of the FY-1986 Consolidated EEO Program Plan.
(ADM/OSDBU/CR)
(SECY SUSPENSE: 2/14/86) 6.
The staff should provide a written status report on the items covered in Commission SRMs that address EEO one month before each semi-annual l
meeting.
(EDO)
(SECY SUSPENSE: 5/3/86)
Chairman Palladino and Commissioner Asselstine request that the staff develop a question on agency EEO performance for inclusion in future exit interview forms.
(ADM/SDBU/CR)
(SECY SUSPENSE: 1/31/86)
,s Chairman Palladino requests that the staff provide to the Commission the number of co-op students represented by percentages of women and minorities for FY-1984 and FY-1985.
l (ADM)
(SECY SUSPENSE: 1/31/86)
Commissioner Roberts requests that the staff provide data tb the Commission on a comparison of the number of NRC EEO complaints to the number of EEO complaints in other federal agencies.
Percentage data may be used for this comparison.
j (SDBU/CR)
(SECY SUSP.5NSE: 2/4/86) l ENCLOSURE 0 JAN 2 4 506
3 A.
CONTINUED Commissioner Zech requests that a study be done by the staff to identify those individuals who under reduction in force -
(RIF) exercises are also eligible for retirement.
(ADM)
(SECY SUSPENSE: 1/31/86)
SECY will track the periodic meetings of the Commission with the staff and the EEO advisory committees and ensure that each advisory committee is invited to attend these meetings.
In this regard the next Commission meeting on the EEO program should take place in early June 1986.
B.
STAFF REQUIREMENTS - BRIEFING BY GPU ON TMI-2 CLEANUP AND TMI-1 OPERATIONAL EXPERIENCE, 10:00 A.M., TUESDAY, JANUARY 14, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) tiemo SECY to RECORD dated 1/23/86 The Commission met with representatives of the General Public Utilities Corporation (GPU) and GPU Nuclear Corporation (GPUN) to receive a briefing on the status of the cleanup of TMI-2 and the restart of operations at TMI-1.
The following representatives of GPU and GPUN were in attendance at the meeting:
William G. Kuhns Chairman and Chief Executive Officer GPU John F. O' Leary Chairman of the Board GPUN Philip R. Clark President and Chief Executive Officer GPUN Frank R. Standerfer Vice President and Director of the TMI-2 Project GPUN E. E. Kintner Executive Vice President GPUN The Commission decided to discuss at an agenda planning session the possibility of a briefing by Department of Energy exper'ts on DOE findings related to fission product releases during the TMI-2 accident including any implication to the Source Term work l
conducted by RES.
l l
ENCLOSURE 0 JAN 2 41925 l
4 B.
(CONTINUED)
The Commission asked the GPU representatives to discuss at the next briefing of the commission the steps GPU is taking in informing the public on corporate activity related to TMI operations and cleanup.
GPU indicated to the Commission that by June 1986 it would be able to provide to the Commission a plan for the disposal of the water in the TMI-2 reactor vessel.
C.
STAFF REQUIREMENTS - BRIEFING ON EVENT AT KERR-MCGEE SEQUOYAH FACILITY, 1:00 P.M.,
FRIDAY, JANUARY 10, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C.
0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello dated 1/23/86 The Commission met to be briefed by staff on the status of the January 4 accident involving the rupture of an uranium hexafluoride cylinder at Kerr-McGee's Sequoyah Fuel Facility in i Gore,' Oklahoma.
The Commission requested that the staff provide a plan for addressing the Sequoyah event to include the following:
1.
when the report of the site investigation team will be available and what the scope of the report will be, 2.
staff priorities and schedule for resolving issues at the site, including how and when will restart of the facility be decided, 3.
when staff believes they will be prepared to provide a follow-on briefing for the Commission including lessons
- learned, 4.
the staff recommendation on asking Kerr-McGee officials to brief the Commission, and 5.
information from the staff on whether there are any other Federal or state agencies responsible for regulating the chemical hazard at the Sequoyah facility and if so, what the responsibilities are.
The above information requested by the Commission is to be provided with the plan for addressing the Sequoyah event.
(NMSS)-
(SECY Suspense:
2/7/86)
ENCLOSURE 0 2 4 1986
9 5
1 C.
CONTINUED Commissioner Asselstine requested information on whether the Resource Conservation and Recovery Act provisions apply to the Sequoyah facility.
Commissioner Asselstine also requested that staff. inform him as to whether the public and state and local officials were informed of the pending application for renewal of the Sequoyah facility's operating license prior to its September 1985 renewal.
(NMSS)
(SECY Suspense:
2/7/86)
(Commissioner Asselstine indicated that he would provide in writing to the staff additional questions regarding emergency planning.)
Commissioner Bernthal requested information on the normal free volume for the type of cylinder that ruptured during the event at the Sequoyah facility.
Commissioner Bernthal further requested information on whether the prohibition on heating the overfilled cylinder to remove excess uranium hexafluoride was in response to DOE's 1978 circular.
(NMSS)
(SECY Suspense:
2/7/86)
ENCLOSURE 0 JAN 2 41986
S z
N NRR MEETING NOTICES *
[
JANUARY 24, 1986 si DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 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.
1/28/86 50-029 AR-5033 Discuss staff comments on the Yankee Atomic J. Clifford 10:00 a.m.
Air Rights Bldg.
licensee's Detailed Control Room Electric Company Design Review.
1/28-31/86 50-155 Big Rock Point Perform a Detailed Control Room Consumers Power T. Rotella 8:00 a.m.
Plant Design Review and Safety Parameter Company l
Charlevoix C.,
Display System licensing review.
Michigan 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.
1/29/86 Room 201 Discuss B&WOG response to NRC B&W Owners Group L. Lois 10:30 a.m.
Landow Bldg.
questions.
1/29/86 50-289 P-110 Discuss the proposed steam GPUN-TMI-1 J. Thoma 9:30 a.m.
Phillips Bldg.
generator plugging criteria for TMI-1.
m
??5 i
g A
Copi7s of 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 u=
.a
$I NRR MEETING NOTICES
- s JANUARY 24, 1986 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 1/30/86 50-295 P-114 Meeting with Commonwealth Edison Commonwealth Edison J. Norris 9:00 a.m.
50-304 Phillips Bldg.
Company (CECO) regarding reload Company methodology for Zion 1 and 2.
1/30/86 P-110 Discuss SAFER Model Qualification GPUN, NMPC, &
T. M. Su 8:30 a.m.
Phillips Bldg.
for Evaluation of Loss of Coolant GE Accidents for Non-Jet Plants.
2/5/86 P-118 Overview of B&W Owners Group B&W Owners Group W. Paulson 10:00 a.m.
Phillips Bldg.
Activities.
1:15 p.m.
Discussion of the B&W Owners Group program with regard to the Dec. 26 Rancho Seco event and the Davis-Besse June 6, 1985 event.
E P8 55 m
o 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
it E
NMSS MEETING NOTICES FOR WEEK ENDING: 1/24/86 h
Division of Fuel Cycle and Material Safety 8R DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 2/6/86 Project
- Willste, Evaluation of CASTOR V Basket Reps of NRC, Roberts M-37 8th floor Cracks.
GNSI & VEPC0 conf room 2/6/86 Willste Meeting of the Ad Hoc Interagency Reps of NRC, Shum 9:00 Room 110 Task Force to do a Public Health EPA, CDC.
Assessment as. a result of the ORNL, DOE, Kerr-McGee accident.
State of.0klahoma, Consultant from the University of Rochester Division of Waste Management 2/5-7 Colorado State Univ.
Geotechnical and MFliegel
- K11egel Geohydrology Aspects 4 WMGT staff
,rf T of WM
,f 2/10 Savannah, Georgia ASME/EPRI Radwaste Workshop TCJohnson TCJohnson To be determined 2/10-12 Washington, D.C.
Nat'l Council of American CRussell CRussell Indians Executive Council SWeisberg, SP Meeting Division of Safeguards 9
h!
NONE 8
1 M
e
o
$5 January 24, 1986 to RII MEETING NOTICE Si u,
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT
'01/28/86 RII Office Enforcement Conference -
Licensee, Regional Walker 10:00 am Florida Power Corporation Administrator and Crystal River 3 Selected RII Staff Members 01/29/86 RII Office Meeting with 0. Dixon and Licensees and Grace 11:00 am D. Nauman, SCE&G, to Regional Administrator discuss issues of mutual interest 2:00 pm RII Office Meeting with C. Woody and Same as above Grace t
A. Adomat, Florida Power and Light Company to discuss current issues pertaining to FP&L l
01/30/86 RII Office Meeting with Georgia Power Licensee, Regional Walker 10:00 am Company to discuss improve-Administrator and ments in the SALP at Hatch Selected RII Staff Nuclear Power Plant in the Members area of maintenance 01/31/86 RII Office Enforcement Conference Same as above Walker 10:00 am Florida Power and Light Company - Turkey Point 1
E, c
O 8?
?;
o
.