ML20136E675
| ML20136E675 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851101, NUDOCS 8511210548 | |
| Download: ML20136E675 (50) | |
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) .s November 6, 1985 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 1, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Co'ntents Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Inspection and Enforceinent D Nuclear Regulatory Research E Executive Legal Director F*
International Programs G
, State Programs H*
P.esource Management I*
Analysis and Evaluation of Operational Data J Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L CRGR Monthly Report M*
Executive Director for Operations N*
i Items Addressed by the Comission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution) l
.d s
l *No input this week. //
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/ T./~A. fir.v'ni-Rehm,' Assistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781 851121054s 851106 PDR COMMS NRCC WEEKLYINFOREPT PDR
HIGHLIGHTS OF WEEKLY INFORMATION REPORT i WEEK ENDING NOVEMBER 1, 1985 Limerick On October 22, 1985, the Appeal Board affirmed the Licensing Board's-Second Partial Initial Decision (PID-2) in all respects except one..
- PID-2 dealt with several site specific safety issues, environmental-
. qualifications QA/QC of welding, onsite emergency planning and NEPA
! severe accident risk contentions. On the single exception, the Appeal i Board reversed and remanded to the Licensing Board the issue concerning the proximity of offsite medical support facilities for the treatment ,
of traumatic injuries. The Appeal Board also concluded that this one !
deficiency in the licensee's emergency plan is not so significant as to ;
- warrant license suspension.
Shoreham Emergency Plan Drill On October 29, 1985 FEMA responded to an NRC request for an emergency plan drill at Shoreham. FEMA stated that "an'y exercise without .. ;
participation by State and local governments would not allow us sufficient demonstration to reach a finding of reasonable assurance."
It went on to say, though, that an exercise would be valuable to the NRC in deciding to continue the Shoreham licensing process or in !
1 providing a basis for a predictive finding by the NtC. FEMA offered two options: (1) to hold a limited exercise which would set aside all 1 functions and exercise objectives related to State and local
- participation; and (2) to hold a full exercise in which exercise
! controllers would simulate the roles of State and local officials.
FEMA requested that the Connission decide on one of these options by i
! November 15, so that a drill could be held in January, 1986.
I
, Brunswick Steam Electric Plant, Unit 1 l l
l Restart of Brunswick, Unit 1 began on October 30, 1985 after a 7-month l outage for refueling, maintenance and completion of the environmental i qualification program. During this outage other work was also accomplished including fire protection modifications, Mark I modification, inspection (with intergranular induction heating stressstress corrosion crackingIHSI)).
improvement ((IGSCC) TMI l modifiestion, seismic support modification and masonry wall design and construction work.
Nuclear Fuel Services. Inc.
On October 29, 1985, members of the NRC staff met with representatives of Nuclear Assurance Corporation (NAC) of Atlanta, Georgia, and Nuclear Fuel Services, Inc. (NFS), and its parent company Texaco, to discuss the legal implications of the purchase of NFS by NAC. It was agreed that, in the near I future, NAC would submit a letter to NMSS requesting approval of the transfer. j l NOV 1 1985 l
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l 0FFICE OF ADMINISTRATION l Week Ending November 1,1985 l
ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 727 41 Granted 572 29 Denied 168 16
, Pending 166 19 ACTIONS THIS WEEK Received
- , Jim Pedro, Requests a copy of SECY-85-120, "Public Availability
ll (85-717)
Janice D. Sears, Requests a copy of an 0IA report entitled, " Review of Troutman, Sanders, NRC's Quality Assurance Inspection Program for Reactors Lockerman & Under Construction."
Ashmore (85-718)
Hiram McBeth, Requests four categories of records regarding power
.,it Mid-South plants.
Technical Services (85-719)
Shlomo P. Neuman, Requests a copy of the technical proposal submitted by The University of the contract awardee under RFP-RS-RES-85-114.
Arizona (85-720)
Franets Kreysa, Requests six categories of records related to Canada's Neutron Products Byproduct Materials License No. 54-00300-04, Amendment Inc. 35.
(85-721)
Gary Redmore, Requests a listing of all NRC Byproduct Material Syncor Licensees in Region I.
International Corp.
(85-722)
CONTACT: J. M. Felton 492-7211 ENCLOSURE A NOV 11985 e
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2 Received, Cont'd Peter T. Rathje, Requests copies of 23 specified monthly operation Doc-Search reports for the Haddam Neck nuclear power plant.
Associates (85-723)
Z. Reytblatt, Requests four categories of records regarding leak Illinois rate tests.
Institute of Technology (85-724)
Victor W. Palmer, Requests records related to employment practices The Federal concerning NRC's full time Administrative Law Judges.
Administrative Law -
Judges Conference (85-725)
E. F. Kurtz, Jr. , Requests a list of, and copies of, NRR Office letters.
Duquesne Light
.. (85-726) 1
'l Luther Daniel Requests records related to Fort Bliss, Texas.
(85-727)
Kathiann M. Kowalski, APPEAL TO THE EDO for the release of two specified Squire, Sanders denied records regarding the Parkersburg, West Virginia, and Dempsey site of Amax, Inc.
(85-A-41-85-375)
. Granted l
~! Steven C. Sholly, In response to a request for records concerning the
' recent visit of the Caseload Forecast Panel to Seabrook, MHB Technical Associates Unit 1, made available four records. Informed the (85-669) requester that two additional records subject to this request are already available at the PDR.
Steven C. Sholly, In response to a request for a list of NRC Project MHB Technical Managers and Resident Inspectors by name, plant name, Associates and office telephone number, made available a list of (85-678) names. Infomed the requester that a record providing the remaining requested infomation is available for purchase from the Government Printing Office.
Patty Day, In response to a request for a copy of the August 26, NUS Corporation 1975, Supplement 1 to the Report to the ACRS by NRR, (85-685) In the Matter of Westinghouse Electric Corporation -
Reference Safety Analysis Report - RESAR-41, made available a copy of the requested record.
David R. Ennis, In response to a request for the operator exam results NUS Corporation for Duke Power Company's Oconee power plant for the (85-692) years 1979 through 1982, made available six records.
ENCLOSURE A NOV 1 1985
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Granted, Cont'd Sheryl Wurl, In response to a request for copies of complaints Dakota Midland lodged against the Dakota Midland Hospital Radiation or Hospital Nuclear Services by the Presentation Health System, St. I (85-695) Luke's Hospital, or any other party during calendar years 1984 and 1985 to date, informed the requester that the NRC is not in possession of records subject to this request.
(NRCemployee) In response to a request for copies of two specified (85-704) memoranda regarding herself, made available copies of the records.
Mark T. Spears, In response to a request for a list of ail 1985 SBIR Arthur Anderson Phase I and Phase II awardees, made available a copy of
& Co. the requested list.
(85-705)
Bernard M. Savaiko, In response to a request for a listing of manufacturers Department of licensed pursuant to 10 CFR 32.14 for the manufacture Army and distribution of electron tubes containing
, (85-708) Promethium-147, made available a copy of the requested list.
Charles W. Kelly, In response to a request for copies of all IE Notices for Core Corporation Material Licensees, infomed the requester that these (85-713) records are already available at the PDR.
Joseph Cuthbert, In response to a request for a list of all 1985 SBIR Advanced Technology Phase I awardees, made available a copy of the requested Center of South- list.
. Eastern Pennsylvania I
(85-714)
Janice D. Sears, In response to a request for a copy of an 0IA report Troutman, Sanders, entitled, " Review of NRC's Quality Assurance Inspection
. Lockerman & Program for Reactors Under Construction," informed the Ashmore requester that this report is already available at the (85-718) PDR.
Denied Kay L. Dove In response to a request for a copy of SECY-85-65 and (85-586) any records that are related to this paper, denied eight records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Mozart G. Ratner, In response to a request for six listed reports regarding Attorney-At-Law the General Electric Company of Wilmington, North (85-598) Carolina, made available two records. Denied portions of four records containing information which identifies procedures for safeguarding licensed special nuclear material at a licensed facility.
ENCLOSURE A NOV 11985
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Denied, Cont'd Billie P. Garde, In response to a request for records related to the Government July 26, 1985, briefing by Georgia Power Company about Accountability its Readiness Review Program for the Vogtle plant, Project including the transcript of the briefing, made (85-599) available five records. Informed the requester that the transcript of the July 26 briefing is already available at the PDR. Denied three records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
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ENCLOSURE A NOV 11985 i
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WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING NOVEMBER 1, 1985 PROPOSALS UNDER EVALUATION RFP No.: RS-RG5-86-331
Title:
" Radiation Monitoring Instrumentation Quality Assurance Program"
Description:
The purpose of this project is to provide a fully implemented quality assurance program for an extensive inventory of instrumentation which includes scintillation detectors, ionization chambers, multi-channel analyzers and neutron detectors and to assure a constant state of readiness for equipment dedicated for emergency response. The contractor shall possess a background in radiation protection technology, knowledge of nuclear counting procedures and a background in the practical and theoretical operating characteristics of a variety of radiation measuring instruments.
Period of Performance: One year with a one year option Sponsor: Region V ,
Status: RFP closed on October 24, 1985. Proposals forwarded to Source Evaluators for review on October 31, 1985.
RFP No.: RS-0IE-85-159
Title:
"NRC Training Courses for Inspectors and Engineers"
Description:
The contractor will provide experienced instructors and other experts to conduct two training courses of 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> duration each. One course shall be titled, " Electrical Technology and Codes," the other " Instrumentation Technology and Codes."
Period of Performance: One year with 3 one year options Sponsor: Office of Inspection & Enforcement Status: The competitive range has bean established and negotiations were l
held during the week of October 28, 1985.
CONTRACT AWARDED IFB No.: RS-ORM-85-334
Title:
"On-call Maintenance for Microcomputers and Related Equipment"
Description:
On-call maintenance including all necessary maintenance, labor, parts, documentation, supplies, test equipment, transportation and related services for NRC microcomputers and related equipment.
Period of Performance: 2 years i Sponsor: Office of Resource Management 1 Status: Time and materials requirements Contract No. NRC-33-86-288 awarded to J. C. Services in the amount of $34,000, effective November I, 1985.
ENCLOSURE A NOV 11985 1
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..Q OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending November 1, 1985 River Bend On October 25, 1985, Gulf States Utilities informed the staff that the environmental qualification program is complete and all covered equipment has been qualified.
River Bend Station did not go critical on October 25, 1985 as previously projected by the staff. GSU current estimate for criticality is October 2728, 1985. River Bend received their low power license on August 29, 1985 and completed loading fuel on September 21, 1985. GSU initially projected a criticality date of September 26th, j which has slipped due largely to a stretch out in startup surveillance i procedures.
North Anna Power Station, Unit 1 (NA-1)
At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, Thursday (10/24/85), failure of a breaker in a battery room exhaust fan resulted in the grounding of the 480 Volt 1-J-1 Bus.
Loss of the 1-J-1 Bus caused the loss of various loads including the loss of semi-vital Bus 1-B. Loss of Bus 1-B caused the loss of the l non-vital SOY panel which closed valves TV-CC-106 A, B, and C which supply component cooling water (CCW) to the RCP A, B, and C upper bearing lube oil coolers and stator coolers.
At 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> operators determined CCW to RCP's could not be recovered 3
(Short term) and NA-1 began ramp down from 100% power at a rate of 1%
per minute (later increased to 5% per minute). RCP bearing i temperatures were observed to be rising toward the critical 195'F limit. At 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> RCP bearing temperature indication reached 195'F i
and a manual reactor-turbine trip took place at 87% power and all three RCP's were secured. The Unit was stabilized and placed in natural
- circulation mode.
l At 0519 hours0.00601 days <br />0.144 hours <br />8.581349e-4 weeks <br />1.974795e-4 months <br />, the RCP 106-A was energized by jumper rig and CCW was restored to RCP-A. RCP "A" was restarted with bearing temperature in normal range (130-150*F). Repairs to the 1-J-1 Bus were completed and 1-J-1 Bus was re-energized and loads restored to the bus. At 0951 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.618555e-4 months <br />, the RCP "C" was restarted with bearing temperature normal. The licensee is presently assessing transient and investigating breaker failure of battery exhaust fan.
ENCLOSURE B NOV 1 1985
Limerick ;
l On October 22, 1985, the Appeal Board affirmed the Licensing Board's !
Second Partial Initial Decision (PID-2) in all respects except one.
PID-2 dealt with several site specific safety issues, environmental )
qualifications, QA/QC of welding, onsite emergency planning and NEPA l severe accident risk contentions. On the single exception, the Appeal l Board reversed and remanded to the Licensing Board the issue concerning l the proximity of offsite medical support facilities for the treatment of traumatic injuries. The Appeal Board also concluded that this one deficiency in the licensee's emergency plan is not so significant as to warrant license suspension.
Seabrook At about 4:00 a.m. on October 28, 1985, when the plant's reactor coolant system reached 150*F, Seabrook Station, Unit 1 began its month long hot functional test (HFT). This test is about a week ahead of its milestone date.
Most of the plant's systems and components have been individually tested, but this will be the first time they will have all been tested together in a major integrated test at a normal operating temperature of about 575*F. The reactor coolant pumps are utilized as the heat source.
River Bend Station On October 27, 1985, the licensee declared an unusual event when a low level indication was received by the River Bend Division ECCS. The low level indication was the result of manually filling the Division 1 reference leg without electrically isolating the level indicator from the ECCS. After receiving low level indication, ECCS activated LPCS and RHR systems which ran for 2-3 minutes until the level indicator was electrically isolated. An LER is in process and Region IV is following up.
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ENCLOSURE B NOV 1 1985 ,
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< - t 3-Shoreham Emergency Plan Drill On October 29, 1985 FEMA responded to an NRC request for an emergency plan drill at Shoreham. FEMA stated that "any exercise without participation by State and local governments would not allow us sufficient demonstration to reach a finding of reasonable assurance."
It went on to say, though, that an exercise would be valuable to the NRC in deciding to continue the Shoreham licensing process or in providing a basis for a predictive finding by the NRC. FEMA offered two options: (1) to hold a limited exercise which would set aside all
! functions and exercise objectives related to State and local participation; and (2) to hold a full exercise in which exercise controllers would simulate the roles of State and local officials.
4 FEMA requested that the Consnission decide on one of these options by l November 15, so that a drill could be held in January, 1986.
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River Bend 4 River Bend Station went critical (with the head on) at 12:37 a.m. (CST) on October 31, 1985. The first rod was pulled at 9:27 p.m. (CST). By going critical with the head on, River Bend can save about 5-days in j their power ascension schedule.
! River Bend Station is operated by Gulf States Utilities. River Bend
- received their low power license on August 29, 1985, and completed fuel loading on September 21, 1985. River Bend has approximately 80 surveillance tests to complete before going above 5% power.
Hurricane / Tropical Storm Juan rainfall is expected to total less than 12 inches at Baton Rouge (25 miles south of River Bend). The River Bend FSAR is based on a PMP of 47.1 inches in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
! Brunswick Steam Electric Plant, Unit 1 Restart of Brunswick, Unit 1 began on October 30, 1985 after a 7-month outage for refueling, maintenance and completion of the environmental qualification program. During this outage other work was also accomplished including fire protection modifications, Mark I modification, intergranular stress corrosion cracking (IGSCC) inspection (with induction heating stress improvement (IHSI)), TMI modification, seismic support modification and masonry wall design and construction work.
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ENCLOSURE B
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4-Palo Verde Unit 1 On October 29, 1985 while starting RCPs in Mode 3 in preparation for startup following the October 24, 1985 reactor trip, a failure occurred 4
in a non safety grade bus powering the RCP load centers. Details of 1
the failure and the failure mechanism are unclear at this time. The utility is investigating the failure and does not anticipate starting up before November 6, 1985. The unit is currently in Mode 5.
Three Mile Island - Unit 2 On Thursday, October 31, 1985, GPU Nuclear began the first phase of defueling the damaged reactor core. The operations in this limited i
initial phase involve the rearrangement of core debris within the
- reactor vessel. This will provide clearance for the installation of l equipment which is needed to facilitate the removal of fuel from the reactor vessel.
4 Specially trained operators, under the direction of licensed Fuel Handling Senior Reactor Operators, used long-handled manual and hydraulic tools to move damaged fuel and assorted core material within the reactor vessel. In the next few weeks initial defueling activities are expected to include; loading of debris into specially designed baskets, which will later be loaded into defueling canisters and removed from the reactor vessel, and the iCentification and positioning of core debris samples for later removal and examination. The licensee expects to begin removing fuel from the reactor vessel sometime during November 1985. Onsite NRC personnel are monitoring activities.
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l' ENCLOSURE B i
NOV 11985 I
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NRC TNI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING NOVEMBER 1, 1985
- 1. DEFUELING On Thursday October 31, 1985, GPU Nuclear began the first phase of defueling the damaged reactor core. The operations in this limited initial phase involve the rearrangement of core debris within the reactor i vessel. This will provide clearance for the installation of equipment
! which is needed to facilitate the removal of fuel from the reactor l vessel.
I
- Specially trained operators, under the direction of licensed Fuel Handling Senior Reactor Operators, used long-handled manual and hydraulic
, tools to move damaged fuel and assorted core material within the reactor vessel. In the next few weeks initial defueling activities are expected to include; loading of debris into specially designed baskets, which will later be loaded into defueling canisters and removed from the reactor vessel, and the identification and positioning of core debris samples for later removal and examination. The licensee expects to begin removing i fuel from the reactor vessel sometime during November 1985. Onsite NRC personnel are monitoring activities.
- 2. PLANT STATUS The facility remains in long term cold shutdown with the Reactor t Coolant System (RCS) vented to the reactor building atmosphere and i the reactor vessel head and plenum assembly rei aved 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 oftheplenum).
The modified internals indexing fixture is installed on the reactor 4 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 Internal Indexing Fixture in preparation for
, defueling. I 1
i ENCLOSURE B j NOV 11985
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- 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 70*F to 93'F with an average of 82*F.
The average reactor building temperature is 58'F. The reactor building airborne activity is 5.0 E-8 uC1/cc Tritium and 3.5 E-10 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 fuel canister storage racks.
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- 3. WASTE MANAGEMENT-TheSubmergedDemineralizerSystem(SDS)continuesprocessingbatch 125, Fuel Transfer Canal through Train No.1. To date a total of
, 186,201 gallons has been processed.
EPICOR II is temporarily shutdown while changing out liners.
4 -
Total volume processed through SDS to date is 3,174,794 gallons, and i
the total volume processed through EPICOR II is 2,700,737 gallons.
10 CFR 61.55 Exemption approval was given by NRC which authorized the licensee to classify EPICOR II liners containing 1 microcuries
- per cubic centimeter of Strontium 90 as Class A waste.
- 4. DOSE REDUCTION / DECONTAMINATION ACTIVITIES
} -
Decontamination activities are continuing on the 281' level of the auxiliary building.
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.
- Removal of insulation and decontamination of the pressurizer is in progress.
- 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 October 12 I through October 19, 1985. A gama scan detected no reactor related
. activity.
The Lancaster water sample taken at the water works intake and i
analyzed by EPA consisted of a seven day composited sample taken
- from October 13 through October 19, 1985. A gamma scan detected no f
reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between October 23 and October 30, 1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower j limits of detectability.
i ENCLOSURE B NOV 11985 y \
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- 6. RADI0 ACTIVE MATERIAL / WASTE SHIPMENTS During October 1985 the shipments listed below were made from the TMI site.
October 1 - Unit 1, a new fuel assembly was returned to vendor at Lynchburg, VA.
October 3 - Combined laundry shipment; 75 drums, I box of protective clothing to Royersford, PA.
October 8 - Unit I liquid radioactive samples sent to Rockville, MD.
October 9 - Combined laundry shipment; 40 drums, 2 boxes of protective clothing to Royersford, PA.
October 11 - Unit 2 lower head debris samples were sent to Idaho National Engineering Laboratories at Scoville, ID.
October 15 - Combined laundry shipment; 73 drums, 2 boxes of protective clothing to Royersford, PA.
October 17 - Unit I uncompacted trash in a steel box and three liners containing dewatered resins to Hanford, WA.
October 21 - Combined shipment of barrels and boxes of compacted and uncompacted waste to Hanford, WA.
October 21 - Unit 1 solidified radioactive liquid in a steel liner sent to Barnwell, SC.
October 24 - Combined laundry shipment; 97 drums, 2 boxes of protective clothing to Royersford, PA.
October 29 - An EPICOR II dewatered resin liner was sent to Hanford, WA using the recently approved NRC and Washington state exemptions for shipment / disposal of Strontium 90 in wastes.
October 30 - Combined laundry shipment; 49 drums,1 box of protective clothing to Royersford, PA.
October 31 - Unit 2 scrap metal was sent to Oak Ridge, TN.
- 7. REACTOR BUILDING ACTIVITIES Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.
Installation of the vacuum defueling system is in progress.
Work is in progress on the canister positioning system.
Canister handling bridge indexing and load testing is in progress.
The initial phase of defueling the reactor core is in progress.
- 8. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is expected to be completed in October.
Spent Fuel Pool has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
ENCLOSURE B NOV 1 1985
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- 9. NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change numbers 29, 31, and 32.
- Fuel Canister Technical Evaluation, Revision 1.
- Defueling Safety Evaluation.
- SDS Technical Evaluation and System Description Update.
- Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
- Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
- Containment Air Control Envelope Technical Evaluation Report, Revision 5.
- 10. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for 11:00 AM, November 19, 1985, in Washington, DC, before the NRC Commissioners. The next meeting in the TMI area is scheduled for December 12, 1985, at the Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to approximately 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.
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N OSURE B NOV 11985
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I 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Ittes of Interest Week Ending November 1, 1985 Near Tere NRC Actions Under the Nuclear Waste Policy Act 1983 Section: 114(f) of NWPA: Preliminary Determination of Site Suitability Action: The Commission met with representatives of States and Tribes on Friday, September 6, 1985 to receive their views on 00E's timing of the preliminary determination. The Commission then requested OGC to examine whether NRC is legally required by NWPA to take any action
, now in response to the current DOE position on the timing of the preliminary determination. In a memo to the Commission on September 24, DGC advised that the Commission had na need to act now, but should not remain silent on the issue.
Status: The OGC staff prepared and forwarded to OCM on October 25, 1985 for Commission review, an appropriate statement to be issued to restate the Commission's concurrence decision on the DOE Siting Guidelines.
Section: 114(e) of NWPA: Project Decision Schedule Comments Action: DOE had requested comments on the draft PDS by September 13, 1985.
The Commission voted to approve the PDS comments on September 19, 1985. The final edited version was submitted to SECY on October 16, 1985 for transmittal to DOE.
Status: The PDS comments were edited at the Commission to include the Commission decision (with two Commissioners disagreeing) on 114(f).
The comments were transmitted to DOE on October 24, 1985. l Section: 301 of NWPA: DOE Mission Plan l Action: NRC testified concerning the final Mission Plan before both houses i of Congress in early September. l
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ENCLOSURE C NOV 1 1985
i Status: NRC has been invited to testify on November 6, 1985 before the House Subcommittee on Energy Research and Production concerning the implementation of NWPA and also the Mission Plan, among other l topics. NRC testified before the Senate Subcommittee on Nuclear Regulation on October 30, 1985. l NFS-Erwin Strike by OCAW members continues. There has been some negotiating between the l Union and NFS within the last three weeks but no resolution has been reached.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problems with site operations have arisen to date.
B&W Apollo and Parks Township, PA.
On October 29, 1985, representatives of B&W met with Division of Safeguards personnel to discuss the consolidation and revision of two Category 11 physical security plans.
Carolina Power & Light Company, Shearon Harris Nuclear Power Plant On October 28, 1985, Carolina Power & Light Company was issued Materials License No. SNM-1939 for Shearon Harris Nuclear Power Plant, Unit 1, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies, incore fission chambers containing enriched uranium, and sealed sources containing uranium and neptunium for irradiation ~ surveillance capsules. All materials are for eventual use at the Shearon Harris Nuclear Power Plant, Unit 1.
Nuclear Fuel Services, Inc.
On October 29, 1985, members of the NRC staff met with representatives of Nuclear Assurance Corporation (NAC) of Atlanta, Georgia, and Nuclear Fuel Services, Inc. (NFS), and its parent company Texaco, to discuss the legal implications of the purchase of NFS by NAC. It was agreed that, in the near future, NAC would submit a letter to NMSS requesting approval of the transfer.
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ENCLOSURE C l NOV 1 1985
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OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending November 1, 1985
- 1. The following Significant Enforcement Actions were taken during the past week:
- a. EN 85-74, a Notice of Violation and Proposed Imposition of Civil Per.alty in the amount of $80,000 was issued October 29, 1985 to Maine Yankee Atomic Power Company (Maine Yankee). The action involves inoperable root valves which rendered the four channels for.the low steam generator pressure trip function of the Reactor Protective System and three of four channels for the low steam generator pressure trip function of the Feedwater Trip System inoperable.
- b. EN 85-75, Order Suspending License (Effective Immediately) was issued October 25, 1985 to Institute for Medical Research of Bennington (Bennington, VT) for failure to meet commitments in its license and in a Confirmatory Action Letter. Specifically, the licensee allowed unauthorized use of radioactive material, use of material by unauthorized persons, and the possession of quantities of radioactive material in excess of authorized limits.
- 2. The following IE Preliminary Notifications were issued during the past week:
- a. PNO-TMI-85-10, GPU Nuclear Corporation (TMI Unit 2), Defueling Operations to Begin.
- b. PN0-II-85-101, Metropolitan Hospital (San Juan, PR), Teletherapy Unit Malfunction,
- c. PNO-II-85-102, Mississippi Power and Light Company (Grand Gulf Unit l
1), Crack Indications on Surface of Recirculation Pipe.
- d. PNO-III-85-93, American Electric Power (D.C. Cook), Failure of Reactor Trip Breaker.
- e. PN0-III-85-93A, American Electric Power (D.C. Cook), Failure of ReactorTripBreaker(Update).
- f. PNO-IV-85-55, Gulf States Utilities (River Bend), Initial Criticality (Mode 2).
- g. PNO-V-85-72,ArizonaPublicService(PaloVerdeUnit1),ReactorTrip With Safety Injection.
- h. PNO-V-85-73, Arizona Nuclear Power Project (Palo Verde Unit 1),
Extended Plant Shutdown Resulting From a Non-Class 1E Electrical Bus Bar Failure,
- i. PNO-V-85-74, Pacific Gas and Electric (Diablo Canyon Unit 1), Con- ,
denser Tube Leak. ENCLOSURE D NOV 11985 i
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- a. IE Information Notice 85-83, Potential Failures of General Electric PK-2 Test Blocks was issued October 30, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.
- b. IE Information Notice 85-84, Inadequate Inservice Testing of Main Steam Isolation Valves was issued October 30, 1985 to all nuclear power reactor facilities holding an operating license or a construc--
tion permit.
- c. IE Information Notice 85-85, Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following Fire-Protection Deluge System Malfunction was issued October 31, 1985 to all nuclear power reactor facilities holding an operating license or a construc-tion pennit.
- d. IE Bulletin 85-01, Steam Binding of Auxiliary Feedwater Pumps was issued October 29, 1985, to those nuclear power reactor facility licensees and construction holders listed in Attachment 1 of the Bulletin for action and to all other nuclear power reactor facilities for information.
- 4. Other Items
- a. Senior Management Meeting Deputy Director, IE was in Region III, October 30, 1985 to meet with Regional representatives and Commonwealth Edison regarding La Salle.
- b. D.C. Cook On October 29, 1985, D.C. Cook Unit 2 experienced a failure of one of two reactor trip breakers to open during a successful trip from 79%
power. NRC Headquarters is supporting an augmented response to this event by providing technical experts from NRR and IE to jcin the Region III special inspection team that is already onsite. Region III has issued a confirmatory action letter to freeze the evidence and hold both Units 1 and 2 down until this matter is resolved. A PN has been issued.
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ENCLOSURE D )
NOV 1 1985 1
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- c. Civil Penalties Paid i
1.) On October 28, 1985, payment in the amount of $100,000 was
! received from American Electric Power (D.C. Cook) for enforcement action (EA 85-94) relating to the failure to i
i adequately control access to vital areas.
l
' 2.) On October 30, 1985, payment in the amount of $50,000 was received from Sacramento Municipal Utility District (Rancho Seco) for enforcement action (EA 85-103) relating to violations i
i involving a hot leg high point vent leak.
- d. Incident Response Activities 1.) The Incident Response Branch, Division of Emergency Preparedness and Engineering Response (DEPER) conducted an Emergency Response Coordinator Workshop #10 at Headquarters on October 29-31, 1985.
In addition to developing standardized job descriptions for core i
positions on the site and base teams, the group met with DOE i
counterparts to discuss items of mutual interest.
2.) On October 29, 1985, a member of the Incident Response Branch, 1
DEPER, conducted a tour of the NRC Operations Center for a management representative from the Nuclear Safety Center, .
Republic of Korea. This tour discussed the agency's incident response program.
', e. Vendor Program i
1.) The Vendor Program Branch, Division of Quality Assurance Vendor and Technical Training conducted the following inspections this
, week:
a.) NTS, Hartwood, Virginia - to inspect and witness post LOCA functional tests of Rosemount RTDS being performed for
! Consumer Power.
b.) Yarway Corporation, Blue Bell, Pennsylvania - to follow up on reported' valve stem problem with Yarway valves.
! c.) TVA and Sequoyah, Knoxville, Tennessee - to look at cable qualification problems for Limitorque operators.
d.) Region II - to assist in an inspection of TVA's l implementation of procurement system corrective actions.
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1 ENCLOSURE D
! . NOV 1 1985 l
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4 I f. IGSCC Detection i A representative of Enegineering and Generic Connunications Branch, ~
i Division of Emergency Preparedness and Engineering Response (DEPER), ;
was at the EPRI NDE Center in Charlotte, NC on October 31 and i November 1 to monitor IGSCC detection requalification of personnel ;
t from several organizations and their automated systems. The i organizations and systems are: LMT, Inc. - ALARA 1; Combustion Engineering - Introsport 98; Nuclear Energy Services - UDRPS.
- g. Quality Assurance l 1.) Representatives of the Quality Assurance Branch (QAB), Division of Quality Assurance, Vendor and Technical Training (DQAVT) visited Bechtel Power Corporation offices in San Francisco, i California on October 22-25, 1985 to inspect Hope Creek Independent Design Verification Program corrective actions.
2.) A representative of the QAB, DQAVT visited the WNP-3 site on October 28-29 to review WNP-3 Readiness Review Program activities.
i 3.) Representatives of the QAB, DQAVT visited TERA offices in
- Bethesda, Maryland on October 28-November 1,1985 to inspect
- Comanche Peak Design Adequacy Program Plan activities.
4.) A representative of the QAB, DQAVT participated in a site visit
! to the Salem plant as part of the NRR review and survey of l maintenance practices in the industry the week of October 28.
- h. Assessment Program
- Representative of Safeguards Material Program Branch, Division of
- Inspection Programs, was in Minneapolis /St. Paul, MN this week on j assessment of programs with RIII.
- 1. Accompanied Inspection Representative of Safeguards Materials Program Branch, Division of Inpsection Programs was in Richland, WA this week to accompany Region i V inspections at Exxon.
! j. Readiness Review Public Meeting i
Chief Reactor. Construction Program Branch, Division of Inspection i Program'and Representative of Quality Assurance Branch, Division of j Quality Assurance Vendor and Technical Training participated in a
- public meeting with Region V and WNPS Personnel in Satsop, WA on l
October 29, 1985 to discuss the Readiness Review process for 4
construction of WNP 3.
NOV 1 1985 i
I
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- k. Transportation Training Course Representative of Safeguards Materials Program Branch, Division of Inspection Programs was in Region II this week to conduct the Transportation Training Course for selected members of RII staff.
- 1. Outage and Pre-Operations Readiness Inspection Consultants and Representatives of Reactor Construction Program, Division of Inspection Program, met October 28, 1985 in preparation
' for the upcoming Fort Calhoun station outage installation and pre-operations readiness inspections.
j ENCLOSURE D NOV 1 1985 I
4 OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending November 1, 1985 Sixth Semi-Annual Proc ram Partners Review Meeting on the Joint Severe-Fuel-Damage ancl Source-Term Research Program This program review meeting was held in Bethesda, Maryland on October 16-18, 1985, with our program partners: Belgium, Canada, the Federal Republic of Germany, Italy, Japan, the Republic of Korea, the Netherlands, the United Kingdom, the American Institute in Taiwan, and EPRI (the U.S. Electric Power Research Institute).
Our foreign partners are furnishing about 25% of the support for this program through direct funding and some in-kind research.
The partners were generally pleased with the progress in the program.
Major topics covered at the meeting were: preliminary results of the recent Degraded Core Coolability experiment DCC-3 in ACRR; the recent Debris Formation experiment DF-3 in ACRR with a PWR control rod; new results from data analysis and Post-Irradiation Examination (PIE) of the recently-completed PBF Severe Fuel Damage tests and the initial NRU full-length coolant boildown test; an update of the DOE work on the TMI-2 core examination; a sumary of the new German fuel-damage test facility CORA and the test plans that have been worked out in conjunction with NRC; sumaries of new results and the current status of fission-product and aerosol behavior in severe accidents; application and assessment of the mechanistic fuel-damage SCDAP code particularly by the U.K.; integration of thermal hydraulics and fission-product behavior into the SCDAP/RELAPS and the MELPROG/ TRAC / VICTORIA codes; plans for the experimental assessment and validation of the new mechanistic MELPROG core-melt-progression code; and a sumary of the current status of the NRC activities on source-term reassessment and severe-accident policy.
NOV 1 1985 ENCLOSURE E
s Open-House Demonstrations of the Nuclear Plant Analyzer (NPA)
The NPA provides on-line, operator-controlled, computer simulation of reactor thermal hydraulics, with color graphic outputs to analyze reactor system transients in order to provide the Office of Nuclear Reactor Regulation (NRR) with a broad technical basis for licensing decisions. A demonstration of the Brookhaven National Laboratory, boiling water reactor NPA and the Idaho National Engineering Laboratory, pressurized water reactor NPA was held in Room P-114 of the Phillips Building on October 23, 1985, with hands-on participation
- by NRR staff members.
ACRS Subcommittee Meeting on Waste Management Materials Research The RES Waste Management Branch (WMB) presented the materials portion of the RES HLW waste management program at a combined meeting of ACRS Subcommittees on Waste Management (D. Moeller, Chairman) and Metal Components (P. Shewman, Chairman).
The topics presented focused on research directed at the waste form, overpack, packing / backfill / seals,andwastepackage(groundwater) environment. Phenomena being studied in relation to each of these areas were discussed, as well as details of each research contract. Principal lines of discussion included the adequacy of technical communications from DOE, and timing of some research investigations in view of the fact that DOE has not yet made a final selection of waste package materials or design. It is anticipated that a report will be prepared by the Subcommittees.
i NOV 11985 ENCLOSURE E
4 RES Rulemaking Activities RES Independent Reviews of Rulemakings: By memorandum of February 13, 1984, " Control of NRC Rulemaking by Offices Reporting to the EDO,"
Offices were directed that effective April 1,1984,(1) all offices under ED0 purview must obtain EDO approval to begin and/or continue a specific rulemaking, (2) resources were not to be expended on rulemakings that have not been approved, and (3) RES would independently review rulemaking proposals forwarded for ED0's approval and make recommendations to the ED0 concerning whether or not and how to proceed with the rulemakings.
To date, RES has received 83 rulemakings for independent review. The EDO has reviewed / approved 72 of those rulemakings for initiation, continuation, or tennination. RES has 11 rulemakings in hand for independent review, of which 5 are new proposed rulemakings for initiation and 4 are ongoing
- rulemakings for temination. The other two rulemakings are the first in
] RES' annual review program. All rulemakings due for annual review by the end of 1985 are in early stages of review.
i Emergency Preparedness for Fuel Cycle and Other Radioactive Material
] Licensees: In 1981 the NRC issued orders to certain fuel cycle and
! other radioactive material licensees requiring them to submit comprehensive onsite radiological emergency plans. Rulemaking was initiated on August 3,1981 for codification of those orders.
The proposed rulemaking package was concurred in by all offices and given to Mr. Minogue on October 21, 1985, for signature on transmittal to Mr. Dircks.
Pressurized Thermal Shock (PTS): In SECY-85-262, the EDO stated he would keep the Commission infomed of the development of a draft regulatory guide (Rev. 2 of Reg. Guide 1.99) that includes a method for calculating RT different than that included in the pressurized themal shock rule pu0bshed on July 23, 1985.
In a memo dated October 25, 1985, NRR transmitted to RES the PTS Regulatory Guide for editing and publication for public conrnent. NRR requested that RES
- assign high priority to this task. (Congress had requested NRC to resolve the USI's by the end of FY 1985, and publication of this regulatory guide for comment marks the resolution of USI A-49.)
CONTACT: M. Au, DRA0 44-37920 or S. Turel, DRA0 44-37925 ,
ENCLOSURE E l
NOV 1 1985
e Publication to be Issued in the Near Future
Title:
Format and Content of Plant-Specific Pressurized Thernal Shock Safety Analysis Reports for Pressurized Water Reactors (Draft Regulatory Guide)
Description:
Provides guidance for performing analyses required by the PTS rule (550.61 of 10 CFR Part 50).
Contact:
RoyWoods(NRR/ DST) -
492-4714
~
Recently Issued Publication Draft Regulatory Guide and Value/ Impact Statement: Proposed Revision 1 to Regulatory Guide 5.62, " Reporting of Physical Security Events", Task SG 901-4. Comments requested by December 31, 1985.
Contact:
K. Jamgochian (301)443-7985 i
i 1
NOV 11985 ENCLOSURE E
f ITEMS OF INTEREST
- 0FFICE OF INTERNATIONAL PROGRAMS WEEK ENDING NOVEMBER 1, 1985 International Meetings The following international meeting notices supplement those previously announced
December 2-6, 1985, Vienna, Austria - IAEA Consultants Meeting to Develop Safety Series Document on Maintaining On-Site Habitability i During Accidents at Nuclear Installations December 2-6, 1985, Vienna, Austria - IAEA Advisory Group Meeting on Quality Assurance for Computer Software June 2-6, 1986, Leningrad, USSR - IAEA Technical Consnittee Meeting on Behaviour of Used Fuel Assemblies and Storage Equipment at Long-Term Wet Storage Conditions September 2-12, 1986, Athens, Greece - IAEA International Symposium on the Significance and Impact of Nuclear Research in Developing Countries i
International Organization Vacancy Notices The following vacancy notices from international nuclear agencies have been posted on NRC bulletin boards.
IAEA, Vienna, Austria:
P-4 Senior Auditor, Office of Internal Audit and Management Services, Department of Administration P-3 Evaluation Officer, Evaluation Unit, Department of Technical i Cooperation l P-3 Project Officer, Latin America Section, Division of Technical l Assistance and Cooperation Department of Technical Cooperation P-4 Area Officer, Asia and Pacific Section, Division of Technical Assistance and Cooperation, Department of Technical Cooperation P-2 Chemist, Chemistry Unit, Seibersdorf Laboratory, Division of Research and Laboratories, Department of Research and Isotopes P-5 Head, Fellowships and Training, Fellowships and Training Section, Division of Technical Assistance and Cooperation, Department of Technical Cooperation ENCLOSURE G NOV 1 1985
J 1
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! International Agency Vacancy Notices continued ,
NEA, Paris, France:
{ A2/A3 Administrator, Radiation Protection and Waste Management
] Division, Nuclear Energy Agency 1
Foreign Visitors !
! On October 22 Mr. Peter Saverys of the Belgian Ministry of Foreign
! Affairs visited IP and ELD. Mr. Saverys, in the U.S. at the invitation i of the USIA, was interested in obtaining a general overview of NRC's .
, activities and specifics of reactor licensing procedures.
l On October 25 Mr. Fred Nilsson of the Swedish Nuclear Power 1 Inspectorate visited B. D. Liaw of NRR for discussions on pipe i undercladding cracks and methods of dealing with them.
i On Monday and Tuesday Dr. Samuel Harbison, a Superintending Inspector of the UK Nuclear Installations Inspectorate, gave a presentation to NRC
! staff on the British approach to safety goals and met with IE
- representatives to discuss emergency planning, RES representatives to 1
discuss revisions to radiation protection standards, and NRR
} representatives to discuss reactor siting policy.
, t
! On Tuesday and Wednesday Mr. Shigeru Bandou, Assistant General Manager of the Japanese Nuclear Power Safety Infonnation Research Center 4
! (NUSIRC), and Mr. Mikio Hada, Manager of NUSIRC's Internatinal Cooperation Office, met IP and AE0D representatives to discuss the i exchange of infonnation between NRC and the Japanese regulatory
- authority and with NRR representatives to discuss human factors-related
- issues. Messrs. Bandou and Hada also toured the Peach Botton BWR and
. Point Beach PWR to discuss the facilities' maintenance programs and to ,
i meet with the NRC resident inspectors. '
4 3
Foreign Trip Reports i Guy A. Arlotto. Director. DET. RES, and C. Z. Serpan, RES
{ April 19-May 10. 1985; Visited 5 pain. Italy Switzerland. FRG UK.
l France. Fin'and, and Belgium:
1
! The purpose of the trip was to gain a better understanding of the safety i research programs in materials in the countries visited as well as of
} their research facilities, and to discuss NRC's exchange programs and
! cooperation with other countries, i l l
ENCLOSURE G
- NOV 1 1985
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3 Foreign Trip Reports continued Robert W. Roussin, Director, Engineering Physics and Mathematics
- Division, ORNL September 5-18, 1985; Visited FRG and France:
1 l
Mr. Roussin attended meetings of the shielding specialists and the EURADOS Working Committee No. 4. in Stuttgart. In Paris he visited with CEA/CEN-LEPF personnel and with the Director of the NEA Data Bank in Saclay.
E. C. Beahm, Member of Development Staff of Chemical Technology Division, ORNL September 10-16, 1985; Visited UK and France:
l The purpose of the trip was to participate in an OECD workshop on iodine chemistry in reactor accidents, held in Harwell, and to exchange information in iodine chemistry at KWU, Erlangen.
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i ENCLOSURE G NOV 1 1985
_ _ . . _ . . _ . _ _ _ . _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ _ _ . . _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ . _ . _ __m.__.____ _________m.___ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING NOVEMBER 4, 1985
- 1. AE0D is issuing a Preliminary Case Study Report entitled " Effects of Ambient Temperature on Safety Related Instrumentation and Control Systems" in accordance with its " peer review" process. The report documents the study of operational events involving failures of electronic components in safety-related instrumentation and control (18C) systems in operating nuclear plants, due to high ambient temperature. The study was initiated by an event at the McGuire Station where an extended loss of control room area ventilation cooling occurred, leading to increased ambient temperature and instrumentation failures. The report concluded that the problem of high ambient temperatures affecting heat sensitive electronic components is potentially generic to all operating nuclear plants that use such compo-nents. Technical specifications regarding area ventilation system and instrumentation system were also reviewed and found incomplete. The study also found that the staff evaluation of the station blackout issue regarding environmental effects on plant I&C equipment could contain potentially deficient assumptions. Several reconinendations addressing the findings and conclusions of the study are provided in the report.
ENCLOSURE J NOV 1 1985
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REGION I l
TMI-1 STATUS REPORT FOR THE PERIOD OCTOBER 25 - NOVEMBER 1, 1985
- 1. Plant Status i
As of 8:00 A.M. on November 1, 1985, TMI-1 was at 48% power.
- 2. Test Program Status The licensee's planned test program and current status for restart of TMI-1 are shown on the attached Figure 1. Special testing planned during the next week includes an integrated control system test that requires a change in power from 48% to 40%, then back to 48%. This test was originally planned for last week but was rescheduled.
- 3. Facility Operations Summary Steady state operation at 48% power continued except as noted below.
- 4. Items of Special Interest NRC Notifications During the period, there were no events that required notification of NRC by the licensee. There were, however, a number of other events of interest and they are discussed below.
Plant Transient On October 25, 1985, electricians were measuring pump vibration signals from a cabinet in the relay room. The workers used a power source on the integrated control (ICS) panel to provide power to the test equipment.
This caused an electrical interference signal with the main turbine electro-hydraulic control (EHC) system. The EHC system tripped to manual and the system closed the turbine stop/ control valves. The plant responded as expected. Turbine header pressure increased to 1035 psig, and two atmospheric dump valves, two turbine bypass valves, and a main steam relief valve were actuated. The operators quickly took manual control of a main feedwater pump and the turbine-generator and stabilized the plant transient. Within an hour, the ICS was placed into automatic control and the plant was returned to steady-state conditions at 48% power.
Radioactive Water Spill in Makeup Pump Room On October 29, 1985, the TMI-1 Restart Staff was informed that a leak of 150 gallons of primary water from the makeup and purification system occurred between 4:20 and 4:30 p.m. on October 28, 1985. At'the time, ENCLOSURE L NOV 1 1985
2
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- licensee personnel were conducting corrective maintenance on a minor leak .
! in one of the three makeup pumps. The pump was isolated by closing valves l on each side to permit depressurization and draining of the pump. Since l
one of the isolation valves leaked, draining of the pump continued for an j extended period of time. A loca1' radiation monitor alanned causing an i evacuation of personnel from the pump cubicle. Escaping radioactive noble i gases caused ventilation process monitors to respond but not alarm.
Licensee personnel reentered the pump cubicle and secured the leak. The licensee estimates that approximately 0.7 Ci of noble gases (primarily Xe-133) were released to the environment and dose calculations indicate -
that the release was a small fraction of regulatory limits. The licensee l conducted a critique of the event. The TMI-1 Restart Staff will review 1
the licensee's followup actions.
! NRC Thermoluminescent Dosimeter (TLD) Monitoring Program The NRC TLDs for the period October 18 - November 1,1985, were collected on November 1 and will be processed at the Region I TLD i
laboratory. The monitoring results will be included in the next weekly i status report. '
i i
Other l The unplanned power reduction that occurred on October 25, 1985, resulted j in the licensee re-zeroing the clock for the 100 consecutive hours above j 35% power needed to place TMI-1 in the rate base. On October 29, 1985, j the licensee announced that as of 3:00 p.m. that day they had satisfied ,
i these requirements, and that TMI-1 would be placed in the rate base pending completion of a 10-day wait after their notification of the qualifying power operation run.
1 i
S. TMI-1 Restart Staff Status During the Period l
1 l The TMI-1 Restart Staff continued 16-hour shift coverage during the
! period. The shifts were manned by personnel from Regions I and II, the
! Reactor Training Center, and by a reactor operator examiner from Battelle
- Pacific Northwest Laboratories, an NRC contractor. Region I startup i inspectors discontinued daily coverage consistent with the reduced testing activity. A Region I reactor engineer was on site during
,! portions of the period to augment the resident inspection staff.
The staff-developed inspection plans, which are now issued bi-weekly, are sufficiently flexible to cover the unique activities conducted by the i Ifcensee. The inspection plan for this period covered the primary functional areas of operations, maintenance, and surveillance. .The shift inspectors assessed operator performance and organizational interfaces on
, each shift. In addition, the resident and region-based inspectors l
followed the various off-normal events identified by the shift inspectors 1
ENCLOSURE L NOV 1 1985 t .
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3 and assisted in the verification of proper procedural implementation during special test evolutions. The TMI-1 Restart Staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee should be permitted to proceed beyond the next hold point at 48% power.
Contact with the press and public continued throughout the period. The Region I Public Affairs Officer (PAO) remained at the Region I office.
We continued to maintain daily contact with the Commonwealth of Pennsylvania during this period.
During the period, the TMI-1 Restart Staff terminated its issuance of daily highlights to the Executive Director for Operations. Future reports will be issued for items of special significance, and a report of the radioactive water spill was included in the daily highlights on October 30, 1985. The third weekly status report for the period October 18-25, 1985, was issued by the TMI-1 Restart Staff on October 28, 1985.
Inspection Report No. 50-289/85-22 was issued on October 30, 1985. One apparent violation was identified for the licensee's failure to properly implement controls for scaffolding in a safety-related area.
- 6. TMI-1 Restart Staff Composition During Period I
The TMI-1 Restart Staff was comprised of the following personnel during the period:
4 W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-1 Restart Manager D. R. Haverkamp, Technical Assistant F. I. Young, Resident Inspector, TMI-1 R. J. Urban, Reactor Engineer N. J. Blumberg, Startup Inspector W. Apley, Shift Inspector, Battelle PNL
, D. P. Falconer, Jr., Shift Inspector, Region II L. J. Reidinger, Shift Inspector, Reactor Training Center T. F. Stetka, Shift Inspector, Region II C. P. Hix, Secretary
. L. M. Prough, Secretary ENCLOSURE L NOV 1 1985
TABLE A
! TMI-I SPECIAL TLD MONITORING RESULTS Station Distance Direction Baseline Field Exposure 10/2/85-10/18/85 (miles) mR/ day mR/ day (Mean + s.d.) (Mean + s.d.; total uncertainty)
Control - 0.14 + 0.01; 0.02 2 3.9 101 0.19 + 0.02 0.19 I 0.005; 0.03 3 2.7 109 0.16 I 0.02
~
0.17 T 0.002; 0.03 4 1.8 163 0.16 T 0.02 0.20 T 0.01; 0.03 5 2.2 161 0.18 T 0.02 0.17 T 0.01; 0.03 6 1.0 150 0.17 7 0.03 0.18 T 0.01; 0.03 7 0.6 136 0.17 7 0.02 0.19 T 0.01; 0.03
, 8 0.4 83 0.16 T 0.03 0.19 T 0.005; 0.03 0.16 T 0.01; 0.02 9 0.5 60 0.16 7 0.02 10 1.7 1 0.14 I 0.02 0.16 T 0.0003; 0.02 11 0.9 25 0.16 I 0.01 0.22 T 0.003; 0.03 l 12 2.8 46 0.16 I 0.02 0.17 I 0.001; 0.03 14 2.5 358 0.14 T 0.02 0.16 T 0.004; 0.02 16 3.1 0 0.14 I 0.02 0.17 I 0.01; 0.03 18 3.5 349 0.17 T 0.03 0.15 7 0.001;0.02 19 3.2 343 0.17 I 0.02 0.18 I 0.02; 0.03 20 5.0 318 0.16 I 0.01 0.18 T 0.01; 0.03 21 1.3 348 0.13 I 0.01 0.18 T 0.01; 0.03 22 3.1 17 0.17 I 0.02 0.18 T 0.002; 0.03 23 3.8 64 0.13 I 0.01 0.14 T 0.01; 0.02 24 3.6 44 0.17 I 0.01 0.19 7 0.01; 0.03 i Control ! 0.15 7 0.002; 0.02 i 34 2.3 267 0.17 + 0.01 0.17 7 0.002; 0.03 35 1.8 299 0.17 I 0.01 TLD MTssing 36 1.2 267 0.12 I 0.02 0.16 + 0.003; 0.02
- 37 1.4 256 0.14 I 0.01 0.16 T 0.0011; 0.02 38 1.9 225 0.18 I 0.02 0.17 T 0.0002; 0.03 39 2.1 200 0.13 T 0.01 0.19 T 0.003; 0.03 1
40 2.5 204 0.16 7 0.02 0.16 7 0.01; 0.02 46 3.0 177 0.14 7 0.02 0.16 I 0.01; 0.02 50 4.9 145 0.1410.04 0.1710.01;0.03 Abbreviations:
mR = millirem s.d. = standard deviation 4
ENa0SURE L NOV 1 1985
10auss is:49 mc REG 1 NO.021 002 _
l* FIGURE 1 THI-1 RESTART TEST PROGRAM STATUS t- .- c.
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, 755 Powan Testina . j g ,
,' (5 navs) a (p 751 Powan l Oranaton TRAINING g Ann Pt. ANT I .
PanFonnAnet
"*"'I**'"'
E.
. (30 pays) 3
( i - W 3 33
- E 1001 Powan itsiina (5 aAvs)
. TunstNt/AAcyon in e .
A g Comatettyt MalwitiAmet/MAnasantit Rt' view (10 thavs) : s .............usmsuum. ems...............j ENCLOSURE L NOV 1 1985
REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT NOVEMBER 1, 1985 Plant Status The plant remains in cold shutdown. The circulating water canal is drained. Decay heat removal loop No. 1 is drained for maintenance. Emergency Diesel Generator No.1 is inoperable due to an inoperable ventilation damper. The diesel firewater pump has been repaired, i i j i i 1 I EllCLOSURE L NOV 11985
- .- -. - - - ~.- - .- . _ - - .- - . - _ -- .. - _ - - - - . _ - - - . . . - . - _ - . - . . - . . -. - A. Region III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMD OF AUGUST 5, 1985
- 1. Item: Adequacy of the licensee's management and maintenance activities t
=
E ACTION SlRTUS/C0fetENTS , (b) Evaluate and take action on the Region III is observing maintenance activities and evaluating !
@ licensee's response to findings LER's, DVR's and other items as they relate to the control of ,
- concerning management practices maintenance. A maintenance survey team inspection conducted- ;
(e.g., control of maintenance on September 16-20, 1985 confirmed previous concerns identified programs and post-trip reviews). by Region III. A followup team inspection is planned for early ! 1986. DRP in conjunction will DRS will assess management ; practices prior to restart.
- 6. Item: -Reliability of the AFW containment isolation valves and other safety-related valves ACTION STATUS /C0fetENTS (a) Monitor the licensee's trouble- Troubleshooting activities related to containment isolation [
shooting activities valves AF599 and.AF608 are complete. Region III specialists [ are evaluating and monitoring MOVATS testing on other safety- i related motor operated valves. About 50% of 166 valves have i been completed. ;
'(e) Determine that the procedures for Limitorque operators for valves AF599 and AF608 have been adjustments of the AFW isolation adjusted and the valves have been tested under dp conditions. i valves such as torque switch bypass Confirmatory testing will be performed during startup.
switches are clear and proper, and l that associated training programs are adequate. Confirm that adjustment : settings are consistent with plant ; procedures, i E n t i 2
- 7. Item: Adequacy of emergency notifications ACTION STATUS /C00MENTS
, w Q (a) Verify the adequacy of the licensee's Investigation of the adequacy of the licensee's procedures
= procedures and training for the report- and training for the reporting of events to the NRC ing of events to the NRC Operations Operations Center has been completed. One violation of NRC Center. requirements was found. Inspection results are documented in Inspection Reports 85023 and 85034.
- 8. Item: Reliability of AFW pump turbines ACTION STATUS /C0pmENTS (a) Monitor the licensee's trouble- Troubleshooting activities are complete. Region III shooting activities including will monitor confirmatory testing during plant startup possible hot plant operation to as part of startup test activities.
1 confirm failure mode. (d) Verify that the AFW system has been Results of test review group meetings have culminated adequately tested to confim system in the development of a charter outlining test review group i configuration involved with design responsibilities and activities. basis events. l (e) Review the implementation of the The licensee is developing a training program on resetting operator training program to assure of the trip throttle valve. This training will include proper operator actions, such as resetting of trip mechanism at operating conditions, . resetting of trip throttle valve. therefore, the training will be completed during plant ' restart.
- 9. Item
- Reliability of the PORY ACTION STATUS /C00mENTS (a) Monitor the licensee's trouble- Troubleshooting activities have been completed. Confirmatory shooting activities testing will be conducted at operating temperature and pressure. Additional research test data has not been provided g to the licensee.
1 5 ! i E m 3 r-i
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- 12. Ites: Resolution of equipment deficiencies y ACTION STATUS /COMENTS All the Re.gion III activities relative to
" (a) Monitor the licensee's trouble- troubleshooting / root cause activities have been shooting activities completed and are documented in Inspection Reports 5
- 85-021, 85-022 and 85-025.*
l
- Inspection Report 85025 is in draft and will be issued in approximately 2 weeks .
l l l l l l I I P S
!ii m 4 r-
Other Activities The new electric motor driven startup feedwater pump (SUFP) is in place. Installation of pipe and valves is about 90% complete. Conduit installation,
; cable pulling and wire termination is in progress. The old SUFP has been electrically disconnected and it's discharge piping is no longer connected to the feedwater system.
Evaluations and inspections of safety system piping supports are continuing. Nonconformance Reports (NCRs) have been written against 1370 of 1515 pipe supports inspected so far. Inspection of individual supports has been 4 suspended to allow the inspection teams to concentrate on verifications of locations of a sample group of piping supports. The licensee's engineering department has received 1261 NCRs for evaluation. Rework is required on 103 of the 776 supports that have been evaluated. There are 16 licensee inspection teams on this project. MOVATS testing continues on the 166 safety-related motor-operated valves on site. Eighty seven valves have been tested, a few of these will require 4 retesting. Beginning next week the licensee will test continutously with three overlapping ten hour shifts. During funtional testing of snubbers (required by Technical Specifications) 3 three snubbers did not meet test acceptance criteria. Technical Specifications now require the removal and functional testing of thirty j additional snubbers. Planned Meetings Scheduled meeting with NRR to discuss licensees activities relating to SFRCS-November 4,1985. Planned Special Inspections and Evaluations Special team inspection to review licensee activities regarding hangers and supports-November 13-22, 1985. 4 N0y ENCLOSURE L , 1 1985 5
4 . 4 ITEMS ADDRESSED BY THE COPWISSION - WEEK ENDING NOVEMBER 1. 1985 i i
- A. STAFF RECUIREENTS - DISCUSSION WITH EPA. ADVISORY COPMITTEE ON REACTOR l 5AFEGUAR[5 AM) STAFF ON EPA STANDARD FOR H .W. 1:30 P.M.. 40N)AY. OCTOBER 21o
- 1985. COPM SSIONERS' CONFER ENCE ROOM. D.C. OFFICE (OPEN TO PU H.IC AlitNDANCE?
l Memo SECY to RECORD dated 10/29/85 2
, The Concission met with representatives of the Environmental
} Protection Agency .(EPA) , the Advisory Committee on Reactor i Safeguards (ACRS), and staff to discuss EPA's environmental l standards for the management and disposal of high-level radio- , { active waste. Representatives of the Department of Energy also i took part in this meeting. I In addition to NRC staff, the following individuals participated in.this meeting: , l Sheldon Meyers, Acting Director
; office of Radiation Programs ,
j EPA I Terry Yosie, Director i EPA Science Advisory Board i
- Floyd Galpin, Chief j Waste Management Standards Branch Criteria and Standards Division l Office of Radiation Programs l l EPA I
I Daniel Egan, Health Physicist Waste Management Standards Branch Criteria and Standards Division office of Radiation Programs EPA l Dade Moeller ACRS William Purcell, Associate Director 2 Office of Geologic Repositories l ME ) Ralph Stein, Acting Director j Engineering'and Licensing Division i Office of Civilian Radioactive Waste Management. { ME f Chairman Palladino requested Commissioners to reexamine their ' ! vote sheets on SECY-85-272 and inform the Office of the Secretary l as to their present position on this paper. . (OCM) l (SECY Suspense: 10/30/05) [ ENCLOSURE O ! NOV 11985
1 q l 3 l B. STAFF REQUIREMENTS MEMORANDUM - AFFIRMATION / DISCUSSION AND VOTE.11:30 A.M., THURSDAY, OCTOBER 24, 1985r COMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE? Memo SECY to H. E. Plaine dated 11/1/85 i I. SECY-85-34B - Policy Statement on Confidentiality i The Commission, by a 5-0 vote, approved the policy statement as modified in the attached copy. You should revise the statement as indicated and return it for signature and publication in the Federal Register. (OGC) (SECY Suspense: 11/15/85)
Attachment:
- Ne enclosed As stated 4 i ) I l l ENCLOSURE O NOV 1 1985 l l l l
E W US NRR MEETING NOTICES *
- E NOVEMBER 1, 1985 J
DOCKET APPLICANT / l DATE/ TIE NUMER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/4/85 50-346 P-114 Technical discussions on Toledo Edison Co. A. De Agazio 1:00 pm Bethesda short and long-term in- (Davis-Besse)
) provement to AFWS and SFRCS t 11/4/85 50-280 P-118 To discuss integrated Virginia Elect & T. Chan 9:00 am 50-281 Bethesda living schedule and Reg. Power 3 Guide 1.97 schedule re Exit Core Thermocouples upgrade at Surry 1
11/4-5/85 50-275/323 P-110 Discuss Inservice Testing Pacific Gas & Elec H. Schierling 9:00 am Bethesda (Diablo Canyon) j' 11/5/85 50-483 P-118 To discuss proposed modifi- Union Electric T. Alexion 9:30 am Bethesda cations to the LTOP system j at Callaway 11/5/85 50-445 Plantation Inn Monthly Status Meeting on Texas Utilities A. Vietti-Cook 8:30 em 50-446 Granbury, Texas Comanche Peak 11/6/85 P-422 Technical Specification NRC Personnel R. Each 9:00 am Bethesda Improvement Project 0 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 P o i N i
E
- s l
g NRR MEETING NOTICES
- DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION _ PURPOSE ATTENDEES NRR CONTACT 1 l 11/6/85 50-443 PSNH Seabrook To discuss Power Systems Nblic Service Co. V. Nerses 10:00 am 50-444 Off., Suite 1309 Branch Review of Associated of New Hampshire 7910 Woodmont circuits Bethesda 1 11/6-7/85 50-275/323 AR-5033 Discuss status of licensee's Pacific Gas & Elec. H. Schierling . 9:00 am Bethesda Detailed Control Room Design Review 11/6/85 50-282 P-422 Information exchange meeting Northern States Power D. Di Ianni i 1:00 pm , 50-306 Bethesda to establish reliability of auxiliary feedwater system ) at Prairie Island ; 11/6/85 50-390 P-422 Briefing by TVA on structural TVA B. Long ]12:00 Noon 50-391 Bethesda welding program and related
- employee concerns l
- 11/7/85 50-440 Perry Site To determine readiness for Cleveland Elec. Ill. J. Stefano
' 9:00 am Perry, Ohio a low power operating Co.
- license 11/12/85 P-110 To discuss auxiliary actuating Vortech F. Cherny 1 10
- 00 am Bethesda devices for PWR Safety Valves
- which have been proposed for use in France 11/13-14/85 50-247 Reg. I Office To discuss Inservice Testing Consolidated Edison M. 51ossen 9
- 00 am King of Prussia, Program for Indian Point 2 PA 4
Copiss of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms. ! E P ! 8 i si m
"O
NMSS MEETING NOTICES ' me FOR WEEK ENDING: 11/1/85 SE Division of Fuel Cycle and Material Sarcty . ea ATTENDEES / DOCKET Q LOCATION PURPOSE APPLICANT NRC CONTACT m DATE/ TIE NUtBER 70-371 Willste To discuss draft license aiaendment T. Gutman (UNC NP) Bidinger 10/31/8S G. Bidinger (FC) SNM-368, UNC Naval Products. Baltimore, Presentation at Johns Hopkins R. Cunningham (FC) Cunningham 11/19/85 8:30 am MD University - Seminar on Low-Level Waste - Under the auspices of CARER. , DIVISION OF WASTE MANAGEMENT None , DIVISION OF SAFEGUARDS None o
. 1 o
P 8 m "O
. se .
SE o ra IE MEETING NOTICES sen ATTENDEES / DOCKET . PURPOSE APPLICANT NRC CONTACT
'DATE/ TIME NUMBER LOCATION ACRS Brief ACRS Subcommittee on Reactor IE E. L. Jordan 11/4/85 Operations regarding recent signi- NRR ficant operating events at nuclear power plants.
ACRS Brief full ACRS regarding recent IE E. L. Jordan 11/7/85 significant operating events at NRR nuclear power plants. i 4
~
i 8 1 s;-
+
i
e. o E RES MEETING NOTICES November 1,1985 g 5 m DOCKET ATTENDEES / LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME NUMBER NL-014 To review draft report, NUREG/CR-4349, Schurman, INEL Au 11/6-7/85 Methods for Evaluating Alternative Bongarra, NRR Techniques and Fonnats for Presenting Goodman, NRR Procedures in NPPs P-514 To discuss seismic risk Reiter, NRR Abramson 11/4/85 Sobel,NRR 1 1 P 8 ' E i T
t L
.c AE00 MEETING NOTICES g$ November 1, 1985 m
LOCATION PURPOSE ATTENDEES NRC CONTACT DATE/ TIME River Bend-1 To collect and dis- Peter Lam (AE0D) Peter Lam 11/13/85 8:30 a.m. cuss information on Stuart Rubin (AE00) reactor vessel level - transient that occurred
- on 9/23/85.
EWS-257 Technical exchange of INPO, AE00, NRR, IE K. Seyfrit ! 11/26/85 8:00 a.m.- information on 5:00 p.m. operating events and data, i e 1 l [ 4 i E P 5: Si m 73 )
( ji Ncvember 1,1985 ; (( RII MEETING NOTICE
?N DOCKET ATTENDEES /
NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME 11/4 Atlanta, GA Meeting with Georgia Power Deputy Regional Adm., R. Walker 1:30 pm (GPA Corporate Company to discuss the R. Walker, and other Office) results of the SALP for RII Staff members and Plant Hatch and Plant the Licensee Vogtle. 11/5 Region II Office Meeting with Carolina Licensee and selected A. Gibson 9:30 am Power & Light Company to RII Staff members discuss Shearon Harris Appendix R Fire Protection Program. 11/8 Region II Office Meeting with Georgia Power Licensee, NRR, IE, R. Walker 10:30 am Company regarding crack and selected RII 4 found in nitrogen injection Staff members line at Plant Hatch on 12/15/84. i n to C
i l l ~ 9 . 2 ,.-
# REGION III REETING NOTICES ,
l 4 e WEEK ENDING: Noves6er 1, 1985
, h DOCKET ATTENDEES /
NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME ! Glen Ellyn, IL Enforcement Conf. J.G. Keppler & staff J.G. Keppler 11/13/85 50-315 50-316 D.C. Cook Jnd.Mich. Elec. l 10 a.a . Glen Ellyn, IL Enforcement Conf. A.B. Davis & staff A.B. Davis
! 11/19/85 50-10 Dresden Connonwealth Edison i 1 p.a. 50-237 50-249 50-254 Quad Cities 1
50-265 Glen Ellyn, IL Enforcement Conf. J.G. Keppler & staff J.G. Keppler 11/22/85 50-454 50-455 Byron Connonwealth Edison 1pa 50-373 LaSalle 50-374 1 4 O
. e Z
P i i 8 C i
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