ML20135C942
| ML20135C942 | |
| Person / Time | |
|---|---|
| Issue date: | 09/11/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-850906, NUDOCS 8509130076 | |
| Download: ML20135C942 (34) | |
Text
.
PIM September 11, 1985 For:
The Commissioners T. A. Rehm, Assistant for Operations, Office of the EDO From:
WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 6, 1985
Subject:
A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Enclosure Contents A
Administration B
Nuclear Reactor Regulation C
Nuclear Material Safety and Safeguards D
Inspection and Enforcement E
Nuclear Regulatory Research F*
Executive Legal Director G*
International Programs H
State Programs I*
Resource Management J
Analysis and Evaluation of Operational Data Small & Disadvantaged Business Utilization & Civil Rights K*
L*
Regional Offices M*
CRGR Monthly Report l
N*
(
Executive Director for Operations l
0*
Items Addressed by the Commission
[
P Meeting Notices Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
/
T. A. Re
, nas;;;. fTor Operations
%913006850911 l
C Office of the Executive Director i
WEEKLYINFOR for Operations
Contact:
T. A. Rehm, E00 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING SEPTEMBER 6, 1985 Arkansas Nuclear One, Unit No. 1 I
At 7:10 AM CDST, August 28, 1985, a slightly opened 3/4" drain line valve from the reactor coolant system (RCS) let down system released approximately 500 gallons of reactor coolant (RC) into a containment piping penetration room which is located in the Auxiliary Building.
This resulted in air-borne contamination in the Auxiliary Building and an offsite release of 0.15 Maximum Permissable Concentration (MPC) at the site boundry. The area monitors in the Auxiliary Building first gave an indication of the release plus the operators noted the lowering
~
of the RCS makeup tank level. The piping penetration room was flooded j
with several inches of RC. An operator was contaminated upon enterino the room and closing the valve. Another operator was slightly contaminated when he went to assist the first operator. A total of six people were in the Auxiliary Building at the time. All have been examined for contamination and decontaminated as necessary. The plant was at 100% power at the tima. The licensee has no explanation for the valve being opened at this time but believes that the opening of the valve could be caused by vibration.
Hope Creek Generating Station On September 4, 1985, an inadvertant actuation of the C0 fire suppressionsystemoccurredinoneofthefourdieselge$eratorfuel2 oil storage tank rooms at Hope Creek. Twenty-three people were taken l
to nearby hospitals for treatment. Of thenc twenty-three, one was listed in " serious" condition upon arrival; howw er, his condition is I
now listed as " guarded". These men were not in the tank room at the j
time of the actuation. Overpressurization of the room caused seepage of CO around the room door and fire dampers inte adjacent areas where them$nwereworking. The cause of the actuatica is unknown. The system is designed to inject a 2-ton " burst" of C0 irto the room;-
however,- during the event a continuous discharge o$ curred, injecting approximately 10 tons of CO,.
PSE&G and OSHA are investigating the incident. On September 3, 1985, Hope Creek received the first shipment of fuel onsite. Fuel delivery will conclude by the end of the month. PSE&G's fuel load date continues to be December 1, 1985.
Three Mile Island, Unit 1 (TMI-1)
On Tuesday, August 27, 1985, the 3rd U.S. Circuit court of Appeals issued a judgement that denied the petition for review of the Commission's decision lifting the immediate effectiveness of the 1979 shutdown order on TMI-1 and affirmed the Connission's Order CLI-85-9, May 29, 1985. On Thursday, August 29, 1985, the Panel ordered that the existing stay is to remain in effect until disposition of motions for rehearing. No extensions of time will be permitted, i.e., parties seeking rehearing have until September 10 to file.
The plant is in Hot Shutdown (subcritical at operating temperature and l
pressure) and physically ready for restart on August 21, 1985.
i The plant experienced a partial loss of Non-Nuclear Instrumentation when an operator pulled out a strip chart recorder to review the trend readings and cable insulation failed causing a ground-short.
Instrumentation was restored within 60 minutes. Corrective actions SEP 6 1985
___related to this event are not expected to delay plant restart.
OFFICE OF ADMINISTRATION Week Ending September 6,1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 620 38 Granted 489 26 Denied 132 14 Pending 178 21 l
l ACTIONS THIS WEEK Received 4
Urban K. Jonson Requests records regarding technology of nuclear power (85-608) reactors and proper universities and merit scholarships for nuclear physics and nuclear engineering.
And'rew Fischman, Requests copies of all records related to an application Charles E. Simon submitted by Mars, Inc., for use of an air-irradiation and Company process for the sterilization of pet food at a new Ka1Kan (85-609) pet food processing facility.
i Hal B. Tucker, Requests applications for Senior Reactor Operator Duke Power Company licenses filed subsequent to the operating license for (85-610) 19 specified plants and requests for waivers from experience requirements of section A.1 a of enclosure 1 l
of H.R. Denton's March 28, 1980, letter or NUREG-1021 for such applications.
Richard Webb, Requests 14 specified records.
Studies of Nuclear Hazards and Constitutional Law (85-611) l M.A. Mathews, Requests a co'py of the report entitled, " Civilian General Electric Enrichment Requirements Program."
(85-612)
I Billie P. Garde,
_ Requests all records'related to the inspection /.
Government investigation of allegations regarding Nine Mile I
Accountability Point by John Ryan, Rudolph Nonnan and Anthony Laratta.
Project (85-613)
CONTACT:- J. M. Felton ENCLOSURE A 492-7211' SEP 6123
2 Received, Cont'd Billie P. Garde, Requests all records related to the staff's Government determination of the applicant's potential material Accountability false statement on U-Bolt sample (BN 85-077) regarding Project the Comanche Peak nuclear power plant.
(85-614)
Sylvia Lenoff, Requests copies of contracts NRC-10-81-359, Procurement Market NRC-10-84-211, NRC-25-82-315, and NRC-33-85-322 Research i
(85-615)
Michael S. Terpilak, Requests four categories of records regarding byproduct t
Nucleon Lectern material license number 37-20826-01 issued to Alaron Associates Inc.
Corporation.
(85-616)
Teresa S. Barnhart, Requests a list of employees in the Office of NTEU Steward Administration who received awards from January 1, 1984, (85-617) through September 1, 1985.
Frank Tankersley, Requests a list of Reactor Operators.
Frank Tankersley Associates, Inc.
(85-618)
James F. Pierce, Requests records regarding Mr. James Neel and/or Environmental Mr. David Gravely in their association with PyroChem, Task Force Inc.; Nuclear Engineering, Inc.; and U.S. Ecology, Inc.,
(85-619) relating to the Maxey Flats nuclear disposal site in r
Hillsboro, Kentucky, and Sheffield, Illinois.
James H. Shumock, Requests a list of the firms that bid on Proposal No.
Thompson RS-01E-85-157.
Engineering Testing, Inc.
i (85-620) l Steven Aftergood, APPEAL TO THE ED0 for the release of 15 denied records Committee to regarding the proposed rule for limiting the use of Bridge the Gap highly enriched uranium in research and test reactors.
(85-A-36-85-379)
Steven Aftergood, APPEAL TO THE ED0 for a waiver of fees regarding his Committee to reouest for records concerning the proposed rule for Bridge the Gap limiting the use of highly enriched uranium in research (85-A-37-85-379) and test reactors.
Jim Thomas, APPEAL TO THE ED0 for the release of three denied NTEU President records relating to theft of NRC equipment.
(85-A-38-85-509) i ENCLOSURE A SEP o1985 b
o
3 Granted Martin Levy, In response to a request for records regarding the NTEU Chief Steward rules for obtaining free parking at the Nicholson (85-504)
Lane Building or all records used in the past by NRC management in determining the allocation of free parking spaces, and records which have changed the rules, made available 21 records.
John Morley, In response to a request for four categories of records Governor's Task regarding high-level radioactive waste disposal, made Force on High-available four records.
Level Radioactive Waste (85-539)
T.P. Bracke, In response to a request for a copy of the nonproprietary Combustion version of Exxon Nuclear Report, XN-NF-739 concerning Engineering, Inc.
seismic evaluation of nuclear fuel, informed the (85-540) requester that the entire report contains confidential business (proprietary) infomation and no nonproprietary version exists.
Cindee Virostek In response to a request for two categories of records (85-555) regarding Babcock _& Wilcox facilities in Pennsylvania, made available 18 records.
Infomed the requester that additional records subject to this request are already available at the PDR.
Dona DeZube.
In response to a request for copies of correspondence Montgomery County the NRC has received from Representatives Barnes and Sentinel Byron and Senators Mathias and Sarbanes during the past (85-564) two years, made available 19 records.
Steven Aftergood, In response to a request for copies of records related to Committee to the February 1985 meeting between NRC representatives and Bridge the Gap representatives of the Israeli Energy Commission, made (85-579) available seven records.
l David A. Repka, In response to a request for records relating to NRC's Bishop Libeman, policies for waiver of fees under the F0IA, made Cook, Purcell available one record.
l and Reynolds (85-580)
I Donald Pay.
In response to a request for copies of records since Technical January 1,1985, concerning the low-level radioactive Information waste disposal in South Dakota and agreement state status Project for South Dakota, made available nine records.
Informed (85-583) the requester that he may wish to contact the Chem-i Nuclear Systems, Inc. for a 1983 videotape about low-level radioactive waste.
ENCLOSURE A SEP 61985 E
4 Granted, Cont'd Sandra Swan Travis, In response to a' request for copies of responses to Data -Services the NRC's Request for Quotation No. 503155 for (85-588) storage space for various irformation media in the Washington, DC, metropolitan area, made available three records.
Steven Aftergood, In response to a request for a copy of a report prepared Committee to by the Office of Inspector and Auditor entitled, " Review Bridge the Gap of NRC's Quality Assurance P*ogram for Reactors Under (85-603)
Construction," informed the s equester that this report is already available at the PDR.
Urban Jonson In response to a request for records regarding technology (85-608) of nuclear power reactors and proper universities and merit scholarships fur nuclear physics and nuclear engineering, made available five records.
Denied Lyle Graber.
In response to a request for a copy of SECY-85-103, NUS Corporation denied portions of this paper, release of which would (85-562) tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
1 ENCLOSURE A SEP _61985 r
I WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING SEPTEMBER 6,1985 IFB ISSUED i
IFB No. : RS-ADM-86-211
Title:
" Newspaper Clipping Services"
==
Description:==
The contract is required to assist and support the NRC's Library Branch in the gathering and clipping of news articles relevant to.the NRC mission, on a local and national basis.
Such clippings snall be used in preparation of the NRC Media Monitor, a daily distributed publication.
Period of Performance: 2 years Sponsor: Division of Technical Information & Document Control Status: IFB issued on August 26, 1985. Bids due on September 26, 1985.
i PROPOSAL UNDER EVALUATION l
t t
RFP No. : RS-NMS-85-009
Title:
" Technical Assistance in Hydrogeoiogy - Project B - Analysis"
==
Description:==
The contractor shall provide technical assistance to the i
NRC in its review of DOE site investigations for a potential High Level Waste geologic repository.
Period of Performance: _ 2 years with 3 one-year options Sponsor: Office of Nuclear Material Safety and Safeguards Status: Best and Final offers received on September 4,1985, and forwarded to Source Evaluation Panel for review on September 4,1985.
CONTRACT AWARDED i
RFP No. : NRR-85-051 l
Title:
" Technical Specifications Review and Reactor Transient Computer Code Input"
==
Description:==
Provide a systematic evaluation of equipment requirements in six operational modes and investigate current NRC analytical capability for reactor system transients in 1
nuclear plants and upgrade this capability for BWR's.
Period of Performance: '15 months Sponsor: Office.of Nuclear Reactor Regulation Status: Cost-Plus-Fixed-Fee contract awarded to SBA/Scientech, Inc. in the amount of $196,200, effective September 3,1985. This firm has been certified by the.Small Business Administration as a socially and economically disadvantaged firm eligible for l
noncompetitive awards under that agency's 8(a) program..
i CONTRACT CLOSED-0UT NRC-10-83-318 Literature Research Corp.
1 ENCLOSURE A SEP 6 1985 l
._,,-.u..
- 1
J 0FFICE OF NUCLEAR REACTOR REGULATION 4
ITEMS OF INTEREST Week Ending September 6, 1985 Comanche Peak 1 and 2 On August 29, the Licensing' Board issued a memorandum and order which
[
declined to adopt, at this time, the Texas Utilities Electric Company proposal to litigate its corrective action plan to resolve all remaining issues prior to its execution.
It also denied the applicant's request to declare intimidation and harassment issues moot.
In addition, the Board provided its preliminary, non-binding j
comments on aspects of_the corrective action plan and the future course for the proceeding.
In effect, this means that the Board is likely to litigate both previous old issues as well as the applicant's corrective action plan and its implementation.
The Board stated that it is difficult to forecast when-hearings in the case will be concluded.
V. C Sumer Nuclear Station Unit 1 l
Temporary construction strainers were found in both containment spray pump suction lines. They are now removed and an evaluation of system operability with the strainers installed is being performed. A record review of all other ECCS systems indicates that their temporary construction strainers were removed.
l Also, an STA found that the over>ower-delta i trip setpoint was not responding correctly. This was )ecause permanent jumpers that are supposed to be installed in the OP-delta T card were not. This condition has existed since licensing.
1.
l Finally, an STA found that both RHR systems were inoperable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l
last week, while the plant was heating up in Mode 3.
A special unannounced inspection will be conducted next week _by Region II due to these events.
Arkansas Nuclear One, Unit No. 1 l
At 7:10 AM CDST, August 28, 1985, a slightly opened 3/4" drain line.
valve from the reactor coolant system (RCS) let down system released approximately 500 gallons of reactor coolant (RC) into a containment i
piping penetration room which is located in the Auxiliary Building.
This resultad in' air-borne contamination in the Auxiliary Building and l
an offsite release of 0.15 Maximum Permissable Concentration (MPC) at the site boundry. -The area monitors in the Auxiliary Building first gave an indication'of the release plus the operators n-ted the 1c.werir.g l
of the'RCS makeup tank? level. The piping penetration rcom was flooded ENCLOSURE B with several inches of RC. An operator was. contaminated upon entering t
SEP 6 1985 j
l 1
1-
_2_
1 i
the room and closing the valve. Another operator was slightly j
contaminated when he went to assist the first operator. A total i
of six' people were in the Auxiliary Building at the time. All l
have been examined for contamination and decontaminated as necessary. The plant was at 100% power at the time. The licensee has no explanation for the valve being opened at this time but believes that the opening of the valve could be caused by vibration, j
)
Three Mile Island, Unit 1 (TMI-1) t On Tuesday, August 27, 1985, the 3rd U.S. Circuit court of Appeals issued a judgement that denied the petition for review of the l
Commission's decision lifting the immediate effectiveness of the 1979 shutdown order on TMI-1 and affirmed the Commission's Order CLI-85-9, May 29, 1985. On Thursday, August 29, 1985, the Panel ordered that the l
existing stay is to remain in effect until disposition of motions for i
rehearing. No extensions of time will be permitted, i.e., parties
}
seeking rehearing have until September 10 to file.
l The plant is in Hot Shutdown (subcritical at operating temperature and
}
pressure) and physically ready for restart on August 21, 1985.
i The plant experienced a partial loss of Non-Nuclear Instrumentation I
when an operator pulled out a strip chart recorder to review the trend readings and cable insulation failed causing a ground-short.
j Instrumentation was restored within 60 minutes. Corrective actions t
related to this event are not expected to delay plant restart.
j River Bend Station i
At 3:30 a.m. on August 31, 1985, Gulf States Utilities (GSU) began f
loading fuel at River Bend Statien (RBS). As of the morning of-ll September 3. 1985, 92 out of a total of 624 bundles had been loaded, GSU currently projects completion of fuel load by September 13, 1985, with initial criticality by September 20,.1985. RBS received its low i
' power. operating license from NRR on August 29, 1985 Arkansas Nuclear One, Unit 1
[
t At 6:04 P.M. on September 2, 1985,-ANO-1 tripped on Reactor Coolant I
.-System high pressure as a result of a trip of "B" Main Feedwater Pump 1
(WWP). A broken shaft in the WW turbine governor assembly caused the-l WWP to trip on an overspeed' condition. The "A" WWP remained in
~
operation. All systems performed their desired functions'in the required manner. The Emergency Feedwater System was not required to.
operate and no manual initiations of the safety systems were required.
1985.
~
The unit went critical again at 3:03 A.M. on September 3, j
i ENCLOSURE B l
4 SEP
'6 1985 j
j
Point Beach Nuclear Plant, Units 1 and 2 4
On August 26, 1985, Wisconsin Electric Power Company filed a request before the Consnission for extension of the deadline -for final environmental qualification of Crosby Lift Indicating Switch Assemblies (LISAs) installed at Point Beach Nuclear Plant, Units 1 and 2.
These assemblies provide pressurizer safety valve position indication to control room operators.
The licensee has requested an extension until the e.nd of the respective 7
1986 refueling outages for each unit in order to modify the assemblies 4
as determined necessary by the qualification testing program. These November 1986 (Unit 2) planned to end in May 1986 (Unit 1) and in outages are currently Perry-By Order dated September 3, 1985, the Atomic Safety and Licensing Board for Perry issued a favorable partial initial decision whien will enable issuance of licenses to CEICO for the operation of Perry Units 1 and j
2.
This Order pertains to the emergency plans, TDI diesel generator reliability and hydrogen control-contention issues litigated at i
hearings held in April /May 1985. The Board's decision is predicated on a number of conditions which must be satisfactorily demonstrated to NRR
{
by CEICO prior to the issuance of the o>erating license. The j
conditions are not expected to impact tie current licensing schedule i
for Perry Unit 1.
i Hope Creek Generating Station i
fire I
On September 4, 1985, an inadvertant actuation of the C0 suppressionsystemoccurredinoneofthefourdieselge$eratorfuel2 I
oil storage tank rooms at Hope Creak. Twenty-three people were taken 1
to nearby hospitals for treatment. Of these twenty-three, one was listed in " serious" condition upon arrival; however, his condition is L
now listed as " guarded". These men were not in the tank room at the l
time of the actuation. Overpressurization of the room caused seepage of-C0 around the room door and fire dampers into adjacent areas where 7
l the men were working. The cause of the actuation is unknown. The system-is designed to inject a 2-ton " burst" of CO,into the room; however, during the event a continuous discharge occurred, injecting approximately 10 tons of CO. PSE&G and OSHA are investigating the i
2
-incident.
On September 3, 1985, Hope Creek ~ received the first shipment of fuel t
r onsite. Fuel delivery will conclude by the end of the month.- PSE&G's fuel load date continues to be December 1, 1985.
l
-ENCLOSURE B i
SEP 6 1985
. 1 Diablo Canyon Unit 2 RCP Failure On August 31 a Unit 2 reactor coolant pump failed while in Mode 3 (suberitical) as a result of failure of the motor winding. The cause for failure is under investigation. The motor is being removed offsite power testing program (pects a delay of about 6 weeks in the Unit 2 lo for rewinding. PG&E exthe Unit has not yet exceeded 5% power level).
Unit 1 is currently operating at 100% power level.
Sequoyah Nuclear Plant, Units 1 & 2, Browns Ferry Nuclear Plant, Units 1,z, and 3, Watts Bar Nuclear Plant, Unit 1 TVA has confirmed that Mr. C. Mason has left his position at the Wolf Creek Nuclear Station to serve as TVA's Manager of Operations for Nuclear Power. He will be responsible for the operation of TVA's five operating units and for the licensing of the Watts Bar Nuclear Plant, Unit 1.
l P
i i
i ENCLOSURE B
.SEP 6 1985 i
NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING SEPTEMBER 6, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to th 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 oftheplenum).
The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).
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 91*F with an average of 80*F. Average cold leg temperature is 53*F.
The average reactor building temperature is 59'F. The reactor building airborne activity is 9.6 E-9 uCi/cc Tritium and 3.8 E-10 uCi/cc particulate, predominantly Cesium 137.
2.
WASTE PANAGEMENT The Submerged Demineralizer System (SDS) was shutdowr during this period.
EPICOR II began processing the 61,000 gallon batch from CondensateTank1A(C0T-1A)onSeptember6,1985.
-Total volume processed through SDS to date is 2,963,375 gallons, and the total volume processed through EPICOR II is 2,547,671 gallons.
l ENCLOSURE B
[
SEP 61985 l
l
1.
2 About 61,000 gallons of water had been transferred from COT-1A to l
CCT-1 in preparation for processing through EPICOR II. After an i
additional batch is transferred, COT-1A will be desludged and used for storage of borated makeup water.
3.
DOSE REDUCTION /DECONTAMINA1 ION 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 j
305' level of the reactor building.
4.
ENVIRONMENTAL MONITORING 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 the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from August 17 to August 24, 1985. Gamma scans detected no reactor related radioactivity..
The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consists of a 4
seven day composite sample taken from August 18 to August 24, 1985.
A ganna scan detected no reactor. related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI Site collected a sample'between August 29 and September 4,1985. No reactor related radioactivity was detected.. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
5.
REACIOR BUILDING ACTIVITIES Work continued on installation of the north end platform and the defueling tool racks.
Defueling Water Cleanup System preoperational testing continued.
Installation of cable tray shielding is in progress.
Work continued on staging of reactor building sump recirculation-system components into the building.
System testing is in progress.
6.
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 late September.
The third of four canister storage racks is onsite with the remaining rack scheduled for delivery by mid-September.
Inspection and repairs to cracked welds in the racks is currently under evcluation. -(See Section 8 - Defueling Preparations)
ENCLOSURE B SEP 61985
3 7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.
Recovery Operations Plan Change numbers 29, 31, and 32.
Fuel Canister Technical Evaluation.
Defueling Safety Evaluation.
Application for seismic exemption.
SDS Technical Evaluation and System Description Update Core Stratification Sample Safety Ev&luation Recovery Operations Plan (ROP) Change No. 30 which implements R0P Change Request No. 24 was issued September 3, 1985.
8.
DEFUELING PREPARATIONS The licensee's integrated schedule for the TMI-2 project shows initial defueling beginning in October 1985. Delivery of several key defueling system components has been delayed and could impact the defueling schedule.
Initial delivery of defueling canisters was scheduled for Jul This schedule has been delayed due to Quality Assurance (QA) y 1985.
problems at the canister vendor.'s facility. The vendor is Nuclear Energy Services Manufacturing (NES) located in Greensboro, North Carolina. A report of an NRC inspection at the facility, issued on July 26, 1985, identified specific QA problems which require corrective action. NRC approval of the licensee's planned use of the defueling canisters is contingent upon satisfactory resolution of vendor QA problems.
Delivery of the fuel canister transfer shields has been delayed due todifficultiesatthevendor's(NES) facility. A portion of one shield was dropped in July during its construction and the component was scrapped because of the damage and had to be refabricated.
- Delays as a result of the programmatic QA deficiencies noted above have also occurred. One of the two shields was delivered this week, the other is scheduled for delivery the week of September 9,1985.
This is about one month behind the original projected schedule.
Delays have occurred in the delivery of fuel canister storage racks for the Fuel Handling Building. A temporary hold was placed on the racks during their fabrication at NES because of programmatic QA problems noted above. Three of the four racks have since been l
delivered to the TMI site.
Inspections by GPU personnel identified cracks in several structural welds in two of the racks. GPU has attributed the cracking to fatigue failure due to transportation induced vibrations during shipping.
Further inspections and. repair of the racks is in progress at the site. The fourth rack is scheduled for delivery in the near future.
Installation of the racks in the "A" spent fuel pool was origir, ally scheduled for late August.
ENCLOSURE B SEP 61985
4 i
NRC licensing review of the proposed fuel shipping cask is in progress.
The license application for the NUPAC-125B cask, which is designed to withstand transportation accidents, was submitted in June.
Initial NRC review of the application identified issues relating to the structural and criticality analyses of the package.
Resolution of the technical issues is in progress and is not expected to have a significant impact on the fuel shipping schedule.
However, commencement of defueling is contingent upon resolution of The li' ensee currently. projects the these transportation issues.
c first fuel shipment to occur in March 1986.
9.
_PUBLIC MEETING-The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 11, 1985. The meeting wili be at the Environmental Matters Committee Room (Room 160), House Office Building, College Avenue, Annapolis, Maryland from 6:00 to 9:00 PM. The purpose of the meeting is to inform the public of progress being made in the TMI-2 cleanup and to allow the public to voice concerns and make comments on any aspects of the cleanup. The status of the processed water will also be discussed.
Persons desiring the opportunity to speak before the Panel are asked to l
contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
i l
[
ENCLOSURE B l
SEP 6 1965 I
e-
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending September 6, 1985 Near Term NRC Actions Under the Nuclear Waste Policy Act Section:
114(e) of NWPA:
Cooperation on Preparation of Project Decision Schedule.
Action:
DOE has requested comments on the draft Project Decision Schedule by September 13, 1985.
Status:
Proposed staff comments were transmitted from E00 to the Commission on August 21, 1985 for their approval and submittal to D0E.
Section:
114(f) of NWPA:
Preliminary Determination of site suitability.
Action:
As stated in the final Mission Plan submission to Congress, DOE plans to make a preliminary determination of site suitability upon recommendation of three sites to the President, now scheduled for November 1985.
Status:
The Commission will be meeting with representatives of States and Tribes on Friday, September 6, 1985 to receive their views on the timing of the preliminary determination:
Section:
301 of NWPA:
DOE Final Mission Plan.
Action:
DOE submitted the Final Mission Plan to Congress on July 9, 1985.
Status:
NRC has been requested to testify concerning the Mission Plan before the Senate Committee on Energy and Natural Resources on Thursday, September 12, 1985, and before the House Subcommittee on Energy and the Environment, Committee on Interior and Insular Affairs, on Friday, September 13, 1985.
Uranium Mill Tailings Lawsuit The Uranium Recovery Field Office (URFO) has informed us that the three judge panel of the 12th Circuit Court, hearing the industry lawsuit against the EPA Uranium Mill Tailings Standard (40 CFR Part 192), has decided in favor of the EPA.
The panel agreed with the Environmental Defense Fund that the agency erred in not also issuing standards to protect groundwater at inactive mill tailings sites, and has remanded that aspect of the standard to EPA for reconsideration.
The industry is expected to request the full court to review the decision.
The decision will affect the requests for hearings now pending i
on license amendments issued by URF0 to implement the EPA standards, since the requests are based in part on the same jurisdictional arguments.
The decision ENCLOSURE may also eliminate the need for the Commission meeting scheduled for September 10 to hear the industry arguments regarding the EPA standard.
SEP 6 1985
. Yellowcase Shipment in Truck-Train Accident On August 27, 1985, e truck hauling drums of uranium oxide yellowcake collided with a train near Fessenden, North Dakota.
The truck driver was killed, the train was derailed, and 30 of the 53 drums of yellowcake ruptured, spilling several tons of uranium oxide in an area about 100 x 200 feet along the railroad tracks.
The yellowcake shipment was enroute from Saskatchewan Mining Development Corporation in Saskatoon, Saskatchewan, Canada, to Kerr-McGee in Gore, Oklahoma.
The State of North Dakota emergency response team took charge at the accident site, rerouting traffic over a detour around the rail crossing, as the train blocked the highway.
In response to a request from the State, Region IV sent two people to the site to observe and provide technical advice. The Canadian Provence of Saskatchewan requested, and was granted, permission to send their emergency response team as observers.
Region IV representatives at the site report that the North Dakota emergency response team has done a good job of protecting the public health and safety and directing actions at the site.
Because a convenient detour was available, the train was left in place, blocking the highway, for several days to avoid spreading the spilled yellowcake.
Contractor cleanup crews were employed to recover the yellowcake and decontaminate the site.
A large vacuum cleaner was used to pick up the bulk of the spilled yellowcake. Weather conditions were favorable for limiting the spread of the spilled material, with light winds and intermittent misty rain.
There was no blowing of dust, yet not enough rain to wash away the yellowcake or hamper the cleanup efforts.
Initially, there was some question about how to handle the body of the truck driver, which had yellowcake spilled over it.
It was determined that washing the body would not cause maximum permissible concentrations to be exceeded even if washings went into the sanitary sewer system.
The body was sent to a hospital at Minct, North Dakota, for autopsy and decontamination.
l i
The locomotive of the train was also contaminated and is being cleaned at the site.
After vacuuming most of the yellowcake from the ground, workers used l
shovels and other equipment to pick up dirt containing traces of yellowcake.
Over a short distance, it was necessary to take up a portion of the railroad t
track to cleanup the spill on the railroad bed.
All cleanup activities are expected to be finished by Thursday, September 5, 1985.
Information for answering questions about the degree of hazard caused by the accident was prepared by the staff of the Division of Fuel Cycle and Material Safety and forwarded to Region IV and to the Office of Public Affairs.
t ENCLOSURE C SEP 6 1985
DOE Work on Subcritical Measurements G. Bidinger attended the DOE Workshop on August 77-29, 1985, in Albuquerque, New Mexico.
Different subcriticel measurement methodologies were reviewed and discussed by DOE contractor personnel and foreign nationals.
Development of methodologies and instrumentation will continue.
The objective of the program is to develop a subcriticality danger alarm.
Proceedings of the Work-shop will be published.
i i
t 5
f i
ENCLOSURE C i
SEP 61985
-r
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending September 6, 1985 1.
The following Significant Enforcement Actions were taken during the past week:
EN 85-59, a Notice of Violation and Proposed Imposition of Civil a.
Penalty in the amount of $100,000 was issued August 30, 1985 to Tennessee Valley Authority (Watts Bar Unit 1). The staff was advised of the Commission's approval of this action by SECY Memorandum dated August 28, 1985. The. action involves the status of control room design modifications at Watts Bar Unit 1.
These modifications were required by Appendix D to the Watts Bar Safety Evaluation Report.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-TMI-85-08, GPU Nuclear Corporation (TMI Unit 2), State of Pennsylvania TMI Cancer Study Results.
b.
PNO-I-85-62, Duquesne Light Company (Beaver Valley Unit 1), Reactor Trip and Safety Injection Due to Loss of Instrument Air Pressurc.
PNO-I-85-64, Public Service Electric and Gas (Hope Creek), Carbon c.
Di, oxide Release at Hope Creek.
d.
PNO-II-85-86A, Alabama Power Company (Farley Units 1 & 2), Florida Power Corporation (Crystal River Unit 3); Mississippi Power and Light Company (Grand Gulf Unit 1 & 2), Actions in Response to Hurricane "Elena"(Update).
PN0-III-85-77, Detroit Edison Company (Fermi Unit 2), Apparent e.
Violation of Containment Integrity.
f.
PNO-III-85-78. Edlow International (Washington, DC), Termination of Uranium Storage License.
PN0-IV-85-44B,SaskatchewanMiningDevelopmentCorporation(Saskatoon, g.
Saskatchewan, Canada), Truck-TrainAccidentInvolvingSpreadofUranium Concentrates (Update).
h.
PN0-IV-85-46, Gulf States Utilities (River Bend), Licensing and Fuel Load.
ENCLOSURE D SEP 6 1985
. 3.
The following IE Information Notices were issued during the past week:
a.
IE Information Notice 85-75, Improperly Installed Instrumentation, Inadequate Quality Control and Inadequate Post Modification Testing was issued August 30, 1985 to all nuclear reactor facilities holding an operating license or a construction permit.
4.
Other Items a.
Engineering Assurance Program Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Program visited the Stone &
Webster Corporation office in Cherry Hill, NJ on September 6,1985 to inspect Nine Mile Point 2 Engineering Assurancc Drogram activities, b.
Operations Center A tour of the NRC Operations Center was conducted by a member of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response on August 30, 1985 for visitors from China, The Philippines, and Indonesia, and on September 4, 1985 for prospec-tive bidders of the Technical Assistance for Emergency Response contract. These tours discussed the agency's incident response program.
c.
Pre-Outage Review Representatives of the Reactor Construction Program Branch, Division of Inspection Programs; the Vendor Programs Branch, and the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Program; consultants, and Region III conducted a pre-outage review inspection at the Dresden site during the period September 3-6,
- 1985, d.
Radiation Safety Workshop For Pool Irradiators Chief and representative of the Safeguards Materials Program Branch, Division of Inspection Programs, were at Rutgers University in New Brunswick, NJ this week to attend a workshop in Radiation Safety for Pool Irradiators. They also visited a pool irradiator nearby at j
Mine Hill, NJ.
t I
ENCLOSURE D SEP 61985
e.
Team Inspections A team inspection involving three inspectors from the Performance Appraisal Section, a Region II Senior Resident Inspector, two NRC contractors, and an inspector from the Quality Assurance Branch is in progress at Turkey Point during the period August 26-30 and September 9-13, 1985. The purpose of this inspection is to assess the operational readiness of a selected engineered safeguards system (in this case, auxiliary feedwater). The inspection methodology involves an operational review of the system design from an engineer-ing perspective, a review of maintenance and surveillance practices as they apply to the selected system, a review of system design changes and modifications, and an assessment of the adequacy of the training and procedural support for the selected system.
f.
Civil Penalties Paid On August 30, 1985, payment in the amount of $50,000 was received from Florida Power Corporation (Crystal River) for enforcement action (EA 84-104) relating to inadequate protection for vital equipment.
1 i
ENCLOSURE D l
SEP 6 1o85 l
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending September 6, 1985 Semiscale Semiscale test S-FS-11 was successfully conducted this week. This test simulates a 50 percent break in the steam generator feedwater line of a Combustion Engineering (CE) system 80 type plant. This type of accident was chosen for study in response to a NRR re' quest because very conservative analyses by the vendor indicated the potential for higher than anticipated primary system pressure during these transients. User need letter from NRR dated September 12, 1984 also identifies the need to perform feedwater line break tests since these data were needed to assess the codes. Thus data from these experiments will be used to assess the codes to predict primary-to-secondary coolant heat transfer and thereby the maximum primary coolant system pressure resulting from this transient. At 600 seconds following break initiation, it was assumed that the operators of a commercial reactor would initiate approved
~
operator actions. These were also simulated in Semiscale to provide data to assess the effectiveness of these actions. Following operator recovery operations, the Semiscale broken loop steam generator was isolated and refilled with auxilliary feedwater. The purpose of this phase of the test was to evaluate the ability of the best-estimate codes to assess primary-to-secondary coolant heat transfer under these conditions.
Completion of a Log-In Procedure in Brookhaven National Laboratory (BNL)
Nuclear Plant Analyzer (NPA)
The BNL NPA simulates the reactor system transients occurring in Boiling WaterReactors(BWR-4).
It has interactive capabilities for simulation of reactor operator actions.
It will be used to evaluate reactor operating guidelines and the significance of operator errors. The first version of a log-in procedure has been completed to control remote access to the BNL-NPA by off-site users with an IBM-PC and a commercial telephone line.
Los Alamos National Laboratory (LANL) Program Review Meeting A technical and management review meeting was held between
. representatives of NRC (RES, NRR) and LANL on August 28-29, 1985 to discuss the following three topics:
l ENCLOSURE E SEP - 61985
2 1.
LANL Report Improvements; 2.
Computer Code TRAC Improvement; and 3.
NPA (Nuclear Plant Analyzer) Status and Plan At the meeting LANL agreed to improve technical content and quality of their reports. NRC submitted a list of needed TRAC improvements. LANL will review the list and estimate the cost of improvements. After estimates are completed, NRC will assign priorities to different tasks.
On the NPA, LANL agreed to submit a detailed plan and schedule for its development.
Further details are discussed in the meeting minutes.
Pressurized Thernal Shock - Thermal Fluid Mixing International Agreement With Germany On September 6,1984 the USNRC entered into an agreement with Kernforschungszentrum Karlsruhe (KfK) to obtain experimental data on fluid mixing in a reactor cold leg and downcomer in the Heiss Dampf Reaktor(HDR). Mixing phenomena have been asserted by U.S. industry as being an important factor in mitigating thermal shock to embrittled pressure vessel material. The HDR is a full length facility modified to include typical cold legs of U.S. design. KfK has recently completed 20 thennal fluid mixing tests in the HDR. Approximately 13 of these tests are representative of U.S. design. Preliminary data will be provided to the NRC in September, 1985. The data will be analyzed by Professor Theofanous of the University of California, Santa Barbara to
)
assess and improve the REMIX-PTS code which is used for calculating downcomer fluid temperatures under loop stagnation conditions.
Finland On June 7, 1984 the USNRC entered an agreement with Imatran Voima Oy (IVO) of Finland to obtain experimental data on fluid mixing in a reactor cold leg and downcomer.
IVO has made several hardware modifications to 2/5 scale multiloop facility and enhanced its instrumentation as requested by NRC.
IVO has recently completed five of twenty tests that will be performed for the NRC. These data will be sent to the NRC during the first week of September, 1985. These data will be analyzed by Professor Theofanous of the University of California, Santa Barbara in order to assess and improve the REMIX-PTS code.
ENCLOSURE E I
SEP 6 1985
. Severe Accident Risk Assessment Work on the risk and risk reduction assessment for the five reference plants generally continues in accordance with the final schedule established June 27, 1985.
However, there has been one change to the We have schedule which has the full support of NRR, RES, and IDCOR.
~ expanded the program to include a BWR MARK 11 containment type (the LaSalle station). As a result there will be a minor adjustment in the This revision is overall scheduling of the now-six reference plants.
being negotiated with our contractor, Sandia, and will be available in l
late September.
I i
Pitting Corrosion Statistics RES staff (K. Kim and M. McNeil) recently met with researchers at the National Bureau of Standards (NBS) to discuss pitting statistics research being i
performed for RES by NBS. Also in attendance were NBS's subcontractor on this project (the University of Manchester, UK) and representatives of NMSS and Aerospace Corporation, an NMTS contractor.
This was the first opportunity since the project began to meet with the U. of Manchester workers together with NBS, and go over in detail the conduct of the research to be done. The discussion focused on the statistical variability of historic pitting data, and the significant role of radiolysis on pitting corrosion in repository environments. This project was initiated recently to explore the statistics of pitting corrosion and identify methods of statistical extrapolation of short term laboratory tests to the time periods of relevance to containment of i
radioactive wastes in a high level waste repository. The research is examining the distributions and correlations of pit number, pit depth, and corrosion time to determine what confidence can be placed in long term prediction of pitting corrosion behavior of iron and low carbon steel HLW overpacks in a geologic repository environment. This work is an essential adjunct to research being carried out at BNL and Battelle Columbus laboratories, examining the electro l
chemistry and kinetics of localized corrosion (e.g., stress corrosion and pitting corrosion) of HLW overpack materials in expected repository environments. Other RES efforts are addressing question of quality control and manufacturing considerations needed to assure reliable waste package performance.
ENCLOSURE E SEP 61985
4 New Radiation Protection Instrument EG&G Idaho, Inc., in a DOE-funded project, has developed a new radiation survey instrument that has been demonstrated at Idaho National Engineering Laboratory and at Battelle Pacific Northwest Laboratory to be highly accurate (under laboratory conditions) for the measurement of beta radiations as commonly encountered in the nuclear industry. Field testing of existing instruments is funded by the Office of Nuclear Regulatory Research when necessary to assure the validity and up-to-date status of regulatory guide recommendations.
Performance of the DOE-developed instrument is being field tested under an NRC research contract at the TMI-2, Oyster Creek and Maine Yankee reactors by EG&G personnel under actual working conditions. Reasonably good performance has been reported for the TMI-2 site. Results are expected from the other sites soon.
If the DOE instrument achieves the perfomance levels anticipated, it could solve many of the problems with beta radiation measurements currently encountered in NRC-licensed activities, and the NRC could develop new criteria for acceptable beta radiation measurements--criteria that are not presenity achievable because of present limitations on commercially available instrument capability.
Hurricane Date Collection In considering hurricanes in licensing review, a frequent issue has been detemination of the magnitude of the storm surges associated with hurricanes on coastal sites. Storm surge run-up is affected by a number of factors, not only oceanographic and meteorological factors which vary with the location and sequence of events (e.g., tide cycle, direction and speed of the hurricane), but also local coastal topography (offshore sea bottom elevations and onshore elevations as well as coastal configuration). Validation of the analytical models which are used by licensees to predict these effects has been handicapped by lack of field data relating land forms and storm characteristics.
In late August 1985, Hurricane Elena, a major hurricane, approached the west coast of Florida near the Crystal River nuclear power plant site.
1 In doing so, it crossed a network of instruments which was established around the coast of Florida by a RES sponsored program with the US Army Corps of Engineers to collect oceanographic information related to stom surge and storm generated waves. As Elena's direction of movement became better known, contractor personnel were dispatched with additional l
instruments to obtain more stom surge and meteorological data to supplement the data from the permanently installed stations. Recorded data retrieval will be completed soon.
Infomation collected by the network will be used in the licensing process to calibrate and improve NRC numerical'models used to evaluate the adequacy of licensees ENCLOSURE E j-SEP 6 1985
4 5
predictive calculations of storm surges and related flood levels from the design basis hurricanes. '
t Part 72 Revision l
l A proposed rule entitled " Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High Level Radioactive Waste" is being prepared. The proposed rule will be a revision of existing 10 CFR Part 72 to clarify its application to storage of high-level l
radioactive waste in a monitored retrievable storage facility (MRS).
This revision results from a provision of the Nuclear Waste Policy Act of 1982 that requires that an MRS, if construction of an MRS is approved by i
Congress, be subject to licenisng by NRC. Minor changes are also proposed to clarify issues that have arisen since 10 CFR i
Part 72 was made effective on November 28, 1980. The proposed rule has been approved by the pertinent offices and is being prepared fc-submittal to the Office of the Executive Director for Operations.
l Decommissioning Rule Amendments
~
July 12,1985, was the cl osing date for public comment on the proposed i
rule amendments to 10 CFlt Parts 30, 40, 50, 51, 70 and 72, " Decommissioning Criteria for Nuclear Fac lities." Comment letters were received from 135 individuals, compani4s and utilities, industry groups and government entities..These letters' ranged in length from 1 to over 50 pages and covered a number of complex issues and a wide diversity of views.
RES is currently in the process of review and organization of these connents. To date, 90%
of the comment letters have been reviewed and placed into 8 major categories and 100 subcategories.
l l
i ENCLOSURE E SEP 6 1985 i
I I
I
e 0FFICE OF STATE PROGRA!15 ITEMS OF INTEREST WEEK ENDING SEPTEMBER 6, 1985 Training Course During the week of September 23-27, 1985, twenty State radiation control personnel and two persons each from the Navy and Air Force will attend the course entitled " Introduction to Licensing Practices and Procedures" in Bethesda.
Conference of Radiation Control Program Directors The summer meeting of the Executive Board of the Conference of Radiation Control Program Directors was held September 3-5 in Bethesda. The Board met with the Deputy EDO and was briefed by Sheldon Meyers, Director, Radiation Programs, EPA, on statu.s of EPA's radiation program activities.
National Association of Towns and Townships Steve Salomon. OSP, attended the annual educational conference in Washington, D. C. of the National Association of Towns and Townships, September 5-6, 1985. The topics of interest relevant to NRC included hazardous waste disposal and hazardous materials transportation.
1 k
{
i ENCLOSURE H SEP 61985
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA
~
ITEMS OF INTEREST WEEK ENDING SEPTEMBER 6, 1985 1.
AE00 issued the final report of a trends and patterns analysis of engineered safety feature (ESF) actuations that occurred during the first six months of 1984 at commercial U.S. nuclear power plants (AE0D/P503).
Based on the analysis and evaluation described in this report, AEOD concluded that:
(1) events necessitating ESF actuations have not i
generally been individually significant and their occurrence frequency should not be of major concern; this holds true for failures and problems associated with these actuations; (2) the majority of the reported ESF actuations were unnecessary and the rate of these actuations could be greatly decreased by reducing the number of equipment failures during nonnal operation, reducing the number of personnel errors during maintenance and testing, and revising actuation setpoints to more appropriate protective levels; and (3)
L the limited number of ESF actuations, the wide variety of ESF systems, and the differences in the types of ESF actuations make comparisons between units very difficult.
AE0D determined, however, that some units appear to be experiencing repeated unresolved actuations which could ultimately challenge continued equipment operability and proper personnel response. Further, AE0D found that four potentially significant problems occurred in the ESF actuations studied. AE00 will investigate these items in an attempt to L
determine the generic applicability of these problems and define if f
further actions, whether generic or unit specific, should be required to properly address any concerns.
2.
AE00 issued the final report of a trends and patterns analysis of I
unplanned reactor trips (i.e., reactor scrams) that occurred in 1984
)
at commercial U.S. nuclear power plants (AE0D/P504).
Based upon the evaluations and analysis described in this report, AE0D
[
arrived at the following general observations with regard to reactor trips:
(1) the reduction of hardware failures, primarily in balance of plant (BOP) systems, would significantly reduce the number of reactor
[
l trips; (2) there are a number of post trip recovery complications due i
to equipment failures and personnel errors unrelated to the original l
trip cause that have the potential for having significant safety implications; and (3) many reactor trips are being initiated by i
unlicensed personnel.
In addition to these general observations, the report contains a number of specific conclusions based upon the i
analysis of the 494 reactor trips which were identified in 1984.
Overall, AE00 observed a slight decline (9%) in the rate of automatic l
and manual reactor trips from 1983 to 1984.
(
I l
ENCLOSURE J l
i SEP 6 1985 l
l
~
l
-a NRR MEETING NOTICES
- SEPTEMBER 6, 1935 v
DOCKET APPLICANT /
I l
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 9/9-10/85 50-498 P-110 & P-118 To discuss Power Systems Houston Lighting &
P. Kadambi 9/9-1:00 pm 50-499 Bethesda Branch Mechanical Questions Power Co.
9/10-8:00 am (South Texas)
/
9/10/85 50-305 P-328C Discussion on_, impending Wisconsin Public Serv. M. Fairtile 9:00 am Bethesda license amendenent related to (Kewaunee) steam generator tube repairs 9/10/13/85 50-440 Perry Plant NRC Staff Audit of Resolution Cleveland Electric J. Stefano 8:30 am Perry, Ohio and implementation of Human Illuminating, Co.
Engineering Discrepancies 9/11/85 50-424 Bechtel Offices Discuss in detail the appli-Bechtel M. Miller 8:30 am 50-425 12400 Imperial cant's seismic and pump and.
EG&G Norwalk, Calif.
valve equipment qualification Southern Co. Serv.
program (Vogtle)
Westinghouse 9/12/85 EPRI Offices Quarterly Meeting - EPRI Light EPRI H. Berkow 9:30 am 1800 Mass. Ave.
Water Reactor Steering Committee Washington,0C and NRC Policy Committee 9/12/85 50-410 Suite 530 Discuss FSAR Chapter 14 Review Niagara Mohawk M. Haughey
'8:30 am 4520 EW Highway (Nine Mile Pt. 2)
Bethesda, Md.
f9/12/85 50-325 Room 5033 Discuss detailed control room Carolina Power & Light M. Grotenhuis 9:00 am 50-324 Air Rights Bldg Design Review (Brunswick)
Bethesda, Md.
I
- Copics 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 o
C A
1 j
m NRR MEETING NOTICES
- m DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 9/13/85 50-269/270/
P-118 To discuss review results in Duke Power Co.
H. Nicolaras 9:00 am 287 Bethesda report, "A Review of the Oconee 3 Probalistic Risk Assessment:
Internal Events, Core Damage Frequency" 9/18/85 50-219 GPU Nuclear Toreview$tatusoflicensing GPU Nuclear J. Donohew 9:00 am Parsippany, NJ actions for Oyster Creek 9/18-20/85 50-443 Seabrook Site To inspect completion of Power Public Serv. Co. of V. Nerses 50-444 Seabrook, NH System Branch confirmatory New Hampshire items Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms.
E P8 E
m "O
l
~
NMSS MEETING NOTICES FOR WEEK ENDING_* 9/6/85 y
Division Cf Fuel Cyclo and Material Safcty ATTENDEES /
DOCKET APPLICANT ~
NRC CONTACT bTE/ TIE NUteER LOCATION PURPOSE 9/10-11/85
. Project Willste To discuss topical report submitted J. Massey, et al.
Roberts 9:30 am -
M-39 5th floor by NUTECH for a horizonta} modular (NUTECH) conf room storage system for irradiated J. Counts (IE) nuclear fuel.
J. Roberts (FC)
F. Sturz (FC)
Reps, of SAIC 9/17-18/85 Project West Valley, Meeting on design aspects of W. Hannum, et al.
Clark M-32 Ni supernatant treatment system (00E) and comments on SAR review.
T. Clark (FC) e Division of Safeguards Mone Division of tlaste Management None r
P S
!5
'J L.--__--___
E, RES MEETING NOTICES September 6,' 1985 5
DOCKET ATTENDEES /
DATE/ TIME NUPEER LOCATION PUP. POSE APPLICANT-NRC CONTACT 9/24/85 1133-5S Present results of the contract PNL Turel "Use of Computers to Meet the Requirements of 10 CFR 73.55" 9/26/85 ll33-SS Safeguards Workshop RES Safe-Ting guards Section k58 A
~
h
Sept. 6, 1985 u>
RII MEETING NOTICE cn
-d$
ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DOCKET 9/13/85 Region II Enforcement Conference Licensee, and Selected Walker Florida Power Corporation RII Staff Members 9:00 am regarding two security events at the Crystal River 3 facility E
P S
E m
T
M
-o REGION III PtEETING NOTICES g
, WEEK ENDING:
September 7, 1985 DOCKET ATTER0EES/
DATf/ TIME NUP!9ER LOCATION PUllPOSE APPLICANT....
IJRC CONTACT 9/26/85 50-440 Perry,OH SALP Cleveland Elec. Illum.
A.B. Davis 50-441 Perry Plant A.B. Davis & staff 9/20/85 50-373 Glen Ellyn, IL ts?."C6nt ' ' "
Coimohsiaitfi 531s6n A.B. Davis 10 a.m.
50-374 LaSalle Station A.B. Davis & staff s
D:
.1, A
I s
"x i
5 i
E a.
i i
e s
._