ML20058N400
| ML20058N400 | |
| Person / Time | |
|---|---|
| Issue date: | 03/25/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20058M131 | List:
|
| References | |
| FOIA-92-436 SECY-82-129, WIR-820319, NUDOCS 9310140245 | |
| Download: ML20058N400 (40) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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INFORMATION REPORT SECY-82-129 March 25, 1982
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For:
The Commissioners i
T. A. Rehm, Assistant for Operations, Office of the EDO From:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 19, 1982
Subject:
A summary of key events is included as a convenience to those Comissioners 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
Management and Program Analysis J*
Controller Analysis and Evaluation of Operational Data K
L*
Small & Disadvantaged Business Utilization & Civil Rights N
Regional Offices N*
CRGR Honthly Report 0
Items Approved by the Connission T. A. Rem.., Adtant for Operations Office of the Executive Director for Operations
- No input' this week.
Contact:
DISTRIBUTION:
T. A. Rehm, EDO ff f0R INTERNAL NRC
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s a~"~ 0^"^ ^' ^ e ISTRIBUTION ONLY 492-778I jgQaSa~t rClLsu;3
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9310140245 930218 PDR FOIA GILINSK92-436 PDR
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SUMMARY
OF THE WEEKLY INFORMATION REPORT Week Ending March 19, 1982 LaSalle 1 According to Commonwealth Edison, essentially all construction and all testing for fuel load is complete. The applicant's estimate for fuel loading is one to three weeks after the official March 15, 1982. NRC's resident inspector estimates the unit will not be ready until May 1,1982.
WNP 3 The Washington Public Power Supply System has notified the NRC that the planned date for submitting the OL application has been shifted from April to June 1982.
Construction completion is schedoled for late 1985.
CRBR The Yellow Creek nuclear plant has been under construction near Iuka, Mississippi; however, TVA recently announced the postponement of both units indefinitely.
Inspection of this site in its present circumstances indicated that it would be an acceptable location for the CRBRP.
Insider Rule The Insider Rule package is in the concurrence process and is expected to be forwarded to the EDO by March 31, 1982.
Annual Report sent draft to OCA for Rep. Bevill's Appropriations Subcommittee; also sent draf t to NRC of fices.
fiemorandum of Acreement with INPO Forwarded to EDO for signature a revised overall Memorandum of Agreement (MOA) with INPO addressing cooperative activities on operational experience data.
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a OFFICE OF ADMINISTRATION Week Ending March 19, 1982 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF RE00ESTS Initial Appeal of Request Initial Decision Received 172 6
j Granted 117 0
Denied 12 4
Pending 43 2
ACTIONS THIS WEEK Received Kathy O'Reilly, Requests a copy of the non-proprietary portions of proposal RFP-RES-81-204 submitted by General Physics.
ADTECH (82-137)
Andrea L. Kronzek, Requests a copy of a Petition for Rulemaking filed FOI Services. Inc.
by Dr. George V. Taplin 3/28/79. Docket #PRM-35-1 (82-138) and all information relating to the petition and the use of technetium-99m inhalation.
Doris Falkenheiner, Requests copies of tne final detailed analysis of Public Law the construction completion schedule for River Utilities Group Bend, Unit 1.
(82-139)
Cassandra Dixon, Requests a copy of NUREG/CR-0628, PNL-2889, REV.,
Don't Waste America September 1979, " Prediction of the Net Radon (82-140)
Emission from a Model Open Pit Uranium Mine."
Troy B. Conner, Jr.,
Requests a copy of a memorandum of Chief Administrativ-Conner & Moore Judge Cotter dated December 22, 1981 entitled "New (82-141)
Form for Initial Decisions," and any documents discussing or transmitting the December 22, 1981 memorandum or discussing a new fonnat for proposed l
findings of fact and conclusions of law.
Joseph Gallo, Requests, on behalf of Tayloe Associates, three Isham, Lincoln & Beale categories of documents regarding Invitation for (82-142)
Bid No. RS-SECY-82-471, " Stenographic Reporting Services."
Joseph Gallo, Requests, on behalf of Tayloe Associates, all Isham, Lincoln & Beale records sent by the Alderson Reporting Company to (82-143) the Contracting Officer or his assistants and all records sent in response by the Contracting Officer or his assistarts to the Alderson Reporting Company between November 1981 and March 1982 regarding Invitation for Bid No. RS-SECY-82-471, " Stenographic Reporting Services."
CONTACT:
J. M. Felton ENCLOSURE A a92-7211 l
2 Received, Cont'd Bruce Kooi, Requests five categories of documents regarding F.0.I. A. Specialists Contract NRC-03-82-096 " Technical Assistance in (82-144)
Support of NRC Reactor Licensing Program."
Granted Steven C. Sholly, In response to a request for copies of specified Union of Concerned documents and certain records related to meetings, Scientists which were noted in the NRC staff listing (82-92) entitled "TMI Action Plan Steering Group Chronology",
made available copies of 15 documents. Informed the requester four additional documents are already available at the PDR. Also informed the requester four documents were not located upon search of pertinent files.
Steven C. Sholly, In response to a request for a copy of SECY-82-35 Union of Concerned concerning TMI-1, made available a copy of this Scientists SECY paper.
l (82-97)
(NRC employee)
In response to a request for information concerning (82-106) candidate selection made under NRC Vacancy Announcement R81-5486, made available four documents.
H. Milton Smith In response to a request for a copy of the non-(82-113) proprietary version of the proposal under Request for Proposal ADM-82-358, made available a copy of the requested record.
( An individual requesting In response to a request for records in the NRC information about himself) on himself, informed the requester the NRC has no (82-116) information pertaining to him.
Malcolm H. Philips, Jr.,
In response to a request for records regarding Debevoise & Liberman inspections referred to by Mr. Wayne Reinmuth in (82-125) his statement during the meeting of the ACRS Subcunnittee on Regulatory Activities on March 3, 1982, made available three documents.
Informed the requester five additional documents and the transcript and handouts for the March 3,1982 meeting are already available at the PDR.
ENCLOSURE A f
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0 Granted, Cont'd l
In response to a request for copies of three NUREG Roger L. Boyer (82-128) reports and other reports dealing with recommendation!
for the present nuclear power plant licensing process and on the evaluation of fault trees by the computer program MOCUS, made available three NUREG reports and access to three additional NUREG reports.
Linda Weiss, In response to a request for lists of awarded NRC Weiss & Associates contracts since October 1,1980, made available (82-130) two lists.
Rick Krainin, In response to a request for copies of four NUREG New York Public Interest reports along with copies of three reports on Research Group, Inc.
nuclear waste management, made available copies of (82-131) the requested NUREG repcrts. Informed the requester he may obtain copies of the three reports on i
i nuclear waste management by writing to the National Technical Information Services.
Cassandra Dixon, Made available a 00py of NUREG/CR-0628, PNL-2889.
Don't Waste America (82-140)
Denied None i
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ENCLOSURE A
e DIVISION OF SECURITY
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Week Ending March 19, 1982 Vikonics Key Cards i
The Division of Security will issue new access control system Vikonics Key Cards to all personnel who currently possess valid Rusco Key Cards or whose Office / Division Directors have requested the new cards. For further details regarding dates, times and card-issuing locations, see Announcement No. 26 dated March 12, 1982.
NRC Procedures and Guidelines for the Protection of Classified National Security Council Information The Executive Director for Operations signed Bulletin 2101-18, subject as above, on March 18. 1982. This Bulletin, prepared at the request of the National Security Council, sets forth specific security procedures (e.g., access, receipt, i
handling and reproduction) for classified National Security Council information.
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DIVISION OF CONTRACTS Week Ending March 19, 1982 RFP ISSUED RFP-RS RES-B?-014 Title "The 10th Water Reactor Safety Research Information Meeting" j
Description - To coordinate and administer the planning and arrangements for conducting the "10th Water Reactor Safety Research i
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Information Meeting".
Period of Performance - From effective date of contract through November 29, 1982 Sponsor - Office of Nuclear Regulatory Research Status - RFP istued March 15, 1982 Closing date is March 29, 1982 l
IFB ISSUED IFE RS-ACM-E2-377 Title
" Lease of Sedans" Description - To lease ten (10) new mid-size sedans.
Period of Performance - One year from effective date of contract with option
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for an additional year Sponsor - Office of Administration i
Status - IFB issued March 12, 1982 Closing date March 29, 1982 CONTRACT AWARDED NRC-10-S2-364 Title
" Maintenance for IBM Mag Card I Executives, Mag Card II Memory Typewriters, Selectric III's and Electronic 75's."
Description - To perform maintenance, repairs, and replacement of parts to IBM Mag Card I Executives, Mag Card II Memory Typewriters, Selectric III's and Electronic 75's.
Period of Performance - One year from contract effective date Sponsor - Office of Administration Status - A fixed price (requirements) contract in the amount of
$45,508.00 awarded to Celtech, Inc., on March 18, 1982 under the 8(a) program.
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ENCLOSURE A f
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I DIVISION OF CONTRACTS Week of March 20, 1982 i
CONTRACTS CLOSED OUT i
NRC-07-78 431 Centaur Assoc.
3/15/82 AT(49-24)-0322 Naval Surf. Weapons Cntr.
3/18/82 j
l AT(49-24)-350 Univ. of California 3/15/82 l
NRC-04-74-176 JRB Associates 3/15/82 l
ENCLOSURE A I
OFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING MARCH 19, 1982 I
l DIABLO CANYON l
Two long days of discussions were held on Wednesday and Thursday of last I
week among lawyers and technical persons representing PG&E, Governor Brown, Joint Intervenors and NRC Staff concerning a possible settlement among all parties on the scope of Diablo Canyon Seismic Design Reverification program and the independent company or companies to carry out such a program. As a result of the ' apparent progress achieved by these discussions, all parties agreed to extend the deadline for agreement until the following Tuesday.
The representatives then consulted with each of their respective parties
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over the next several days. On Tuesday of this week the parties reported to the NRC Staff the results of these consultations. Based on these reports, the Staff concluded and all parties agreed that further discussions'were not i
likely to be fruitful in reaching a settlement that all parties would accept.
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NRC Staff, in accordance with the Comission decision of March 4, is now censidering PG&E's proposal that Teledyne Engineering Services be approved.
as the independent company to carry out the Seismic Design Reverification l
program required by the Commission's Order of November 19, 1981.
La Salle County Station, Unit 1 The LPM contacted Commonwealth Edison in order to obtain 'the latest fuel lead date for La Salle County Station, Unit 1.
The applicant 1
(L. De1 George) indicated that essentially all construction and all testing for fuel load is complete.
The only thing remaining is for paper work to be completed by its staff and Region III.
Mr. De1 George indicated that Region III was at the site.and on March 12, 1982, i
-Cordel.1 Reed would be calling Mr. Denton to indicate the status. His estimate for fuel. loading was 7 days.up to three weeks after the official March 15, 1982 date. As a result of this call, the LPM called Roger Walker at the site and conveyed the above telephone conversation.-
His imediate reaction was that he could not see Unit.I being ready until.
May 1, 1982.
McGuire Unit'No.1
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Unit No. 1 was shutdown on February 25, 1982 for steam generation inspection.
During startup following the inspection outage, an unusual event
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.g-declared at 3:00 AM on March 18, 1982.
Prompt entry and inspection inside containment revealed that a relief valve (IN-68) on the comon RC sample line upstream of the heat exchanger was stuck open resulting in approximately 20 gpm leak into the containment building. The relief e
valve was closed, the line isolated and red tagged, at 5:00 AM. The unusual event was secured at 5:30 AM. The exact cause of the relief valve malfunction has not been detenuned but could have resulted from the required RC startup over-pressure test. The valve will be repaired / replaced.
Unit startup operation is proceeding.
ENCLOSURE B
' Unidentified leak of greater than 10 gp :.
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NRR Weekly Highlight MAINE YANKEE 1.
During routine removal of a steam generator primary side manway cover, 6 studs failed; there are a total of 20 studs per manway cover. The studs had been exposed to boric acid from a small primary leak and to Furnanite a sealing compound applied last autumn to seal the leak. Analysis of the failure mode is underway. Ultrasonic testing of all primary side manway studs has revealed crack indications in five additional studs from the affected manway; no crack indications were observed in bolts from the other manways. Maine Yankee is a CE three loop design, rated at 2630 Mwt, currently shut down for scheduled I
maintenance.
2.
A meeting will be held in P-110 at 9AM Wednesday March 17 to discuss the steam generator manway stud cracking experience at Maine Yankee. Members of the staff, Maine Yankee Atomic Power Company and the CE Regulatory Response Group will attend.
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l The Washington Public Power Supply System '(WPPSS) has notified the NRC. ',.
staff of a change to the planned date for submitting the OL application..
for Unit 3.
.The date has been shifted from April,1982 to June,1982. -
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Unit 3 is now approximately 47" complete, with construction, completion. _ ' '
scheduled for late 1985.
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UPCOMING CRBR MEETIN35
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Subject:
Clinch River Breeder Reactor Leak hetection System Date/ Time:
March 29, 1982, at 10:00 a.m.
Location:
Air Rights Building, Room 5033 Bethesda, Md.
Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
D. Moran, J. Mauck, R. Stark, et. al. (NRC) 2.
Subject:
Clinch River Breeder Reactor Containment s' stems Review "
y Date/ Time:
April 1, 1982, at 8:30 a.m.
' Location:
Phillips Building, Room P-114, Bethesda, Maryland Attandees:
J. Longenecker, D. Goeser, et. al. (00E)
F. Eltawila, H. Holz, J. Long, R. Stark, et. al. (NRC)
ENCLOSURE B j
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NRR Weekly Highlight 3-UPCOMING CRBR MEETINGS (cont'd) 3.
Subject:
Clinch River Breeder Reactor Materials and Mechanical Engineering Review Meeting 1
Date/ Time:
April 6-7, 1982, at 8:30 a.m.
Location:
Air Rights Building, Room 2242, Bethesda, Md.
i Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
H. Holz, S. Hou, F. Litton, R. Stark, et. al. (NRC) i SUMMARIES OF CRBR REVIEW MEETINGS 26, 1982 in Bethesda, Maryland to discuss A meeting was held on January 1.
the shutdown heat removal system for the Clinch River Breeder Reactor i
The applicants described the automatic action features of the Plant.
shutdown heat removal system and the natural circulation capacity of the The applicants presented a comparison of the natural circulation system.
In addition, analysis for the homogeneous core and the heterogeneous core.
the applicants described the themal centers and elevation differences for the major components in the natural circulation mode of heat removal.
The. applicants natural circulation analyses assume that the plant trips from rated power with a loss of electrical power. The applicants' acceptance criterion for the natural circulation analyses is the core hot channels temperatures shall be below the sodium boiling temperature.
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The applicants' analyses are documented in CRBRP-ARD-0132. CRBRP-ARD-These documents include natural circulation 0142, and WARD-D-0308.
predictions for FFTF and an evaluation of the FFTF natural circulation test results.
The applicants indicated that a final CRBR natural circulation report would be issued late in 1982.
2.
A meeting was held on February 9 and 10,1982 in Bethesda, Maryland to discuss the Clinch River Breeder Reactor Structural Design. The applicants This presented the design bases and criteria for the structural design.
included discussions on: the plant duty cycle; elevated temperature design; reactor system seismic analysis; reactor internals design; control rod system design and testing; reactor internals testing; piping design analysis and testing; provisions for inservice inspection; and, the structural requirements for the auxiliary liquid metal system.
The NRC staff review comments were documented in four sets of questions which were sent to the applicants. The staff questions are: CS 250.1 and CS 250.2 sent on February 19, 1982; CS 250.3 through CS 250.9 sent 26,1982; CS 210.1 through CS 210.9 sent on February 26, on February 1982; and, CS 210.10 through CS 210.14 sent on March 11, 1982. A follow-up meeting has been planned in mid-April to discuss the applicants responses to the staff questions.
ENCLOSURE B i
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1 NRR Weekly Highlights
-4 SUMMARIES OF CRBR REVIEW MEETINGS (cont'd)
A meeting was held on February 11, 1982 in Bethesda, Maryland to discuss 3.
i the fire protection systems for the Clinch River Breeder Reactor Plant.
The applicants described the fire protection program and discussed the The ability to cope with conventional fires and uquid metal fires.
applicants program for conventional fires is consistent with standard Their program for dealing with liquid light water reactor technology.
sodium fires relies on leak detection systems, catch pans, fire suppression I
decks, inerted atmosphere, cell liners, and sodium carbonate extinguishers.
The leak detection systems utilize photoelectric and ionization chamber smoke detectors and optical detectors. The detectors are located throughout j
the reactor containment building, the reactor service building and the i
steam generator building. The details of the leak detection systems are documented in sections 7.5 and 9.13 of the PSAR. The consequences of aThe liquid sodium spray fire are documented in section 15.6 of the PSAR.
results show that the peak gas pressure and temperature occur within j
two minutes of spray initiation. The gas aerosols have been analyzed j
assumming all radioactive spray releases are contained in the aerosol.
The applicants show that these events are within 10CFR 100 guidelines.
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A meeting was held on February 12, 1982 in Bethesda, Maryland to discuss f
the auxiliary liquid mets 1 systems found in Chapter 9 of the CRBR PSAR.
.The applicants described the design bases, functions, design criteria, and system classification for equipment and systems documented in the PSAR.
Tne systems discussed included: heating ventilating and air conditioning systems; the chilled water system; the plant service water system; the atmospheric filtration systems; the fire protection system; the diesel generator support systems; the floor drainage systems; the reactor refueling l
system; and, the pining and equipment electrical heating and control system.
The HRC staff and consultants indicated that the staff review of Chapter 9 was on schedule.and that formal staff questions would be issued early in l
March 1982.
5.
On March 1-3, 1982 NRC staff members visited the Yellow Creek, Murphy Hill and Savannah River sites with respect to consideration of these alternatives to the proposed site at Oak Ridge.
The Yellow Creek Nuclear Plant has been under construction near luka, Mississippi; however, TVA recently announced the postponement of both units indefinitely.
Inspection of this site in its present circumstances indicated that it would be an acceptable location for the CRBRP.
ENCLOSURE B e
i NRR Weekly Highl'ights -
SUMMARIES OF CRBR REVIEW MEETINGS (cont'd)
The Murphy Hill site is approximately 7 miles north of Guntersville,
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Alabama, and is located on the eastern shore of Guntersville Reservoir in the Tennessee River. Although this site is presently being prepared for construction of a coal gasification facility, the applicant proposed that the NRC staff review it as representative of the resource area.
Inspection of the site indicated no obvious reason why it would not be acceptable for the CRBRP if the coal gasification plant is not constructed.
Although numerous nuclear facilities have been constructed at the Savannah River Plant (SRP) site, there is still plenty of room to accomodate the CRBRP. The area inspected by the staff appeared to be suitable and is probably licensable. However, because of concerns i
regarding Cha*-leston seismicity, considerable effort would most likely have to be expended to validate the site at the proposed SSE and OBE design bases.
6.
A meeting was held on March 4,1982 in Bethesda, Maryland to continue the NRC review of the applicants' organization structure and qualifications.
The meeting was attended by Messrs. J. Anderson, P. Brewington, R. Copeland, J. Green and J. Longenecker of the applicants and Messrs. F. Allenspach, G. Rivenbark and R. Stark of the NRC staff. The applicants described the functions of the CRBR Project Office. This discussion included detailed descriptions by the applicants' key personnel in the following a) Project Director, b) Engineering, c) Quality Assurance, d) areas:
Operations Division, and e) Licensing and Environmental Assessment. The applicants' discussion also included detailed responses to NRC staff i
questions, such as:
the role of Breeder Reactor Corporation and the role of the Project Steering Comittee.
The NRC staff finds this portion of the applicants' organization to be l
I functioning acceptably. The staff, however, recommends that the Operations Division have a more active role in the design review process. This should include significant responsibility for the design review of field I
modifications and future design changes.
The staff will continue its review of the applicants' organization. The staff plans to review the function of the Lead Reactor Manufacturer in the near future.
ENCLOSURE B i
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NRC T5I PROGRAM OFFICE WEED.Y STATUS REPORT
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l March 14,1982 - March 20,'1982 1
f Plant Status Heat transfer from the reactor coolant system (RCS) i Core Cooling Mode:
loops to reactor building ambient.
l Available Core Cooling Modes: Decay heat removal systems.
Long tem cooling "B" (once through. steam generator-B).
.RCS Pressure Control Mode: Standby pressure control (SPC) system.
B'ackup Pressure Control Modes: Mini decay heat removal' (MDHR) system.
Decay heat removal (DHR) system.
Pajor Parameters.(as of 0500, March 19,1982) (approximate values)
Average Incore Thermocouples: 101*r Maximum Incore Themocouple:
130*F RCS Loop Temperatures :
.A B
Hot Leg 94*F 97*F 82*F 7B'F Cold Leg ((1) 2)
87'F 79'F RCS Pressure: 96 psig Reactor Building: Temperature :
63*F Water levei :
Elevation 283.2 ft. (0.5 ft. from floor) i Pressure:
-0.3 psig Airborne Radionuclide Concentrations :
1.5 E-6 uti/cc H3 (sample taken 3/18/82)
<7.5 E-6 uCi/cc ~KrB5 (sample taken 3/1/82) d Effluent and Environmental (Radiolooical) Information_
Liquid effluents from the TMI site released to the Susquehanna 1
River after processing, were made within the regulatory limits and i
in accordance with NRC rcquirements and City of Lancaster Agreement dated February 27, 1980 During the period March 12, 1982, through March 18,1982, the effluents contained no detectable radioactivity at the discharge point'although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calculations l
indicate that less than five millionths (0.000005) of a curie of cesium was discharged.
The public can' check current gat =a radiation levels in effluent water released from TMI by looking at the remote monitor recorder that has been installed at the EPA iMI Field Station office,100 Brown Street, Middletown. This recorder replicates the output from an on-site ENCLOSURE B I
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l instrument that continuously samples water released from TMI Industrial Water Outfall and monitors it for gamma radiation.
This monitor also automatically notifies EPA and PA-DER personnel if the gamma radioactivity in the water exceeds one-twentieth (1/20) of the Federal limit for cesium-137 in the environment.
As a confirmatory practice, part of the monitored water is automatically collected for later laboratory analysis.
Airborne releases to the environment as measured by Airborne Effluents.
2.
licensee installed monitors at discharge stacks, are listed below. These releases were well within regulatory limits.
February 1982 Unit II EPTCOR 11_
Noble gases (Ci)
<9.47 x 101
<1.53 x 101 Tritium (Ci) (C1) 7.61 x 101 1,49 x 10-7 6
Particulates 1,68 x 10-5.77 x 10-3 3.
Environmental Protection Agency (EPA) En_vironmental Data.
Results from EPA monitoring of the environment around the TM1 site Were as follows :
3 The EPA measured KR-85 concentrations (pCi/m ) at several l
environmental monitoring stations and repo,rted the following l
J results :
1 Location February 5,1982 - February 26, 1982 (pCi/m3)
Goldsbo ro 25 Observation Center 30 Middletown
.31 Yorkhaven 23 All of the above levels of Kr-85 are considered to be background level s.
No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gamma rate networks during the period from March 10, 1982 through Parch 18, 1982.
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NRC Environmental Data.
Results from NRC monitoring of the environment around the IMI site were as follows:
The fol' lowing are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Sa-isl e_
Period (uti/cc)
(uCi/cc) l HP-291 March 10,1582 - March 17,1982
<5.3 E-14 <6.3 E-14 ENCLOSURE B f
w v-During the period March 15,1982 to 5.
NRC Environmental Samples.
the NRC obtained environmental samples from the March 19,1932, following locations:
- control soil and liquid samples (airport and river)
- liquid samples from the Unit 2 air intake tunnel and borated water storage tank (BWST) pipe chase
- soil samples in vicinity of the BWST
- soil samples in vicinity of processed water storage tank (PWST)
These samples will be analyaed at the Radiological and Envircnmental Sciences Laboratory in Idaho.
Recently the East Dike Monitorino of East Dike Runoff Basin Water:
la closec caten casin for natural runoff water) showed 51ightly elevated 5.
The East Dike samples taken during February 1982, level s of tritium (H-3).
This by EPA indicated an average concentration of 600 pC1/1 : 250 concentration.is about twice the natural background concentration of B-3 in surface water in the TMI area.
The EPA and HRC will continue to. sample the East Dike.
Licensee Radioactive Material and Radwaste' Shioments.
7.
On Monday, March 15,19B2, three Unit 1 liquid samples (various locations) were mailed to Radiation Kanagement Corporation, Philadelphia, Pennsylvania.
16, 1982, one drum containing 13 SDS (Submerged On Tuesday, March Demineraliser System) samples from Unit 2 was shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
15, 1982, two Unit 1 precoat stmples were shipped On Tuesday, March to the Westinghouse Electric Company Laboratory, Waltz Mills Site, Madison, Pennsylvania.
On Thursday, March 18,1982, steam generator tube plugging equipment.
used in Unit 1, was returned to Westinghouse Electric Company, Advanced Reactor Division, Madison, Pennsylvania.
On Thursday, March 18, 1982, 51 drums containing contaminated laundry from Unit 1 and Unit 2 were shipped to Tri-State Industrial Laundries, Utica, New York.
18, 1932, nine Unit 1 liquid samples (various On Thursday, March locations) were shipped to the Westinghouse Electric Company Laboratory, Madison, Pennsylvania.
ENCLOSURE B f
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- l. l Ma.ior Activities Submerced Demineralizer System (5051 processing of batch 23 (reactor coolant oleed tank water) was completed on March 12, 1982 The 1.
The SD5 batch 23 process parameters are enclosed in' Attachment 1.
l Processing of reactor system is now secured for minor maintenance. coolant system wate l
June 1982.
The EPICOR II system continued to process 505 effluents 2.
EPICOR II.
Performance parameters-are enclosed in Attachment 1.
curing One week.
3.
Reactor Buildino Entries.
Following four reactor building entries 14, 1982, the flush portions of the gross Huring tne week of Marcn Approximately 10,000 decontamination experiment were completed.
gallons of processed water were added to the reactor building sump during the flushing. The gross decontamination experiment will be concluded next week after technicians test strippable coatings and chemical decontamination data techniques in limited areas of the Post decontamination data will also be collected reactor building.
next week to evaluate the effectiveness of the gross decontamination experiment.
Preliminary area radiati'on surveys following the flushes on the 305 ft, elevation and the 347 f t, elevation indicate an apparent decrease in radiation levels.
It is difficult to quantify the magnitude of the cecrease due to significant variations in the radiation levels in various areas of the reactor building, apparent variations in the effectiveness of the decontamination, and the preliminary status of the data.
Subsequent weekly status.
reports will discuss the results as they become available.
Reactor Coolant System (RCs) processino. The licensee is directing 4
engineering ef fort towards preparations for processing the RCS The basic through the submerged demineralizer system (505).
operation of the SDS will remain the same as during the processing of the reactor building sump water except that the effluent will be directed to a reactor coolant bleed tank in preparation for injection Since the back into the RCS instead of to EPICOR 11 for polishing.
RCS cannot be drained, a feed and bleed operation to and from the reactor coolant bleed tanks will be used to recove water from the This feed and blee.d type operation i
RCS in preparation for processing.
will result in total processing of approximately 300,000 gallons.
Since the ef fluent of the SDS is directed back into,the RCS, additions to the total inventory of processed water at TMI are minimized.
The chemistry of the water injected back irito the RC5 must be closely controlled to reduce the possibility of corrosion of materials in, the RCS. Preliminary discussions have been held between the NRC and the licensee to scope and discuss the problems involved.
(
Testing and evaluations are continuing in thfs area.
ENCLOSURE B l
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s
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5-On darch 3,1982, the makeup water path to the RCS was shifted from The shif t was necessary to ensure makeup water Loop A to Loop B.
injected into the RCS is not removed from the RCS through the letdown line (installed only on Loop A) without passing through the This will improve the efficiency of the feed and reactor vessel.
Reactor coolant system water bleed operation when it is commenced.
processing is currently scheduled to commence during the month of Jane 1982.
9 Control Rod Drive Disassembly _.
A proposed technique for inspecting the interior of the Unit 2 reactor vessel with a television camera 5.
was practiced in the Unit 1 reactor building on Monday and Tuesday, The technique was proposed by the Technical March 15 and 16,1982.
Assistance and Advisory Group (TAAG) and involves re=oving a control rod drive lead screw to make an opening in the top of the reactor The control rod drive vessel head to insert a television camera.
disassembly and camera insertion were completed ahead of schedult at Unit 1 and the tops of several fuel assemblies were inspected The control rod drive was and video taped on Monday afternoon.
reassembled on Tuesday.
In -Unit 1, the camera was maneuvered to inspect the fuel assembly under the disassembled control rod drive and the four adjacent fuel assemblies. The camera produced a clear image of the tops of fuel It is pins and other components on top of the fuel assembly.
. expected that the technique will be attempted in Unit 2 sometime this year to provide some visual indications of the conditions ofThis w the reactor core.
j Prior to performing the operation in Unit 2, the reactor coolant system will need to be depressurized and the primary system water 1evel lowered below the upper flanges of the control rod drives.The Unit 2 NRC review of these proposed actions has been initiated.
reactor coolant system pressure was lowered in increments during the accident recovery and is presently maintained at approximately 90 psig.
i I
ENCLOSURE B l'
lY.
Ils v.
. K=
,s
/.
~6-6 Future Meetings 23, 1982, the TMI Advisory Panel will meet with On Tuesday, March 1.
the NRC Commissioners at 1:30 PM in Washington, DC to discuss various issues related to the cleanup of THI Unit 2.
14, 1982, Lake Barrett will be the keynote On Wednesday, April 2.
speaker for the Southern Pennsylvania Association Occupational Health Nurses, to be held at the Holiday Inn in York.
)
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i ENCLO5URE B.
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=
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.+
4
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ATTACHMENT 1 1
1
]
4 SDS Performance for Batch Number 23 i
Average Average Average Radionuclide Infl uent_
Effluent DF (uc/ml)
Tuc/ml)
C'esium 137 1.4 x 10 1.3 x 10-2 3,1 x 103 j
I i
Strontium 90 8.8 x 10-1 1.7 x 10-2 5.2 x lol I
1 EPICOR II'Perfomance March S.1932 to March 15, 1982
.t Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/m1) 4 Cesium 137 5.2 x 10-3 3.0 x 10-7 1.7 x 10 Strontium 90 1.1 x 10-2
<1.2 x 10-5
>9.2 x 102 i
i Antimony 125 7.4 x 10-3
<3.5 x 10-7
>2.1 x 104 S
1 I
.i ENCLOSURE B f
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS r
Items of Interest Week Ending March 19, 1982 Insider Rule The Insider Rule package is in the office concurrence process.
It is anticipated this rule will be forwarded tc the EDO by March 31, 1982.
r l
t ENCLOSURE C i
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l 1
l Meetines - Division of Fuel Cycle and Material Safety j
1.
Subject:
Site visit to National Bureau of Standards wit'h Region I I
inspector to discuss consolidation of the NRB licenses.
Date/ Time:
March 18, 1982, 1:30 pm Location:
Gaithersburg, Maryland Attendees:
W. T. Crow and A. L. Soong (NMSS), Representatives from Region I and NBS.
2.
Subject:
Review of Certification of Compliance No. 9152 (Model
- CNS 1-13C II)
Date/ Time:
March 18, 1982 Location:
Three Mile Island Attendees:
W. H. Lake and R/ H. Odegaarden (NMSS) and Representatives from TMI/NRC Staff and General Public Utility Nuclear l
3.
Subject:
Meeting with elected officials of Burlington", Iowa to discuss Transportation of Radioactive Materials.
Date/ Time:
March 21, 1982 Location:
Burlington, Iowa Attendees:
C. E. MacDonald and C. Hillman (NPSS) and elected officials of Burlington, Iowa 4.
Subject:
Meeting to discuss the requirements for a Health Physics plan for proposed stabilization activities at the APAX site near Parkersburg, West Virginia.
Date/ Time:
March 22, 1982, 10:00 am Location:
Willste Building Silver Spring Attendees:
W. A. Nixon (NMSS) and Representatives from AMAX 5.
Subject:
Attending symposium on groundwater transpcrt modeling for near-surface disposal of nuclear wastes and on-site visit of licensed facilities at University of Seattle, Washington.
Date/ Time:
March 22-26, 1982 Location:
Seattle, Washington Attendee:
E. Y. Shum (NMSS) l 6.
Subject:
Pre-licensing site visit (Kawecki Berylco, Inc.)
l Date:
March 24-26, 1982 i
Location:
Reading, Boyertown and Revere, Pennsylvania Attendee:
A. L. Soong (NMSS) 7.
Subject:
Peeting regarding technical specifications regarding General Electric Morris Operations Date/ Time:
March 25, 1982, 9:00 am Location:
Fifth Floor Conference Room. Willste Building Attendees:
L. C. Rouse, A. T. Clark and J. Roberts (NPSS) and i
Representatives from General Electric.
ENCLOSURE C I
1 j
1
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8.
Subject:
Meeting with Sandia National Laboratory regarding the application review process for materials licensees.
I Date/ Time:
March 29 - April 1, 1982 Location:
Albuquerque, NM Attendees:
T. F. Carter, Jr. and J. R. Cook (NMSS) and Representatives from Sandia.
i 9.
Subject:
Meeting to discuss United Nuclear Corporation's Decontamination Plan at Wood River Junction.
Date/ Time:
March 31,1982,1:30 pm Fifth Floor Conference Room, Willste Building Location:
Attendees:
R. G. Page, W. T. Crow, E. Y. Shum and G. H. Bidinger (NMSS).
and Representatives from United Nuclear Corporation.
j i
- 10.
Subject:
ASLB Prehearing Conference on TVA Brown Ferry Nuclear Plant
- Low-level radioactive waste storage, j
Date/ Time:
April 1,1982 l
Location:
Madison County Courthouse, Huntsville, Alabama Attendees:
P. Loysen and F. Sturz (NMSS) ASLB Members, ELD Representative, and Representatives from TVA and the Petitioners.
Planned Meetings - Division of Safeouards 1.
Subject:
Testimony before Senate Judiciary Subcommittee on Criminal Law re implementation of the Convention for the Physical Protection i
of Nuclear Material -
Date:
March 24, 1982 l
Location:
Capitol Hill Attendees:
R. F. Burnett j
l 2.
Subject:
Meeting with General Electric, Westinghouse, and ACRS j
l on Design Concepts to Counter Sabotage l'
Date:
March 24, 1982 Location:
Albuquerque, New Mexico-l
~
Attendees:
Tom Allen, SGPR 3.
Subject:
10 CFR 73.55, confirmatory site visit to Susquehana Steam Electric Stati'on Date:
March 25, 1982 Location:
Berwick, PA Attendees:
C. Gaskin, SGPR 4.
Subject:
10 CFR 73.55 confirmatory site visit to Salem Nuclear Station Date:
Parch 23-24,19S2 Location:
Salem Delaware Attendees:
J. Davidson, SGPR Veetines - Division of Waste Management 1.
Subject:
State Participation in High-l.evel Waste Licensing Date/ Time:
March 25, 1982 Location:
Willste Building, Room 106 Attendees:
WK4T, WMPI, and Office of State Programs ENCLOSURE C
, -. - - -,. - - - -,,,. - - - ~. - -,, -..,.. -
I OFFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST MARCH 15, 1982 - MARCH 19, 1982 l
1.
There were no Significant Enforcement Actions imposed during the past week.
\\
2.
The following Preliminary Notifications were dispatched during the week:
PNO-I-82-23a, Maine Yankee Atomic Power Co. (Maine Yankee Atomic Power a.
Station) - Stud Failure in Reactor Coolant System Pressure Boundary-Bolted Closures (Update).
l b.
PNO-I-82-24, Baltimore Gas & Electric Company (Calvert Cliffs Units 1 and l
- 2) - Light Plane Emergency Landing.
PNO-III-82-26, Wisconsin Electric Power Co. (Point Beach Unit 2) - Unplanned c.
Gaseous Release.
d.
PNO-III-82-28, Consumers Power Company (Palisades Nuclear Power Station -
Outage Greater than 48 Hours -- Main Transformer Overheating.
j i
PNO-IV-82-10, Nebraska Public Power District (Cooper Nuclear Station ) -
i e.
Early Warning System Operability.
J f.
PNO-IV-82-11, U. S. Coast Guard - Report of Radioactive Device Sighted Offshore.
PNO-V-82-12, Southern California Edison Co. (San Onofre Unit No. 2) - Loss g.
I of Shutdown Cooling and Positive Reactivity Addition.
h.
PNO-V-82-12A, Southern California Edison Co. (San Onofre Unit No. 2) -
Boron Concentration Stratification in Refueling Water Tanks.
3.
Other Items Division of Emeroency Preparedness EPLB staff members participated in the Vermont Yankee, Monticello, Surry, and Cook emergency preparedness implementation appraisals which all began on March 15, 1982.
EPLB staff members participated in the Oyster Creek and Turkey Point emergency preparedness exercises which began on March 16, 1982.
EPLB staff members participated in the Susquehanna emergency preparedness exercise which began on March 17, 1982.
1 ENCLOSURE D d
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0FFICE OF NUCLEAR RESULATORY RESEARCH a
l IMPORTNiT EVENTS FOR THE WEEK ENDING PARCH 19,1982 Experimental Programs Branch BWR Refill /Reflood Procram l
1.
NRC, EPRI and GE have come to an agreement concerning the course of BWR TRAC work under this cooperative program. Previously, INEL j
staff had expressed concern that the INEL and GE TRAC work might be diverging. Effective immediately, the GE base version will be the official INEL Version 12 scheduled for release within a 1
few weeks. GE will imediately apply two updates to include j
features which GE desires (level tracking and improved Andersen-Ishii).
GE and INEL are now coordinating future planning for the next unified version (probably MOD 1 in mid-FY 1983). INEL and GE will present their recomended plan to NRC and EPRI on April 20, 1982 at the BWR TRAC mid-year review.
4 Analysis of 30 SSTF Bata has been adversely impacted by a potential GE 0
j overrun and by loss of key staff at GE. NRC and EPRI are currently evaluating how best to recover from this situation.
1 2.
BWR FIST Program l
Facility construction is continuing on schedule although a number of very tight critical paths have been identified. A draft test plan has been prepared and is under review by the PMG.
j Analysis efforts may become the critical path item due to a decision to use Version 12 of BWR TRAC in facility scaling studies. A is projected because of this change. The change 1-1/2 nonth delay'made at this time in order to align GE TRAC effort j
to Version 12 was with INEL work. The switch to Version 12 would be required at some point in the future anyway and will likely save resources in the long term.
3.
FLECHT SEASET The report NUREG/CR-1534. "PWR FLECHT SEASET Steam Generator Separate Effects Task Data Analysis and Evaluation Report," has been published and distributed. Evaluation of tests performed to measure and to characterize the steam generator secondary side to primary side heat transfer under postulated inlet fluid conditions for a hypothetical PWR LOCA are presented in this report.
ENCLOSURE E
1
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Experimental Programs Branch 4.
Semiscale Steam Generator System Operational (50) Tests have been initiated following completion of the Intermediate Break Test Series. These 50 tests will provide data needed to plan and conduct the upcoming feed and steam line break test series.
The meetings held on RELAPS (March 8), Semiscale (March 9) and Selected Tests (March 10), while intended for NRR, were broadly attended. With representatives from the major national f abs PWR vendors, utilities, consulting firms and universities. The prograns appear to be responsive to NRR needs judging from the feedback received during and following the meetings. They are also of significant interest to groups outside NRC.
5.
Data Bank The Data Bank program is presently in the process of entering data from GE Single Heated Bundle Tests (Runs 2330, 2331, 2329, 2319 and2314). The successful addition of these data should be completed in about one week.
Analytical Models Branch
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A meeting was neld in Silver Spring on March 11. 1982 with Dr. H. Karwat, who represents BMFT of FRG. The meeting was requested by Dr. Karwat to l
explore the desirability of arranging a meeting for specialists from both nations to review safety issues concerning reactor containment.
The following agreement was reached:
1.
Hydrogen Control and the HDR Containment Test Program merit discussion in the proposed meeting.
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2.
The meeting should be held here so that USNRC can present more completely our positions and programs on hydrogen control.
FRG will propose a date, possibly sometime in April 1982.
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ENCLOSURE E l
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~3~
Analytical Models Branch i
2.
to'E has re:eived from BNL the eawal for RACNA-3B, a BWR systems cw.e j
tnat simulates three dimensional neutron kinetics and multichannel core
]
hydraulics of nonhomogeneous non-equilibriurn two phase flow. The report i
discusses code models and solution techniques, enumerates code capabilities and limitations, and presents results of developmental code assessment.
I j
The manual has been transmitted to NRR for corrrnents. A meeting with BNL and i
NRR is planned for the first week of May to discuss RAMONA-38 applications j
to NRR's needs.
l 3.
The Simulator Working Group had a three day meeting in Gaithersburg to j
prepare the first draft of a report which will discuss the needs in nuclear power plant simulation and outline a five-year RI,0 program. The report and i
the proposed program will be submitted to the. Congress by DOE. The first i
draft is to be discussed at a meeting tentatively scheduled for
]
April 15, 1982.
)
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Fuel Behavior Branch 1.
ACRR Debris-Coelability Experiment D. 5 i
Debris-coolability experiment D-5 has been oerformed in the ACRR test 2
reattor. This experiment is part of the joint program among NRC, EURATOM, 1
and Japan on the coolability limits and post-dry-out behavior of internally-
)
heated beds of particulate LMFBR core debris in a sodium pool. D-5 was the first experiment in the series to use an approximately prototypic
" full" size distribution for the simulated LMFBR particulate fuel debris j
that ranged from 40 to 4,000 microns in the 11cm deep bed. A primary goal j
of D-5 was investigating bed behavior in extended dryout up to local j
temperatures of 2000*C.
}
At a very low power level (0.2 w/g UO ) during the initial slow stepwise 2
increase in bed specific power towards dryout, and with the bed boiling, q
j-but not in dryout, the bed spontaneously opened up internal cooling cha nnel s. This had occurred in previous experiments without particulate fines.
but at much higher bed s'pecific power. "The channeled bed was extremely coolable, remaining in single-phase convection without boiling as the 3
a power was increased by a factor of 10 over a 10-hour period. Local dryout in the bed was finally reached at a bed power of 2.5 w/g 00, which is a 2
decay heat level of 2.5% of nominal full LMFBR specific power which occurs 3.5 min. a fter shutdown. Failure of high-temperature bed-diagnostic thermocouples terminated the experiment. Because of the very high coola-i bility of the channeled D-5 debris bed, this bed could not have been driven to the planned 2000*C local temperature in the bed dry-out zone at j
bed specific powers that can occur in any LMFBR accident scenario, or at i
1 specific powers that were achievable in this ACRR experiment.
T l
ENCLOSURE E
h
. Fuel Behavior Branch Results of this and others of the recent D-series experiments indicate that the true dry-out coolability limit of beds of post-accident LMFBR particulate core debris in sodium is determined in most cases by this spontaneous opening up of cooling channels in the bed, which greatly increases the bed coolability, and not by the coolability limit of the
, particulate debris in the packed bed geometry as initially formed.
Experiments and modeling of this bed dynamics are far more complex than studies of the coolability limits of fixed-geometry packed beds that have been done previously. Essentially all the useful data on this LMFBR debris-bed dynamics has come from the D-series experiments in ACRR, which provide internal (fission) heating of the bed, real reactor materials and temperatures, and extended particle-size distribution.
As part of the LWR Severe Fuel Damage (SFD) program, somewhat similar experiments in ACRR are planned to provide data and develop models on the dry-out coolability limits of severely-damaged LWR fuel and LWR core debris under reflooding, in order to determine the range of severe accident conditions for which reflooding will terminate the accident within the reactor vessel. It now appears likely that the coolability limits of severely-damaged LWR fuel and LWR core debris involve only the coola-bility limits of fixed-geometry beds, and not the more complicated debris-bed dynamics.
2.
EG&G-SNL Technical Information Exchance Meeting on the Coolability of Severely Damaged twR Fuel This information-exchange meeting was held at EG&G on March 8.
The purpose of the meeting was to review the severely-damaged fuel and core-debris coolcbility area of the Severe Fuel Damage (SFD) program, and i
l in particular the recently completed coolability module of Mod 0 of the SCDAP Severe Fuel Damage Code. The SFD program is an integrated program in which EG&G performs integral tests in PBF and analysis, and develops the integral SCDAp code. Sandia performs phenomenological separate-effects experiments, mostly in ACRR, and develops phenomenological models for use in future Mods of SCDAP. Sandia also has special expertise in debris coolability from its extensive fast-reactor-safety experiments and model development. A primary purpose of the meeting was to further infor-mation exchange and close day-to-day coordination at the working level.
l Three Sandia specialists in debris coolability and R. W. Wright of the Fuel Behavior Branch attended the meeting, along with a larger number of EG&G staff.
The meeting was successful, with a good interchange of views. The Mod 0 coolability module of SCDAP was reviewed favorably by the Sandia staff present.
Follow-on coordination needs were identified.
ENCLOSURE E F
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I Publications to be Issued in the Near Future
Title:
Standard Format and Content of Site Characterization Reports for High-Level Waste Geologic Repositories
==
Description:==
The proposed guide sets forth the format preferred by the NRC staff for the submission of information by DOE in its Site Characterization Reports, in compliance with the provisions of 10 CFR Part 60. The proposed guide also provides the level of detail that the staff feels is appropriate for information presented in the Site Characterization Reports by DOE.
Centact:
C. N. Ostrowski 427-4634 Publications Issued Durino the Week of March 15-19, 1982 Draf t Regulatory Guide and Value/ Impact Statement: Training and Certification of Independent Spent Fuel Storage Installation Operators.
Comments requested by May 20,1982.
i ENCLOSURE E
i ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MARCH 19, 1982 Foreion Visits to NRC On Monday IAEA Director General Hans Blix, Deputy Director General for Safe-guards Hans Gruemm and Mr. Johann Molander. Dr. Blix's assistant, met w'ith Chairman Palladino, Commissioners Gilinsky, Bradford Ahearne and Roberts, W. J. Dircks and J. R. Shea to discuss current IAEA issues, particularly safeguards matters.
On Wednesday Yasuo Sakakihara, Managing Director of Japan NUS, made a courtesy call on Chairman Palladino.
Also on Wednesday Ambassador Roland de Kergorlay, Head of the Delegation of the Commission of the European Communities to the U.S., accompanied by Mr. Francois Lafontaine, Science and Technology Secretary of the EC Washington Delegation, met with Chairman Palla61no, R. B. Minogue and J. D. Lafleur, Jr.,
to discuss possible NRC participation in the EC's Super Sara test program.
On Wednesday Dr. Tomihiro Taniguchi, Director of the Office of Nuclear Power Operations of the Japanese Agency for Natural Resources and Energy ( ANRE),
and two members of the Japanese ACRS met with representatives of NRR and RES to exchange information on Japanese and U.S. steam generator operating experience and related research. The Japanese described, among other things, their regulatory approach to inservice inspection, secondary water control regulations, and degradation experience. The visitors also toured TMI on Tuesday to review the status of the clean-up operations and to discuss SG experience with GPU representatives. Additional appointments were scheduled for the visitors on Thursday and Friday to cover operator qualification, RPV thermal shock, the resident inspector program, and emergency planning.
IAEA.Safecuards IP drafted proposed testimony and related documents for Chairman Palladino in preparation for a joint hearing on IAEA safeguards before the Subcommittee on International Economic Policy and Trade and the Subcommittee on Inter-i national Security and Scientific Affairs, of the House Committee on Foreign Affairs. Ambassador Kennedy, Ambassador Kirk, and ACDA Director Rostow also testified at the hearing, which was held on March 18.
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ENCLOSURE G l
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Foreicn Reports The following foreign reports were received in IP March 15-19:
(For further information contact Eva Szent-Ivany IP, X27788.)
From Canada:
AECL-Mi s c-204 A Study of Piping Failures in US Nuclear Power Reactors ** - PROPRIETARY From France:
M. I. - Nuclear Safety Bulletin - SN No.24 November-December 1981 (Sent for translation) f From the FRG:
l GRS - STAR Disturbance Analysis and Surveillance System **
(Answers to regulatory review questions.)
From Jaoan:
Atoms in Japan - January 1982**
STA - Annual Report - April 1980 - March 1981**
National Institute 3f Radiological Sciences Nuclear Safety Research Index 1982**
(Prepared for the OECD INDEX. The topics are the verification tests being carried out by Nuclear Power Engineering Test Center.)
i ANRE - Material for Nuclear Power Plants - October 1981**
Water Chemistry of Steam Generator Secondary Side and Associated System ** - PROPRIETAF From Taiwan:
Monthly Operating Report of January 1982 for Chinshan Nuclear Power Plants #1L2**
1 Special Reports (RO-03-010 & R0-03-011) of Kuosheng Nuclear Power Plant il i
From the CEC:
i Eur 7693 EN/FR - Evaluation of the Community's Indirect Action Programme on Management and Storage of Radioactive daste**
i Deleted from PDR copy
- Indicates the reports are in English ENCLOSURE G I
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST t
WEEK ENDING MARCH 19, 1982 P
The Office of State Programs is assisting the NRC Region V Office in sponsoring a regional meeting in Walnut Creek, CA on March 31 and April 1 l
for the Governor-appointed liaison officers from Alaska, Arizon4 California, The subjects which will be discussed Hawaii, Nevada, Oregon and Washington.
include emergency planning, waste management, spent fuel shipments and notification, as well as other items of mutual regulatory interest.
Robert Wood, Darrel Nash, Jerome Saltzman, OSP, and Frank Cardile, RES, met on March 16 with representatives from the Internal Revenue Service to discuss IRS' latest views on the tax deductibility from current income of a IRS reviewed with the NRC staff utility's collections for decommissioning.
the proposed revenue ruling that it has indicated to a power reactor licensee will soon be forthcoming and discussed how such a revenue ruling might affect the NRC's consideration of different methods to assure financing of decommissioning. The proposed ruling would not allow tax deductibility.
Jerome Saltzman discussed the Commission's final rule on nuclear property insurance during a panel meeting on property insurance at American Nuclear Insurer's Annual Meeting in New York on March 18.
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ENCLOSURE H I
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OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS l
Items of Interest WEEK ENDING - MARCH 19, 1982 i
Annual Report Sent draf t to OCA for Rep. Bevill's Appropriations Subcomittee.
Also sent draft to Offices.
Publication Distributed NUREG-0020. " Licensed Operating Reactors," (Gray Book) dated December 1981.
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ENCLOSURE I I
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING MARCH 19, 1982 Briefino on Proposed LER Rule On Tuesday, March 16, AE00 (Michelson and Heltemes) briefed the Commission on the proposed LER rule (SECY 82-3) and the associated data storage and retrieval capabilities, and the AEOD process for performi.tg trends and pattern analysis. The current AE0D activities and products were discussed as well as anticipated future activities after the Sequence Coding and Search System is in routine operation.
Memorandum of Acreement with INPO The revised overall Memorandum of Agreement (MOA) with INP0 and Appendix 1 addressing cooperative activities on operational experience data were discussed with the INPO staff. The latest revision incorporates NRC staff comment and has been reviewed by INPO. Consequently, it has been forwarded with a recommendation that it be signed by the EDO.
Other appendices are in various stages of preparation and review.
It is anticipated that several other appendices will be ready for final review and signature in the near future.
ENCLOSURE K
REGION III ITEM 5 OF INTEREST Week Ending March 19, 1982 The Regional State Liaison Officer and the Chief of the Transportation Certification Branch, NMSS met on March 21, 1982 with local officials from i
l Iowa and Illinois in Burlington, Iowa to discuss the proposed rail shipment of spent fuel from the Cooper Station in Nebraska to the General Electric Corporation storage facility in Morris, Illinois. Also participating in the meeting were representatives of the State of Iowa, the G.E. Company, Nebraska Public Power District, Burlington Northern Railroad and the Environmental l
Policy Institute. A similar meeting was held in Creston, Iowa on March 4, 1982.
U.S. Representatives James Leach (Iowa) and Thomas Railsback (Illinois) sponsored the meeting.
I The Regional State Liaison Officer will meet with the Chairnan of the Ohio House Energy and Environment Connittee on March 24, 1982 to discuss NRC l
regulatory responsibilities regarding low-level radioactive waste nanagement and the development of a flidwest Compact for regional waste management.
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ENCLOSURE M l
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REGION IV ITEMS OF INTEREST Week Ending March 19, 1982 l
The State Liaison Officer from Region IV met with Texas State officials in l
Austin Thursday, March 18th to discuss current developments regarding a state l
owned and operated low-level radioactive waste burial site.
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ENCLOSURE n L -
l 1.
REGION V ITEM 5 0F INTEREST Week Endino March 19, 1982 Sacramento Municioal Utility District Rancho Seco 312 During a thunder storm on the after; con of 3/18/82, there were several lightning strikes on and near the site. The Met Tower apparently was hit and put out of service. Several radiation meters around the site perimeter were made inoperable and three construction workers on site pouring concrete felt the electrical charge from a strike but were not injured.
Portland General Electric Co.
Trojan - DN 50-344 The latest analyses of primary coolant activity indicate that the dose equivalent iodine concentration has reached a plateau, with values ranging from 75 to 85 percent of the Technical Specification (TS) limit. Gross specific activity remains at 45 to 50 percent of the TS limit; and steam generator leakage remains at less than five gallons per. day.
Southern California Edison Co.
I San Onofre DN 50-361 Shortly aftcr 5:00 a.m. on 3/14/82, with the reactor in Mode 6 (core fully leaded with unirradiated fuel), plant operators lost shutdown cooling flow on both trains, apparently due to air binding of the pumps which are served l
by a common suction header. Flow was re-established by adding borated water to the pump suction from the Refueling Water Storage Tanks (RWST). This action resulted in reduction of the reactor coolant boron concentration by about 40 ppm and the overflow of 300 to 500 gallons of borated water from I
the incore instrumentation nozzles located in the reactor vessel head.
Despite the reduction in boron concentration, Technical Specification limits were maintained by a substantial margin.
The cause of the reduction in boron concentration is attributed to an in-adequate procedure for measuring the boron concentration in the RWST. The cause of the air binding of the pumps is still being investigated.
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ENCLOSURE M
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 19, 1982 A.
SECY-82 LICENSE AMENDMENT FOR PROPOSED EXPORTS OF DISPERSED TRITIUM TO ADDITIONAL DESTINATIONS (XB001141, AMENDMENT 01), Memo Secy to Dircks, 3/15/82 j
I This is to advise you that the Commission (with Chairman Palladino and Comissioners Ahearne and Roberts agreeing) has approved the proposed amendment to allow the export of an additional quantity of 40,000 curies of dispersed tritium incorporated into sealed light sources assembled in devices for weapons systems to Bahrain, India, Oman, Pakistan, i
Saudia Arabia, and Taiwan.
Commissioner Gilinsky ' abstained from this. action, Commissioner -
Bradford did not participate.
4 The Office of International Programs was informed of this action on March 12, 1982.
B.
SECf-82 PROPOSED RETRANSFER FOR REPROCESSING (SPAIN TO THE U.K.), Memo i
i Secy to Dircks, 3/15/82 This is to advise you that the Commission (with Chairman Palladino and Commissioners Ahearne and Roberts agreeing) has approved the proposed response to the Department of Energy (DOE), subject to the modifications contained in the attached final draft.
l Co==issioner Bradford indicated that he preferred the letter proposed by the staff in SECY-81-677 and also agrees with.
Commissioner Gilinsky.
Commissioner Gilinsky disapproved, indicating that the Commission should make reference to its finding on the ineffectiveness of international safeguarding of. plutonium.
The Office of International Programs was informed of this action on March 11, 1982.
It is requested that you forward a copy of the letter to DOE l
to the Office of the Secretary when signed.
Attachment:
Not Included ENCLOSURE 0 e
i l
H ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 19, 1982 C.
SECY-82 PROPOSED RETRANSFERS FOR REPROCESSING (JAPAN TO THE U.K. AND FRANCE), Memo Secy to Dircks, 3/15/82 This is to advise you that the Commission (with Chairman i
Palladino and Commissioners Ahearne and Roberts agreeing) l has approved the proposed response to the Department of Energy (DOE), subject to the modifications contained in the attached final draft.
Cc=missioner Bradf ord indicated that he pref e:. red the letter proposed by the staff in SECY-81-677 and also agrees with Commissioner Gilinsky.
Commissioner Gilinsky disapproved, indicating that.the Commission should make reference to its finding on the ineffectiveness of international safeguarding of plutonium.
Coc.missioner Ahearne asked that the staff provide the current status of their addressal of transient shipments of spent fuel (reference SECY-80-533).
The Office of International Programs was informed of this action on March 11, 1982.
i It is recuested that you forward a copy of the letter to DOE to the Office of the Secretary when signed.
Attachment:
Not Included D.
STAFF RE0VIREMENTS - AFFIRMATION SESSION 82-8, 3:00 P.M., THURSDAY,'4 ARCH 11, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE),
Memo Secy to Dircks, Bickwit and Kammerer, 3/17/82 l
l
.I.
_ SECY-82 Pacific Gas & Electric Co. 's Nctice of Permaturity and Advice of Withdrawal in Stanislaus (Antitrust)
I The Commission, by a vote of 5-0, approved an order referring the ma^ter to the presiding Licensing Board for consideration. A majority of the Comission (Chainnan Palladino, Comissioners l
Gilinsky and Brac' ford) approved a modification proposed by Chairman Palladino.
(OGC)
(Subsequently, the order was signed by the Secretary.)
ENCLOSURE O
'i I
l-l ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 19, 1982 D.
STAFF REOUIREMENTS (cont'd)
SECY-82 Final Rule (1) to Eliminate Reouirementsf Financial Qualifications for Power Reactor Aoplica II.
i The Connission approved a final rule to amend J
j l
for power reactors at the CP and OL stages, and to amend 10 CF l
to require power reactor licensees to maintain on-site property Chairman Palladino'and damage insurance for decontamination.
Comissioners Ahearne and Roberts approved the rule as modified b Corraissioner Ahearne; Conrnissioner Bradford disapproved the rule; Co=nissio.er Gilinsky approved in part and disapproved in part s
The Comission:
approved the final rule, as modified, for publication in the j
1.
Federal Recister, to be effective as stated in the staff paper; (SP)
(SECY Suspense: 3/26/82) requested that appropriate Congressional comittees be notified; 2.
and (SP/0CA)
(SECY Suspense: 3/26/82) requested that copies of the final rule be distributed to affected 3.
applicants, licensees and other interested persons.
(ADM)
(SECY Suspense: 4/9/82)
Section 201 of the Energy Reorganization Act, 42 U.S.C.15841, provides I
that action of the Co. mission shall be detemined by a " majority vote 'of Corrnissioner Ahearne was not present when this the members present."
item was affimed, but had previously indicated his approval of the Had Comissioner Ahearne been present, he would have affinnei his prior vote. Accordingly, the formal vote of the Comission was e0 order.
in favor of the decision.
2 ection 201 of the Energy Reorganization Act, 42 U.S.C. 55841, provides Sthat action of the Comission shall be detennined by a " majority vote of Corraissioner Ahearne was not' present at the meeting the members present."
Had he been present at the meeting he would which this rule was approved.
To enable the Conrnission to proceed in this have voted with the majority.
matter without delay, Comissioner Bradford who was a member of the minority Accordingly, on the question up for decision, abstained in the femal vote.
the femal vote of the Cc=nission was two approved, one approved in part, one abstention.
ENCLOSURE O l
,