ML19351E734
| ML19351E734 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-801205, NUDOCS 8012190123 | |
| Download: ML19351E734 (64) | |
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December 11, 1980 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING DECEMBER 5,1980 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Standards Development C
Nuclear Material Safety and Safeguards D
i Inspection and Enforcement E
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Nuclear Regulatory Research F*uh;~-
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- w Executive Legal Director G k$'
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F-2 2
.c International Programs H
y State Programs I
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Management and Program Analysis J
Controller K*
Analysis and Evaluation of Coerational Data L
Small and Disadvant' aged Business Utilization M*
Items Approved by the Commission
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N Calendar of Speaking Engagements 0
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T. A. Renm, Assistant for Operations Office of the Executive Director for Operations
- No input this week.
CCriTAC.T:
. A..Rehn, 27781
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8012190 12 3
t Summary of_ Weekly Information Report Week Ending December 5, 1980 North Anna, Unit 2 During the weekend, the Unit 2 main generator step up transformer had a fault which caused damage to the bus duct system between the generator bus terminal and the~ transformer. There were minor fires in the area which were caused by the hot metal. The reactor tripped and all shutdown systems responded satisfactorily.
Davis-Besse, Unit No. 1 On December 3, 1980, the reactor tripped due to a reactor coolant pump trip.
Following the reactor trip, the main steam isolation valves closed. The operators then manually actuated the Steam and Feed Line Rupture Control System (SFRCS), which then allows steam generator level to be controlled automatically by the auxiliary feedwater system. Actuation of SFRCS should start both auxiliary feedwater pumps; however, one of the pumps did not start automatically and required separate cperator action to start.
IE is reviewing the event.
TMI Reactor Building Entry The fifth entry into the Unit 2 reactor building is scheduled for Thursday, December 11, 1980. The planned tasks include replacement of the neutron source range, amplifier, decontanination experiments and additional radiation' mapping.
Contamination of TMI Building Expansion Joints Durir.g a radiclogical survey of the 281 elevation of the Unit 2 auxiliary building on November 27, 1980, contanination was found in two expansion joints.
The licensee has implemented a plan to determine the source and extent of the contamination.
Wood River Junction Public Meeting On December 2,1980, at the request of the State of Rhode Island, a public meeting was held in Wood River Junction to inform the public of the progress of the decantamination effort at the United Naclear facility. Also of concern was 1) the status of the waste shipments to Nevada, which received a consider-able amount of publicity recently when the State of Nevada neturned six truck -
loads of waste to UNC which had been destined for burial; 2) issues that were discussed in meetings held in July of this year; and 3) recent stories in the press concerning the disposal of liquid wastes from lagoons to the environs by UNC.
Licensee Transcortation Activities in Possible Ncn-Comoliance with Part 71 On November 26, 1980, a notice was mailed to approximately 170 NRC radiography licensees stating that all their transportation activities may not be conducted
Q 2-in accordance with 10 CFR Part 71. The letter noted that they neither were registered with NRC for any shipping packages nor had an NRC approved quality assurance program. Licensees who fail to respond to the letter will be referred to IE for followup action at a later date.
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4 0FFICE OF ADMINISTRATION Week Endiag December 5, 1980 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 668 38 Granted 520 14 Denied 102 19 Pending 46 5
ACTIONS THIS WEEK Received (An individual requesting Requests a copy of his Official Performance information about himself)
Appraisals.
(80-584)
Linda A. Sanders, Requests all correspondence between the NRC Johnson City Press-Chronicle and the Nuclear Fuel Services Plant in Erwin, (80-585)
Tennessee from June, 1980 through September, 1980.
Charles A. Green, Requests a copy of a staff study on the putential Knight-Ridder Newspapers of presently licensed sites to cause significant (80-536) radiation exposure to surrounding populations in the event of a severe accident.
Anthony F. Earley, Jr.,
Requests, on behalf of the Utility Group on Hutton & Williams ATWS, 51 categories of documents relating to l
(80-587)
" Proposed Rulemaking to Amend 10 CFR Part 50 Concerning Anticipated Transients Without Scram l
(ATWS) Events."
i Michele McCarthy Reouests information on the Windscale nuclear (80-588) reactor accident in Cumberland, England in October, 1957.
John Vail, Attorney-At-Law Requests informat#on indicating the whereabouts (80-589) of plutonium or other radioactive substances unaccounted for by Nuclear Fuel Services of l
Erwin, Tennessee.
CONTACT:
J. M. Felton 492-7211 l
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. Received, Cont'd Stephan C. Volker, Requests a copy of " Guidelines for Decontamina-Sie ra Club Legal Defense tion of Facilities and Equipment Prior to Release Fund, Inc.
for Unrestricted Use or Termination of Licenses (80-590) for By-product, Source or Special Nuclear Material" dated November 1976.
Lilias Jones, Requests a copy of NUREG/CR-ll38, NUREG/CR-Black Hills Alliance 1273, and " Investigation of Radon-222 infspicns (80-591) from Underground Uranium Mines, Prtire;$ Fxpsrc.1.
R. B. Borsum, Requests a copy of " Summary of Meeting Meid on Babcock & Wilcox June 5,1978"; referenced in a Jtoo 3,1978 (80-592)
Memorandum for:
Faast Rosa from R. Fitzpatrick.
Lilias Jones, Requests a copy of ten listed documents.
i Black Hills Alliance (80-593)
Granted Jeffrey D. Littlejohn, In response to a request for information LAND Minnesota Chapter relating to the transportation and inspection (80-537)'
of eight shipments of radioactive waste from the Dairyland Pcser Cooperative, Lacrosse Boiling Vater Reactor in Wisconsin, and nine categories of documents regarding cask model NFS-4, made available 10 documents.
Al Stern, In response to e request for a list of firms that Al Stern Associates responded to a specifit :4RC announcement in (80-557) the Commerce Business Daily, made available a copy of this list.
Joseph Halapatz, In response to a request, on behalf of an NRC (Representing an NRC employee for a copy of NRC Form 50 regarding that employee)-
employee, made available two documents.
(30-558) l Richard Shaikewitz, In response to a request, on behalf of his Wiseman, Shaikewitz, client, for information concerning her deceased McGivern & Wahl husband and information on the incidence of (30-561) carcinoma in uranium workers, made avails.ble one document.
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ENCLOSURE A l
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3-Granted, Cont'd McNeill Watkins, II, In response to a request for records of NRC Debevoise & Liberman staff opposition to making the fire protection (80-564) rule applicable to future plants or licenses i
and records related to such future application of the rule on which NRC staff relied in analyzing the question, made available three documents. Informed the requester additional documents subject to the request are already available at the PDR.
McNeill Watkins, II, In response to a request for six categories of Debevoise & Liberman information relating to fire protection require-(80-566) ments in Appendix R to 10 CFR Part 50 under the Commission's final rule on " Fire Protection Program for Operating Nuclear Power Plants,"
made available one document.
(Individuals requesting In response to requests for copies of the information about themselves) transcript of their Senior Reactor Operator (80-579,80-580,80-581)
License exam results, made available this information.
Denied Charles W. Elliott In response to a request for documents pertaining (80-544) to five categories of information regarding spent fuel shipments traveling on certain routes in the Commonwealth of Pennsylvania, made available 12 documents. Denied portions of five documents containing safeguards information.
(NRC employee)
In response to a request for documents pertaining (80-567) to the selection for Vacancy Announcement 80-3428, made available three documents.
Denied portions of two documants, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
Martin Levy, In response to an appeal, on behalf of an NRC NTEU Steward employee, for a copy of the Personnel Performance (80-A-30-80-492)
Appraisals for three named individuals, continued to deny this information, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
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DIVISION OF CONTRACTS Week Ending December 5,1980 RFP'S ISSUED 1.
RFP RS-RES-81-235 4
Title.- Seismic History of the Eastern Seaboard from New York to Norfolk, Va.
Description - The work to be accomplished under this contract comprises a comprehensive search of all available records in major repositories throughout the northeastern United Stated for the purpose of discoverina new infomation on earthquake occurrence and effects. The region to be surveyed extends from New York City to Norfolk, Virginia, and includes the Appalachian Mountains within its western bcundary. The historical period to be covered' extends from the earliest records available up to 1930. The results of this search is to be published in a catalog, suitable for interfiling with existing catalogs.
Period of Performance - One year Sponsor - Office of Nuclear Regulatory Research Status - RFP issued November 26, 1980.
Proposals are due January 5, 1980.
2.
RFP RS-ADM-81-389 Title - Holding Public Meetings Amid Conflict Description - To develop and conduct a course on planning and conducting meetings where conflict is anticipated in public co...ent.
Period of Perfomance -' Ten weeks Sponsor - Office of Administration l
Status - Letter RFP issued December 1,1980 to USDA, Graduate School.
Proposal due December 12, 1980 l
l PROPOSALS UNDER EVALUATION 1
l RFP RS-NRR-81-138 Title - Technical Assistance in Support of NRC's Reactor. Licensing l
Actions (Program II)
Description - The purpose of the proposed contract is to provide support to NRR for the management and review of 300 backlog operating reactor licensing actions.
Ultimate decisions regarding the acceptability of the proposed licensing actions will be made by NRR after review of the contractor's evaluation and recomendation.
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Period of Performance - Two years Sponsor - Office of Nuclear Reactor Regulation Status - Best and Final offers due on December 8, 1980.
ENCLOSURE A l;-
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CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
Contract No.
Contractor Close-Out Date AT(49-24)-0033 Thorion Industries 12/1/80 AT(49-24)-0287 Price Waterhouse 11/28/80 AT(49-24)-0173 Project Software & Development 11/28/80 AT(49-24)-0306 Edwards Trucking 12/4/80 AT(49-24)-0257 Sport Chevrolet Co.
11/26/80 NRC-10-79-398 Dictaphone Corp.
11/26/80 o
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ENCLOSURE A i
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DIVISION OF SECURITY dEKLY INFORMATION REPORT WEEK ENDING DECEMBER 5, 1980 The draft of a Comprehensive Automated Information System Security Plan (AISSP) ta meet the requirements of OMB Circular A-71, Transmittal Memorandum Number 1, was issued and distributed to all Directors of Offices and Divisions for cocrnent on November 24, 1980. Comments are requested to be returned to the Division of Security by January 2,1981.
The Facilities and Systems Security Branch (FSSB) conducted a periodic security survey at Reg' ion II, Atlanta, Georgia, on December 4-5, 1930.
It resulted in the assignment of a satisfactory rating.
1 The Division of Security received comments ft om the Office of Inspection and Enforcement (0IE) on all security plans previusly submitted by licensee facilities under 10 CFR Parts 25 and 95. The receipt of these ten plans completes inter-office coordination.
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s NRR HIGHLIGHTS (December 1 - 5, 1980)
North Anna Power Station, Unit 2 The resident inspector at North Anna Power Station advised that during the weekend the Unit 2 main generator step up transformer had a fault which caused damage to the bus duct system between the generator bus terminal and the transformer. There were minor fires in the area which were caused by the hot metal. The reactor tripped and all snutdown systems responded satisfactorily.
Divis-Sesse, Unit No. 1 At 9:23 am on December 3,1980, the reactor tripped due to a reactor coolant pump trip.
Following the reactor trip, the main steam isolation valves closed. The operators then manually actuated the Steam and Feed Line Rupture Control System (SFRCS), which then allows steam generator level to be controlled automatically by the auxiliary feedwater system.
Actuation of SFRCS should start both auxiliary feedwater pumps; however, one of the pumps did not start automatically and required separate operator action to start.
ihe causes of the failures have not yet been identified. The Office of Inspection and Enforcement is reviewing the event to ensure the causes of failures are identified and corrected prior to allowing the plant to again operate.
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NRC iMI-PROGRAM 0FFICE WEEKLY STATUS REPORT Week of November 23 - Cecenber 6,1980 Plant Status Core Cooling Mode: Reactor coolant System (RCS) nect transfer to reactor building ambient (air and sump water). !
Available Core Cool;ng Modes: 0TSG "A" or "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: One of two decay heat removal pumps to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST) to provide control of pressure.
Major Parameters (As of 0500, December 5,1980) (approximate values)
Average Incore Thermocouples: 1340F Maximum Incore Thermocouple:
1680F RCS Loop Temperatures:
A B
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Hot Leg.
1290F 1320F 0
0 71 F 70 F Cold Leg (1) 0 0
70 F 70 F (2)
Pressurizer Temperature: 720F 0
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Reactor Building:
Temperature: 65 F Water level: Elevation 290.5 ft. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.5 psig (Heise)
Concentration: 1.4 x 10-4 uCi/cc (Kr-85) (sample taken 12/4/80)
Environmental & Effluent Information 1.
Liquid effluents from TMI-l released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
2.
No liquid effluents were discharged from THI-2.
3.
EPA _ Environmental Data. Results from EPA monitoring of the environment around the TMI site were as follows:
-ENCLC3URE B
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EPA Environmental Data. Results from EPA monitoring of the environment around tne TM1 site were as follows:
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The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m3) at several environmental monitoring stations and reported the following results:
Location November 21 - December 1, 1980 3
(pCi/m )
Bainbridge 18 Goldsboro 22 Observation Center 22 Middletown 19 All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and gama rate networks during the period from Hovember 26 through December 4,1980.
4.
NRC Environmental _ Data. Results from NRC monitoring of the environment around tne TML site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-131 Cs-137 Samole Period (uCi/cc) (uCi/cc)
HP-244 November 26 - December 3, 1980
<7.9 E-14 <7.4 E-14 5.
License _e Radioactive Material and Radwaste Shioments_. The following shipment was made:
On Monday, December 1,1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Vi rginia.
Ma_ior Activities 1.
Reactor Decay Heat Cooling. The loss of Decay Heat to Ambient Test
(_ transfer of reactor decay heat to the reactor building ambient) is continuing. A decrease in key plant temperatures is noted since l
the start of the test on November 6, 1980. Short period review of l
thermocouple data indicated an apparent decrease of approximately 60F for the average value of the incere thermocouples (1400F to 1340F) and the hottest loop hot leg temperature decreased approximately 60F (1380F to 1320F).
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The licensee will be submitting a proposal to the NRC to justify the shutdown of the secondary plant "or long term layup based on test data and this includes finalizing the special operating (test) procedure to a formal operating procedure.
2.
Reactor Building P_ urge / Entry.
The fifth entry into the Unit 2 reactor builoing is seneduled for Thursday, December 11, 1980. A pre-entry purge was conducted on Thursday, December 4,1980. An estimated six curies of Kr-85 was released during tnis period. A second purge is scheduled to commence Tuesday, December 9, 1980.
This purge will continue through the entry. The objective of the second purge is to minimize Kr-85 concentrations during operations inside the reactor building.
The planned tasks inside the reactor building include replacement of the neutron source range preamplifier, decontamination experiments, and additional radiation mapping. The decontamination experiments are designed to test the effectiveness of various decontamination solutions. A detailed radiation map will be made on the 305' elevation and a three man team will climb into the refueling pool (presently dry) to take radiation readings in the vicinity of the reactor head. One of the entrants will climb a vertical ladder to the polar crane to assess the condition of the crane.
3.
Contamination of Building Exoansion Joints.
During a radiological survey of the 281' elevation of the Unit 2 auxiliary building on November 27, 1980, contamination was found in an expansion joint.
The expansion joint lies between the service building on one side and the auxiliary building and the air intake tunnel on the other
. side. Further licensee investigations revealed contamination in a second expansion joint which is contiguous to the first and which circles the reactor building. The expansion joints appear to be mere highly contaminated towards the seal injection room which is adjacent to the reactor building and through which the second expansion joint runs. The seal injection room is currently inaccessable because of high radiation levels as a result of previous reactor coolant system leakage. The contamination has been identified as l
including CS-134, CS-137, Ru-106, Sb-125, Ce-144; and Sr-90. Water samples taken from the expansion joint by the licensee, showed cesium activity of 0.85 - 1.7 uCi/ml.
The licensee has implemented a plan to determine the source and the extent of the contamination.
The on site NRC staff will continue to closely monitor the licensee's actions in this area and licensee's plan.
The plan includes taking core samples of the expansion joints and excavating to monitor the outside edges of the expansion joints.
ENCLOSURE ~B l
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Long Term _, Spent _ Resin Storage Fa,cility. During this rernrting period the licensee received the analysi,% rasults from L contractor laboratory on a water sample from the sump used to collest crainage for the Long Tarm Spent Resin Storage Facility (Module A and 3).
Gamma spectroscopic analyses indicated trace amounts (1.2 x 10-8 uCi/ml) of Cs-137.
Tritium analysis indicated 3 x 10-5 uCi/ml.
The licensee strongly suspects that this activity is due to rain water inleakage picking up known liner loose surface contamination and tritium vapor offgassing through liner fittings.
Module A has been in use as a repository for EPICOR-I snd EPICOR-II spent resins since early 1980.
The nodule nas 60 cells.
Each cell can accommodate one 6' x 6' (nominal external dimensions) liner or two 4' x 4' line rs.
Presently the A module contains approximately 50 liners. The S module is strucurally con.ciete but is empty at the present time.
Water drains are provided at the bottom of edch storage cell.
Ine drains from both the A and B modules flow to a common sump.
Collected sump water is being stored onsite for processing and onsite storage.
NRC review of the licensee's surveillance program in this area continues.
Meetice Attended On Friday, December 5,1980, L. Barrett attended a meeting with the Atomic Industrial Forum Working Committee on TMI-2 Recovery, to discuss the NRC's site office role in cleanup operations of TMI-2.
Future Meetings 1.
On Thursday, December ll,1980. L. Barrett and R. Bellamy will attend a public briefing in Harrisburg sponsored by the Department of Environmental Resources on the status of decontamination at Three Mile Island. Representatives from General Public Utilities (GPU) and the U.S. Environmental Protection Agency will also be participating in the presentation.
2.
On Friday December 12, 1980, L. Barrett and R. Bellamy will attend a meeting in Parsippany, New Jersey, with GPU and Met-Ed to discuss proprietary information concerning EPICOR-II radwaste system.
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ENCLOSURE B i
9 0FFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING DECEMBER 5,1980 1.
Member State Comments on IAEA Draft Safety Guide SG-D7, " Emergency Power Systems at Nuclear Power Plants" By letter dated December 3,1980 from Joseph D. Lafleur, Jr. to John Trevithick of the Department of State, Member State comments are being transmitted to the IAEA on draft safety guide, SG-D7.
We are strongly recommending that the IAEA incorporate the substance of certain U.S. comments into SG-D7; however we are not recommending that publication of the guide be delayed unduly because of differences over these items.
In other words, the guide would be improved, in our view, and made more consistent with U.S. practice if the comments are incorporated, but the guide contains important provisions which should be published in any event without further delay.
SG-D7 contains provisions intended to meet the objectives and minimum requirements of Part 7 of the IAEA Code of Practice -Design for Safety of nuclear Power Plants. SG-07 provides general guidance for all types of emergency power systems (EPS), and gives, in Appendix A, specific guidance on emergency electric power systems (EEPS).
The contents of SG-D7 cover most of the same subjects as the relevant portions of 10 CFR Part 50, Appendix A, Criterion 17 (Electric Power Systems), and Regulatory Guides 1.6, 1.9, 1.32, 1.47, 1.53, 1.75, 1.81, 1.93,1.108,1.118,1.128 and 1.129.
The goals of SG-D7 and applicable U.S. documents addressing emergency power systems are similar; however, there are differences between American practice and the provisions of SG-07, Rev. 6.
The most significant difference is the SG-D7, Sec. 3.1.2 recommendation that in evaluating power grid stability, the stability be considered when the second largest generating unit is forced off, when the largest unit is already-disconnected, i.e. the two largest units are off.
It is current U.S. practice to only consider grid stability : hen the largest generating snit is forced off.
With respect to the remaining differences between SG-D7 and current U.S.
practice, the recommendations of the safety guide are less demanding.
Thus, U.S. cractice requires r.t least two offsite transmission lines; SG-D7 permits one. SG-07 fr: plies that the nuclear plant capability to run back to house load, without' tripping on loss of load is sufficient compensation for the use of a single offsite transmission line; the U.S.
does not.
SG-D7 pernits qualification of emergency power system equipment by analysis alone; the U. S. does not.
SG-07 allows automatic connections between independent EEPS safety divisions; the U. S. does not.
SG-D7 racommends that plant battery chargers have the capacity to recharge plant batteries'in an acceptable time; U.S. practice limits acceptable time to eight hcurs. And finally, SG-07 requires a plant battery capacity of only
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thirty minutes at full load; the U.S. requires two hours for PWR's and four j
hours for BUR's.
ENCLOSURE C i
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Degraded Cooling Steering Group meeting: On November 26, 1980, the Degraded Cooling Steering Group met for approximately four hours to continue the coordination of staff efforts related to degraded cooling rulemaking.
A main item of discussion concerned a draft document, presented at the meeting by RES, entitled " State of Technology Report on Release of Fission Product Iodine." The objective of the proposed report would be to provide the Commission with the best available technical information concerning accidental release of radioactive iodine. RES explained that such a document is necessary in view of facts and opinions being published by industry and Government laboratory representatives indicating that traditional assumptions concerning accidental iodine release may not only be overly conservative but simply wrong. The draft RES document goes on to explain that "This report is to be a dispassionate reporting of facts and available bases for informed judgment..." The Steering Group endorses the RES proposal provided a parallel program goes forward "in-house" to put the RES proposal in proper perspective; the Group intends to make a recommendation to the EDO.
Another item of discussion concerned the Severe Accident Sequence Analysis (SASA) program recently instituted by RES. RES explained the program in detail and requested that the Steering Group indicate whether or not it supports the program.
The Steering Group concluded that the SASA program should be continued for another two months but that user office endorsement be required before the program goes forward on a full scale. The Group has forwarded its conclusion to Mr. Minogue by memo.
Other subjects covered were a November 26, 1980 memo from Bernero to Arlotto entitled " Decisions for the DCC Rulemakings" and a presentation by Conti, SD, updating the rulemaking action plan. Both subjects will be discussed in more detail at subsequent meetings.
3.
Training Course for Certified Health Physicists: Thirty health physicists on tne NRC headquarters staff are certified by the American Board of Health Physics.
This relatively large number of Certified Health Physicists (CHP's) is a significant asset and resource to the Commission.
CHP's must complete a prescribed number of continuing education units every four years to retain their certified status. To assist NRC CHP's in this regard, SD organized and presented a series of training courses designed to satisfy these education requirements. The courses involved 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of instruction i
on five topics -- radiation epidemiology, respiratory protection, radiation genetics, environmental and internal dosimetry, and environmental aspects of nuclear reactors.
Instructors were NRC staff personnel, NRC contractor personnel, and NRC consultants.
In addition to NRC CHP's, the series was open to other NRC staff members and to other CHP's residing in this area.
The first training session was held July 7,1980; the final one was held December 3,1980. The series of courses was approved by the American Board of Health Physics and will enable most of the NRC CHP's to retain their certification.
(Contact:
R. E. Alexander 443-5975)-
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Meeting with Dr. William Brandom, University ~of Denver, December 4,1980:
A meeting was held with Dr. William Brandom, Professor of Biological Sciences at the University of Denver, to discuss the preliminary results of cytogenetic analyses done on residents of Grand Junction, Colorado (high radon environment due to mill tailings) and Greeley, Colorado (control population).
The cytogenetic analyses were part of a feasibility study funded by the Environmental Protection Agency to determine the biological effects of exposure to radon and radon daughters. NRC is funding the second year of the cytogenetic portion of this study which will examine the use of c,cogenetics as an indicator of low-level radiation exposure.
Also discussed were the merits of: 1) having a baseline chromosome registry of nuclear workers in case of overexposures; and 2) establishing a system similar to the British National Radiological Protection Board system which utilizes cytogenetic analyses to estimate the dose received by individuals thought to have been overexposed to radiation when either their conventional physical dosimeter indicates an "off scale" exposure or when the worker was not wearing a dosimeter.
(Contact:
D. Flack 443-5860)
Publications Issued During the Week of December 1-5, 1980 Draft Regula. tory Guide and Value/ Impact Statement: Second Proposed Revision 3 to Reg. Guide 1.33, Quality Assurance Program Requirements (Operation), Task RS 902-4 (Comments requested by January 30, 1981)
Reg. Guide 3.44, Rev.1: Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)
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ENCLOSURE C
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest 4
Week Ending December 5,1980 US/IAEA Safeguards Agreement NMSS staff provided assistance to the State Department in finalizing the initial U.S. eligible facilities list. The State Department has indicated they intend to deliver this list along with the written comernication required to put the agreement into force, to the IAEA on December 5,1980.
Subgroup on Nuclear Export Control Meeting (SNEC)
During the November 20, 1980, SNEC meeting, NRC's proposed amendment to Part 110 to permit export of small samples to IAEA labs under the U.S. Voluntary Offer was discussed. Concern was voiced by Executive Branch members in reference to the NRC approach which considers such export transactions as having a non-nuclear end-use. No formal counter-proposal was offered, however, and the different agencies represented at this group will continue to review the matter.
Commerce's drafting of changes to their pertinent export licensing reggiations to contro1' technology not on the " Nuclear Referral List" continues. A purpose of the proposed changes is to prevent certain technology and non-nuclear equipment from going to unsafeguarded facilities.
ISIS Source Evaluation Panel Meeting On December 2,1980, the ISIS Source Evaluation Panel held its first meeting to discuss the Request for Preposals (RFP). The DOE representative on the panel indicated that DOE requirements will not be available before the end of February 1981, and will then be subject to review.
l Specific changes will be made to the present RFP (originally prepared in February of this year) responsive to anticipated guidance from the Ccamission l
related to the'0PE examination of ISIS.
The Panel inteads to prepare the RFP for release early in 1981.
Advanced Material Accounting Svstem Simulation (AMASS) f On December 5,1980, the kickoff meeting will be neld for the project,
" Evaluation of Material Accounting Performance at fluclear Fuel Cycle Facili ties". NUSAC, Inc., was awarded the' contract to assist the NRC in applying the Advanced Material Accounting System Simulation (AMASS) to six nuclear fuel cycle facilities over the next 24 months. The first facility.
I to be evaluated is Nuclear Fuel Services, Erwin, Tennessee. The schedule l
for this evaluation will be established at this first meeting.
ENCLOSURE-D I
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Items of Interest 2
Wood River Junction Public Meeting On December 2, at the request of the State of Rhode Island, a-public meeting was held in Wood River Junction to inform the public of the progress of the decontamination effort at the United Nuclear facility. Also of concern was the status of the waste shipments to Nevada which received a considerable amount of publicity recently when the State of Nevada returned six truckloads of waste to UNC which had been destined for burial. The meetino was chaired l
by state officials and the NRC was represented by members of IE, SP and NMSS staffs. A considerable amount of interest was centered around issues that were discussed in previous meetings held in July of this year. These iters were as follows:
1.
Status of a deep monitoring well, previously suggested by USGS, to evaluate the vertical extent of groundwater contamination under the UNC site. USGS, the state and NRC are working together to establish the optimum location of the well, plus-the appropriate samples to be taken.
I 2.- The public was briefed on the status of the investigation concerning the processing of zero-power fuel at the UNC.
The main interest centered around the 1976 to 1980 period when this material was processed without license authorization. This is an ongoing investigation by IE.
3.
Status of IE's investigation into the allegations concerning burial of wastes on site.
IE reported that two burials had been made in the early days of plant operations and that both had since been dug up and transferred to a licensed burial ground. Both burials were made in accordance with regulations existing at that time.
4.
Status of IE's1 proposed domestic well sampling program to determine if-the contamination in the aquifer has not migrated offstte.
Also discussed were recent stories in the press concerning the disposal of liquid wastes from lagoons to the environs by UNC. A former guard has alleged that UNC personnel had pumped liquid process waste containing radionuclides from the lagoons into a nearby ditch and that lagoon liners had been deliberately ounctured to allow the liquid waste to migrate into the soil.
IE stated that this would be'the subject of a future investication.
3 ENCLOSURE D
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Items of Interest 3
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The Governor has appointed a Citizens Advisory Council which is comprised of a member from each of four communities surrounding the UNC facility. This Council will provide input to the State to assure public awareness of the actions taken by UNC, the State and NRC during the decommissioning process.
Each Council member presented a list of concerns which will be subject to review by the staff. Several local citizens groups also presented a list of demands to be considered by the state, NRC and the licensee. The Concerned Citi:: ens of Rhode Island (CCRI), which has been very vocal regarding alleged license violations at. United Nuclear as well as the environmental effects of the acquifer contamination under the UNC property, demanded an opportunity for a nearing so that they could have input into the decommissioning process prior to any staff action. They were informed that the NRC's regulations provide any individual or group an opportunity to petition for a hearing and that CCRI's legal council, who is very familiar with these procedures, had been so informed.
Visit to Mallinckrodt Chemical Plant, St. Louis, Missouri On Tuesday, December 2, two members of the Material Control and Accountability Licensing Branch visited the Mallinckrodt Chemical Plant in St. Louis, Missouri to obtain information on the measures employed by the facility to protect and account for centrolled substances. Discussions were held with two accompanying DEA inspectors on their role in enforcing government replations covering bulk manufacturing of controlled substances.
U.S.-Canadian Bilaterial Discussions Members of the Safeguard's staff participated in US-Canadian Bilateral Discussions on Nuclear Terrorism hosted by DOE, December 2-4, 1980.
Included in the Agenda j
was a briefing by the NRC staff on the Insider Study (NUREG-0703).
Propzed MC&A Uparade Rule The proposed MC&A Upgrade Rule has been distributed for concurrence by the Offices of Inspection and Enforcement, Standards Development, and the l
Executive Legal Director.
It is anticipated that the rule will be forwarded i
to' the Connission at the end of December.
Licensee Transportation Activities in Possible Non-compliance with Part 71 l
On November 26, 1980, a notice was mailed to approximately 170 NRC radiography licensees stating that all their transportation activities may not be conducted in accordance with 10 CFR Part 71. The letter noted that they neither were registered with NRC for any shipping packages nor had an NRC approved quality l
Licensees who fail to respond to the letter will be referred assurance program.
to IE for followup action at a later date.
ENCLOSURE D
Items of Interest 4
West Valley Demonrtration Project On December 3,1980, members of NMS5 and ELD staffs met with DOE to hold initial discussions concerning the interagency agreement required by the West Valley Damonstration Project Act. This agreement will define the interrelationship between agencies necessary to accomplish NRC's role for review and consultation during the course of the activities conducted by DOE under the project. During this first meeting a preliminary draft of the interagency agreement prepared by DOE was reviewed and discussed, and general requirements to revise and expand several of the draft sections were identified. A second meeting has been tentatively scheduled for December 17, 1980.
1 ENCLOSURE D
OFFlCE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST Week Ending Decenber 5,1980 1.
Preliminary Notifications relating to the following actions were dispatched during the week; a.
PN0-I-80-167A Undeveloped Land, Rochelle Park, New Jersey - Radioactive Material in a Restricted Area (Update) b.
PNO-I-80-172 Indian Point Unit 2 - Contamination of an Individual PNO-II-80-167 H. B. Robinson 2 (CP&L) - Primary Coolant System Leak c.
d.
PNO-II-80-168 North Anna Unit No. 2 - Failure of Main Generator Output Bus e.
PNO-III-80-218 Clinton 1 - Slippage in Fuel Load Schedule f.
PN0-III-80-219 Point Beach 1 - Reactor Trips Caused by Closure of the Main Feedwater Regulating Valve g.
PNO-III-80-220 Dresden Unit 2 - Reactor Trip and Scram Discharge Volume Level Monitoring System Malfunction h.
PNO-III-80-221 Palisades Nuclear Power Plant - Equipment Problems Resulting in Extending a Plant Shutdown for More Than Two Days
- i. PNO-III-80-222 Davis Besse 1 - Reactor Shutdown Exceeding Two Days
- j. PNO-III-80-223 Zion Station, Unit 1 - Equipment Problems Resulting in Plant Shutdown in Excess of Two Days k.
PN0-IV-80-39 Wolf Creek Generating Station (KG&E) - Work-hold Agreement Related to Safety-related Piping at the Wolf Creek Generating Station 1.
PN0-TMI-80-52 Three Mile Island, Unit 2 - Contamination of Expansion Joints m.
PNS-I-80-25 Millstone Nuclear Power Station, Unit II - Senior Reactor Operator Involved in Fatal Shooting n.
PNS-II-80-32 and 32A Brunswick 1 and 2 (CP&L) - Bomb Threat 1
2.
The following IE Circulars were issed:
IE Circular 80-24, "AECL Teletherapv Unit Malfunction," was issed on a.
December 2,1980 to all teletherapy licensees.
b.
IE Circular 80-25, " Case Histories of Radiography Events," was issued on December 5, 1980 to all radiography licensees.
ENCLOSURE E 2
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The following Information Notice was issued:
a.
IE Information Notice 80-29 (Supplement No.1), " Broken Studs on Terry Turbine Steam Inlet Flange," was issued on November 26, 1980 to all Light Water Reactor Facilities holding power reactor Operating Licenses or Construction Permits.
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OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST' WEEK ENDING DECEMBER 5, 1980 Davis-Besse Nuclear Power Station, Units 2 and 3 On December 1, 1980, the Appeal Board issued a Memorandum and Order (ALAB-622) with respect to the applicants' request of November 17, 1980 to withdraw their applications for permits to construct.Unitsi2 and 3.
The Appeal Board struck from its docket two ASLB partial decisions relating to Units 2 and 3 which were subject to appellate review sua sponte and remoy_ed this. proceeding from the list of proceedings in which appeal boards are considering the generic issue of radon releases. The Appeal Board also stated that the applicants' request for full termination of this proceeding must be directed to the ASLB.
Three Mile Island Nuclear Station, 'Jnit 1 (Restart)
On December 5, 1980, the Commission issued a Memorandum and Order (CLI-80-39) with respect to the question certified by the presiding ASLB as to whether the issue of psychological stress can be legally relevant to this proceeding.
By a divided vote of 2-2, the Commission directed the ASLB not to consider the issue of psychological stress and to deny all contentions related thereto. The Commission also decided to reconsider the natter when a fifth Commissioner was appointed and confirmed.
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ENCLOSURE G
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ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 5, 1980 Italian Earthauake Effect IP received notification from CHEN, Italy on December 4, reporting on the effects of the recent earthquake on two Italian nuclear power plants:
Latina (a GCR) and Garigliano (a BWR). Garigliano is located about 150 km, and Latina about 200 km, from the earthquake epicenter. Both plants were shut down at the ' time of the earthquake. Although both plants felt t.he carthquake, no known damage or abnormal consequences were sustained by either plant. Ground accelerations recorded at both plant sites have been forwarded to the appropriate staff offices.
Notification of Korean Nuclear Officials of Lost Radioactive Material IP this week used the Department of State cable network to officially advise the Korean Administrator of the NRC-Korean Nuclear Regulatory Bureau (NRB) i information exchange arrangement of the apparent loss during 1979 of a package containing 10 medical applicators, containing a total of 125 MCI Cesium 137, being shipped by the 3M Company to Seoul, National University Hosoital (PNO-III-80-212). (Word over the loss had only recently reached l
NRC.) Although DOT had already nctified the Ministry to which NRB reports, NRC repeated the message to assure delivery and to fulfill our obligation under the arrangenent to notify the NRB when such potential safety problems are discovered. The staff is continuing to review circumstances surrounding the loss of the material and reporting of the loss to NRC.
- Progress on Renewal of Arrangement with the British i
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ENCLOSURE H
2 Bangladesh Agreement for Cooperation IP received from State a copy of the U.S. - Bangladesh Agreement for Cooperation and a reauest for formal NRC views. Staff is reviewing the agreement and plans to forward it to the Commission the week of December 8.
Meeting with Monsanto Officials On November 3, IP representatives met with Messrs. Taylor and Schimmel from the Monsanto Corporation. Topics discussed included the status of Monsanto's pending export license application for 1 mg of Californium-252 for India and the status of the proposed amendments to NRC's export regulations regarding l
byproduct material.
Foreign Visit to NRC On Tuesday Mr Antonio Carraminana nf the Spanish Junta de Enercia Nuclear c
(JEN, NRC's rgulatory counterpart) met with D. Sells of LB-2/NRR to discuss technical issues related to a Spanish facility for which the South Texas Project is a reference plant.
- Foreign Reoorts l
- Deleted from PDR copy.
ENCLOSURE H
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OFFICE OF STATE PROGRAMS l
ITEMS OF INTEREST WEEK ENDING DECEMBER 5, 1980 A meeting of the State Liaison Officers will be held at the H Street offices on December 9 and 10.
Chairman Ahearne, Mr. Dircks and several NRC offices will make presentations to the S LO ' s.
Governor Ella Grasso has written Chairman Ahearne indicating I
Connecticut is interested in becoming an Agreement State.
The staff plans to arrange a meeting with Connecticut officials to discuss the program.
Joel Lubenau represented NRC at a planning meeting of the Radiation Policy Council's staff on Roles and Functions of Federal and State Relations.
Bill Menczer, RSLO, Region III, met with the Regional Advisory Committee in Glen Ellyn, Illinois on December 2 to plan future RAC activities and exercises.
Bob Trojanowski, RSLO, Region II, participated in a number of emergency planning activities during the week of December 1 - 5.
On December 2 and 3 he was in Columbia, S. C. with State officials and later that week he participated in the McGuire EP exercise in North Carolina.
During the week he also met with the Tennessee State Liaison Officer, met with the Fairfield County j
(S.C.) Administrator to discuss EP matters relating to the Summer Facility and attended a public meeting to discuss a recent problem at the Nuclear Fuel Services facility in Irwin, Tennessee.
On December 3, 1980, the Illinois State Legislature overrode t
Governor James Thompson's veto of a bill which bans the 1mportation into the State of spent nuclear fuel from States that do not accept spent fuel from Illinois' power plants.
The implication of this action is that spent fuel from the San Onofre Power Plant cannot be shipped to Illinois for interim storage at the Morris Operations Facility in Morris, Illinois.
San Onofre is currently the only power station that ships spent fuel into Illinois.
It is anticipated by State officials that the legislation will be challenged in court on the constitutional grounds of restricting interstate commerce.
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i ENCLOSURE I l
OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS J
Items of Interest WEEK ENDING DECEMBER 5, 1980 TMI Action Plan Tracking System Briefed the Chairman on the Action Plan Tracking System.
NFS Erwin Report Briefed EDO on report on inventory differences, concentrating particularly on statistical bounds on adjustments to the reported differences.
Information for Transition Group (1) At request of Mr. Kennedy updated the information in the Basic Facts Book and Program Area Briefing Book given earlier to Mr. Carnesale.
(2)
Assembling response to additional request for information from the Group.
Abnormal Occurrence Published 2nd Quarter CY-80 Report to Congress.
WITS-II f
Briefed AEDO on basic reports for EDO segment of WITS-II.
Value-Impact _
Briefed EDO on status and problems associated with value-impact analyses.
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0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING DECEMBEk 3, 1980 An AE00 report on the June 11, 1980 event at St. Lucie has been completed.
This event involved a natural circulation cooldown following the simul-taneous loss of compcaent cooling P'r to all reactor coolant pumps.
During the natural circulation cooldown, a rapid depressurization of the Reactor Coolant System (RCS) caused the relatively stagnant reactor coolant in the upper head of the reactor vessel to flash creating a steam bubble.
The presence of the steam bubble in the reactor vessel head resulted in large oressurizer level oscillations caused by alternately shifting the alignment of the charging pumps between the cold leg and the auxiliary spray connection in the pressurtzer. Although the voiding of the reactor vessel head does not represent an immediate safety concern, this office has developed recommendations, based on our investigation of this event, that should be considereu. Of the recommendations made, the most important concerns operator training and development of operating procedures. The rapid depressurization of the RCS during natural circula-tion, for example, resulted in a plant condition that was not anticipated by the plant operators. ~ The fact that the plant behavior did initially puzzle the operators clearly indicates that guidance needs to be developed such that operators are aware of what conditions will lead to voids in the primary system, other than the pressurizer, how to recognize the presence of voids, and how to either cooldown the RCS with voids or collapse the voids.
l The AEOD report ccntains a detailed description of the event, along with our findings, recommendations, and conclusions. Arrangements are in progress to
.. ave the report reviewed for factual content by NRR, IE, and the utility (plant management) prior to the formal issuance of the report. The formal issuance is expected next month. A copy of the report is being placed in l
the PDR at the same time it is issued to other organizations.
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AE00 also issued a report on the AE0D Actions on the Crystal River 3 Loss of Non-Nuclear Instrumentation and Control Power Event. This report documents l
AEOD's involvement and conclusions regarding this event. AEOD's recommenda-l tions associated with the study of this event have been forwarded previously l
to NRR for appropriate action. Thus, this report contains no additional items warranting specific review or action.
i ENCLOSURE L i
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ITEM 5 APPROVED BY THE COMMISSXON - BEEK EWDhG DECEMBER 5,1980 l
n Ao SECY-80-419. - NUCLEAR EXPORTS TO SWITZERLAND (COMMfSSXONER ACTXON ! TEM).
Memo--
5ECY to Dircks, dtd 12/4/80.
This is to advise you that the Cc= mission's action with reseect to a' letter forwarded by Chairman Ahearne to Dr.'ar:e:inski cf the White Ecuse en November 24, 1980 is considered to have completed action on the subject paper.
The office of International Programs was informed of this mattet by telephone on December 3, 1980.
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SECY-80-505 - RESPONSE TO GAO RECOMMENDATIONS ON ELECTRICITY PLANNING (COMMISSIONER ACTION ITEM. Memo SECY to Dircks, dtd 12/4/80.
This is to advise you that the Cc=ission (with all Commissioners approving) has approved the propcsed NRC cc=ents to Congress, as modified by the changes centained in the attached final.
drait Le::er.
The Office of Nuclear Reactor Regulation was informed of this action by telephone on December 4, 1980.
s.
It is recuested that you rev'.se the letter per the attached
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draft and forward final versions for all Congressional addressees for the signature of Chairman Ahearne to the Office of the Secretary by c.o.b. December 8, 1980.
C.
SECY-80-356A - PROPOSED REPROCESSING RETRANSFER FROM SWITZERLAND (BEZNAU) TO U.K.
(COMMISSIONER ACTION ITEM). Memo SECY to Dircks, d d 12/4/80.
This is to advise you that the Cccmission's action with res:ect to a letter forwarded by Chaiman Ahearne to Dr.'3r:ezinski of the White Ecuse on November 24, 1980 is l
considered to have ce=pleted action en the subject paper.
l The Of fice of International Programs was informed of this matter by telephone en Dece=her 3, 1980.
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SECY-80 497 E'!IEW 0F DELEGATIONS OF AUTHORITY AND OTHER DOCUMENTATION (COMMISSIONER ACTION ITEM).
Memo SECY to Bickwit/Manranan, etc 12/5/80.
This is to advise you that the Cc=ission (with all Cc::nissioners i
apercving) has appreved ycur rece mendation that no revisions cf the delegatien Of authority are reenized at this-time as a result of implementation cf Recrganizaticn Plan No. 1 of 1920.
In ccnnection with his appreval, Chai man Ahearne provided' the fellowing cc=ent:
"Suggest issue be reexamined wnen new Chai=an. is appointed. "
The Cffices of the General Counsel and ?cliev Ivaluation
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were infc = ed of-this action bv telephone en December S, 1980.!D" D
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ENCLOSURE N
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STA: F REQUIREMENTS - DISCUSSION AND V0TE,11:00 A.'M., FRIDAY, NOVEMBER 21, 1980, COMMISSIONERS' CONFERENCd ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Kammerer/Fouchard, ata 12/2/80.
I.
SECY-80 475 - Recortino of Physical Security Events The Commission discussed the proposed final rule contained in the subject paper.
The Commission by a vote of 4-0 approved the' final rule as modified:
- to clearly state the relationship between the strategic significance of nuclear material and the reporting-requirements; (SD)
- the definition of the reporting time period be modified as in
-Attachment 1.
(SD)
The Commission noted that:
1.
the a endments are to be published in final form in the Federal Register; (SD) (SECY Suspense: 12/22/80) 2.
upon publication of the amendments, the revised guide (Enclosure B
. of the subject paper) is' to be published concurrently; (SD) (SECY Suspense: 12/22/80) the appropriate Congressional coanittees are to be notified; 3.
(SD) (SECY Suspense: 12/22/80) 4 a public announcement (such as Enclosure 9 of the SECY paper) is to be issued when the amendments are filed with the Office of the Federal Register; (OpA/SD)
(SECY Suspense: 12/22/80) 5.
approval by the General Accounting Office of the report requirements in the prop 1 sed rule is to be obtained.
(ADM/SD) (SECY Suspense: 2/10/81)
II., SECY-80 457 - EDO Delecation of Authority The Commission discussed the EDO delegation of authority and approved several codifications.
(See Attachment 2)
The Commission requested that:
l 1.
OGC draft a separate subsection to 0103.02 to cover budget control's executien 2.
OGC draft language as proposed in Attachment 2, p.3; 3.
OGC draft alternative language to 0103-031 (See Attachment 2, p.3)
(Subsecuently the Office of the General Counsel has indicated.that they will be preparing a memo suggesting alterr;tive language for all items in which the Commission was unable to agree.)
ENCLOSURE N 6
e SCllEDULED SPEAKillG ENGAGEMENTS Date Organization Loca tion Subject Speaker 12/?2/80 ORNL Conference on Leach-Gatlinburg, TN Leachability as an Element in John D. Randall ability of Radioactive Regulatory Strategy (co-authored Solids by D. M. Sollenberger). Aspects of leachability. are discussed in contexts of IlLW, LLW, and leach tests.
3/26/01 22nd Annual Quality Clinic / Knoxville, TN What the NRC Regulations W. Ruhlman, R0 II' Require from a QA Program 3/31/81 American Chemical' Society Atlanta, GA Regulatory Implications of II. Peterson, SD Radiation-Dose Effect Rela tiortships 4/1/01 Spouses of Operating Staff Education Center Quality Assurance Requirements A. Cerne, R0 I at Seabrook Station Seabrook, Nil and Iicensing Procedures Related to Seabrook Station ENCLOSURE 0