ML19320D097
| ML19320D097 | |
| Person / Time | |
|---|---|
| Issue date: | 07/10/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-800703, NUDOCS 8007180544 | |
| Download: ML19320D097 (22) | |
Text
- -
y July 10,1980 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 3,1980 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation 8
Standards Development 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 K*
Analysis and Evai ation of Operational Data L*
L Items Approved by the Commission M**
Calendar of Speaking Engagements N
/
/T
.AA>>.vMor Operations Office of Executive Director for Operations
- No input this week.
- Deleted from Commissioners and PDR copy.
CONTACT:
T. A. Rehm 27781 4
8007180:5"5/3/
Summary of Weekly Infonnation Report Week Ending July 3,1980 Millstone 1 Millstone 1 scrammed on June 25 caused by an overpower signal from the APRMs while the reactor power was increasing beyond 85% power. The overpower APRM trip was caused by a pressure surge.
San Onofre, Unit 1 Southern California Edison is addressing concerns regarding (1) tube degradation phenomenon, (2) detectability of defects in excess of the 40% tube plugging limit, and (3) tube leakage which might occur in service during plant transients or a design basis accident.
Turkey Point 3 and 4 Florida Power and Light notified the NRC that some auxiliary feedwater piping could become overstressed during an earthquake. A temporary modification will be in place and a long-term solution will be started immediately.
Duane Arnold Technical Specification changes were requested for Duane Arnold on June 28 to permit interim operation at reduced power with one recirculation loop out of service. The Tech Specs required the plant to be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the damaged pump could not be returned to service. The licensee determined that repairs probably could not be effected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
NFS - West Valley On June 26 the Deputy Director of NMSS signed a pair of letters to the co-licensees for the shutdown of the reprocessing facility at West Valley, N.Y.
The purpose of the letters is:
(1) to formally reiterate the staff's reasons for conducting a detailed inspection and evaluation of the high-level liquid waste storage system at West Valley and (2) to require a meeting among the staff and the co-licensees in order to resolve indemnification issues that have been raised by one of the co-licensees, Nuclear Fuel Services, Inc.
SAFER - Insider Study Project The project, Insider Crime Analogous to the Potential Threat to Nuclear Program, sponsored by SAFER has been completed. A research information letter describing the results will be written shortly.
OFFICE OF ADMINISTRATION l
Week Ending July 4, 1980 j
l ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 416 29 Granted 304 6
Denied 70 14 Pending 42 9
ACTIONS THIS WEEK Received Lloyd Etheredge, Requests information on tapes available for purchase of University of California NRC meetings during and prior to the Three Mile Island (80-332) crisis.
J. Scott Taylor, Requests, on behalf of Scott Luminous, Inc., all Attorney-At-Law documents relating to this company.
(80-333)
. Harry Salzberg, Requests information regarding the applictaion of the NRC,
Black Hills Alliance source materials license requirements to the extraction c (80-334) uranium source material and the subsequent transfer across state lines and the processing of over 15 pounds of said source material for research and development purposes.
John F. Doherty Requests a copy of 21 listed documents.
(80-335)
Jacob Scherr, Requests six categories of information regarding an James Barnes Executive Order submitted to Congress by the President Center for Law & Social on June 19, 1980 authorizing exports to India of special Policy nuclear material and replacement parts for use at the
.(80-336)
Tarapur power station in India.
Tom Trevino, Requests a copy of the winning proposal in response to Science Applications, Inc.
contract solicitation NRC-02-80-024.
(80-337)
Paul Sheldon Davis Requests information relating to the security force at (80-338)
Nuclear Fuel Services site at Erwin, Tennessee.
CONTACT: - J. M. Felton 492-7211 ENCLOSURE A
2 Received, Cont'd Stephanie J. Nocells, Requests a copy of the winning proposal in response to Advanced Technology, Inc.
contract solicitation NRC-08-80-338 entitled " Study of (80-339)
U.S. Nuclear Health and Safety Information Dissemination.
Judah C. Soniner, Requests all records developed in the course of Attorney-At-Law investigations for 12 listed companies and seven listed (80-340) individuals.
Michael E. Veve, Requests all documents relating to any inspections Attorney-At-Law conducted between January 1,1979 and June 30,1980 at (80-341) any facility owned and operated by Pharmatopes, Inc.,
Phamaco Nuclear, Inc., and Nuclear Phamacy, Inc.
William Reynolds, APPEAL TO THE EDO for documents prepared for compliance American Friends with the NRC regulations 10 CFR Part 73 concerning the Service Committee physical protection of irradiated reactor fuel in transit-(80-A-21-80-275) for eight listed point-to-point routes.
Granted Rick Trombetta In response to a request for information on the release (80-312) of Krypton gas into the atmosphere from Three Mile Island, made available three documents.
A11etta d'A. Belin, In response to a request, on behalf of her client, all Center for Law in documents relating to or mentioning her client's name, the Public Interest made available two documents.
(80-313)
(NRCemployee)
Infomed the requester the NRC has no information (80-317) pertaining to her in the Office of the Inspector and 1
Auditor or infomation.on any charges made against her.
(NRCemployee)
Infomed the requester the NRC has no information (80-319) pertaining to him in the Office of the Inspector and Auditor or information on any charges made against him.
Anthony Goncalves, In response to a request for a copy of the NRC's National Employee Telephone Directory, made available a copy of this book.
Benefit Associates (80-325)
Lana C. Cobb, In response to a request, on behalf of an NRC employee, NTEU Steward for a copy of NRC-181 forms for three named employees, (80-329) made available this information.
Denied None ENCLOSURE A
DIVISION OF CONTRACTS CONTRACT AWARDS 1.
NRC-05-80-253 Title - Development of an Automated Vendor Selection System Description - Development of a system to collect and categorize nuclear component vendor-related data and select vendors for inspection, based upon safety significance, inspection history, and other weighted criteria.
Period of Performance - Two years Sponsor - Office of Inspection and Enforcement Status - A cost-plus-fixed-fee contract, in the amount of $149,528.56, was awarded to Gasser Associates, effective June 30, 1980.
2.
NRC-10-80-673 Title - ADP Systems Support Description - Provide necessary personnel to support automated information systems maintained by ADPS.
Period of Performance - One year Sconsor - Office of Administration Status - Pursuant to the NRC's 8(a) program, a labor-hour type contract, with a ceiling of $196,970.28, was awarded to SBA who then subcontracted the effort to Technassociates, Inc., an eligible 8(a) concern.
CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
Contract No.
Contractor Close-Out Date NRC-10-77-099 U.S. Civil Service Commission 7/1/80 ENCLOSURE A
0FFICE OF NUCLEAR REACTOR REGULATION WEEKLY ITEMS OF INTEREST (Week Ending July 4,1980)
Millstone 1 Millstone 1 scrammed on June 25, 1980.
The scram was caused by an overpower signal from the APRMs while the reactor power was increasing beyond 85%
power. The over power APRM trip was caused by a pressure surge, the result of erratic electro-mechanical pressure regulator behavior.
This faulty pressure regulator behavior is not a new phenomenon at Millstone 1.
The licensee is in contact with the manufacturer of the pressure regulator.
San Onofre, Unit 1 Initial findings of a steam generator inspection currently ir, progress at San Onofre Unit 1 indicate the recent development of caustic intergranular attack (IGA) ar.d associated cracking affecting approximately 460 tubes at the top of the tubesheet of the three steam generators.
Sixty one percent of the quantifiaH e defect indications exceed 95% throach-wall.
The San
$no$e b Ne he!ec! bkik![ $f"hef!c!
skofM!bO,"$b!U" n
ne plugging limit, and (3) tube leakage which might occur in service during plant transients or a design basis accident.
Southern California Edison has initiated actions to address these concerns.
Oyster Creek Nuclear Generatina Station Jersey Central Power & Light Company has requested a meeting with NRR on June 30,1980 to discuss their proposed action regarding visual indications of a crack in the core spray system piping of the Oyster Creek Plant.
The current estimated startup date from an extended refueling outage is July 2, 1980.
The core spray spargers also have cracks.
Operation until the 1981 refueling outage with repair fixtures (clamps) on the spargers has previously been evaluated and approved by NRR.
Turkey Point 3 and 4 Florida Power and Light notified the NRC that some auxiliary feedwater piping could become overstressed during an earthquake.
This was discovered during the review for Bulletin 79-14 by the Bechtel Corporation. The piping involved is the suction line from the condensate storage tank and a steam supply line from Units 1 and 2.
A temporary modification will be in place by Sunday and a long term solution will be started on imediately.
No shutdown is required for the modification.
Region II has been informed.
No PN will be issued.
ENCLOSURE B
-2 Duane Arnold Tcchnical S3ecification chanaes were requested for Duane Arnold on June 28,1930, to permit inthrim operation at reduced power with one recirculation loop out of service.
At approximately 3:30 P.M. on June 27, 1980, damage to the slip rings on one recirculation pump motor resulted in the respective pump being out of service. The Technical Specifications required the plant to be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the pump could not be returned to service.
The licensee determined that repairs probably could not be effected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and telecopied an snendment request to permit plant operation for several days with one recirculation loop out of service. An unrelated problem in April 1980 resulted in one recirculation pump being inoperative and the licensee requested technical specification changes to pernit operation with one recirculation loop out of service until repairs could be effected.
The staff issued an amendment on May 6,1980, to permit such operation at power levels up to 50t of rated power. The licensee's amendment request on June 28, 1980, was a request for interim reinstatement of that previous snendment. The staff concluded that reinstatement of the orevious amendment on an interim basis was acceptable and issued the Tech Spec changes.
TE was notified of the licensing actions.
o ENCLOSURE D
-=
NRC TMI Il0 GRAM 0FFICE WEEKLY STATUS REPORT L'eek of:
June 29-July 5, 1980 Plant Status 5
Core Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser,
^
and RCS loop-A and B cyclic natural circulation to reactor building ambient.
Available Core Cooling Modes: OTSG "B" to the main condenser; long term j
cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: Makeup system in conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0500, July 3,1980) (approximate values)
Average Incore Thermocouples: 140*F Maximum Incore Thermocouple:
195*F RCS Leop Temperatures:
A B
Hot leg 147'F 150*F Cold Leg (1) 105*F 82*F (2) 124 F 84 F RCS Pressure:
80 psig (Heise) 93 psig (DVM controlling)
Pressurizar Temperature:
Si*F Reactor Building:
Temperature:
92*F Water level:
Elevation 290.3 ft. (7.8 ft. from floor) via penetration 401 manometer Pressure:
-0.5 to -0.1" Hg (Heise, controlling withpurgeinprogress)
(As of 0700, July 7,1980) Curies released (Kr-85):
27,814 by effluent monitor calculations Curies remaining (Kr-85): 0.37 uCi/cc by building sample (total 21,070)
Maximum purge flow rate:
540 cfm Average stack flow rate:
100,000.cfm Environmental & Effluent Infonnation 1.
. Liquid effluents from TMI-1 released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
ENCLOSURE B
2 2.
No liquid effluents were discharged frem TMI-2.
3.
Results from EPA monitoring of the environment around the TMI site were:
EPA environmental stations registered b ckground levels for air particulate and water samples.
Gamma scan results for all sampling locations were negative.
Kr-85 was measured at the TMI Observation Center from noon on July 1 to noon on July 2,1980, showed a concentration of 3,100 pCi/m3 This significant increase in Kr-85 concentration was expected during the reactor building purge operation.
This concentration corresponds to 0.014 mrem and 0.00012 mrem dose to the skin and to the whole body, respectively.
Other sampling locations including Bainbridge, Goldsboro, Hill Island and Middletown showed no Kr-85 concentrations above background.
4.
NRC Environmental Data The West Screen House continuous air sample (WP-222) for the sampling period June 25 through July 2,1980, has been delivered to the EPA Coordination Center for analysis.
The licensee provided the following monthly inventory of Kr-85 releases for 1980:
January-80 C1, February-80 Ci, March-63 Ci, April-69 Ci, May-85 Ci, June (to midnight of June 25) 58 Ci.
On Saturday, June 28, 1980, the purge of the-reactor building was started. The total calculated amount of Kr-85 released as of 7:00 a.m., July 7,1980, is 27,814 Curies.
Remaining concentration in the containment building based on the last building air sample was 21,070 Curies.
Results of the environmental TLD measurements for the period April 30 to May 29,1980, indicate no gamma levels above natural background.
Fifty-eight TLD's registered doses ranging from 0.11 mR/ day to 0.20 mR/ day.
Average dose was 0.16 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
On July 2,1980, the fifty-eight NRC environmental TLD's were collected and taken to Region I, King of Prussia, for readout and evaluation.
The cumulative doses calculated to a hypothetical maximally exposed individual in each of the 16 sectors (22.5* each) were reported by Met-Ed. The following is a list of the cumulative dose through midnight of July 1,1980.
ENCLOSURE B
o 3
Calculated 00se-mrem Sector Skin NholeBody 1
0.41 5 1 E-3 2
0.83 9.8 E-3 3
0.27 4.3 E-3 4
0.071 9.0 E-4 5
0.18 1.7 E-3 6
1.67
.1.5 E-2 7
1.08 8.7 E-3 8
0.26 2.8 E-3 9
0.0054 6.3 E-5 10 0.0076 4.9.E-5 11 0.0 0.0
. 4 E-6 6
12 0.0021 13 0.0 0.0 14 0.027 5.1 E-4 15 0.081 1.1 E-3 16 0.084 9.3 E-4 These doses were well below the dose limits required by the Commission's order.
5.
Radioactive Material and Radwaste Shipmentt Offsite were as follows:
On Monday, June 30,1980, a Unit 2, 40 mi reactor coolant sample was shipped to Babcock and Wilcox, Lynchburg, Virginia, for analysis.
On Monday, June 30,1980, a Unit 2 shipment of 18 wooden boxes of non-compacted (LSA) trash was sent to Nuclear Engineering Company (NECO), Richland, Washington.
On ' Jrsday, July 3,1980, a Unit 2 CC-T-2 (EPICOR II) simple was sent to Science Applications Incorporated (SAI), Rockviile, Maryland.
6.
EPICOR II Processing Status:
(Auxiliary building approximate quantities)
Amount processed this week:
37,000 gallons Amount processed to date:
384,000 gallons Amount to be processed:
90,000 gallons j
7.
The transfer of waste water from the lower fuel pool storage tank to the "C" reactor coolant bleed tank has been completed.
The "C" tank was processed, and the remaining water from the "C" ta'nk was transferred to the "B" reactor coolant bleed tank.
- Also, the upper fuel pool corage tank is being routed to the "B" reactor i
ENCLOSURE.B-
4 coolant bleed tank.
A sample is being taken on the miscellaneous waste holdup tank.
Due to the waste water transfer processes and the holiday weekend, EPICOR II is presently down and expected to restart on July 9,1980, 8.
Long-term spent resin storage facility.
Fifty-four of the sixty spent resin storage cells in the "A" long term waste storage module hold spent resin liners.
The "B" module is scheduled to be completed by July 30, 1980. Also, the licensee began stacking 4X4 liners on June 5,1980, two per storage cell.
At present, the licensee has stacked three 4X4 liners.
Additionally, six more storage cells have become available due to the shf oment of Unit I liners off site.
The interim staging has four empty cells.
Based on current liner generation rate and the above storage factors, it coes not appear that EPICOR II will have to be halted becauce of the lack of storage space.
Major Activities This Week 1.
Reactor Building Purce.
Purging of the reactor building atmosphere utilizing the modified hydrogen control system continued at various system flow rates based on meterological conditions.
Shutdown other than those due to weather conditions occurred to perform filter changeouts on instrumentation : ample systems and for minor corrective maintenance on various sys:em components.
Periodic monitor equipment filter grab samples were analyzed and indicated particulate activity relea e within regulatory limits.
This was confinned by NRC Region I M-bile Laboratory.
An additional monitor, consisting of a 3X3 inch sodium iodide crystal detector installed in the plant stack sample line, is providing signals to a multi channel analyzer where Kr-85 gamma signals are distinguished from other potential isotopes, in particular Cesium 137.
This new monitor is being used as backup to the plant effluent monitor (HP-R-219A) with associated filter sample analyses.
The sample analysis requires the removal of HP-R-219A particulate filter, once per day, for spectral analysis to identify any particulate activity indication.
All releases were made in accordance with the Comission Order, the Technical Specifications and the licensee's procedures.
2.
Reactor Building Entry.
On Tuesday, July 1, 1980, one hole was drilled in the inner door of personnel airlock no. 2.
Utilizing this hok (approximately 1 inch) as access to the aP safety interlock solenoi, pin, the licensee determined that the pin was stuck in the interlock function position preventing the roller mechanism from being operated. The pin was subsequently restored to the deenergized state.
ENCLOSURE B
T 5
~ d On Thursday, July 3,1980,'the handwneel was suede'ssfu1Ty turned ~..
beyond the interlock position indicating roller mechanism disengagement.
During these events the innsr-door was held "clo~s'ed b ' restrai'nts.
.v l
Plans for opening the inner door and'contain'medt entry 'were'not finalized as yet in light of reactdr building pair'ge evolutions ~.'
3.
Mini-Decay Heat (MDH) System.
During this week the staff approved-a tecnnical cocument report on expected reactor core boron concen-tration with the initial startup of.the MDH s'ystem. 'Th'e-analysis results indicated that local baron conce'ntration in the core will not go below the Technical Specification (propose'd) limit of< d -
3,000 ppm when MDH is started on the reactor coolant system (RCS).
Several system modification work items are still in progress.
Operation is expected by the end of July 1980.
The staff approved the operating and emergency procedure for opening DH-Vl/171. These valves are in parallel and isolate the RCS frca the decay heat systems.
A schedule date for opening these valves was not finalized by the licensee.
ENCLOSURE B
6 Meetings attended wi9h Public Officials and XnteresRed Groups During the week of June 30, 1980, through July 5,1980, J. Collins, E. Bretthauer (EPA), and representatives from the Department of Environmental Resources held a daily news conference to brief the media on current activities of purging the reactor building.
Future Meetings The Atom Safety and Licensing Board has scheduled a prehearing conference on July 7,1980, in Harrisburg, Pennsylvania, on proposed technical specification changes to the license for the damaged Unit 2.
I i
I l
I l
ENCLOSURE 5
J OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending July 4, 1980 BRIEFING OF GOVERNOR GARRAHY'S STAFF As requested in Governor Garrahy's (Rhode Island) letter dated June 23,1980, to Chairman Ahearne, a member of the NMSS staff will brief the Governor's staff on July 8,1980 on the status of the decommissioning activities at United Nuclear's Wood River Junction, Rhode Island, plant. NMSS, as well as IE/ Region I, will represent NRC at a public meeting in Charlestown, Rhode Island that same evening.
Also, members of the NMSS staff briefed Senator Pell's staff about United Nuclear's status on July 1,1980. The main concern centers around contamination of an under-ground aquifer by a leaking lagoon at UNC, discovered and corrected in 1977. The aquifer is slowly purging itself into the Pawkatuck River approximately 1500 feet away. The contamination represents no threat to any present drinking water suppl ies.
N_FS-WEST VALLEY On June 26, 1980, the Deputy Director of NMSS signed a pair of letters to the co-licensees for the shutdown of the reprocessing facility at West Valley, New York.
The purpose of these letters is twofold:
(1) to formally reiterate the staff's reasons for conducting a detailed inspection and evaluation of the high-level liquid waste storage system at West Valley; (2) to require a meeting among the staff and the co-licensees in order to resolve indemnification issues that have been raised by one of the co-licensees, Nuclear Fuel Services, Inc. (NFS).
The staff's contrauor responsible for conducting these inspections, Rockwell Hanford Operations, has been informed of NFS' position that must be met in order to allow Rockwell to conduct inspection activities on the West Valley site. NFS' position is that appropriate indemnification agreements must be developed which would include assurances that any damage discovered as a result of these on-site activities would be presumed to be attributable to those activities unless it could be otherwise clearly proven. NFS' position effectively blocks our contractor from gathering safety-related information that is required by the NRC staff. As such, this position is unacceptable to the staff. As a result, the staff has initiated one of its available courses of action by sending the above-described letti < ') the co-licensees. The meeting mentioned above is tentatively scheduS ; p July 17,1980.
MEETING WITH DOE ON UMTRCA--TITLE I REMEDIAL ACTION PROGRAM Division of Waste Management, Uranium Recovery Licensing Branch, staff met with DOE l
headquarters and Albuquerque Program Office staff on June 25, 1980, to discuss pro-cedures and plans for implementing the requirements of Title I of the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). Agreements reached included that in addition to the review and concurrence functions described by the Act, NRC would be formally requested by DOE to participate as a cooperating agency in the NEPA process related to each site within about 60 days. This would ensure early involve-ment of NRC in the overall program including participation in the formulation and evaluation of alternative remedial actions for each of the designated processing sites.
ENCLOSURE D
NEGOTIATIONS COMPLETED ON NRC/FAA MEMORANDUM OF UNDERSTANDING (MOU)
On June 30, 1980, a proposed memorandum of understanding between the NRC and the FAA was submitted to IE and ELD for final staff coordination. This agreement pro-vides for an information ' ik between the NRC Operations Center and the FAA Hijack Command Center. Negotiat.. n; with staff of the FAA's Office of Civil Aviation Security were conducted by the Division of Safeguards in the development of the MOU.
INMM MEETING, PALM BEACH Robert F. Burnett attended and participated in the annual meeting of the Institute of Nuclear Materials Management held in Palm Beach, Florida.
Papers presented by Mr. Burnett included "The Future Outlook for U.S. Nuclear Safeguards" by William J.
Dircks; "NRC Response to Significant Inventory Differences" by Robert F. Burnett; and
" Physical Protection Rules and Requirements--What Drives Them?" by Robert A.
Erickson.
ENCLOSURE D
OFFICE OF INSPECTf0N AND ENFORCEMENT Items of Interest Week Ending July 3, 1980 1.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-I-80-96 Millstone Unit 2 - Design Error in New Fuel Assemblies b.
PNO-II-80-119 Browns Ferry Unit 3 - Failure of Control Rods to Insert During a Scram c.
PNO-III-80-120 D. C. Cook Unit 2 - Possible Inaccurate Media Coverage Concerning Reactor Shutdown d.
PNO-III-80-121 Mallinckrodt, Inc., St. Louis, MO - Transportation Accident Involving Radioactive Material in Toledo, OH e.
PNO-III-80-122 Prairie Island Unit 1 - Utility News Announcement on Steam Generator Tube Leakage f.
PNO-III-80-123 Prairie Island Unit 1 - Unit Shutdown Due to Steam Generator Tube Leakage g.
PNO-III-80-124 Radioactive Exposure Device Found in Ohio h.
PNO-III-80-125 Marble Hill Units 1 & 2 - Establishment of Grand Jury by the U. S. Attorney Relative to the Concrete Honeycomb Coverup Issues at the Marble Hill Site
- i. PNO-III-80-126 Monticello - Chlorine Leak - Four Work;rs Sent to Hospital J.
?10-V-80-55 Palo Verde Unit 3 - Fire at Construction Site k.
PNO-TMI-80-35 Three Mile Island Unit 1 - Reactor Coolant System Overflow 1.
PNO-TMI-80-36 Three Mile Island Unit 2 - TMI-2 Reactor Building Purge m.
PNO-TMI-80-37 Three Mile Island Unit 2 - Reactor Building Purge Status
- n. - PNO-TMI-80-38, -38A, & -38B - Three Mile Island Unit 2 - Reactor Building Purge Status ENCLOSURE E
1 OFFICE OF NUCLEAR REGULATORY RESEARCH Important Items - Week Ending July 5, 1980 SAFER Insider Study Project The project, Insider Crime Analogous to the Potential Threat to Nuclear Program, (FIN A-0132) sponsored by SAFER for the Physical Security Development Branch (SGPD) has been completed.
The following final reports were received from LLNL under this program:
a.
"The Insider Threat to Secure Facilities: Data Analysis" -
~
b.
"The Distribution of Illegal Incident Characteristics:
Cases of Bank Fraud and Embezzlement, Computer-Related Crime, and :nsider Theft from Drug Manufacturers and Distributors" - NUREG/.R-ll18.
A research information letter (RIL) describing these results will be written very shortly.
a 9
e ENCLOSURE F
9 ITEMS OF INTEREST OFFICE OF liiitxt<AilviiAL PROGRAMS nttK tiiUlfid dVLi 4, 196U INTERNATIONAL COOPERATION Research Arrangement To Be Proposed IP this week drafted an information exchange renewal Arrangement to be forwarded within the next few days for the consideration of the FRG's Federal Ministry of the Interior (BMI).
The present Arrangement will expire October 1,1980.
Foreign Visitors to NRC On Monday, Mr. Da Silva of the Fuel Department of Furnas, a Brazilian utility, met with J. B. Devine and M. R. Petersor. of IP to discu~ss export issues.
On Monday, Mr. G. Finetti, of the Department of Nuclear Safety and Health Protection of the Italian National Committee for Nuclear Energy (CNEN), met with NRR technical staff to discuss (1) TMI-2 short-term recommendations, (2) backfitting, (-3) Mark III containment, (4) hydrogen control in post-LOCA conditions, (5) operator training, (6) recirculation pump overspeed (7) diesel qualification tests, and (8) ATWS.
On Tuesday,. Mr. Finetti returned to meet with J. D. Lafleur, Jr., IP Deputy Director and IP staff representatives to discuss the exchange of information between NRC and the CNEN.
On Tuesday, Mr. J. C. E. (Jim) Button, Controller Safety of the Australian Atomic Energy Commission (AAEC), met with (1) 8. K. Grimes of NRR to discuss liaison with and promulgation of emergancy plans to local residents and arrangements for the adoption of countermeasures in the event of an emergency, (2) R. Blond of PAS /RES to discuss the use of stable iodine for thyroid blocking, (3) D.
A. Nussbaumer, V. L. Miller and W. J. Walker of FCMS/NMSS to discuss the health and safety aspects of radiopharmaceutical manufacturing, and radiological safety training for manufacturing plant personnel, and (4) J. R. Metzger of IE to discuss surveillance and monitoring of radiopharmaceutical mar.ufacturers by NRC.
ENCLOSURE H
OFFICE OF MANAGEME:lT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING JULY 4, 1980 FY 82-84 Budget Review Process Assisted D/EDO and ED0 in reviewing major agency programs proposed by the offices.
Construction Status Report (Yellow Book)
The Yellow (for the period of January 1,1980 to April 30, 1980) was printed and released for distribution.
6
+
E.
l-s ENCLOSURE J
^
l
CALENDAR OF SPEAKING ENGAGFMENTS July 14-18
!!arold Peterson, SD, will lecture on " Environmental
'- nsport and Bioaccumulation" before the Third Annual Heaith Physics Society Summer School July 16 John Hickey, SD, will speak on " Regulatory Standards in Environmental Releases" before a Health Physics Society Course on Environmental Releases of Radioactivity 4
a s
ENCLOSURE N
. -.