ML19312E882
| ML19312E882 | |
| Person / Time | |
|---|---|
| Issue date: | 06/05/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-800530, NUDOCS 8006180074 | |
| Download: ML19312E882 (29) | |
Text
_
,YD, June 5,1980 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 30, 1980 A sumary 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 8
Standards Development C*
Nuclear Material Safety and Safeguards D
Inspection and Enforcement E
Nuclear Regulatory Research F*
i Executive Legal Director G
International Programs H
State Programs I
Management and Program Analysis J
Controller K
Analysis and Evaluation of Operational Data L*
Items Approved by the Commission S
M**
- N
' T! A. Rehmr-A ant for Operations Office of Executive Director for Operations
- No input this week.
- Deleted from Comissioners anc POR copy.
Contact:
T. A. Rehm 27731 8006180074
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending May 30, 1980 North Anna Unit 1 The licensee is commencing a 12-day shutdown of Unit 1 following a series of events in which a spuricos safety injection actuation occurred when a vital electrical bus was lost, resulting in an RCP shutdown. These events followed a reactor trip which occurred on May 22, 1980, when the "C" steam generator feedwater regulating valve failed to open.
Turkey Point 4 On May 23 a shallow crack in the feedwater nozzle to the pipe reducer was discovered in the Unit 4 steam generator. Ultrasonic testing also discovered small indications in other steam generators. All cracks are now being repaired and will be completed before return to power.
Beaver Valley 1 On May 22, while in cold shutdown, two RHR systems were inoperable because of a leak in a fitting of the 3/4" line that leads to the 12" common header from both pumps. The leak appears to be similar to several LERs reported previously in RHR systems that have been attributable to fatigue caused by vibration.
Zion 2 A keyday crack 0.6 inches in depth was found in the Unit 2 turbine rotor. The crack size represents a depth approximately 1/3 of critical size.
TMI Reactor Building Entry On May 30, the licensee entered the personnel airlock and equalized the pressure across the inner door with reactor building atmosphere. However, a mechanical restriction was experienced and the inner door handwheel did not go beyond the point needed to open the door.
It appears that the a P safety interlock pin is stuck. Attempts.to free this pin failed. The next course of action is under review by the licensee.
Spent Fuel Shipments Rule A Federal Register noticc containing the revised Spent Fuel Shipments Rule will be puolisneo on June 3, 1980. The rule is expected to become effective on July 3, 1980.
FY 1982 Budget Formulation OMB was briefed on the new decision units procosed by the Program Offices.
Preliminary approval was granted.
OFFICE OF ADMINISTRATTON Week Ending May 30, 1980 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF RE0 VESTS Initial Appeal of Request Initial Decision Received 359 24 Granted 253 6
Denied 58 10 Pending 48 8
ACTIONS THIS WEEK Received Thomas A. Miller Requests a copy of the report of the NRC inspection of (80-276)
Atomics International and the allegations of Stanley Schecter.
Lindsay Audin, Requests a copy of the grant proposal from Mr. Ned Westchester County Lighlman to the NRC and a copy of the contract governing Board of Legislators the grant.
(80-277)
Jim Robey Requests information on nuclear power plant locations in (80-278) the United States, a listing of accidents at these locations, and information on nuclear wastes.
Stephanie J. Nocella, Requests a copy of the winning technical proposal and the Advanced Technology, Inc.
contract awarded under contract solicitation NRC-03-80-ll7 (80-279) entitled " Study and Requirements for Operator Licensing."
Eugene R. Fidell, Requests information on a contract between the Regulatory Attorney-At-Law Staff and the " Human Design Group" referred to in a (80-280)
Ma 16, 1980 Decision and Order in Metropolitan Edison Cc.apany.
Eugene R. Fidell, Requests all correspondence from Mr. Robert Martin to Attorney-A6-Law Mr. Victor Stello, or vice versa since April 1, 1980, (80-281)
Mr. Stello's telephone logs since April 1,1980 and all travel claims submitted by Mr. Martin since April 1,1980.
(An individual requesting Requests information on his Reactor Operator License information about himself) exam results.
(80-282)
CONTACT:
J. M. Felton 492-7211 ENCI.CSURE A.
2 Received Cont'd Virginia B. Foote, Requests all documents pertaining to the design, s1 ting Center for Development and/or consideration of the U.S. military installations Policy in the Republic of Korea on the proposed nuclear reactors (80-283) to be located near Gyaema.
Lincoln B. Hubbard, Requests the cost benefit analysis of Mr. R1 chard E.
American Association of Cunningham's order of May 7,1980, list of tne incidents.,
Physicists in Medicine the estimated excess exposures received by both patients (80-284) and radiation therapy personnel, and the way in which the indicated malfunction was detected.
Granted J. Michael McGarry, In response to a request for several categories of documer Attorney-At-Law pertaining to transportation routes submitted by Duke (80-201)
Power Company in its application to tFansport spent fuel from the Oconee Nuclear Station to the McGuire Nuclea-Station, made available 16 documents.
(An individual requesting In response to a request for a copy of all documents and information about himself) files indexed or tr.aintained under his name, informed the (80-247) requester the NRC has no information pertaining to him in its personnel, security, inspector and auditor, or radiation exposure records.
David S. Thomas In response to a request for the names and present duty (80-248) stations for all NRC employees in Region II, made available this information.
William H. Briner, In response to a request for copies of licenses and Duke University amendments issued to Cooper Medical Center, made available Medical Center 20 documents.
l (80-265)
Marvin Resnikoff, In response to a request for a copy of NL Industr1es Sierra Club Radiation amended application, including route information, when i
Waste' Campaign it becomes available to the NRC, informed the requester (80-266) that a request made pursuant to the FOIA applies only to records in the possession of the agency on the date the request was received.
(An individual requesting Made available information on his Reactor Operator License information about himself) exam results.
(80-282)
ENCLCSURE A
3 Denied (NRC employee)
In response to a request for the employee's rating, the (80-240) names and ratings of all A candidates, and the rating of the selactee for the position on vacancy announcement
- 80-1000, denied portions of the Candidate, Evaluation, Certification and Selection Record (CERT), the disclosure af which would constitute a clearly unwarranted invasion of personal privacy.
1 i
E';CLOSUCE i
DIVISION OF CONTRACTS t
Week Fnding May 30, 1980 PENDING COMPETITIVE REQUIREMENTS RFP RS-RES-80-176 Title - Non-Equilibricm Heat Transfer and Two-Phase Instrumentation Description - This pro,ect is to experimentally and analytically investi-gate non-equilibrium effects in post-CHF heat tran. fir,-
including advancement of the state-of-the-art for measure-ment of non-equilibrium two-phase flow parameters. The project should include direct measurement of non-equilibrium i
conditions under controlled flow conditions, improvements in the modeling of film boiling and refinement of non-equilibrium two-phase flow measurement techniques.
Period of Performance - Three years Sponsor - Office of Nuclear Regulatory Research Status - CBD notice issued May 29, 1980 4
PROPOSALS UNDER EVALUATION i
i 1.
RFP RS-0SD-80-016 l
Title - Disease Incidence Rates from Occupational Exposure to Hazardous Substances Description - Compile from the existing published literature and knowledge-able opinion the occupational disease incidence rates from hazardous substances in the workplace in such a way that these incidence rates can be compared to the cancer incidence rates for workers exposed to radiation.
Period of Performance - One year Sponsor - Office of Standards Development Status - Proposals under evaluation.
2.
RFP RS-RES-80-192 Title - Effective Peak Acceleration for Nuclear Power Plant Design i
Description - The objective of this project is to develop recommendations for methods to be used in selecting design response spectra or time histories to be used to characterize motion at the fou'ndation level of nuclear power plants.
Period of Performance - Two years and four months Sponsor - Office of Regulatory Research Status - Technical proposals distributed May 23, 1980, for evaluation by technical panel members.
l i
i
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l CMCLOSURE A i
1 l
L
2 CONTRACT AWARDS NRC-08-80-338 Title - Study of U.S. Nuclear Health and Safety Information Dissemination to Foreign Countries Description - Study to determine if existing nuclear health and safety dissemination practices and mechanisms are adequate to serve the legitimate information needs of regulatory bodies in developing countries and, in the case of a negative finding, propose alternative methods whereby these needs can be better met.
Period of Performance - Six months Sponsor - Office of International Programs Status - A cost-plus-fixed-fee contract in the amount of $81,426.00 was awarded on May 28, 1980, with an effective date of June 3, 1980, to the Franklin Institute.
ENCLOSURE A 1
0FFICE OF NUCLEAR REAC Q REGULATION WEEKLY ITEMS OF INTEREST (Week Ending May 30,1980)
Calvert Cliffs Unit No.1 At 6:03 p.m. on May 20, 1980, Calvert Cliffs 1 was manuC ly tripped following a loss of all service water (SW) resulting in high tn oine generator bearing temperatures and increased containment temperatur. The common SW pump suction line had become air locked when the No.12 SW heat exchanger was returned to service after cleaning. B3&E located the air inleakage, isolated the source, and returned both SW systems to service by 9:30 p.m.
The air inleakage came from a broken tube in an instrument air aftercooler. During the loss of the SW system, the auxiliary feedwater (AFW) system, in conjunction with steam dump was used for reactor cooling.
Suction of the AFW system pumps was from condensate storage tank No.12 until its level was reduced to about 30 feet when the suction was manually changed to tank No. 11. At about 10:00 p.m., the control room operator gave_ instructions to return the AFW system pump suction to normal, from No.12 condensate storage tank.
However, he transposed the valve numbers which resulted in the auxiliary operator closing one isolation valve on each s ction line.
This mistake was not discovered until the 1:00 a.m. valve survey performed on Ma,7 21, 1980 (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> later). AFW was, therefore, net available, if required, for Unit 1 during this 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period.
It had no effect on Unit 2.
This violated the Technical Specifications which require AFW system operability in Modes 1, 2, and 3 or until hot shutdown is r,eached (below 300*F).
BG&E has modified their procedures to reduce the probability of misvalving the AFW system. The staff has questioned the comon service water suction line and will follow up on this issue.
Rancho Seco On May 25 and 26, 1980, earthquake shocks were felt at Rancho Seco.
The epicenters were located near Marmoth Lakes, California. The largest quake measured greater than 6.0 on the Richter scale. None of the plant's five accelerometers were triggered. The devices have a sensitivity of 0.01g in acceleration.
ENCLOSURE.B
North Anna Unit 1 A spurious SI actuation occurred at 1:45 AM, May 23, 1980, when a vital electrical bus was lost while NA-1 was shut down following a reactor trip which occurred at 11:47 PM, May 22, 1980.
The 11:47 PM (May 22) trip was caused by a high steam generator "C" level alarm 'and resultant turbine / reactor trip.
The high level alarm occurred when the "C" steam generator feedwater regulating valve failed to open.
At the time the 11:47 PM trip occurred, the RCP "A" seal leak off went to zero which required the shut down of RCP "A".
A short time later RCP "A" was restarted and a loss of No. 3 vital bus occurred.
(The reason for the loss of the vital bus not known at this time.) The loss of No. 3 vital bus caused a spurious electrical transient actu-ating a high steam flow alarm point. Also, the loss of the vital bus actuated phase A & B isolation cutting off component cooling water to the RCP's with resultant RCP shutdown.
decrease alarm which with the The RCP shutdown resulted in a Tavg already locked in high steam flow alarm actuated SI at 1:45 AM (May 23). SI was of 3 minutes duration.
The facility went into natural circulation and is presently in Hot shutdown (Mode 4) with RCP's operational.
Initial reports indicate no radioactive releases.
Preliminary review indicates emergency procedures were followed. Two resident on-site inspecturs are now reviewing the incident.
Also, the licensee's onsite Safety Engineering Staff Group is analyzing the series of events.
The licensee will bring the plant to Cold shutdown (Mode 6) and commence a 12 day shutdown originally scheduled to commence May 27, 1980.
Trojan Mount St. Helens erupted again on Sunday, May 25, at 2:30 p.m.
Ash fell at the Trojan site. Accumulation was estimated to be 1/4 inch in the form of mud due to the rainfall which occurred during the ashfall.
Ash fallout occurred over wide areas of western Washington and northwestern Oregon.
The ashfall has not caused any problems at the Trojan site, but Portland General Electric Company has been washing down insulators in some electric substations since the mud has been causing flashovers.
PGE has enaaged a consultant to assess any effects of ashfall on operating equipmentlpumps, diesels,etc.)inthepathoftheinitial(May18)large eruption.
Extra air filters are on site.
Trojan is currently shut down for annual refueling and caintenance.
Startup is scheduled for about July 1.
e Turkey Point 4 Late on Friday, May 23, 1980, a crack in the feedwater nozzle to pipe reducer was discovered in a Turkey Point 4 steam generator. The indication was of a shallow crack and is in a location which is typical for cracks to be found.
However, only one crack was found; typically there are more than one. The radiography used to locate the crack was improved over tnat used in the previous examination about eight or nine months ago in which no crack was found.
By Tuesday, May 27, 1980, ultrasonic testing (UT) on the feedwater nozzle crack had confirmed the existence of the crack in one steam generator (SG) of Unit No. 4.
UT also discovered srall indications in the other SG's which upon re-radiographing could be detected. All cracks are now being repaired.
The repair will be completed before return to power.
Oconee Station Due to the recent discovery of holddown spring failures at the Davis-Sesse Station, Duke Power Company has examined all the spent fuel, specifically for holddown spring status, in both of the Oconee Spent Fuel Fools.
At the completion of the inspection, Duke orally reported to the Resident Inspector that four broken springs and one defective spring, out of 745 asserblies inspected, were found.
B&W is tracking down the Quality Assurance records for the failed springs -and hopes to have this data by t'ay 29,1980 Oconee Unit 2 Baron Dilution Event The'IE Res.ident Inspector informed the NRR Oconee Project Manager en May 23, 1980, of a baron dilution event that occurred during a cold shutdown of the reactor on May 7,1980.
At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, head on the vessel, the boric acid concentration was at 1884 ppm.
A large demineralizer, used to clear chlorides out of the coolant was valved into the primary system.
In one hour and fifty minutes the boric acid concentration was reduced to 1539 ppm. To maintain a 1% shutdown margin, the minimum required concentration, all rods in, is 1300 ppm. This uncontrolled dilution event occurred because the operators believed the water in the demineralizer was saturated with boric acid, when in fact it was filled with undiluted This report is subject to modification as more information is water.
received.
Corr ective action is under review.
0 ENCLCSL;E ?
_4
~
Eeaver V. alley 1 The Beaver Valley 1 Resident Inspector advised the Project Manacer at 2 p.m. on May 22, 1980 that the two RHR systems were inoperable from 9:30 a.m. to 2:20 p.m. on May 21, 1980 because of a leak in a fitting of the 3/4" line that leads to the 12" cc =on header fr:m both pumps.
The plant has been in cold shutdown since 11/30/79 for refueling and extensive maintenance.
During the -- 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period when the RHR system was inoperable the temper.ature of the reactor coolant increased frcm 90*F to only ll5'F, therefore; an alternative cooling system was not required. The radiological hazard associated with the leak was controlled and not reported to be significant.
This leak appears to be similar to several LERs reported previously in RHR systems that have been attributed to fatigue caused by vibration.
Zion 2
~
preliminary results from the Zion 2 turbine rotor inspection indicates that on Rotor 1, Disc 1 a keyway crack 0.5 inches in depth was found.
This crack size represents a depth approximately 1/3 of critical size.
<estinghouse had credicted that the naximun kerelay crack on a il Disc would be 1.24" or 0.89 of the critical crack depth (l.a0").
The Staff's crediction was 1.11" or 0.79 of the critical crack depth.
The actual crack is 0.43 of the critical crack deoth.
I EtiCLOSURE B p
STATUS OF SHUTDOWN PLANTS (May28,1980)
Restart Date Arkansas 1 Reactor Coolant Pump Seal Repair 6/5/80 Beaver Valley Refueling / Turbine Repairs 7/22/80 Unknown Browns Ferry 1 Reactor Trip Unknown
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Brunswick 1/2 Refueling Unknown Cooper-Refueling Crystal River 3 Refueling 6/1-15/80 Unknown Davis-Besse 1 Refueling Dresden 1 Chemical Cleaning 9/1/81 Fitzpatrick Refueling 7/7/80 Unknown Fort Calhoun Refueling Haddam Neck Refueling 7/4/80 Hatch 1 RHR Valve Repair Unknown Humboldt Bay Seismic Evaluation Unknown Indian Point 1 ECCS Unknown X:waunee Refueling 6/21/80 Millstone. 2 Seismic Modification Unknown Oconee 2 Refueling / Valve Tuneup
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6/14/80 Oyster Creek Refueling Unknown Peach Bottom 2 Refueling 7/10/80 Peach Bottom 3
- 3B Recire. Pump Seal Repair Unknown San Onofre Refueling 5/31/80 Sequoyah Mode 4 - Hot Standby August 1980 Surry 2 Refueling Unknown Three Mile Island 1 Order Unknown Three Mile Island 2 Accident Unknown Trojan Refueling 7/1/80 Turkey Point 4 SG inspection 7/1/80 Yankee Rowe Turbine Repair 10/1/80 Zion 2 Refueling 6/14/80 1
=
ENCLOSURE S
NRC TMI PROGRAM OFFfCE WEEKLY STATUS REPORT Week of: May 24-30, 1980 Plant Status 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: 0TSG "B" 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: Makeup system in conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
~
Major Parameters ( As of 0500, May 30,1980) (approximate values)
Avert 4* Incore Thermocouples: 155*F Maximum Incore Thermocouple:
192*F RCS Loop Temperatures:
A B
Hot Leg 148 F 151 F Cold Leg (1) 94*F 92*F (2) 86 F 82'F RCS Pressure:
80 psig (Heise) 93 psig (OVM controlling)
Pressurizer Temperature:
99*F Reactor Building:
Temperature:
78*F Pressure:
-0.7 psig (Heise)
Water level:
Elevation 290.2 ft. (7.7 ft. from floor) via penetration 401 manometer Environmental & Effluent Information 1.
Liquid effluents from TMI-l released to the Susquehanna River, after crocessing, were within the limits specified in Technical Specifications.
2.
No liquid effluents were discharged from TMI-2.
3.
Results from EPA monitoring of the environment arcund the TMI site v.e re :
EPA environmental stations registered background levels for air l
particulate and water samoles. Gamma scan results for all sampling locations were negative.
E.'iCLCSURE S l
2 Gas / Air (Kr-85) sample results during the period May 16 through May 23,1960 werg:
Goldsboro - 23 pCi/m, TML Observation 3
3 ano Bainbridge - 23 Centeg-27pCi/m,Middletown-22pCi/mThe EPA states that the Kr-E5 b pCi/m.
in the vicinity of TMI to be in the range of 20 and 40 pCi/m.
Instantaneous direct radiation readings showed an average level of 0.012 mrem /hr at the 17 monitoring stations.
The measurements are all attributed to naturally occurring radio-activity.
4.
NRC Environmental Data The West Screen House continuous air sample (HP-217) for the sampling period Nay 21 through May 28, 1980 has been delivered to the EPA Coordination Center for analysis.
The following are the NRC air sample analytical results for the onsite continuous air samoler:
Samole Period 1-131 Cs-137 (uCi/cc)
(uCi/cc)
HP-213 April 25 - 30,1980
<6.7E-14
<7.0E-14 HP-214 April 30 - May 7,1980
<4.8E-14
<5.0E-14 M-215 May 7 - 15,~1980
<.2E-14
<4.0E-14 No reactor-related radioactivity was detected.
The licensee provided the following monthly inventory of Kr-85 releases for 1980:
January-80 Ci, February-80 C1, March-63 C1, April-69 Ci, and May (to midnight of May 29) 82 Ci.
Total through May 29th - 374 Ci.
Results of the environmental TLD measurements for the period March 18 to April 30, 1980, indicate no gamma levels above natural background.
Fifty-eight TLD's registered doses ranging from 0.09 mR/ day to 0.18 mR/ day.
Average dose was 0.13 mR/ day.
These dose rates are consistent with natural background radiation
,in the TMI area.
5.
Radioactive material and Radwaste shipments offsite were as follows:
On Tuesday, May 27, 1980, a Unit 2 reactor coolant sample was sent to the Babco'ck and Wilcox (B&W) facility, Lynchburg, Virginia for chemical and radiochemical analysis.
Two Unit 2 waste shipments, LSA boxes and LSA 55 gallon drums, will be shipped upon verification by the licensee of the isotopic :ontent of the ccmpacted and uncompacted waste.
6.
EPICOR II Processing Status:
(auxiliary cuilding approximate quantities)
Amount processed this week:
11,000 gallons Amount processed to date-111,000 gallens Amount to be processed:
137,000 gallons E"C' CSP.E 3
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3 Major Activities (Past and Present) 1.
Reactor Building Entry.
Efforts continued in the review of data and in the troublesnooting of equipment associated with the personnel airlock (No. 2) inner door failure to open.
On Friday, May 30, 1980, the licensee entered the airlock and equalized pressure across the inner door with reactor building atmosphere (outer door closed).
It was determined that the inner door handwheel could not physically go beyond approximately 120-150 (angular) from the closed position (counter-clockwise).
This is near the same position that the adP safety interlock (addressed in last week's report) took affect on the outer door. After air equalization the handwheel for both doors should go beyond this point for door roller mechanism actuation to open the door.
A definite mechanical restriction was experienced (at the 120-150* point) and verified by a NRC Program Office Staff member.
It appears that the 2L P safety interlock pin is stuck in a position to prohibit additional movement of the inner nandwheel.
Attempts to free this pin by tapping on the area of the door where the interlock mechanism is positioned (inside the reactor building) failed.
The next course of action is under review by the licensee and will be monitored by the NRC/TMI Program Office.
2.
(Temocrary) Nuclear Samoling System (NSS).
The NSS system was to be operational cy June 1,1980, and be reacy to draw the first primary sample from this new system on June 2,1980.
However, on May 29, 1980, the licensee implemented a preoperational test procedure that inadvertantly isolated the only operable reactor coolant system pressure source / indication.
The operation of this system was therefore delayed pending a review of the circumstances of this event by the licensee and NRC/TMI Program Office Staff.
This system will have the capability to sample the RCS, and selected other key radwaste storage tanks.
Also, this sytem will support the separation of Units 1 and 2 since Unit 2 sampling is presently accomplished ih Unit 1.
3.
Submerged Demineralizer System (SDS).
On May 28, 1980, a letter was forwarded to GPU/ Met-Ed aovising them tnat our May 16, 1980 letter (NRC/TMI-80-089) should not be" interpreted as approval of the SDS as the preferred technique for decontaminating ne water in the containment building sump and primary system.
The letter advised Met-Ed that approval of any system will be prececed by NRC's evaluation cf the environmental impacts of alternate techniques as given in :ne staff's final Programmatic Envircnmental Impact statement, censistent with the Commission's policy on tnis natter of November 21, 1979 (44 F.R 57738).
Since Met-Ed has not receivec NRC approval for use of tne SDS, purchase and installation of any tortiens of the system are at its' Cwn risk.
The letter also requested '*et-Ec to promptly complete their contingeqcy clan, which is being deveiccec tc transfer tne untreated *ater fecm the containment ouiicin; te suitacly snielced cr-:ite tar <s, secald ne need arise.
ENCLCSURE E'
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 30, 1980 Publication of Spent Fuel Shipments Rule and Guidance A Federal Register notice containing the revised Spent Fuel Shipments Rule will be puolished on June 3,1980. The revised guidance, NUREG-0561/Rev.1, has been forwarded to the Office of Administration for publication sometiae before June 13,1980. The rule is expected to become effective on July 3,1980.
Safeguards Measures to Prevent Insider Sabotage of Reactors Representatives of the )ivision of Safeguards and the Office of Research met with personnel from Science Applications, Incorporated (SAI) and Sandia Laboratories to be apprised of the current status of the project.
The MAIT computer code has been modified for use on both PWR and BWR reactors, and the base cases have been run. SAI will commence evaluating alternative work rule configurations designed to improve protection against insider sabotage.
Chemical Reprocessing of Non Power Reactor Fuel Personnel from the Idaho National Engineering Lab. met with the NRC staff to discuss progress to date and future direction of the technical assistance contract on " Reprocessing of Nonpower Reactor (NPR) Fuel Into Forms Directly Useable in a Clandestine Fission Explosive (CFE)." This study is assessing the resources that would be needed by a subnational group that planned to convert NPR fuel into a bomb useable form to determine whether Cat. I Upgrade Rule Safeguards need to be applied to NPR's. The program so far is on schedule and an interim report is due June 30, 1980.
Federal Radiation Policy Council The Federal Radiation Policy Council has established task forces on which NHSS/
FC is participating.
The first is on low-level radioactive waste from medical and research institutions.
The first meeting was held on May 27, 1980. The following federal agencies are represented on the task force:
HHS (Chair),
DOE, EPA, FEMA, NSF, DOT, NRC, D00 and RPC.
The second is to examine existing Federal approaches to occupational exposure guidance and regulations, to define the problems related to revising regulations using a standard approach and to examine options for solving existing problems.
The first task force meeting was held on May 23, 1980 with representatives from the following agencies: OSHA (Chair), DOC, 00E, EPA, 000, HHS, NRC, DOT and VA.
E.NCLOSU:.E :
2 The third task force met with the cbjective of proposing a policy position concerning the protection of the public from health risks from exposure to radon and radon daughters in inhabited structures.
The first meeting of task force was held on May 20,1980. The following federal agencies are represented on the task force:
EPA (Chair), HUD, DOE, NRC, 00C, HHS and DCJ.
Order Authorizing Resumption of Limited Solution Mining Operations at the Wyoming Mineral Corporation Irigaray Project The Division of Waste Management issued an order effective May 23, 1980, modifying Source Material License No. SUA-1341 and terminating the Show Cause Order of April 21, 1980, which had directed immediate suspension of normal production operations at the Irigaray site due to evidence of uncontrolled vertical excursions of leaching solutions.
The decision'to terminate the April 21, 1980 Show Cause Order was based on the results of a shallow zone well drilling and sampling program conducted by the licensee which showed that lixiviant and pollutants are, in the short term, being confined laterally to the well field vicinity.
License modifications directed by the May 23, 1980 Order included: (1) Requiring the licensee, within 90 days, to demonstrate that continued operation of this project should be authorized by providing a detailed geologic and hydrologic analysis that shows that control of the in-situ leaching process and restoration of the groundwater are achievable.
(2) Changing lixiviant to sodium carbonate / sodium bicarbonate solution.from previously used ammonia based solutions.
(3) Continued monitoring of diagnostic wells.
(4) Conducting additional aquifer pumping tests.
(5) Limiting production to previously mined well fields.
(6) Continued efforts to remove existing contamination.
Mount Taylor Project Technical Assistance Completed On May 16,1980, the Uranium Recovery Licensing Branch forwarded to the New Mexico Environmental !mprovement Division (NMEID) a tailing management evaluation report on the Mt. Taylor Uranium Mill Project proposed by Gulf Mineral Resources Company.
The tailings management evaluation was provided as part of a technial assistance agreement with the State of New Mexico. Under the technical assistance agreement, a radiological assessment of the Mt. Taylor Project had been provided on April 4,1980 The.GC and New Mexico environmental review. process ultimately resulted in Gulf developing and proposing the burial of tailings in specifically excavated trenches more than 50 feet below grade.
ENCLOSURE D
0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending May 30, 1980 1.
Houston Lighting and Power Company (South Texas Project Units 1 and 2) -
Civil Penalty Action - On May 23, 1980, the Commission received a check from the subject licensee in the amount of $100,000 in full payment of proposed civil penalty issued on April 30, 1980.
2.
The following Notifications of Significant Enforcement Action were dispatched during the past week:
a.
EN-80-07A Alexandria Hospital, Alexandria, VA - On May 23, 1980, an Order Imposing Civil Penalties in the amount of $2,100 was issued to the subject licensee. After consideration of the licensee's response to the Notice of Proposed Imposition of Civil Penalties, the IE Staff concluded that the items of noncompliance did occur and no adequate reasons were given by the licensee for mitigation or remission of the proposed penalties.
b.
EN-80-19 Virginia Electric and Power Company (Surry Units 1 and 2) -
On May 28, 1980, a Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $8,000 were issued to the subject licensee. This action is, based on two alleged items of noncompliance relating to the improper radiation surveys of waste drums delivered to a carrier for transport and improper radiation surveys of the transport vehicle after loading.
3.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-I-80-83 Salem Unit 1 - A Security Guard Taken to Offsite Hospital b.
PNO-I-80-84 Haddam Neck - Inadvertent Gaseous Release c.
PNO-II-80-93 North Anna Unit 1 - Spurious Safety Injection Actuation d.
PNO-II-80-94 Turkey Point Unit 4 - Feedwater Pipe Crack e.
PNO-II-80-95 Hatch Unit 1 - Unit Shutdown f.
PNO-III-80-100 Palisades - Unit Startup After Prolonged Shutdown g.
PNO-III-80-102 Illinois Department of Transportation, Springfield, IL -
Mositure Density Gauge Run Over By Truck h.
PNO-III-80-103 Diamond Shamrock Chemical Co., Fairport Harbor, OH -
Licensee Unable to Account for Gauge Containing Cs-137 Sealed Source 1.
PNO-V-80-38 Rancho Seco - Series of Earthquakes in Central California During May 25-27, 1980 ENCLOSURE E
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- j. PNO-V-80-39 Trojan - Ash Fallout From Mt. St. Helens k.
PNO-V-80-40 Nuclear Engineering Company, Richland, Washington Burial Site - Banning of Commonwealth Edison Co., Quad-Cities Nuclear Power Station, Cordova, Illinois (NRC Licensee) for Radioactive '4aste Shipments 1.
PNO-V-80-41 Diablo Canyon Units 1 & 2 - Earthquake Off of Central California Coast on May 28, 1980 m.
PNO-V-80-42 Washington Nuclear Project No. 3 - Collapse of Tower Crane at WNP-3 Site n.
PNO-TMI-80-31 Three Mile Island Unit 2 - Failure to Maintain Contajnment Integrity o.
PN0-TMI-80-32 Three Mile Island Units 1 & 2 - Ambulance Leaves Site p.
PNS-I-80-12 Indian Point Units 2 & 3 - Bomb Threats q.
PNS-III-80-07 Zimmer - Bomb Threats r.
PNS-III-80-08 Zimmer - Bomb Threat 4.
The following IE Circular was issued:
a.
IE Circular 80-13. " Grid Strap Damage in Westinghouse Fuel Assemblies,"
was issued on May 28, 1980 to all holders of power reactor operating licenses and construction permits for pressurized water reactors.
5.
The following IE Information Notices were issued:
a.
IE Information Notice 80-22, " Breakdown in Contamination Control Programs," was issued on May 28, 1980 to all holders of power reactor operating licenses and those nearing operating license issuance.
b.
IE Information Notice 80-23, " Loss of Suction to Emergency Feedwater 4
Pumps," was issued on May 29, 1980 to all power reactor facilities with an operating license or construction permit.
E"CLOSLF.E E
OFFICE OF THE EXECUTIVE LEGAL 01 RECTOR ITEMS OF INTEREST WEEK ENDING MAY 30, 1980 UCS Petition For Emergency and Remedial Action In a Memorandum and Order (CLI-80-21), dated May 23,1980, the Commission affirmed its decision of April 13, 1978 not to grant the Petition which sought Commission action with respect to fire protection for electrical cables and environmental qualification of electrical components.
Douglas Point Nuclear Generatina Station, Units 1 and 2 On May 27, 1980, the presiding ASLB terminated this proceeding at the request of the applicant.
Sterling Power Project, Unit 1 On May 28, 1980, the Rochester Gas and Electric Corp., Applicant, requested the Appeal Board to terminate all proceedings involving the Sterling application because it is discontinuing the project.
Diablo Canyon Nuclear Power Plant, Units 1 and 2 On May 29,1980, Commissioner Kennedy issued a Memorandum to Counsel for the Parties in which he again stated that there is no basis for disqualifying himself from the proceeding as a result of his October 19, 1979 meeting with applicant's representatives. However, because of the short time remaining of his term of office, and because of a desire to avoid fruitless expenditures of litigative resources, the Commissioner stated that he will not participate farther in this proceeding.
Sterling Power Project, Nuclear Unit i On May 29, 1980, the Commission issued an Order in which it affirmed ALAB-502.
In ALAB-502, the Appeal Board partially affirmed an initial decision authorizing the issuance of a construction permit and interpreted the Commission's "obviously superior" standard for choosing among alternative sites.
Chairman Ahearne and Commissioner Bradford dissented.
i ENCLOSUEE G
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ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MAY 30, 1980 INTERNATIONAL COOPERATION Incident at la Hague I
June Meeting of the IAEA Board of Governors, Vienna, Austria, June 1980 IP has advised the Department of State that NRC will likely not ask to be included on the U.S. delegation to the June meeting of the IAEA Board of Governors, but-.that we are planning to be represented at.the September meetings of the Board and the IAEA General Conference.
- Deleted fren POR copy.
ENCLOSL'RE H i
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2 June Meeting of the IAEA Board of Governors continued The main items for action or discussion at the June meeting were discussed in State Department telegram Vienna 5822, dated May 10, 1980. These items include:
IAEA's role in post-INFCE activities; the successor to IAEA Director General Eklund; the designation of new 1980-81 Board members; the project / supply agreement for the Triga research reactor and LEU fuel to be provided to Malaysia by the U.S.;
the 1979 Safeguards Implementation Report; the Indonesia Safeguards Agreement; the 1979 IAEA annual report; and the 1981 budget document.
Renewal of Exchange Arrangement with Italv The Italian Comitato Nazionale per l'Energia Nucleare (CNEN) this week advised IP that, except for a few minor changes which its legal office might require, it 4
finds the proposed renewal text of the NRC-CNEN information exchange Arrangement acceptable, and is preparing the Italian language version to be signed simulta-neously.
CNEN President U. Columbo has already indicated his intent to visit Washington for the signature.
Foreign Assignees to NRC Two foreign regulatory officials arrived at NRC to begin. training assignments:
Mr. Jose F. 31stulfi, from the Brazilian CNEN, will be with the Inspection and Enforcement Region IV office, Vendor Inspection Branch, for approximately one month; Mr. Librado S. Gesalta, from the Philippine Atomic Energy Commission, will be with the NRR Division of Systems Integration, Power Systems Branch, for a six-month period.
Other assignees currently at NRC are: Miss Rosario Salas Collantes and Mr. Fernando Recreo, both from the Spanish JEN, assigned to NRR; Dr. Oguz Akalin, from the Turkish Atomic Energy Commission, assigned to NRR; and Mr. Philip Wisco, from the Philippine Atomic Energy Commission, assigned to I&E Region IV for six months and then to be assigned to NRR for another six months.
Mr. David C. Y. Huang, Taiwan Atomic Energy Council, has been invited to be with the NRC/TMI Program Office, and is expected to arrive by mid-June.
Assignments are also'being developed for the following: Mr. Bernard Fourest, from the CEA in France to be with NRR; Mr. Kwang Hak Choi, Korean Atomic Energy Bureau, to be with I&E Region I; and Mr. Michael Laraia, from the European Communities, to be with *he NRC/TMI Program Office.
IP has also coordinated the interests of foreign regulatory agencies to have selected staff members work with Metropolitan Edison on the TMI-2 clean up project. Spain, Brazil, and Taiwan have each nominated one staff member for the Met Ed' program.
These nominations have been sent to Mr. Robert Arnold, Vice President, Metropolitan Edison.
ENCLOSUc.E H y-- - - -
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Foreign Visitors On Tuesday, Mr. E. Aust, Project Leader for Containment Pressure Suppression of the German Research Institute (GKSS), met with F. Eltawila, CSB/NRR, to discuss the pressure suppression containment activities between the NRC and the GKSS.
On Wednesday and Thursday, Mr. Lars Svensson of the Swedish State Power Board toured Indian Point-2 to view feedwater flow instrumentation.
1 On Thursday, Messrs. Lennart e rlsson and Bengt Lydell, of the Department of Energy Conversion of the Chalmers University of Technology in Sweden, met with R. Bernero, Director, and W. E. Vesely of PAS /RES to discuss probabilistic methods of reactor safety analysis.
Foreien Reports I
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1
- :eleted from PDR Copy ENCLOSURE,H
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~ EXPORT / IMPORT AND INTERNATIONAL SAFEGUARDS Meeting of the Safeguards Action plan Working Group (APWG)
NRC staff from the Offices of IP and NMSS attended a scheduled meeting of the APWG on May 29 at the State Department. The group (1) was provided a new work plan (IV.B.3) from the Arms Control and Disarmament Agency for review and comment; (2) discussed briefly work plan I.B.2 and agreed that further review and comment was necessary; and (3) reviewed activities associated with work plan IV.C.2 and concluded that no further action was necessary at this time. The next scheduled meeting is planned for July 22.
GA0 Study of NNPA EDO, IP, NMSS, ELD, and IA Offices met with GAO representatives on May-27 for an initial meeting to discuss how the NRC goes about applying the criteria of the NNPA to export license applications. The Commission's sources of information was a subject of special attention. The purpose of this GA0 effort is to analyze the effectiveness of having a review of the NNPA criteria conducted independently of that performed by the Executive Branch.
It is one element of the study of the imple-mentation and impact of the NNPA, called for by Section 602 of the Act.
ENCLOSURE H
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MAY 30, 1980_
State Agreements The North Carolina and New York City Health Departments' regulatory programs for control of agreement materials will be reviewed during the week of June 2, 1980.
A partial review of the Oregon Department of Human Resources program will also be conducted during the week of June 2.
Program Develoement Gail Grambau, summer intern, joined the staff this week and will produce the State Legislation report during the detail of Betsy McCarthy to ADM.
1 i
ENC!.CSU:E I
OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING MAY 30, 1980 Abnornal Occurrence A potential abnormal occurrence pertaining to a loss of confinement at B&W was sent to the Commission fo.- approval.
Decommissioning With SD's concurrence, updated information in " Program Area Briefing Book" on NRC's decommissioning program for Commissioner Gilinsky.
I Annual Report Promised delivery date for advance copies is on/about June 9 with full press run completed later in the week.
, Congressional Index Index for Congressional correspondence for April was sent to Office Directors and others.
1 ENCLOSURE J e
0ffice of the Controller Items of Interest Meek Ending May 30, 1950 FY 1980 Reorocramming Congressional approval received from the Hart Subcommittee was based on the condition that the " Commission Management Study" and the " Nuclear Data Link Study" be conducted in accordance with tie Conference Bill on NRC's FY 1980 Authorization.
The Senate Appropriations Committee has not year approved.
FY 1982 Budcet Formulation DMB was briefed on the new decision units proposed by the Program Offices.
Preliminary approval was granted.
h Enclosure K
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