ML19323H104
| ML19323H104 | |
| Person / Time | |
|---|---|
| Issue date: | 05/29/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-80-273, WIR-800523, NUDOCS 8006120059 | |
| Download: ML19323H104 (35) | |
Text
__-_ - -____ -_ - - _ _ _
- fo UNITED STATES C.
"d NUCLEAR REGULATORY COMMISSION 7[
WASHINGTON, D. C. 20555
/M' M
S'"-*-"
INFORMATION REPORT For:
The Ccmmissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO Subiect:
WEEXLY INFORMATION REPORT - WEEK ENDING MAY 23, 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
B Nuclear Reactor Regulation Standards Development C
Nuclear Material Safety and Safeguards D
Inspection and Enforcemen't E
Nuclear Regulatory Research F*
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 Ccemission M**
Status of Nuclear Power Peactors N
/^,
/T eM for Oceratier
^
. A.
Office of Executive Director for Operations
- No input this week.
- Deleted frem Commissioners and PCR copy.
Contact:
T. A. Rehm 27731 1
800612005T
e O
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending May 23, 1980 Arkansas Nuclear One, Unit No.1 The Unit 1 reactor was shutdown on May 10, 1980, after the pump seal for primary reactor coolant pump C experienced a leak that eventually released approximately 60,000 gallons of reactor coolant water into the containment.
The leakage rate was 200-300 gpm by the time the reactor coolant pump was secured. Small break LOCA procedures were used to control the transient.
It will take two to three weeks to repair the pump seals and clean up the containment for normal operations.
Quad Cities On May 19, 1980, Quad Cities had an unplanned release of radioactive gas when Unit 2 was coming back to power after a weekend outage to repair a condenser tube leak. The gas released was 12.95 Ci of mostly Xe-138 and Xe-135, released over a 20-minute period, and amounting to 1.8% of Technical Specification limits.
Pilorim Unit 1 During start-up from the Spring refueling outage, recirculation pumps were placEd out of service due to failure of the overspeed circuitry, which caused overheating of the MG set slip rings. As a result of the damage, start-up was delayed and projected for no earlier than May 18, 1980.
In addition, a potential labor strike which was expected to commence at 8:00 am on May 16 was averted.
Davis Besse, Unit 1 (DB-1)
On May 14, 1980, the Toledo Edison Company (TECo) reported to the NRC the existence of damaged fuel assembly holdown springs at DB-1.
TECo is inspecting all of the fuel assemblies. They have not yet identified the cause of the damage, but are planning to have one of the springs removed from its assembly and shipped to a hot cell for detailed inspection.
Fort Calhoun, Unit 1 After filling and venting the RCS f'ollowing an extended refueling outage, the closure studs were noticed to be corroded. The studs were previously ultrasonically inspected and showed no indications. A consultant reinspected the studs and verified that the inspection techniques previously_ used were inadequate for this type of problem.
OPPD is in the process of reexamining the studs.
TMI Reactor Buildina Entry Entry was terminated after repeated attempts failed to open the inner door of the containment personnel airlock. The licensee suspects that the problem is due to a differential pressure safety interlock malfunction which prevented the inner door handwheel from going beyond the equali:ation position. The licensee is exploring these developments. No containment entry is planned.
0FF7CE OF ADMINXSTRATION Week Ending May 23, 1980 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF RE00ESTS Initial Appeal of Recuest Initial Decision Received 350 22 Granted 247 5
Denied
-57 10 Pending 46 7
ACTIONS THIS WEEK Received Eugene R. Fidell, Requests a copy of SECY-75-429 dated August 11, 1975.
Attorney-At-Law (80-264)
William H. Briner, Requests all documents on Cooper Medical Center since Duke University March 16,1978.
Medical Center (80-265)
Marvin Resnikoff, Requests information concerning the proposed routes Sierra Club Radioactive of the spent fuel shipments from Chalk River, Canada Waste Campaign to South Carolina.
(80-266)
Michael S. Balter Requests documents pertaining to the proposed (80-267) elimination of a "nine-year-old" rule that bans environmental impact report analysis of possible risks in the event of major accidents at nuclear reactors.
Andrew B. Reid Requests information on listed companies.
Black Hill, Alliance
'(80-268)
Marion P. Johnston, Requests all documents pertaining to Joseph M. Hendrie:
Center for Law ir participation as a consultant to the NRC prior to the Public Interest becoming Chairman, relating to Diablo Canyon, the (80-269)
Hosgri fault around Diablo Canyon, and NRC policies, standards, rules or regulations for seismic design, construction, or seismic analysis of nuclear power plants.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A
2 4
Received, Cont'd Andrew B. Reid, Requests all documents since October 1979 concerning Black Hills Alliance the proposed Draft EIS on the decomissioning of the (80-270)
Edgemont uranium mill.
Martin Levy, Requests the amount of time spent by all individuals NTEU Steward involved in [an NRC employee's] grievance.
(80-271)
(An individual requesting Requests all documents relating to him in the NRC.
informationabout.himself)
(80-272)
(NRC employee)
Requests documents concerning the selection in (80-273)
Vacancy Announcement R-79-589.
Eugene R. Fidell, Requests all documents since March 22, 1980 concerning Attorney-At-Law the Three Mile Island facility.
(80-274)
William Reynolds, Requests a copy of the " Route Oveview" and documents American Friends as prepared for compliance with rules for the Physical Service Comittee Protection of Irradiated Reactor Fuel in Transit for (80-275) eight listed proposed or approved routes.
Marvin Resnikoff APPEAL TO THE EDO for a copy of NL Industries recently Sierra Club ' 21oactive approved route plan for the Canadian shipment of Waste Campaign spent fuel.
(80-A-15-80-219)
(NRCemployee)
APPEAL TO THE EDO for information concerning Yacancy (80-A-16-80-240)
Announcement 80-1000.
Granted Paul M. Murphy, In response to a request for six categories of Attorney-At-Law documents regarding the Consumers Power Company, (80-150) made available 20 documents.
Aram Schefrin, In response to a re:;uest for the names and addresses Lovett & Linder, Ltd.
of personnel who were involved with the use of by-(80-229) product radioactive materials at the Rhode Island Hospital made available this information.
i (An individual requesting In response to a request for documents retrievable information about himself) by search under his name, informed the requester the (80-242)
NRC has no documents subject to his request.
Ie
'l ENCLOSURE A
3 Granted, Cont'd In response to a request for four catecories of Ellyn R. Weiss, documents pertaining to or written by Dr. Joseph Sheldon, Harmon
& Weiss M. Hendrie, made available 10 documents.
(80-243)
John E. McKeever, In response to a request for a copy of 17 listed Schnader, Harrison, documents, made available these records.
Segal & Lewis (80-250)
Mike Tappan In response to a request for a copy of two reports (80-253) and a copy of the NRC's Gray Book dated January,1980, made available this inforLation.
David White, In response to a request for a copy of WASH-740, Vermont Public Interest WASH-1250, NUREG-0660, Draft 3 and NUREG-0460, made Research Group, Inc.
available access to these reports.
(80-255)
Robert E. Cunningham In response to a request for a copy of WASH-740, made (80-259) available access to this report.
(NRCemployee)
Informed the requester the NRC has no information (80-262) pertaining to him in the Office of the Inspector and Auditor or infomation on any charges made against him.
Denied R. Leonard Vance, In response to a request for nine categories of Commonwealtti of Virginia information relating to the radioactive waste shipments (80-145) to enter the U.S. through Portsmouth, Virginia, made available 65 documents. Denied portions of six documer considered comercial or financial (proprietary) information.
Pat Bible, In response to a request for records relating to the Kingsport Times 1979 inventory difference at Nuclear Fuel Services, Inc (80-179)
Erwin, Tennessee, informed the requester this information is classified.
4 ENCLOSURE,A
DIVISION OF CONTRACTS Week Ending May 23, 1980 IFB'S ISSUED IFB RS-01E-80-259 (Two-Step IFB)
Title - Nondestructive Examination (NDE) Mobile Van, Region I Description - Special vehicle designed to be used for conducting independent nondestructive examinations of licensees' facilities.
Period of Performance - 120 days Sponsor - Office of Inspection and Enforcement Statur - IFB issued May 22, 1980 to those firms who submitted acceptable technical proposals under Step 1.
Bids are due June 16, 1980.
PROPOSALS UNDER EVALUATION 1.
RFP RS-RE5-80-192 Title - Effective Peak Acceleration for Nuclear Power Plants 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 foundation level of nuclear power plants.
Period of Performance - Two years and four months Soonsor - Office of Regulatory Research Status - RFP closed May 20, 1980. Proposals to be submitted to Sourc?
Selection Panel for establishment of technical competitive range.
2.
RFP RS-ADM-80-694 Title - Statistical Analysis to Assist NRC Senior Personnel Hearing Counsel Description - The contractor will provide services to the NRC Senior Personnel Hearing Counsel for the purpose of assisting him in preparing and presenting the Agency's case in a pending equal employment opportunity class action litigation.
Period of Performance - Five months Sponsor - Office of Administration Status - Proposals under evaluation.
3.
PCP RS-01E-80-253 Title - Development of an Automated Vendor Selection System (AVSS)
Description - Develop AVSS to enable OIE to make the most cost effective use of its limited resources to inspect a meaningful range of vendors of equipment and services to NRC licensees.
Period of Performance - Two years Sponsor - Office of Inspection and Enforcement
~
Status - Competitive range established. Negotiations being conducted on May 23, 1980.
ENCLOSURE A l
2 CONTRACT AWARDS NRC-19-80-472 Title - Alternative Processes for TMI-2 Kr-85 Removal Description - Identify factors critical to deciding best approach for Kr-85 removal.
Evaluate conditions under which the SAP becomes a feasible alternative.
Evaluate merit of adopting SAP as a substitute for purge venting.
Period of Performance - Three months Sponsor - Office of Policy Evaluation Status - Firm Fixed Price Contract No. NRC-19-80-472 awarded to Science Applications, Inc., effective May 6,1980, in the amount of
$35,440.00.
CONTRACTS CLOSED OUT (All administrative action completea and final payment made)
Contract No.
Contractor Close-Out Date AT(49-24)-0351 United Engineers & Constructors, 5/16/80 Inc.
ADMINISTRATIVE MATTERS Contract No. NRC-04-79-209 with Essex Corporation for project entitled
" Human Factors Evaluation of Control Room Design." Sponsor - Original contract sponsored by TMI Special Inquiry Group with RES funds.
Sub-sequent work added by modification No. 2 funded by NRR.
The contractor is required to review plant control rooms for NRC and, based on the data obtained therefrom, develop control room review guidelines, evaluation criteria, and an audit plan. While performing this work for NRC the contractor entered into several agreements with utilities for the same or similar type work.
NRR, ELD, and DC have reviewed these contracts and have reason to believe that a potential conflict of interest situation exists.with respect to the contractor continuing to perform this work for NRC.
The Contracting Officer issued a Stop Work Order to Essex on May 13, 1980, which was followed by a Cure Notice on May 16, 1980. The Cure Notice advises the contractor that NRC is considering the contract for " Default" and offers the contractor an opportunity to provide any relevant factual information which may impact the Government's final decision regarding the termination for " Default." Upon receipt and review of this infor-mation.-NRR, ELD and DC will determine whether the termination for
" Default" is warranted.
ENCLOSURE A
DIVISION OF FACILITIES AND OPERATIONS SUPPORT Item of Interest Week Ending May 23,1980 ATMOSPHERIC RELEASE ADVISORY CAPABILITY (ARAC)
Facility support and communications have been provided adjacent to the NRC Operations Center for the pilot testing of an Atmospheric Release Advisory Capability terminal. The terminal supports programs of the Office of State Programs and the Office of Nuclear Reactor Regulation.
The terminal became operational May 16, 1980 i
l l
l ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION WEEKLY ITEMS OF INTEREST (Week Ending May 23, 1980)
Arkansas Nuclear One, Unit No.1 At 1:45 a.m., Saturday, May 10,1980, 'the pump seal for primary reactor coolant pump C experienced a leak that eventually released approximately 60,000 gallons of reactor coolant water into the containment. A leak of approximately 12 gpm was discovered while the operators were pe-foming the nomal procedure for leakage rate determination. Technical Specifications require shutdown if that reactor coolant system leakage is greater than 10 gpm. As the reactor coolant system leakage is greater than 10 gpm. As the reactor was being brought to a normal controlled shutdown, the leakage rate increased until, when the reactor coolant pump was secured (shut off at 3:00 a.m.), the leakage was 200 - 300 gon. The reaccor High. pressure injection was manually used for ca.ked was tripped at 2:50 a.m.
up,, cool _ ant,by_ operating and throttling charging,p_ umps., The small break LOCA. pro cedures were used to control the transient.
Pressuruer level and pressure were us to" control make' 6p~cbolist.,Mirli~n' tTsatufation was at least' 100*F at all-~ -
~
In times. Decay heat removal was initiated by the RHR pumps at 9:00 a.m.
order to bring the reactor to a cold shutdown,and therefore atmospheric pressure',
These valves are the operators closed the core flood tank isolation valves.
required by Technical Specifications to be locked open during power operation; of these valves is removed by locking To do this, the power to the operator open the. breakers which furnish power to the valves. These breakers are located inside the containment. Therefore, to provide power to these valves in order that they could be closed by the operators, two men entered the con-tainment to unlock and operate the breakers.
They were in the containment for ~
41/2 minutes r.nd each received approximately 50 mr dose. The field of radiation was 400 to 1000 mr/hr which is consistant with the amount expected for the reactor coolant which was discharged.
The operators initially attempted to open the nitrogen vent valves on the core flood tanks.
The vent valve for one tank operated but the valve to the other tank did not operate. The operators chose instead to close the core flood
' tank isolation valves.
It will be two to three weeks to repair the pu=p seals and clean up the contain-ment for normal operations.
NRR is continuing to review both the details of the reactor coolant pump seal at AND-1 and the lockout of power inside containment to emergency equipment for ali reactors.
l l
ENCLOSURE B
=
w n
.,e,,
2 Ouad Cities-The PM was informed by the RI that on 5/19/80, Quad Cities had an unplanned release of radioactive gas. The gas released was 12.95 Ci of mostly Xe-138 and Xe-135, released over a 20 minute period, and amounting to 1.8% of Technical Specification limits.
The release occurred when Unit 2 was coming back to power after a weekend outage to repair a condenser tube leak. At 5:30 P.M. on 5/19/80, an attendant was sent to close the bypass valve on Unit 2 charcoal absorber.
He instead opened the bypass valve of Unit 1, then operating at 82% power, allowing the unplanned release up the stack.
The red phone was used. A PN is being issued, and there is news media coverage of the event.
A previous unplanned gaseous release occurred at Quad Cities Station on 5/1/80 when a loop seal partially vented and released gas, amounting to about 7% Technical Specification limit, thru the turbine building vent system.
Pilerim Unit 1 During start-up from the Spring refueling outage, an apparent common-mode failure of the overspeed circuitry for the recirculation pump MG sets caused overheating of the MG set slip rings. The slip rings, which were shrunk - fit onto the shaft, translated laterally on the shaft and resulted in both recirculation pumps being placed out of service.
Trcuble shooting the recirculation pump MG set failures that occurred during start-up has been completed and repairs are in progress. The B MG set experienced minor damage caused by the fai'.ure to reinstall leads that were lifted during ATWS-RPT pre-op testing. The lifted leads removed DC excitation and lead to overspeed and subsequent slip ring damage. The A MG set experienced major damage due to a frayed wire shorting the DC excitation to ground. As a result of the A MG set damage, start 'Jp is now being projected for no earlier than Sunday, May 18, 1980.
In addition, a potential labor strike which was expected to commence at 0800 on 5/16/80 was averted.
ENCLOSURE B r
Davis-Besse, Unit No.1 (DB-1)
On May 14, 1980, the Toledo Edison Company (TECo) reported to tre NRC the existence of damaged fuel assembly holddown springs at the 0B-1 which is currently undergoing it-first refueling outage. The function of the spring (one per assembly) 1s to provide a positive holddown margin to oppose hydraulic forces. The plant staff had been inspecting the reactor specimen holders when it first observed a damaged spring.
As of Pay 19, 1980, subsequent inspections of 42 assemblies in the spent fuel pool and 68 assemblies in the core have revealed 11 total cases of damage. The damage is characterized by cracked, broken, or potentially broken springs. A total of 65 fuel assemblies in the core remain to be inspected.
TECo has not yet identified a potential cause for the darage, but is planning to have one of the springs removed from its assembly and shipped to a hot cell for detailed inspection. Also, the utility has not provided to the staff the safety implications of operating with broken springs. B&W has indicated that there is no prior history of this problem on its plants.
The Office of Inspection and Enforcement is following up on TECo's inspection prcgram and it is anticipated that the lead responsibility for studying the safety implications will be transferred to the Office of Nuclear Reactor Regulation.
Fort Calhoun, Unit 1 On May 16,1980, after filling and venting the RCS following an extended refueling outage a srall leak was observed at the "C" RCP during a 200 psi leck check. Upon examination, the closure studs were noticed to be corroded. Visual examinations of f
the A, B and C RCP closure studs showed corrosion on some studs in each pump, with indications of wastage in the 31/2" diameter down to 1 1/2".
The RCPs are Byron Jackson pumps fabricated of SS with 16 cs closure studs. The stuc had been ultrasonically inspected during the current outage with no indications. The consultant was reca'lled and on 5/18/80 reinspected the studs, thereby verifying that the inspection techniques used were inadequate for this type of problem.
OPPD is in the process of removing A, B and C RCPs to perform further inspections en all studs; "D" RCP studs will be visually and ultrasonically examined. Acceptance criteria for reuse of installed studs is being developed.
ENCLOSURE B
NRC TMZ PROGRAM OFFICE WEEKLY STATUS REPORT Week of: May 17-23.1980 Plant Status Core Cooling Mode:
Cyclic natural circulation in the "A" reac*ar coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main cor. denser, and RCS loop-A and B cyclic natural circulation to reactor builcing ambient.
Available Core Cooling Modes:
OTSG "B" to the main condenser; icng term cooling "S" (OTSG-B); decay heat removal.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
i Backup Pressure Control Mode: Mskeup system in conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0600, May 23,1980) (approximate values)
Average Incore Themocouples: 156*F Maximum Incore Themocouple:
192*F RCS Loop Temperatures:
A B
Hot Leg 151 *F iS5"F Cold Leg (1) 77*F 106*F (2) 78'F 122*F RCS Pressure:
84 psig (Heise) 94 psig (DVM - controlling)
Pressurizer Temperature:
109*F Reactor Building:
Temperature: 78'F Pressure:
-0.7 psig (Heise)
Water level: Elevation 290.2 f t. (7.7 ft. frtst floor) via penetration 401 mancmeter (see major activities below)
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.
Results frem EPA monitoring of the environment around the THI site were:
EPA environmental stations registered background levels for air particulate and water sarr les.
ENCLOSURE B
2 Gas / Air (Kr-85) sample results during the period May 9 through May 16,1980, were: Goldsboro - 23 pCi/m3 TMI Observation Center - 34 pCi/m3, Middletown - 24 pC:/m3,, and Bainbridge -
24 pCi/m3 The EPA states that the Kr-85 background concen-tration in the vicinity of TMI to be between 20 and 40 pCifm3 Instantaneous direct radiation readings showed levels within the range of natural background (0.008 mR/hr to 0.020 mR/hr) at all of the EPA monitoring locations during this reporting period.
4.
NRC Environmental Data The West Screen House continuous air sample (HP-216) for the sampling period May 15 through May 21, 1980, has been delivered to the EPA Coordination Center for analysis.
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 f rcm 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.
The licensee provided the following montnly inventory of Kr-85 releases for 1980: January - B0 Ci, February - 60 C1, March - 63 Ci and April - 69. Total through April - 292 Ci Kr-85.
5.
Radioactive material and Radwaste shipments offsite were as follows:
On Monday, May 19, 1980, a Unit 2. reactor coolant sample and smear sample was sent to the Babcock and Wilcox (B&W) facility, Lynchburg, Virginia, for chemical and radiochenical analysis.
On Wednesday, May 21,1950, a Unit 1 LSA ccmpacted waste shipment was sent to Barnwell, South Carolina.
' Two Unit 2 waste shipments, LSA boxes and LSA 55 gallon drums, are on hold pending further licensee evaluation of the isotopic content of the compacted and uncompacted waste.
There was a temporary postponement of radioactive waste ship-ments to Richland, Washington, due to road conditions in Washington State after the recent eruption of Mt. Saint Helen volcano.
6.
EPICOR II Processing Status:
(auxiliary building approximate quantities)
Amount processed this week:
20,000 gallons Amount processed to date:
300,000 gallons Amount to De processed:
144,000 gallons
~
ENCLOSURE 3 '
3 Major Activities (Past and present)
Reactor Buildina Entry. At approximately 9:00 p.m., on May 20, 1980, 1.
tne licensee attempted to enter the TMI-2 reactor building, the first such attempt since the March 28 accident.
The procedure was terminated af ter repeated attempts failed to open the inner door of the containment personnel airlock.
It was thought that the possible causes for the failure to open the door were:
seal surface adhesion or door hinge binding due to corrosion; and/or suction effect due to vacuum conditions between inner door seals.
However, a licensee representative conducted a debriefing with the NRC TMI Program Office staff concerning the events that occurred on Review of this information indicated new developments May 20,1980.
tnat must be explored prior to further attempts to actually open the airlock inner door as noted below.
After the decision to terminate the procedure, the airlock rc
- cn to normal phase was initiated and this included making the innsr/
outer door interlock operable which prevents both doors from being open simultaneously.
(This interlock is presently operable.)
During this evolution it was noted by the licensee that the inn 2r door handwheel was beyond the closed stop position by approximately 1 turn. This meant that the 1-2 turns of full travel experienced by the operators did not include that section of travel to actually operate the door roller mechanism which pennits opening the inner The 1-2 turns did include that section of travel to open the coor.
air pressure equalizing valve between the reactor building and airlock.
The licensee suspects that the inner door handwheel did not go beyond the equalization position due 'to a differential pressure (AP) safety interlock malfunction. Normally this interlock pre-vents the inner or outer door from opening if differential pressure across the door is greater than i psig. The interlock does permit equalization as was experienced during the events of May 20.
On Friday, May 25, 1980, the airlock was entered again, with the inner door closed mair.taining containment integrity. to trouble-shoot the electrical / mechanical aspects of the ap safety interlock for both doors using the outer door as a model. Electrical checks (continuity, solenoid deenergization) proved satisfactory. However, it was noted that the slight distortion of the operating mechanism on the outer door dic cause the aP safety interlock solenoid pin to stick in an energized position enforcing the interlock function to prevent door opening. This distortion was simulated by maintaining a grip on the door handwheel. When the handwheel was released the solenoid returned to the deenergized position.
ENCLOSURE B
4 Based on this information the 4P safety innerlock malfunction is The solenoid / pin assembly is located inside the not ruled out.
The next step in the licensee's reactor building for the inner door.
plan for determining why the inner door cid not open is to equalize air pressure between the airlock and the reactor building (outer door closed) and attempt to go beyond the air equalization position on the inner door handwheel. The inner door will be maintained closed by temporary mechanical means ("come-along").
No containment entry is planned.
On Thursday, Reactor Buildino Sumo Water Level Measurements.
2.
tne Heise gage useo in tne oetermination of reactor May 22, 1980, building water level via the decay heat system was isolated.
Reasurements of water level was shif ted to manometer system thrcugh This shif t in measurer,ents systems was necessitated penetration 401.
over concern about excessive cycling of DH-V6B Containment Sump Isolation to the Decay Heat System.
Failure of this valve was possible and could result in an unisolable reactor building leak.
The gage had to be isolated because of known leakage through DH-VSB, Borated Water Storage Tank (BWST) Isolation to the Decay The resultant pressure head from the BWST would be Heat System.
greater 'han the range of the gage causing gage damage.
Mini Decay Heat Removal (MDHR1 System. While flow testing both of 3.
the MDhR pumps, af ter the system had been hydro tested, the licensee The leak was approximately detected a seal leak on the "A" pump.
The flow test was inmediately terminated and the punps I spm.
shut-off. The pump manufacturer has been contacted to aid in determining the cause of the leak.
The pump seals, because they are of a high grade quality, are not an off-the-shelf item.
The pump manufacturer is trying to obtain replacement seals from their customers' inventory.
If they can not be obtained from this source, it is estimated that there could be a 5 week delay because the seals would have to be special ordered.
Ground Water Monitorino Samoles Results.
Sample results are not yet 4.
16, 1960.
available from the licensee for tnose samples taken on May The cask support platform for the Submerced Deminerali:er System.
5.
summergeo camineralizer system (SDS) that will clean up containment building sump water was recently installed.
The platform spans the Unit 2 "B" spent fuel pool.
The 24-by-11-by-2-foo. device will support the ion exchange polishing unit and filter manifold which are a care of the SDS.
Workers have begun installing a filter support rack which will house the disposable filters used to remove undissolved solids fran l
the water being processed.
The spent fuel pool was drained and decontaminated earlier in preparation for the installation of the 505.
Equipment installation is scheduled to continue for the next 6-10 weeks.
ENCLOSURE 3
5 Meetings Held with rublic Officials and Interested Groups 1.
On May 20,1980, J. Collins,.T. Elsasser, K. Abraham and G. Sanborn responded to media inquiries concerning the unsuccessful attempt to enter the Unit 2 centainment. They also attended the Met-Ed press conference following the event.
2.
On May 21, 1980, J. Collins. T. Elsasser, K. Abraham and G. Sanborn attended the press conference held by Met-Ed to discuss additional aspects of the unsuccessful containment entry attempt.
3.
On May.25, 1980, J. Collins addressed a group of concerned citizens of Lower Manchester Township at a meeting held at the Mount Wolf Lutheran Church.
Future Meetings 1.
On June 9,1980, J. Collins will meet with the pennsylvania Arson Association in Lancaster to discuss clean-up operations at TMI-2.
2.
J. Collins will present an invited paper entitled, "NRC Involvement During the TMI Accident" at the 1980 Annual Meeting of the American Nuclear Society, June 8-13, 1980, in Las Vegas, Nevada.
1 I
ENCLOSUR'E E
)
0FFICE JF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING MAY 23, 1980 1.
Radiation Policy Council: On May 21,1980 there was an initial meeting of the principal Working Group of the Radiation Policy Council to plan an agenda of topics that the full Council should address. It is expected that this agenda would be ready in September. NRC representatives have been named to three initial sub-working groups:
Occupational Exposure:
P. Vacca, NMSS Natural Radioactivity (Radon):
R. Wilde, NMSS Medical /Research Low-Level Waste Disposal:
W. Walker, NHSS A public meeting of the Radiation Policy Council is scheduled for June 11, 1980 to solicit public input on topics which should be addressed by the Council. A notice of this meeting will appear in the FEDERAL REGISTER.
In addition, each of the Federal agencies will perform direct mailings to organizations that might have an interest,in this meeting.
[H. Peterson (443-5860)]
Reculatory Guides to be Issued in the Near Future
Title:
Qualification of Nuclear Power Plant Inspection, Examination, and Testinc Personnel Excected Issuance Date: June 1980 Descriotion: Endorses ANSI /ASME N45.2.6-1978 concerning qualification requirements for inspection, testing, and examination p?rsonnel during pre-op, startup and operational phases.
Contac t:
G. F. Guppy 443-5913
Title:
Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants Excected Issuance Date: June 1980 Descriotion: Endorses ANSI /ASME N45.2.23-1978 concerning qualifications of Teac aucitors and auditors. Minor exceptions taken to the standards.
Contact:
G. F. Guppy 443-5913
-E" CLOSURE C
Title:
Auditing of Quality Assurance Programs for Nuclear Power Plants Exoected Issuance Date: June 1980 Descriotion: Endorses ANSI /ASME N45.2.12-1977 standard of the same title concerning accomplishment of audits as to when and how to conduct them. Major exceptions are taken to the standard in the area of frequenc) of audits with the NRC view of establishing maximum intervals while the standard leaves frequency up to management judgement.
Contact:
G. F. Guppy 443-5913 l
Title:
Nuclear Power Plant Simulators for Use in Operator Training Excected Issuance Date: August 1980 Descriotion:
Endorses ANS.3.5, " Nuclear Power Plant Simulator for Use in Operator Training" with modifications. The ANS 3.5 standard establishes minimum criteria for the degree of simulation, performance and functional capability of the simulator.
Contact:
J. S. Wiebe 443-5913 Publications Issued Durine the Week of May 19-23, 1980 Reg. Guide 5.14. Rev.1 - Use of Observation (Vis.1 Surveillance) Techniques in Material Access Areas [ Issued to Reflect Comments]
Draft Regulatory Guide and Value/ Impact Statement: Instruction Concerning Risk from Occupational Radiation Exposure, Task OH-902-1 [ Issued for Comment; Comments requested by July 21,1980]
E!!CLOSU:.E C
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Endino May 23, 1980 International Safeguards The Safeguard Agreement Implementation Group (SAIG) met on May 19, 1980, to discuss NRC preparations for the implementation of the US/IAEA Safeguards Agreement and develop recommendations for updating the list of eligible licensed facilities. A revised draft of the list is currently being prepared.
Process Monitorino MC&A Draft final reports on the safeguards applicability of process monitoring data of B&W Leechburg, B&W Lynchburg, and General Atomics San Diego plants were received from contractors, distributed for comment, and briefings arranged.
An interim report on a portion of the NFS Erwin plant was also received from a contractor, and technical direction was presented to the contractor for modification of the work necessary for support of the MC&A Upgrade Rule development.
Physical Protection of Irradiated Reactor Fuel in Transit The Federal Recister notice prepared for the final interim rule and letters to Congress informing them of the Commission's action have been signed by the Director, HMSS, and forwarded t; the Division of Rules and Records.
1 The revised NUREG-0561 is being cc.91eted and will be submitted for publication by May 27, 1980.
Kerr-McGee Evaluation of Potential Disposal Sites - Illinois u
Kerr-McGee has been conducting an evaluation of potential sites in Illinois for use as disposal sites for the thorium wastes now stored at their closed-down West Chicago plant. Federal, state and local representatives were invited to a meeting called by Kerr-McGee sa hay 20, 1980, to discuss the alternate site evaluation work. No state officials attended the meeting, presumably because the State of Illinois has brought suit against Kerr-McGee on the subject of the wastes at the West Chicago site. After presenting technical information resulting from their site survey, Kerr-itGee stated that they would go no further in alternate site evaluation work because of lack of cooperation and assistance from state agencies in defining or addressing the technical acceptability of alternate sites and in solving the social and political problems of site selection.
ESCLOSU:E D
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending May 23, 1980 1.
Babcock and Wilcox Company - Civil Penalty Action - On May 21, 1980, the Commission received a check in the amount of $100,000 from the subject company is full payment of the proposed civil penalty issued on April 10,1980.
The following Notification of Significant Enforcement Action was dispatched 2.
during the past week:
a.
EN-80-18 American X-Ray & Inspection, Inc. - On May 19, 1980, an Order Revoking License No. 21-15455-01 was issued to American X-Ray &
Inspection, Inc. This action is based on the provision of the Order to Show Cause and Order Suspending License issued on February 28, 1980.
Since no answer was filed, the Order revoking the license was issued.
1 Preliminary Notifications relating to the following actions were dispatched 3.
during the past week:
a.
PN0-I-80-78 Pilgrim Unit 1 - Transportation Incident b.
PNO-I-80-79 Veterans Administration Hospital, Buffalo, New York -
Ruptured Iodine-125 Seed c.
PNO-I-80-80 Department of the Navy, Philadelphia Naval Yard, Philadelphia, PA - Four (4) Rems Film Badge Exposure d.
PNO-I-80-81 & -81A Calvert Cliffs Unit 1 - Inoperability of Auxiliary Feedwater Systems (AFW) e.
PNO-I-80-82 Oyster Creek - Individual Sustaining Radioactive Contamination in Cut f.
PNG-II-80-73D Brunswick Units 1 & 2 - Unauthorized Disposal of Radioactive Material g.
PNO-II-80-86 & -86A Crystal River Unit 3 - Delay in Refueling Restart Due to Control Rod Drive (CRD) Flange Leakage
'I h.
PNO-II-80-87 Surry Unit 2 - Contractor Personnel Injury
- i. PNO-II-80-88 Crystal River Unit 3 - Radioactive Trash Found at Onsite Dumo
- j. PNO-II-80-89 Crystal River Unit 3 - Cracked Fuel Holddown Springs k.
PNO-II-80-90 Hartsville Unit A QC Inspector and Two Laborers Injured ENCLOSURE E
. 1.
PNO-II-80-91 U. S. Department of Energy Savannah River Plant -
Hydrogen Sulfide Release m.
PNO-II-80-92 General Electric Company, Wilmington, NC - UF6 Release n.
PNO-III-80-94 & -94A Zion Unit 2 - Cracks in Low Pressure Turbine Discs o.
PNO-III-80-95 Davis-Besse Unit 1 - Broken Fuel Rsembly Holddown Springs p.
PNO-III-80-96 Kay-Ray Incorporated, Arlington Heights, IL - Stolen 10 Millicurie Cs-137 Source q.
PNO-III-80-97 Prairie Island Unit 2 - Unscheduled Shutdown r.
PNO-III-80-98 Quad Cities Unit 1 - Unplanned Airborne Radioactivity Release on Monday, May 19, 1980, at Approximately 4:30-4 :50 P.M.
s.
PNO-III-80-99 American X-Ray & Inspection, Inc., Farmington Hills, MI -
Neeting With Non-Licensee Workers Exposed to Radiation From Radiography Actbities t.
PNO-III-80-101 Point Beach Units 1 & 2 - Loss of Red Phone Circuit to Point Beach Due to President Carter's Trip to Mt. St. Helens, Washington State u.
PNO-IV-80-21C Arkansas Nuclear One, Unit 1 - Reactor Coolant Pump Seal Failure (Supplemental Infomation) v.
PNO-V-80-35 University of California, Berleley, CA - Accidental Release of Radioactivity w.
PNO-V-80-36 Nuclear Engineerign Co., Richland, Washington Burial Site -
Banning of Atomic Disposal, Inc. (NRC Licensee), Tinely Park, Illinois For Rad % active Waste Shipments x.
PNO-V-80-37 Trojan, Washington Public Power Supply System, EXXON Nuclear, Pacific Northwest Laboratories - Eruption of Mount St. Helens -
Effects on Major Licensees in the Pacific Northwest y.
PNO-TMI-80-29 Three Mile Island Unit 2 - Unit II Reactor Building Entry z.
PNO-TMI-80-30 Three Mile Island Unit 2 - Unsuccessful Attempt to Enter Containment aa. PNS-80-02 Antinuclear Demonstrations bb.
PNS-I-80-11 Indian Point Units 2 & 3 - Bomb Threats cc. PNS-II-80-13 Turkey Point - Bomb Threat dd. PNS-II-80-14 Westinghouse Nuclear Fuel Facility, Columbia, SC -
Bomb Threat E"CLOSUP.E E i
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MAY 23, 1980 INTERNATIONAL COOPERATION IAEA Safety Mission to Brazil IP received on April 28 a letter from the IAEA reouesting that the U.S. propose an expert to participate in an IAEA safety mission to Brazil in July. The purpose of the Mission is to assist in reviewing the applicability of the lessons learned from the TMI accident to the Angra I nuclear power plant and, more specifically, to evaluate a report prepared by the utility concerning the implementation of.TMI lessons.
IP will work with NRR to attempt to identify a suitable US candidate who can be recommended to the IAEA.
IAEA Recuest for US Assistance for a Workshoo on Two-Loon Westinchouse Plant The IAEA has requested US assistance, in the form of $20,000 and the services of selected US experts, to coriduct a workshop at the Josef Stefan Institute in Ljubljana, Yugoslavia during the summer or fall of 1980. The purpose will be to assist the regulatory bodies of Yugoslavia, Korea and Brazil in safety reviews of two-loop Westinghouse plants. One such plant is in operation in Korea and three others (one each in Korea, Brazil and Yugoslavia) are under construction. There is no US reference plant for this design.
IP has informed State and DOE that NRC supports the idea of such a workshop and would hope to be able to provida Ore or two experts to_ participate in it.
Emeroency Precaredness Discussions with the Canadians The NRC-FEMA emergency planning and response discussions with the Canadians i
(reported in detail in the April 25 " Weekly Activities") have been postponed to July 10-11 because of the non-availability during the originally scheduled May 29-30 ceriod of some of the key local officials who were in charge of the Mississauga evacuation.
NRC will be represented at these meetings by NRR, SD, IE, and SP/ FEMA.
We were advised on May 22 that FEMA is preparing a letter to the EDO accepting his invitation for a permanently assigned FEMA staff member to join the team, as well.
Foreion Assionees The European Communities-(EC) has proposed Mr. Michele Laraia, an Italian national currently working for the EC, for a six-month assignment in the MRC/TMI Program Of fi ce.
IP will coordinate this assignment with NRR, OELD, and SEC.
Foreion Visitors to NRC On Wednesday, Dr. Antonio Carrea, Special Adviser for Ncn-Proliferation and Safe-guards '4atter to President Carlos Castro Madero of the Argentine National Atomic Energy Commission (CNEA) and Member of the IAEA Safeguarcs Advisory Committee, et. itn J. R. Shea, IP Director; J. B. Devine, IP Assistant Director (Designate)
ENCLCSUPE H
2 for Exports / Imports and International Safeguards; R. F. Burnett, Director of Safeguards of NMSS; J. M. Becker of ELD; and R. S. Senseney of IP. The discussions centered principally on (1) the status of pending export licenses to Argentina, (2) general safeguards and physical security issues, and (3) Argentina's future nuclear energy program.
Dr. Carrea returned to NRC on Friday for an informal dis-cussion of current nuclear issues with Commissioner Kennedy.
On Thursday, Messrs. G. Waplington and 0. Buettner of Electrowatt Engineering Services Ltd., a consultant to the UK Nuclear Installations Inspectorate (NII),
met with C. Michelson of AEOD and J. L. Crooks of MPA to discuss LERs and their possible applications to a data library being considered by the British.
On Thursday, Mr. M. Hirata of the Japanese Atomic Energy Research Institute (JAERI) met with R. F. Burnett, Director of the Division of Safeguards of NMSS, to discuss general safeguards and physical protection issues.
Foreien Recorts The following foreign reports were received at IP during the period of May 19 to 23. The ** indicates the reports are in English.
For further information contact Maxine Johnson (492-7788) IP.
From Denmark:
A Proposal on General Design Criteria for the Disposal of High-Level Waste (April 1980)
From FRG:
Contracted Dose Analysis Conducted in the Biblis Nuclear Power Plant (RWE)
(January - December 1977)
Radiation Protection During the First Refueling Shutdown of ' nit A of J
Biblis Nuclear Power Station ** (April - August 1976)
Studies on Design, Equipment, and Organization for Personnel Employed in Nuclear Facilities as Inspectors, Attendants, and Maintenance Workers in the Control Area (May 1977)
First Revisions of Block A in the Biblis Nuclear Power Plant (November 1976)
Radiation Protection Experiences in the Stade Nuclear Power Plant (1973 - 1976)
Radiation Protection in Biblis - A Description of Organization of the Health Physics Group: Some Data Are Given on Radiation Exposure of Personnel During 1976 Deses During Work Performed in the Control Area of the Biblis Nuclear Power Plant, 1976
- Dele:ed from the PDR copy.
~
ENCLOS'?E H
3 Foreign Reports - Cont'd From Italv:
Seven Reports on the Caorso Nuclear Power Plant (CA/029 - CA/035)
Internal Procedures of the CNEN's Nuclear Safety and Health Protection, and the Divisions of Nuclear Power Plants and Inspections From S. Korea:
Monthly Operating Data for KoRi Nuclear Power Plant Unit 1**
(February 1980)
From NEA:
Analysis and Evaluation of the Crystal River Unit 3 :ncident (Prepared by the Nuclear Safety Analysis Center and the Institute of Nuclear Power Operations),
March 1980**
EXPORT / IMPORT AND INTERNATIONAL SAFEGUARDS Meetino of the NRC Safeauards Imolementation Group (SAIG)
IP joined staff members of other NRC offices on May 19 at NMSS to discuss matters related to the US/IAEA. Safeguards Agreement. The principal focus of attention was on the U.S. eligible facility list that will be provided to the IAEA, sub-sequent to signing of the Agreement, to identify those U.S. facilities that will l
be subject to IAEA safeguards inspection. Other matters discussed included development of forms that will be used by licensees to implement the offer, NRC involvement in the preparation of Facility Attachments, amending NRC regulations to accommodate the shipment of samples taken by the IAEA and security clearances for IAEA inspectors. Some of these matters will be further discussed with the Executive Branch.
French Visit Regarding Fuel for High Flux Reactor (HFR), Grenoble Michel Jacquemain and Dr. Wolfgang Grillo, Institute Max Von Laue-Paul Langenin, Grenoble, France, accompanied by Bill Yeomans, of Transnuclear, Inc., called on IP staff May 21 to express concern for the delivery of 72.6 kilograms HEU for the High Flux Reactor, Grenoble, (License Application XSNM01362 which was received 8/8/78 by NRC.
Executive Branch views were dated 3/28/80 and the case is now under review by staff). The visitors were surprisingly well informed as to the cause 1
of delay and were concerned that circumstances beyond their control were causing them fuel supply problems.
'Deletet frem PDP. copy.
ENCLOSU:.E H
s.
4
. proposed Comoonent Excort to Argentina IP has received favorable Executive Branch views on a proposed export to Argentina of a device for checking welds at the Atucha I power reactor (XCOM0293). These are the first set of Executive Branch views received for this facility.
Proposed Component Exoorts to Australia, Finland, and Norway IP is preparing Commission action papers on three component export applications for Australia, Finland, and Norway pursuant to 10 CFR 1110.40 (b)(5) because the proposed exports are destined to countries to which the Commissioners have not previously authorized an export pursuant to the NNPA of 1978.
prooosed Component Export to India for the Bhabha Atomic Research Center IP is p. eparing a Commission action paper on a proposed component export to India or use at the Reprocessing Division of the Bhabha Atomic Research Center. The Executivs Branch has concluded that the proposed export does not meet the requirer.ents of the Atomic Energy Act and should, therefore, be returned to the applicant without action.
US/IAEA Safeguards Agreement On Thursday, May 22, NRC staff met with Executive Branch staff to discuas chances to the provisional eligible facilities list necessary to produce the final list which will be provided to the IAEA upon ratification of the Agreement. Status reports on their respective activities were provided by NRC and DOE.
j i
)
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1 1
l ENCLOSURE H
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MAY 23, 1980 Program Development Dean Kunihiro, the new regional State liaison officer in Region V reported for duty on May 19 and during the week participated in an orientation to become familiar wi
.he regional office. Along with Mr. Robart, the previous RSLO, Dean and other n..
4rs of the Region V staff attended a hearing of the California Regional Watu Quality Board in Oakland on May 20. The hearing was held by the Board to consider reissuance of the NPDES Permit for waste discharges by General Electric Company's Vallecitos Nuclear Center.
State Agreements Program The Georgia Department of Natural Resources radiation control program for agreement materials will be reviewed during the week of May 27, 1980.
The North Carolina, Oregon and New York City Health Department programs will be reviewed during the week of June 2,1980.
Mr. Wayne Kerr addressed the 1.2th annual meeting of the Conference of Radiation Control Directors in Louisville, Kentucky and participated in several workshops and board meetings.
E" CLOSEE I.
OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING MAY 23, 1980 Annual Report Anticipate advance copies of NRC's 1979 Annual Report available during first week in June with full press run by mid-June.
Testimony for Nuclear Safety Oversicht Committee Completed draft of NRC's testimony to President's nuclear safety oversight committee for hearings scheduled for week of May 26 in California.
Manaaement Information Printed and distributed April issue of " Operating Unit Status Report" (Gray Book).
ENCLOSURE J
i OFFICE FOR t.NALYSIS AND EVALUATION OF OPERATIOMAL DATA ITEMS OF INTEREST WEEK ENDING MAY 23, 1980 On Wednesday and Thursday (May 21 and 22), AEOD participated in a Nuclear Plant Reliability Data System Workshop at San Antonio, Texas. AE0D's participation was directed at presenting the AE0D cperational data usage program and providing a status report on activities to improve the Licensee Event Reports (LERs).
The attendees were extremely interested in the status of the NRC's Advanced Notice of Rulemaking to make NPRDS mandatory. While the staff recommendations have not yet been developed, it was indicated that a Commission Paper providing a specific recommendation was targettd by SD for early July.
l ENCLCSL'P.E L 1
ITEMS APPROVED BY THE COMMISSION - RECEIVED WEEK ENDING MAY 23, 1980 A.
SECY 80-206 - H. R. 6570 (Memo Chi 1k to 'sickwit dated 5-19-80)
This is to advise you that the Commission (with four Comissioners concurring) has approved the dispatch of the proposed letter.
Comissioner Bradford would have preferred to have certain deletions made to the text.
Comissioner Gilinsky did not participate in this action.
The staff is requested to provide an original of the letter for the Chairman's j
signature.
B.
STAFF REOUIREMENTS - DISCUSSION OF ACTION PLAN (SECY 80-230),11:20 A.M., FRIDAY, MAY 16, 1980, COMMISSIONER 5' CONFERENCE ROOM, D. C. OFFICE (OPEN TO PUBLIC ATTENDANCE) (Memo Chilk to Dircks, Bickwit anc Hanranan cated 5-20-60)
The Comission* agreed that the list of requirements for new operating licenses,
~
as set forth in Enclosure 1 of SECY.80-230, subject to inclusion of item C-2-2 (which had been inadvertently omitted), constituted sufficient THI-related additions to the pre-THI regulatory requirements, and requested that:
(a) An appropriate Staff Requirements Memorandum be prepared to provide specific instructions to the staff on implementation of the list of j
requirements; (ope) **
l (b) A proposed Commission policy statement be prepared to provide guidance to j
applicants, the staff and the licensing boards on how TMI-related issues should be dealt with in individual licensing proceedings.
In this connection, the Chairman indicated he would circulate a preliminary draft for Commission review and coment.
(OCM/0GC) (SECY Suspense:
5/21/80)
(c) A brief summary of the history and rationale for the full-power operating license requirements be compiled from existing sources where possible.
The summary would be designed to accompany the proposed Policy Statement when issued.
(NRR) (SECY Suspense: 5/21/80)
'Comissioner Kennedy was not present.
- A draft Staff Requirements Memorandum was circulated to the Comission on 5/20/80.
t l
euetOSUn.<
C.
SECY 80-178 - COMMISSION ACTION ON STAFF EXPORT LICENSING APPROVAL (COMMISSIONER ACTION ITEM) (Memo Chilk to Dircks catec 5-21-80)'
This is to advise you that the Commission (with Chairman Ahearne and Commissioners Kennedy and Hendrie approving) has approved staff export licensing actions at variance with approved delegations of authority.
Commissioners Gilinsky and Bradford limited their approval to those items not yet shipped, except XSNM-1586 SNM to Argentina, which they disapproved in connection with SECY-80-198.
In connection with his approval Chairman Ahearne commented:
" Note that we should perhaps refrain from congratulating ourselves on how we have s;mplified the export process, since we apparently have taken back authority for minor cases" In connec. tion with his partial approval Commissioner Bradford commented:
"I am also as uming that Section 128 does not apply to XSNM-1634, since I will not apply nunc cro tune to any of these exports."
The Office of Internation;l Programs was informed of this action by telephone on May 20, 1980.
D.
SECY 80-280 - APPROVAL OF A PROPOSED LICENSE TO EXPORT HIGH-ENRICHED URANIUM TO THE NETHERLANDS (LICENSE APPLICATION NO. XShM 1333) (COMMISSIONER ACTION ITik) (Memo Cn11k to D1rcks cated 5-21-E3)
This is to advise you that the Commissioners have reviewed the subject license to Transnuclear, Inc. The Commission (with all Commissioners approving) has accepted your recommendation to export to the Netherlands 20.050 kilograms of uranium, enriched to 93.3% U-235, in the form of uranium hexaflouride.
The Office of International Programs was informed of this action by telephone on May 20,1980.
E.
SECY S0-210 - ApDROVAL OF OROPOSED LICENSE TO EXPOST HIGH-ENRICHED URANIUM TO BELGIUM (LICENSE APPLICATION NO. X5N!! 1591)(COMMISSIONER ACTION ITEM) (Memo Chilk to Cir:ts catec 5-21-20) i This is to advise you that the Commissioners have reviewed the subject license to Transnuclear, Inc. The Commission (with all Commissioners approving) has accepted your recommendation to export to Belgium 113.182 kilograms of uranium, i
enriched to 93.3% U-235, in the fcrm of uranium hexaflouride.
The Office of International Programs was informed of ti.:s action by telephone on May 20, 1980.
E"CLOSUEE M
. F.
SECY 78-593C - PROPOSED LICENSE TO EXPORT LOW-ENRICHED URANIUM FOR THE WBRL IN TAIWAN ( X5NM 1279, SECY 78-593) (COMMI55IOf4ER ACTION ITEM) (MEMO Cn11k to Dircks cetec 5-21-80)
This is to advise you that the Comissioners have reviewed the subject license' to Transnuclear, Inc. The Comission (with all Comissioners approving) has accepted your recommendation to export to Taiwan 31.84 kilograms of uranium, enriched to 19.2% U-235, in the form of uranium hexaflouride.
The Office of International Programs was informed of this action by telephone on May 20,1930.
G.
STAFF REOUIREMENTS - BRIEFING ON UPGoJDE OF ODERATIONS CENTER (NUCLEAR DATA LINK) 10:05 A.M.. THU'15 DAY, MAY 15.1980, ROOM 550 EAST-WEST TOWERS, BETHESDA, P.ARYLAND (03E'4 TO PUBLIC ATTENDANCE) (Memo Chilk to Dircks cated 5-21-80)
The staff briefed the Commission on the status of staff actions pertaining to the nuclear data link concept.
During the briefing the Commission provided the fo2. lowing guidance:
1.
Review the four options concentrating on Option 2 and on the requirement for standardization.
Identify to what extent the listed data points are required to regulate nuclear power.
2.
Use the monitoring and advisory spectrum of NRC roles. (---line on Chart 1) (attached) as the perspective for further study.
3.
Provide further information on funding with respect to costs, program year requirements and possibilities of cost pass-through to licensees.
4.
Clarify the ACRS views expressed in their letter of May 6, 1980.
5.
Report to the Commission in four-six weeks.
Attachment:
(notincluded)
Chart 4
E" CLOSURE M
' H.
STAFF REOUIREMENTS - AFFIRMATION SESSION 80-22*, 3:30 7.M., THURSDAY, MAY 15, 1980, ROOM 550 EAST WEST TOWERS. BETHESDA, MARYLAND (OlEN TO PUBLIC ATTENDANCE)
C'emo Cnilk to Dircks anc Bickw1: cateo 5-22-80)
I.
SECY-80-131 - Accident Considerations Under NEPA (CONSENT CALENDAR ITEM)
M (Commissioners Gilinsky & Bradford The Comission, by)a vote of 3-2 dissenting in part :
1.
approved the publication of the attached Federal Register Notice sentaining a statement of interim policy relative to accident considerations under NEPA.
(NRR) (SECY Suspense: 6/3/80)
II. SECY-A-80 Prooosed Resconse to Motion Filed With the Commission (CONSENT CALENDAR ITEM) l The tcmmission by a vote of 5-0E:
1.
approved an Order referring an interlocutory motion from the Environmental Coalition on Nuclear Power to the Atomic Safety Licensing Appeal Board for appropriate action; (OGC)
(The Secretary signed the Order on May 16, 1980, and the Order was transmitted to the Appeal Board on May 16,1980).
Chairman Ahearne requested:
2.
that EDO check into problems associated with LPDRs (noted on page 19 of the 4/11 Board Order).
(EDO)(SECYSuspense: 6/3/80)
III. SECY-A-80 Recuest for Commission Fundine of Witnesses Called by Intervenors in TMI-l Restart (CONSENT CALENDAR ITEM)
The Conmission, by a vote of 5-0$/:
1.
aoproved a Memorandum & Order which denies the request of the Consumer Advocate of Pennsylvania to provide financial assistance to intervenors for retalaing expert witnesses to be called during the TMI-1 restart proceeding. Comissioner Bradford filed a separate concurring opinion with which Commissioner Gilinsky agrees.
(OGC) l (The Secretary signed the Memorandum & Order on 5/16/80).
- Aii footnotes for Inis 5ession apoear on page 5.
8 ENCLOSURE
H.
(Cont'd)
IV. SECY-A-80-58/58A - Intervenor Fundino in TMI-1 Restart -- Licensing Boarc Certification (CONSENT CALENDAR ITEM)
The Comission, by a vote of 5 d:
1.
approved a Memorandum & Order which makes it clear that although the Comission has not yet determined whether the issue of psychological distress should be. considered in the TMI-1 restart proceeding, the Comission will not provide funds for interveners to plan for and address this issue in fiscal year 1980.
(OGC)
(The Secretary signed the Memorandum & Order on 5/16/80)
V.
SECY-A-80-29A - Certification to the Comission by the Licensino Board in the Tnree Mile Islanc Restart Proceedino -- Docket No. 50-289 (CONSENT CALENDAR ITEM)
The Commission, by a vote of 3-2M (Cor.:nissioners Gilinsky and Bradford approving in part and disapproving in part as noted below):
1.
approved a Memora'ndum & Order stating that 10 CFR 50.44 will not be waived in the restart proceeding, and that post-accident hydrogen gas control should be an issue in this proceeding. (OGC)
(The Secretary signed the Memorandum & Order on 5/16/80).
Comissioners Gilinsky and Bradford indicated that they would have preferred waiving 10 CFR 50.44 in the restart proceeding. Their separate views were attached to the Memorandum & Order.
Attachment:
(notincluded)
As stated 1/
Section 201 of the Energy Reorganization Act, 42 U.S.C. 5841, provides that action of the Comission shall be determined by a
" majority vote of the members present." Commissioners Gilinsky and Kennedy were not present at the meeting at which this item was approved.
Had Comissioner Gilinsky been present, he would have dissented from the decision in part. Had Commissioner Kennedy been present, he would have voted with the majority. Accordingly, the formal vote of the Comission is 2-1 in favor of the proposed Notice.
2/
Section 201 of the Energy Reorgani:ation Act, 42 U.S.C. 5841, provides that action of the Comission shall be determined by a
" majority vote of the members present." Commissioners Gilinsky and Kennedy were not present at the meeting at which this Order was approved. Had they been present they would have voted to approve this Order. Accordingly, the formal vote of the Co=ission is 3-0.
ENCLOS'$E
I.
STAFF REOUIREMENTS - AFFIRMATION SESSION 80-23, 2:05 P.M., FRIDAY, MAY 16, 1980, CCMMISSIONERS' CONFERENCE ROOM, D. C. OFFICE (OPEN TO PUBLIC ATTENDANCE) (Memo Cr.iik o Bickwit catec 5-19-80)
Affirmation of Order in Taracur Exoort (SECY-79-674A,80-238,80-2383)
The Commission, by a vote of 5-0*:
Approved the proposed Memorandum & Order stating that the Commission cannot find, based on a reasonable judgment of the assurances provided by the Government of India and other information available, that license applications XSNM01379 and 1569, XCOM0240, 0250, 0376, 0381 and 0395 meet the. criteria for issuance set forth in Sections 109, 127 and 128 of the Atomic Energy Act, and is, accordingly, referring these applications to the President pursuant to the procedures set forth in Section 126(b)(2) of the Atomic Energy Act.
(OGC)
(The Secretary signed the Memorandum & Order on May 16, 1980).
-Section 201 of tne Energy Reorganization Act, 42 U.S.C. 5841, provides that action of the Commission shall be determined by a " majority vote of the members present."
Ccmmissioner Kennedy was not present at the meeting at which this Order was aporoved.
Had he been present he would have voted to approve this Order.
Accordingly, the formal vote of the Commission is 4-0.
l 9
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ES:'.050RE M
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)
STATUS OF NUCLEAR POWER REACTORS UNDER NRC PURVIEW - APR. 30,1980 SOURCE: OFFICE OF MANAGEMENT & PROGRAM ANALYSIS Number Capacity
- Of Units (MWe) 1
- 67 LI C E N S E D TO O P E R ATE................................. 49,000 (Excludes 3 which have operating licenses but are shut down indef-initely - Three Mlle Island 2, Humboldt Bay, and Indian Point 1) f 3 LICENSED FOR LOW-POWER TESTING...................... 3,000 85 CONSTR U CTION PERMIT G R ANTED....................... 94,000 34 Under Operating License Review..................... 37,000 51 Operating License Not Yet Applied For................ 57,000 (Excludes 3 which have been denied certification by the N.Y. State Giting Board - Sterling 1 and Jamesport 1 & 2) 11 UNDER CONSTRUCTION PERMIT REVIEW.................. 14,000 (Excludes 3 which are indefinitely postponed - Montague 1 & 2, and Clinch River; and 2 which have been denied certification by the N.Y. State Siting Board - New Haven 1 & 2) 166 TOTA L............................................. 159,000 * *
- j 1
' Net Maximum Dependable Capacity for operating units for which it is established.: net Design Electrical Rating for all other units.
"The 67 units have accumulated 463 reactor years of operation. An additional 56 reactor years of operation have been accumulated by permanently or indefinitely shut down units.
'" Numbers do not add exactly due to rounding.
j NOTE: Only units docketed by NRC are included. Hence.two status categories
(" Ordered" and " Publicly Announced") included in similar charts issued thrt, ugh December 1979 are not used.
NPI 50 1
ENCLOSU.E N
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