ML20053B026
| ML20053B026 | |
| Person / Time | |
|---|---|
| Issue date: | 05/20/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-820514, NUDOCS 8205270636 | |
| Download: ML20053B026 (37) | |
Text
,, c PDL m
,5 44 May 20, 1982 o
<-l IP ip
- s p/ g For:
The Commissior.ers
'l
/
From:
T. A. Rehm, Assistant for Operations, Office of the 0 s
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 14, 1982 4
3
'A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
Executive Legal Director F
International Programs G
State Programs H
Resource Management I
Analysis and Evaluation of Operatic.ial Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L
CRGR Monthly Report M*
Executive Director for Operations N*
Items Addressed by the! ommission 0
C
- No input this week.
D
//
T. A. Rei,
ssistant for Operations Office of the Executive Director for Operations FOR SUBSCRIBERS ONLY
Contact:
y l
T. A. Rehm, E00 l
492-7781 l
8205270/,36
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending May 14, 1982 LaSalle Unit 1 The licensee's projected initial criticality date for Unit 1 is June 23, 1982. Open items fo a full power license are 1) independent design audit report and evaluatioa; 2) snubber list and tendon lift-off teG spec tables;
- 3) complete a successful emergency exercise; and 4) provide the interim meteorological improvement.
Three Mile Island Unit 2 During the week of May 17, 1982, GPU Nuclear Corp plans to initiate the processing of the approximately 90,000 gallons of contaminated water in the reactor coolant system through the Submerged Demineralizer System. The 90,000 gallons of contaminated water represent the last major body of water generated during the accident which has not been processed.
Spent Fuel Storage On May 10, 1982 Ridihalgh Eggers and Associates submitted a quality assurance l
plan for the design and fabrication of the REA 2023 Dry Storage Cask for review. The REA 2023 cask was recently selected by DOE through contract for demonstration of dry cask spent fuel storage.
US/ Australian Bilateral Agreement A draft agreement has been prepared to use as a basis for discussions with the Australians that start May 18 at the State Department. The Agreement places some very specific requirements on the U.S. when dealing with Australian origin material.
Some regulation amendments will be necessary l
(specifically,10 CFR 110) and some repcirting requirements will need to be slightly revised.
Emergency Preparedness NUREG-0849, Standard Review Plan for Review and Evaluation of Emergency Plans for Research and Test Reactors has been completed and sent to the printer for publication.
Bailly Generating Station, Nuclear-1 l
L, On May 6,1982, the Atomic Safety and Licensing Board issued an Order granting the motion of the applicant to tenninate the pending proceeding relating to the l
applicant's request for an extension of its construction pennit. The Licensing Board further held that the applicant's construction permit is deemed to have expired but that "neither the expiration of [the construction pennit] nor the tennination of this proceeding... shall preclude NIPSCO from applying for a new construction permit in the future with regard to the Bailly site".
l T
9 D
OFFICE OF ADMINISTRATION Week Ending May 14, 1982 ADMINISTRAfIONOFTHEFREEDOMOFINFORMATIONACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 254 7
Granted 1 91 0
Denied 26 6
Pending 37 1
ACTIONS THIS WEEK Received Daniel Akst, Requests all documents relating to NRC activities The Record concerning Sheffield Brook, Rare Earths, Inc.,
(82-219)
W. R. Grace and Company and Electro-Nucleonics, Inc., in Wayne, New Jersey; and any other materials relating to radiation in Wayne, New Jersey.
Ellyn R. Weiss, Requests a copy of any research reports, or other Harmon & Weiss documents relating to recent research results (82-220) suggesting that nuclear waste or spent fuel may react with salt to form sodium.
Amy George, Requests a copy of contract NRC-10-82-358 for MBA Management, Inc.
Career Counseling.
(82-221)
(NRC employee)
Requests three categories of information regarding l
(82-222) her EE0C Complaint.
Andrea K. Wilson Requests copies of all correspondence between (82-223)
Dow Chemical Company and the NRC regarding Dow Chenical receiving a license from the NRC to incinerate lab wastes contaminated with low-level radiation in 1974 and a copy of Dow's license.
Larry Yellen, Requests four categories of information regarding Better Government employees of the NRC having traveled to or from Association Europe on Supersonic Transports (SSTs) from (82-224)
January 1,1981.
CONTACT:
J. M. Felton ENCLOSURE A i
492-7211 l
1
2 Received, Cont'-d Lynn Connor, Requests cost / benefit analyses used for Doc-Search Associates prioritizing the generic issues which were (82-225) discussed on the April 13, 1982 Commission meeting.
(NRC employee)
Requests a copy of an Office of Inspector and (82-226)
Auditor report.
Granted Steven C. Sholly, In response to a request for seven categories Union of Concerned of documents regarding "TMI Action Plan Tracking Scientists System" report dated January 1982, made available (82-180) seven documents.
(NRC employee)
In response to a request for copies of her rating (82-198) factor certification forms for Vacancy Announcements 82-1450, 82-1295, 82-0997 and 82-5226, made available four documents.
J. L. Miller, In response to a request for a copy of the citation Mount Sinai and fine levied against Nuclear Pharmacy within Medical Center the past two or three years, made available a (82-203) copy of the letter and notice of violation.
Richard I. Lavine, In response to a request for a copy of all Attorney-At-Law intelligence-type records regarding Texas (82-211)
Mcbilization for Survival, informed the requester the NRC has no documents subject to this request.
Tom Schlesinger In response to a request for copies of all (82-218) contracts awarded by NRC and its predecessor, AEC, to E. R. Johnson Associates and its subsidiaries, informed the requester the NRC has no documents subject to this request.
Suggested that he contact the Department of Energy.
Amy George, Informed the requester a copy of contract NRC MBA Management, Inc.82-358 is already available at the PDR.
(82-221)
Denied Jan L. Kodner, In response to a request for 11 categories of Tutt & Kodner documents relating to the LaSalle Nuclear Power (82-168)
Plant, made available 17 documents.
Denied portions of 31 documents in order to withhold the names of individuals and personal identifiers so as to protect the confidentiality of these sources.
ENCLOSURE A
o DIVISION OF CONTRACTS ITEMS OF INTEREST
.. WEEK ENDING MAY 14,1982 RFP NO.: RS-NMS-82-033 Title :
" DEVELOPMENT OF A MATERIAL ACCOUNTING DATA STORAGE / ANALYSIS SYSTEM"
==
Description:==
The contractor shall develop a simple computerized material accountina data storage / analysis system utilizing the NIH compute,.._ility in conjunction with NRC-based hardware.
Period of Performance: 18 months after award Sponsor: NMSS Status: Best and Final proposals under evaluation May 12, 1982 through May 17, 1982 CONTRACTS CLOSED-0VT NRC-10-80-664 Boeing Computer Service 5/10/82 NRC-ll-78-630 Battelle Columbus Lab.
5/11/82 NRC-05-79-259 Mobile Systems 5/12/82 NRC-03-79-154 U.S. Naval Research Lab.
5/13/82 NRC-04-79-179 Mathematical Applications Group, Inc.
5/07/82 NRC-03-77-001 Univ. of California 5/10/82 NRC-03-75-099 Dept. of Commerce, NOAA 5/12/82 NRC-03-76-277 Dept. of Commerce, NOAA 5/12/82 NRC-03-78-161 Science Applications, Inc.
5/12/82 NRC-03-77-037 Nuclear Associates Int'1.
5/12/82 NRC-03-78-174 Dept. of Commerce, Bureau 5/12/82 of Census ADMINISTRATIVE MATTERS 1.
The General Accounting Office report entitled, "Less Sole-Source, More Competition Needed on Federal Civil Agencies Contracting" (SLRD-82-40, dated April 7,1982), makes a number of recommendations relative to increasing competition for contract awards.
Pursuant to provisions of Section 236 of the Legislative Reorganization Act of 1970, the agency must respond to their recommendations within 60 days.
Response due to Commission May 21, 1982.
2.
Under contract NRC-04-81-178, Battelle Columbus Laboratories is performing a study on degraded piping. Battelle recently inquired whether or not the NRC would consider them to be in a conflict of interest position should l
they beccme the successful offeror on an Electric Power Research Institute (EPRI) request for proposals (RFP).
The EPRI project which is entitled, l
l'
" Pipe Rupture and Depressurization Experiments" has similarities to the l
ongoing NRC projects. Af ter a thorough comparison of the work to be performed and the objectives of both the NRC and EPRI projects, the NRC l
has determined that Battelle could compete for the EPRI project without l
the potential for a conflict of interest arising from the work being performed under the NRC contract.
l e
ENCLOSURE A l
i i
4 DIVISION OF SECURITY ITEMS OF INTEREST Week Ending May 14, 1982 NRC Top Secret Classification Authority By order dated May 7,1982, Presioent Reagan gave the NRC Top Secret Clas-sification Authority under the provisions of Executive Order 12356.
e e
a Y
ENCLOSURE A
0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 14, 1982 1.
LA SALLE UNIT 1 CURRENT PLANT STATUS On April 17, 1982, a fuel load and a low power testing license was issued to Commonwealth Edison Company (licensee) for La Salle Unit 1.
The licensee initiated fuel loading on April 18, 1982 and completed fuel loading by April 30,1982. On May ll, 1982, the licensee informed us that its projected initial criticality will be June 23, i982; no mechanical problems have been encountered. The licensee is attempting to heat the primary water to 1700F by pump heat and perform a hydro-test at pressure on the vessel.
Presently, the licensee is correcting preop deficiencies that were deferred until after fuel load and is responding to some concerns of its independent design audit.
STARTUP TESTING SCHEDULE Mil estone Schedul ed Actual Begin Fuel Load 4-15-82 4-18-82 MODE 4 5-9-82 5-11-82 (Shutdown below 212 F)
MODE 3 5-19-82 (Shutdown above 212 F)
MODE 2 6-15-82 (Initial Criticality)
(Startup/ Standby)
MODE 1 7-1-82 (Run)
UNUSUAL EVENTS During the licensee's fuel loading, a 16th bundle subtritical test verification was completed.
Fuel load proceeded through a total of 32 bundles at which.
' me the neutron source / fuel / detection chamber geometry was such that a high ti count rate was observed.
Fuel loading was discontinued; the geometry was reviewed; and the procedure was revised as a' result of an engineering evaluation and approval.
The geometry was changed by relocating the detection chamber in accordance with the revised procedure, and fuel loading was continued.
ENCLOSURE B
k ::
1.
LA SALLE UNIT 1 (Cont'd)
OPEN ITEMS FOR FULL POWER LICENSE 1.
Independent design audit report and evaluation.
2.
Snubber list and tendon lift-off Tech Spec Tables.
3.
Complete a successful emergency exercise and demonstrate an adequate alerting / notification system.
4.
Provide the interim meteorological improvement.
OTHER ITEFG THAT MAY IMPACT LICENSING 1.
2.206 Letter and Amendment from the Attorney General of Illinois making allegations relative to poor construction work.
2.
2.206 Letter from Illinois Friends of the Earth making similar allegations of poor construction work.
2.
SAN ON0FRE UNIT 2 CURRENT PLANT STATUS On February 16, 1982, a fuel load and low power testing 'icense was issued l
to Southern California Edison Company, San Diego, Gas and Electric Company, the City of Anaheim, California, and the City of Riverside, California. The startup testing program is currently in progress, and the plant is currently scheduled to go above 5% power in late June,1982.. The schedule as of issuance of the license and the current schedule are given below.
Slippage to date resulted from repair of leaking check valves and other minor repairs.
STARTUP TESTING SCHEDULE - SAN ONOFRE 2 l
ORIGINAL CURRENT / ACTUAL MILESTONE SCHEDULE
. SCHEDULE Begin Fuel Load
'2-17-82 2-19-82 Fuel Loading and Head t-Tensioned 3-13-82 3-13-82 Begin Hot Functional Testing
.3-30-82 4-09-82 O
3 6-82 J'
Initial Criticality
/.
5-22-82 6-16-82 6-26-82 Exceed.5% Power l
ENCLOSURE B I
I ::
2.
SAN ON0FRE UNIT 2 (Cont'd)
- 3. /
UNUSUAL EVENTS
-a
,. [
' c.
T; There have been two unusual events declared since fuel loading.
The first' '
occurred on March 14, 1982, when a loss of shutdown cooling was caused by inadventent injection of. nitrogen into the shutdown cooling system, thereby disabling both SDCS pumps..The system was vented and shutdown cooling was restored within'90 minutes. 1)uring the time when shutdown cooling was being re-established, the boron concentration of the RCS was diluted from 2004 ppm to'1962 ppm because the SDCS pump suction was switched to the RWST, which was at 1640 ppm boron. The RCS boron concentration did not approach the technical specification limit of 1720 ppm. Since there was no. irradiated fuel in the core, plant safety was not affected by this event.
The second unusual event o'ccured on April 28, 1982, when greater than 1 gpm of unidentified RCS leakage existed. The event was terminated when the RCS drain valves were, properly seated by cycling them. This event occurred during leakage testing of check valves'between the RCS and the
~HPSI and LPSI/SDCS systems.
Six of.these check valves were found to have greater than allowable leakage, and were repaired before proceeding, thereby delaying the testing program.about ten. days.
OPEli LICENSING ITEMS FOR FULL POWER,...
1.
GA Design Verification Program - Program and staff $ view complete, SSER input transmitted to DL.
.~
2.
CE Feed and Bleed Issue - Generic review in progress - SSER input justifying full power operation before completion of generic review has been transmitted to DL. '
3.
Off Site Emergency Plan - SSER input from EPLB transmitted to DL. ~ Final FEMA confimation of correction of implementation deficiencies required prior to issuance of full power license.
4.
Full Power Technical Speciification Revisions - Licensee proposal due 5/12/82.
Staff evaluatiod required.
i 5.
ASLB Initial Decision - e'xpected by Mid-May,1982.
9e 1
7 ENCLOSURE B
k
. 3.
TROJANNUCLEARPLdNT Trojan has completed fuel cycle 4 and is currently in a refueling outage.
The unit operated during the cycle with evidence of some fuel failures.
Dose-equivalent iodine coolant activity rose throughout the cycle, reaching 80-85% of the technical specification limit near the end-of-cycle.
The core is now unloaded. All fuel assemblies (FA) have been visually inspected and 176 have been sipped.
Eight FAs are visably damaged.
Nine other FAs had some evidence of damage as deduced from sipping.
Most of the fuel failures appear to be due to " baffle-jetting" of coolant through gaps in the reactor internals core baffle.
High-velocity coolant impinges on the fuel rods, and induces vibration thereby causing mechanical damage (broken fuel rods, damaged grid spacers, missing fuel pellets).
The gaps in the internals baffl-e will be gauged starting May 10.
The license, Portland General Electric Co., and Westinghouse are pursuing a resolution to the problem.
No corrective action plan has yet been established.
4.
THREE MILE ISLAND UNIT NO. 2 During the week of May 17, 1982, GPU Nuclear Corporation (the licensee) plans to initiate the processing of the approximately 90,000 gallons of contaminated water in the reactor coolant system (RCS) through the Submerged Demineralizer System (SDS).
In accordance with the Commission's Statement of Policy of April 27, 1981, the NRC staff approved the use of the SDS to process the highly contaminated water in the reactor building sump and RCS on June 18, 1981 and the Commission was informed of the staff intent to approve the use of the SDA at TMI-2 on June 10, 1981 (see SECY-81-369).
The staff's Safety Evaluation Report (NUREG-0796) related to the operation of the SDS was issued in June 1981.
Over the past eight j
months, the licensee has processed approximately 635,000 gallons of reactor I
building sump water and this activity is essentially complete as only l
several thousand gallons remain in the building sump.
The 90,000 gallons.
I of contaminated water in the RCS represents the last major body of water generated during the accident which has not been processed.
The processing of the RCS will be on a batch feed and bleed basis.
Speci-fically, reactor coolant will be bled from the RCS at the same rate that previously processed accident generated water is fed to the RCS until 50,000 gallons is collected. The 50,000 gallon batch will then be processed through the SDS and this processed water will be used as the feed for the collection, and subsequent processing, of the next 50,000 gallon batch from the RCS.
In this manner, the processing of the RCS water by feed and bleed l
will continue untii the gross activity in the water is reduced to 1 pCi/ml l
or less. At present, the gross activity in the water is approximately l
30 pCi/ml, consisting primarily of Cs and Sr radionuclides.
Decontamination l
ENCLOSURE B i
4.
THREEMILEISLANDONITNO.2(Cont'dl.
of the RCS water to 1 pCi/ml or less will be sufficient to initiate additional RCS cleanup activities including the defueling of the core.
Following core defueling, the RCS water will be removed and polished for ultimate dispositien.
The environmental impacts resulting from RCS water processing are presented in the SDS Safety Evaluation Report (NUREG-0796) and are within the scope of impacts previously assessed in the Final Programmatic Environmental Impact Statement (NUREG-0633) for TMI-2 cleanup.
5.
MEETING There was a meeting on May 12, 1982, with Germans to discuss OBE versus SSE seismic design requirements.
l I
s~
i e
ENCLOSURE B r
O t
O NRC TM1 PROGRAM 0FFTCE. WEEKLY STATUS REPORT f
May 9,*1982 - May 15', 1982
.T
~
Plant Status Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
Available Core Cooling Modes:
Decay heat removal (DHR) systems, Mini.
DHR(MDHR) system.
RCS Pressure Control Mode:
Standby pressure control (SPC) system.
Backup Pressure Control Modes: MDHR and DHR system.
Major Parameters (as of 0500, May 14,1982) (approximate values)
Average Incore Thermocouples:
103 F '
Maximum Incore Thermocouple:
129'F RCS Loop Temperatures:
A B
98 F 10l*F Hot Leg Col'dLeg(1) 85 F 84*F (2) 90 F 86*F Pressure:
96 psig Reactor Building: Temperature:
72*F Water level:
Elevation 282.8 ft.
(0.15 ft. from floor)
~
Pressure:
-0.35 psig Airborne Radionuclide Concentrations:
3 4.5 E-7 uCi/cc H (sample taken 5/4/82) '
85 7.8 E-6 uCi/cc Kr (sample taken^5/4/82) 5.3 E-10 uCi/cc particulates l
l (sample taken 5/13/82) 1.
Effluent and. Environmental (Radiological) Informatiori Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period May 7, 1982, through May 13, 1982, the effluents contained no detectable radioactivity at the discharge point and I
l individual effluent sources, which originated within Unit 2, contained no detectable radioactivity.
~
ENCLOSURE B I
1 l
. m 2.
Airborne Effluents Airborne releases to the environment as measured by licensee installed monitors at discharge stacks are listed below.
These releases were well within regulatory limits.
April 1982 Unit II EPICOR II I
I Noble Gases (Ci)
<2 29 x 10
<2.97 x 10 Particulates (Ci) 1.50 x 10-6 3.15 x 10-7 Tritium (Ci) 1.80 2.30 x 10-3 3.
Environmental Protection Agency (EPA) Environmental Data The EPA.tiddletown Office has not received the environmental Kr-85 analytical results for the samples which were taken April 16, 1982, through May 7, 1982, from the EPA's Counting Laboratory at Las Vegas, Nevada.
These results will be included in a subsequent report.
No radiation above normally " occurring background levels was detected in any of the samples collected from the EPA's air and gamma rate networks during the period from May 5,1982 through May 13, 1982.
4.
NRC Environmental Data Results from NRC monitoring of the environment around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-319 May 5, 1982 - May 8, 19.82*
<1.4 E-13 <l.4 E-13
- Note:
The NRC continuous air sampling equipment was placed out-of-servic.e on Nay 8,1982.
Repairs to the equipment are in progressiand-the unit is expected to be returned to service on May 19, 1982.
5.
Licensee Radioactive Material and Radwaste Shipment On Friday, May 7,1982, five 250 milliliter. liquid samples from Unit 1 were mailed to Westinghouse Corporation, Madison, Pennsylvania.
On Tuesday, May 11, 1982, 10 drums containing Unit 2 miscellaneous submerged demineralizer system (SDS) samples were shipped to Oak Ridge Nationaf" Laboratories, Oak Ridge, Tennessee.
ENCLOSURE B
Major Activities
~
1.
Submerged Demineralizer System (SDS).
Processing of SDS batch 26 (reactor coolant bleed tank water) was completed on May 8, 1982. The performance parameters for this batch are included in Attachment 1..The 5n5 system is now secured for minor maintenance in preparation for processing of reactor coolant system (RCS) water (see RCS processing).
Preparations are being made for the first shipment of an SDS vessel to Richland, Washington.
SDS vessel number D-15 contains approximately 4,800 curies of predominately cesium 137 and strontium 90. A special Type B shipping cask has been provided for this shipment.
The SDS vessel and the shipping cask cavity will be inerted with nitrogen in order to meet the requirements of the Certificate of Compliance (C0C) for shipping. The actual shipment is scheduled to start,on May 21, 1982.with arrival at Richland expected on May 25, 1982.
The receiver, Pacific Northwest Laboratory (PNL), will use this vessel as part of their DOE-sponsored vitrification research and development program.
2.
EPICOR II.
The EPICOR II system continued to process SDS effluents auring the week and its performance parameters are included in.
3.
Reactor Coolant System (RCS) Water Processing.
Engineering and construction efforts by the licensee in preparation for RCS processing have been completed.
Recovery Operations Plan Change 12, which addresses chemistry specifications for chlorides, dissolved oxygen, and dissolved hydrogen, has been approved by the NRC/TMIP0 site office and the Chemical Engineering Branch of Nuclear Reactor Regulation.
The functional test of modifications and sampling systems for RCS processing is completed.
RCS processing through SDS will occur on an approximately 14 day cycle.
The first seven days of the cycle will consist of RCS letdown to the "C" reactor coolant bleed tank (RCBT), concurrent with makeup to the RCS from the "A" RCBT, until approximately 50,000 gallons of RCS water are in the "C"
RCBT.
The next seven days of the cycle will constitute actual processing of th,e 50,000 gallon batch 2.from the "C" RCBT through the SDS system. The process will bypass the SDS feed tanks. This seven day feed and bleed cycle followed by the seven day SDS cycle will continue until
~
all the RCS water..has.beqn process.ed.
The RCS processing operation is s
scheduled to begin on May 17, 1982.
4.
Reactor Building Entries.
The next reactor building entry is scheduled for Thursday, May 20, 1982.
Supporting activities for the control rod drive lead screw removal will commence during this entry.
Scheduled,
tasks include radiati.on surveys of reactor coolaqt system high point l
I vents and the in containment nitrogen supply syscem. A dose rate monitoring device will be lowered into various areas inside the "D-rings" (reactor coolant system radiation barriers) to determine whether the radiation levels in the "D-rings" will permit personnel access to attach a tygon tube type wgter level monitor to the reactor coolant system.
l l
ENCLOSURE B t
1
-4 e:~... y.f Prior to lead screw removal, the reactor coolant system will be depressurized and the primary water level will be lowered below the tops of the control rod drive housings.
The lead screw removal and closed circuit television inspection of the reactor vessel upper internals is scheduled for July 1982.
~
,5.
Groundwater Monitoring.
The elevated tritium concentrations in groundwater in the vicinity of the borated water storage tank have remained in essentially the same ' range as identified in previous Weekly Status Reports.
Past Meetings 1.
On May 11, 1982, Lake Barrett participated in a panet discussion on THI issues, which was locally televised in the Central Pennsylvania area.
Other panelists included Susan Shanaman, Chairman, Pennsylvania State Public Utilities Commission; General Dewitt Smith, Director, Pennsylvania Emergency Management Agency;'Mr. Philip Clark, Executive Vice-President, General Public Utilities; Mr. Steven Sholly, Union of Concerned Scientists; Ms. Kathy McCaughin, Bipartisian Committee to Vote "No", and Mr. Earl Peters, Friends and Family of TMI.
The moderator for the panel discussion was Representative James Wright, Chairman of the House Select Committee on TMI.
The purpose of the discussion was to provide information to residents of the Dauphin, Cumberland and Lebanon counties, which have referendums on May 18th to answer yes or no to the following question:
"Do you favor the restart of TMI Unit 1, which was not involved in the accident of March 28, 1979?"
2.
0n May 11, 1982, Lake Barrett met with a group of Middletown mothers to discuss various TMI Unit 1 and Unit 2 issues. They expressed their opinion that Unit i should not be restarted until Unit 2 is cleaned up.
Future Meetings 1.
On May 19, 1982, Lake Barrett will meet in the Middletown Office with several Middletown area residents to discuss TMI issues.
2.
On May 20, 1982, Harold Denton, Bernard Snyder and Lake Barrett will testify in Washington, DC, before Senator Alan K. Simpsons' Senate Subcommittee on Nuclear Regulation, Environment and Public Works Committee.
ENCLOSURE B i
A
ATTACHMENT 1 SDS PERFORMANCE FOR BATCH NUMBER 26 Average Average Average
~
Radionuclide Influent Effluent DF (uc/ml)
(uc/ml) 3 Cesium 137 1.5 1.5 x 10-3 1.0 x 10 Strontium 90 9.1 x 10-2 9.8 x 10-3 9.3 J
EPICOR II PERFORMANCE May 7, 1982 - May 14, 1982 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml.)
3 1.5 x 10-3 4.5 x 10-7 3.3 x 10 Cesium 137 2
Strontium 90 6.2 x 10-3
<1.1 x 10-5
> 5.6 x l'0 3
Antimony 125 3.5 x 10-4
< 3.4 x 10-7
>1.0 x 10 i
1 i
R- +
0 l
l l
e i
ENCLOSURE B
OFFICEOFfiCLEAP,tiATERIALSAFETYANDSAFEGUARDS Items of Intere_s_t, t
Weeking Ending May 14, 1982 Meeting With W. R. Grace & Co.
W. R. Grace and Company, formerly Rare Earths, Inc., processed are to recover natural thorium and rare earths at a facility near Pompton Plains, New Jersey.
The ore-processing at this facility included work done under Atomic Energy Commission (AEC) contract and also AEC licensed activities.
This facility was identified in the HMSS review of formerly licensed sites as a facility that did not have adequate documentation in the file to indicate that it would meet todays criteria for an unrestricted area.
Contamination in excess of current criteria was verified by Region I in 1981 and a later Aerial Radiation Survey indicated that contamination also existed offsite in the vicinity of a nearby creek.
In early 1982, NMSS contracted with Dak Ridge Associated Universities (0RAU) to perform a comprehensive radiological survey of both the W. R. Grace property and the offsite properties to determine what, if any, remedial action is required.
The survey of the offsite properties was completed by May 1, 1982 and there was considerable public interest.
In a parallel action in January 1982, the NMSS staff requested DOE to evaluate the former AEC contracts to determine whether or not the Pompton Plains site should be included in the DOE Formerly Utilized Site Remedial Action Program (FUSRAP).
By letter dated April 21, 1982 from W. E. Mott (DOE) to R. G. Page, Dr. Mott indicated that it was DOE's legal opinion that this site should be included in the FUSRAP program and that they would include it as a FUSRAP site upon receipt of the NRC radiological survey results and other pertinent information from NMSS.
Spent Fuel Storage On May 10, 1982 Ridihalgh Eggers and Associates submitted a quality assurance l
plan for the design and fabrication of the REA 2023 Dry Storage Cask for review.
The plan will be included as Chapter 11 in the Topical Report on the REA 2023 cask which REA will submit this summer. The REA 2023 cask was recently selected by DOE through ccntract for demonstration of dry cask spent fuel storage.
Spent fuel capacity of the cask is about 10 metric tons.
Site Visit During the week of March 3-7, 1982, Safeguards personnel visited the GE-Vallecitos and General Atomic facilities in California.
The decommissioning of the plutonium fuel laboratory and plutonium analytical laboratory at GE are in the final stages, with all waste shipments to DOE to be completed by the end of June 1982.
e ENCLOSURE C l
l l
2 US/ Australian Bilateral AgYeement For the past two months, the NMSS staff has been participating in weekly meetings at the State Department to develop and review the Administrative Arrangements to implement the US/ Australian Bilateral Agreement.
A draft has been prepared to use as a basis for discussions with the Austrai that start May 18 at the State Department.
The Agreement places some very specific requirements on the U.S. when dealing with Australian origin material. Some regulation amendments will be necessary (specifically,10 CFR 110) and some reporting requirements will need to be slightly revised. The U.S. will need to initiate some new records keeping systems particularly for moderator material and nuclear equipment and components.
Notification of pending rulemaking has been sent to nine licensed facilities that are major exporters and importers of nuclear material. Additional notification may become necessary depending on the results of the working sessions with the Australians.
TRANSEAVER Meeting Staff members of the Division of Safeguards will discuss the TRANSEAVER (Transportation by SEA Verification) project with representatives of FEMA, D00, CIA, and the Department of State on May 13, 1982, at the State Department. This meeting is to provide discussion of the project and its interagency funding.
TRANSEAVER is an interagency project which will allow for the remote safeguarding of shipments of nuclear materials, or other valuable cargo, at sea.
" REC 0VER" Briefing by ACDA On May 12, Dr. Jeorg Menzel, Chief, Nuclear Safeguards and Technology Division (ACDA), provided a briefing on the REC 0VER program for NMSS. The objective of this program is the improvement of international safeguards through the remote monitoring of safeguards sensors and the secure transmission of safeguards data to central or local IAEA safeguards offices. NMSS is preparing an assessment l
of the program to provide a basis for determining the extent to which NRC supports the program as one means of strengthening IAEA safeguards.
i I
t-v I
ENCLOSURE C
Meetings - Division of Safeauards
-1.
Subject:
Briefing at Ft. Bragg'(NRC-Classified)'
Date:
May 14,1982 Location:
Ft. Bragg, NC Attendees:
Robert F. Burnett, Brant Jones (NRC) 2.
Subject:
Site visit to Ft. St. Vrain to familiarize the Safeguard Re/iewer with the Physical Security Program.
Date:
May 24-27,1982 Location Denver, CO Attendees:
Charles Gaskin (NRC) 3.
Subject:
Site visit to San Onofre and Diablo Canyon.
In San O'nofre -
will discuss safety safeguard relationships. At Diablo Canyon - will discuss a preliminary review of the pending Revision 11 of the Physical Security Plan.
Date:
May 17-21,1982 Location:
San Onofre and San Luis Obispo, CA Attendees:
Charles Gaskin (NRC) 42
Subject:
Discuss MC&A issues and implenentation of the physical security upgrade with Babcock and Wilcox.
Date:
May 12-14,1982 Location:
Lynchburg, VA Attendees:
Gordon Gundersen, Odell Smith (NRC) 5.
Subject:
To discuss comments on the proposed Category I nonpower reactor physical protection with the l
University of Virginia.
Date:
May 18,1982 l
Location:
Charl.ottsville, VA Attendees:
Carl Withee, L. J. Evans, Jr., Carol Rossomondo, Donald Carlson (NRC)
Bryce Shriver (University of VA) t+
6.
Subject:
To discuss. comments on the proposed Category I nonpower reactor physical protection with the National Bureau of Standards
[-
Date:
May 20,1982 Location:
Washington, D.C.
Attendees:
Carl Withee, Robert Dube, Carol Rossomondo, Donald Carlson (NRC)
Mr. Rabi (NBS) l ENCLOSURE C
!!eetinos-DivisionofSafecuards(Cont'd) 7.
Subject:
To discuss comments on the proposed Category I nonpower reactor physical protection rule with Texas A&M University.
Da te:
June 29,1982 Location:
Texas A&M'Un~iversity College Station, TX Attendees:
Carl Withee, Donald Carlson, L. J. Evans, Jr. (NRC)
Dr. John Randall and, other representatives of the Training Research and Test Reactor Managers Group 8.
Subject:
To discuss the Environmental Impact Statemen't update on CRBR fuel cycle safeguards.
l Date:
May 12-13,1982 Location:
Willste Building, Silver Spri.ng, MD Attendees:
Davis Hurt, Robert Dube (NRC)
Pat Reardon, Ken Byers, Bob Sorenson (Pacific Northwest Lab.)
Meetings - Division of Fuel Cycle and Material Safety 1.
Subject:
Review of Topical Report - Dry Spent Fuel Storage Cask i
Date/ Time:
May 17 - 20 Location:
Livermore, California Attendees:
L. C. Rouse (FC), J. P. Roberts (FC),
Representative from Lawrence Livermore Laboratory
~
1,,
2.
Subject:
Familiarization with General Electric plant operations for review of the renewal application and to observe Region II Health Physics inspection of GE plant operations.
Date/ Time:
May 24 - 28 location:
Wilmington, North Carolina Attendees:
A. L. Soong (FC) 3.
Subject:
Attend 1AEA meeting.
Date/ Time:
May 27 - June 5 Location:
Vienna, Austria Attendees:
E.Y.Shum(FC).
ENCLOSURE C
Meetings - Division of aste Management I
1.
Subject:
Future SCR Report from BWIP Project Date:
May 21, 1982 Location:
Olympia, WA Attendees:
Nicholas D. Lewis; H. J. Miller, R. J. Wright, WMHT; R. D. MacDougall, WMPI 2.
Subject:
Saturated and Unsaturated Flow in Fractured Media Date:
May 22-25, 1982 Location:
Tucson, AZ Attendees:
T. Verma, WMHT; Dr. Simpson, Dr. Neuman, Dr. Evans, Dr. Davis, and Dr.' Thompson 3.
Subject:
Conference of Radiation Control Program Directors; Talk to be given on 10 CFR Part 61 Date:
May 26-28, 1982 Location:
Portland, ME Attendees:
R. Dale Smith, WMLL W
I l
l l
1-l l
w l
ENCLOSURE C 1
l i
N OFFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST Week Ending May 14, 1982 l
t 1.
The following Significant Enforcement Actions were taken dUring the past w' ek:
e EN-82-15. Virginia Electric and Power Company (Surry Unit 1) - A Notice a.
of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $50,000.wereissued on May 10, 1982. This action is based -
on one violation concerning the failure to follow procedures which resulted in exceeding a limiting condition for operation.
b.
EN-82-16, Consumers Power Company (Palisades) - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $16,000 Wercissued on May 12, 1982.
This action is based upon the licensee's failure to maintain containment integrity during reactor startup and the failure to follow safety-rclated procedures durin'g maintenance o.n a control rod drive mechanism.
2.
The following Preliminary Notifications were dispatched during the past nek:
a.
PN0-I-82-35, Philadelphia Electric Company (Limerick Unit 2) - Public Utility Commission Order.
b.
PNO-I-82-36, Vermont Yankee Nuclear Power Corporation (Vermont Yankee) -
Freight Train Derailment Near Site.
c.
PN0-II-82-49A, Carolina Power and Light Company (Robinson Unit 2) - Update On Broken React 5i. Coolant Pump Bolts.
d.
PNO-II-82-51 A, Duke Power Company (0conee Units 1, 2, and 3) - Degraded Tendons In The Shield Wall.
c.
PNO-II-82-54 and 54A, Nuclear Fuel Services, Incorporated (Erwin, T.N),
Reported Inventory Difference.
f.
PN0-II-82-55, Duke Power Company (Catawba Units 1 and 2) - Change In Fuel Load Dates.
g.
PNO-III-82-45, Commonwealth Edison Company (Dresden Unit 2) - Scheduled Maintenance Outage.
h.
PNO-III-82-47, Consumers Power Company (Palisades) - Plant Outage to Repair Generator Exciter.
i.
PN0-V-82-24, Southern California Edison Company (San Onofre Unit 1) -
Debris Identified In Secondary Side Of Steam Generator.
j.
PNO-V-82-25, Soutnern Californic Edison Company (San Onofre Unit 1) -
Loss of Salt Water Cooling System And Flooding in Saltwater Pump Bay.
P.
Y ENCLOSURE D
4 k.
PNO-V-82-26, Washington Public Power Supply System (Washington Nuclear Project No. 2) - Meeting Between NRC -RV Regional Administrator And Representatives Of The Governor Of The State Of Washington On May 15, 1982.
3.
IE Bulletins and Information Notices a.
IE Bulletin 82-01, Revision 1, " Alteration of Radiographs of Welds in Piping Subassemblies" was issued on May 7,1982. The revision added three plants to the list of facilities that are required to take action, and clarified that the scope of the Bullatin was limited to pipes having wall thickness less than 1/2 inch.
b.
IE Information Notice 82-13, " Failures of General Electric Type HFA Relays" was issued on May 10, 1982 to all nuclear power reactor facilities holding an operating license or construction permit.
c.
IE Information Notice 82-14 "TMI-l Steam Generator / Reactor Coolant System Chemistry / Corrosion Problem" was issued on May 12, 1982 to all nuclear power reactor facilities holding an operating license or construction permit.
4.
Other Items a.
Division of Reactor Programs The GA0 audit of the NRC Resident Inspector. Program will not include visits to Regions II and III as previously planned.
The GA0 will complete their audit activities in Region IV but will not continue the audit due to a Congressional request of higher priority.
b.
Division of Engineering and Quality Assurance (1) A memorandum describing the consulting services and laboratory analyses available to the regions was sent to Regional Administrators on May 7, 1982.
The contract services available are for " Independent Assessment -
Destructive Testing and Analysis" and " Technical Assistance to Support l
NRC Personnel In The Investigation of Incidents."
(2) A meeting was held on May 6-7, 1982 with members of ASNT, ASME, EPRI, utilities, and NRC staff to develop a plan for the improvement of NDT personnel qualifications and certification.
' ' ~
c.
Division of Emergency Preparedness i
(1) The Director, DEP, and staff members participated in the evidentiary hearing this week on emergency preparedness related to the Waterford license application.
l l
l ENCLOSURE D
(2) NUREG-0849, Standard Review Plan For Review And Evaluation Of Emergency Plans For Research And Test Reactors has been completed and sent to the printer for publication. NUREG-0849 is the third and final document which addresses emergency preparedness plans
.1Tirresearch and test reactors. The other two documents are Draft ?
ANSI /ANS 15.16 Standard for Emergency Plans For Research Reactors dated November 1981, and NRC Regulatory Guide 2.6, Revision 1, Emergency Plans for Research and Test Reactors, dated March 1982, which endorses ANSI /ANS 15.16.
d.
Investigation Staff MOU with Department of Labor is in final negotiations.
D0L is epxected to concur in a final change by cob 5/14.
At this point, MOU will be ready for NRC/ DOL signature.
K W
ENCLOSURE D
0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending May 14, 1982 Nuclear Plant Data Bank System Demonstrations Invitations were sent to NRC staff and contractors, for the Nuclear Plant Data Bank System demonstrations that are scheduled for the week of May 17, 1982.
TRAC Analysis of Steam Generator Overfill Transients A LANL report on a TRAC analysis of steam generator overfill transients for a B&W plant was received. The report number is LA-TCA-TN-81-4 and was written by Britt Bassett.
It concerns calculations performed, at NRR/AE00 request, of the overfilling of once-through steam generator secondaries, leading to combined primary / secondary blowdown. A series of six calculations were performed.
The base calculation assumed runaway main feedwater to one steam generator causir.g it to overfill, leading to a main-steam-line break.
Four additional calculations build onto the base case with combinations of a pump-seal failure, a steam-generator tube rupture, and the pilot-operated relief valve act reseating. A sixth calculation involves only the rupture of a single steam-generator tube.
The results of this analysis indicate that for the transients investigated, the emergency cooling system provided an adequate make-up coolant flow to mitigate the accidents.
Independent Code Assessment Program As part of the independent code assessment program INEL completed the following calculations using TRAC-BDl:
a.
TRAC-BD1 Calculation and Data Comparison of International Standard Problem 12, EG&G-CAAD-5860 b.
TRAC-BD1, Version 11, Code Assessment Calculation of General Electric TLTA ECC/No ECC Test 6425 and 6426, EG&G-CAAD-5827 TRAC-BDl, Version 12, Assessment Using GOTA Data, EG&G-CAAD-5868.
/
c.
ENCLOSURE E
MT-4 Test The 12-rod PNL cruciform for NRU LOCA heatup-clad-ballooning test MT-4 was fabricated, inspected, and prepared for shipment to the NRU reactor.
Test MT-4 is scheduled for May 25-28. Test MT-4 is a near-adiabatic heatup test with cladding heatup rates of approximately 4K/sec under conditions like those used for the ORNL out-of-pile clad-ballooning multi-rod burst test B-6 and for several of the FRG REBEKA out-of-pile clad ballooning tests.
The MT-4 test data will be used to benchmark the B-6 and REBEKA clad ballooning test data and also cladding behavior predictions based on these data.
ORNL BDHT The following final analysis reports are now available$ (a) " Experimental Investigations of Uncovered-Bundle Heat Transfer and Two-Phase Mixture Level Swell Under High Pressure Low Heat Flux Conditions," NUREG/CR-2456, (b) " Dispersed Flow Film Boiling in Rod Bundle Geometry - Steady State Heat Transfer Data and Correlation Comparisons," NUREG/CR-2435, and (c) "An Analysis of Transient Film Boiling of High Pressure Water in A Rod Bundle,"
NUREG/CR-2469. A facility description and the experimental data reports will be available shortly.
FLECHT-SEASET A program management meeting on technical matters related to the FLECHT-SEASET meeting was held on May 6 and 7,1982 at the h[ Bethesda Office in Maryland.
During the first day of the meeting, status on the natural circulation tests and the 163 blocked bundle was presented by h[.
Representatives from NRR commented on the proposed 163 blocked bundle test matrix. A revised test matrix will be prepared by h[ for comments by PMG members as well as vendors, utilities and etc. A briefing on the W FLECHT-SEASET program to vendors, utilities and etc., is tentatively scheduled for the first week of June in Pittsburgh.
In addition, EPRI presented its flow blockage model.
On the second day of the meeting, the COBRA-TF code development was presented by PNL. h[ discussed the proposed h[/PNL joined effort on the flow blockage model to be incorporated into COBRA-TF as part of the work scope of the 163 blocked bundle test program. W/PNL will provide the PMG members with a detailed schedule and workscope on FLECHT-SEASET/ COBRA-TF-co-operation.
ENCLOSURE E
Semiscale The 100 percent break of a feedline, Test S-SF-1, was run May 5,1982.
Preliminary data examination indicates a successful test. Test S-SF-1, a smaller feedline break, is scheduled to be run on May 12, 1982.
Three steam line break tests remain in the SF series, which is scheduled for completion in June. We plan another SO (Systems Operation type) test to repeat S-07-6 following the SF series and prior to the loss of power test series.
NRC/DAE Data Bank Data from the LOFT L1-2 test were added to the data bank. This test contained two sets of data: 1) Blowdown - 200% double-ended cold leg break and 2) an extended isothermal hot wall test.
Human Factors Society SECY-82-178 dated April 26, 1982 informed the Commission of the opportunity to be brieftd by the Human Factors Society on their study and report on a long-range Human Factors Program for the NRC. The Commission has requested and the Human Factors Society has agreed to provide a briefing on May 25, 1982, starting at 10 a.m.
- 4. +
w ENCLOSURE E I
0FFICE.0F THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING MAY 14, 1982 Bailly Generating Station, Nuclear-1 On May 6,1982, the Atomic Safety and Licensing Board issued an Order granting the motion of the applicant (Northern Indiana Public Service Company), to termi-nate the pending proceeding relating to the applicant's request for an extension of its construction permit. The Licensing Board further held that the appli-cant's construction permit is deemed to have expired but that "neither the expiration of [the construction permit] nor the termination of this proceeding
... shall preclude NIPSCO from applying for a new construction permit in the future with regard to the Bailly site".
The Licensing Board also directed that the applicant must implement a site restoration plan previously agreed to by the parties and approved by the Board.
San Onofre Units 2&3 On May 14, 1982, the Licensing Board issued its Initial Decision resolving the full power emergency preparedness contentions and authorizing the issuar.ca of full-power operating licenses for both units subject to the findings by the Director, NRR, on all other matters required by 10 CFR H 50.57(a). The Licensing Board imposed conditions regarding installation of additional services in an extended (i.e. greater than 10 mile) EPZ and expansion of off-site medical services for the public as well as a number of items requiring confirmation by the staff. The Board has retained jurisdiction over the adequacy of the siren warning system.
9" ENCLOSURE F
~
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS
- . WEEK ENDING MAY 14, 1982 Korean Technical Cooperation Activities Les Gage, TMI-Site, departed May 12 for a three-week IAEA technical assistance mission to Seoul, Korea, where he will assist the Atomic Energy Bureau in the area of fire protection safety review.
Foreign Visitors On Monday and Tuesday, Dr. Roger H. Clark, Head of Nuclear Assessments of the UK Radiological Protection Board (NRPB), met with senior RES and NRR staff to discuss the use of probabilistic modeling -in the development of a variety of safety standards and regulatory issues.
On Wednesday, Dr. Max Hintergraber and Mr. Rolf Wittman of the German vendor Kraftwerk Union (KWU) and their consultant Dr. Dietmar Hosser met with J. P. Knight, AD/CSE, and technical staff of the NRR Division of Engineering and the RES Division of Engineering Technology to discuss Operating Basis Earthquake versus Safe Shutdown Earthquake seismic design requirements in the U.S. and the FRG.
Proposed Exchange Arrangement with Austria Dr. Walter Binner, Head of the Austrian Research Centre at Seibersdorf (0FZS),
has forwarded to IP a proposal for a general information exchange and coopera-tion arrangement between NRC and the 0FZS, patterned after the NRC-Danish National Agency of Environmental Protection arrangement he had requested as a sample. The 0FZS has already signed for its part.
IP is considering the proposal and will circulate it to ELD and RES within the next few days. We will also clear any action with the Executive Branch before proceeding.
t l
- t-i l
ENCLOSURE G
O Foreign Reports 9
7 i
Deleted from PDR copy Indicates the reports are in English t
' %, 9 9
ENCLOSURE G
-?-
- Foreign Reports - Cont' d Deleted from PDR copy
(.
ENCLOSURE G
0 0FFICE OF STATE PROGRAMS
'I ITEMS OF INTEREST WEEK ENDING MAY 14, 1982 00E Report on Low-tevel Radioactive Waste Compacts The NRC has been asked by the U. S. Department of Energy to review its draft status report, " Low-Level Radioactive Waste Compacts," prepared in response to a request from Senator James A. McClure, Chairman, Committee on Energy and Natural Resources. The draft DOE report is also being sent by DOE to all States and other Federal agencies for comment.
i e-Speaking Engagement Jerry Saltzman will speak to the American College of Nuclear Medicine in i
Washington, D. C. on May 31, 1982 on the subject of Radioactive Wastes.
ENCLOSURE H
I' 0FFICE OF RESOURCE MANAGEMENT ITEM 0F INTEREST WEEK ENDING MAY 14, 1982 Publications Issued two reports:
(a) Summary Information Report (SIR) Vol.1, No. 2, dated April 1982, NUREG-0871 and (b) Licensed Operating Reactors Status Sunmary Report (Gray Report), Vol. 6, No. 2, dated February 1982, NUREG-0020.
I (9
ENCLOSURE I
f REGION III ITEMS OF INTEREST WEEK ENDING MAY 14, 1982 1.
The Regional State Liaison Officer and a Region III environmental inspector met May 12-13 with representatives of NMSS, U.S. Ecology (licensee), and state and federal agencies to survey the status of the low-level waste disposal site at Sheffield, IL, and the licensee's pro-posed decommissioning program.
2.
Meetings
Subject:
Interface between Region III and the Federal Emergency Management Agency, Region IV Date/ Time:
May 17, 3:30 p.m.
Location:
Region III Office Attendees:
John Anderson, Director, FEMA, Region V James G. Keppler, Regional Administrator, and staff
Subject:
Systematic Assessment of Licensee Performance for Commonwealth Edison Co. construction sites -- Byron 1 & 2, Braidwood 1 & 2, LaSalle 1 & 2 Date/ Time:
May 18, 1:00 p.m.
Location:
Region III Office Attendees:
Commonwealth Edison Co. representatives A. B. Davis, Deputy Regional Administrator, and members of Region III and NRR staff
Subject:
Recent Regulatory Performance of Duane Arnold Energy Center Date:
May 19 Location:
Licensee's Offices, Cedar Rapids, IA Attendees:
Duane Arnold, Chairman, Iowa Electric Light & Company, and staff members James G. Keppler, Regional Administrator, and staff
Subject:
Investigation status - Zimmer construction activities Date:
May 20 Location:
Cincinnati, OH Attendees:
U.S. Attorney (Cincinnati)
Representatives of Region III, IE, and 0IA t~
v ENCLOSURE L
REGION V ITEMS OF INTEREST WEEK ENDING MAY 14, 1982 Sacramento Municipal Utility District Rancho Seco - DN 50-312 An extension auxiliary feedwater header design has been approved with six penetrations through the OTSG shells. Work will begin during the week of 5/17/82.
Southern California Edisor Company SONGS DN 50-206 At 10:20 a.m. (PDT) on May 13, 1982, the licensee declared and terminated an unusual event at SONGS-1.
Both trains of Saltwater Cooling were lost for about 24 minutes at 8:18 a.m.
The reactor was in Mode 5, depressurized with 115 degrees F average reactor coolant system temperature at the start of the event.
During maintenance activities on the South Saltwater Pump, the licensee was removing the pump internals from the casing at about 8:00 a.m.
Since the floor of the pump bay was below sea level, the seawater inlet gates were open, and main circulating water pumps were secured, flooding began from the sea into the pump bay. At about 8:18 a.m., the level in the pump bay reached about four feet (sea level at low tide) and the North Saltwater Pump was secured to prevent pump damage. The licensee was in the process of replacing the South pump internals to stop the flooding. At about 8:42 a.m., the licensee had cross-connected the traveling screen wash water pumps to the saltwater system to re-establish saltwater cooling and terminate system temperature rise and had replaced the South Saltwater Pump internals in the casing to terminate flooding. The licensee was in the process of re-establishing normal saltwater system flow by pumping down the pump bay to start the North Salt Water Pump. The licensee was evaluating the situation cause and effects. The final reactor coolant system temperature l
was about 117 degrees F while the component cooling water temperature increased by 15 degrees F during the event to 77 degrees F.
Southern California Edison Company l
SONGS DN 50-206 The licensee has reported that fiberscopic examination of the secondary side tube sheet of the "A" steam generator revealed several cylindrical fragments on the periphery of the cold leg side of the steam generator. The fragments l,
are believed to be segments of the two-inch diameter carbon steel wrapper l'
support rods formerly, but not presently, used for support purposes, and what appears to be a thickness (feeler) gauge.
Video camera inspection of the tube sheets of all three of the steam generators is planned, as well as retrieval and inspection of the fragments and eddy current inspc: tion of l
steam generator tubes that may be affected.
ENCLOSURE L l
l
/
ITEMS ADDRESSED BY THE COMMISSION - tiEEK ENDIfC MAY 14, 1982 A.
STAFF REQUIREMENTS - AFFIRMATION SESSION, 4:10 P.M., MONDAY, MAY 10, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy to Dircks, 5/12/82 SECY-82-190 - Approval Under Section 145 b. of the Atomh.c Energy Act of 1954, as Amended, for the Employment of Mr. James P.
Jordan as a Consultant to Commissioner Thomas M.
Roberts and for Access to National Security Information and Restricted Data The Commission, by a vote of 3-0 (Chairman Palladino and Commissioners Ahearne and Roberts approving; Commissioner Gilinsky abstaining because he had not had an opportunity to review the SECY paper) (1) determined pursuant to Section 145 b. of the Atomic Energy Act of 1954, as' amended, that the employment of Mr. Jordan as a consultant to Commissioner Roberts and permitting him access to National Security Information and Restricted Data is clearly consistent with the national interest; and (2) granted Mr. Jordan an NRC "Q" access authorization.
B.
STAFF REQUIREMENTS - DISCUSSION OF SECY-82-150 - THE PERFORMANCE APPRAISAL TEAM (PAT) INSPECTION PROGRAM, 2 P.M., THURSDAY, MAY 6, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy to Dircks, 5/12/.82 The Commission was briefed by staff on its recommendations concerning the continuation of the Performance Appraisal Team.
The Commission requested:
a.
information on whether for those plants that have not provided the NRC copies of the final INPO report, the resident inspector has access to the report at the plant site; b.
a list of those plants at which the trial Construction Appraisal Team inspections were conducted during 1981; w
c.
a copy of the IE October 23, 1981 Policy Review Group report.
(IE) (SECY SUSPENSE:
5/19/82)
{
ENCLOSURE 0 I
P
-2 '. '. Y.. :.
~
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MAY 14, 1982 C.
RULEMAKING ON CERTIFICATION OF RADIOGRAPHERS (SECY-82-102), Memo Secy to Dircks, 5/13/82 This is to advise you that the Commission has agreed that the ruleme' ting on certification of radiographers raises a major policy issue.
The Commission therefore requests that this issue should come to the Commission at the rulemaking stage.
This completes SECY action on COMJA-82-2.
D.
SECY-82-142 - REPORT TO THE CONGRESS ON ABNORMAL OCCURRENCES FOR OCTOBER _-
DECEMBER 1981, Memo Secy to Dircks, 5/14/82 This is to advise you that the Commission (with all Commissioners agreeing) has approved the proposed Abnormal Occurrence Report to Congress as modified in Attachment 1.
The Commission believes that the staff should reevaluate the Turkey Point Unit 4 overpressurization event (Item 3 of to the paper) for inclusion in the next quarterly report.
You also should provide the Commission with the reasoning for making or not making the event an abnormal oCCurrenCO.
' (F,OO) (SECY Suspense: 6/11/82)
IfEOO
Attachment:
Not Included l
l l
i ENCLOSURE O
.