ML20235W742
| ML20235W742 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/23/1989 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Bettenhausen L NRC |
| References | |
| NUDOCS 8903130162 | |
| Download: ML20235W742 (5) | |
Text
.i FEB 2 31983 Docket Nos. 50-289; 50-320 MEMORANDUM FOR:
Lee H. Bettenhausen, Chief, Projects Branch No. 1, Division of Reactor Projects FROM:
Curtis J. Cowgill, Chief, Reactor Projects Section 1A
SUBJECT:
TMI STATUS REPORT FOR THE PERIOD JANUARY 14 - FEBRUARY 17, 1989 Enclosed is the TMI Resident Office monthly status report, which covers both TMI-1 and TMI-2. This report is to provide NRC manageme..t and the public with highlights of significant events at TMI-1 and TMI-2 from an NRC regulatory perspective.
ORIGINAL SGNED BY I/
urtis J. Cowgill, Chief Reactor Projects Section 1A
Enclosure:
As Stated cc w/ enclosure:
S. Varga, NRR J. Stolz, NRR R. Hernan, NRR M. Masnik, NRR T. Martin, EDO J. Partlow, NRR J. Roe, NRR L. Whitney, NRR T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania Governor's Office of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI D. Davenport L. Drey E. Harzler A. Herman H. Hucker J. Johnsrud P. Smith H. Spinelli C. Wolfe Cor.cerned Mothers and Women Public Document Room Local Public Document Room 0FFICIAL RECORD COPY MONTHLY STATUS REPORT - 0001.0.0; k 11/29/80 8903130162 890223 PDR ADOCK 0300
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0FFICIAL RECORD COPY MONTHLY STATUS REPORT.- 0002.0.0 11/29/80
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ENCLOSURE THI-1 AND TMI-2 STATUS REPORT FOR (HE PERIOD JANUARY 14 - FEBRUARY 17, 1989 1.
TMI-1 a.
Facility Operations Summary During the report period, the licensee operated the plant at full power.
As of February 17, 1989, the TMI-1 reactor was at 100 percent power with Tave at 579 F and the Reactor Coolant system (RCS) at 2155 psig, b.
Items of Special Interest Relief Valve Failure On February 14, 1989 at approximately 5:45 p.m., a relief valve on the second stage feedwater heater (No. 2B) unseated and released steam to the atmosphere. The steam was second stage extraction steam from the high pressure turbine being used to heat the main feedwater entering the steam generators.. Initial efforts to reseat the valve by temporarily gagging it were unsuccessful. The valve remained open for approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> until a temporary modification was made to gag the valve for an indefinite time period. A replacement valve has been obtained and will be installed at the next available outage. The licensee compensated for the loss of the pressure relief protection for the heater by caution tagging valves to ensure that a parallel heater (No. 2A) remains cross-connected to the affected heater.
A minor amount of radioactivity was released during the event due to minute amounts of contaminants in the secondary side of the steam gene-rator. The licensee calculated that a total of 2.27 microcuries of Iodine-131 and 1051 microcuries of noble gas was released. These re-leases will result in an offsite does of 4.9 E-3 millirem and 2.37 E-6 millirem, respectively. These quantities were determined to be well within regulatory limits specified in Appendix I to 10 CFR Part 50 for gaseous releases.
2.
TMI-2 a.
Facility Activities Summary Following removal ~of'the Incore Guide Support Plate from the vessel on l
January 12, 1989, defueling resumed. Using pick and place methods and the air lifting tools, debris was removed from atop and below the El-liptical Flow Distributor (EFD). Approximately 24,000 pounds of debris were removed during this reporting period. About 67,000 pounds of mate-rial remain.
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,Encfosure L2 Defueling efforts will continue until a production rate of'4000 pounds per week can no longer be maintained. ' Following a drop-off in the de-fueling rate, the plasma-arc cutting equipment will'be.re-installed in the vessel, then.the EFD will be cut and removed.
Removal of the EFD will--facilitate defueling in the reactor lower head.
During this period,' tests were conducted to characterize the material located on the lower head.
Results of these tests _are undergoing evalu-ation; however, preliminary indications'are that a solid slab of're-solidified material extends from the northwest sector to the southeast sector of the lower-head, covering the central one-third width of the head. Tests will be performed on this material to determine its consis-tency and the methods in which it can be broken up and removed.
b.
Items'of Special Interest On February 19, 1989, the licensee made the' eighteenth rail shipment of-core debris to the Idaho National Engineering Laboratory. To date, 259 canisters have been shipped to the' Department of Energy facility.
3.
NRC Staff Activities The NRCistaff assigned on site at the beginning of the period consisted of the senior resident inspector, three resident inspectors, a project manager (for TMI-2), and a. secretary.
.The staff was reduced to one senior resident inspector and.two resident in-spectors on January 30.
R. Conte, who had been the previous senior resident, l
was transferred to the NRC Region I office for another permanent assignment.
Additionally, the site staff secretary resigned on February 10. Both posi-tions will be filled in the future. A new senior resident will be assigned on April 2, 1989.
a.
Inspection Reports-l
'During this period, Region I issued the following inspection reports.
TMI-1 Inspection Report No. 50-289/88-28 on February 2, 1989, ad-dressing routine inspections of operations activities.
'TMI-1 Inspection Report No. 50-289/88-32 on January 9, 1989, ad-dressing an inspection of the technical and safety review process.
r On January 31, 1989, the NRC staff issued a safety evaluation and approval letter regarding criticality safety during plasma arc cutting. This approval allows extended use of the plasma' arc torch over that previously authorized.
The new authorized areas include the upper core support assembly baffle plates and the core support shield.
OFFICIAL RECORD COPY MONTHLY STATUS REPORT.0004.0.0 i
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4.
Public Meetings The Advisory Panel for the Decontamination of TMI-2 met on Thursday, February 16, 1989. The panel was briefed on the status of NRC actions and the status of the cleanup. The GPU Nuclear staff described the evaporator which is pro-posed to dispose of the accident generated water. The Advisory Panel ques-tioned the GPU Nuclear representatives about scheduling and funding.
The next meeting of the Advisory Panel is tentatively scheduled for Thursday, April 13, 1989. The meeting location will be at the Holiday Inn Center City, 23 South Second Street, Harrisburg, Pennsylvania.
Persons desiring to speak j
before the Advisory Panel are asked to contact Mr. Thomas Smithgall at 211
)
Marietta Avenue, Lancaster, Pennsylvania, 17603 (telephone: 717-291-1041).
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0FFICIAL RECORD COPY MONTHLY STATUS REPORT - 0005.0.0 11/29/80 i
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