ML19340D987
| ML19340D987 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/08/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-150 NUDOCS 8101060105 | |
| Download: ML19340D987 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION 3
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December 8, 1980 NRC/TMI-80-150 p'
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MD10RANDUM FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation j.i M
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Bernard J. Snyder, Program Director, TMI Program Office FROM:
John T. Collins, Deputy Program Director.
TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of November 23 - December 6,1980.
As discussed in the last report, this report covers a two week period.
l 6' John T. Collins Deputy Program Director TMI Program Office
Enclosure:
As stated cc:
ED0 OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors X00S X0MA TMI Program Office Staff (15)
HEW EPA RO&NS Branch Chief, Region I i
FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser 8
810106o los
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of flovember 23 - December 6,1980 l
Pl_ ant _ Status Core Cooling Mode:
Reactor coolint System (RCS) heat transfer to reactor building ambient (air and sump water).
Available Core Cooling Modes: OTSG "A" or "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control flode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: One of two decay heat removal pumps to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST) to provide control of pressure.
Major Parameters (As of 0500, December 5,1980) (approximate values)
Average Incore Thermocouples:
1340F Maximum Incore Thermocouple:
1680F RCS Loop Temperatures:
A B
4 Hot leg 1290F 1320F Cold Leg (1) 700F 710F 0
0 (2) 70 F 70 F RCS Pressure: 97 psig (DVM)
Pressurizer Temperature:
720F 0
Reactor Building:
Tempera ture: 65 F Water level: Elevation 290.5 f t. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.5 psig (Heise)
Concentration:
1.4 x 10-4 uCi/cc (Kr-85) (sample taken 12/4/80)
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 Tiil-2.
3.
EPA __ Environmental Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of November 23 - December 6,1980 Plant St_atus Core Cooling Mode:
Reactor coolant System (RCS) heat transfer to reactor building ambient (air and sump water).
Available Core Cooling Modes: 0TSG "A" or "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: One of two decay heat removal pumps to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST) to provide control of pressure.
Major Parameters (As of 0500, December 5,1980) (approximate values)
Average Incore Thermocouples:
1340F Maximum Incore Thermocouple:
1680F RCS Loop Temperatures:
A B
Hot Leg.
1290F 1320F 0
Cold Leg (1) 700F 71 F 0
(2) 70 F 70 F RCS Pressure:
97 psig (DVM) 0 Pressurizer Temperature:
72 F Reactor Building:
Temperature: 65 F Water level:
Elevation 290.5 f t. (8.1 ft. from floor) via penetration 401 manometer Pressure:
-0.5 psig (Heise)
Concentration:
1.4 x 10-4 uCi/cc (Kr-85) (sample taken 12/4/80)
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.
EPA _ Environmental Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
2 3.
EPA Environ _ mental _ _ Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
The EPA measured Krypton-85 (Kr-85) concentrations (pC1/m3) at several environmental monitoring stations and reported the following results:
Location flovember 21 - December 1, 198_0 I
(pCi/m )
Bainbridge 18 Goldsboro 22 Observation Center 22 Middletown 19 All of the above levels of Kr-85 are considered to be back-ground levels.
flo radiation above normally occurring background levels were i
detected in any of the samples collected from the EPA's air i
and gamma rate networks during the period from fMvember 26 through December 4, 1980.
i I
4.
IIRC Environmental __ Data. Results from f1RC monitoring of the environment around the TF11 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-244 November 26 - December 3,1980
<7.9 E-14 <7.4 E-14 5.
Licensee _ Radioactive Material and Radwaste S_h_ipments. The following shipment was made:
On Monday, December 1,1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
Major Activities 1
Reactor _D_e_ cay Heat Cooling. The loss of Decay Heat to Ambient Test
(_ transfer of reactor decay heat to the reactor building ambient) is
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continuing. A decrease in key plant temperatures is noted since the start of the test on November 6,1980. Short period review of thermocouple data indicated an apparent decrease of approximately 60F for the average value of the incore thermocouples (1400F to 1340F) and the hottest loop hot leg teverature decreased approximately 60F (1380F to 1320F).
AP 4
3 The licensee will be submitting a proposal to the t;RC to justify the shutdown of the secondary plant for long term layup based on test data and this includes finalizing the special operating (test) procedure to a formal operating procedure.
2.
Reactor B_uildin_g Purge / Entry.
The fifth entry into the Unit 2 reactor building is scheduled for Thursday, December 11, 1980. A pre-entry purge was conducted on Thursday, December 4,1980. An estimated six curies of Kr-85 was released during this period. A second purge is scheduled to commence Tuesday, December 9,1980.
This purge will continue through the entry.
The objective of the second purge is to minimize Kr-85 concentrations during operations inside the reactor building.
The planned tasks inside the reactor building include replacement of the neutron source range preamplifier, decontamination experiments, and additional radiation mapping. The decontamination experiments are designed to test the effectiveness of various decontamination solutions. A detailed radiation map will be made on the 305' eleva:1on and a three man team will climb into the refueling pool (presently dry) to take radiation readings in the vicinity of the reactor head. One of the entrants will climb a vertical ladder to the polar crane to assess the condition of the crane.
3.
Co_ntaminatior, of Buildi_ng Expansio_n Joints.
During a radiological survey of the 281' elevation of the Unit'7 auxiliary building on flovember 27, 1980, contamination was found in an expansion joint.
The expansion joint lies between the service building on one side and the auxiliary building and the air intake tunnel on the other side.
Further licensee investigations revealed contamination in a second expansion joint which is contigucus to the first and which circles the reactor building. The expansion joints appear to be more highly contaminated towards the seal injection room which is adjacent to the reactor building and through which the second expansion joint runs. The seal injection room is currently inaccessable because of high radiation levels as a result of previous reactor coolant system leakage. The contamination has been identified as including CS-134. CS-137, Ru-106, Sb-125, Ce-144; and Sr-90. Water samples taken from the expansion joint by the licensee, showed cesium activity of 0.85 - 1.7 uCi/ml.
The licensee has implemented a plan to determine the source and the extent of the contamination.
The on site flRC staff will continue to closely monitor the licensee's actions in this area and licensee's plan.
The plan includes taking core samples of the expansion joints and excavating to monitor the outside edges of the expansion joints.
4 4.
Lono Term Syent Resin Storage Facility During this reportinq pari'6d too licensee received the'7nWysis results C ^
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' tract' laboratory on a water sample from the sump used to collet - n a i ne a-for the Long Term Spent Resin Storage Facilit.y (Module A and i>;
Gamma spectroscopic analyses indicated trace amounts (1.2 x 10-8 uCi/ml) of Cs-137.
Tritium analysis indicated 3 x 10-5 uCi/ml.
The licensee strongly suspects that this activity is due to rain water inleakage picking up known liner loose surface contamination and tritium vapor offcassing through liner fittings.
Module A has been in use as a repository for EPICOR-I and EPICOR-II spent resins since early 1980.
The module has 60 cells.
Each cell can accommodate one 6' x 6' (nominal external dimensions) liner or two 4' x 4' liners.
Presently the A module contains approximately 50 liners.
The B module is strucurally complete but is empty at the present time.
Water drains are provided at the bottom of each storage cell ine drains from both the A and B modules flow to a common sump.
Collected sump water is being stored onsite for processing and onsite storage flRC review of the licensee's surveillance program in this area continues.
fleet i_ng At te_nd_ed On Friday, December 5,1980 L. Barrett attended a meeting with the Atomic Industrial Forum Working Comittee on THI-2 Recovery, to discuss the NRC's site office role in cleanup operations of Tf1I-2.
Fu_ture Meetings 1.
On Thursday, December 11, 1980, L. Barrett and R. Bellamy will attend a public briefing in Harrisburg sponsored by the Department of Environmental Resources on the status of decontamination at Three Mile Island. Representatives from General Public Utilities (GPU) and the U.S. Environmental Protection Agency will also be participating in the presentation.
2.
On Friday, December 12, 1980, L. Barrett and R. Bellamy will attend a meeting in Parsippany, New Jersey, with GPU and Met-Ed to discuss proprietary information concerning EPICOR-II radwaste system.
.