ML19255C323
| ML19255C323 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/19/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-044, CON-NRC-TMI-82-44 NUDOCS 8208130462 | |
| Download: ML19255C323 (8) | |
Text
DIST71BUTION TMIPO HQ r/f TMI SITE r/f W ENTRAL FILE NRC PDR LOCAL PDR Site Operations July 19, 1932 File LRC/THI-82-044 f;D10PJJiDUM FOR:
Harold R. Denton, Director Office of i:uclear Reactor Regulatico Bernard J. Snyder, Program Director TMI Program Office FROM:
Lake 11. Carrett, Deputy Program Director THI Program Office
SUBJECT:
URC THI PROGRIJi 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of July 11 - 17, 1982. Itajor itens included in this report are:
Liquid Effluents EPA and liRC Environmental Data Radioactive liaterial and Rcdwaste Shipments Submerged Denineralizer System Status EPICOR II Recctor Coolant System Feed and Bleed Reactor Building Entries (RCS Vcnting/Depressurization)
EPICOR II Prefilter Inerting Tool Status LWR Occupational Dose Data
%imal signed by T*e E Berrett
'j Lake 11. Barrett Deputy Program Director
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liRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT July 11, 1982 - July 17, 1982 Plant Status Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS) to reactor building ambient.*
Available Core Cooling Modes: Mini Decay Heat Removal (MDHR) system.*
RCS Pressure Control Mode:
RCS is vented to the reactor building.*
Major Parameters (as of 0500, July 16, 1982) (approximate values)
Average Incore Thermocouples:
102 F Maximum Incore Thermocouple:
124 F RCS Loop Temperatures:
A B
Hot Leg 98 F 101 F Cold Leg (1) 9'7 F 87 F
~
(2) 99 F 89*F Pressure:
The reactor cool' ant system is vented to the reactor building.
Reactor Building:
Temperature:
85*F Pressure:
-0.17 psig Airborne Radionuclide Concentrations:
5.5 E-7 uCi/cc H (sample taken 7/15/82) 85 9.0 E-6 uCi/cc Kr (sample taken 7/7/82) 5.0 E-10 Ci/cc particulates (sample taken 7/15/82)
- See Mejor Activities Section - Reactor Building Entries (RCS Venting /Depressurization) 1.
Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with f4RC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period July 9, 1982, through July 15, 1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained small amounts of radioactivity.
Calculations indicate that less than two-millionths (0.000002) of a curie of cesium end less than three hundred-thousandths (0.00003) of a curie of tritium were discharged.
. 2.
Environmental Protection Agonty (EPA) Environmental Data The EPA Middletown Office has not received the environmental Kr-85 analytical results for the samples which were taken June 12, 1982, through July 9, 1982, from the EPA's Countirg 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 July 7, 1982, through July 15, 1982.
3.
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 Samole Period (uti/cc)
(uCi/cc)
HP-327 July 7, 1982 - July 14, 1982
<6.5 E-14
<6.5 E-14 4.
Licensee Radioactive Material and Radwaste Shipment On Thursday, July 15, 1982, three (3) drums containing Babcock and Wilcox (B&W) tools used for work on the Unit 1 Once Through Steam Generator, were shipped to the B&W Research Center, Lynchburg, Virginia.
Major Activities 1.
Submerged Demineralizer System (SDSl.
The SDS is currently shutdown while RCS drain-down for the " Quick Look" continues.
SDS processing will continue after a 50,000 gallon batch of RCS water is collected in Reactor Coolant Bleed Tank "C".
2.
EPICOR II.
The EPICOR 11 system is currently shutdown on a standby status.
3.
Reactor Coolant System (RCS) Feed and Bleed.
The fifth feed and bleed cycle of RCS water began on July 10, 1982 and was completed on July 11, 1982. This batch consisted of approximately 30,000 gallons.
To date, 230,000 gallons of RCS water have been bled from the RCS. Two hundred thousand gallons have been processed through SDS (four batches) and returned to the RCS.
4.
Peactor Building Entries.
During the week of July 11, 1982, three reactor buliding entries were made to support the closed circuit television inspection nf the reactor vessel internals.
The closed
. circuit television inspection is scheduled for Wednesday, July 21, 1982.
On Monday, July 19, 1982', a centrally located control rod drive mechanism will be disassembled, and an attempt will be made to uncouple the leadscrew from the control rod.
If the uncoupling is successful, the leadscrew will be removed to make a 11/2 inch diameter opening for the television canera. The uncoupling procedure includes the flexibility to disassemble adjacent control rod drives if the initial uncoupling is unsuccessful.
Assuming a leadscrew is uncoupled and removed, the camera will be used to inspect and video tape the interior of the control rod guide tube and the tops of at least five fuel assemb" es on Wednesday, July 21, 1982.
In preparation for the television inspection, the reactor coolant system was vented and depressurized. During the reactor building entries this week, operators opened vents on the reactor coolant system high points (hot legs, pressurizer, and reactor vessel) to vent trapped gas from the primary system to the reactor building.
Nitrogen overpressure was valved to the high point cants and the primary system was drained via the normal letdown system, to a level midway down the control rod drive mechanism.
At this level, the fuel assemblies are still 20 feet ur. der cooling water.
Decay heat removal from the core will be affected by the change in the primary system water level. The heat transfer path from the~ core to the steam generators via the hot legs was eliminated when the water was drained from the top sectjons of the 36 inch diameter hot leg pipes.
It is anticipated that core temperatures will increase slightly due to the reduced heat transfer capability. The present core average temperature is.102'F.
Calculations indicate that the core is producing 45 kilowatts of decey heat (equivalent to approximately 40 home toasters).
Contingency plans for maintaining core temperatures below boiling include refilling the primary system and using the mini decay heat removal system.
As of Monday morning, July 19, 1982, the average core temperature increased to 106 F.
Gas and water samples were taken from the reactor head vent (vent on top of a control rod drive mechanism).
Preliminary results indicate that the turbidity of the water sample was 200 NTU*.
Previous primary water samples (taken frcm.the let down sample line) indicated a turbidity of approximately 10 hTU.
If the 200 KTV sample is representative of the turbidity above the fuel assemblies, the success of the television inspection may be impaired. The analysis of the water sample indicated that the baron concentration was 3820 ppm.
The concentration of gross alpha emitters was 8.9 x 10" uti/cc (alpga emitters in samples from the letdown systems were typically in the 10~ uCi/cc range).
The gas sample from the control rod drive mechanism indicated that hydrogen was the predominant gas (63%).
The krypton 25 concentration was 1.1 uti/cc.
During the venting, the gases were released to the reactor building and eventually to the environment.
Effluent monitors indicated that less than three curies of krypton were released.
Following the reactor vessel inspection, the licensee will evaluate the primary system parameters (temperature stability, water inventory, etc.)
to determine whether to refill and repressurize the system.
'Nepheiometric Turbidity Units - An empirical measure of turbidity based on measurement of the light-scattering characteristics (Tyndall effect) of the particulate matter in the sample.
EPICOR 11 Prefilter Inerting Tool Status. The first sampling and 5.
inerting of an EPICOR 11 prefilter (PF) is scheduled to begin the week of As previously highlighted in the June 7, 1982 Weekly July 26, 1982.
Status report, a remotely operated inerting tool was functionally tested in preparation for shipment of the 49 EPICOR II PF's which are currently stored at the TMI site.
This special TV monitored inerting tool, which was provided by the DOE, will be used in conjunction with a 30 ton concrete blockhouse to remotely sample each individual EPICOR liner.
(See Attachment 1 for EPICOR PF inerting configuration.)
In the actual EPICOR PF shipment preparations, the licensee plans to perform all inerting operations at the Solid Waste Storage Facility (SWSF). The sequence of operations will include:
(1) removal of the existing shield block, (2) installation of the blockhouse and inerting tool, (3) inerting the SWSF cell cavity with nitrogen, (4) lower the vent tool on the liner and leak testing the Unit, (5) remove the PF vent plug and sample the gas environment, (6) purge and inert the PF with nitrogen, and (7) reinstall the vent plug and remove equipment in preparation for Combustible gas generation rates will be monitored on shipment.
selectively high curie leaded liners over a 14-day period to demonstrate that gas composition in the vessel will be non-flamable over twice the expected shipment period.
The first EPICOR II PF shipment is scheduled for August 10, 1982.
LWR Occupational Dose Data (Preliminary).
Bned on reports submitted to 6.
tne NRC in accorcance with 10 CFR Part 20.407, from 70 light-water-cooled nuclear reactors, the Radiological Assessment Branch, Division of System Integration, KRR, has prepared a preliminary compilation and analysis of occupational radiation doses for 1981.
The average collective dose, per reactor, was 779 person-rems * (which was slightly lower than the 791 person-rems per reactor reported in 1980).
The average collective cose, per preasurized water reactor (PWR) was 656 person-rems (boiling water reactors had an average approximately 50%
higher). The total dose for TMI (Units I and 2) was 376 person-rems, which is well below the national average.
Attachment II shows the total doses reported for the years 1981, 1980, and 1979 for a selection of PWR sites and includes TMI. The most frecuent reasons given by licensees for the dose decreases, for 1981 as compared to 1980, was that their plants did not have major refueling or maintenance outages.
For
- The average dose per person multiplied by the number of persons.
example, one thousand people, each exposed to one millirem (1/1000 rem) would have a collective dose of one person-rem.
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