ML20052C571
| ML20052C571 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/26/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-024, CON-NRC-TMI-82-24 NUDOCS 8205050184 | |
| Download: ML20052C571 (9) | |
Text
DISTRIBUTION TMIPO HQ r/f TMI SITE r/f N DAL FILE NRC PDR LOCAL PDR April 26,1982 Site Operations File NRC/THI-82-024 90-HEMORANDUM FOR:
Harold R. Denton, Director cs Office of Nuclear Reactor Regulation p,
4 Bernard'J.' Snyder, Program Director 3
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TMI Program Office v
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FRON:
Lake H.'Barrett, Deputy Program Director 4
THI Program Office
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SUBJECT:
NRC THI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report.for the period of April 17,1982 to.
April 24,1982 Major items included in this report are:
Liquid Effluents NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments Submerged Demineralizer System Status EPICOR II Reactor Coolant System Water Processing Reactor Building Entries Groundwater Monitoring Status Public Heatings k
!s**."'Psisaw W ett Lake H. Barrett Deputy Program Director TMI Program Office Enclosure : As stated
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PDR ADOCK 05000320 R
PDR OFFICIAL RECORD COPY unce. -.....-__
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s Harold R. Denton April 26,1982 Bernard J. Snyder cc w/ encl:
ED0 OGC Office Directors Coimaissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS THI Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI.
DRPI Chief, RI Public Affairs, RI State Liaison, RI
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT '
April 18,1982 - April 26,1982 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 systems.
Long term cooling "B" (once through steam generator-B).
RCS Pressure Control Mode: Standby pressure control (SPC) system.
Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.
Decay heat remoal (DHR) system.
f Major Parameters (as of 0500, April 23,1982) (approximate values)
Average Incore Thermocouples: 103*F Ma*ximum Incore Thermocouple:
130*F RCS Loop Temperatures:
'A B
Hot Leg 97 F 100*F
~
Cold ' Leg (1) 84
- F 85 F (2) 89*F 90*F W
RCS Pressure: 96 psig Reactor Building:
Temperature :
69*F
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Water level:
Elevation 283.2 ft. (0.5 ft.. from floor)
Pressure:
.3 psig Airborne Radionuclide Concentrations :
l 2.6 x 10-5 uCi/cc Kr85 f
(sample taken 4/20/82)
I
<1.8 x 10-8 uCi/cc H3 (sample taken 4/20/82) 1.04 x 10-9 uCi/cc particulate (sample taken 4/21/82) j 1.
Effluent and Environmental (Radiological) Information l.
Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and l
in accordarice with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period April 16, 1982, through April 22, 1982, the effluents contained no detectable radioactivity at the discharge point and o
individual effluent sources, which originated within Unit 2, contained no' detectable radioactivity.
l 1
- 2'.
2.
Environmental Protection Agency (EPA) Environmental Data Results 'from EPA monitoring of the environment around the TMI site were as follows:
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following results :
Location liarch 12,1982 - April 2,1982 (pCi/m3)
Goldsboro 23 Observation Center 30 Middletown 22 Yorkhaven 30 All of the above levels of Kr-85' are considered to be background l evel s.
Results.for the samples taken April 2,1982 through April 16,1982, will be reported 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 April 14, 1982 through April 22, 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:
I-1 31 Cs-137 Sampl e Period (uCi/cc)
(uCi/cc)
H P-316 April 14,1982 - April 21,1982
<6.6 E-14: <6.6 E-14 4.
Licensee Radioactive Material and Radwaste Shipments On Tuesday, April 20, 1982, 38 drums of Unit 1 compacted trash (Low Specific Activity, LSA) were shipped to Chem Nuclear Systems, Inc., Barnwell, South Carolina.
On Friday, April 23, 1982, four containers of samples taken in Unit 1 (various locations) were shipped to the Babcock and Wilcox Research Center, Lynchburg, Virginia.
o Major Activities _
l.
Submerged Demineral_izer System (SDS).
The SDS is shutdown for minor maintenance.
During the next reporting period the 50S is scheduled to commence processing approximately 30,000 gallons of reactor coolant bleed tank water.
2.
EPICOR II.
The EPICOR II system is shutdown because of lack of water to be processed.
3.
Reactor Coolant System (RCS) Water Processinq.
Engineering and construction efforts by the licensee are continuing in preparation for RCS processing which is presently scheduled to commence in May 1982. Actual RCS processing may be postponed while the SDS processes the remaining water (approxim.ately 40,000 gallons) in the reactor building. Approximately 80% of the procedures needed to commente RCS water processing has been approved by the NRC/TMIPO site office.
The NRC/TMIP0 site office, with support from the Chemical Engineering Branch, NRR, is' reviewing the licensee's request to revise the Recovery Operations Plan to incorporate changes to accomodate RCS processing.
3.
Reactor Building Entries.
During the reactor building (RB) entry
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on Thursday, April 22, 1982, a suction hose was installed into the incore instrumentation trough on the 282 ft. elevation floor.
The trough extends below the general floor level and was chosen as the optimum suction location to remove the remaining water from the RB basement. The pump installation should be completed during the next RB entry. The pump discharge will be connected to the existing transfer hose between the floating sump pump and the submerged demineralizer system. In addition to the suction hose installation, technicians removed the reactor building dome radiation monitor, H PR-214.
The dome monitor will be shipped to an offsite laboYatory for analysis.
The table below is a summary of RB man-hours and man-rem for accident recov'ery entries.
The summary is subdivided into pre-gross decontamina-tion experiment entries (entries 1-16) and the gross decon.tamination experiment entries (entries 17-56).
Entries 1 through 16 Entries 17 through 56 7/23/80 to 9/24/81 10/27/81 to 3/31/82 Total Man-hours 199 507 Total Man-rem 63 115
-4.
A 14 month look ahead at major milestones in the RB recovery schedule includes the following events:
June 1982, insertion of the axial power shaping rods (APSR).
July 1982, closed circuit television inspection of the upper reactor vessel internals Summer 1983, reactor vessel head removal (funding permitting).
A prerequisite for the television inspection is the requirement to depressurize the reactor coolant system and to lowe.- the RCS water level below the top of the control rod drive mechanisms (CRDM).
Preparations for RCS processing through the submerged demineralizer system (SDS) are progressing in parallel with the identified milestones.
However, under the current concept, RCS processing will be suspended whenever the primary system is depressurized.
It is planned to refill and repressurize (50 psig) the primary system after ths television inspection of the reactor internals.
Insertion of the APSR's is the first event on the milestone schedule.
There are eight APSR's' in the TMI-2 core.
The APSR's are designed to control core power distribution during reactor operations and normally these rods are not inserted during reactor shutdowns.
Following the reactor' shutdown on March 28, 1979, the APSR's remained in their last position, withdrawn approximately 35 inches (25% of their full travel). The normal rod uncoupling procedure (prerequisite for head removal) requires the rods to be fully inserted.
In conjunction with the APSR insertion to support reactor disassembly, a testing program has been devised to monitor the APSR movement with externally mounted sonic detectors, and electric power requirenents to the APSR drive motors will be measured in an attempt to gain additional information about the condition of the core.
The next RB entry is scheduled for Wednesday, April 28, 1982 In addition to completing the installation of the sump pump, technicians sill test the operation of the RB fire detection systems and maintenance workers will service the airlock door mechanisms.
5 Groundwater Monitoring Program.
The licensee is conducting a program of increased surveillance frequency of the onsite test bo ri ngs.
One of the objectives of the licensee program is' to identify the source of tritium in test borings 2, 3,16, and 17. is a graph of tritium activity in the three test borings with the highest concentrations.
A sample taken on March 23,1982, from test boring 17 had the highest tritium concentration (1,100,000 pCi/L) of any sample taken during the ground water monitoring program.
On April 8,1982, the concentration'-
in test bor'ing 17 decreased to 610,000 pCi/L.
Since January 1982, groundwater near the borated water storage tank (BWST) has apparently leaked into underground structur.es in the vicinity of the BWST (Air Intake Tunnel and BWST Pipe Chase).
As part of the present monitoring program, a more detailed characterization
4.
of the isotopic makeup of the contaminated water is the air intake tunnel and the borated water storage tank (BWST) was conducted.
The additional analytical.results indicated minute concentrations (s6 x 10-8 uCi/ml) of Sb-125 in the BWST pipe chase and the air
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intake tunnel.
A more sensitive analysis of water from the BWST indicated an Sb-125 concentration of 6.5 E-6 uCi/cc. Preliminary evaluation of the analytical results indicates that the Sb-125 to tritium ratios in the air intake tunnel are consistant with those in the BWST.
This constant ratio strongly indicates that the source of radioactivity in the groundwater is from the BWST.
Although difficult to quantify. it appears that the leakage of BWST water
=s approximately 3,000 gallons.
4 O
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Past Meetings On April 22, 1982, the Three Mi,le Island Advisory Panel held a meeting in Harrisburg, Various representatives from GPUN, NRC, DOE and EPA gate status reports on 1) funding proposals in Congress, 2) the recent reactor building decontamination experiment, 3) accident water processing,
- 4) upcoming reactor coolant system processing (which is scheduled to begin in fiay), and 5) DOE's agreement to remove purification system demineralizer vessels and filters.
Extensive discussion took place on the subject of tritium, which has been showing up in groundwater adjacent to TMI-2 buildings as a result of a leak in the area of the Borated Water Storage Tank last January.
The relative levels of radioactivity in the area have been minimal (approximately one curie of tritium).
However, the amount of water leakage, originally thought to be 50-60 gallons, has been determined to be closer to 2,000-3,000 gallons.
Bill Kirk (EPA) reported undetectable levels of radionuclides in five EPA monitored wells just off the island.
Chairman Minnich also offered three proposals which were passed by the Panel :
1.
Send a letter to the legislative leadership of the Commonwealth of Pennsylvania endorsing that the $5 million for the cleanup proposed by Governor Thornburgh in FY 83 budget, remain in tact through the budget process.
2.
Send a similar letter to Congress reinforcing the need and' the Panel's support of $27 million for TM1 cleanup proposed for FY 83 DOE budget.
3.
Send a letter to the Pennsylvania PUC suggesting the $23 million currently slated for amortization of TMI-2 capital costs pursuant to deferred energy rate charge, be diverted to the cleanup.
Monies slated for rate reduction relief would remain in tact.
Chairman Minnich felt such a move would be a positive sign to Congress of Pennsylvania's commitment to the cleanup.
Future Meetings 1.
On Tuesday, April 27, 1982, Lake Barrett will meet with a group of Middletown mothers to discuss issues and concerns related to the cleanup program at TMI Unit 2, the status of Unit 1, and the financial status of GPU Nuclear.
2.
On Wednesday, April 28, 1982, Harold Denton, Bernard Snyder and Lake Barrett will testify in Washington, DC, before Senator Alan K. Simpsons' Senate Subcommittee on Nuclear Regulation, l
J Environment and Public Works Committee.
TRITitJr* CONCENTDATIONS 1788280 S
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