ML19339B246
| ML19339B246 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/20/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-141 NUDOCS 8011060580 | |
| Download: ML19339B246 (3) | |
Text
_.
' UNITED STATES NUCLEAR REGULATORY COMMisslON
,p h,
WASHINGTON, D. C. 20555 i
"t s....,/
October 20, 1980 g
NRC/TMI-80-141 MEMORANDUM FOR:
H. R. Denton, Director, Office of Nuclear Reactor Regulation B. 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 week of October 12 - 18, 1980.
hI cedk 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 HEW EPA R0&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser
- TMI Program Office Staff 8011060$ N
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of October 12 - 18, 1980 Plant Status Core Cooling Mode:. Cyclic natural circulation in the "A reactor coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient.
Available Core Cooling Modes: 0TSG "B" to the main condenser; lone-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: Makeup system in> conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0500, October 17,1980)-(approximate values)
Average Incore Thermocouples:
142 F Maximum Incore Thermocouple:
180 F RCS Loop Temperatures:
A B
Hot Leg 135 F 139 F Cold Leg (1) 78 F 95 F (2) 78 F 91 F RCS Pressure:
95 psig (DVM) 85 psig (Heise)
Pressurize Temperature:
82 F Reactor Building:
Temperature:
75 F Water level:
Elevation 290.5 ft. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.1 psig (i Concentrction: '8.2 x 10 jeise)
JCi/cc (Kr-85) (sample take.o10/'6/80)
Environmental & Effluent Information 1.
Liquid effluents from THI-l released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
i 2.
No liquid effluents were discharged from TMI-2.
w y
y w
-+w yi a
g
2 3.
EPA Environmental Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
The EPA measured Kr-85 concentrations (pCi/m3) at several environmental monitoring stations and reported the following-results:
Location October 3 - 10, 1980 (pC1/md)
Bainbridge 18 Goldsboro 18 Observation Center 26 Middletown 33 Hill Island
, Monitor Removed All of the above levels of krypton-85 are considered to be background levels.
No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and gama rate networks during the period from October 8 thenugh October 16, 1980.
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-237 October 8 - October 15, 1980
<7.4 E-14 <7.4 E-14 5.
Licensee __ Radio _a_ctive Material and Radwaste Shipments. The' following shipments were made:
On Monoay, October 13, 1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W) Lynchburg, Virginia.
On Tuesday, October 14, 1980, 98 drums of compacted and 6 boxes of nnn-compacted Unit 2 LSA waste were shipped to Nuclear Engineering Company (NECO) Richland, Washington.
On Wednesday, October 15, 1980, 52 drums of compacted and 12 boxes of non-compacted Unit 2 LSA waste were shipped to NEC0, Richland, Washington.
On Thursday, October 16, 1980, 12 boxes of non-compacted Unit 2 LSA waste were shipped to NEC0, Richland, Washington.
3 Cn Friday, October 17, 1980, 10 boxes of Unit 2 non-compacted LSA waste were shipped to NEC0, Richland, tlashington.
On Friday, October 17, 1980, three Unit 1 sample:. were sent to Teledyne Isotopes Westwood, New Jersey.
The samples included a 1000 ml waste evaporator condensate storage tank (WECST) montly composite, a 1000 ml WECST '.'B" sample, and a 200 ml Decay Heat System "A" sample.
Major Activities _
l.
Mini Decay Heat (MDH) System.
The MDH system remains in an operational status pending final verification of the inline filter changeout methodology and issuance of technical specifications.
2.
Reactor Bu_ilding Entry and purge.
The third entry into the Unit 2 reactor building was compTeted at 11:54 a.m. on Thursday, October 16, 1980.
The entry team of three health physics technicians and two maintenance men remained in the reactor building for up to 87 minutes. The maximum exposure, based on dosimeter readings, was less than 500 mr.
A preamplifier for an inoperable neutron source range monitor was removed and the two associated neutron sensors ware jumpered to wires which terminate outside of the reactor bu'lding.
The preamplifier will be inspected ano repaired if necessary.
T1e two neutron sensors will be tested from outside of the reat tor building.
Tentative tasks for the next entry, which is scheduled in November, will include reassembly of the preamplifier and the neutron sensor connections.
The maintenance personnel also reset tripped differential pressure interlocks on the equipment hatch perennel airlock.
The interlocks tripped and failed to reset when the ditferential pressure on either side of the airlock doors exceeded approximately 0.5 psid.
An inoperable noise monitor preamplifier was iamnved for offsite analysis. Photographs, swipes and area radiation surveys were also made during the entry. The duration of the entry was extended past the scheduled 60 minutes to complete the assigned tasks which required more time than anticipated. The entry team was not exhausted physically and did not exceed.the precalculated dose of 500 mr.
The entry team's physical comfort was improved by a decrease in protective clothing requirements and by cooler temperatures in the reactor building.
3.
Reactor Heat Removal to Ambient Test. As described in last week's report, the licensee proposed to discontinue steaming the "A Once Through Steam Generator (OTSG) and allow reactor decay heat to be removed by heat transfer to reactor building environment (ambient).
The proposal was finalized. in a _ test procedure which was reviewed by the onsite NRC staff. The procedure was sent back to the licensee for resolution of comments. No start date for this test was finalized.
4 4.
Spent Resin _ Storage Status. Fiftytwo of the sixty spent resin storage cells in the "A" longterm waste storage module hold spent resin liners. 'Six-of the occupied cells contain stacked 4' x 4' liners (twa.er storage cell). The "B" longterm waste storage 4
module is presently empty with a holding capacity. equivalent to Module "A".
The licensee has continued to relocate liners from the temporary interim storage facility. At present, twenty of the twenty-eight cells hold liners. One liner has.been transferred to the "A" long-term waste storage module since the previous update of September 8, 1980.
Future Meetings 1.
On Monday, October 20, 1980, B. Snyder, T. Elsasser, W. Kirk (EPA) and T. Gerusky (DER) will meet with PANE (people against nuclear energy) to discuss contents of the draft Programmatic Environmental Impact Statement (PEIS).
2.
On Thursday, October 23, 1980, T. Elsasser, W. Kirk (EPA) and T. Gerusky. (DER) will meet with the PA-Medical Society to discuss the contents of the draft PEIS.
9 e