ML19351D900
| ML19351D900 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/10/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-147 NUDOCS 8011200351 | |
| Download: ML19351D900 (6) | |
Text
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UNITED STATES
[ j* :.s t 'i NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 a
f' November 10, 1980 NRC/TMI-80-147 2
MEMORANDUM FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation 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 Enclored is the status report for the week of November 2 - 8, 1980.
b $0 John T. Collins Deputy Program Director TMI Program Office y
Enclosure:
As stated
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ED0 0GC wj Office Directors
- D Ml Co7nissioner's Technical Assistants NRR Division Directors N
f5 NRR A/D's Regional Directors IE Division Directors XOOS X0MA HEW EPA RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I c
Public Affairs, Region I T. Elsasser TMI Program Office Staff sonacc%\\
1 NRC TMIlROGRAM OFFICE WEEKLY STATUS REPORT f
Week of November 2 - 8,'1980 Plant Status Core Cooling Mode:
Cyclic natural circulatiLn in the "A" and "B" reactor coolant system (RCS) loops with heat transfer to i
reactor building ambient (air and sump water).
Available Core Cooling Modes: 0TSG "A" or "B" to the main condenser; 3
long-term cooling "B" (OTSG-B); dacay heat removal, i
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 rei:irculation back l
to the borated water stor:ge tank (BWST) to provide control of pressure.
Major Parameters (As of 0500, Nmember 7,1980) (approximate values)
Average In'. ore Thermocouples:
140 F i
Maximum '.ncore Thermocouple:
177*F RCS Loop Temperatures:
A B
Hot Leg 135 F 138'F ColdLeg(1) 76 F 76*F j
(2) 76 F 76 F 4
l RCS Pressure: 90psig(DVM) i 80 psig (Heise)
~
Pressurizer Temperature:
78 F Reactor Building:
Temperature:
70'F Water level:
Elevation 290.5.ft. (8.0 ft.. from floor) via penetration 401 ~ manometer Pressure:
-0.2 psig (heise) l Concentration:
1.6 x 10-4 uti/cc (Kr-85) (sample taken 11/5/80)
Environmental & Effluent Information 1.
Liquid effluents from TMI-l released to the Susquehanna River, i
after processing, were within the limits specified in Technical l
Specifications.
.2.
No liquid effluents were discharged from TMI-2.
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2 3.
EPA Environmental Data.
Results from EPA monitoring of the environment eround the TM1 site were as follows:
The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m3) at several environmental monitoring' stations and reported the following results:
L,0ca tion _
October 24 - 31, 1980 (pCi/m3)
I Bainbridge 25 Goldsboro 19 Observation Center 20 Middletown 21 All of the above levels of Kr-85 are considered to be back-ground 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 29 through November 6, 1980.
4.
NRC_ Envir_onmental Data.
Results from NRC monitoring of the environment around the TMI site were as fullows:
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)
. 8.1 E-14 <8.1 E-14 HP-240 October 29 - November 5, 1980 5.
Licensee Radio _ active Material _ and Radwaste Shipments. The following shipments were made:
On Monday, November 3, 1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W) Lynchburg, Virginia.
On Tuesday, November 4, 1980, a metal box containing solidification equipment parts (LSA) was shipped to the Larken
, Laboratory of the Dow Chemical Company, Midland, Michigan.
l On Friday, November 7, 1980, 32 drums containing Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries, Utica, New York.
3 l
Major Activities 1.
Mini O_ecay Heat (MDH) System.
The MDH system remains in an operational status pending turnover to tre operations group and issuance of technical specifications.
2.
Reactor Building Purge and Entry.
A purge of the reactor building atmosphere was completed on Friday, November 7,1980.
Approximately 10-15 curies (Kr-85) were released.
The next entry into the building is scheduled for November 13, 1980, in which another purge of the building atmosphere is anticipated to start on November 12, 1980.
Task items to be completed have not been finalized but plans include:
reinstallation of a source range preamplifier; continued radiological and photographic surveillance; decontamination assessment; and movement of the fuel handling bridge to permit access to the fuel transfer cavity on future entries.
3.
Reactor _ Decay Heat Cooling.
At 9:00 a.m., on November 6, 1980, the licensee commenced the Loss to Ambient Test (Loss of Reactor Decay Heat to Reactor Building Ambient Test).
This test was initiated to demonstrate that sufficient heat transfer occurs from the reactor coolant system to the reactor building ambient (air and sump water) to adequately cool the reactor core.
This test reflects a change in the past reactor coolant mode since the March 28 accident.
Prior to the test steaming occurred under vacuum in the "A" once through steam generator (OTSG) with the "B" 0TSG isolated. The test condition now requires both OTSG's to be isolated.
The test is cenducted in accordance with a procedure (with associated safety evaluation) approved by the onsite NRC staff.
The test will be terminated if:
The average incore thermocouple temperature exceeds 150 F or increases more than 10 F in one hour.
Any incore thermocouples and hot leg termperature exceeds 200 F.
The hot leg temperature for either OTSG increases more than 10 F in one hour.
Equipment necessary to reestablish steaming on the "A" 0TSG will remain operable throughout the test.
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The test is planned to last 15 days. At that time the licensee will evaluate gathered data and recommend to the onsite NRC staff on whether or not to continue the test.
No appreciable change in reactor core / cooling system steady state (equilibrium) temperatures were noticed si.:ce the commencement of the test.
Onsite staff review of this area continues.
4.
NRC TMI_ Program Office Dmty Program _ DirecLtor Position.
On Thursday, November 6,1980, it was announced that Lake H. Barrett, Nuclear Reactor Regulation, was appointed Deputy Program Director of the NRC TMI Program Office.
Mr. Bar ett will leave his present position as Section Leader for the Radiological Section of Operating Reactors Assessment Branch, NRR, and is expected to be on site late November 1980.
l 1
5 Meetings Held On Thursday, November 6, 1980, J. Collins was the guest speaker for the Middletown Rotary Club.
Several people raised concerns about the possibility of a or more delay before TMI-could i
be restarted and its affect, va their current electricity bills.
Also of interest, was the current decontamination efforts presently going on at TMI-2.
Future Meetings 1.
On Monday, November 10, 1980, V. Gilinsky, B. Snyder, J. Collins, F. Congel, T. Elsasser and M. Bills (EPA) will meet with local officials, citizens and press at the Forum in Harrisburg to discuss the contents of the draft Programmatic Environmental Impact Statement (PEIS).
E.
On Wednesday, November 12, 1980, J. Collins will attend a luncheon meeting with the Hummelstown Rotary Club to discuss various aspects of the TMI-2 cleanup program.
3.
On Wednesday, November 12, 1980, the NRC's newly established Advisory Panel for the Decontamination of Three Mile Island, Unit 2, will hold its first meeting at the Forum in Harrisburg, PA.
The 12-member panel will meet to discuss its role ar an advisory body to the Commission and the scope of its activities.
In addition, it will be briefed by the NRC staff on the draft PEIS on the Unit 2 cleanup effort.
4.
On Thursday, November 13, 1980, J. Collins will meet with the Lancaster Jcycee's to discuss current and future activities on the cleanua operation of the Unit 2 reactor building at TMI.
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