ML20002C297
| ML20002C297 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/22/1980 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-153 NUDOCS 8101090972 | |
| Download: ML20002C297 (4) | |
Text
- pp.a ae%q'o UNITED STATES E'
',i NUCLEAR REGULATORY COMMISSION
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E W ASHINGTO N, D. C. 20555 j
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,o December 22, 1980 A
NRC/TMI-80-153 2
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$5 3
met 10RANDUM FOR:
Harold R. Denton, Director,
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.i Office of Nuclear Reactor Regulation
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Bernard J. Snyder, Program Director, l
TMI Program Office FROM:
Lake H. Barrett, Acting Program Director, TMI Program Office
SUBJECT:
flRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of December 14-20, 1980.
Due to the holiday period, the next report will cover the two week period December 21, 1980, through January 3,1981.
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- v Lake H Barrett Acting Deputy Program Director Tf1I Program Office
Enclosure:
As stated cc:
ED0 OGC Office Directors 4
Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors X005 X0MA Ti1I Program Office Staff (15)
HEW j
EPA RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser 187 0109 0 91 a. p
l NRC Tf11 PROGP.AM 0FFICE WEEKLY STATUS REPORT 1
i Week of December 14-20, 1980
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Plant Status i
Core Cooling Mode: Cyclic natural circulation in the "A" reactor coolant i
system (RCS) loop via tne "A" once through steam generator (OTSG), steaming to the main condenser, j
and RCS loop-A and B cyclic natural circulation to reactor building ambient.
t Available Core Cooling Modes: 0TSG "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removt.l.
j 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 l
s to the borated water storage tank (BWST) to provide I
contrcl of pressure.
Major Parameters (As of 0500, Decemver 19,1980) (approximate values) i Average Incore Themocouples:
113 F Maximum Incore Themocouple:
153 F RCS Loop Temperatures:
A B
Hot Leg 112 F 116 F i
Cold Leg (1) 86 F 82 F i
(2) 96 F 86*F l
RCS Pressure: 83 psig (DVM) i l
Pressurizer Temperature: 69 F i
Reactor Building:
Temperature: 63 F Uater level:
Elevation 290.5 ft. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.25 psig (Heise)
Concentration:
3.8 x 10-5 uCi/cc (Kr-85) (sample taken 12/17/80)
Effluent and Environmental (Radiological) Information 1.
Liquid effluents from TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requiremerts and ~ City of Lancaster Agreement dated February 27, 1980. The concentrations of radioactive materi.al in the discharged effluent during this weekly period were less l
than the Lower Limits-of Detection (LLD).
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EPA Environmental Data. Results from EPA monitoring of the environment l
around the TNI site were as follows:
3 The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:
Loc _ation December 8 - December 12, 1980 (pCi/m3)
Bainbridge 28 i
I Goldsboro 26 Observation Center 30 Middletown 19 i
All of the above levels of Kr-85 are considered to be back-I ground levels.
tio radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air j
and ganina rate networks during the period from December 10 through December 18, 1980.
3.
flRC Environmental Data. Results from f4RC monitoring of the environ-ment around the IMTsi~te were as follcws:
j The following are the f1RC air sample analytical results for the onsite continuous air sampler:
Sample Period (uCi/cc)
(uCi/cc_}_
HP-246 December 10 - December 17, 1980
<8.2 E-14 <8.2 E 14 4.
Licensee Radioactive Material and Radwaste Shipments.
The following shipments were made:
On f1onday, December 15,1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, l
Vi rginia.
On Wednesday, December 17, 1980, contaiminated cork samples from the Unit 2 auxiliary building expansion joint were shipped to Science Applications, Incorporated, (SAI), Rockville, fla ryland.
i On Thursday, December _ 18, 1980, a box containing Unit 2 i-
_ air filter and smear sample papers was mailed to Teledyne j
Isotopes, Westwood, New Jersey.
i Pn Thursday, December 18, 1980,- a box containing a Unit 1-l waste evaporator condensate sto' rage tank (WECST) monthly
(
composite sample was mailed to Teledyne Isotopes, Westwood, New Jersey.
3 Major Activities i
1.
R_eactor Decay Heat Removal.
Decay heat removal (approximately j
80 W) continues to be removed by steaming (under vacuum conditions) in the "A" Once Through Steam Generator (OTSG) and by heat transfer from reactor coolant system to reactor building ambient. Work continues on resolving staff comments on the licensee's proposal to use the loss to ambient mode as a viable means of decay heat removal.
Approval of the licensee's procedure is expected next week.
2.
Contamination of Building Expansion Joints.
Sample results of cork aojacent to the air intake tunnel show no activity above the lower i
level of detectability. This indicates that the water stop in the i
expansion joint between the " control and service building" and the
" air intake tunnel" is intact and keeping the contamination from spreading past the water stop.
The licensee is developing a plan to remove the contaminated water from the expansion joints and is continuing in their efforts to ensure the contamination is not being released to the environment.
The onsite NRC staff will continue to closely monitor the licensee's actions in this area.
l Meetings Attended 1
On Wednesday, December 17, 1980, L. Barrett, A. Fasano D. Haverkamp, and M. Shanbaky attended a meeting at NRC Region I, King of Prussia, PA.
Licensee management representatives were present to discuss the Unit 1 Health Physics Program Evaluation concerning acceptable corrective action for the evaluation findings and applicability to Unit 2.
2.
On Thursday, December 18, 1980, B. Snyder and L. Barrett attended the Tf11 Advisory Panel meeting at the William Penn fluseum in Harri sburg.
The topic of discussion was radioactive waste manage-l ment.
Presentations were given by Mr. G. Cunningham, Assistant Secretary for the Department of Energy (DOE), Mr. R. Arnold, Chief Operating Executive, General Public Utilities Nuclear Group (GPUNG),
j and representatives from Congressman Udall's staff and the ACRS.
The panel focused on the progress towards the disposal of Till radiaoctive water. The panel also expressed concern that DOE could accept TMI high level waste only for research and development (R&D) purposes and therefore store that accepted waste only and that it did not appear any organization is taking the lead in resolving any legislative hurdles for TMI waste disposal.
Concerns on delays of the cleanup efforts and financial status of GPU were also expressed.
3.
On Friday, December 19, 1980, L. Barrett, R. Bellamy and G. Kalman,
held a seminar on the Three Mile Island containment building, in Bethesda, Maryland for the NRC staff.