ML19345F720
| ML19345F720 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/26/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-005, CON-NRC-TMI-81-5 NUDOCS 8102190113 | |
| Download: ML19345F720 (6) | |
Text
s ka "'%g p
,7
,o, UNITED STATES y
g NUCLEAR REGULATORY COMMISSION j
WASHING TON, D. C. 20555 January 26, 1981 NRC/TMI-81-005 MEMORANDUM FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation g
Bernard J. Snyder, Program Director, TMI Program Office FROM:
Lake H. Barrett, Acting Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of January 18 - 24, 1981
$6 O
aux Lake H. Barrett Acting Deputy Program Director TMI Program Office
Enclosure:
As stated cc:
E00 OGC Office Directors
~
Comissioner's Technical Assistants e
4 g, f, k',I,hM [U NRR Division Directors NRR A/D's g
y- )
Regional Directors ptB 0 21g-IE Division Directors C
h0
,,,, g i,, T, #
TMIProgramOfficeStaff(15) of RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser 8102 3 90 I/J
- /
NRC TMI PROGRAM OFFICE BEEKLY STATUS REPORT Week of January 18-24, 1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
Available Core Cooling Modes: Long-term cooling "B" (once through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode:
Standby pressure control (SPC) system.
t Backup Pressure Control Mode: One decay heat removal pump to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST).
Major Parameters (as of 0500, January 23,1981) (approximate values)
Average Incore Thermocouples:
1240F 0
Maximum Incore Thermocouple:
156 F RCS Loop Temperatures:
A B
Hot Leg 121 F 124 F U
Cold Leg 68 F.
68 F 0
0 68 F 69 F RCS Pressure: 105 psig Reactor Building: Temperature: 61 F Water level: Elevation 290.6 ft. (8.1 f t. from floor) via penetration 401 manometer Pressure:
-0.4psig{geise)
Concentration:
1.9 x 10 uCi/cc (Kr-85) (sample taken 1/21/81)
\\
Effluent and Environmental'(Radiological) Infonnation 1.
Liquid effluents from TMI site released to the Susquehanna River af ter pro-cessing, were made within the regulatory limits and in accordance with NRC requirements and City of ~ Lancaster Agreement dated February 27, 1980.
During the period January 1,1981, to January 24, 1981, minute amounts of contamination with an origin from Unit 2 were discharged from the TMI site.
The NRC TMI Program Office staff verified that no accident related water, as defined in the City of Lancaster Agreement dated. February 27, 1980, was discharged from Unit 2.
Although the concentrations of radioactive effluent were not detectable at the discharge point, calculations indicated that less than two millionths (0.000002) of a curie of cesium-137 (Cs-137) was discharged.
This represents less than 0.0001% of the permissible total liquid effluent activ-4 ity as specified in Technical Specifications for other operational commercial power reactors.
2 2.
EPA Environmen_ta_1_ Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
The EPA measured Krypton-85 (Kr 85) concentrations (pC1/m3) at several environmental monitoring stations and reported the following results:
Loc _ _a tion January 9 _ January 16, 1981 j
3 (pCi/m )
Bainbridge 19 Goldsboro 25 Observation Center 22 Middletown 23 All of the above levels of Kr-85 are considered to be back-ground levels.
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 January 16, 1981, through January 22, 1981.
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-131 Cs-137 Sample ye_r,1,od luc 1/ccl (uCi/cc) o HP-251 January 15, 1981-January 21, 1981
<9.7 E-14 <9.7 E-14 No reactor related radioactivity was detected, i
l Environmental TLD measurenents for the period November 26, 1980, l
to January 9,1981, indicate gansna radiation to be at the natural background levels. Fifty-four TLD's registered doses ranging from 0.18 mR/ day to 0.31 mR/ day. Average dose was 0.23 mR/ day.
These dose rates are consistent with natural background radiation i
in the TMI area.
4 Li_cens__ee_Radioa_ctive Material __and_ Radwa_ste Shipments. The following shipments were made:
On Monday, January 19,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
d 3
On Friday, January 23, 1981, three boxes containing sixteen Unit 2 air sample filters, a Unit 1250 mi sample taken from d
the decay heat removal system, and twenty Unit 2 air sample filters and smear papers, were mailed to Teledyne Isotopes, Westwood, fiew Jersey.
Majo_r_ Ac_tivities l
I 1.
Reactor _B_uildi_ng Purge / Entry. The sixth reactor building entry continues to be scheduled for February 3 and 5, 1981.
The major activities to be performed include installation of a closed circuit i
television system, work on the source range monitor, and a decon-tamination test. The day between the entries will be used to perform circuit checks and prepare personal equipment needed by members of the entry team.
2.
Submerged Demi _neralizer System (SDS). The SDS construction is approximately 70% complete and initial testing of completed portions
~
of the SDS is in progress. The onsite TMI Program Office is closely following developments in this area to reduce any potential i
I technical regulatory delays in the event the decision is made to allow use of the SDS to process water.
Consistent with this philosopny, the increased inspection efforts on the SDS installatic, are planned.
3.
_ Contaminate _d_ Building Expansion Joint. The licenses submitted a report to the onsite TMI Program Office staff on January 19, 1981, which concluded that the source of the contamination is the seal injection cubicle in the auxiliary building and not the reactor building. The staff is currently reviewing this report.
I 4.
Ground Wa_ter Monitoring Status.
Following the detection of trace quantities of cesium in monitoring well (MW)-2, the licensee assigned analysis priority to water samples from MW-2.
The most recent analysis by a licensee contracted laboratory included results of water samples taken on January 14, 1981. The January 14 1981, sample taken from MW-2 contains 81 pic.ocuries per liter (8.1 x 10-8 uCi/cc) of cesium-137 (Cs-137) and 37 picocuries per liter (3.7 x 10-8 uCi/cc) cesium in water in unrestricted areas is 2 x 10-5 u(MPC of Cs-134. The maximum permissible concentration 7
Ci/cc for Cs-137 and 9 x 10-6 uCi/cc for Cs-134.
The analysis of water samples taken from other wells through November 26, 1980, has not shown significant variation from the previously reported tritium activity. All wells continue to indicato tritium levels above natural background. Tritium concentration ranged from a low of 130 pci/l in MW-1 to a high of 4,690 pei/l in !W-17.
The licensee's s
investigation to determine the source of the radioactivity in lW-2 is continuing, and is being closely monitored by the onsite TMI l
l Program Office staff.
l l
4 5.
0_nsite An_alytical Laboratory _. On January 16, 1981, the onsite TMI Program OfTice staff identified several safety and radiological inadequacies in the licensee's onsite analytical laboratory. The safety and radiological problems were brought to the licensee management's attention. Subsequently the licensee agreed to shut-down the onsite analytical laboratory pending completion of-corrective action. Until then, the licensee will continue to send the reactor
+
coolant system samples to the licensee's contractor laboratory.in 7
Lynchburg, Virginia.
i 4
J tl 3
'l i
e r-w,:,,,,----,,
-,-v-,,=,,,,.,
,.,-..,.,,.,n.,-v,.--,,.v<
,,.r,-,.
+,n+, -, -,.- - -, - ~, -
,--n-
,,,---a,
-r,,,,~,.,
,,,4,
-,-,n,
-en-m,,,
-c y-
5 Meetings Attended On Thursday, January 22, 1981, Lake Barrett and Richard Conte attended a public briefing at the Forum in Harrisburg. The briefing w2s sponsored by the Department of Environmental Resources (DER) concerning the status of decontamination at Three Mile Island Unit 2 (TMI-2).
Robert Arnold and Gale Hovey of the TMI Nuclear Generating Station, provided an updated review covering the following areas: cork seal contamination, contamination in sumps of a waste storage module, ground water contamination, new method of cooling the TMI-2 reactor, recent correspondence between General Public Utilities (GPU) and the NRC, disposal of the processed cleaned up accident water at TMI-2 and future entries into the TMI-2 containment building. After their presentation, Lake Barrett gave a status report on the NRC's efforts towards solving problems related to t
disposal of TMI-2 higher radioactivity level waste. He stated that the TMI site is not appropriate for ultimate disposal of radioact!ve waste and summarized recent NRC correspondence to the Department of Energy (D0E), which expressed the desirability of greater DOE involvement in waste disposal. Additionally he stated that it was the NRC staff's position that NRC licensing procedures would not apply to DOE facilities, which may process, store or dispose of TMI waste provided that the facilities were used primarily for defense related activities.
Af ter the presentations, the meeting was opened for a question and answer session with the press and the local public. Major areas of concern centered around the cesium in the on-site monitoring wells and requests for further information regarding site hydrological data.
It was also suggested, to improve communications, that a special 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> /per day " rumor control" telephone line be developed by the licensee for area residents to call so they could obtain accurate information regarding activities at TMI.
Future Meetings 1.
On Thursday, January 29, 1981, Lake Barrett will treet with the Mayor of Lancaster to discuss the status of TMI-2.
2.
The NRC's Advisory Panel for the Decontamination of Three Mile Island Unit 2, will hold meetings in Harrisburg, on February 4,11 and 19,1981. The public is invited to observe all three of these meetings, which will be held at the Forum of the Education Building on Commonwealth and Walnut Streets.
Each of these meetings are scheduled to begin at 7:00 p.m. 'and end at 10:30 p.m.
i i
9 I
l l
v4if80 staffs NoCsian atastaTCav Comu:ssi04 I
natmeG'04 B C 30466 Potf act & PE85 8af D
- e... e..... t.
w g n,,,e, eepse, Ce=*****
gg e
9
?
e
,