ML19343D464
| ML19343D464 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/29/1981 |
| From: | Conte R, Moslak T Office of Nuclear Reactor Regulation |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8105040562 | |
| Download: ML19343D464 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION M
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- C WASHING TON, D. C. 20555
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January 29, 1981
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MEMORANDUM FOR:
N. Moseley, Director, Reactor Operations Inspection, IE
-THRU :
A. N. Fasano, Chief S e Operations Section, TMI Program Office 1.
FROM:
R. J. Conte, Senior Resident Inspector, Unit 2, Site Operations Section, TMI Program Office T. A. Moslak, Radiation Specialist, Site Operations Section, TMI Program Office
SUBJECT:
FACT FINDING AS RESULT OF N. M0SELEY QUESTIONS DURING WEEK 0F JANUARY 12, 1981 Based on several telephone conversaticns during the week of January 12, 1981, between your office and the TMI onsite NRC staff, information was gathered on various topics in response to you and your staffs questions concerning selected events at the time of the TMI 2 accident. These questions are summarized in enclosure 1 with listed answers.
Subsequent enclosures 2 through 4 are used for the more detailed answers.
For 766 purposes, 30 staff-hours were involved in this effoit (excluding documentation).
If you have any questions on this we will ba glad to discuss them with you.
$fr R. J.' Conte Senior Resident Inspector, Unit 2 Site Operations Section TMI Program Off*ce ~'
s 3 'T \\
T. A. Moslak Radiation Specialist Site Operations Section TMI Program Office 4
Enclosures:
As Stated cc:
E. Brunner l
R. Keimig l
i 810 504 0 36Q
Encicsura 1 Que_stions/ Responses _
l.
When did the licensee know of the Hydrogen (H ) concentration in p
the reactor building within the first few day 5 of the accident?
What logs are available for review? What personnel can be interviewed?
~
How was the analysis / sampling accomplished and data recorded?
Per_ sons Co_ntacted. The following personnel that gave significant infonnation during the course of the' fact finding interviews are listed below.
J. Chwastyk, Plant Operations Supervisor J. Deman, Radiation Protection Foreman R. Dubiel, Supervisor Radiological Engineering, Unit 1 K. Harner, Chemistry Supervisor, Unit 2 J. Flaherty, Accident Assessment Engineering I. Morrill, Micrographics Supervisor Log / Records. The following logs and records were reviewed to ddvelop a sequence of events (enclosure 2) for H2 concentration sampling and data analysis. Those marked by asteriks (*) were deemed not useful to the review.
(1) HCN-0003, Hydrogren Calculation, Hydrogen Content Analysis and Recommendation File (2) Control Room Operator's (CRO) Log (3/28/79-4/15/79)
(3) Shift Supervisor's Log (3/28/79 4/15/79)
(4) Primar: Chemistry Log (3/28/79 4/15/79)
(5) HCN-0001 H2 Recombiner Perfonnance File
- (6) HCN-0002 H Bubble Reactor Coolant System (RCS) Data 2
- (8) HC-0001 RCS H2 Data
- (9) ReactorCoolantAirSampleLog1978(Radiological)
The sequence shows that the earliest successful sample was taken on 3/31/79 between 5:18 and 6:38 a.m. and yielded a result of 1.7%
H2-
2 Sampling Techniques / Data Acquisition.
It appears that three techniques were utilized for measuring H2 concentration in the reactor building. The majority and earliest of the samples were by grab samples at the HPR-227 sampling rack (particulate, iodine and noble gas monitors used this same sample point). A gas chromotograph (partitioner) was used on the grab sample for analysis. An in line analyzer, referred to as B&W (Babcock and Wilcox) In-line Analyzer, also utilized the same sample points. This was installed some time during March 31 - April 3,1979.
Further, the H2 Recombiner either had a monitor or the sample point was used for grab sample hydrogen measurements (this was not pursued any further in light of the general thrust of this question as to earliest known concentration values). Results of all three techniques are listed in enclosure 2.
Based on discussions, it appears that there was little reliance on the in line analyzer.
2.
Where are Gas Chromotograph charts and how are they used?
Response. The charts are used to input data to a progransnable calculator for a gas concentration (H, 0, and N2) printout. No 2
2 charts were available for review and only one printout was available for review.
It appears they were discarded. The results are recorded in various plant logs.
3.
Where are the Reactor Building Entry Forms (Procedure 1630.2) that give toxic gas concentrations (possible use in early days of the accident)?
Response. To date, these were not found.
It appears they got contaminated in the health physics (HP) office (at the auxiliary building entrance) at the time of the accident. The licensee is attempting to locate all records that were in the HP office at that time and/or determine final disposition. The onsite staff will followup on this item.
4.
When was Halliburton Tank brought on site (1st week of accident) to refill BWST (Borated water storage tank)?
Response.
Sunday, April 1, 1979.
5.
When was the first low level shipment made from site within 1st week of accident (date, contents, destination)?
Response.
Unit 1, 85 ft3 dewatered resin in Barnwell, shipped 4/11/79.
6.
When did the truck for the shipment (above) arrive on site to make the shipment?
Response.
The licensee representative stated that the resin liner was loaded on the trailer in preparation for shipment on March 27, 1979.
No rad surveys were perfonned prior to April 11, 1979.
3 7 '.
When was the IWTS ({ndustrial waste treatment system) sampled with a result of 6 x 10- uCi/cc (Xe-?), when taken and analyzed?
Respons.e.
Examining the sample results from the " pre-April 9,1979
'(Xe-133m or fe there was no sample with a concentration of 6 x 10-sample index "
135).
Xenon data ranged from a low of 10-6 uCi/cc to a high of 10-3 uC1/cc with some sample results having "no detectable quantities" and "high Xe background" entered as data. The data is listed in enclosure 3.-
It appears that the given Xenon data is not reliable in that a high Xenon background existed in the counting facility at the time of the accident.
See enclosure 4 for other sample /run times for IWTS.
8.
When was the IWTS/IWFS operated (during the 1st week of the accident)?
Response. See enclosure 4
Enclcsu_ra_2 Reactor _ Building _ Gas _ Sample Sequence of Events Date Time Event Refer _ence*
3/31/79 0518-0638 Lineup (AH-V101-108) 2 & 3**
3/31/79 0700 Sample Result 1.7%
1 3/31/79 1500 Sample Result 1.9%
1 3/31/79 2100 Sample Result 2.0%
4 3/31/79 2245-2251 Lineup 2
3/31/79 2210 Sample Result 1.7%
4 4/1/79 0119-0228 Lineup 2
4/1/79 0600 Sample Result 2.6%
1 4/1/79 0700(7AM-7PM)
Result 1.9% (Result 2.4%)
4 (4) 4/1/79 0710-0717 Lineup 2&3 4/1/79 0740 SS Log Result 2.6%
3 4/1/79 0845 Result 2.4%
1 4/1/79 0931 Result 2.4%
4 4/1/79 0937 Result 2.4%
3 4/1/79 1000 Recornd Result Illegible Possibly 3.0% 3 4/1/79 1044-1158 Lineup 2&5 4/1/79 1200 Recorded Result 2.2%
1 4/1/79 1225 1030 Result 2.0%
2, 3 & 4 4/1/79 1330 Recorded Result 2.0%
1 4/1/79 1330 Recorded Result 2.1%
2, 3 & 4 4/1/79 1500 Recorded Result 2.0%
1&4 4/1/79 1805 1500 Sample 2.0%
2&3 4/1/79 1830 Recorded Result 2.0%
1&4 4/1/79 1900 See 1830 Result 4
--w-
.s.-
-~
. f(cont)
' Date Time Ever.t Reference 4/1/79 2230-2254 Lineup 2&3 4/1/79 2230 Result 2.3%
1&4 4/2/79-0600-0617 Lineup 2&3 4/2/79 0600 Result 2.4%
1&4 4/2/79 0940 Lineup 2&3 4/2/79 1030 Result 2.1%
1 & ',
4/2/79 1240-1315 Lineup 2&3 4/2/79 1323-1347 H Recombiner Start-up 2&3 2
4/2/79 1542***
Result 2.1% (Recombiner Performance) 5 4/2/79 2336 In Line Analyzer Result 2.1 B&W Record Book ****
4/2/79 2347 Lineup 2&3 4/2/79 2342 In Line Analyzer Result 2.1 B&W Record Book ****
4/3/79 1010 In Line Analyzer Result 2.1 B&W Record Book ****
4/3/79 1021 In Line Analyzer Result 2.0 B&W Record Book ****
4/3/79 1245-1307 Lineup 3
(correlation for ref. 2 & 3 not done for4/3on) 4/3/79 1842-2020 Lineup 3
4/3/79 2208-?
Lineup 3-l 4/3/79 2300 2.01k ample From In-line Monitor RB H S 3
4/3/79 2235 Result 2.01%
1 4/3/79 2300 Result 2.3%
4-l l
l
~~
4 Enclos_u_re 2 (cont)
' Date
)) met Event
' Reference 4/4/79 1556-1631 Lineup 3
4/4/79 1610 In Line Analyzer Result 1.5 B&W Record Book ****
4/5/79 1840-?
Lineup 3
4/6/79 2000 H2 Recombiner Result 1.65 B&W Record Book ****
4/6/79 2245 Recorded Result 1.8%
4 4/6/79 2245 In Line Analyzer Result 1.8 B&W Record Book ****
4/7/79 0600 H Recombiner Result 1.59 B&W Record 2
Book ****
- See Enclosure 1 Question #1, Logs / Records
- 1100 Control Room Operator Log 3/29/79, HP-R-227 was isolated from reactor building and secured.
Based on interviews, this appeared to be an aborted attempt to sample the building due to water in the sample line.
- Daily H2 Concentration Results given 4/2-13/79 with no time correlation (Ref5)4/13/79 end point result.97%
- Not observed during review (verbal report) - Five other results given for 4/7/79 to 4/9/79 which appear to be consistent with the in line analyzer, i
-a,-----+,-
- -. - - - -, ~ -,...
'_Enclo_ surg 3
_IWTS Effluent-Samp_les at SampTing Point No_. _1_07_
Sample _No.
Da t_e/ Tim __e__
~ Analyzed By AD007 3/29/79 1330 Science Applications Inc.(SAI)
A0008 3/29/79-1700 SAI A0009 3/29/79-1000 SAI A0022 3/29/79-1000/2000/1400 Water Sample Analyzed at Observation.
Center (0BW)-15/16 A0023 3/29/79-1330/1700/0600 0BW-1/8/9 A0036 3/30/79-1200 SAI A0038 3/30/79-2000 SAI i
A0039 3/30/79 1600 SAI A0040 3/30/79-0600 SAI A0096 3/30/79-2000 No entry A0148 3/31/79-2400 OBW-7 A0150 3/31/79-0800 0BW-12 A0151 3/31/79-0400 OBW-ll A0152 3/31/79 0600 OBW-10 A0153 3/31/79-1800 OBW-19 A0154 3/31/79-1200 OBW-18 A0155 3/31/79 1400 0BW-17 A0156 3/31/79-2000 OBW-16 A0157 3/31/79-2200 OBW-24 A0187 3/31/79-0400 OBW-ll 3/31/79-0800 OBW-12 3/31/79 0200 0BW-13 3/31/79-0600 OBW-14
Enclosure'3_(cont) 2 Sampl e - No._
-Date/ Time Analyzed'By A0188 3/31/79-1200 OBW-18 3/31/79-1800 OBW-19 4/1/79-0200 OBW-20 4/1/79-0400 OBW-21
/.0202 4/1/79-2000 No entry A0254.
4/1/79-0000 OBW-22 A0255 4/1/79-0400 OBW-21 A0256 4/1/79-0200 OBW-20 A0257 4/1/79-1800 OBW-36 A0259 4 1/79-1600 OBW-34 A0261
- ./31/79 1600 OBW-32 A0262 4/1/79-1400 OBW-31 A0263 4/1/79-0800 OBW-30 A0264 4/1/79-1200 OBW-28 A0265 4/1/79-0800 OBW-27 A0266 4/1/79-0600 0BW-26 A0284 4/1/79-1600/1800 OBW-34/35 A0285 4/1/79 1400/16(1 OBW-31/32 A0287 4/1/79-0600/0800/1200 OBW-26/27/28 A0288 4/1/79-0000/0330 OBW-23/24 4
Xe-133m and Xe-135 concentrations for the IWTS sagple point (No.107) ranged from "none detected" to slightly greater than 10- uCi/ml.
Entries for numerous samples stated "high Xenon background."
i This disparity of data indicates that no firm conclusion car be made regarding the Xenon concentration of IWTS effluent.
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Encicsura_4 IWTS/IWFS ' Log _ Book _#1 fr_o_m'Aug_ust 1978 to August _i980 Date
~ Time Entr/
3/28/79 0130 Systoa dropped cakes - IWFS Shutdown 3/28/79 N.E.
IWTS Shutdown Unit 2 Site Energency 3/29/79 0815 IWTS and IWFS sumps' sampled for. activity prior to starting up systems -
3/29/79 1100 Resampled IWTS and IWFS (Bob McCanis informed me ti.ey had a possible Xenon problem and did not know if it was one or both systems) 3/29/79 1315 Started up IWTS per Chemistry Dept.
instruction sump level is 100%+
3/29/79 1330 Per chemistry instruction took liter sample of IWTS effluent flow 0 HPDES sample point
- 107 (entry line out:
" sample every-12 hours")
3/29/79 1410 Informed by SS to terminate IWTS release due to Xenon in sample NOTE:
Total release (IWTS) was 90 gpm for 40 minutes effluent integrator reads 243018 x 10 3/29/79 1610 Started IWTS per Dick Dubiel 0 200 gpm flow and IWTS sump level 100%+
IWFS sump' level 76%
3/29/79 1700 IWTS - sample #107 taken (Bold print) take samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> polymer pumps setting now cation:
from 35 to 55 anion:
from 40 to 60 3/29/79 1815 Stopped dump
.