ML20203H356
| ML20203H356 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/22/1986 |
| From: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8608040383 | |
| Download: ML20203H356 (5) | |
Text
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JUL 2 21986 Docket No. 50-289 MEMORANDUM FOR: Harry Kister, Chief Projects Branch No. 1 FROM:
Allen R. Blough, Chief Reactor Projects Section IA
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD JULY 11 - 18, 1986 Enclosed is the TMI-1 weekly status report from the NRC Resident Office at THI-1 for the subject period.
The NRC staff continued to monitor routine plant operations at full power.
TMI-1 status reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of TMI-1 activities for the previous week. Subsequent inspection reports will address many of these topics in more detail.
i Origina1 Signed Byt Allen R. Blough, Chief Reactor Projects Section IA Branch 1, DRP
Enclosure:
As stated cc w/ enclosure:
F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania R. Benko, Governor's Office of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI H. Hucker A. Herman C. W. Wolfe J. Johnsrud P. Smith Public Document Room Local Public Document Room 8608040303 e60722 ADOCK0500gg9 PDR p
R OFFICIAL RECORD COPY - TMIl WEEKLY STATUS REPORT ZEEI3l J
'l (
2 bec w/ enclosure:
K. Abraham, RI P..Lohaus, RI R. Starostecki, RI H. Kister, RI R. Conte, RI (20 cys)
W. Baunack, RI R. Freudenberger Region I Docket Room (w/ concurrences)
RI:DRP RI:DRP R:
P M, Conte Blough Kister 7/1.I/86 7/N/86 7/2)/86 0FFICIAL RECORD COPY - TMIl WEEKLY STATUS REPORT u
ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD JULY 11 - 18, 1986 1.
Plant Status As of 8:00 a.m. on July 18, 1986, TMI-1 was operating at 100 percent power and at normal reactor coolant temperature (579 F) and pressure (2155 psig).
2.
Facility Operations Summary At the start of the period, the plant was operating at 100 percent power and continued to operate at 100 percent during the reporting period. No significant operational problems were identified during the report period.
3.
Items of Special Interest Fire Pump Building Damage On July 18, 1986, the licensee sustained significant damage to the diesel-driven fire pump building. At 12:35 a.m.,
the fire suppression deluge system associated with the IB auxiliary transformer actuated. Actuation of this system caused a pressure drop in the station's fire-main pressure causing additional fire pumps to start, including diesel-driven fire pump FS-P-3.
Due to apparent equipment malfunction, the sump associated with FS-P-3 was overpressurized. Overpressurization of this sump caused the sump's manway cover to be blown off and through the roof of the diesel-driven fire pump building.
The licensee is in the process of assessing the damage to the fire pump and building. Technical Specifications allow continued plant operation with the fire pump inoperable, since three additional fire pumps are available.
INPO Inspection The Institute of Nuclear Power Operations (INPO) conducted an evaluation at TMI-1 July 14-18,1986, and will continue their evaluation July 22-25, 1986. This is the first such evaluation since power operations began in October 1985. There will also be an INP0 corporate assist visit in Parsippany, New Jersey, on August 4-8, 1986.
For the site evaluation, a 20 member team is covering the following areas: organization and admini-stration; operations; maintenance; technical support; radiological protec-tion; chemistry; training and qualification; and operating experience review.
1 i
2 4.
Systematic Assessment of Licensee Performance (SALP)
The NRC Region I SALP board met on June 6, 1986, to discuss licensee per-formance between September 16, 1985, and April 30, 1986, which included the TMI-1 restart period of September 16, 1985, to January 10, 1986. A management meeting between NRC and GPUN to discuss the SALP is scheduled for 9:00 a.m., July 30, 1986, at the NRC Region I Office in King of Prussia, Pennsylvania. Members of the public may attend this meeting as observers.
Because of space limitations, it is important fcr those planning to attend to contact Allen R. Blough at (215) 337-5146 or (717) 948-1160.
The subject SALP period is termed "SALP I,"
since it is the first of two SALP's that were directed by the Commission in their restart order of May 1985. A previous SALP report which focused solely on the restart period (September 16, 1985, to January 10,1986) was issued May 14, 1986 (NRC Inspection Report No. 50-289/85-98).
5.
NRC Thermoluminescent Dosimeter (TLD) Monitoring Program for TMI The special NRC TLDs for TMI for the period April 2 - July 3,1986, were processed at the Region I TLD laboratory.
The TLD readings are provided in the attached Table A.
The monitoring results indicate that the radia-tion levels at these monitoring locations remain at natural background levels. These readings can be expected to vary slightly from period to period due to variations in natural background, independent of releases from the plant.
6.
NRC Staff Activities During the Period During this report period work week, the NRC staff on site consisted of the senior resident inspector and one region-based inspector. One resi-dent inspector was assigned to project engineer duties in Region I.
The other two resident inspectors were on vacation.
On July 11, 1986, NRC Region I issued Inspection Report 50-289/86-06, covering April 11, 1986, to May 16, 1986. One apparent violation was identified and specifically cited.
It dealt with failure to adhere to certain facility procedural requirements. The report also addressed an apparent violation of NRC environmental qualification requirements, which was not cited because it will require additional Region I review. An ap-parent " deviation" from training commitments in the radwaste transporta-tion area was also identified. A written response to the cited violation and deviation is expected from the licensee within thirty days.
The NRC staff at TMI-1 was comprised of the following personnel during the period:
R. Conte, Senior Resident Inspector C. Hix, Secretary R. Freudenberger, Engineer in Training
TABLE A TMI TLD MONITORING RESULTS Station Distance Direction Baseline Field Exposure 4/2/86-7/3/86 (miles) mR/ day mR/ day (Mean 1 s.d.) (Mean i s.d.; total uncertainty)
Control #1 0.15 + 0.01; 0.02
~
Control #2 0.13 1 0.007; 0.02 2
3.9 101 0.19 1 0.02 0.20 1 0.01; 0.03 3
2.7 109 0.16 + 0.02 0.16 + 0.01; 0.02 4
1.8 163 0.1610.02 0.1710.007;0.03 5
2.2 161 0.18 1 0.02 0.18 1 0.002; 0.03 6
1.0 150 0.17 1 0.03 0.19 1 0.006; 0.03 7
0.6 136 0.17 1 0.02 0.18 1 0.008; 0.03 8
0.4 83 0.16 1 0.03 0.19 1 0.001; 0.03 9
0.5 60 0.16 1 0.02 0.20 1 0.001; 0.03 10 1.7 1
0.14 1 0.02 0.20 1 0.002; 0.03 11 0.9 25 0.16 1 0.01 0.20 1 0.01; 0.03 12 2.8 46 0.16 + 0.02 0.23 + 0.02; 0.04 14 2.5 358 0.1410.02 0.1910.001;0.03 16 3.1 0
0.14 1 0.02 0.20 1 0.005; 0.03 18 3.5 349 0.17 1 0.03 0.17 1 0.005; 0.03 19 3.2 343 0.17 1 0.02 0.20 1 0.009; 0.03 20 5.0 318 0.16 1 0.01 0.20 1 0.02; 0.03 21 1.3 348 0.13 1 0.01 0.15 1 0.008; 0.02 22 3.1 17 0.17 1 0.02 0.19 1 0.004; 0.03 23 3.8 64 0.13 1 0.01 0.19 1 0.01; 0.03 24 3.6 44 0.17 1 0.01 0.20 1 0.01; 0.03 34 2.3 267 0.17 1 0.01 0.19 1 0.001; 0.03 35 1.8 299 0.17 1 0.01 0.18 1 0.001; 0.03 36 1.2 267 0.12 1 0.02 0.14 1 0.007; 0.02 37 1.4 256 0.14 1 0.01 0.16 1 0.004; 0.02 38 1.9 225 0.18 1 0.02 0.19 1 0.002; 0.03 39 2.1 200 0.13 1 0.01 0.15 1 0.003; 0.02 40 2.5 204 0.16 1 0.02 0.17 1 0.006; 0.03 46 3.0 177 0.14 + 0.02 0.16 + 0.01; 0.02 50 4.9 145 0.1410.04 0.16}0.005;0.02 Abbreviations:
mR
= millirem s.d. = standard deviation REMARKS:
Twenty-nine environmental (offsite) locations are monitored using special TLDs for the TMI site. Two control TLDs were stored in a 1/2" thick lead shield at the NRC TMI Office for two weeks.
The baseline data for the environmental monitoring were calculated using the past ten quarters of monitoring results. All monitoring results indicate normal natural background radiation levels.