ML20205N569
| ML20205N569 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/23/1986 |
| From: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8605020196 | |
| Download: ML20205N569 (5) | |
Text
,
O APR 2 3 286 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 April 11-18, 1986 Enclosed is the TMI-1 weekly status report from the NRC Resident 0ffice for the subject period. Licensee cold shutdown work activities continued with orienta-tion toward completing work in preparation for startup.
The NRC staff continued to follow the outage status; including steam generatnr tube plugging work, in-spection of the emergency feedwater' nozzles, battery replacement and testing; and to conduct random inspection of other test and work activities.
TMI-1 status reports are intended to provide NRC tranagement and the public with highlights from an NRC regulatory perspective of TMI-I activities for the pre-vious week. Subsequent inspection reports will address many of these topics in more details.
Original Signed Byg Allen R. Blough, Chief Reactor Projects Section IA Branch 1, DRP
Enclosure:
As stated 8605020196 860423 PDR ADOCK 05000289-R PDR OFFICIAL RECORD COPY TMll WEEKLY STATUS REPORTIE3l 1
I
Harry Kister 2
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 Public Document Room Local Public Document Room bec w/ enclosure:
K. Abraham, RI P. Lohaus, RI R..Starostecki, RI W. Kane, RI H. Kister, RI J. Durr, RI R. Conte, RI (20 cys)
W. Baunack, RI Region I Docket Room (w/ concurrences)
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-RI.025-et, Conte Blough Kister Dur.c
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/86 4.1 46-4/ef/86 0FFICIAL RECORD COPY TMIl WEEKLY STAT'J REPORT -
11/29/80 L
ENCLOSURE i
TMI-1 STATUS REPORT FOR THE PERI 00 April 11 - 18,1986 1.
Plant Status As of 8:00 a.m. on April 18, 1986, TMI-1 was in a cold shutdown condition with reactor vessel water level maintained at the reactor vessel nozzles and the primary side of the steam generators drained for tube plugging work. The decay heat system was maintaining reactor vessel water tempera-ture at 100 20 F.
2.
Facility Operations Summary Cold shutdown outage activities continued throughout the period. Work was oriented toward job completion and recovery of systems to support plant startup scheduled for the middle of next week.
The circulating water system was started and this resulted in a small vapor plum, visible from off-site, being emitted from the large natural draft cooling tower.
3.
Special Interest Items Steam Generator Eddy Current Test Results/ Tube Plugging The licensee conducted an analysis of eddy current examination results.
One purpose of the eddy current testing was to ensure that the integrity of the steam generator tubes was not adversely affected by recent plant operations. The results of the licensee's analysis determined that there was no significant degradation of the steam generator tubes.
Twenty-five tubes, however, were removed from services during this outage in accordance with Technical Specification Requirements.
Most of these tubes were located in areas where previous problems were noted.
In addi-tion to eddy current inspection, drip and bubble tests were also performed on both OTSG's. Both tests indicated no leakage. This was the first time l
that the generators did not indicate some leakage during these tests.
In a related matter, on Friday, April 18, 1986, the NRC issued License Amendment No. 116 which increased the defective tube criteria from 40%
to 50*; through-wall indication.
During this period the licensee plugged tubes that were considered defective using the r.ew criteria.
Feedwater No::le Insoection/ Repair Due to the failure of auxiliary feedwater no:Ile thermal sleeve / collar weld observed at Oconee 1, the licensee began to inspect collar welds at TMI-1. This inspection originally was scheduled to be performed during the next refueling outage; however, due to other corrective maintenance being performed on the emergency teedwater spray ring, one of the six 0FFICIAL RECORD COD (
TF.". WEEKLY STATUS REPORT -
2 thermal sleeves was required to be removed. Cracks were observed in this assembly, consequently, the licensee performed the scheduled NDE examina-tion on the remaining thermal sleeves.
Dye penetrant testing revealed linear cracks on four of the twelve nozzles in the toe of the welds con-necting the nozzle thermal sleeve to the collar. This weld does not form part of the steam generator secondary side pressure boundary.
The li-censee made necessary repairs and reinstalled the thermal sleeves.
Environmental Qualification Meeting In their March 1986 inspection, the NRC Performance Appraisal Team (PAT) identified an Emergency Feedwater System valve power scpply cable which had not been evaluated for TMI-1 Environmental Qualification (EQ).
Because the cable type had been evaluated for the licensee's Oyster Creek plant, the licensee was able to promptly determine EQ for that particular cable type at TMI-1. Since then, the licensee had been reviewing EQ of all com-mon equipment (such as cable, terminal blocks, splices, and penetration seals) to determine if other similar cases might exist. At 10:00 a.m.,
April 18, 1986, members of NRC Region I, the Office of Nuclear Reactor Reguiation (NRR), and the Office of Inspection and Enforcement (IE) met with the licensee to discuss both EQ methodology and the results of the recent licensee review. The licensee indicated that he had done a reveri-fication program for EQ of cables and other common equipment.
This program identified one additional cable type for which no 11-1 EQ file existed.
The licensee indicated that he had obtained a cable test report, and is reviewing the report and developing an EQ file. Also, as a result of the meeting the licensee committed to make additional efforts before restart to identify model numbers of installed terminal blocks.
(Note:
terminal blocks are often marked with only the manufacturer's name and no model number.) The licensee plans to summarize the reverification effort in a letter to NRC Region I.
4.
NRC Staff Status During the Period During this report period, the NRC staff on site consisted of the senior resident inspector and two resident inspectors, supplemented by a radia-tion specialist from Region I.
Certain members of Region I management were on site Friday, April 18, 1980, to participate in the above-noted EQ meeting.
The resident staff continued to folios plant status and outage work and conducted random inspections of these activities.
Primary focus was tube plugging, feecwater nozzle inspection, and battery replacement and testing, c
l
e Enclosure 5.
Systematic Assessment of Licensee Performance (SALP)
At 7:30 p.m. on Thursday, April 24, 1986, members of NRC Region I manage-ment will be available at the NRC's Middletown office (Downtown Mall, 100 Brown Street, Middletown, Pennsylvania) to answer questions from the public regarding both the SALP and NRC inspection programs at TMI-1. Because of space limitations at the Middletown Office, it is important for those planning to attend the public meeting to contact Allen R.
Blough at (215) 337-5146 or (717) 948-1160.
6.
NRC Thermoluminescent Dosimeter (TLD) Special Monitoring Program for TMI The special NRC TLDs for TMI for the period March 4 - April 1,
- 1986, were processed at the Region I TLD laboratory. The TLD readings are pro-vided in the attached Table A.
The monitoring results indicate that the radiation 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.
In the future these reports will be provided on a quarterly basis.
7.
The participating NRC staff at TMI-1 for the period was:
P. Clemons, Radiation Specialist
- R. Conte, Senior Resident Inspector C. Hix, Secretary D. Johnson, Resident Inspector R. McBrearty, Reactor Inspector F. Young, Resident Inspector
- Also participated in the EQ meeting.
E0 Meeting R. Blough, Chief, Reactor Projects Section 1A, DRP J. Durr, Chief, Engineering Branch, Division of Reactor Safety W. Kane, Deputy Director, Division of Reactor Projects (DRP)
W. Potapovs, Chief, EQ and Inspection Section, IE J. Thema, Licensing Project Manager, NRR G. Zech, Chief, Vendor Program Branch, IE R. LaGrange Technical Reviewer, NRR H. Garg, Tecnnical Reviewer, NRR