ML20214W619
| ML20214W619 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/04/1986 |
| From: | Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8612100328 | |
| Download: ML20214W619 (5) | |
Text
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DEC 4 1986 Docket No. 50-289 MEMORANDUM FOR: Allen R. Blough, Chief Projects Branch No. 1 FROM:
Richard J. Conte, Chief Reactor Projects Section IA
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD NOVEMBER 14 - 28, 1986 Enclosed is the first biweekly status report from the NRC Resident Office at TMI-1 for the subject period. As noted in previous weekly reports, November 14, 1986, was the effective date TMI-1 status reports would be issued on a biweekly basis.
During this two week period, the NRC staff continued to monitor routine plant operations during cold shutdown and associated outage activities.
TMI-1 status reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of TMI-1 activities.
Original Signed By g Richard J. Conte, 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
8612100328 861204 J."
Wolfe ADOCK 05000 89 Johnsrud hDR P. Smith E. Harzler D. Davenport Concerned Mothers and Women Public Document Room Local Public Document Room 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80 JE EE751 )
\\
Harry Kister 2
bec w/ enclosure:
K. Abraham, RI P. Lohaus', RI W. Kane, RI H. Kister, RI F. Young,.RI (20 cys)
W. Baunack, RI R. Freudenberger, RI Region I Docket Room (w/ concurrences)
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I:DRP Youn61 on e Blough 12/k/86 12/ Y/86 I2/}//86 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80 i
ENCLOSURE TMI-I STATUS REPORT FOR THE PERIOD NOVEMBER 14 - 28, 1986 1.
Plant Status As of 8:00 a m. on November 28, 1986, TMI-1 was in cold shutdown on the IA-Train of Decay Heat Removal with reactor coolant temperature at 105 F and 0 psig RCS pressure.
Reactor vessel (RV) water level is being main-tained at 10-18 inches above the center line of the RV cold leg inlet piping.
2.
Facility Work Summary The plant was maintained in cold shutdown with the licensce accomplishing the removal of three tubes from the "A" Once-Through Steam Generator (OTSG). Approximately eleven feet of each tube was removed in sections, and the licensee plans to ship these sections to Babcock & Wilcox (B&W) test facilities in Lynchburg, Virginia, for analysis. Also, the licensee completed removal of the shaft seal package for "C" reactor coolant pump to inspect the sealing surfaces and for seal refurbishment. Work on the "A" reactor coolant pump (RCP) seal will be performed after completion of the work on the "C" RCP seal. Work continues on modifications which are required by the NRC regulation 10 CFR 50 Appendix R and upgrade of the emergency feedwater system to safety grade.
In addition, work continued in the area of steam generator eddy current inspection, refueling prepara-tions and installation of the engineered safety features ventilation system for the fuel handling building.
3.
Items of Special Interest Check Valve Damage During performance of an Inservice Testing (IST) inspection on six-inch main steam check valve, MS-V-9A, the licensee discovered that the internal parts of the check valve were missing.
This check valve is located in the supply line to the emergency feedwater (EFW) pump steam line from the "A" OTSG.
Specifically, the nut and washer that connect the check valve disc to the flapper were missing.
The valve, MS-V-9A, had never been disassem-bled but a similar valve, MS-V-98, had been disassembled in 1984 with no damage found.
The licensee is investigating the cause of the valve failure.
During a search for the missing parts, the nut was discovered downstream of the check valve, but the washer is still missing.
The valve had functioned properly during plant operations and testing.
The licensee disassembled and inspected the other similar check valve, MS-V-98, and found no problems.
The resident inspectors will continue to follow the licensee's corrective actions.
i Steam Generator Eddy Current Inspection The licensee has completed eddy current inspection sample of 3 percent in each steam generator as required by technical specifications (TS).
Upon preliminary review of the analysis of this eddy current inspection data, an indication of greater than 40 percent throughwall indication was noted in one tube in each generator. As required by technical specifications, the licensee has increased the sample size to 6 percent for each steam-generator. The licensee continues to perform eddy current testing and evaluation of the data obtained. The eddy current inspection is scheduled to be completed late in December 1986.
Borated Water Storage Tank (BWST) Inleakage During the period of November 6 through November 9,1986, the licensee conducted the containment integrated leak rate test at which time the re-ac+or building was pressurized to approximately 50.5 psig. During this p *iod, approximately 5,000 gallons RCS water leaked from the decay heat sys, em to the borated water storage tank (BWST).
The RCS was depressur-ized et this time.
The shifting of the water to the BWST resulted in a slight radiation reading increase at the Reuter-Stokes environmental moni-toring station located just outside the protected area and adjacent to the BWST on site. Radiation levels at the Reuter-Stokes environmental monitor-ing station increased from 8 microRems/ hour to as high as 14 microRems/ hour and have since decreased to 11 microRems/ hour. Since then, the licensee has placed the BWST on clean-up recirculation through a filtering system to reduce the radiation levels at the BWST. All RCS water that leaked into the BWST was contained in the BWST or the associated piping with no liquid releases to the environment.
4.
NRC Staff Activities During the Period During this report period, the NRC staff consisted of three resident in-spectors. The senior resident inspector was detailed to the region during this period.
Seven region-based inspectors were on site part time to con-duct a review of the radiological control program, OTSG tube pulling and eddy current activities, modifications involving seismic work and refueling preparations.
Mr. H. Kister, Chief, Reactor Projects Branch (RPB) No. I retired, effec-tive December 1, 1986. Accordingly, on a temporary basis, Mr. F. Young will be the Senior Resident Inspector at TMI-1; Mr. R. Conte, formerly the Senior Resident Inspector at TMI-1 will be Chief, Reactor projects Section (RPS) No. IA; and, Mr. A. Blough, formerly Chief, RPS No. IA, will be Chief, RPB No. 1.
OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80
P The NRC staff a+ TMI-1 was comprised of the following personnel during the period.
Region-based inspectors were on site part time.
R. Freudenberger, Reactor Engineer, RI H. Gray, Lead Reactor Engineer, Region I (RI)
C. Hix, Secretary D. Johnson, Resident Inspector D. LeQuia, Radiation Specialist, RI K. Manoly, Lead Reactor Engineer, RI J. Prell, Reactor Engineer, RI J. Rogers, Resident Inspector M. Shanbaky, Chief, Facilities Radiation Protection Section, RI A. Weadock, Radiation Specialist, RI F. Young, Senior Resident Inspector t
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