ML20210E624
| ML20210E624 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/17/1986 |
| From: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8609250056 | |
| Download: ML20210E624 (4) | |
Text
.,,
t SEP 171986 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 SEPTEMBER 5 - 12, 1986 Enclosed is the TMI-1 weekly status report from the NRC Resident Office at TMI-1 for the subject period. The NRC staff continued to monitor routine plant opera-tions 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 pre-vious week.
Subsequent inspection reports will address many of these topics in more detail.
Original Signed By:
Allen R. Blough, Chief Reactor Projects Section 1A Branch 1, DRP
Enclosure:
As stated 8609250056 860717
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PDR ADOCK 05000289 R
pop OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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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 i
Friends & Family of TMI H. Hucker A. Herman C. Wolfe J. Johnsrud P. Smith E. Harzler Concerned Mothers and Women D. Davenport Public Document Room I
Local Public Document Room bec w/ enclosure:
K. Abraham, RI P. Lohaus, RI W. Kane, RI i
H. Kister, RI R. Conte, RI (20 cys) l W. Baunack, RI l
R. Freudenberger, RI l
Region I Docket Room (w/ concurrences) l k
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OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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e ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD SEPTEMBER 5 - 12, 1986 1.
Plant Status As of 8:00 a.m. on September 12, 1986, TMI-1 was operating at 100 percent power and at normal reactor coolant temperature (579 F) and pressure (2155 3
psig).
I 2.
Facility Operations Summary The plant continued to operate at 130 percent during the reporting period.
No specific operational problems were identified.
During this period, Channel D reactor protection system calibration / check surveillance was completed. Also, reactor protection channels A, C, and D were re-cali-brated for the axial power shaping rod (APSR) withdrawal scheduled for Saturday, September 13, 1986.
3.
Items of Special Interest Reactor Coolant Pump Seal i
During the past several weeks, the "C" reactor coolant pump No. 1 seal return flow has gradually increased from a nominal 2 gallons per minute (gpm) to approximately 6.0 gpm. A new wider range flow instrument (3-10 gpm) was installed on the seal leakoff line to replace the narrow range instrument (0-6 gpm). After the reactor coolant " flush" on September 4-5, i
1986, the seal leakoff increased from 5.2 to 6.0 gpm. Since increased flow could indicate seal degradation, the licensee and the NRC inspectors are closely monitoring seal performance.
j Reactor Building Activity During the report period, reactor building (RB) radiation monitor RM-A-2 showed an increased activity in the building. The licensee discovered that pr.essurizer sampling valve CA-V-1 was leaking through the seal leak-off line discharging into the reactor building sump. By the end of the week, the seal leakoff line was capped, but a union in the line was found to have leaks.
The licensee and NRC inspectors are monitoring RB activity.
Rod Configuration Change The licensee has experienced higher plant reliability, and consequently higher fuel usage, than originally envisioned for the first year after restart.
Therefore, in accordance with License Amendment No.120, dated September 2, 1986, the licensee is making preparations to withdraw the axial power shaping rods out of the core on September 13, 1986. This will facilitate more complete use of available fuel to extend the current 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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Enclosure 2
fuel cycle to about 290 effective full power days. The licensee calibrated reactor protection channels A,C, and D to the new reactor power imbalance limits approved by NRR.
Reactor protection channel B will be re-calibrated prior to the APSR pull.
The licensee intends to decrease power to 60 per-cent during the APSR withdrawal and slowly increase power to 100 percent.
With this additional reactivity available, it is expected that full power operation could continue until mid-October 1986 at which time a plant power coastdown would occur until the start of the refueling outage currently scheduled to start November 1, 1986.
4.
Planned Public Meeting At 7:30 p.m. on Tuesday, September 23, 1986, members of NRC Region I man-agement 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 most recent Systematic Assessment of Licensee Performance (SALP) and NRC inspection programs at TMI-1.
The meeting will be similar in purpose to the one held in Middletown on April 24, 1986, to discuss an earlier SALP.
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.
Response
thus far indicates a relatively small meeting (i.e. 10-15 attendees).
5.
NRC Staff Activities During the Period During this report period, the NRC staff consisted of the senior resident inspector and three resident inspectors.
The NRC staff at TMI-1 was comprised of the following personnel during the period:
R. Conte, Senior Resident Inspector C. Hix, Secretary D. Johnson, Resident Inspector J. Rogers, Resident Inspector F. Young, Resident Inspector 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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