ML20195C050
| ML20195C050 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/18/1988 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8811020325 | |
| Download: ML20195C050 (5) | |
Text
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OCT 181988 Docket Nos. 50-289; 50-320 MEMORANDUM FOR:
Lee H. Bettenhausen, Chief, Projects Branch No. 1, Division of Reactor Projects FROM:
Curtis J. Cowgill, Chuf, Heactor Projects Section 1A, DRP
SUBJECT:
THI STATUS REPC'dT FOR THE PERIOD SEPTEMBER 10 - OCTOBER 7,1988
. Enclosed is the TMI Resident Office monthly status report, which covers both TMI-1 and TMI-2. This report is to provide NRC management and the public with highlights of significant events at THI-1 and TMI-2 from an NRC regulatory perspective.
ORIGINAL SIGNED BY Curtis J. Cowgill, Chief Reactor Projects Section IA 4
Enclosure:
As Stated cc w/ enc 1:
S. Varga, NRR J. Stolz, NRR R. Hernan, NRR M. Masnik, NRR T. Martin, E00 J. Partlow, NRR J. Roe, NRR T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania Governor's Office of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI
- 0. Davenport L. Orey E. Harzler A. Herman H. Hucker J. Johnsrod P. Smith H. Spinel'11 C. Wolfe' Concerned Mothers and Women Public Document Room local Public Document Room 0FFICIAL RECORD COPY TMI 1&2 MONTHLY STATUS REPORT 5 0001.0.0 I
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OCT 181988 l.
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M. Miller, RI 1(2 copies)
K. Abraham, RI l
W. Kane, RI j
i R. Conte, RI (8 copies)
.s W. Baunack, RI C. Cowgill, RI J. Wechselberger, RI J. Bell, NRR Region I Docket Room (w/ concurrences)
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10/0/88 0FFICIAL RECORD COPY TM1 1&2 HONTHLY STATUS REPOR1 -
0002.0,0 11/29/80
o ENCLOSURE TMI-1 AND TMI-2 STATUS REPORT FOR THE PERIOD SEPTEMBER 10 - OCTOBER 7, 1988 1.
THI-1 a.
Facility Operations Summary During the report portod, the licensee decided to shut down the reactor to troubleshoot and repair the cause of a high flow in the No. 1 seal leak-off line of a reactor coolant pump. On September 17, 1988, the plant was taken off itne, repairs were completed, and power operations were ruumed on September 26, 1988. As of October 7, 1988, the THI-1 reactor was at 100 percent power with Tave at 579 F and Reactor Coolant System (RCS) pressure at 2155 psig.
b.
Items of Special Interest Reactor Coolant Pump Seal On Septenber 17, 1988, the licensee decided to shut down TMI-1 to iden-tify the cause of a high flow in the No. I seal leak-off line for the "D" reactor coolant pump (RCP). On September 15, 1988, the "0" RCP No.
1 seal leak-cff started to increase from 2-4 gpm (normal readings) to 4-5 gpm.
By September 17, 1988, the flow was 6-8 gpm.
The licensee suspected a probh'n with the No.1 seal itself; and, upon discussing the problem of the seal package with the vendor (Westinghouse), they decided to shut down for repairs.
The licensee had previously replaced this seal package on all four RCP's during the refueling outage that ended about eight weeks ago. The other three RCP's had normal readings from the No I seal leak-off; and, over-all, the unidentified Rea.ctor Coolant System (RCS) leak rate remained significantly less than the 1 gpm technical specification limit.
Upon disassembling the No. I seal package, two damaged 0-rings were found.
These are considered to be the cause of the increased leak-off flow.
The damage to the 0-rings was attributed to improper installation during the refueling outage.
Upon completing repairs and follow-up testing the "0" RCP, the licensee observed an increase in shaft vibration and realigned the pump / motor assembly.
The indicated vibration still remains a little higher (10-15 mils) in the "0" RCP than in the other three RCP's (6-8 mils). However, this indicated vibration has not affected pump performance, nor has it affected seal leak-off flow.
The licensee is evaluating the cause of the vibration restings to determine if they are the result of a malfunc-tioning vibratioi sensor or indicate true vibrations.
OFFICIAL RECORD COPY TMI 1&2 MONTHLY STATUS REPORT -
0003.0.0 11/29/80
Enclosure 2
High Heat-Up Rate On September 29, 1988, upon reviewing computer data gathered during plant heat-up operations, the licensee determined that the technical specifi-cation limit for RCS heat-up rate had been exceeded.
This occurred when the plant was preparing to resume power operations following a one-week outage'to repair a RCP seal.
Based on this review, the actual heat-up rate, using RCP's as the heat source, was in the range of 55-61 F/ hour.
These values exceeded the heat-up rate limit of 50 F/ hour as required by the technical specifications. A preliminary engineering assessment by the licensee indicates that the primary system did not have signifi-cant thermal stresses as a result of exceeding this limit.
This event will be detailed in a future NRC inspection report. Also, a Licensee Event Report will be issued at a later date.
2.
THI-2 a.
Facility Activities Summary During this reporting period, cutting of the grid forging continued.
The grid forging is the third of five plates that comprise the Lower Core Support Assembly (LCSA) that is to be recoved to provide access for de-fueling the lower head of the reactor vessel. Decontamination of plant surfaces and systems continues.
Several plant areas have been isolated from routine use and placed in an interim status as meeting Post-Defuel-ing Monitored Storage (PDMS) conditions set forth in the licensee's Safety Analysis Report (SAR) submitted to the NRC staff on August 16, 1988. Other plant areas are scheduled for verification to determine if they meet the interim PDMS isolation criteria set by the licensee but not yet approved by NRC.
b.
Items of Special Interest Defueling Operations Cutting of the grid forging continued at a modest pace.
Difficulty is still being experienced with the plasma are cutting equipment.
The torch tips have experienced several failures that require the torches to be re-built.
The X-Y bridge has been removed from the vessel for repairs of various motors and positioning eqaipment and reinstalled. Also, it required decontamination prior to work on the bridge components.
To date, all of the in-core guide tubes have been cut to permit easier access to e.uts on the grid forging itself. All of the forging support posts have also been cut and removed from the top of the forging.
Of the seventy-seven cuts requirer to remove the forging, fifty-five have d
been attempted or completed.
Of these, only seven have been verified as totally complete.
Some will require recutting as a result of uneven cuts or incomplete penetration during initial cutting.
OFFICIAL RECORD COPY TMI 1&2 MONTHLY STATUS REPORT -
0004.0.0 11/29/80
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Enclosure 3
The licensee completed surveys of two plant areas to determine that quantities of fuel existing in these areas warrant no additional defuel-ing.
These areas are the reactor vessel plenum assembly and the letdown coolers. The results indicate that no further defueling in these areas is required and that the quantities of fuel in these areas is negligible.
The post-defueling survey reports for these two areas were transmitted to the NRC in a letter dated September 30, 1988. Additional surveys for other areas will be reported as they are completed, for such areas as the steam generators and various sections of Reactor Coolant System (RCS) piping.
Tte compilation of these reports will form part of the basis l
for the final assessment of completion of defueling efforts.
No shipments of casks containing core debris was N de during this report-
)
ing period.
Decontamination / Dose Reduction Activities Scabbling, steam cleaning, and hands-on decontamination continue in the auxiliary and fuel handling buildings. To date, the majority of the 143 cubicles have been decontaminated to end point criteria.
The remaining cubicles contain contaninated plant systems that first must be cleaned before the cubicle is decontaminated.
Flushes of these systems are being performed to lower dose rates in these cubicles.
The licensee continues to assess specific plant areas for placement of these areas into an in-terim PDMS condition as defined by their SAR.
3.
NRC Staff Activities The NRC staff assigned on site consisted of the senior resident inspector, three resident inspectors, a project manager (for TMI-2), and a secretary.
1 During this period, Region I issued the following inspection reports.
TMI-1J50-289) l 88-22 on October 4, 1988, on the post-modification testing program.
No violations were identified.
(MI-2 (50-320) 88-13 on October 5, 1988, on TMI-2 defueling/decontaminataon activities.
No violations were identified.
4.
public Meetings On October 25, 1988, the members of the Advisory Panel on the decontamination of TMI-2 will meet with the NRC Commissioners.
The meeting is scheduled for 11:00 a.m. in the NRC building at 11555 Rockville Pike in Rockville, Maryland.
Members of the public may attend the meeting.
OFFICIAL RECORD COPY TMI 1&2 MONTHLY STATUS REPORT -
0005.0.0 11/29/80
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