ML20246L725
| ML20246L725 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/26/1989 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8905180388 | |
| Download: ML20246L725 (5) | |
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1 APR 2 61989 Docket Nos. 50-289; 50-320 MEMORANDUM FOR:
Jacque P. Durr, Acting Chief, Projects Branch No. 1, Division of Reactor Projects FROM:
Curtis J. Cowgill, Chief, Reactor Projects Section 1A
SUBJECT:
TMI STATUS REPORT FOR THE PERIOD MARCH 19 - APRIL 15, 1989 Enclosed is the TMI Resident Of fice 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 TMI-1 and TMI-2 from an NRC regulatory per-
- spective, ggg gggg gy Curtis J. Cowgill, Chief Reactor Projects Section 1A
Enclosure:
As Stated cc w/ enclosure:
S. Varga, NRR J. Stolz, NRR R. Hernan, NRR M. Masnik, NRR T. Martin, EDO J. Partlow, NRR J. Roe, NRR L. Whitney, NRR T. Gerusky, BRP/ DER, Commonwealth of Penns3 1/ania Governor's Office of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI D. Davenport L. Drey E. Harzler A. Herman H. Hucker J. Johnsrud P. Smith H. Spinelli C. Wolfe Concerned Mothers and Women Public Document Room Local Public Document Room h
0FFICIAL RECORD COPY TMI STATUS REPORT - 0001.0.0 11/29/80 Iy 8905180388 890426 PDR ADOCK 05000289 p
PNV
7_
Jacque P. Durr 2
APR 2 61989 bec w/ enclosure:
K. Abraham, RI (2 copies)
M. Miller, RI W. Kane, RI W. Baunack, RI C. Cowgill, RI J. Bell, NRR Region I Docket Room (w/ concurrences)
F. Young, RI (3 copies)
D. Johnson T. Moslak i
c) J RI:DRP RI:DRP
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} CCowgill if J
4/20/89 rr?
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ENCLOSURE TMI-1 AND TMI-2 STATUS REPORT FOR THE PERIOD MARCH 19 - APRIL 15, 1989 1.
TMI-1 Facility Operations Summary _
a.
During the report period, the licensee operated the plant at nearly full power. A brief power reduction from 100% to about 80% occurred for about one hour on April 2, 1989 as the result of a failure of a heater drain pump.
No challenges to plant safety systems occurred during this period.
b.
Items of Special Interest Heater Drain Pump Failure On Sunday, April 2, 1989, the bearing assembly on one of two operat-ing heater drain pumps failed resulting in a shearing of the pump shaft and damage to the pump casing and motor shaft. When the pump failed, power was reduced until a standby heater drain pump was placed on line.
Subsequently, full power operations were resumed a short time later.
SALP Management Meeting On April 10, 1989, the NRC staff met with GPU Nuclear management to discuss the results of the Systematic Assessment of Licensee Per-formance (SALP) Report (50-289/87-99).
The SALP report documented the results of the NRC Region I SALP Board that met on March 2, 1989, to assess the overall performance of Unit 1 for the period November 1,1987 through January 15, 1989.
2.
TMI-2 a.
Facility Activities Summary On Friday, March 31, 1989, defueling crews completed cutting the central portion of the Elliptical Flow Distributor (EFD) into 26 pieces.
Eventual removal of these pieces will provide access to remove core debris from the reactor vessel's lower head.
A piece of the EFD was lifted to examine the condition of three in-core instrument guide tubes underneath.
Of the three tubes, two were melted and one was intact.
Examinations will continue to be made of other core internals and vessel material to assess how well they withstood conditions during the accident.
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Enclosure 2
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Following cutting of the EFD, a series of vertical cuts were made in j
the core baffle plates to facilitate their removal. Before the 1
baffle plates are taken out, the pieces of the EFD will be lifted out, then the deoris at the bottom of the reactor vessel will be re-moved. After this rubble is removed, the baffle plates will be un-bolted with a hydraulic wrench and taken out.
This will permit re-moval of debris from the annular region behind the baffle plates.
3.
NRC Staff Activities i
The NRC staff assigned on site at the beginning of the period consisted of an acting senior resident inspector, a resident inspector, and a project manager for TMI-2.
A newly selected senior resident inspector, Mr. Francis Young, reported to the site on April 2, 1989.
a.
Inspection Reports During this period, Region I issued the following inspection reports.
TMI-1 Inspection Report No. 50-289/89-01 on March 28, 1989, addressing routine inspections of operations activities.
TMI-1 Systematic Assessment of Licensee Performance (SALP) Re-port No. 50-289/89-99, on April 3, 1989 addressing the overall performance of Unit 1 for the period from November 1,1987 to January 15, 1989.
b.
Proposal to Dispose of Accident - Generated Water The public hearing on evaporation of accident generated water (AGW) at Three Mile Island Unit 2 by the Atomic Safety and Licensing Board (ASLB) concluded on Tuesday, November 15, 1988.
Contentions liti-gated were the analysis of the "no action alternative," characterize-tion of the AGW, evaluations of potential release of micro-organisms, and the health effects of tritium. The ASLB ruled in favor of the licensee on February 3, 1989.
The joint interveners requested a stay and filed an intent to appeal the decision to the Atomic Safety and i
Licensing Appeal Board (ASLAB) on February 20, 1989.
On Tuesday, April 4, 1989 the ASLAB denied the request for a stay.
On Thursday April 13 the NRC Commissioners, by a 4-0 vote, affirmed the ASLB ruling. The ASLB ruling is now immediately effective. The l
operation of the AGW disposal system is now dependent on resolution of detailed technical issues with the NRC staff and construction and start-up testing by the licensee.
s L
O Enclosure 3
Safety Evaluation for Upper Core Support Assembly Defueling c.
On April a,1989 the NRC staff issued an approval letter and Safety Evaluation (SE) for Upper Core Support Assembly (UCSA) defueling.
This approval allows the licensee to remove baffle plate sections of.
the UCSA. The SE evaluated the licensee's load handling safety pro-gram and the potential consequences of load drops involving the j
baffle plate sections.
d.
Public Meetings The Advisory Panel for the Decontamination of Three Mile Island Unit 2 met on Thursday, April 13, 1989.
The panel was briefed on the status of the AGW disposal and the status of the Post Defueling Moni-tored Storage (PDMS) environmental evaluation by the NRC staff The GPUN staff briefed the panel on the status of cleanup activities, the offsite radiation monitoring program, and cleanup scheduling and funding. The next meeting of the Advisory Panel is tentatively scheduled for Thursday, July 27, 1989 at the Holiday Inn in Center City, Harrisburg.
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