ML20210R877
| ML20210R877 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/23/1986 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Eisenhut D, Lyons J NRC |
| Shared Package | |
| ML20210R875 | List: |
| References | |
| FOIA-86-293 NUDOCS 8605200093 | |
| Download: ML20210R877 (2) | |
Text
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UNITED STATES
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E WASHINGTON, D. C. 20555
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April 23,1986 Docket No. 50-289 l
MEMORANDUM FOR:
H. Denton J. Knight A. Thadani O. Eisenhut G. Lainas H. Berkow J. Lyons T. Speis W. Travers H. Thompson B. Sheron C. Grimes.
F. Miraglia W. Russell W. Johnston R. Bernero G. Holahan C. Thomas T. Novak
'G.-Edison.
O. Parr F. Schroeder R. Weller W. Regan R. Houston C. McCracken V. Benaroya D. Crutchfield G. Knighton D. Vassallo THRU:
John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B FROM:
John Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
SUBJECT:
DAILY HIGHLIGHT TMI-1 INSPECTION OUTAGE The TMI-1' steam generator inspection outage was scheduled to end last Ilonday
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(April 21). The OTSG inspection is complete. NRR reviewed the preliminary inspection results and found them within expectations. Of the 1556 tubes inspected in the A - OTSG, two had free span indications with greater than 50% throughwall penetration.
In order to allow plant operation to the next refueling outage (December 1986), NRR issued a license amendment on April 18, 1986 which allowed operation of the OTSG with a primary side defect of up to 50% throughwall penetration under a restrictive set of conditions. The amendment is in hearing and a Final No Significant Hazards Consideration finding was made.
Separate from the steam generator inspection issues, an IE Ferfomance Appraisal Team (PAT) inspection raised questions concerning the equipment qualification program for generic items such as cables, terminal blocks, splices, and equipment seals. NRR supported a site meeting on April 18 to discuss these issues. The meeting resulted in all questions being resolved except for the issue of terminal blocks. The licensee was to conduct a site audit of
.teminal blocks and provide the results to Region I before achieving criticality.
The audit was conducted and the issue of terminal blocks was resolved to
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Region I's satisfaction. But while conducting the audit, the licensee found that the power cables going from terminal blocks to the containment air coolers were actually welding cable and not properly qualified power cables.
The terminal blocks are physically mounted on the fan coolers. The licensee C6052OOO93 860512 PDR FOIA WEISS86-293 PDR I
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-2 had assumed that the manufacturer lJoy) had qualified the entire component (ie. fan cooler) from the terminal block through the motor.
In fact, Joy had i
qualified everything but the power cables and that was left to the purchaser.
There are six power cables per cooling unit and three cooling units in containment. The licensee replaced all 18 power cables. Startup comenced late in the day on April 22.
Jo n Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B u
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