ML20092P764
| ML20092P764 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/05/1984 |
| From: | Bauser D METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE |
| To: | Linenberger G, Smith I, Wolfe S Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8407090350 | |
| Download: ML20092P764 (8) | |
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July 5, 1984 (202) 822-1215 Administrative Judges Ivan W.
Smith, Chairman Sheldon J. Wolfe Gustave A.
Linenberger, Jr.
Atomic Safety and Licensing Board U.S.
Nuclear Regulatory Commission Washington, D.
C.
20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1)
Docket No. 50-289 (Restart - Remand)
Dear Chairman Smith and Administrative Judges Wolfe and Linenberger:
During the June 28, 1984 prehearing conference, the Li-l censing Board requested that Licensee's counsel provide it with a current status report on the readiness of TMI-l to restart.
Tr. 27,308 (Chairman Smith).
Based on a report today from Mr.
Henry D.
Hukill, Vice Presidant of TMI-1, Licensee's counsel anticipates that TMI-l could be physically ready to operate by the middle of this month.
Licensee is continuing to conduct long-range maintenance and modification work at TMI-1.
Once restart authorization is received, Licensee anticipates that it would take 7 to 10 days to place this work in a status to per-mit plant operation.
The mid-July date is based on the need for 7 to 10 days of lead time.
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8407090350 840705 PDR ADOCK 05000289 G
SHAw, PITTMAN POTTs & TROWORIDGE
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..o, o,c.o.tco..o..,,o~s Ivan W.
Smith, Esquire Sheldon J. Wolfe, Esquire Mr. Gustave A.
Linenberger, Jr.
July 5, 1984 Page 2 For the information of the Board and the parties, Licensee encloses two letters sent by Licensee to the NRC Staff, dated June 27 and July 3, 1984, respectively, which report on the steam generator leakage recently detected at TMI-1.
Sincerely, b Mk h Deborah B.
Bauser Counsel for Licensee DBB:jah Enclosure cc:
Service List d
e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Commission In the Matter of
)
)
METROPOLITAN EDISON COMPANY
)
Docket No. 50-289 SP
)
(Three Mile Island Nuclear
)
(Restart - Management Phase)
Station, Unit No. 1)
)
SERVICE LIST Nunzio J.
Palladino, Chairman Administrative Judge U.S. Nuclear Regulatory Commission John H.
Buck Washington, D.C.
20555 Atomic Safety & Licensing Appeal Board Victor Gilinsky, Commissioner U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Washington, D.C.
20555 Administrative Judge Thomas M.
Roberts, Commissioner Christine N. Kohl U.S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Washington,
D.C.
20555 Board U.S. Nuclear Regulatory Commission James K. Asselstine, Commissioner Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Administrative Judge Ivan W.
Smith, Chairman Frederick Bernthal, Commissioner Atomic Safety & Licensing Board U.S. Nuclear Regulatory Commission U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Washington, D.C.
20555 Administrative Judge Administrative Judge Gary J. Edles, Chairman Sheldon J. Wolfe Atomic Safety & Licensing Appeal Atomic Safety & Licensing Board Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington,'D.C.
20555 Washington, D.C.
20555 n
Administrative Judge Mr. Henry D. Hukill Gustave A. Linenberger, Jr.
Vice President Atomic Safety & Licensing Board GPU Nuclear Corporation U.S. Nuclear Regulatory Commission P.O.
Box 480 Washington, D.C.
20555 Middletown, PA 17057 Docketing and Service Section (3)
Mr. and Mrs. Norman Aamodt Office of the Secretary R.D.
5 U.S.
Nuclear Regulatory Commission Coatesville, PA 19320 Washington, D.C.
20555 Ms. Louise Bradford Atomic Safety & Licensing Board TMI ALERT Panel 1011 Green Street U.S. Nuclear Regulatory Commission Harrisburg, PA 17102 Washington, D.C.
20555 Joanne Doroshow, Esquire Atomic Safety & Licensing Appeal The Cnristic Institute Board Panel 1324 North Capitol Street U.S. Nuclear Regulatory Commission Washington, D.C.
20002 Washington, D.C.
20555 Lynne Bernabei, Esq.
G vernment Accountability Jack R.
Goldberg, Esq. (4)
Off ce of the Executive Legal 15 5 Co ecticut Avenue Washington, D.C.
20009 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Ellyn R.
Weiss, Esq.
Harmon, Weiss & Jordan Thomas Y.
Au, Esq.
2001 S Street, N.W.,
Suite 430 Office of Chief Counsel Washington, D.C.
20009 Department of Environmental Resources Michael F.
McBride, Esq.
505 Executive House LeBoeuf, Lamb, Leiby & MacRae P.O. Box 2357 1333 New Hampshire Avenue, N.W.
Harrisburg, PA 17120 Suite 1100 Washington, D.C.
20036 Michael W.
Maupin, Esq.
Hunton & Williams 707 East Main Street P.O.
Box 1535 Richmond, VA 23212 l
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opu Neeseer carperessii~
Poet Office Sox 45 l
Route 441 South
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Middletcwn, Pennsylvania 170674191 in r t
717 944 7e21
,"a TELEX 44 2388 Writer's Direct Olet Num0er.
5211-84-2161 June 27, 1984 l
Office of Nuclear Reactor Regulations John F. Stolz Chief Attn:
Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Connission Washington. 0.C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. OPR-50 l
Docket No. 50-289 TMI-1 Steam Generator Leakage Testing This letter is to provide you with additional information now availa the condition of the TMI-1 steam generators.
As you are aware, secondary chemistry data are routinely monit evaluated for trends at TMI-1 as part of our steam generato d to tritium concentrations, as well as slight decreases in pH, were foun monitoring program.
The leak indicate a small increase in leakage in the "B" steri generator.
RCS rate was detennined O be approximately 1.5 gph under the curren Although a rough projection to hot RCS conditions (about300psig).
conditions indicates a primary-(to-secondary leak rate belo administrative limit of 7 gphgph), additional investigations of conducted.
Bubble tests of tubing above approximately the elehenth tube One tube (80-45) have been conducted in the "A" and "5" steam generators.
Tube in the "3" steam generator was identified as bubbling significantly.
I By 80-45 has bubbled slightly and intermittantly during past bubble t using stoppers 6t various levels in the bubbling tube, it has been determined that primary coolant can pass through a crack very i
upper tube sheet, then down through the tight tube-to-tumsheet 1
l GPU Nuclear Corporetion le a subsidiary of the General Pub 3
___ tek
., JW; Jahr Some leakage via comprising thaeet pint and into the secondary system.
l tutw-to-tubesheet such pathways has a> ways been predicted for the m ill be joints.
plugged before return to service.
fibroscope.
Additional inspection of the leaking joint is planned using a d to identify Drip tests of the "B" lower tubesheet area are also schedule f the steam significant leakage contributors, if any, in the lower t from lower in planned as confimation that feakage is past the joint, no h
generator. While the ECT equipment is in place, a sample population J
All these tests are scheduled for completion l
the tube.
tubes will also be monitored.
this week or early next week.
th In the course of performing the highly sensitive bubble testin l
istble,very tubes, 6 plugged and 8 unplugged were seen to have faint y vSe i,
h ity "A" 0TSS (which had no evidence of a leakage increase based slight bubble formation.
Stopper tests cf the unplugged bubbling tubes indicated This type of
'i monitoring).
leakage past the tube-to-tubesheet joint in all cases.
t ble and bubbling has been seen in past tests, and is considered to be a nsion and the not unexpected for mechanical joints such as the kinetic expaN l observation' mechanical rolled plug.these tubes but their locations have been no during any future bubble tests.
d SPU has Subject to review as further testing and examinations are com nerators concluded that earlier evaluations of acceptability of the steam g for service are unaffected by the additional information.
I Sincerely.
Director TMI-1 3
HDH/n1G/CW5/mle cc:
R. Conte C. McCracken H. Silver i
GPU Nuclear Corporation a
- h. T + -
m;. f gg gg Pest Office Sox 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct olal NumDer:
5211-84-2169 M y 3, 1984 Office of Nuclear Reactor Regulations Attn:
John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Comission Washington, D.C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. OPR-50 Docket No. 50-289 TMI-1 Steam Generator Inspection In my letter of June 27, 1984, I described additional testing being conducted to investigate a small leakage increase in the "B" steam generator.
This testing is now complete.
As reported previously, bubble testing identified only one tube as bubbling significantly, tube 80-45 in OTSG "B".
A fibrescope was placed in tube 80-45 with the secondary pressurized.
Water could be seen coming through a crack at a point above the kinetic expansion joint qualified length, confirming that the leakage path was between the tube and tubesheet.
This tube has been plugged.
Drip tests of the "B" steam generator identified nine plugs in the lower tubesheet, and three tubes that were dripping very slightly.
The three tubes (which included 80-45) had all been previously identified by the bubble test.
Eight of the slightly dripping plugs were rolled plugs.
Slight dripping or wetness is acceptable and not unexpected for this type of joint. A third plug was an explosively welded plug, which was repaired by placing a new plug below it.
2 Eddy current testing using a differential probe has now been conducted for all tubes identified as bubbling, all tubes with less than 40 percent through wall indications left in service in the "B" generator, and approximately seventy other tubes in the "B" generator which are part of the supplemental ECT sample population.
No new eddy current indications were found.
No known indications were found to have grown.
No tubes that were bubbling have any ECT indications below the kinetic expansion joint, confiruing that bubbling is past the joint in all cases.
No additional ECT is planned.
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
6 One very low voltage ECT signal was noted by data analysts in tube 70-8 in the "B" generator, six inches above the lower face of the upper tube sheet.
A review of previous inspections showed a signal of the same shape and voltage at that location for both pre-and post-expansion inspections, indicating that this signal does not represent a new or growing defect.
This size and type of signal, which is very close to the threshold of detectability of the probe in use, cannot reliably be distinguished from background using this probe.
This threshold of detectability has been considered and found acceptable in GPU's evaluation of the steam generators. When such small signals are identified, additional inspections using the more sensitive 8x1 probe are normally conducted to determine whether the anomalous signal represents an ECT indication or simply part of background.
The additional time necessary to prepare equipment and to carry out this inspection is not considered warrented for one tube.
Rather than leave the steam generators open to oxygen for the additional time period this tube will be plugged as a precautionary measure.
In addition to the two tubes described above, GPU plans to plug one additional tube in the "B" generator, tube 79-41.
This is one of the slightly bubbling tubes identified in my June 27, 1984 letter. Although it bubbled so slightly that the water surface above remained undisturbed, bubble fomation at the tube surface appeared somewhat more frequent than for other slight bubblers.
In the interest of maintaining secondary activity levels as low as possible, this tube is being plugged.
GPU's investigations of the small leakage increase are now complete, and plugging is complete. The steam generators will be closed and returned to service this week. All evidence continues to support the conclusions drawn in GPU's submittals on the acceptability of the steam generators for return to service.
Baseline leakage will be re-established, as required after plugging, prior to criticality.
Sincerely, ill Vice President - TMI-1 HDH/MJG/ RAS /mle cc:
R. Conte J. Van Vliet l