ML19305B163
| ML19305B163 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/27/1980 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003190249 | |
| Download: ML19305B163 (8) | |
Text
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Meeting Sunnary for Point Beach February 27, 1980 Docket Files E C PDR Mr. Bruce Churchill, Esquire ORB Reading Shaw, Pittman, Potts and Tr:we ri:ge ER di"9 1800 M Street, N.W.
Denton Washington, D. C.
20036 D.
s nhut DocumengDepargent R. Tedesco University of Wisconsin 18 Stevens Point Library Stevens Point, Wisconsin SLEl W. Gammill L. Shao Mr. Glenn A. Reed, Manager J. Miller Nuclear Operations R. Vollmer Wisconsin Electric Power Co:::a.ny Point Beach Nuclear Plant T. J. Carter 6610 Nuclear Road A. Schwencer Two Rivers, Wisconsin 5424' D. Ziemann P. Check G. Lainas D. Crutchfield
- 8. Grimes T. Ippolito R. Reia V. Noonan G. Knighton D. Brinkman Project Manager OELD OI&E (3)
C. Parrish/P. Kreutzer i
ACRS (16)
NRC Participants NSIC 4
4 ERA' ensee Short Service List i
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February 27, 1980 Docket No. 50-266 LICENSEE:
Wisconsin Electric Power Company FACILITY:
Point Beach Nuclear Plant, Unit No. 1
SUMMARY
OF MEETING HELD ON FEBRUARY 6, 1980 TO DISCUSS UPCOMING STEAM GENERATOR TUBE INSPECTION On February 6, 1980, the NRC staff met with representatives of Wisconsin Electric Power Company to discuss the forthcoming steam generator tube inspec-tion required by the NRC Confirmatory Order of November 30, 1979.
The Order requires that the licensee submit for NRC review their inspection plans.
The Order requires a tube inspection within 60 EFPD following the issuance of the Order. A list of attendees is contained in Attachment 1.
Highlights of the meeting are summarized below.
A steam generator (SG) moisture carryover test has recently been conducted on Unit 1 to see if the lower temperature pressure operation has had any affect on moisture separator performance. The test was conducted at 390 MWe (78% power) at an SG pressure of 600 psi, and used Na-24 as the tracer chemical.
Preliminary results indicate carryover is less than 0.1%, which is the same carryover measured previously at full load and normal Tav.
Therefore, lower pressure operation (low Tav) has not affected moisture separator performance.
The test result is well below the design value 0.25%.
The Unit 2 shutdown (refueling) has been put off two weeks until the end of March, since the SG inspection required on Unit 1 will fall due and is scheduled to begin on February 29, and WEPC0 is trying to avoid both units being out of service at the same time. WEPC0 visualizes a nominal 10-day outage for SG inspection, assuming all goes well.
We stated that we planned to send one or more NRC technical personnel to the site in order to expedite our evaluation of the inspection results.
Present primary-to-secondary leakage is about 30 gpd, as measured by the condenser off gas monitor. Assuming this stays constant at this low level, WEPC0 plans to shut down the unit on February 29 and conduct an inspection similar to the one conducted in December.
All tubes in an area bounded by previous crevice defect problems would be examined.
This amounts to 950 tubes in A and 850 in B - about 30% of the unplugged tubes.
See Attachment 2.
In addition, 20 randomly selected tubes in other areas would be examined in each SG.
The vertical extent of the inspection will include the tube sheet up to and including the first support plate.
Multi-frequency ECT will be used.
)
4 Meeting Summary February 27, 1980 No tube removal of any previously plugged tubes is planned, e.g., the 5 tubes plugged with defects at or above the tube sheet plugged in October 1979.
However, if they do see any defects at or near the top of the tube sheet, WEPC0 would remove one such tube for metallurgical examination.
Ooses due to tube removal have been 40-50 man-res/ tube by dosimeter readings, and about 22 man-rem / tube based on TLD readings.
2000/800 psi testing is planned as before, and further crevice flushing will be done if time allows.
WEPCO presented four future plans of action or options, depending on what is found during the inspection:
1.
Assuming no defects fcund.
Return to power (at 2000 psia).
Would consider increasing Tav somewhat.
Continue with additional Confirmatory Order restrictions except for the 30/60 day inspections and tests.
Operate until fall shutdown.
2.
Assuming defects are found within tube sheet.
Plug all tubes with any ECT indications.
no increase in Tav.
Continue with Confirmatory Order restrictions except for 30/60 day inspections and tests.
3.
Assuming defects are found near top of tube sheet.
Pull one tube.
Plug all others with any defects.
Continue with Order restrictions, except 30 EFPD test.
Plan to do ECT in 60 EFPD unless metallurgical exam of removed tube indicates otherwise.
no increase in Tav until pulled tube has been evaluated.
l l
l
Meeting Summary February 27, 1980 4.
Assuming all defects are greater than 1" above tube sheet.
(i.e. thinning / cracking similar to earlier experience)
Use Tech. Spec. plugging limit of 40%.
continue to operate as in 1. above.
For all options 1-4 above, an ECT would be conducted in November 1980.
Following a staff caucus, we made the following remarks:
1.
The timing and extent of the next inspection will have to depend on the results of the upcoming inspection. We added, however, that we were not optimistic that a continuous run until November would be justified.
2.
The tube sample size outside of the area of historic crevice problems is too small (20 tubes), and should be at least 3%, consistent with the sampling program in Reg. Guide 1.83.
The sampling program should provide for a logical progression of sample size in the event defective tubes are found.
3.
One of the 5 tubes with defects at or above the top of the tul'e sheet (plugged in October 1979) should be removed for examinat.'on unless this inspection reveals an unplugged tube with defects in this area.
WEPC0 agreed with 1 and 2 above, and added that the inspection program will have to remain flexible depending on the results found. Also, the next inspection should be determined then.
WEPC0 did not agree with pulling a plugged tube at this outage. They stated that:
a.
A good technical basis exists to show that these tubes did not have IGA.
b.
This has never been done before (removing an explosively plugged tube); there are some questions about how it could be done; more time is needed to study the problem; a mock-up and test should be done ahead of time; the timing is too tight to do now.
WEPC0 stated that they could be ready to and would pull one of these 5 plugged tubes by the November 1980 outage, and that t'ey do plan to pull an unplugged tube if defects at the tube sheet surface are discovered in the upcoming inspection.
5
r
.-s Meeting Summary February 27, 1980 We stated our position that one of these 5 tubes should be recoved, and unless convinced otherwise, it should be done at this outage.
/
Y f fI l!)hk C. M. Trame11 Operating Reactors Branch #1 Division of Operating Reactors Attachments
- 1. List of Attendees
- 2. Tube sheet maps I
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3' List of Attendees Steam Generator Meeting February 6, 1980 NRC W
C. Trammell W. D. Fletcher B. D. Liaw R. Bagley J. Strosnider C. Hirst E. Murphy W. White D. liuang L. Frank P. Boehnert (ACRS staff)
W. (Joe) Collins J. Weeks (BNL)
Wisconsin Electric Power S. Burstein R. Menning C. W. Fay D. Porter G. Frieling Shaw, Pittman, Potts & Trowbridge G. Charnoff J. O'Neill 4
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