ML19296D328
| ML19296D328 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/26/1980 |
| From: | Charnoff G SHAW, PITTMAN, POTTS & TROWBRIDGE |
| To: | Trammell C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296D329 | List: |
| References | |
| NUDOCS 8003030501 | |
| Download: ML19296D328 (2) | |
Text
.
SHAW, PITTMAN, PoTTs & TRoWBRIDGE 18 0 0 M STR E ET, N. W.
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J. PATetC E MsC n ET SETM M.MOQOa$leN saMES TMO*ea5 LENnamT S M EILA E. aceCA F F E NTY STEVEN L. ne E if1 E m DEugSA A.agDQway DEAM O.avuCR R E N N ETM J. Mau?M AN JQMN ENGEL DAVIO kAWWENCE pelLLEN February 26, 1980
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Mr. Charles M. Trammell Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wash,j.ngton, D..C.
20555 Re:
Wisconsin Electric Power Company Point Beach Nuclear Plant, Unit 1 Docket 50-266
Dear Mr. Trammell:
Pursuant to Paragraph IV(1) (b) of the Confirmatory Order for Modification of License, issued November 30, 1979, there is enclosed a copy of the eddy current program which will be conducted at Point Beach nuclear plant, Unit 1, at the shutdown scheduled for the purpose of conducting the test required under Section IV(1) (b).
e cere l
N Cha/
i rnoff f
er Counsel for Wisconsin Electric Power Company cc:
Service List 8003030 I
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION In the Matter of
)
)
WISCONSIN ELECTRIC POWER COMPANY
)
Docket 50-266
)
(Point Beach Nuclear Plant,
)
(Modification of Unit 1)
)
License)
SERVICE LIST Mr. Darrell G. Eisenhut Kathleen M. Falk, Esquire Office of Nuclear Reactor Regulation Wisconsin's Environmental U. S. Nuclear Regulatory Commission Decade, Inc.
Washington, D. C.
20555 114 East Mifflin Street Madison, Wisconsin 53703 Mr. Samuel J. Chilk Secretary Docketing and Service Section U. S. Nuclear Regulatory Commission Office of the Secretary Wasington, D. C.
20555 U.
S. Nuclear Regulatory Commission Marian E. Moe, Esquire Washington, D. C.
20555 Office of General Counsel U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Edwin J. Reis, Esquire Office of Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Lewis T. Mittness Executive Secretary Public Service Commission of Wisconsin Hill Farms State Office Building 4802 Sheboygan Avenue Madison, Wisconsin 53702 C. F. Riederer, P. E.
Public Service Commission of Wisconsin Hill Farms State Office Building 4802 Sheboygan Avenue Madison, Wisconsin 53702 0
/ /
S' 030 G,/'
February 22, 1980
^
Mr. Sol Burstein:
POINT BEACH NUCLEAR PLANT UNIT 1 STEAM GENERATOR INSPECTION - MARCH 1980 On February 6, Wisconsin Electric met with the NRC staff in Bethesda to review the tests and examinations to be performed as required by paragraph IV 1 b of the Confirmatory Order for Modification of License issued November 30, 1979.
Based on the discussions at that meeting, the following are the plans for the tests and inspections to be conducted during the outage scheduled to begin on February 29, 1980:
1.
A 2000 psid primary-to-secondary hydrostatic test during unit shutdown.
To do a 2000 psid test will require increasing primary pressure to 2250 psig for the duration of the test.
2.
A 800 psid secondary-to-primary hydrostatic test.
3.
A multifrequency eddy current examination of (see attached tubesheet maps) :
(a)
The hot leg side, up through the first support plate, of approximately 950 tubes in the' "A" steam generator and 850 tubes in the "B" steam generator.
This inspection " bounds" the areas where crevice corrosion has been found in the past including at least one tube beyond the location of any tube previously plugged due to crevice corrosion.
If any crevice corrosion is determined on the boundary of these areas, the inspection will be expanded to a point where no crevice defects are found in tubes bounding the areas.
(b)
A random sampling of tubes outside the bounded area will be examined on the hot leg side up to the first support plate.
During the February 6 meeting, NE proposed to do 20 tubes in each steam generator, similar to the December 1980 inspection-however, the NRC suggested a larger sampling of 3%
of the unplugged tubes outside the bounded area.
Therefore, present plans are to do approximately 75 tubes in each steam generator as shown on the attached diagrams.
Any defects found within the tubesheet crevice up to one inch above the top of the tubesheet will be plugged.
Any defects found above this point will be plugged in accordance with present Technical Specifications if the defect is determined to be 40% or more of the nominal tube wall thickness..
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Mr. Sol Burstein February 22, 1980 (c)
An inspection of the cold leg will be conducted from the hot leg on 20 selected peripheral tubes in each steam generator.
As noted above, this is a special inspection in accordance with the Confirmatory Order and not an inspection required by the Technical Specifications.
Therefore, we are not planning on following the provisions of Table 15.4.2-1 of the Technical Specifications for expanding the sample if crevice defects are found.
However, it is recognized that paragraph IV.6 of the Confirmatory Order requires that the NRC agree that the results of the tests are acceptable.
Therefore, we intend to keep the NRC staff closely informed of the results during the examinations and to invite them to be present at Point Beach to facilitate their review.
Based on the findings, it is possible that some additional testing may be performed beyond the plans outlined above.
As you know, the NRC has expressed some cons arn that the five tubes plugged in November which had defects near or slightly above the top of the tubesheet may indicate that the crevice-type intergranular attack may exist above the tubesheet crevice.
We are not planning on pulling one of these five tubes during the 60 EFPD outage in March for the following reasons:
1.
While (leaking) explosive plugs have been drilled
.out in the past, such an operation is difficult and (obviously) results in radiation exposure to the craftsmen.
In accordance with the ALARA policy, we should minimize such exposure.
Further, we have experienced broken tools (drills) during such activity which then requires personnel entry into the steam generator primary plent3 area to correct the situation.
Such entry, of course, results in further significant man-rem exposure.
2.
We are unaware that an explosively plugged tube has ever been removed under field conditions.
Such a tube may have been distorted by the explosive shock wave to the extent that its removal is much more difficult than a normal tube.
You will recall that we had significant difficulties with the first tube we removed in October and that tube had not been subject to plugging.
Further, it is possible that the plugging
~
operation may have affected the defect area near the top of the tubesheet to the extent that useful data could not be obtained by metallurgical examination.
Mr. Sol Burstein February 22, 1980 3.
A review of the previous eddy current examination tapes related to the five tubes reveals that the defects have probably existed since 1975 and have not changed significantly.
Their plugging in October resulted from the use of the multifrequency technique which more clearly indicated that defects existed.
As you know, tubes have been plugged in the past in the vicinity of the tubesheet sludge pile and the defects in the five tubes are probably related to the earlier degradation problems since our metallurgical examination of the tubes pulled in October revealed no evidence of intergranular attack near the top or above the tubesheet.
4.
The hydrostatic tests required by the Confirmatory Order provide adequate assurance of tube integrity above the tubesheet.
Further, if sufficient intergranular attack were to exist above the top of the tubesheet to significantly weaken a tube (s), it is likely that the pressure differen-tial would cause a crack in this unconfined region such that the eddy current examination would indicate a defect.
We recognize, however, the interest in obtaining further evidence as to the nature of any defects which may be found near or just above the top of the tubesheet.
Therefore, we will be prepared to pull one tube if one or more tubes are found which show defects at or within one inch above the top of the tubesheet.
If more than one such tube is found, all but the one to be pulled will be plugged as noted above.
If no defects are found in this area of interest, that would be further evidence of a lack of a serious problem.
Nevertheless, in view of the above-mentioned interest, it is appropriate that further effort be expended, prior to the scheduled refueling cutage in the Fall of 1980, to provide necessary assurance that techniques exist to allow an explosively plugged tube to be successfully pulled at that time with minimum personnel exposure.
While the final results of the crevice flushing process conducted last fall are not compiled, evidence indicates that some chemicals were removed.
Therefore, we are planning on repeating one or more cycles of flushing depending upon time available and results obtained.
Should you have any questions or emaments on these plans, please advise.
- s h,.
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, fA.
C. W.
Fay, Director Nuclear Power Department Attachn St
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Copies to Messrs. D. K. Porter, G. A. Reed, Gerald Charnoff
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