ML20211G501

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Forwards from Licensee to Staff Providing Info Re Change Request 148
ML20211G501
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 10/30/1986
From: Churchill B
GENERAL PUBLIC UTILITIES CORP., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Paris O, Shon F, Wolfe S
Atomic Safety and Licensing Board Panel
References
CON-#486-1331 OLA-1, OLA-2, NUDOCS 8611040046
Download: ML20211G501 (2)
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Text

y 13 3 I SHAW, PITTMAN, PoTTs & TROWBRIDGE DOLKETED A PARTNtaswer aNCLuOiNG PMOFESS8CNAL CORPORATIONS USNRC 2300 N STREET N. W.

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". .,*,a wmITER'S OIRECT OsAL NuweEn Sheldon J. Wolfe, Chairman Oscar H. Paris Administrative Judge Administrative Judge f Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel i U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Frederick J. Shon Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of GPU NUCLEAR CORPORATION, et al.

(Steam Generator Plugging CrTt Hia)

Docket Nos. 50-289-OLA-1 and 50-289-OLA-2

Dear Administrative Judges:

Attached for the information of the Board and the parties is a letter dated October 28, 1986, from Licensee to the Staff pro-viding information relevant to Change Request 148.

Sincerely,

(

Seh21888SIo8ke' G j

Bru . Churchill Counsel for Licensee Enclosure cc: Service List Attached -g[))

DOCKETED USNRC i

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION.26 BCT 31 P2:38 i Before the Atomic Safety and Licensin4FBoard

uv#-y In the Matter of )

GPU NUCLEAR CORPORATION, et al. ) Docket Nos. 50-289-OLA-1

) 50-289-OLA-2

) (Steam Generator (Three Mile Island Nuclear ) Plugging Criteria)

Station, Unit No. 1) )

SERVICE LIST

, 2 Sheldon J. Wolfe, Chairman Docketing and Service Section (3)

Administrative Judge. U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc.

Washington, D.C.. 20555 315 Peffer Street Harrisburg, PA 17102 l Oscar H. Paris Administrative Judge Thomas Y. Au 4 Atomic Safety and Licensing Assistant Counsel Commonwealth

! Board Panel of Pennsylvania l U.S. Nuclear Regulatory Commission Dept. of Environmental Resources t

Washington, D.C. 20555 Bureau of Environmental Resources-

} Room 505 Executive House Frederick J. Shon P.O. Box 2357 t 4

Administrative Judge Harrisburg, PA 17120

) Atomic Safety and Licensing Board Panel Louise Bradford i

j U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc.

Washington, D.C. 20555 1011 Green Street j Harrisburg, PA 17102 i Mary E. Wagner, Esq.-(2) i Office of Executive Legal Director i U.S. Nuclear Regulatory Commission
Washington, D.C. 20555 Atomic Safety and Licensing 1 Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555

9 GPU Nuclear sp any, ew J sey 07054 201 263 650'5 TELEX 136-482 Writer's Direct Dial Number.

October 28, 1986 5000-86-1064 5211-86-2189 Office of Nuclear Reactor Regulation Attn: J. F. Stolz, Di rector PWR Projects Directorate No. 6 Division of Licensing j U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stolz:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 '

l Laboratory Analysis of Pulled Tubes By letter dated February 19, 1986, GPU Nuclear Corporation infomed you of our intention to remove portions of up to three tubes from the TMI-1 OTSG durina the next refueling outage, designated 6R, as part of our ongoing evaluation' of the TMI-1 OTSG's. On September 22, members of my staff met with representatives of the NRC to discuss our program for evaluation of the OTSG's during 6R, which includes the laboratory analysis of pulled tubes as well as eddy current examination.

The 6R eddy current inspection will be in accordance with Technical Specification 4.19 as auamented by the inspection plan outlined in TR-008, Rev. 3 " Assessment of TMI-1 Plant Safety for Return to Service Af ter Steam Generator Repair", which was transmitted by letter dated September 14, 1983.

We believe that the results of the eddy current examination will reconfirm our I previous conclusions that primary side corrosion is not an ongoing phenomenon.

The results of the laboratory analysis are expected to confim.our previous conclusions with respect to the corrosion morphology; however, we do not expect that this laboratory analyses will differentiate between previous IGA /IGSAC or any newly formed IGA /IGSAC. The analysis will also provide further confimation of the adequacy of the eddy current program. We have established the objectives of the laboratory analysis as: (1) correlation of field eddy current data with destructive analysis results; (2) further evaluation of eddy current sensitivity and accuracy by incorporation of the results into the process qualification data base; (3) detemination of the extent and type of degradation in each tube; and (4) characterization of surface film oxide by microanalytical technique.

%$Y@

GPU Nuclear is a part of the General Public Utilities System

i In determining candidate tubes for analyses, GPUN identified tubes in one generator, OTSG A, which have exhibited indications above the fifteenth support plate during previous eddy current examinations. This initial screening identified nine candidate tubes. Historical data on these tubes from 1986.and 1984 eddy current examinations, as well as 1982 results, where available, are provided in the attached Table 1. GPUN believes that analysis of three tubes will provide sufficient information to confirm ou. previous evaluations, while limiting occupational exposures associated with the removal process and minimizing compromise to the generator associated with the removal of good tubes.

In determining the best candidates for analysis, GPUN used the following 1

evaluation criteria:

1. IGA potential based on multiple indications in close proximity j 2. " Grain dropout", as sugaested by a decrease in throughwall with a

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corresponding increase in signal amplitude.

3. Relatively strong signals (voltage) and throughwall extent approaching the plugging limit.
4. Removal capability, based on dome height which dictates the maximum length of tube segment which can be removed without cutting. This criterion has ramifications in ALARA considerations as well as sample adequacy, 5.- Indications detected by .540 Standard Differential probe but unconfirmed by 8 x 1 absolute probe.

Each of the nine candidates was evaluated in terms of these criteria, and ranked accordingly, as shown in Table 2. While none of the tubes individually satisfies all five selection criteria, the three selected tubes (A-141-3, A-8-45, A-35-83) do, in conjunction with one another.

These nine candidate tubes will undergo in-situ eddy current examination at the beginning of the outaae, and the comparative rankino is subject to change based on this inspection. Also, since the removal of kinetically expanded tubes is a relatively new process, tubes other than the three preselected tubes may be removed if difficulties are experienced durino the removal process.

GPUN also intends to perform a burst test on a portion of a tube removed from service to demonstrate the strength of the tube.

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GPUN believes that our tube selection process and program for laboratory analysis are in accordance with the NRC comments provided by letter dated May 2,1986.

I S ce\tly, FW Yice President Technical Functions l RFW/SK/pa(4081f) cc: R. Conte J. Thoma i

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TABLE 1 OTSG A TUBE PULL CANDIDATES FOR OUTAGE 61 1986 1984 1982 Indication 1986 .540 1984 .540 1982 .540 8x1 8xl Smi Dome Axial (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval)

Row Tut! Height Location  % V  % V  %. V Colls Volts Coils Volts Coils Volts 8 45 24.6 15+39.5 26 1.7 26 1.8 S/N .5 I .9 1 .6 NA 15+36.8 33 .8 36 .9 NDD 2 .8 1 .9 NA 15+35.8 23 1.1 30 1.0 NDD 1 .5 1 .6 NA 15+33.5 ( 20 .7 S/N .6 NDD 1 .2 I .4 NA 15+30.7 4 20 .7 26 .7 NDD NDD 1 .5 NA 15+30.1 < 20 .6 < 20 .8 NDD NDD 1 .4 NA 18 84 15.8 15+41.9 23 1.3 23 1.8 S/N .7 1 1.5 1 (1) .3 NA 15+40.8 33 1.0 33 1.1 S/N .4 1 .4 1 .5 NA 15+39.7 S/N .6 NDD S/N .3 NDD 1 .5 N f.

15+38.2 23 1.5 33 1.6 S/N .5 1 1.3 '

.5 NA 15+36.7 S/N .5 S/N .7 S/N .2 NDD NDO NA 15+35.9 26 .9 20 1.2 S/N .4 1 .2 1 .4 NA 15+34.5 23 1.2 30 1.4 S/N .5 I .6 1 .6 NA 15+33.9 4 20 .9 26 1.0 S/N .3 NDO AID NA 15+33.6 S/N .5 NDO NDO . NDO NDD NA 15+33.1 ( 20 1.3 30 1.4 S/N .6 1 .3 I .4 NA t 15+32.6 < 20 1.1 4 20 1.2 S/N .6 1 .5 1 .5 NA 15+31.7 <20 1.1 < 20 1.4 S/N .6 1 .2 I .4 NA 15+31.3 <20 1.0 < 20 1.3 S/N .5 1 .6 1 3 NA S/Z Low Signal to Noise Ratio (( 3:1)

NDD No Detectable Discontinuities IDC ID Chatter '

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TABLE 1 OTSG A TUBE PULL CANDIDATES F02 OUTAGE 6R 1986 1984 1982 Indication 1986 .540 1984 .540 1982 .540 8x1 8xl 8xl Dome Axial (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval)

Row Tube Height Location  % V  % V  % V Colls Volts Colls Volts Coils volts 141 3 16.8 15+39.9 S/N .6 S/N .6 NDD NDD 1 .2 NA 15+37.6 4 20 .7 < 20 .8 S/N .4 NDD 1 .2 NA 15+36.9 26 1.0 23 1.0 S/N .4 I .3 1 .6 NA 15+35.8 33 1.0 36 1.1 S/N .4 1 .5 1 .5 NA 15+34.3 30 1.6 33 1.7 NDO 1 .7 1 .7 NA 15+32.6 26 1.1 26 1.3 S/N .3 NDD 1 .5 NA 15+32.1 S/N .7 S/N .7 NDD 1 .2 I .4 NA 15+30.4 30 1.3 33 1.4 S/N .4 1 (1) .4 1 .5 NA 15+27.6 < 20 .8 S/N .8 S/N .4 1 .4 NDD NA 15+26.7 NDD S/N .6 NDO NDD NDD NA 15+25.3 26 1.1 26 1.1 NDD NDD NDD NA 15+22.7 S/N .7 S/N .8 NDD 1 .3 1 .4 NA 15+15.3 S/N .8 S/N .7 NDD 1 .3 1 .3 NA 15+15.0 S/N .9 S/N .9 NDO 1 .4 1 .4 NA 15+07.8 23 1.2 23 1.3 S/N .5 1 .4 1 .7 NA 15+07.5 4 20 .8 23 .8 S/N .3 1 .4 1 .5 NA 15+04.5 S/N .7 S/N .6 S/N .2 1 .2 NDD NA

1) 2-1 c:11 indications at this evaluation. not adjacent cot 1s.

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< m TABLE 1 OTSG A TU8E PULL CANDIDATES FOR OUTAGE CR 1986 1984 1982 Indication 1986 .540 1984 .540 1982 .540 8xl 8x1 8x1 Dome Axial (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval)

Row Tube Height Location  % V  % V  % V Colls Volts Colls Volts Colls Volts 5 3 15.8 15+43.9 23 1.5 23 1.5 N00 1 .4 1 .4 N/A 15+44.6 36 2.4 36 2.2 S/N .3 1 .5 1 .3 N/A 60 126 21.6 15+02.0 DNG .6 DNG .6 DNG .6 N00 NDO N/A 15+12.5 S/N .5 S/N .5 S/N .3 NDO NDO N/A 15+13.5 S/N .6 (20 .7 S/N .4 1 .2 1 .2 N/A 107 120 14.4 15+44.8 4 20 1.6 26 1.4 S/N .4 1 .4 1 .2 N/A 107 2 17.2 15+33.4 sc20 1.6 30 1.5 S/N .3 1 .5 .8 1 N/A 15+37.5 4020 1.4 20 1.4 S/N .5 1 .4 1 .I N/A DNG - Ding I

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TABLE 1 OTSG A TUBE PULL cme 0IDATES F03 OUTAGE (IR 1986 1984 1982 Indication 1986 .540 1984 .540 1982 .540 8x1 8x1 ' 8x1 Dome Axial (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval) (Re-eval)

! Row Tube Height Location  % V  % V  % V Colls Volts Colls Volts Coils Volts

,35 83 42.9 15+35.6 46 1.4 46 1.1 400 1 .6 1 .5 NA

'103 121 20.6 15+44.3 33 1.0 43 1.1 N00 1 .8 1 1.0 NA 15+43.9 36 2.1 43 2.1 S/N .7 1 1.1 1 1.2 NA l

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TABLE 2 COMPARATIVE RANKING

  • _ , _.

OTSG A TUBE PULL CANDIDATES FOR OUTAGE 6R TUBE N0. IGA / MULTIPLE GRAIN STRONG EASE OF SCREENED INDICATIONS DROPOUT SIGNAL REMOVAL INDICATION /

UNCONFIRMED A-141-3 Yes Yes Moderate No Yes A-8-45 Yes Possible Moderate Moderate Possible A-18-84 Yes Possible No No Yes A-35-83 No No Yes Yes No A-103-121 Moderate Possible No No No A-107-2 Moderate Yes No No No A-60-126 Yes No No Moderate No A-107-120 No Yes No No No A-5-3 Moderate No No No No

  • In ranking the candidates, a "Yes" was assigned 2 points, a "No" was assigned 0 points, and other responses were assigned 1 point.

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