ML20117C736

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Provides Summary of Results of Confirmatory Testing Performed for 11/16 Inch Steam Generator Tube Sleeves
ML20117C736
Person / Time
Site: Callaway Ameren icon.png
Issue date: 08/19/1996
From: Schnell D
UNION ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-M95203, ULNRC-3420, NUDOCS 9608280024
Download: ML20117C736 (5)


Text

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I901 Chouteau Avenue Post Oflice Box 149 St. Louis. Mssouri 63166 a

314-554-2650 I

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UNION

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-U.

S. Nuclear Regulatory Commission ATTN:

Document Control Desk l

Mail Station F1-137 Washington, D.

C.

20555-0001 Gentlemen:

ULNRC-3420 TAC No. M95203 CALLAWAY PLANT DOCKET NUMBER 50-483 REVISION TO TECHNICAL SPECIFICATION 3/4.4 - REACTOR COOLANT SYSTEM l

References:

1) ULNRC-3357 dated April 12, 1996 l

2)

K. M.

Thomas ltr to D.

F.

Schnell l

dated July 23, 1996 j

3) ULNRC-3410 dated August 2, 1996 l

This letter provides a summary of the results of the confirmatory testing that was performed for 11/16 inch steam generator tube sleeves.

l Reference 3 committed to provide this information by i

L August 15, 1996.

However, in a telecon on August 15, 1996 with the NRC Project Manager for Callaway Plant, Union Electric indicated that the results would be provided the week of August 19, 1996.

If you have any questions concerning this I

information, please contact us.

Very truly yours, L-O f

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Donald F. Schnell DFS/WEK Attachment J

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9608280024 960819 PDR ADOCK 05000483 P

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d STATE OF MISSOURI

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SS COUNTY OF CALLAWAY

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Donald F.

Schnell, of lawful age, being first duly sworn upon oath says that he is Senior Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By Donald F.

Schnell Senior Vice President Nuclear SUBSCRIBED and sworn to before me this

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day of ANS//9 1996.

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  • N"'m an. cer a,qg

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cc:

T. A. Baxter, Esq.

l Shaw, Pittman, Potts & Trowbridge l

2300 N. Street, N.W.

I Washington, D.C.

20037 L

M.

H.

Fletcher Professional Nuclear Consulting, Inc.

l 19041 Raines Drive l

Derwood, MD 20855-2432 1

L.

Joe Callan i

Regional Administrator U.S. Nuclear Regulatory Commission Region IV i

611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 l

l Kristine M. Thomas (2) l Office of Nuclear Reactor Regulation r

U.S. Nuclear Regulatory Commission i

1 White Flint, North, Mail Stop 13E16 l

11555 Rockville Pike l

Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission l

P.O. Box 360 Jefferson City, MO 65102 l

Ron Kucera l

Department of Natural Resources P.O.

Box 176 Jefferson City, MO 65102 Don Woodlan TU Electric 1601 Bryan Street Dallas, TX 75201-3411 Pat Nugent Pacific Gas & Electric Regulatory Services P.O. Box 56 Avila Beach, CA 93424

1 Attachment Page 1 of 2 RESPONSES TO NRC REQUEST FOR ADDITIONAL.

'INFORMATION - CALLAWAY LASER WELDED SLEEVING By letter dated August:2, 1996 (ULNRC-3410), Union Electric committed to provide a summary.of the tests performed to validate the formal laser welded tube sleeve weld process.

Summary of Weld Process The formal'ASME Code qualification of the laser weld process has been completed.

The qualification data package which includes I

the Weld Process Specification and the Process Qualification Records are available for review.

1 Two-pass and three-pass processes have,been formally qualified.

The qualification testing included the preparation of six samples for the following welding power ranges for each process:

324W to 336W l

.337W to 349W 350W to'361W A total of 36 weld samples on sleeved tube-mockups were made.

j These samples were visually inspected using a Welsh Allyn probe

.and UT inspected.

Following the heat' treatment process, the l-samples were sectioned for metallographical examinations and PT.

[

The results for all 36 samples were acceptable in-that.the welds l-had adequate widths at the sleeve / tube interface and had no hot cracks.

.The weld surfaces were found to be acceptable for UT l

inspection.

Summary of Lower Joint Qualification Testing Three types of tests were performed to qualify the elevated tube sleeve lower joint, 1) primary-to-secondary leak resistance testing, 2) secondary-to-primary " onset of significant leakage testing" and 3) sleeve pullout testing.

A nominal roll expansion torque of 120 i10 inch-lbs. was identified during the scoping test and verified during the qualification test.

The roll expansion torque is applied to a three-pin roll expander having an effective rolling height of 2 inches.

A nominal rolled height of 1.75 inches is specified.

Eighteen primary-to-secondary side " process qualification" leak test samples were fabricated and tested.

All of the samples met the leakage acceptance criteria from Page 4-20 of WCAP 14596.

C Attachment Page 2 of 2 q

Onset of Significant Leakage (contact pressure) testing is I

performed to determine the interfacial radial contact pressure I

between the rolled sleeve and the tube.

The contact pressure is I

then used to calculate sleeve rolled joint pullout resistance.

i All of the samples tested (nominal and maximum diameters)

L withstood a differential pressure of 5500 psi without exhibiting l

indications of onset of significant leakage.

Therefore,

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l adequate pullout resistance, with margin, is provided by the i

I rolled joint at a nominal torque of 120 inch-lbs. with a torque l

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range of 110 to 130 inch-lbs.

i Three pullout test samples were fabricated.

All the pullout j.

test results exceeded the criterion of three times the maximum l

endcap load during normal operation with adequate margin.

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