ML18227D274

Transmitting Steam Generator Inspection Program for Unit No. 4 in Order to Comply with Foregoing Requirements

ML18227D274
Person / Time
Site:	Turkey Point
Issue date:	04/11/1977
From:	De Mastry J, Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
Z-77-112
Download: ML18227D274 (8)

Text

NRC FORM 195 I2-78 I e- .~

U.S. NUCLEAR REGUI.ATORY COMMISSION OO~CK NRCiDISTR IBUTION FOR PART 50 Do CKET MATERIAL NUMB'+

FILE NUMBER j

FROM: DATE OF DOCUMENT Florida Power & Light Company 4/11/77 Mr Stello, Jr. Miami, Fla. DATE RECEIVED Robert E. Uhrig. 4/14/77 i .ETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED j; wlCit'

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c A)RIG INAL NCLASSIFIED Clcopv DESCRIPTION ENCLOSURE Ltr. trans the following: Consists of Steam Generator Inspection Program Planned for Spring 1977 Refueling..

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PLANT NAME Turkey Point Unit No. 4 RJL SAFETY FOR ACTION/INFO RMATION ASSIGNED AD.

PROJECT MANAGER C ASST 0 LIC ASST INTERNAL D ISTRI BUTION PLANT .'SYSTEMS "

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. PETERSON CHECK BUTLE SITE ANALYSIS MELTZ VOLLMER HELTEMES AT&I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KRE GER EXTERNAL DISTRIBUTION C TROL LPDR0 NAT LAB TIC: REG V IE ULR KSON OR NUMBER'7loyovvF NSIC: LA PDR ASLB4 CONSULTANTS.

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FLORIDA POWER & LIGHT COMPANY April 11 t IKIMrwrOat',<<V rf~ripg Z,-77-112

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Office of Nuclear Reactor Regulation ))

Attn: Victor Stello, Jr., Director Division of Operating Reactors ~a@"I@IOI U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stello:

Re: Turkey Point Unit 4 Docket'o.'0-251 On February 8, 1977, the Nuclear Regulatory Commission ordered that Turkey Point Unit No. 4 shall be brought to cold shutdown condition in order to perform an inspection of steam generators at the end of the current fuel cycle or within 120 equivalent days of operation from February 8, 1977, whichever occurs first. Florida Power 6 Light, Company has developed a Steam Generator Xnspection Program for Tur-key Point Unit No. 4 in 'order to comply with the foregoing requirements. A copy of this program is forwarded herewith for your information.

We are presently scheduled to commence the inspection of Unit 4 steam generators on April 27, 1977. We request that any questions or comments which you may have on our inspection program be given to us by April 15, 1977, to avoid any, impact on our schedule.

El Very truly your's,"

Robert E. Uhrig Vice President REU/GDW/hlc Enclosure cc: Norman C. Moseley, Region IX Robert Lowenstein, Esq.

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TURKEX POINT UNIT NO. 4 STEAM GENERATOR INSPECTION PROGRAM PLANNED. FOR SPRING 1977 REFUELING

1. SIudge maps utilizing standard eddy current technique follows.

will'e made as a)'very other tube will be probed in rows 7, 14, 21, 28/

33, and rows 38 through 45 between columns 15 and 78.

b) Sludge Mapping will be performed in all three steam generators.

2. A complete Regulatory Guide 1.83 inspection will be per-formed.

3. current inspection will be performed in the one o'lock Eddy and ll o'lock wedge regions to detect flaws in the,.'tubes.

This inspection vill be conducted using a standard probe, but we also plan to include selective use of the helical scan probe which is under'evelopment and scheduled to be field-tested in early April, 1977. This testing in all three steam generators.

vill be performed

4. An eddy current dent location pxogram will be performed as follows:

a) A comprehensive full dent program is planned. for one steam generator. Steam generator "C" has tentatively been selected.

b) A representative program is planned for the remaining two steam generators.

c) Ne expect to use a standard .540 inch diameter probe at reduced gain.

5. Tube gauging will be conducted on all three steam generators utilizing three different size eddy current. probes (.540 in.,

.610 in., and .650 in. diameters).

6. A program to definitely determine the location of the leak in the 4C steam generator tube R-45, C-53 has been developed which includes:

a) A topside entry into "C" steam generator.

b) Cutting tube R-45, C-53, above the 'uppermost tube support plate.

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c) Eddy current. testing through the open tube end using a standard probe., The helical scan probe currently scheduled for'ield testing in early April is also planned to be used.

d) Tube gauging utilizing the .540 in , 610 in., and

.650 in., diameter probes.

e) Development of a probe that can be used. to selectively pressuxize short lengths of the tube with water and/or air to locate leaks by pressure decay or other means.

7 0 Handhole inspections;using TV and/or photographs will be used to inspect the flow slots and determine the extent of hourglassing on the Nl tube support plates in steam generators A, B, and C..

8. TV and/or photographs will be used to inspect the flow slots and determine the extent of hourglassing on the $ 6 tube support plate in steam generator B.

9. Wrapper to shell annulus measurements will be made on steam generators B and C.

10. Condition of tube support plates in steam generators A, B, and C will be assessed by Eddy current mapping using 3 1/2 KHz frequency. Nore than 300 tubes per S/G will be probed.

Should Eddy current testing reveal flaws located just'above the tubesheet in several tubes near the edge of the tube bundle periphery, the straight length of an affected,'cces-sible tube will be pulled.

12. Eddy current testing of U-bends is planned as follows:

a) Steam generator B; Rows 2-5, columns 1-92 Will be tested at 100 KHz using beaded flex 0.540 probe.

b) Any tube(s) which give indication at 100 KHz will be reprobed using 400 KFIz.

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