ML19093B027

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01/11/77 Letter in Response to IE Circular 1976006 Stress Corrosion Cracking in Stagnant Low Pressure Stainless Piping Containing Boric Acid Solution at Pwr'S Described Inspection Reporting Program for Piping System
ML19093B027
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/23/1977
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: O'Reilly J
NRC/RGN-II
References
Download: ML19093B027 (10)
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Attachment I-e e C".:

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REPORT OF INSERVICE INSPECTIONS CONDUCTED BY VEPCO NDT PERSONNEL REFUELING OUTAGE NO. 3 UNIT NO. 2 SURRY FOWER STATION

. SEPTEHBER 19 7 7

. ~\. ()l/\ ~____;,...,,_;\- -

PREPARED BY: . cfJ. p~~~~~s~7' REVIEWED B Y : _ ~ ~ - - - ' - * - - - -

. C,:/... JOHNSON APPROVED BY: _ _ _ _ _ ~/A--u~-----

B. R. snyA

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DOCKET NO. 50-281 LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY

e e C..

VIRGINIA ELECTRIC AND POHER COMPAi'lY SURRY UNIT NO. 2 THIRD REFUELING - 19 77 INSPECTION

SUMMARY

Inservice inspection of ASME Section XI and Vepco Technical Specification items were accompltshed at Surry Unit No. 2 luring September 1977. The items which Westinghouse Inservice Inspection services performed are detailed in their report. ***. I The items which VEPCO NDT personnel accomplished during this inspection r \

pe:dod are detailed ,_ ..... , ..-.--. .

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ISI-261 Tech *. Spe.co Area Method Component Ref. Ref. Inspected of Inspection_

Misc. Inspections Table 4. 2-1 Low Head SIS VT Item 7 .2 Piping in Valve Pit Table 4,.2-1 Sensitized VT /

Section H Stainless Steel Piping RS and CS UT System Welds In accordance with VEPCO correspondence (Serial No. 345/112476, ,Tan~ 11~ 1977) to Mr. Moseley, U. S *.Nuclear Regulatory Commission> a volumetric examination was performed on the recirculation and containment spray systems piping. Twenty welds were inspected with preference given to welds located in the low areas. The inspection was accomplished using VEPCO UT Procedure NDT-11.1~ The accept/reject

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, criteria was NB-5330 of Section III ASME Boiler and Pressure Vessel Code thru Summer of 1975 Addenda.

e EXAMINATION RESULTS:

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Relevant indications were found by visual methods on the Low Head SIS Piping. Visual indications of arc strikes~ weld splatter, .rust and scale were found on*the*Low Head SIS Piping in the valve pit. These indications were numerous, and were not judged to be.of a serious nature for immediate correction; therefore, these indications willbe removed*by proper maintenance procedures as the station scheduling permits.

The Recirculation and Containment Spray Ultrasonic examination revealed two reportable indications (Weld No. 3 on RS-103-153 and Weld No. 3 on RS-104-153),

however, after radiography was performed, these. welds were evaluated as acceptable.

The ultrasonic indications were caused by I .. D. and O.D. geometry.

Photograpi1s of all indications (visual and ultra.sonic) were taken. These photos and the radiographic film on the R.S. system~ will remain on file with the Surry Records DepartmP.nt at Surry Power Station. They are available upon request.

In* accordance with the VEPCO correspondenoe *previously mentioned, concerni:,1g the Recirculation and Containment Spray systems piping, this report includes the following brief description of activities which provide assurance that the piping will be dry or flushed to maintain the low levels of corrodants.

The shell side drains on all Recirculation Spray Heat Exchangers and the iow point drains installed on the spray header piping are left open (per valve I

lineup checkout). These drains are periodically inspected for unusual drainage.

Dewatering pumps have b.een installed at the inside Recirculation Spray Pump suction wells. Procedure changes have been implemented which require dewatering the pump wells prior to operating the pumps for the required monthly surveillance test.

(

e 3 Each heat exchanger shell side was flushed with primary grade water, during the refueling outage, to insure a minimum amount of residual contami-nants at the start of the operating period"

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e e Attachment II

(_1 EDDY CURRENT INSPECTION REPORT REFUELING OUTAGE NOo 3 c*1 illHT NO. 2 SEPTEMBER 1977

_VIRGINIA ELECTRIC AND POWER COMPANY

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e VIRGINIA ELECTRIC AND POWER COMPANY

( SURRY NO. 2 SEPTEMBER 1977 EDDY CURRENT INSPECTION In September 1977, Eddy Current Inspection i,as performed by VEPCO on the tubes in Loops "A11 , "B", and "C".Steam Generators. The inspection program was performed to reins*pect those areas found to have eddy current indications during the previous inspection; and to inspect areas which are suspected to have indications. The Eddy Current Inspection was coriducted in accordance with VEPCO Procedure NDT-14.1, and Regulatory Guide 1.83. Included in this report are the certifications of the data collectors and evaluators. This program specified examination at lf00 KHZ to detect and measure potential tube defects. Also included in this report are the calibration certification sheets on the electronic r-.. equipment and calibration standard used during the. inspection program.

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A U--Bend Inspection of all available tubes in the first five rows was j

conducted from the Cold Leg in each steam generator at 100 KHZ. This i~spection revealed no detectable defects in the U-Bend regions.

Additional gaging inspections were conducted in the Hot Leg of each steam generator. This gaging program was based on past experiences, and to an extent, was run in conjunction with_the Regulatory Guide inspection.

S.G. > Lf0% Indications Mistakes Ga~

"A" 6 3 47 II B II 13 1 58

( II C" 2 56

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  • Explosive plugging was performed by Westinghouse in accordance with Process Specification NPT-33 included in this reporto.

A sununary of the inspection program per steam generator follows.

"A" STEA1'1 GENERATOR A total of 154) tubes were inspected at lf00 KHZ in the Hot Leg.

704 tubes were checked thru the U-Bend. 189 tubes were checked past the l) 7th Support. 650 tubes were ispected

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past the 1st Support to reinspect proplem areas from previous years.

Of the total, 115 had indications of O.D. tube defects (only those tubes that showed defect indications are included in this report). A breakdown of the indic~tions is ~s follows:

76 tubes< 20% defect, 20 tubes 20-29%, 13 tubes 30-39%, 6 tubes> 40%0 A complete list and drawing (showing the tubes 2:_ l10%) are included* in this report.

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A total of 56 tubes were -plugged in "A;; Steam Generator.. In addition to the 6 tubes found to have indications ~ 40% ~ 3

  • tubes were plugged by mistake and 47
  • j tubes were plugged due'--to the gaging data collected.

A list of tubes plugged in this inspection and a drawing showing the location of those tubes are included in this reporto Th'ere are a total of 645 tubes plugged in "N 1 Steam Generator.

"B" STEAM GENERATOR A total of 1633 tubes were inspected at 400 KHZ in the Hot Leg.

593 tubes were checked thru the U-Bend. 273 tubes were checked past the 7th Support. 767 tubes*were inspected past the 1st Support to reinspect problem areas. from previous years.

Of the total, 176 had indications of O.D. tube defects (only those tubes that showed defect indications are included in this report). A breakdown of all

( indications is as follows:

I

.* e 3 "B" STEAM GENERATOR (CONTINUED)

  • 76 tubes <20%:defect,-50 tubes 20-29%, 37 tubes.30-39%, 13 tubes> 40%.

A complete list and drawing (showing the tubes> 40%) :are. included in,this report) o A total.of 72 tubes were plugged in "B" Steam Generatoro In addition to the 13.tubes found to have indications..:_ 40%, 1 tube was plugged by mistake and

.58 tubes were plugged due to the gaging data collected.

A list of tubes plugged this inspection and a drawing showing the location of those tubes are included in this report.

There are a total of 647 tubes plugged in "B" Steam Generator.

"C" STEJ\J,f GEUERATOR A total of 1968 tubes were inspected at 400 KHZ in the Hot Leg.

465 tubes were checked through the U-Bend. 546 tuhes were checked past the 7th SupporL. 957 tubes ~.,ere inspec:ted past the 1st Support to reinspect problem areas of previous years.

Of the total 209 had indications of O.D. tube defects (only those tubes that showed defect :indications are included in this report)~ A breakdown of the indications is as follows:

95 tubes< 20% defect, 79 tubes 20-29%, 33 tubes 30-39%, 2 tubes> 40%.

A complete list and drawing (sho:wing the tubes..:.. 40%) are included in this report.

A total* of 58 tubes were plugged in "C" Steam Generator. In addition to the 2 tubes found t.o have indi{::ations > 40%, 56 tubes were plugged due to the gaging data collected.

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A list of the tubes plugged this inspection and location of those tubes are included in *this report.

a drawing showing the There are a total of 620 tubes plugged in "C" SteamGenerator.

Prepared By:

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