ML19095A441
| ML19095A441 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/23/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | O'Reilly J NRC/RGN-II |
| References | |
| IEC-76-006, Serial No. 600 IR Unit 2 Sep. 1977 | |
| Download: ML19095A441 (10) | |
Text
'\\ '
VIRGIN! ELECTRIC AND PowER CoMPA'Y RICHMOND,VIBOINIA 23261 December 23, 1977 Mr. James P. O'Reilly Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region II - Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Serial No. 600 PO&M/DLB:wbh Docket 50-280 50""".281 License Nos. DPR-32 DPR-37 In our letter of January 11, 1977, in response to IE Circular 76-06, "Stress Corrosion Cracking in Stagnant Low Pressure Stainless Piping Contain-ing Boric Acid Solution at PWR's 11
, we described our inservice inspection and reporting program for certain low pressure piping systems.
Specifically, in addition to a description of our inspection program, we committed to submit, within 90 days of completion, a summary of the piping examination,. evaluation of results and also a brief description of plant conditions, operating proce-dures and other activities which provide assurance that the effluent chemistry will maintain low levels of potential corrodants in stagnant regions within the piping.
This information for the Surry Unit No. 2 inspection of September 1977 is included in Attachment I.
Also included for your information is Attachment II, "Eddy Current Inspection Report, Refueling Outage No. 3, Unit No. 2 11 Additional information, for either report, data sheets and specific tests results are available spected at the st~tion *
. r,,.
including procedures, upon request or may be in-Yo~rs very truly,
- u. JJ1. xf?~;.r C. M. Stallings Vice President - Power Supply and Production Operations Attachment cc: Mr. Robert W. Reid
e REPORT OF INSERVICE INSPECTIONS CONDUCTED BY VEPCO NDT PERSONNEL REFUELING OUTAGE NO. 3 UNIT NO. 2 SURRY POWER STATION SEPTEHBER 1977 DOCI~G NO.
50-281 LICENSE NO. DPR-37 e
VIRGINIA ELECTRIC AND POWER C011PANY
INSPECTION SUMNARY:
e VIRGINIA ELECTRIC AND PmmR COMP,\\:.'W SURRY mnT NO. 2 THIRD REFUELING - 1977 lnservice inspection of ASHE Section XI. and Vepco Technical Specification items were accomplished at Surry Unit No. 2 during September 1977.
The items
\\yhich Westinghouse Inservice Inspection services performed are detailed in their report.
The items which VEPCO NDT personnel accomplished durins this inspection perioJ are detailed below:
Component Misc. Inspections ISI-261 Ref.
~---
Tech *. Spec.
Ref.
Table 4.2-1 Item 7.2 Table 4. 2-1 Section H Area Inspected Low Head SIS Piping in Valve Pit Sensitized Stainless Steel Piping RS and CS System Welds Method of _Inspection_
VT VT UT In ac-:ordance with VEPCO correspondence (Serial No. 345/1124 76, Jan.. 11, 1977) to Mr. Moseley, U. _s. Nuclear.Regulatory Commission, a volumetric examination was performed on the recirculation and containment sprny 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.l.
The accept/reject crit.cria was NB-5330 of Section III ASME Boiler and Pressure Vessel Code thru Summer of 1975 Addenda.
-z-e e
- . EXAMINATION RESULTS:
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 6n 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 will be 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-10_3-153 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.
Photographs 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 DPp~r.tment at Surry Power Station.
They are available upon request.
In.accordance with the VEPCO correspondenc~ previously mentioned, concerning the Recirculation and Containment Spray syste~s 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 low point drains instali"ed on the spray header piping are left open (per valve lineup checkout).
These drains are periodically inspected for unusual drainage.
Dewatering pumps have been 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
- 3 -
.e e
-~
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.
e EDDY CURRENT INSPECTION-REPORT REFUELING OUTAGE NO. 3 mnT 1m. 2 SEPTEMBER 1977 VIRGINIA ELECTRIC A..~D POWER COHPANY
VI.IA.ELECTRIC AND POW~R COMP~~
SURRY.NO. 2 SEPTEMBER 1977 EDDY CURRENT INSPECTION
--~--------
In September 1977 9 Eddy Current In~pection was performed by VEPCO on the tubes in Loops "A", "B", and "C" Steam Generators.
The inspection program was performed to reinspect 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 conducted 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 400 KHZ to detect and measure potential tube defects.
Also included in this report are the calibration certification sheets on the electronic equipment and calibration standard used during the inspection program.
AU-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 gazing program was based on past experiences, and to an extent, was tun in conJunctlon wit?. the Regulatory Guide inspection.
A[ter ~ompletion of the inspection, 56 tubes were explosively plugged in 11A11 Steam Generator, 72 tubes in "B" Steam Generator, and 58 tubes in 11C Stearn Generator.
A breakdown of the tube plugging is:
S.G.
> 40% Indi.cntions
'Mistakes Gaging.
"A" 6
3 47 "B"
13 1
58 "C"
2 56
r~~~~--------~--------~~
Explosive plugging was.,formed by Westinghous<;.. ill ac.ance with (rocess Specification NPT-33 included in this* report.*.
I A surrunary of the inspection program per steam generator follows.
1'/\\." STEAM GENERATOR A total of 154) tubes were inspected at 400 1GIZ in the Hot Leg.
- 704 tubes were checked thru the U-Bend.
189 tubes were checked past the 7th Sui,port.
l'I 650 tubes were ispected past the 1st Support to reinspect prop,lem Areas from preyious 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 indications is as follows:
76 tubes< 20% defect, 20 tubes 20-29%, 13 tubes 30-39%, 6 tubes 2:_ 40%.
A complete list and drawing (showing the tubes _:: l10%) are included in this report.
A total of 56 tubes were plugged in "A" Ste.am Generator.
In addition to the 6
~ubes found to have indications~ 40%, 3 tubes were plugged by mistake and 47
~uh~s were plugged due.to the gaging data collected.
- A list of tubes plugged in this inspection and a drawing showing the loca"tio*n of those tubes are included in this report.
'There are a tq.tal of 645 tubes plugged in "A" 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
- Jt.h Support.
767 tubes were in"s1,ected 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 £howed defect indications are included in this report).
A breakdown of all indications -is as fallows:
e B'" ~nEAM GENERATOR (CONTINUED)
. -~
e
- 76 tubes <20% *defect,.50 tubes 20-29%, 37 tubes 30-39%, 13 tubes> 40% *
- complete list and drawing (showing the tubes ~ 40%) *are included in. this
- eport).
- A total of 72 tubes were plugged in "B" Steam Generator.
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 j_n "B" Stemn Generator.
"C" STEAN GEHERATOR 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 were inspPcted 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 indicQtions 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 t.ubes > 40%
- A ~omplete list anct*.c.rawing (sho~.,.ing 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 to have indications~ 40%, 56 tubes were pluGged due to the gaging data collected.
I
- -e-A list of the tubes plugged this inspection, and *a dr ing showing the location of those tubes are included in this report.
There are a total of 620 tubes plugged in "C" Steam Generator.
Approved
~.
- A. Johnson -
I I
1