ML20069Q304
| ML20069Q304 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/01/1982 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6820 IEB-82-03, IEB-82-3, NUDOCS 8212080556 | |
| Download: ML20069Q304 (24) | |
Text
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'o OPU Nuclear Uh M[
P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:
December 1, 1982 Mr. Ronald C. Haynes, Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19405
Dear Mr. Haynes:
SUBJECT:
Oyster Creek Nuclear Generating Station Docket 50-219 I&E Bulletin 82-03 The purpose of this letter is to provide our response to questions Nos. 1 and 4 of IEB 82-03, Rev. 1.
It is of the utmost importance to GPUN to assure that our ultrasonic (UT) test m : hods are adequate to detect inter-granular stress corrosion cracking (IGSCC) in thick-walled piping.
In addition, we are actively studying the incidences and causes of thick-wall IGSCC in industry.
Because of our on-going programs to address this phenomenon the positions taken in our answers to IEB 82-03 are subject to change. A detailed response based on present knowledge and information are provided below in IEB 82-03 format.
1.
GPUN is currently in the process of indoctrinating, training and qualifying a new NDE services contractor. When this activity is complete, GPUN will be able to comply with IEB 82-03 by demonstrating our methods and techniques early to middle December. We will be in contact with your staff to make arrangements.
4.a.(1) and (2)
A total of sixteen (16) welds have been selected for inspection l
based on stress rule index (SRI), carbon content and configuration within the system. is an isometric drawing typical of the five (5) recirc loops.
It identifies loop configurations and those welds to be inspected as well as all welds in each loop. Attachment 2 is a table identifying welds to be inspected, their corresponding stress rule indices, IGSCC susceptibility ranking and amplifying reasons as to why the weld was chosen for inspection.
In the event that relevant indications are detected, the ISI sample size will be increased.
I 8212080556 021201 PDR ADOCK 05000219 G
PDR GPU Nuclear is a part of the General Pubhc Utihties System
[
Mr. Ronnld C. Haynao Page 2 4.a.(3)
The recirculation loop piping is constructed of type 316 stainless steel with an outside diameter of 26 inches and a minimum wall thickness of 0.982 inches. A specific alloy chemistry for each piping spool piece is not available; therefore, detailed chemistries for each weld joint cannot be identified. However, an upper and lower carbon coatent bounding can be determined from the material certification which is between 0.041 and 0.053 percent. These values encompass all the piping within the recirculation system.
4.2.(4)
The expected occupational radiation exposure for the planned inspection is described by subtasks below:
1.
Preparation work by Maintenance and Construction
- Removal of Insulation
- Scaf folding Erection
- Scaf folding Removal 100.0 Man-Rem 2.
Inservice Inspection
- Review and Acceptance of NDE 1.0 Man-Rem 3.
- Performance of NDE 18.0 Man-Rem 4.
Radiation Control Surveys Vork Monitoring 1.0 Min-Eem TOTAL EXPOSURE 120.0 Man-Rem The following is a summary of ALARA measures of presently planned in-service inspection (ISI) for reciculation system piping:
Radiation exposure will be reduced during the ISI of the recirculation system by minimizing working time in the drywell and working in the lowest possible radiation areas.
Some of the specific methods OCNGS will use to accomplish exposure reduction are as follows:
Mockup training in conditions similar to the work site for personnel performing the ISI.
Prejob briefings for personnel covering planned work, radiological conditions at the worksite, radiological requirements, etc.
NDE equipment calibration to be performed outside the drywell.
i l
Mr. R:nald C. Haynaa Page 3 Establishing of the maximum possible distance from ISI activities to recirculation piping.
Temporary shielding to be utilized as conditions allow.
i 4.b The CPUN ultrasonic examination procedt.e utilized for the detection of intergranular stress corrosion cracking in austenitic steel pipe is as follows:
the procedure employs a aingle element, 2.25 megahertz frequency, shear wave transducer of one half (1/2) maximum diameter and forty-five degree angle.
System calibration is performed by utilizing a calibration block containing both ten percent (10%) and five percent (5%)
[
notches oriented longitudinally and circumferentially. The ten percent notches are located on both outside and inside surfaces while the five percent notches are located only on the inside surface. The ten percent notches are utilized to establish the initial DAC on the CRT. This DAC is a three (3) point DAC giring a slope line representing an amplitude height easily observed on the CRT. The calibration settings are then increased in sensitivity by scanning the five (5) percent notch on che inside diameter of the calibration block. The subsequent amplitude on the CRT is always less than the ten (10) percent amplitude. Additional gain in sensitivity is achieved by increasing the decibel setting to that level at which the five (5) percent notch amplitude is equal in CRT screen height to the previous inside diameter ten (10) percent notch amplitude. The new sensitivity setting is further increased by adding sir (6) decibels, that is, doubling the sensitivity level of calibration to the new higher level for scanning purposes. Once discernable indications are observed, the evaluation of whether to record or not is made at the primary calibration level of sensitivity for the area of interest, that is to say, five (5) percent notch for 4/8 node indications and ten (10) percent notches for greater than 4/8 node indications. This is done by eliminating six (6) decibels for the 4/8 indication (ICSCC) and evaluating whether or not to re cord. Amplitudes breaking the base line at locations greater than 4/8 l
node (weld) shall have the additional decibels removed to bring the DAC back in line with the ten (10) percent notch calibration sensitivity level.
4.c No previous experience in the examination of recirculation piping i
welds utilizing the methodology of 4.b exists.
4.d A preliminary evaluation of CPUN's UT methods took place on October 29, 1982 at Battelle. Representatives from the NRC and J. A. Jones, EPRI NDE Center, provided instructions to the GPUN personnel.
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Mr. R:nnld C. H:ynas Page 4 As a result of the October 29, 1982 exercise, the following documents were developed and presented to the NRC representative:
1.
UT Calibration Sheets (56 and 57) 2.
UT Data Sheets (92, 93, 94, 95, and 100) 3.
Grid Maps (A, B, C, D, and E)
Upon returning to our facilities, the GPUN NDE examiner replotted the indicaticus for evaluation and review by engineering personnel. The review disclosed that some changes needed to be made to the grid sheets given to the NRC representative at the close of the demonstration. The final report data from the October 29, 1982 exercise describes this new information and is provided for your perusal as Attachment 3.
The preliminary evaluation and review of data led to the conclusion that a modification to the ultrasonic test procedure would be needed to enhance detection of IGSCC in the five (5) percent through-wall range.
The modified procedure planned to be used to examine the recirculation piping is described briefly in 4b above.
Af ter completing the demonstration required by IEB 82-03, Item 1 and the results are made available, a supplement to this letter will be forwarded to you.
It will further address the crack detection capability of the UT methodology to be used during the upcoming outage.
In the event that any questions or comments arise regarding the information provided herein, please contact Mr. J. Knubel at (201) 299-2264.
Very truly yours, 3 =*%#
Petef B. Fiedler Vice President and Director Oyster Creek Swo
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day of ba,rn po and subscribed to before me this
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, 1982.
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" [,"Eb", "c"i "D" H AVE A TOTAL OF 15 WEL DS
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" E" HAs A TOTAL OF 17 wlELDS.
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NITACllMENT 2
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EVALUATION SU MARIES FOR:
I RECIRCULATION LOOP A
' ISGCC SUSCEPTIBILITY ISOMETRIC WELD ID SRI RANK (1) 3 1.41 M
14 1.25 M
15 1.36 M
RiiCIRCUIATION IDOP B ISGCC SUSCEPTIBILITY ISOMETRIC WELD ID SRI RANK (1) 2 1.35 M
3 1.41 M
14 1.38 M
RECIRCULATION LOOP C ISGCC SUSCEPTIBILITY ISOMETRIC WELD ID SRI RANK (1) 8 1.35 M
15 1.36 M
RECIRCULATION LOOP D IGSCC SUSCEPTIBILITY ISOMETRIC WELD ID SRI RANK (1)
-i 2
1.30 M
6 1.34 M
'10 1.33 M
RECIRCULATION LOOP D IGSCC SUSCEPTIBILITY ISOMETRIC WELD ID SRI RANK (1) 2 1.35 M
3 1.41 M
9 1.25 M
13 1.45 M
14 1.41 M
1 1
ATTACl! MENT 2 (CONT'D)
NOTES:
(1)
Evaluation based _ on stress rule index (SRI) and carbon content (.041%
.0535.)
(2) M = Moderate (3) The susceptibility rank is based on the stress rule index (SRI) weighted by the alloy carbon content..The susceptibility designation is bench-marked against field occurences and EPRI/GE pipe test programs.
(4)
IGSCC STRESS RULE IA dX METil0DOLOGY 9+F+R SRI = PM + PB +
Sy Sy +.002E WHERE:
= PRIMARY MEMBRANE STRESS PB
= PRIMARY BENDING STRESS Q
= SECONDARY STRESS F
= PEAK STRESS R
= WELD RESIDUAL STRESS E
= YOUNG"S MODULUS AT TEMPERATURE SY
= ASME CODE MINIMUM YIELD STRESS AT TEMPERATURE
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