IR 05000413/1987034
| ML20236E577 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/19/1987 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20236E563 | List: |
| References | |
| 50-413-87-34, 50-414-87-34, NUDOCS 8710290275 | |
| Download: ML20236E577 (3) | |
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fo UNITED STATES l
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ug'o NUCLEAR REGU.LATORY COMMISSION y~
' REGION ll -
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j 101 MARIETTA STREET,N.W,
E C AT LANTA, GEORGI A 30323
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Report Nos.:
50-413/87-34 and 50-414/87-34 Licensee: Duke Power Company.
422 South Church Street Charlotte, NC 28242 Docket Nos.:
50-413 and 50-414
' License Nos.:
NPF-35 and NPF-52 Facility Name:
Catawba 1 and 2 Inspection Conducted: October 2, 1987
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Inspector: % _ M.
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Date Signed
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Approved by.
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J J Alake, Section Chief.
Da'te Signed I
n neering Branch Di ision'of Reactor Safety SUMMARY
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Scope:
On October 2, 1987, a technical meeting was held with DPC
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representatives in the Region II Office for the purpose of allowing DPC an opportunity to demonstrate the ability of their ultrasonic examination procedure and equipment to detect, accurately locate, and size ID reflectors, including cracks, in the Region II centrifugally cast stainless steel (CCSS)
test specimens.
This demonstration and procedure review resolved Inspector Followup Item 50-414/85-34-01,
" Demonstrate the Ability of Ultrasonic Transducers to Detect Crack in Centrifugally Cast Stainless Steel."
Results: No violations or deviations were identified.
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8710290275 871022 PDR ADOCK 0000
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REPORT DETAILS
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11c Personsucontacte'd
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. Licensee Employees:
- B. Cheezen; Supervisor,' Corporate Quality Assurance
' *J. Cherry, ISI Coordinator, Corporate Quality Assurance L 0ther. organization' '
J.-Menke, Babcock & Wilcox (B&W), Level II Examiner _-
- Attended exitlinterview
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Technical Issues > Involved DPC and ' B&W personnel identified in paragraph 1 above, L visited the
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Region.II office on' October 2, 1987, to demonstrate the capability. of '
their Lultrasonic examination procedure (ISI-119, Rev. 7) and eq'uipment to -
detect,, accurately locate and size actual crack.' flaws propagating from the
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pipe inside' diameter in, CCSS. -The inspector had requested that the licensee demonstrate their procedure and equipment during an inspection-at~
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- the Catawba facility. At that time, the licensee was using-equipment that the ' inspector had not 'seen demonstrated on actual cracks. - DPC was using a-H
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refracted: longitudinal wave transducer and although the refracted q
longitudinal wave transduced is the only practical method of examiningithe-
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'difficiult-to penetrate grain. structure in CCSS.
The transducer suffers-
'signific' ant mode conversion when interfacing with corner type reflectors, j
such' ' as. I.D.
pipe cracks, and unless the transducers -are properly
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fixtured, cracks could go ~ undetected.
The inspector therefore, opened Inspector Followup Item 414/85-34-01, " Demonstrate -the ability of
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Ultrasonic' Transducers to Detect Cracks in CCSS," at the Catawba site to l
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determine if the ultrasonic techniques used by the licensee for the I
examination of CCSS were effective.
I Region 11 provided the CCSS specimens for DPC's performance demonstration test. All specimens containing cracks and artificial reflectors were kept-in a position' that insured the licensee had no prior knowledge of their location. DPC used a SM100-TOKJ0-KEIAI instrument for the examination and
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dual 1 MHZ by 1 inch diameter Aerotech transducers.
The transducers had
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lucite wedges ground to fit the contour of the reactor coolant loop piping.
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B&W performed the actual examination of the test specimens and Region II personnel-provided guidance and monitored the ultrasonic instrument calibration and subsequent crack detection techniques used by the participants. After the participants had completed the examination of the i
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weld samples, the cracks and artificial reflectors were revealed to the licensee by performing a liquid penetrant test on the sample, 3.
Meeting Conclusions During the technical meeting at the Region II office, DPC successfully j
demonstrated the capability of their ultrasonic examination procedure and equipment to detect, accurately locate and size the' actual flaws in the volume subject to examination.
This performance demonstration closed Inspector Followup Item 414/85-34-01.
However, during the inspector's review of ISI-119, Rev. 7, the inspector noted the following: (1) Level 1 examiners were allowed to examine CCSS without direct supervision from a level II or level III' examiner and, (2) the procedure allowed scanning on
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CCSS at a rate of 6 inches /second.
Although neither finding was j
unacceptable by the applicable ASME Code, experience on CCSS has
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demonstrated that only the most experienced examiners should attempt to
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examine CCSS because of grain structure interface and that the rate of scanning should not be over 3 inches per-second.
The licensee concurred that the procedure changes would enhance the integrity of the exar ination.
n Since this procedure was written specifically for stainless steel and nickel base alley weld metals, both of which are difficult to examine, the licensee representatives agreed to revise the procedure prior to its use on reactor coolant CCSS piping at the Catawba facility to incorporate'the changes discussed during the meeting.
Within the areas examined, no violation or deviation was identified.
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