IR 05000280/1986026
| ML20215F436 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/29/1986 |
| From: | Blake J, Coley J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20215F425 | List: |
| References | |
| 50-280-86-26-MM, 50-281-86-26, NUDOCS 8610160204 | |
| Download: ML20215F436 (3) | |
Text
-
,, - -
,
_
.
.
-
-. -
-- --
,
,
s
. - ~
..
- <;
pm Mrg iI UNITED STATES
'
g
'o
' NUCLEAR REGULATORY COMMISSION '
.[
REGION ll
.
y
'
g g
101 MARIETTA STREET,N.W.
- .
ATLANTA, GEORGI A 30323.
'
k *. * * *,o/
'
,
<
,
,
'
'
. Report'Nos.:= 50-280/86-26 and 50-281/86-26,
.
Licensee:. Virginia Electric and Power Company
Richmond, VA 23261 Docket Nos.: 50-280 and 50-281 ~
License Nos.: DPR-32 and DPR-37 Facility Name: Surry 1 and 2 Meeting Condu NRC Regional Office, Atlanta, Geotgia on-September 4, 1986 Inspector :
-
tJ.
ley
~Date Signed
%1
'
p R.
wYo Date Signed
>
.
9M 6b
' Approve by:
-
u y'.BTake,SectionChief Date Signed gineering Branch vision of Reactor Safety
,
SUMMARY
~
Scope: On September 4, 19'86, a technical meeting was held with Virginia Electric and Power Company (VEPC0) representatives in the Region II Office for the purpose
,
of providing VEPC0 an opportunity to demonstrate the capability of their ultra-
sonic examination procedure and equipment to detect actual flaws and artificial reflectors in Region II's centrifugally _ cast stainless steel (CCSS) test
'
. specimens.
VEPC0 was successful in detecting the I.D. reflectors', including cracks.
Region II's CCSS test specimer.s represented examination conditions much
.
worse than VEPC0 will experience during the examination of the Surry forged
'
stainicss steel reactor coolant loop piping.
Therefore, the Westinghouse
procedure (ISI-206, Rev.1), when supplemented with a field change to address
!-
specific equipment, techniques and calibration notch reflectors discussed in this report has den.onstrated conservative detection capability.
,
,
t 8610160204 861003
,
PDR ADOCK 0500
4
,
., - - -.. -,,. -. - - - -, <
. -- - - - -, -
,
,---,m
.,---r
- - - -..-.v-.
, -, = -,
. - -,.
.n
.,
.
.
REPORT DETAILS 1.
Persons Contacted Licensee Employee
- D. L. Spooner, Corporate Nondestructive Examiner (NDE) - Level III Other Organizations hrtford Steam Boiler Inspection and Insurance Co.
- R, L. Coder, Authorized Nuclear Inspector
- kttabtd exit interview 2.
TechM ani Issues Involved As a result of two NRC inspections performed at VEPCO's Surry facility (see RII Report Nos. 280, 281/85-15 and 280, 281/86-13) an unresolved item was (1) the adequacy of a specific refracted identified which questioned:
longitudinal wave transducer to examine the reactor coolant loop piping at the Surry facility and (2) the type of calibration reflectors used to establish the ultrasonic examination sensitivity level when a refracted longitudinal wave transducer is used on centrifuga11y cast stainless steel (CCSS).
During an inspection in June 1986, the inspector reviewed a technical report which discussed a commendable attempt by the licensee to resolve the procedural / equipment issue but the licensee's efforts wereAs restricted severely by the industry shortage of CCSS test specimens.
reported in RII Report Nos. 50-280/86-13 and 50-281/86-13, the inspector offered the licensee the opportunity to use the Region II CCSS cracked and notched specimens in resolving this issue and for improving their examina-tion techniques.
On August 20, 1986, the licensee requested a technical meeting be scheduled for September 4,1986 at the Region II offices.
On September 4,1986, the VEPC0 representative and an authorized Nuclear Inspector identified in paragraph 1 above, visited the Region II Office to demonstrate the capability of their examination procedure (ISI-206, Rev. 1)
locate and size actual cracks in CCSS specimens.
In and to detect, addition, the licensee discussed changes that will be made to the procedure to resolve open item 280, 281/85-15-02.
Region II provided the CCSS specimens for the VEPC0 procedure and equipment evaluation with the cracks covered so that the licensee had no prior knowledge of their location.
VEPC0 used a Sonic Mark I instrument equipped with a 600 volt pulser and a VEPC0 used three different transducers in the evaluation RF module.(1) a refracted longitudinal (RL) wave, dual element, 1 MHZ by one process:
inch transducer, (2) a RL dual element.5 MHZ by one inch transducer and VEPC0 (3) a IMHZ by one inch diameter RL water column fixture transducer.
performed the actual examination of the test specimens and Region II personnel monitored the ultrasonic instrument calbration and subsequent
.
.. _.
_
.
-
_
_
_
.
.-
,,
After the examiner had crack detection techniques used by the examiner.
completed the examination of the weld samples, the cracks and artificial reflectors were revealed to the licensee by performing a liquid penetrant examination on the test sample.
3.
Meeting Conclusions During the technical meeting VEPC0 successfully demonstrated the capability
,
of the ultrasonic procedure to detect actual flaws in the volume subject to Of the three transducers referenced above, the RL dual element examination.
1 MHZ by one inch transducer found all the crack indications and located and The RL water column fixture sized the indications exceptionally well.This transducer missed one crack and was transducer performed second best.
However, the transducer approximately one half inch off in locating the crack.
This that was least effective was the RL dual element.5 MHZ by one inch.
transducer missed one crack and was over one inch off in locating the crack indication.
At the conclusion of the performance test a meeting was held with the licensee to discuss what changes the licensee intends to make in the inspection procedure in order to clear the unresolved item before the The licensee stated the following changes October 1986 outage of Unit 2.
(1) a 10% notch would be added to the calibration would be initiated:
block, (2) a field change would be issued to procedure ISI-206, Rev. I to
,
(a) provide for notch calibration, (b) require that the notch sensitivity will also be the test sensitivity, (c) require that the RL dual transducer be used for axial scanning of the reactor coolant piping wher. the surface condition and geometry of the joint will allow at least 25 percent of the joint to be scanned using the dual trancducer (areas not acceptable for the dual transducer will be examined using the RL fixture) and (d) require that circumferential scans be performed with the more flexible RL water column transducer.
Changes to the inspection procedure and the calibration block will be verified by Region II during the Unit 2, October 1986 outage.
.,
f
-
_- - -,. _
_,. _ _ _ _ __~
.
- -
-