IR 05000400/1984040
| ML18018B856 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/20/1984 |
| From: | Blake J, Coley J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18018B855 | List: |
| References | |
| 50-400-84-40, NUDOCS 8501210022 | |
| Download: ML18018B856 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No.:
50-400/84-40 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Har ris
License No.:
CPPR-158 Inspection Conducted:
NRC Regional Office, Atlanta, Georgia Inspectors:
o ey, eactor neer ate igne ws eactor ng neer Approved by:
a e, ection ie n
neering Branch Di ision of Reactor Safety ate S gne
/I a.) 8'0 ate 1gne SUNNRY Scope:
On November 2, 1984, a technical meeting was held with Carolina Power and Light Company (CPSL), representatives in the Region II Office for the purpose of providing CPSL an opportunity to demonstrate the capability of their ultrasonic examination procedure and equipment to detect actual flaws and artifical reflec-tors in Region II's Centrifugally Cast Stainless Steel (CCSS) test specimens; CPSL was successful in detecting the I.D. reflectors, including cracks.
Region II's CCSS test specimens represented examination conditions much worse than CPSL will experience during the examination of the Shearon Harris wrought stainless steel reactor coolant loop piping.
Therefore, CPSL's procedure IST-501, and ultrasonic equipment have demonstrated conservative detection capability for the preservice
.examination at the Shearoo Harris facility.
t
REPORT DETAILS Person Con@cted e
Licensee Employees
- T. Bromback, Project Specialist, CP8L
- S. Pruitt, Senio~ Specialist, CPKL Other Organizations
- R. Saunders, Level III, Nuclear Energy Services
{NES)
Technical Issues Involved CPSL Shearon Harris, and NES personnel identified in paragraph I above, visited the Region II Office on November 2, 1984, to demonstrate the capability of their ultrasonic examination procedure (IST-501)
and equipment.-
to detect, locate, and size actual crack flaws propagating from the pipe inside diameter in Centrifugally Cast Stainless Steel
{CCSS).
Although the Shearon Harris facility does not have the difficult-to-examine CCSS piping in their reactor coolant loop piping, CPSL will be using a refracted longitudinal wave transducer.
The refracted longitudinal wave transducer is the only practical method of inspecting difficult-to-penetrate weld volumes and most cast stainless steels.
However, the refracted longitudinal wave mode suffers significant mode conversion when interfacing with corner type reflectors such as I.D. pipe cracks.
Therefore, CP&L wanted to test their procedure and equipment detection capability prior to the start of'heir preservice baseline examinations at the Shearon Harris Unit 1 facility.
Region II provided the CCSS specimens for CPSL's performance demonstration test.
All cracks and artificial reflectors were covered so that the licensee had no prior knowledge of their location.
CPSL used a Krautkramer-Branson USL-38 instrument and dual I MHz by I inch transducers.
The transducers had lucite wedges ground to fit the contour of the reactor coolant loop piping at a specific focal length.
NES 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 weld samples, the cracks. and artific'iaT reflector were revealed to the licensee by performing a liquid penetrant test on the sample.
Meeting Conclusions During the technical meeting at the Region II Office, CP&L successfully demonstrated the capability of their ultrasonic examination procedure and equipment to detect actual flaws in the volume subject to examinatio ATTACHMENT 3 Documents Included in Volume
"Duquesne Light Company Beaver Valley Power Station Unit No.
Preservice Inspection Progran" 1.0 DLC PSI PROGRAM ADMINISTRATIVE PROCEDURE:
NCDP No.
1.13, Rev.
1,
"ASME Section XI Preservice Inspection Progran Administrative Procedure" 2.0 DLC PSI PROGRAM/PLANS DOCUMENTS 2.1 NCDP No.
2.13, Rev.
2,
"ASME Section XI Integrated Preservice Inspection Program" 2.1.1 NCDP No. 2.13.5, Rev.
1,
"ASME Section XI Preservice Inspec-tion Plan for Class 2 Pressure Retaining Components" 2. 1.2 NCDP No.
2. 13.6, Rev
. 1,
"ASME Section XI Preservice Inspec-tion Visual Examination Criteria for Pressure Retaining Components and Component Supports" 2.1.3 NCDP No. 2.13.7, Rev. 1,
"ASME Section XI Preservice Inspec-tion Plan for Class 1 Pressure Retaining Components" 2.2 NCD Specification No.
10080-DMS-0002, Rev
.
2, "Specification for Pr eservice Stean Generator Eddy Current Inspection Beaver Valley Power Station Unit No. 2" 2.3 Pump and Valve Test Plan for Preservice Inspection 2.3.1 DLC Startup Manual Chapter 3.7,
"ASME Section XI Prop and Valve Administrative Procedure" 2.3.2 PST Pump Testing Requirements 2.3.3 PST Valve Testing Requirements 3.0 DLC ISI DEPARTMENT MANUALS 3.1 DLC ISI Department Administrative Manual Procedures 3.1.1 GP-101, Rev
. 0, "Establishnent of Reference Points and Data Recording" 3.1.2 GP-102, Rev. 0, "General Inspection Requirements" 3.2 DLC ISI Department NDE Manual Procedures 3.2.1 UT-300, Rev
. 0,
"General Requirements for Ultrasonic Exani-nations"
w,>M y
V P>>
It
K II I
N h J
I'
-2-3.2. 2 UT-301, Rev.
0,
"Screen Height and Ampl itude Control Linearity" 3.2.3 UT-302, Rev
.= 0,
"Procedure for Ultrasonic Exani nation of Ferritic Piping Systems"
2 4 UT 303, Rev
.
0,
"Ultrasonic Exani nation of Austenitic Systems" 3.2.5 UT-305, Rev
. 0,
"Manual Ultrasonic Exanination of Studs and Bolting (High Gain Technique)"
3.2.6 UT-306, Rev
. 0,
"Manual Ultrasonic Examination of Welds in Vessels Over Two Inches in Thickness" 3.2.7 UT-307, Rev
.
0,
"Manual Ultrasonic Exani nation of Vessel Welds frcm 0.2 Inches Up to and Including
Inches in Thickness" 3.2.8 UT-310, Rev
. 0,
"Manual Ultrasonic Exani nation of Welds in Reactor Vessels" 4.0 CONTRACTOR PROGRAMS/PROCEDURES 4.1 DMW-I S I-41, Rev
.
0,
"Manual Ultrasoni c Exani n at ion of Reactor Cool ant Pump Flywheel s" 4.2 DMW-ISI-154, Rev. 2, "Preservice Inspection of Reactor Vessels",
5.0 CLASS 2 PIPING ISOMETRICS 6.0 RELIEF REQUESTS 6.1 Vessel Relief Requests 6.2 Pump Testing Relief Requests
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