ML20032A111
| ML20032A111 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/26/1981 |
| From: | Murphy E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20032A101 | List: |
| References | |
| NUDOCS 8110280304 | |
| Download: ML20032A111 (5) | |
Text
. -.
ATTACHMENT 1
)
UNITED STATES OF AMERICA 1
NUCLEAR REGULATORY COMtilSSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
Docket Nos. 50-266 WISCONSIN ELECTRIC POWER COMPANY 50-301 (Point Beach Nuclear Plant,
)
(Repair to Steam Generator Tube)
Units 1 & 2)
)
/
AFFIDAVIT OF EMMETT L. MURPHY I, Emmett L. Murphy, being duly sworn, depose and state:
1.
I am employed by the U.S. Nuclear Regulatory Conaission as a Materials Engineer in the Materials Engineering Branch of the Division of Engineer-ing, Office of Nuclear Reactor Regulation. A copy of my professional qualifications is attached to this affidavit.
2.
I am responsible for the review and evaluation of those portions of Wisconsin Electric Power Company's (Licensee) Technical Specification Change Request No. 69, dated July 2,1981, as modified by Licensee's request for interim modification contained in its letter dated Octo-ber 12,1981, for which the Materials Engineering Branch has primary review responsibility.
This responsibility includes the safety review and evaluation of the structural, mechanical and inspectability aspects' of the sleeving program.
This also includes the material aspects, which has to do with changes to the material microstructure j
as a result of the sleeving process.
I have the responsibility to review the stress analysis, strength testing, fatigue testing and l
mechanical leak testing of the joints.
i 0110280304 811026 PDR ADOCK 05000266 l
G fDR i
3.
I have reviewed the results of tests perforic.ed by Westinghouse and submitted by the Licensee in support of its sleeving program.
4.
I am providing this affidavit in response to " Licensee's Motion for Summary Disposition of Decade Contentions 3-6 as Related to Interim Operation of Unit 1", filed October 8,1981, and the document attached thereto,~ including the Statement of Material Facts and the Affidavit of David K. Porter.
I have read the Licensee's Motion, the Statement of Material Facts and the Affidavit of David K. Porter.
5.
Based upon qy review of Licensee's submittals in support of its proposed demonstration sleeving program. I state the following supplemental facts concerning Contention 3.
I have reviewed the approach taken by Westinghouse to establish the integrity of the tube / sleeve joint. This consisted of strength and metallurgical tests of the material, coupled with load and functional c
testing of the joint itself. This is an acceptable methodology in the industry.
Laboratory testing has shown a reduction.in the ultimate and yield strength of the sleeve and tube material in the zone local to where the sleeve wall is sealed to the tube wall. However, tensile. tests of the San Onofre and Point Beach joint configurations have demonstrated that the sleeve and tube walls at the seal will reinforce each other. The l
k-3 overall strength of the joint meets or exceeds the design minimum strength in the ASME Code. Based upon these extensive mechanical tests (proof pressure tests, pressure and axial load cycling tests) which have been completed for San Onofre, and the confirmatory testing which has been completed to date for the actual Point Beach joint configuration, we conclude that there is reasonable assurance against a structural failure, including circumferential rupture of the joint during the interim period of the demonstration sleeving program.
Primary side and secondary side hydrotests and eddy current testing will be performed on the sleeved tube assemblies subsequent to the sleeving operation and will provide additional assurance of joint integrity.
However, should a defect go undetected by inservice inspection and result in a leak, restrictive limits on primary to seconciary leakage in the plant license provide assurance that the plant will be shutdown in a timely manner for appropriate corrective action.
6.
Based upon my review of Licensee's submittals in support of its proposed demonstration sleeving program, I state the following supplemental facts concerning Contention 5.
i The eddy current inspectability of the sleeve walls between upper and lower joints will be comparable to that for an unsleeved tube. Geometric i
l l
{
l t
I-
4-4 discontinuities at the sleeve joints will produce signal interference.
However, the use of non-standard eddy current probe types and multifrequency te5niques should permit adequate inspections of these One local area that may present special difficulties is the areas.
sleeve joint which has received the proprietary heating process.
Westinghouse is investigating methods' to improve the inspectability of this area.
In the meantime, eddy current inspection following the sleeving operation will be supplemental by primary side and secondary side hydrotests which will provide additional assurance of joint integrity.
Even if defects should go undetected and leak, restrictive limits m allowable primary to secondary leakage which currently exist in the plant's operating license provide assurance that the plant will be shut down in a timely manner for appropriate corrective action.
I hereby certify that the above statements are true and correct to the cast of try knowledge and belief.
~
Emmett L. Murph Subscrih{dandsworntobeforeme this8eY-day of October, 1981.
n,
. Notary Public f
My Comissivi expires:
- / / 911-
/
.~
EMMETT L. MURPHY I
DIVISION OF ENGINEERING OFFICE OF NUCLEAR REACTOR REGUI.ATION PROFESSIONAL QUALIFICATIONS My name is Emmett L. Murphy.
I am a Materials Engineer in the Inservice Inspection Sectien, Materials Engineering Branch, Division of Engineering, Office of Nuclear Reactor Regulation, of the United States Nuclear Regulatory Cor.n..ission.
In my present position, I am responsible for perfonning technical reviews and evaluations of PWR steam generator tube surveillance and repair programs for NT0L and operating plants.
I hold a Bachelor of Science Degree in Aerospace Engineering and a Master of Science Degree in Civil Engineering, both fran the University of Maryland.
I have had a total of ten years of professional experience of which eight years has been in the nuclear field.
I was employed for almost six years as a structural engineer at the Bettis Atomic Power Laboratory by Westinghouse Corporation.
During qy employment at Bettis, I was involved in the structural design and analysis of core and core structurals of naval reactors.
Since joining the NRC in July 1979, I have been involved exclusively in the steam generator review area.
I have been involved in t':e safety reviews of most of the steam generators which ha.ye experienced si nificant tube 3
degradation durir.g the past two years, including Point Beach Units 1 and 2 and San Onofre Unit 1.
.