JPN-87-008, Forwards Technical Justification for Continued Operation of Ja Fitzpatrick Nuclear Power Plant W/Existing Recirculation Sys Piping. Weld Overlay Repairs Meet Guidelines of Generic Ltr 84-11 & Draft NUREG-0313,Rev 2
| ML20207S723 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/10/1987 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20207S724 | List: |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 GL-84-11, JPN-87-008, JPN-87-8, NUDOCS 8703200215 | |
| Download: ML20207S723 (5) | |
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123 Main Street Wh.te Plains, New Wrk 10601 914 681.6240 A NewYorkPbwer C"t";;"Lemt 4# Authority
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y,,,,10, 1,g, JPN-87-008 U.
S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Technical Justification for Continued Operation with Weld overlavs in Place
References:
1.
NYPA letter, J.
P. Bayne to D.
B. Vassallo, dated April 26, 1985 (JPN-85-34).
2.
NYPA letter, J.
C.
Brons to D.
B. Vassallo, dated May 9, 1985 (JPN-85-42).
3.
NRC letter,'D.
B. Vassallo to J.
P. Bayne, dated May 24, 1985, approved operation for one cycle.
4.
NYPA letter, J.
C.
Brons to l
D.
R. Muller, dated October 28, 1986 l
(JPN-86-49), provided plans for inspections.
Dear Sirs:
l This letter transmits a report which provides technical l
justification for continued operation of the James A. FitzPatrick Nuclear Power Plant with the existing recirculation system piping.
As has been discussed in previous submittals, flaws attributed to intergranular stress corrosion cracking (IGSCC) were observed at nine locations in the FitzPatrick recirculation system.
Weld overlay repairs were applied to six locations.
These repairs meet the guidelines of Generic Letter 84-11 and draft NUREG-0313 Revision 2,
and are described in References 1 and 2.
Revised weld overlay design data is submitted in Attachment I and supersedes data in our previous submittals.
The original overlay thicknesses were calculated based on allowable stresses as specified in the ASME Code.
The revised data is based on allowable stresses as described in ANSI B.31.1, which is more conservative than the ASME code.
This change resulted in slight increases in required overlay thicknesses.
The as-built thicknesses of the overlays, as originally applied, were still greater than the revised values.
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The Nuclear Regulatory Commission approved operation for at least one additional fuel cycle in Reference 3.
Reference 4' provided plans for inspecting the overlays.
The three locations without overlays exhibited only very small indications that were treated with induction heating stress improvement and shown to be acceptable by analysis.
Attachment I documents the technical justification for continued long-term operation without replacement or further repair of the nine flawed welds.
Technical justification is based on several items:
With the overlays, the piping meets the original design basis, (ANSI B31.1,1967 edition with Addenda up to and including 1969), with the exception of the dimensional changes noted below.
The overlays are also shown to meet more recent NRC guidance (as summarized in NUREG-0313, Revision 2 draft), issued subsequent to the time of the FitzPatrick repairs.
The residual stresses are compressive on the inside surface of repaired piping.
This will inhibit-further crack propagation and initiation of new cracks in the original pipe weld.
The overlay weld metal is highly resistant to IGSCC, so degradation of the repair due to crack t
propagation into the overlay is not expected to occur.
Ultrasonic examinations are performed on non-overlayed indications every outage.
I New techniques for inspecting overlays have been developed.
I l
As a result of surface finishing in preparation for inspection during the current outage, there were changes in dimensions for some overlays.
These changes are currently being analyzed, and will be
[
discussed in a separate submittal.
These changes are not anticipated to affect the results of this report.
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I I
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Should you or your staff have any questions regarding this matter, please contact Mr.
J.
A. Gray, Jr. of my staff.
Very truly yours, hn Brons
'enior Vice President uclear Generation cc:
Office of the Resident Inspector U.
S. Nuclear Regulatory Commission P.
O.
Box 136 Lycoming, New York 13093 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 l
.p ATTACHMENT I TO-JPN-87 -008 TECHNICAL JUSTIFICATION FOR CONTINUED OPERATION WITH WELD OVERLAYS IN PLACE 1
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 l
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ex-ss' 1 Dederick Cop. land, an D*rIIMEn January 15, 1987 Anbay N. Ecciardt an HLG-87-001 David R Pacah P.E.
Peter C. Riccar,della, ha Mr. R. A.
Penny New York Power Authority 123 Main Street White Plains, NY 10601
Subject:
Structural Integrity Associates Report
" Technical i
Justification for Continued Operation of James A.
FitzPatrick Nuclear Power Plant With Existing Recirculation System Piping" SIR-86-008, Revision 3.
Dear Bob:
l Enclosed for your use are two copies of the subject report, plus one copy for Sophia Toth.
Two additional copies have been sent to FitzPatrick, attention: IGSCC Trailer, as you directed.
The changes contained in this report are in the Executive Summary and in Chapter 2.
These changes are due to insuring that all weld overlay design calculations and flaw evaluations were done using the allowable stress value of 15.9 ksi at operating-temperature (550"), which is taken from B31.1 Appendix A for A-358 Type 304, Class 1 (Longitudinal seam welds radiographed) which we feel is appropriate for FitzPatrick.
All weld overlays in the as-built condition exceeded the design minimum value, as is discussed in Chapter 2 of the report.
I hope this report revision meets your needs.
If you have any questions, please contact me.
Very truly yours, L. Gustin, P.E.
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