TXX-6908, Final Deficiency Rept CP-87-22 Re FSAR Section 3.8.1 & Spec 2323-SS-14 Requirements for Impact Testing of Matls Not Implemented.Initially Reported on 870617.Requirements Clarified.Condition Not Reportable,Per 10CFR50.55(e)
| ML20236G101 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/27/1987 |
| From: | Counsil W, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-87-22, TXX-6908, NUDOCS 8711020415 | |
| Download: ML20236G101 (2) | |
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F9 Log # TXX-6908 Fi1e # 10110
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903.8 Ref # 10CFR50.55(e) 7UELECTRIC wunam c. counsa October 27, 1987 Eucutive Vke Preshknt U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 i
LINER ATTACHMENT MATERIAL REQUIREMENTS:
IMPACT TESTING SDAR: CP-87-22 (FINAL REPORT)
Gentlemen:
I On June 17, 1987, we verbally notified your Mr. Shannon Phillips of a i
deficiency wherein FSAR (Section~3.8.1) and Specification (2323-SS-14) requirements regarding impact testing of materials attached to the containment I
liner have not been implemented. Our last interim report, logged TXX-6694, t
was submitted on August 31, 1987.
An engineering analysis has determined that this condition is not reportable under the provisions of 10CFR50.55(e).
Specifically, a fatigue / fracture analysis was performed to determine if a postulated crack in the containment liner attachments would impair the integrity of the containment liner.
The analysis of postulated cracks in the heat affected zone of the fillet welds between the liner and attachment plate shows that the liner integrity would not be compromised even if the attachment plate had a lower toughness than the liner.
Thus, the intended safety function of the liner is maintained even though no impact tests on the attachments were performed.
The cause of this condition was determined to be a failure to sufficiently clarify the requirements.of ASME-ACI 359 and the FSAR commitment in the original specification for attachments to the liner.
Specification 2323/SS-14, " Containment Steel Liner," was modified (via Design Change Authorization (DCA) 49089) to clarify the requirements of attachments to the reactor containment liner and to stipulate impact testing of liner attachment materials greater than 5/8 inch in thickness.
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. Records? supporting these conclusions are available'for review by your.
.. inspectors: at the CPSES ' plant site.
Very.truly yours,.
o
- h. b r
y W.-- G. ' Counsil -
' l, By:
D. R..Woodlan h
Supervisor, Docket Licensing' l
l BSD/gj
. c J-Mr. R. D iMartin, Region IV Resident.lnspectors,CPSES(3)
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