3F1283-03, Forwards List of ASME Section XI Code Class 2 Pipe Welds in RHR Sys,Eccs & Containment Heat Removal Sys,Per 830713 Request.Request for Relief from Other Inservice Insp Code Requirements Expected During Early 1984
| ML20082M438 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/02/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 3F1283-03, 3F1283-3, TAC-49973, NUDOCS 8312060140 | |
| Download: ML20082M438 (12) | |
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M Power C 0 m P o a a f a o se December 2,1983 3F1283-03 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Inservice Inspection
Dear Sir:
By letter of July 13, 1983, you requested information regarding A3ME Section XI Code Class 2 pipe welds in residual heat removal systems, emergency core cooling sy.,tems, and containment heat removal systems, which were not examined volumetrically in the 1983 refueling outage. A listing of the subject welds is provided as Attachment A.
All of these welds were examined by dye penetrant method between March 29 and May 25, 1983, and no recordable indications were found. All welds are in piping of 0.40 inch wall thickness or less, and the absence of recordable surface indications provides a high degree of assurance of the integrity of these welds.
It is planned that volumetric examinations for welds located in the auxiliary building (21 examinations) will be accomplished prior to the restart following the Refueling V outage scheduled for Spring 1985. It is our intent to perform the examination of these 21 welds during the twenty months prior to the refueling outage; however, flexibility in scheduling is required to assure examination personnel availability and satisfaction of ALARA considerations. It is planned that examination of the single weld inside the reactor containment building will be accomplished during the Spring 1985 outage.
8312060140 831202 DR ADOCK 05000302 1
PDR 1
S
/i\\
General Off;ce 3201 nurry fourtn street soutn. P O Box 14042. st Petersburg. Flonda 33733 e 813-866-5151
I December 2,1983 3F1283-03 Page 2 It is anticipated that a request for relief from certain other code requirements will be submitted during the first quarter of 1984. This request will define the proposed inspection program features which will be applied to completion of our first 10 year inspection interval.
Sincerely, e
G. R. Westafer Manager Nuclear Operations Licensing and Fuel Management SCP/ mig Attachment cc:
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 (2 copies)
--j
ATTACHMENT A Class 2 pipe welds with pipe wall thickness less than 0.5 inch in residual heat removal, emergency core cooling, or containment heat removal systems scheduled for volumetric examination during 1983 refueling outage, but subjected to surface examination.
Decay Heat Removal System Examination Number Weld Number Sketch
- Number C2.1.31 DH-130A SK-1C
^
C2.1.34 DH-85 SK-111C C2.1.37 DH-61C SK-111C C2.1.40 DH-45 SK-111C C2.1.43 DH-49 SK-109C C2.1.46 DH-23 SK-109C C2.1.49 DH-37 SK-109C C2.2.6 DH-37 SK-109C C2.2.9 DH-24 SK-109C C2.1.52 DH-74 SK-110C C2.1.55 DH-43C SK-110C C2.2.12 DH-40 SK-110C C2.2.15 DH-41 SK-110C C2.1.58 DH-988 SK-112C C2.1.61 DH-103 A SK-112C C2.1.63 DH-100 SK-ll4C C2.1.73
_ DH-67B SK-114C C2.1.67 DH-141 SK-113C C2.1.69 DH-110A SK-113C Make-up System C2.1.80 MU-62 SK-11SC C2.1.81 MU-64 SK-115C C2.1.85 MU-42 SK-116C
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