ML20216D836
| ML20216D836 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/09/1998 |
| From: | Barron H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9804160017 | |
| Download: ML20216D836 (3) | |
Text
Duk3 Power Company A ikke Ewy Compey McGuire Nuclear Station
"#~
MG01VP i
12700 Hagers ferry Rd.
51untersville, NC 28078-9340 H. B. Barron Vic, Presidens, McGuire (704) 873-4800 omcr Nudear Generation Department (704) 875-4809 FAX DATE:
April 9, 1998 U.S. Nuclear Regulatory Comunission Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Units 1 & 2 Docket No. 50-369 and 370 Part Length CRDM Housing Issue Problem Investigation Process No.: 0-M98-0647
References:
- 1) Letter to Mr. Frank J. Miraglia, Deputy Director, Office of Nuclear Regulation, dated March 6, 1998 (OG-98-037)
- 2) Letter to Westinghouse Owners Executive Advisory Committee & Westinghouse Owners Group Primary Representatives, dated March 6, 1998 (OG-98-038)
Gentlemen Reference 1 provides the Westinghouse Owners Group (WOG) completed response to the NRC's formal request to activate the Regulatory Response Group (RRG).
The RRG was tasked to respond to NRC concerns regarding the generic implications of the part length (P/L) control drive mechanism (CRDM) housing issue identified at Prairie Island 2.
Reference 1 documents the information provided by the WOG during a meeting with the NRC on February 27, 1998.
At that meeting the WOG presented information regarding the current assessment of the P/L CRDM housing issue including planned activities.
The affected WOG member utilities met on March 2,1998.
The WOG RRG recommended that the affected utilities voluntarily notify the NRC of site specific plans to address this issue.
For operating plants, it was recommended that individual utilities docket a plan to address this issue within 30 days of receipt of reference 2.
Also, for Units operating with part length CRDM housings installed, it was recommended that the plant operators increase reactor coolant system leakage monitoring awareness until the issue is resolved.
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April 9, 1998 l
U.S. NRC Document Control Desk l
Page 2 i
Unit Status McGuire Unit 1 is in Mode 1, 1004 power.
The next refueling f
outage (Unit 1 EOC12) is scheduled to begin on May 29, 1998.
McGuire Unit 2 is in Mode 1 at 100% power.
The next refueling outage (Unit 2 EOC12) is scheduled to begin February 1999.
McGuire Nuclear Station Applicability McGuire Unit 1 and 2 each have eight P/L CRDMs.
The McGuire P/L CRDMs are constructed with bimetallic welds using Inconel 82 buttering and Inconel 82 weld filler material.
This is in contrast to the Prairie Island P/L CRDM construction which uses 309 buttering and 308 or 308L stainless steel filler material.
1 An operability evaluation for McGuire Units 1 and 2 concludes i
both Units are fully operable.
This evaluation is documented in 1
the McGuire corrective action program (PIP No. 0-M98-0647).
In summary, the basis of operability is supported by the WOG investigation conclusions including that this issue represents a manufacturing defect with no definitive generic application.
1 McGuire Nuclear Station continues to monitor WOG progress in the area of non-destructive examination (NDE) surveillance data.
Also, McGuire continues routine monitoring strategies of enhanced Reactor Coolant System leakage detection.
Action Plans The current plan for McGuire Unit 1 is to inspect all eight P/L CRDM's during the next refueling outage.
This plan is based on the timing of the refueling outage (Uniti EOC12) in relation to:
progress in accumulating further knowledge of the Prairie e
Island P/L CRDM issue, and pending availability of an acceptable UT inspection technique o
for P/L CRDMs with the Inconel 82 weld material.
1 Plans for McGuire Unit 2 will be developed as information becomes available from McGuire Unit 1 inspections and WOG/ industry activities.
I Enhanced Leakage Monitoring McGuire Unit 1 and 2 are required by Technical Specifications to conduct primary system leakage monitoring every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
I l
April 9, 1998 U.S. NRC Document Control Desk Pagei 3 However, primary systems leakage calculations are normally performe,d once a day.
In the case that the primary leakage calculation is not performed daily, it is tracked to ensure the surveillance requirement is met.
I Primary system engineers routinely monitor reactor coolant system leakage calculations and trend leakage rates to maintain margins significantly below Technical Specification limits.
Due to Neouire's elevated attention to leakage monitoring, no further actions were judged to be necessary for meeting the intent of enhanced leakage monitoring.
Sincerely, AML H.
B.
Barron, Jr.
I cca L. A.
Reyes U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center
{
61 Forsyth St.,
SW, Suite 23T85 Atlanta, GA 30323 f
F.
Rinaldi U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 S.
Shaeffer i
NRC Resident Inspector i
McGuire Nuclear Station