ML021570600
| ML021570600 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/06/2002 |
| From: | Edison G NRC/NRR/DLPM/LPD2 |
| To: | John Nakoski NRC/NRR/DLPM/LPD2 |
| Edison G E, NRR/DLPM, 415--1448 | |
| References | |
| TAC MB4582 | |
| Download: ML021570600 (3) | |
Text
June 6, 2002 MEMORANDUM TO: John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management FROM:
Gordon E. Edison, Senior Project Manager, Section 1 /RA/
Project Directorate II Division of Licensing Project Management
SUBJECT:
TELEPHONE CONFERENCE RE: V. C. SUMMER REACTOR VESSEL HEAD INSPECTION RESULTS (TAC NO. MB4582)
On May 2, 2002, a telephone conference was held with South Carolina Electric and Gas Company (SCE&G) to discuss the results of their recent inspection of the V. C. Summer reactor vessel head within the control rod drive mechanism (CRDM) shroud. SCE&G stated that a qualified visual bare metal inspection was completed for essentially 100 percent of the accessible areas of the CRDM nozzles within the CRDM shroud. The licensee stated that the step down insulation prevented access to the back side of some outermost CRDM nozzles.
SCE&G reported that 1) there were no fixed boric acid deposits that prevented clear, unobstructed inspection of the head, 2) there was no evidence of throughwall leakage observed for any penetration, and 3) there was no degradation of the head surface observed. The licensee also stated that there was one area, about 6 inches by 11 inches, where a very thin film of boric acid appeared to have dripped down onto the reactor vessel head from the insulation above. Since there was no active leakage, the licensee concluded that the source of the boric acid film was previous conoseal leakage. The licensee made modifications to the conoseals after the leakage events, and has had no subsequent problems.
Based on the preliminary findings from Davis-Besse, the inspections performed by the licensee, and the susceptibility of the V. C. Summer reactor vessel head to nozzle cracking, the NRC staff did not identify any issues that needed additional followup prior to plant restart. The staff will document its formal review after reviewing the licensee's NRC Bulletin 2002-01 responses.
Docket No. 50-395
Attachment:
List of Teleconference Participants
June 6, 2002 MEMORANDUM TO: John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management FROM:
Gordon E. Edison, Senior Project Manager, Section 1 /RA/
Project Directorate II Division of Licensing Project Management
SUBJECT:
CONFERENCE CALL RE: V. C. SUMMER REACTOR VESSEL HEAD INSPECTION RESULTS (TAC NO. MB4582)
On May 2, 2002, a telephone conference was held with South Carolina Electric and Gas Company (SCE&G) to discuss the results of their recent inspection of the V. C. Summer reactor vessel head within the control rod drive mechanism (CRDM) shroud. SCE&G stated that a qualified visual bare metal inspection was completed for essentially 100 percent of the accessible areas of the CRDM nozzles within the CRDM shroud. The licensee stated that the step down insulation prevented access to the back side of some outermost CRDM nozzles.
SCE&G reported that 1) there were no fixed boric acid deposits that prevented clear, unobstructed inspection of the head, 2) there was no evidence of throughwall leakage observed for any penetration, and 3) there was no degradation of the head surface observed. The licensee also stated that there was one area, about 6 inches by 11 inches, where a very thin film of boric acid appeared to have dripped down onto the reactor vessel head from the insulation above. Since there was no active leakage, the licensee concluded that the source of the boric acid film was previous conoseal leakage. The licensee made modifications to the conoseals after the leakage events, and has had no subsequent problems.
Based on the preliminary findings from Davis-Besse, the inspections performed by the licensee, and the susceptibility of the V. C. Summer reactor vessel head to nozzle cracking, the NRC staff did not identify any issues that needed additional followup prior to plant restart. The staff will document its formal review after reviewing the licensee's NRC Bulletin 2002-01 responses.
Docket No. 50-395
Attachment:
List of Teleconference Participants DISTRIBUTION:
PUBLIC MCase SBloom PDII-1 R/F BSheron WBateman GEdison WKane MWidman KCotton ALee BWetzel EDunnington LReyes LGarner JNakoski KLandis JBlake SCollins McCoy WBearden JJohnson KKarwosky WBorchardt SCoffin ADAMS Accession Number: ML021570600 OFFICE PDII-1/PM PDII-2/LA PDII-1:SC NAME GEdison EDunnington JNakoski DATE 05/29/02 05/28/02 05/29/02 OFFICIAL RECORD COPY
Attachment Participants in May 2, 2002 Teleconference Related to V. C. Summer Inspection Results for Reactor Vessel Head Name Organization G. Edison NRC A. Lee NRC S. Bloom NRC B. Wetzel NRC M. Widman NRC/Region II M. Brown SCE&G R. Sweet SCE&G P. Rose SCE&G F. Rehrig SCE&G F. Miller SCE&G L. Bennett SCE&G W. Wicker SCE&G G. Moffatt SCE&G