ML052140278
| ML052140278 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/29/2005 |
| From: | Archie J South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, RC-05-0117 | |
| Download: ML052140278 (4) | |
Text
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Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 July 29, 2005 A SCANA COMPANY RC-05-0117 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sir/Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 RESPONSE TO NRC BULLETIN 2004-01 INSPECTION OF ALLOY 821182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE CONNECTIONS AT PRESSURIZED-WATER REACTORS (C-04-1719)
Reference:
- 1. Stephen A. Byrne letter to Document Control Desk, RC-04-0100, June 11, 2004
- 2. Stephen A. Byrne letter to Document Control Desk, RC-04-0113, July 26, 2004
- 3. Stephen A. Byrne letter to Document Control Desk, RC-04-0185, November 16,2004 On May 28, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2004-01 to request that utilities provide information regarding Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections at their plants.
Information was requested related to the materials, the methods of inspection and repair, and individual inspection schedules.
Licensees were requested to provide a response within 60 days of issuance of the bulletin. If a licensee could not provide the information or could not meet the requested completion date, they were required to submit a written response indicating this within 15 days of the date of the bulletin.
South Carolina Electric & Gas Company (SCE&G) determined that all necessary actions to provide the requested information for VCSNS could not be achieved within 60 days; therefore, a letter was submitted on June 11, 2004 (Reference 1) to address the 15-day response action required by the bulletin.
Subsequent to the referenced submittal during a telephone discussion between the VCSNS NRC Project Manager, NRC reviewer, and SCE&G, the NRC directed that SCE&G submit an interim response providing available-VCSNS information in regards to the Bulletin items. This interim response (Reference 2) provided the available inspection information. As noted by the referenced response, SCE&G identified the intent to provide a full response to the bulletin by November 17, 2004.
SCEUG I Virgil (. Summer Nuclear Station
- P. 0. Box 88 *Jenkinsville, South Carolina 29065.T(803) 345.5209
- wwwscanax.om
Document Control Desk Letter C-04-1719 RC-05-0117 Page 2 of 2 The response for Requested Information Items 1(a), (b), (c), and (d) was submitted by SCE&G (Reference 3) letter dated November 16, 2004. Item 2 of the bulletin directed licensees to provide information from inspections described in Item 1(c) within 60 days of plant restart of their next inspection of Alloy 82/182/600 pressurizer penetrations and steam piping connections.
The attached provides the response to Item 2 of the bulletin.
Should you have questions, please call Mr. Ron Clary at (803) 345-4757.
I certify under penalty of perjury that the foregoing is true and correct.
7 -Z Executed on Jeffrey B. Arc e
/ / ce resident, Nuclear Operations JT/JBA/mb Attachment c:
N. 0. Lorick S. A. Byrne N. S. Cams T. G. Eppink R. J. White W. D. Travers R. E Martin NRC Resident Inspector K. M. Sutton NSRC RTS (C-04-1719)
File (815.02)
DMS (RC-05-0117)
Document Control Desk Letter Attachment C-04-171 9 RC-05-01 17 Page 1 of 2 SCE&G RESPONSE TO USNRC BULLETIN 2004-001 FOR V.C. SUMMER NUCLEAR STATION (VCSNS)
REGARDING REQUESTED INFORMATION ITEM 2(a)
Requested Information from Bulletin 2004-001 issued May 28, 2004:
(2) Within 60 days of plant restart following the next inspection of the Alloy 8211821600 pressurizer penetrations and steam space piping connections, either:
(a) submit to the NRC a statement indicating that the inspections described in response to item (1)(c) of this bulletin were completed and a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant Indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken andlor repairs made as a result of the indications
- found, Or (b) if unable to complete the inspections described in response to item (1)(c) of this bulletin, submit to the NRC a summary of the inspections performed, the extent of the inspections, the methods used, a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken andlor repairs made as a result of the indications found. In addition, supplement the answer provided to item (1)(d) to explain why the inspections that VCSNS completed were adequate for the purpose of maintaining the integrity of the VCSNS RCPB and for meeting all applicable regulatory requirements which pertain to VCSNS.
Document Control Desk Letter Attachment C-04-1719 RC-05-01 17 Page 2 of 2 RESPONSE (2)(a):
The bare metal visual examinations to address the inspections described in Item (1)(c) of NRC Bulletin 2004-01 were performed during the recent VCSNS refueling outage RF15 completed June 1, 2005. The as-found condition of the pressurizer shell in the area of the Alloy 82/182 welds (Upper head nozzles and Surge nozzle) did not reveal any evidence of boron and the general surfaces were in the as manufactured condition.
The inspections verified that there were no indications of any through wall leakage. There was no evidence of leakage observed or indications identified and thus there were no corrective actions or repairs with follow up NDE required. Neither a summary of indications found by NDE nor a summary of indications are required as there was no evidence of leakage and no evidence of boron detected.