05000423/LER-2005-004, Pressurizer Spray Nozzle Weld Indications
| ML053630044 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/16/2005 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-796 LER 05-004-00 | |
| Download: ML053630044 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(b)(2)(ii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 4232005004R00 - NRC Website | |
text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT 06385
,,,DEC 1 6 a6 ftDominion-SoZ Y I 33B U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/GJC Docket No.
License No.05-796 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2005-004-00g PRESSURIZER SPRAY NOZZLE WELD INDICATIONS This letter forwards Licensee Event Report (LER) 2005-004-00, documenting an event that occurred at Millstone Power Station Unit 3, on October 18, 2005. This LER is being submitted pursuant to 10 CFR 50.73(b)(2)(ii)(A), as a condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded, related to the discovery of indications in the pressurizer spray nozzle weld.
If you have any questions or require additional information, please contact Mr. David W.
Dodson at (860) 447-1791, extension 2346.
Very truly J. Alan Price Site Vice President - Millstone
V-
Serial No.05-796 Licensee Event Report 2005-004-00, Page 2 of 2 Attachments:
1 Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Licensee Event Report 2005-004-00, Pressurizer Sprav Nozzle weld indications Millstone Power Station Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004
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COMM"ISSIZON request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to Industry. Send comments regarding burden estimate to the Records Management Branch (T.6 E6). U.S. Nuclear Regulatory Commission, Washington, DC 2O555 0001 or by nteret e-mail to bis1@nrc.gov, and to the Desk Officer, Office of Information and Regulatoy Affairs, NEO-10202 (3150-0104), Offie of Management and LICENSEE EVENT REPORT (LER)
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FACIUTY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Power Station - Unit 3 05000423 1 OF4 TITLE (4)
Pressurizer Spray Nozzle Weld Indications EVENT D
()
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED ()
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR EQUENTIAL REV MO DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 10 18 2005 2005-004-00 12 16 2005 05000 OPERATINTHIS REPORT IS SUBMITTErDPURSUANT TO THE REQUIREMENTS OF 10 CFR : (Check all that apply) (11)
MODE (9) 6 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER N/A 20.2201 (d) 20.2203(a)(4)
_ 50.73(a)(2)(lii) j 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(lv)(A) 73.71 (a)(4) 20.2203(a)(2)(11) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(11-) 50.46(a)(3)()
- - _50.73(a)(2)(v)(C)
Specify In Abstract below or
.20.2203(a)(2)(IV) 50.73(a)(2)(I)(A)
__50.73(a)(2)(v)(D)
In (If more space is required, use additional copies of NRC Form 366A) ( 7)
- 4.
Corrective Action
The structural weld overlay provided structural integrity for the pressurizer spray nozzle to address the identified weld indications. Additionally, in response to NRC Bulletin 2004 -01, a plan has been developed to provide direction for administrating Alloy 600/82/182 inspections, and will be fully implemented over several outages.
There is high confidence that the ISI program, implemented in accordance with Section Xl of the ASME code, would be capable of detecting similar weld defects.
- 6.
Previous Occurrences
None Energy Industry Identification System (EIIS) codes are identified in the text as [xx].