05000281/LER-2002-001, Residual Heat Removal Piping Corrosion Through-Wall Leak on April 13, 2002
| ML021710180 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/12/2002 |
| From: | Blount R Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 02-331, SPS:TJN R1 LER 02-001-00 | |
| Download: ML021710180 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 2812002001R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 June 12, 2002 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:
SPS: TJN Docket No.:
License No.:
02-331 R1 50-281 DPR-37
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Unit 2.
Report No. 50-281/2002-001-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.
Very truly yours, Richa H. Blount, Site Vice President Surry Power Station Enclosure Commitment contained in this letter:
- 1. A VT-2 inspection will be completed on the Unit 1 RHR 3/4-inch balance lines during the next cold shutdown of Unit 1.
cc:
United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station
APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 NRCFM 6S U
Estimated burden per response to comply with this mandatory information collection (7-2001)
COMMISSION 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 20555-0001, or by internet e-mail to bjsl@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOR-10202 (3150-ENSEE EVENT REPORT LRy I
s 04), Office of Management and Budget, Washington, DC 20503. If a means used (See reverse for required number of digits/characters for each block) to impose information collection does not display a currently valid oMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
[FACILIlYNAME (1) ll DOCKET NUMBER (2)
PAGE (3)
SURRY POWER STATION, Unit 2 05000 - 281 1 OF4 l
TMTE (4)l Residual Heat Removal Piping Corrosion Through-wall Leak l
EVENT DATE (5) l LER NUMBER (6)
]l REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR ACLYNMEDIME05000-E l MONTH l NUMBER NUMBER ll ll___
_l_05000-
.1.
04 lLI3 2002 2002 l -- 001 --
00 06 12 2002 FACILRYNAME DOCUMENTNUMBER 05000-OPERATING j THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (11)
MODE (9)
NA
=
20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 000 %
20.2203(a)(1)
=
50.36(c)(1)(i)(A)
=
50.73(a)(2)(iv)(A)
=
73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 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 (If more space is required, use additional copies of NRC Form 366A) (17)
5.0 ADDITIONAL CORRECTIVE ACTIONS
Post maintenance testing was completed, and the RHR System was declared operable at 16:29 hours on April 16, 2002.
6.0 ACTIONS TO PREVENT RECURRENCE A VT-2 inspection will be completed on the Unit 1 RHR 3/4-inch balance lines during the next cold shutdown of Unit 1 to detect flaws such as TGSCC, or pitting which could lead to TGSCC.
7.0 SIMILAR EVENTS
None.
8.0 MANUFACTURER/MODEL NUMBER The 3/4-inch line was schedule 40, 304 stainless steel.
9.0 ADDITIONAL INFORMATION
None.