05000482/LER-2006-003, For Wolf Creek Generating Station Regarding Indications Discovered on Pressurizer During Preplanned In-service Inspections
| ML063490047 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/07/2006 |
| From: | Garrett T Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ET 06-0056 LER 06-003-00 | |
| Download: ML063490047 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4822006003R00 - NRC Website | |
text
1'CREEK OPERATING CORPORATION December 7, 2006 Terry J. Garrett Vice President, Engineering ET 06-0056 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No.
50-482:
Indications Discovered on Inspections Licensee Event Report 2006-003-00, Pressurizer during Preplanned In-service Gentlemen:
During preplanned in-service examination of the pressurizer nozzle to safe-end dissimilar metal welds, five circumferential indications were discovered. These circumferential flaw indications were smaller than critical flaw sizes reported in Material Reliability Program (MRP) safety assessments. However, Wolf Creek Nuclear Operating Corporation (WCNOC) conservatively assumed the flaws to be unacceptable and installed preplanned full structural weld overlays for repair of the flaws. Therefore, the enclosed Licensee Event Report (LER) 2006-003-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(A), as a condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr. Kevin Moles at (620) 364-4126.
Very Jruly/yours, Terry J. Garrett TJG/rlt Enclosure cc:
J. N. Donohew (NRC), w/a B. S. Mallett (NRC), w/a G. B. Miller (NRC), w/a Senior Resident Inspector (NRC), w/a P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may (See reverse for required number of not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.
- 3. PAGE WOLF CREEK GENERATING STATION 05000 482 1 OF 4
- 4. TITLE Indications Discovered on Pressurizer During Preplanned In-service Inspections
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YERSEQUENTIAL REV MFACILITY NAME DOCKET NUMBER NUMBER NO.
MONTH j
05000 FACILITY NAME DOCKET NUMBER 10 11 2006 2006 003 -
00 12 07 2006 105000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 5 E] 20.2201(b)
El 20.2203(a)(3)(i)
E] 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
F] 20.2201(d)
[] 20.2203(a)(3)(ii)
[
50.73(a)(2)(ii)(A)
[] 50.73(a)(2)(viii)(A)
E] 20.2203(a)(1)
E] 20.2203(a)(4)
[
50.73(a)(2)(ii)(B)
E] 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A)
[] 50.73(a)(2)(iii)
E] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[
20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
[] 50.73(a)(2)(iv)(A)
[
50.73(a)(2)(x) j] 20.2203(a)(2)(iii) fl 50.36(c)(2) fl 50.73(a)(2)(v)(A)
LI 73.71(a)(4) 0
[] 20.2203(a)(2)(iv)
[
50.46(a)(3)(ii) j]
50.73(a)(2)(v)(B) 73.71(a)(5)
[] 20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER
- El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
[=
50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
Operating Experience/Previous Events:
LER 2005-002-00 reported a condition where evidence was found of boric acid deposits indicating a leak in a weld in the steam generator (SG) C and D lower head bowl drain lines. These conditions were attributed to PWSCC and the lower head bowl drain lines were repaired. In addition, the same preventative measure was taken for the lower head drain lines on SGs A and B.