05000400/LER-2013-003, Regarding Reactor Pressure Vessel Head Penetration Nozzle 37 Indication Attributed to Primary Water Stress Corrosion Cracking
| ML14015A256 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/15/2014 |
| From: | Kapopoulos E Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-14-006 LER 13-003-00 | |
| Download: ML14015A256 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 4002013003R00 - NRC Website | |
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aENERGY January 15, 2014 6HULDO +13
Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No.
Ernest J..DSRSRXORVJr.
Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2502 10 CFR 50.73 Subject: Licensee Event Report Reactor Head 1R))OH37,QGLFDWLRQ Ladies and Gentlemen:
Duke Energy Progress, Inc. submits the enclosed Licensee Event Report 2013-003-00 in accordance with 10 CFR 50.73 for the Shearon Harris Nuclear Power Plant, Unit 1, which describes a condition where an indication was identified in reactor vessel head penetration nozzle 37 by inspections performed during a refueling outage.
This document contains no regulatory commitments. Please refer any questions regarding this submittal to Dave Corlett at (919) 362-3137.
Sincerely, Ernest J..DSRSRXORVJr.
Enclosure: LER 2013-003-00 cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, Harris Nuclear Plant Mr. A. Hon, NRC Project Manager, Harris Nuclear Plant Mr. V. M. McCree, NRC Regional Administrator, Region,,
NRC FORM 366 (10-2010)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects.resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an 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.
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
- 1. FACILITY NAME Shearon Harris Nuclear Power Plant, Unit 1
- 2. DOCKET NUMBER 05000400
- 3. PAGE 1 of 3
- 4. TITLE Reactor Pressure Vessel Head Penetration Nozzle 37 Indication Attributed to Primary Water Stress Corrosion Cracking
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME None DOCKET NUMBER 11 18 2013 2013 - 003 - 00 01 15 2014 FACILITY NAME None DOCKET NUMBER
- 9. OPERATING MODE 6
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)
OTHER Specify in Abstract below or
Safety Analysis
The ultrasonic testing results revealed that the flaw was 21% through-wall and axial in orientation. An inspection of the exterior surfaces of the reactor head confirmed there was no leakage. The safety significance of the flaws presence during operation was minimal. An extensive industry safety assessment of PWSCC in reactor vessel head penetrations concluded that a program of periodic nonvisual non-destructive examinations at appropriate intervals supplemented by periodic bare metal visual examinations provides adequate protection against potential safety-significant failures. Based on the industry safety assessment, it is reasonable to conclude that an inspection program in accordance with the requirements of ASME Code Case 729-1 as modified by the additional limitations set forth in 10 CFR 50.55a(g)(6)(ii)(D), provide assurance against any credible PWSCC degradation event that would challenge nuclear safety.
Additional Information
LER 2013-001-00 reported previously identified and repaired flaws on the Harris reactor vessel closure head nozzles. The reported indications in April 2012 and May 2013 also exhibited characteristics of PWSCC.
As stated previously, Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
This report contains no regulatory commitments.