05000400/LER-2013-001, Regarding Reactor Pressure Vessel Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking
| ML13193A347 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/12/2013 |
| From: | Kapopoulos E Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-13-056 LER 13-001-00 | |
| Download: ML13193A347 (5) | |
| 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) 10 CFR 50.73(a)(2)(ii) |
| 4002013001R00 - NRC Website | |
text
(_~ DUKE ENERGY July 12, 2013 Serial: HNP-13-056 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 Subject: Licensee Event Report 2013-001-00 Ladies and Gentlemen:
Ernest J. Kapopoulos, Jr.
Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2502 10 CFR 50.73 Duke Energy Progress, Inc., formerly known as Carolina Power & Light Company, submits the enclosed Licensee Event Report (LER) 2013-001-00 in accordance with 10 CFR 50.73 for the Shearon Harris Nuclear Power Plant, Unit 1. The LER describes a condition where an indication was identified in one of the reactor vessel head penetration nozzles during a review of ultrasonic test data from Shearon Harris Nuclear Plant refueling outage 17 (R017) in 2012. The report also describes four similar reactor vessel indications that were found during R017 that were identified and repaired, but not recognized as being reportable at that time.
This document contains no regulatory commitments. Please refer any questions regarding this submittal to Dave Corlett at (919) 362-3137.
Sincerely, Ernest J. Kapopoulos, Jr.
Enclosure: LER 2013-001-00 cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, Harris Nuclear Plant Ms. A. T. Billoch Colon, NRC Project Manager, Harris Nuclear Plant Mr. V. M. McCree, NRC Regional Administrator, Region II
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 4
- 4. TITLE Reactor Pressure Vessel Head Penetration Nozzle Indications 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 05 15 2013 2013 - 001 - 00 07 12 2013 FACILITY NAME None DOCKET NUMBER
- 9. OPERATING MODE 1
- 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 documented as required.
Safety Consequences
There was a flaw in a fission product barrier which caused HNP to not meet code requirements. A bare metal visual inspection of the exterior surfaces of the reactor head and penetration did not indicate any through-wall leakage, thus there was not a breach in a fission product barrier, and structural integrity of the reactor vessel was not significantly compromised. The flaw was not through-wall and no leakage of reactor coolant occurred. The flaw was such that it would not have propagated under any of the design basis events (earthquake, loss of coolant accident, etc.).
Containment was intact as an additional fission product barrier. Therefore, there was no significant impact to the health and safety of the public.
Per the 2004 Edition of ASME Section XI Acceptance Criteria in Table IWB -3663-1 General Note (a),
Linear surface flaws of any size in the partial penetration nozzle to vessel (J-groove weld) are not acceptable. Section 3.2.4 of NUREG-1022, Event Reporting Guidelines, identifies that defects in the reactor coolant system pressure boundary that cannot be dispositioned as acceptable per ASME Section XI are reportable per 10 CFR 50.73. Therefore this event is reportable in accordance with 10 CFR 50.73(a)(2)(ii)(a), for a condition that a principal barrier was degraded, and 10 CFR 50.73 (a)(2)(i)(A), completion of any nuclear plant shut down required by the plants technical specification.
Corrective Actions
Completed Corrective Actions Nozzles 5,17,38,49 & 63 were repaired utilizing the inner diameter temper bead welding process.
Conducted a 100% review of all RO17 ultrasonic data and confirmed that no additional indications exist which were not properly analyzed and no additional indications required repair Updated Shearon Harris ISI Program to require volumetric exams to be performed on the reactor vessel head every refueling outage.
Planned Corrective Actions
Create mitigating programmatic governance for providing oversight for complex automated Non-Destructive Examination (NDE) inspections through the generation of new procedure(s).
Revise the vendor contract for RO18 to require analysts to perform independent analyses of ultrasonic data, develop work-hour restrictions, and incorporate requirements for an environment conducive to independence and analysis.
Reinforce the need to review and follow the requirements of applicable oversight procedures pertaining to the current assignment with the responsible individuals.
Previous Similar Events
No previous, similar Licensee Event Reports were identified.
Commitments
This report contains no regulatory commitments.