05000400/LER-2015-003, Regarding Reactor Vessel Head Nozzle Repairs
| ML15148A521 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/28/2015 |
| From: | Waldrep B Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-15-044 LER 15-003-00 | |
| Download: ML15148A521 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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 |
| 4002015003R00 - NRC Website | |
text
May 28, 2015 Serial: HNP-15-044 ATTN: Document Control Desk 86Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400/Renewed License No. NPF-63 Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 10 CFR 50.73
Subject:
Licensee Event Report 2015-003-00, Reactor Vessel Head Nozzle Repairs Ladies and *HQWOHPHQ
Duke Energy Progress, Inc., submits the enclosed Licensee Event Report 2015-003-00 in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit No. 1. This report describes a condition where inservice inspection examinations of the reactor vessel closure head nozzles identified conditions indicative of primary water stress corrosion cracking. The nozzles were repaired prior to startup from the refueling outage.
This document contains no new regulatory commitments.
Please refer any questions regarding this submittal to Dave Corlett, Regulatory Affairs Manager, at (919) 362-3137.
Sincerely, Enclosure: Licensee Event Report 2015-003-00 cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 10 CFR 50.73 May 28, 2015 Serial: HNP-15-044 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400/Renewed License No. NPF-63
Subject:
Licensee Event Report 2015-003-00, Reactor Vessel Head Nozzle Repairs Ladies and Gentlemen:
Duke Energy Progress, Inc., submits the enclosed Licensee Event Report 2015-003-00 in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit No. 1. This report describes a condition where inservice inspection examinations of the reactor vessel closure head nozzles identified conditions indicative of primary water stress corrosion cracking. The nozzles were repaired prior to startup from the refueling outage.
This document contains no new regulatory commitments.
Please refer any questions regarding this submittal to Dave Corlett, Regulatory Affairs Manager, at (919) 362-3137.
Sincerely, Benjamin C. Waldrep Enclosure: Licensee Event Report 2015-003-00 cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
NRC FORM 366 (02-2014)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (02-2014)
LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 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 and Information Collections Branch (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.
- 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 Indications Requiring Repair 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 04 07 2015 2015 -
003
- - 00 05 28 2015 FACILITY NAME None DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 6 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 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) 000 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
Safety Analysis
The ultrasonic testing results revealed that the flaws were 16%, 32%, and 23% through-wall extent in nozzles 14, 18, and 23 respectively, 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 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 safety-significant failures. 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
LERs 2013-001-00 and 2013-003-00 reported previously identified and repaired flaws on the Harris reactor vessel closure head nozzles. The reported indications in those LERs also exhibited characteristics of PWSCC.
This report contains no regulatory commitments.