05000412/LER-2018-003, Unacceptable Indication Identified During Reactor Vessel Head Inspection
| ML18355A626 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/19/2018 |
| From: | Bologna R FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 2018-003-00 | |
| Download: ML18355A626 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(vii), Common Cause Inoperability |
| 4122018003R00 - NRC Website | |
text
FENOC' RrstEnergy Nuclear Operating Company Richard D. Bologna Site Vice President 12/19/2018 L-18-304 AITN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 BV-2 Docket No. 50-412, License No. NPF-73 LER 2018-003-00 10 CFR 50.73 Beaver Valley Power Station P.0.Box4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Enclosed is Licensee Event Report (LER) 2018-003-00, "Unacceptable Indication Identified During Reactor Vessel Head Inspection". This event is being reported in accordance with 10 CFR 50.73(a)(2)(ii)(A) and 10 CFR 50.72(b)(3)(ii)(A).
There are no regulatory commitments contained in this submittal. Any actions discussed in this document that represent intended or planned actions are described for the NRC's information, and are not regulatory commitments.
If there are any questions or if additional information is required, please contact Mr. Brian D. Kremer, Manager, Regulatory Compliance, at 724~682-4284.
Sincerely, Richard D. Bologna Site Vice President Enclosure - Unit 2 LER 2018-003-00 cc:
Mr. D. C. Lew, NRC Region I Administrator Mr. J. A. Krafty, NRC Senior Resident Inspector Ms. J. Tobin, NRC Project Manager INPO Records Center (via INPO Consolidated Event System)
Mr. L. Winker (BRP/DEP)
Enclosure L-18-304 Unit 2 LER 2018-003-00
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRC may not conduct or sponsor, and a person Is not required lo respond lo, the Information collection.
3.Page Beaver Valley Power Station, Unit 2 05000 412 1
OF 3
- 4. Title Unacceptable Indication Identified During Reactor Vessel Head Inspection
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year I Sequential I Rev Month Day Year i-ac""Y Name Docket Number Number No.
N/A 05000 01 Facility Name Docket Number 11 2018 2018
- 003.
00 N/A 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check al/that apply)
D 20.2201(b)
D 20.2203(a)(3)(i)
~ 50. 73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
Undefined D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50. 73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50. 73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.3S(c)(1)(i)(A)
D 50. 73(a)(2)(iv)(A)
D 50.73(a)(2)(X)
- 10. Power Level D 20.2203(a)(2)(ii)
D 50.3S(c)(1)(ii)(A)
I D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.3S(c)(2)
D 50. 73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(iv)
D 50.4S(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73. 77(a)(1) 0 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50. 73(a)(2)(v)(D) tJ 73. 77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73. 77(a)(2)(ii)
~JjJJ/;;:;;:
~;;:;:;tt:Ii!:! D 50. 73(a)(2)(i)(C)
D Other (Specify in Abstract below or in
CAUSE OF EVENT
Primary Water Stress Corrosion Cracking (PWSCC) of the Alloy 600 penetration tube material was determined to be the apparent cause of the identified flaw. The failure mechanism is a known issue that is addressed by the requirements of 1 O CFR 50.55a(g)(6)(ii)(D). The repair to Penetration No. 27 utilized an Alloy 690 embedded flaw weld overlay to encapsulate the surface attached flaw. A weld overlay of PWSCC resistant material to isolate the indication from the borated water environment arrests any further PWSCC on the penetration. The embedded flaw weld overlay methodology was pr~viously approved by the NRC for use at BVPS-2.
ANALYSIS OF EVENT
The plant risk associated with the BVPS Unit 2 weld indication identified on Penetration No. 27 of the reactor vessel head is considered to be very low. This is based on the fact that the indication was not through-wall and there was no indication of RCS leakage. The change in core damage frequency derived using the conditional core damage probability, and the change in large early release frequency derived using conditional large early release probability for the observed condition are very small.
CORRECTIVE ACTIONS
- 1. Reactor vessel head Penetration No. 27 was repaired in accordance with the applicable embedded flaw repair methodology approved by the NRC for use at BVPS-2.
I
PREVIOUS SIMILAR EVENTS
Similar reactor vessel head indic~tions were found and repaired during the previous BVPS-2 refueling outages in 2014, 2012, 2009, 2008, and 2006. The BVPS-2 reactor vessel head is an original component.
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