05000412/LER-2009-002, Regarding Unacceptable Indications Identified During Reactor Vessel Head Inspection
| ML093640059 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/21/2009 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-09-329 LER 09-002-00 | |
| Download: ML093640059 (4) | |
| 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 |
| 4122009002R00 - NRC Website | |
text
FENOC FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Paul A. Harden Site Vice President 724-682-5234 Fax: 724-643-8069 December 21, 2009 L-09-329 10 CFR 50.73 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 LER 2009-002-00 Attached is Licensee Event Report (LER) 2009-002-00, "Unacceptable Indications Identified During Reactor Vessel Head Inspection." This event is being reported in accordance with 10 CFR 50.73(a)(2)(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 F. Sepelak, Acting Manager, Regulatory Compliance at 724-682-4282.
Paul A. Harden Attachment cc:
Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager INPO Records Center (via electronic image)
Mr. L. E. Ryan (BRP/DEP)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 08/31/2010 (9-2007)
, the NRC may dsfor ach block) not conduct or sponsor, and a person is not required to respond to, the digits/characters finformation collection.
- 3. PAGE Beaver Valley Power Station Unit Number 2 05000412 1 of 3
- 4. TITLE Unacceptable Indications Identified During Reactor Vessel Head Inspection
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED M SEQUENTIAL REV FACILITY NAME DocKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR None FACILTY NME "DOCKET NUMBER 10 23 2009 2009 002 00 12 21 2009 FACILITYNAME
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
[] 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
E] 50.73(a)(2)(vii)
Undefined E] 20.2201(d)
E] 20.2203(a)(3)(ii)
Z 50.73(a)(2)(ii)(A)
E] 50.73(a)(2)(viii)(A)
[]20.2203(a)(1)
[] 20.2203(a)(4)
[] 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
_ _ 20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A)
E] 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [J 20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
E] 50.73(a)(2)(iv)(A)
[] 50.73(a)(2)(x)
EJ 202203(a)(2)(iii)
[] 56.36(c)(2)
[:] 50.73(a)(2)(v)(A)
El 73.71 (a)(4) 0 %
[] 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[1 73.71(a)(5)
E] 20.2203(a)(2)(v)
[
50.73(a)(2)(i)(A)
E] 50.73(a)(2)(v)(C)
F-OTHER Specify in Abstract below
[]20.2203(a)(2)(vi)
E] 50.73(a)(2)(i)(B)
EJ 50_73(a)(2)(v)(D) or in CAUSE OF EVENT (Continued)
System [AB] fluid from the crack, the further propagation of the flaw is eliminated. The embedded flaw weld overlay methodology was approved by the NRC (relief requests 2-TYP-3-RV-01 and 2-TYP-3-RV-03).
ANALYSIS OF EVENT
The safety significance associated with the BVPS Unit No. 2 reactor vessel upper head penetration indications found on Penetrations No. 49 and 57 during the 2R14 refueling outage inspection is considered to be very low. This is based on the estimated conditional core damage probability and Conditional large early release probability for the, event. Since the indications are not through wall and there was no evidence of RCS leakage, it is conservatively assumed there is a 5 percent probability that the weld flaws could have propagated and resulted in a reactor vessel head penetration Loss of Coolant Accident (LOCA).
CORRECTIVE ACTIONS
- 1. Reactor head penetrations No. 49 and 57 were repaired in accordance with the applicable embedded flaw repair methodology approved by the NRC.
Planning is underway for a reactor vessel head replacement which is expected to occur during a future steam generator replacement outage.
PREVIOUS SIMILAR EVENTS
Similar reactor vessel head indications were found and repaired during the previous BVPS Unit 2 refueling outages in 2008 and 2006. The BVPS Unit 2 reactor vessel head is an original component. BVPS Unit 1 replaced its reactor vessel head in 2006 during its steam generator replacement outage.
CR 09-66489/66557