05000334/LER-2009-002, Regarding Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown
| ML091740055 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/18/2009 |
| From: | Sena P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-09-165 LER 09-002-00 | |
| Download: ML091740055 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 10 CFR 50.73(a)(2)(iv)(B)(6) |
| 3342009002R00 - NRC Website | |
text
FENOC FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Peter P. Sena III Site Vice President 724-682-5234 Fax: 724-643-8069 June 18, 2009 L-09-165 10 CFR 50.73 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 2009-002-00 Attached is Licensee Event Report (LER) 2009-002-00, "Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown." This event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(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. Colin P. Keller, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, Peter P. Sena III 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 digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Beaver Valley Power Station Unit Number 1 05000334 1 of 4
- 4. TITLE Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR None 04 20 2009 2009 002 00 06 18 2009 FACILITY NAME DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[
20.2201(b)
[
20.2203(a)(3)(i)
LI 50.73(a)(2)(i)(C)
[
50.73(a)(2)(vii) 3 LI 20.2201(d)
[
20.2203(a)(3)(ii)
LI 50.73(a)(2)(ii)(A)
[
50.73(a)(2)(viii)(A)
[
20.2203(a)(1)
[
20.2203(a)(4)
E] 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
E] 20.2203(a)(2)(i)
LI 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)
E] 50.36(c)(1)(ii)(A)
E 50.73(a)(2)(iv)(A)
E] 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
E] 50.36(c)(2)
LI 50.73(a)(2)(v)(A)
LI 73.71(a)(4) 0 %
LI 20.2203(a)(2)(iv)
[] 50.46(a)(3)(ii)
LI 50.73(a)(2)(v)(B)
LI 73.71(a)(5)
[
20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A)
LI 50.73(a)(2)(v)(C)
El OTHER Specify in Abstract below
_ _ 20.2203(a)(2)(vi)
LI 50.73(a)(2)(i)(B)
LI 50.73(a)(2)(v)(D) or in
CAUSE OF EVENT
The direct cause of this event was failure of the positioner associated with the controls of FCV-1 FW-489, "B" Bypass Main Feedwater Regulating Valve. The positioner was not providing accurate signals to the boosters on a valve closure input.
The root cause of this event was determined to be foreign material found within the feedwater bypass regulating valve positioner, causing the valve to fail to close during the event. The internal foreign materials found within the positioner were small chipped pieces of the positioner poppet seat and excess thread sealant compound. The foreign material was manufacturing induced and did not represent internal organizational or process weakness related to the procurement and use of this valve.
ANALYSIS OF EVENT
The portion of the main feedwater system which provides feedwater to the steam generators and the main feedwater automatic level control system do not perform safety-related functions. The safety function for main feedwater isolation valve closure functioned correctly. This event is bounded by the safety analysis provided in the Updated Final Safety Analysis Report Section 14.1.9 for the bounding excessive feedwater flow condition from a system malfunction.
The plant risk associated with the BVPS Unit 1 Feedwater Isolation event that occurred on April 20, 2009, due a high water level condition in the 'B' Steam Generator is considered to be very low. This is based on the conditional core damage probability for the event when considering the actual plant conditions that were present at the time of the event.
Based on the above, the safety significance of the Feedwater Isolation event on April 20, 2009, was very low.
A Hi-Hi water level condition was experienced in the 'B' Steam Generator, causing an automatic Feedwater Isolation Signal to be generated. This signal automatically stopped the running Main Feed Pump, which then automatically started both motor-driven Auxiliary Feedwater System (AFW) Pumps. Both motor-driven AFW pumps were actuated in response to the valid high steam generator water level condition, as designed. This was a valid actuation of the Auxiliary Feedwater System, which is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since Auxiliary Feedwater System is an applicable system as listed in 10 CFR 50.73(a)(2)(iv)(B)(6).
This event was reported as specified system actuations pursuant to 10 CFR 50.72(b)(3)iv)(A) at 05:09 on April 20, 2009 (EN 45000).
ANALYSIS OF EVENT (Continued)
There was no loss of safety function pursuant to 10 CFR 50.73(a)(2)(v) since the applicable safety systems functioned as designed.
CORRECTIVE ACTIONS
- 1. The applicable bypass feedwater regulating valve has been repaired and tested satisfactory.
- 2. The applicable Main Feedwater System regulating valve positioners will be re-classified to 'augmented quality' in order to stipulate that newly received positioners receive an internal inspection for foreign material.
- 3. An operating experience will be issued related to the discovery of foreign matter on the positioner valve.
Completion of the above and other corrective actions are being tracked through the BVPS corrective action program.
PREVIOUS SIMILAR EVENTS
A review found no prior BVPS Unit No. 1 and BVPS Unit No. 2 Licensee Event Reports within the last three years for an event involving manufacturer internal valve foreign material.
CR 09-57474