05000219/LER-2007-001, Automatic Reactor Scram Following Trip of Reactor Feed Pump
| ML072670131 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/17/2007 |
| From: | Rausch T AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-2007-026 LER 07-001-00 | |
| Download: ML072670131 (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 |
| 2192007001R00 - NRC Website | |
text
AmerGen.S AmerGen Energy Company www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ o8731-0388 10 CFR 50.73 September 17, 2007 RA-2007-026 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2007-001-00, Automatic Reactor Scram Following Trip of Reactor Feed Pump Enclosed is Licensee Event Report 2007-001-00, Automatic Reactor Scram Following Trip of Reactor Feed Pump. This event did not affect the health and safety of the public or plant personnel. This event did not result in a safety system functional failure. There are no new regulatory commitments made in this LER submittal.
If any further information or assistance is needed, please contact Stevie Du Pont, Regulatory Assurance at 609-971-4033 or Jeff Dostal, Operations, at 609-971-4572.
Sincerely, c)'/Q Rausch Vice President, Oyster Creek Nuclear Generating Station
Enclosure:
NRC Form 366, LER 2007-001-00 cc:
Administrator, USNRC Region I USNRC Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 07035
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or digits/characters for each block) sponsor, and a person is not required to respond to, the information collection.
l3. PAGE Oyster Creek, Unit 1 05000 219 1
OF 4
- 4. TITLE Automatic Reactor Scram Following Trip of Reactor Feed Pump
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR 05000 07
.17 2007 2007
- - 001
- - 00 09 117 2007 FACILITY NAME DOCKET NUMBER I
I 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
N]20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
N 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)
X 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 100 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______NRor i
FNRCForm66A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Stevie Du Pont.
(609) 971-4033CAUSE SYSTEM COMPONENTI MANU-REPORTABLE 11
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE F ACTURER TO EPIX FACTURER TO EPIX X
~
SJ MO G080I y.]I
- 14. SUPPLEMENTAL REPORT EXPECTED 15.EXPECTED MONTH DAY YEAR SUBMISSION YES (If yes, complete EXPECTED SUBMISSION DATE)
NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On July 17, 2007 at 05:21 while operating at 100% power, an automatic reactor scram occurred due to low reactor water level following a trip of the "C" Reactor Feed Pump (RFP). The cause of the "C" RFP trip is attributed to an electrical fault internal to the motor. This transient led to an automatic scram on low reactor water level and subsequent reactor isolation on a low-low reactor level.
There were no safety consequences impacting plant or public safety as a result of this event.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(iv)(A) due to the automatic reactor protection system and subsequent ECCS actuations.
NRC FORM 366 (6-2004)
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
Corrective Action Completed.
The failed RFP motor was replaced and the plant returned to full power operation. Operator training was conducted to emphasize communication of critical parameters between control room staff during transients. Preventive maintenance activities had been created prior to this event for periodic RFP motor refurbishments.
Corrective Action Planned.
Operations will implement corrective actions to enhance the communication of critical parameters during transients. In addition, Dynamic Learning Activities will be developed for operator performance issues that can be addressed by repetition in a simulator training setting.
Previous Similar Occurrences On January 25, 2006, the "B" Reactor Recirculation Pump tripped. An internal fault was the cause of both the recirculation pump motor and RFP motor failures. The "C" RFP motor was scheduled for replacement during the next refueling outage (1R22) in 2008.
Component Data.
Component:
Cause
System:
Component:
Manufacturer:
Model number:
'C' Reactor Feed Water Pump Motor Internal ground fault Feedwater Motor (P-2-2C)
General Electric 31 E724