05000483/LER-2008-005, Regarding Reactor Manually Tripped Due to B Main Feed Pump Tripping on Low Lube Oil Pressure
| ML090070238 | |
| Person / Time | |
|---|---|
| Site: | Callaway  (NPF-030) |
| Issue date: | 12/23/2008 |
| From: | Patterson J AmerenUE, Union Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-05579 LER 08-005-00 | |
| Download: ML090070238 (8) | |
| 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 |
| 4832008005R00 - NRC Website | |
text
AmerenUE P0 Box 620 Cal/away Plant Fulton, MO 65251 December 23, 2008 ULNRC-05579 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001
- 'AmesrelI OCFR50.73(a)(2)(iv)(A)
UFE Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2008-005-00 REACTOR MANUALLY TRIPPED DUE TO "B" MAIN FEED PUMP TRIPPING ON LOW LUBE OIL PRESSURE The enclosed licensee event report is submitted in accordance with 10CFR50.73(a)(2)(iv)(A) to report an event in which the "B" main feedwater pump turbine was tripped due to low lube oil pressure. As a result of the loss of one main feedwater pump, the reactor was manually tripped.
This letter does not contain new commitments.
Sincerely, J)ohn T. Patterson Plant Director EMF Enclosure a subsidiary of Ameren Corporation
ULNRC-05579 December 23, 2008 Page 2 cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8G14 Washington, DC 20555-2738
ULNRC-05579 December 23, 2008 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
LEREventsginpo.org (must send the WORD version of the LIFER to this address)
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Missouri Public Service Commission Records Center (INPO)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
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- 3. PAGE Callaway Plant Unit 1 05000483 1 OF 5
- 4. TITLE Reactor manually tripped due to "B" Main Feed Pump tripping on low lube oil pressure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MNH DY YA AIIYNM OKTNME NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 11 11 2008 2008
- - 005 -
00 12 23 2008
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
E] 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0l 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
Z 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 0l 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 097 El 20.2203(a)(2)(v)
[] 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES On November 11, 2008, startup activities from Refuel 16 were underway at the Callaway Plant. The main feed pump (MFP) turbine "B" lube oil cooler outlet strainer [EIIS system: SL, component: STR] was switched over to the opposite side of the duplex strainer arrangement as part of the in-service leak test, which was completed at 1534. At 1846.33, reactor power had been increased to approximately 97-percent when annunciation was received that the "B" MFP turbine [EIIS system: SJ, component: TRB]
was experiencing low lube oil pressure. Subsequently at 1846.36, the "B" MFP turbine tripped on low lube oil pressure. Annunciation for low lube oil pressure for a MFP turbine occurs at 5.5 psig; a MFP turbine trips on lube oil pressure below 4 psig.
The function of the MFPs is to supply Secondary Plant feedwater to the steam generators (SG) [EIIS system: AB, component: SG] for conversion to saturated steam during power operations. The loss of one MFP at power levels greater than 80 percent challenges the ability to maintain SG water levels at the required levels to support continued plant operations. As directed by plant operating procedure OTO-AE-00001, "Feedwater System Malfunction," the reactor was manually tripped at 1846.40.
All control rods fully inserted during the event and all safety systems responded as designed. An Auxiliary Feedwater (both motor-driven and turbine-driven) [EIIS system: BA, component: P] actuation and a Main Feedwater Isolation [EIIS system: SJ, component: ISV] actuation occurred as expected.
Because these systems responded properly during this event, no additional operator actions or use of other systems/components as a backup function were required, and the plant operators were able to (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) (17)
V.
ADDITIONAL INFORMATION
The system and component codes listed below are from the IEEE Standard 805-1984 and IEEE Standard 803A-1983, respectively.
System:
AB, Reactor Coolant System (PWR)
Components:
SG, Generator, Steam System:
BA, Auxiliary/Emergency Feedwater System (PWR)
Components:
P, Pump System:
SJ, Feedwater System Components:
ISV, Valve, Isolation TRB, Turbine System:
SL, Feedwater Pump Turbine Lube Oil System Components:
PCV, Valve, Control, Pressure STR, Strainer