05000483/LER-2005-003, Re Lo-Lo Steam Generator Level Results in Actuation of Reactor Protection System and Auxiliary Feedwater System
| ML051460336 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/19/2005 |
| From: | Younie C AmerenUE |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC05 153 LER 05-003-00 | |
| Download: ML051460336 (7) | |
| 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 |
| 4832005003R00 - NRC Website | |
text
AmerenUE Callaway Plant PO Box 620 Fulton, MlO 65251 May 19, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 ULNRC05 153 WAmeren UE Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT I UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2005-003-00 Lo-Lo Steam Generator level results in actuation of Reactor Protection Svstem and Auxiliary Feedwvater System The enclosed licensee event report is submitted in accordance with I 0CFR50.73(a)(2)(iv)(A) to report an event which resulted in actuation of the Reactor Protection System and Auxiliary Feedwater System.
This letter does not contain new commitments.
Sincerely, C. R. Younie Manager, Callaway Plant Enclosure at a subsidiary of Ameren Corporation
ULNRC05153 May 19, 2005 Page 2 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7EI Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339
.1
V NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3012007
- 6-2004)
, 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 Callaway Plant Unit I 05000483 I OF 5
- 4. TITLE Lo-Lo Steam Generator level results in actuation of Reactor Protection System and Auxiliary Feedwater System
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILMES INVOLVED MONTH lDAY lYEAR YEAR NUMBER lNO.
MONTH lDAY lYEAR FC~l AElOKTNME FACILITY NAME DOCKET NUMBER 3
29 2005 2005 -
003 -
00 5
19 2005
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
Dl 50.73(a)(2)(vii) 3 El 20.2201(d) 0 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) o 20.2203(a)(1)
[l 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
E 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
O 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A) 0 73.71(a)(4) 0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 0 0
20.2203(a)(2)(v) 0 50.73(a)(2)(i) (A)
El 50.73(a)(2)(v)(C)
El OTHER o 20.2203(a)(2)(vi) 0 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 3/29/05, preparations were underway to perform a leak test of "C" Main Feedwater Isolation Valve (MFIV) AEFV0041 in accordance with plant procedure ETP-AE-ST01 1, STEAM GENERATOR "C" FWIV LEAK TEST-IPTE.
Initial plant conditions at 0700, 3/29/05, were Reactor Coolant System (RCS) temperature was 415 degrees F and RCS pressure was 1525 psig. Level in all four Steam Generators was being controlled at 50 percent using the "B" Condensate Pump. To establish initial conditions for performing the leak test, Control Room staff had been directed to raise RCS temperature to 485 degrees F which would provide a correspondingly higher RCS pressure and result in a more accurate leak rate determination for 'C" MFIV.
The Control Room operators initiated the RCS heatup using condenser steam dumps to control RCS temperature. As RCS temperature was being raised, indications of level oscillations began in "A", "B",
and 'D" Steam Generators (S/G). "C" S/G level indication remained steady state, but subsequently at 0854, "C" S/G low level alarm revealed that the pen in trend recorder AEFRO530 had stuck and level deviations were occurring in "C" S/G also. When the recorder door was opened, the pen began to properly track "C" S/G level again. A work request was generated to correct the problem with AEFR0530.
As RCS temperature approached 485 degrees F, S/G level oscillations continued, with "A" and "D" S/G experiencing the greatest changes. ETP-AE-ST01 1 Initial Conditions required isolating main feedwater flow to "C" S/G and establishing a "C" S/G narrow range level of approximately 40 percent. At 1031, "A" Motor Driven Auxiliary Feedwater Pump (MDAFP) was started in preparation for use in controlling "C" S/G level. Actual flow from the auxiliary feedwater system was not utilized at this time because main feedwater supplied by the "B" Condensate pump was still being utilized to maintain level in "C" S/G.
At 1034, with "C" S/G narrow range level at approximately 47 percent and slowly decreasing toward the prerequisite 40 percent narrow range level, AEFV0041 was closed which isolated main feedwater flow to "C" S/G. Computer trends indicate that with the low pressure differential between condensate pump discharge pressure (608 psig) and main steam header pressure (565 psig), sufficient leakage existed through AEFV0041 so that level in "C" S/G followed the same decreasing level trend as "A", "B", and 'D" S/G. Feedwater flow to the "C" S/G was not effectively isolated until 1048 when a manual isolation valve (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)
IV.
PREVIOUS SIMILAR EVENTS
A review of the Callaway Action Request System (CARS) was conducted to determine if similar events had previously occurred within the past three years. Only one event was identified involving steam generator level oscillations and ensuing reactor trip. This event does not constitute a similar occurrence because it was the result of not initiating feedwater preheating when required.
Additionally, no LERs were identified that involved a similar event.
V.
ADDITIONAL INFORMATION
The system and component codes listed below are from the IEEE Standard 805-1984 and IEEE Standard 803A-1984 respectively.
System:
Not Applicable. There were no failures during or because of this event.
Component:
Not Applicable. There were no failures during or because of this event.