05000483/LER-2005-002, Re Plant Shutdown Required by Technical Specification 3.7.8 for an Inoperable Train of Essential Service Water
| ML051460343 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/19/2005 |
| From: | Younie C AmerenUE |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC05 154 LER 05-002-00 | |
| Download: ML051460343 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4832005002R00 - NRC Website | |
text
AmerenUE Callaway Plant PO Box 620 Fulton, MO 65251 May 19, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 N) ashington, DC 20555-0001 ULNRC05 154 w1AmerenUF Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT I UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2005-002-00 Plant Shutdown required bv Technical Specification 3.7.8 for an Inoperablc train of Essential Service W'ater The enclosed licensee event report is submitted in accordance with 1 OCFR50.73(a)(2)(i)(A) to report an event where a plant shutdown occurred because the Essential Service WMater system was not returned to an Operable status within the time allowed by Technical Specifications.
This letter does not contain new commitments.
Sincerely, C. R. Younie Manager, Callaway Plant Enclosure 5t%9Q -
a subsidiary of Ameren Corporation
ULNRC05154 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
fjlZ It r
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
'6-2004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the informationcoltin PG
- 3. PAGE Callaway Plant Unit I 05000483 1 OF 4
- 4. TITLE Plant shutdown required by Technical Specification 3.7.8 for an Inoperable train of Essential Service Water
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILmES INVOLVED MYN FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENIAL R EV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 3
26 2005 2005 -
002 -
00 5
19 2005
- 9. OPERATING MODE 11.THIS REPORTISSUBMITTED PURSUANTTOTHE REQUIREMENTS OF10 CFR§: (Check allthatapply)
O 20.2201(b) a 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 10 20.2201(d) 0 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 0l 20.2203(a)(1)
[l 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
Co 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 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)
D 50.36(c)(2)
[
50.73(a)(2)(v)(A)
D 73.71 (a)(4)
El 20.2203(a)(2)(iv)
Cl 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B) 0 73.71(a)(5) 100 E 20.2203(a)(2)(v)
ED 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER El 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 At 0300, 3/23105, 72-hour Technical Specification Action 3.7.8.A was entered when a pinhole leak was discovered in "B" Essential Service Water (ESW) system between the "B" ESW pump strainer and discharge isolation valve. Subsequent ultrasonic testing (UT) determined that approximately seven linear feet of piping in the "B' ESW train was affected and required replacement. UT testing was satisfactorily performed on the "A" ESW train to ensure a similar problem did not exist.
"B" ESW train piping replacement was performed in accordance with planned work documents, however at 2100, 3/25/05 all necessary repairs and retests had not been completed. Although only 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> had expired since entering 72-hour Technical Specification Action 3.7.8.A, Callaway Plant proactively decided to commence a reactor plant shutdown in accordance with Technical Specification Action 3.7.8.B for an Inoperable "B" Essential Service Water train. Per 10CFR50.72(b)(2)(i), any initiation of a plant shutdown required by T/S requires notification of the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the initiation. At 2112, Event Notification 41527 was filed with the NRC Operations Center concerning the initiation of the plant shutdown.
At 0300, 3/26/05, with reactor power at 28 percent, Callaway entered Technical Specification Action 3.7.8.B.1 which required the reactor plant to be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. At 0624, 3/26/05 the reactor was declared shutdown and Callaway Plant entered Mode 3. At 0249, 3/27/05 all repairs and retests were completed on the "B" ESW train and it was declared Operable.
Although all repairs to the "B" train of ESW had been completed, it was decided to maintain the unit shutdown and perform additional discretionary work to enhance unit reliability. Examples of the work additions included:
- Repair of a leak on the gas system used to cool the main electrical generator
- Examine and adjust valves used to control the flow of non-radioactive water through the main condenser.
All discretionary repairs were completed and Callaway Plant entered Mode 2 reactor startup, at 0316, 4/2/05. At 1904, Callaway Plant paralleled the main electrical generator to the grid and returned to service.
(If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
The team looked at pump operating history, pump replacement due to degraded flow, potential impact due to the pH excursions in the Ultimate Heat Sink, MIC sample results, piping inspection videos, etc. and all data failed to identify a failure starting mechanism.
Due to the corrosion mechanism identified, the pipe replacement is adequate to prevent the reoccurrence of under-deposit corrosion in the discharge of the "B" ESW pump. The extent of condition UT evaluations was an adequate sample population to provide confidence that there is not wholesale under-deposit corrosion in the ESW system.
IV.
PREVIOUS SIMILAR EVENTS
A review of the Callaway Action Request System (CARS) was conducted to determine if there were any
previous similar events
This review encompassed the time frame of 3/25/02 to 3/25/05. Eleven previous CAR documents were identified that documented leaks in the ESW system. None of these events resulted in a reportable condition. A review was also conducted of LERs submitted within the last three years and no similar LERs were found.
V.
ADDITIONAL INFORMATION
The system and component codes listed below are from the IEEE Standard 805-1984 and IEEE Standard 803A-1984 respectively.
System:
BI Component:
Not Applicable - there were no individual component failures associated with this event.