05000348/LER-2012-005, Joseph M Farley Nuclear Plant, Unit 1 Regarding Unit Shutdown Required by Technical Specification 3.8.1
| ML12269A168 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/24/2012 |
| From: | Lynch T Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-12-1801 LER 12-005-00 | |
| Download: ML12269A168 (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) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3482012005R00 - NRC Website | |
text
Thomas A. Lynch Southern Nuclear Vice President
- Farley Operating Company, Inc.
Farlev Nuclear Plant Post Office Drawer 470 Ashford. Alabama 36312 Tel 334.814 4511 Fax334.814.4728 September 24, 2012 Docket Nos.: 50-348 NL-12-1801 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Ucensee Event Report 2012-005-00 Unit Shutdown Required by Technical Specification 3.8.1 Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73 (a)(2)(i) (A), Southern Nuclear Operating Company (SNC) hereby submits the enclosed Licensee Event Report 2012-005-00. This letter contains no commitments to the NRC. If you have any questions regarding this submittal, please contact Doug McKinney at (205) 992-5982.
Sincerely, 1frJ T. A. Lynch Vice President - Farley TAl.JWEB Enclosure: Unit 1 Licensee Event Report 2012-005-00 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RlYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. M.O. Miller, Senior Project Engineer, NRC Region II
Joseph M. Fariey Nuclear Plant - Unit 1 NL-12-1801 Unit Shutdown Required by Technical Specification 3.8.1 Enclosure Unit 1 Licensee Event Report 2012-005-00
NflC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS: NO. 3150-0104 EXPIRES: 1013112013 (10-2010)
Estimated burden per response \\0 comply w~h Ihis mandatory collection reques!: SO hOUfS. Reported lessons learned are incorporated into the licensing process and fed back 10 IndUSIr& Send comments regarding burden estimate to the FOIA/Privacy Section
- - 5 F53), U.S. Nuclear Regulatory Commission. Washington, DC 20555-0001, or by internet e-mail 10 LICENSEE EVENT REPORT (LER) infocoliects.r6Source@nrc.gov, and \\0 the Desk Officer, Office 01 Information and RegulaloryAffairs, NE 8-10202, (3150-0104), OffICe 01 Mansqament and 8udget, WaShington, DC 20503. II s means used to impose an information collecllon does not display a currenlly vand OMS control number, the NRC may not conduct or sponsor, and a person is not required to respond 10, Ihe information collection.
- 13. PAGE Joseph M Farley Nuclear Plant-Unit 1 05000348 1 OF 4
- 14. TITLE Unit Shutdown Required by Technical Specification 3.8.1
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACIUTlES INVOLVED FACILlTY NAME DOCKET NUMBER SEQUENTIAL REV MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 07 26 2012 2012 - 005 -
00 09 24 2012 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check a/l that apply) o 20.2201 (b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vli) 1 o 20.2201 (d) o 2O.2203(a)(3)(ji) o 50.73(a)(2)(iI)(A) o 5O.73(a)(2)(vlll)(A) o 20.2203(a)(1) o 2O.2203(a)(4) o 50.73(a)(2)(ii)(B) o 5O.73(a)(2)(vlli)(B) o 20.2203(a)(2)(i) o 50.36(c)(1 )(I)(A) o 50.73(a)(2)(1II) o 50.73(a)(2)(lx)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(li) o 50.36(c)(1 )(ii)(A) o 50.73(a)(2)(iv)(A) o 5O.73(a)(2)(x) o 2O.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71(a)(4) o 2O.2203(a){2)(lv) o 50.46(a)(3)(ii) o 5O.73(a)(2)(v)(B) o 73.71(a)(5) 100 o 2O.2203(a)(2)(v) 181 SO.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 2O.2203(a)(2)(vi) o 5O.73(a)(2)(1)(B) o 50.73(a)(2)(v)(D)
Specify in Abstract below or In NRC Form 3S8A
- 12. LICENSEE CONTACT FOR THIS LER FACIUTY NAME TELEPHONE NUMBER (Include Arae Coda)
Joseph M Farley Nuclear Plant I B. D. McKinney I Regulatory Response Mgr.
205-992-5982 I
- 13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU*
REPORTABLE MANU*
REPORTABLE
CAUSE
SYSTEM COMPONENT
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX FACTURER TO EPIX E
EK DG F010 Y
E EK FCO R290 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION
[] YES (If yes, complete 15. EXPECTED SUBMISSION DA TE) 181 NO DATE ABSTRACT (Limit 10 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On July 26, 2012, at 2151 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.184555e-4 months <br /> COT with Unit 1 operating in Mode 1 at approximately 100 percent rated thermal power, a reactor shutdown was conducted in accordance with Condition H of Limiting Condition for Operation (lCO) 3.8.1 following expiration of the Completion Time allowed for compliance with Condition 8.4 of that lCO. The Unit was stabilized in Mode 5 pending necessary repairs to EDG 1 B and its return to operability. Previously, on July 16,2012, lCO 3.8.1 was voluntarily entered and EDG 18 was removed from service for planned 24-month maintenance.
Following completion of the maintenance on July 20, 2012, during the post-maintenance operation evaluation run, oscillations occurred in certain EDG parameters including power output.
Subsequently, within minutes, EDG 1 B unexpectedly shutdown. The initial investigation included an examination of all cylinders which led to the discovery of a damaged piston and cylinder liner on the #12 cylinder. Subsequent investigation determined the immediate cause of the EDG 1 B shutdown was a high crankcase pressure trip; the underlying cause of the engine shutdown was the malfunction of the engine's intercooler thermostatic bypass valve (Q1 R43V0561) due to the failure of one of three !hennal actuating devices. There were no adverse effects on plant safety or on the health and safety of the public as a result of this event.
NRC FORM 366 (1()'20101
4 A. REQUIREMENT FOR REPORT This report is required per 10 CFR 50.73(a)(2)(i)(A) due to the completion of a plant shutdown pursuant to Technical Specifications 3.8.1, wAC Sources - Operating".
B. UNIT STATUSATTIME OF EVENT At the time of this event, Unit 1 was in Mode 1 at approximately 100 percent rated thermal power.
C. DESCRIPTION OF EVENT
On July 26, 2012 at 2151 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.184555e-4 months <br /> CDT, with Unit 1 operating in Mode 1 at approximately 100 percent rated thermal power, the Unit operators commenced a reactor shutdown in accordance with Condition H of Limiting Condition for Operation (LCO) 3.8.1 following expiration of the Completion Time allowed for compliance with Condition 8.4 of that LCO. The Unit was subsequently stabilized in Mode 5 pending necessary repairs to EDG 18 and its retum to operability.
In accordance with 10 CFR 50.72(b)(2)(i) which specifies the reporting requirement for a Technical Specification required shutdown, a 4-hour non-emergency notification was made on July 26, 2012, at 2224 CDT for Unit 1 (Event Notification 48140).
D. CAUSE OF EVENT
On July 16, 2012, at approximately 2152 CDT, Technical Specification LCO 3.8.1 was voluntarily entered on Plant Farley Unit 1 and EDG 18 was removed from service for the purpose of performing the planned 24-month maintenance activities. Five days into the Required Action Statement (RAS), the maintenance was completed and EDG 18 began a post-maintenance operation evaluation run. Approximately two hours into the evaluation run, soon after reaching a fully loaded condition, oscillations were noted to occur for certain EDG parameters (such as load, output amps and power, scavenging air pressure, and governor position). Subsequently, within a few minutes, EDG 1 B unexpectedly shutdown. The initial investigation included an examination of all cylinders which led to the discovery of a damaged piston and cylinder liner on the #12 cylinder.
Subsequent investigation determined that the immediate cause of the EDG 1 B shutdown was a high crankcase pressure trip; the underlying cause of the engine shutdown was the malfunction of the engine's intercooler thermostatic bypass valve (Q1 R43V0561) due to the failure of one of three thermal actuating devices. The malfunction of the thermostatic bypass valve prevented adequate cooling of the intercooler system that in tum led to EDG overheating and cylinder/piston breakdown.
The extent of repairs required to return EDG 18 to operability required a period of time that exceeded the Completion Time allowed by Condition H of LCO 3.8.1, and the Unit was shut down and placed in Mode 5 pursuant to the associated Required Action.
G. ADDITIONAL INFORMATION
- 1) Failed Components:
Component 1:
Pielstick PC-2 Diesel Generator Manufacturer 1 :
Fairbanks Morse Engine Division of Coltec Industries Component 2:
Robertshaw Valve 1-1285-F Manufacturer 2:
Robertshaw Industrial Products Component 3:
Valve Power Pill 96995A20 Manufacturer 3:
Robertshaw Industrial Products
- 2)
Previous Similar Events
There have been no failures of the subject power pili at Plant Farley in the previous three years. See Industry experience identified in section H below.
- 3) Energy Industry Identification System Code:
EDG 1 - EK Thermostatic Control Valve - FCO
- 4) Commitment Information:
This report does not create any new permanent licensing commitments.
H. PREVIOUS INDUSTRY OPERATING EXPERIENCE:
- 1) OE18813 - Failure of Diesel Generator Jacket Water Temperature Control Valve (July 2004)
- 2) OE34938 - High Emergency Diesel Generator Jacket Water Temperature Due to Failed Temperature Regulator (November 2011)
NRC FORM 388A (11).2010)