05000348/LER-2016-001, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications
| ML16161B272 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/09/2016 |
| From: | Gayheart C Southern Co, Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-16-0738 LER 16-001-00 | |
| Download: ML16161B272 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x) 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)(1) |
| 3482016001R00 - NRC Website | |
text
Cheryl A. Gayheart V1ce Pres1dent - Farley June 9, 2016 Southern Nuclear Operating Company, Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford. AL 36312 Tel 334.814.4511 Fax 334.814.4575 Docket Nos.: 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant-Unit 1 Licensee Event Report 2016-001-00 SOUTHERN <<\\
NUCLEAR A SOUTHERN COMPANY NL-16-0738 Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications Ladies and Gentlemen:
This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50.73(a)(2)(i)(B) for Unit 1.
This letter contains no NRC commitments. If you have any questions regarding the submittal, please contact Ms. Julie Collier at (334) 814-4639.
Sincerely, Ms.
. -A.
heart Vice President - Farley CAG/JAC Enclosure: Unit 1 Licensee Event Report 2016-001-00
U.S. Nuclear Regulatory Commission NL-16-0738 Page2 cc:
Southern Nuclear Operating Companv Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. M.D. Meier, Vice President-Regulatory Affairs Mr. D. A. Madison, Vice President - Fleet Operations Mr. B. J. Adams, Vice President - Engineering Mr. C. A. Pierce, Regulatory Affairs Director Ms. B. L. Taylor, Regulatory Affairs Manager-Farley Mr. J. E. Purcell, Operating Experience Coordinator-Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager* Farley Mr. P. K. Niebaum, Senior Resident Inspector* Farley
Enclosure Joseph M. Farley Nuclear Plant-Unit 1 Unit 1 Licensee Event Report 2016-001-00 Condition Prohibited by Technical Soecifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION !APPROVED BY OMB: NO. 315CHI104 EXPIRES: 10/3112018 11-2015) iEs1Jmated, the NRC may not conduct or sponsor end a parson Is no equlrad to respond to, the lnlonnation collacHon.
- 1. FACILITY NAME
~* DOCKET NUMBER
~.PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000- l 348 I OF 3
~.11TLE Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILinES INVOLVED YEAR I SEQUENTIAL I REV NO ACILITY NAME P<JCKET NUMBER MONTH DAY YEAR NUMBER MONTH DAY YEAR 6
9 2 016 ACILITY NAME POCKET NUMBER 04 13 2016 2016 001 -
00
!9. OPERATING MODE
- 11. THIS REPORT IS SUBMnTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201 tbl D 20.2203(alt3ll'l 0 50. 73(a)(2)(11)(A) 0 50.73(a)(2)(viii)(A) 1 D 20.2201 tdl 0 20.2203(a)(3)(11) 0 50. 73(a)(2)(11)(B) 0 50.73(a)(2)(viii)(B)
D 20.2203ta>t1 >
0 20.2203(a)(4) 0 50. 73(a)(2)(111) 0 50.73(a)(2)(1x)(A) 0 20.2203(a)(2)(1) 0 50.36(c)(1)(1)(13A) 0 50.73(a)(2)(1v)(A) 0 50.73(a)(2)(x)
- 10. POWER LEVEL 0 20.2203(a)(2)(11) 0 50.36(c)(1)(11)(A) 0 50. 73(a)(2)(v)(A) 0 73.71(a)(4)
D 20.2203(a)(2)(111)
D 50.36(c)(2) 0 50.73(a)(2)(v)(B)
D 73.71(a)(5) 100%
D 20.2203(a)(2)(1v)
D 50.48(a)(3)(11) 0 50.73(a)(2)(v)(C) 0 73.77(a)(1) 0 20.2203(a)(2)(v)
D 50.73(a)(2)(1)(A) 0 50. 73(a)(2)(v)(D)
D 73.77(a)(2)(1) 0 20.2203(a)(2)(vi)
~
50.73(a)(2)(1)(B)
D 50.73(a)(2)(vll) 0 73.77(a)(2)(11) 0 50.73(a)(2)(1)(C) 0 OTHER Spedfy In Abstract below or In NRC Fonn 31111A
- 12. LICENSEE CONTACT FOR THIS LER
~CENSEE CONTACT ELEPHONE NUMBER (lndude Ares Code}
Julie Collier 334-814-4839 CAUSE SYSTEM COMPONENT MANU*
REPORTABLE
CAUSE
SYSTEM COMPONENT MANU*
REPORTABLE FACTURER TOEPIX FACTURER TOEPIX E
EC BKR V'/121 y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) ~NO SUBMISSION DATE
!ABSTRACT (Limil lo 1400 spacss, i.e, approxlrnale/y 15 single-spaced typawrillen lines)
On 4/12/2016 at 0312 COT, with Unit 1 (U1) at 100 percent power and Unit 2 (U2) In Mode 5, the U2 supply breaker for 1-2R 600V Load Center (LC) was racked out and the control power fuses removed for both U2 supply breaker and U1 supply breaker to support replacing an agastat relay on the U2 supply breaker. On 4/13/2016 at 0456 COT the U1 supply breaker for the 1-2 R 600V LC, tripped open when the control power fuses were restored and would not reclose. Technical Specifications (TS) 3.8.9 Condition A was entered for Unit 1 at 0456 on 4/13/2016 and exited at 0938 on 4/13/2016. Investigation attributed the cause to dirty contacts on the call switch located In the U2 supply breaker cubicle. This condition would have prevented the U1 supply breaker from recloslng If a loss of offsite power had occurred between 04/1212016 at 0312 and 4/13/2016 at 0938, leaving the 1-2R LC de-energized. This caused the LC to be Inoperable for Unit 1 for more than the time allowed by TS 3.8.9 and Is reportable per 10 CFR 50.73(a)(2)(i)(B). This Is not reportable for Unit 2 due to the unit being in Mode 5 and having the necessary portion of the electrical power distribution subsystems operable.
Corrective Action
The U2 supply breaker cell switch was cycled which cleaned the contacts and the U1 supply breaker closed. Post maintenance testing verified operability. Until replacement of the U2 supply breaker cell switch, administrative controls are in place to declare U1 supply breaker inoperable when racked out until the Interlock feature Is verified.
NRC Jo'OKM 366A 11-lfiUJ U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 10131/2018
,............ \\
\\~j LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET Estimated burden per response to ~amply wllh this mandatory collection requast 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons teemed are lncorpo~~tid Into lhellcenslna process and led *II to Industry.
Send commtnls reaan1na bunlen eslfmata to lha FotA. P"rtvacy lll1d lnlorrnallon CollecHons Branch (H F53), O.S. NUcleer Regulatory Commlsslon, Washli!gton, DC 20555-0001, or by lnltmete-mtV to lnlocoiiiCis.Rtso~~n:tOIVC.gOY, and to the Desk l:llftc:er, Office ollnlonnallon and Regulatory Alfalll, NEQ8.102ai!, (3150-0104), Office ol M-gement ll1d Budgtl, Wuhlnglon, DC 20503. II a maans used to inposa an lnlormation CllllectiOn does not clsplay a curraniiY valid OMB ~onlrol number, the NRC may not conduct or sponsor, and a person Is not required to respond to, the Information coMecllon.
Joseph M. Farley Nuclear Plant, Unit 1 05000-348
NARRATIVE
A. PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor Energy Industry Identification Codes are Identified In the text as [XX].
B. DESCRIPTION OF EVENT
YEAR
- 3. LER NUMBER SEQUENTIAL NUMBER 2016 001 On 4/12/2016 at 0312 COT, with Unit 1 (U1) at 100 percent power and Unit 2 (U2) in Mode 5, the U2 supply breaker (ER05-2) for 1-2R 600V Load Center (LC), which can supply power for both U1 and U2, was racked out and the control power fuses removed for both U2 supply breaker and U1 supply breaker (ER02-1) to support replacing an agastat relay on ER05-2. The removal of the fuses for ER02-1 caused all of the protective relays for that breaker to be in a de-energized state. On 4/13/2016 at 0456 COT, ER02-1 tripped open when the control power fuses were reinstalled. An attempt to reclose the breaker was unsuccessful.
Breakers ER02-1 and ER05-2 contain permissive interlocks that prevent these breakers from being closed at the same time. A contact on the ER05-2 cell switch was dirty/degraded preventing continuity between the two sides of the contact. The cell switch failed to send a signal to indicate that ER05-2 was in the racked-out position, which prevented breaker ER02-1 from reclosing.
Technical Specifications (TS) 3.8.9 Condition A was entered for Unit 1 at 0456 on 4/13/2016 when the breaker tripped open and exited at 0938 on 4/13/2016 after the contacts were cleaned on the cell switch, the control power fuses replaced and the 1-2R LC was restored to operable status.
At the time of this event Unit 2 was in Mode 5 in a refueling outage. The TS is not applicable in Mode 5.
Unit 2 had the necessary portion of the electrical power distribution subsystems operable to support the equipment required to be operable.
C. UNIT STATUS AT TIME OF EVENT Unit 1, Mode 1, 100 percent power Unit 2, Mode 5, 0 percent power
D. CAUSE OF EVENT
The cause of the supply breaker being unable to reclose was determined to be a dirty/degraded contact in the cell switch of EROS-2 relay, preventing the interlock from reclosing.
E. REPORT ABILITY ANALYSIS AND SAFETY ASSESSMENT If a loss of offsite power had occurred between 4/12/2016 at 0312 and 4/13/2016 at 0938, ER02-1 would have opened but would not have reclosed due to the contact on the cell switch on ER05-2, leaving the 1-2R LC de-energized. Therefore an LEA is required based on the 1-2R Load Center being inoperable for Unit 1 for longer than the TS 3.8.9 required action completion time. The breaker was in an inoperable condition for approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This is reportable In accordance with 10 CFR 50.73(a)(2)(i)(B).
REV NO.
00
r-mc YEAR
- 3. LER NUMBER SEQUENTIAL NUMBER 2016 001 The Farley onsite standby power source is provided from four Emergency Diesel Generators (EDG)
(1-2A, 1 B, 28, and 1 C). The 1 C EDG has a continuous service rating of 2,850 kW and the 1-2A, 1 B, 28 EDGs have ratings of 4,075 kW. EDGs 1-2A and 1 C are the A-train and EDGs 1 B and 28 are the B-train.
Farley also has a fifth diesel generator (2C), rated at 2,850 kW. that serves as a station blackout diesel and can be manually aligned to supply 8-train power to either unit and supply power to loss-of-site-power (LOSP) loads.
During the time the 1-2R Load Center was inoperable for Unit 1. the EDGs 1-2A (A-train) and the 1 B (S-train) were operable and available to support any event on Unit 1, and the 2C station blackout EDG was functional and available. For Unit 2 the 28 EDG was operable.
No other systems or components were affected by the condition described in this report. During the time of the inoperable LC no events occurred which challenged the offsite power supplies, and there was no loss of safety function. Therefore, the safety and health of the public was not adversely affected.
F. CORRECTIVE ACTION
The cell switch was cycled which cleaned the contacts, allowing ER02-1 to close. The cell switch function which failed is electrically bypassed when ER05-2 is racked-ln. Post maintenance testing with ER05-2 In the racked-in position verified Operability of ER02-1. Administrative controls are in place to declare ER02-1 inoperable when EROS-2 is racked out until the interlock Is verified or ER05-2 cell switch is replaced.
The EROS-2 cell switch is scheduled for replacement In the next Unit 2 Refueling Outage. A preventive maintenance task is being developed for more frequent replacement of this component and other similar breakers.
G. ADDITIONAL INFORMATION
Failed Components:
Low-Voltage Power System [EC], Westinghouse Other system affected:
None Commitment Information:
None
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