05000397/LER-2014-001, Regarding Secondary Containment Pressure Exceeded
| ML14087A008 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/10/2014 |
| From: | Javorik A Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| G02-14-034 LER 14-001-00 | |
| Download: ML14087A008 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 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), Loss of Safety Function |
| 3972014001R00 - NRC Website | |
text
Alex L Javoilk RCoumbla GO*eruln Staton AMR
- P.O.
Box 968, PE04 NORHW STRWOMan WA992-
"Of Ph. S0O.W",6551 F. 509.377.4150 March 10, 2014 G02-14-034 10 CFA 50.73 U.S. Nule Regupl Commission ATTN: Document Control Desk Washington, O.C. 20555-0001 Subject COLUMBIA GENERATING STATION, DOCKET NO. 50-397 U
U EVENT NRPORT NO. M1400140
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2014-001,00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 80.73(a)(2)v)(C), and 10 CFR 50.73(aX2)(v)(D).
There are no commitments being made to the NRC by this letter. If you have any questions or require additional Information, please contact Mr. J.R. Trautvetter, Regulatory Compliance Supervisor, at (509) 377-4337.
Respectfully, A, L. Javorik Vice President, Engineering Attachment: Licensee Event Report 2014-001 -00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C AJ Rapacz - BPA/1399 WA Horin - Winston & Strewn
'IWt XPORMN "07U4IMEREULATORYCOMhlhSSION APPROVED S1CUD=NO.3101=04 EXPIE 801131'1/2017 (01-2014)
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Send comments reprflng budrde esie to the FOIA, P'M and Information Collections LIC SEc EVh REPORT (LER)
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- 1. FCI.ITY E
N.AOCKETMEM R
& P Columbia Generating Station 06=1 397 1
OF 5 Secondary Containment Pressure Exceeded S. EVENT DATE
- 6. LEo NUMBER
- 7. REPORT DATE
&. OTHR ACILIT1 INVOLVED MONTH jOAY REV MONTH FACIUTY NAME DOCKET NUMBER.
MONTH DAY YEAR YEAR SENUMENALR V
N O.
T DAY YEAR 0
04j0 0
j FACILITY NAME DOCKET NUMBER 01 09 2014 2014 - 001 - 00 03 10 2014 05jo0 8.OPERATIING MIOVE It. TIS REPORT Is SualMITTE PUMAUANT TO THE ASOWNEMENTS OF 10 CFA 1: (Check 11 that ppy C) 20.2201(b)
C3 20.2203(a)(3X1i)
E3 s0.7,3(aX(2)(1)(c)
E3 50.73(a)(2)(Vll) r0] 20.2201(d) 1"0 20.2203(a)(3)(ii) 3 60.73(aX2)(0)(A) 0 50.73(a)(2)(viii)(A) 0 20.2203 (a)(1) 0] 20.2203(aX4)
[3 50.73(a)(2)(1l)(8) 0 50.73(a)(2)(viil)(B)
.E 20.2203(a)(2)(I) 0] 60,360()(1)(IXA) 0 50.73(aX2)(ili)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL.)
20.20aX2)(i) 03 50.36(c)(IXII)(A) 13 50.73(aX2)(iv)(A) 0 50.73(a)(2)(x) 13 20.2203(a)(2)(it1)
E0 50.36(C)(2) 0 50.73(a)(2)(v)(A) 03 73.71(a)(4) 0] 20.2203(a)(2XIv) 13 50.46(a)(3)(11)
E3 50.73(aX2)(v)(B) 3 73.71(a)(5) 10 20.2203(a)(2)(v)
E3 60.73(a)2)(iXA) 6 50.73(a)(2)(v)(C) 0 OTHER Specify in Abstract below or In 0] 20.2203(a)(2)(vi)
[3 50.73(aX2)(I)(B) 6 50.73(a)(2)(v)(D)
. LNCENRE CONTACT FOR ToIS LEA FACILITY NAME TELEPHONE NUMBER (Incude Area Code)
Des*r6e Wolfgramm, Senior Ucensing Engineer 509-377-4792 1&. CML E O INE FOR EACH COMPONET rFAILUREIDESN IBED IN THIS REPORTr
CAUSE
SYSTEM COMPONENT MANU.
REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
'14. SUPLM=ENTAL Eow 7
- 16. EXPECTED "
MONTH DAY YEAR YES (ff yes complete 1. EXPECTED SUBMISSION DATE)
Q3 NO DAT 04
ý30 2014
.II___Il
_____III1_
__I__I_________
.T ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On January 9, 2014 at 1743 and 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br /> secondary containment was declared Inoperable during repositioning of the dampers. These two events had durations of 3 and 2 minutes respectively. Control Room operators took manual control of the Reactor Building Exhaust Air flow system to restore secondary containment in the first event, and the controller restored pressure automatically In the second.
On January 15, 2014 at 0907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br /> and February 17, 2014 at 0304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br /> secondary containment was declared inoperable during repositioning of the dampers and during high winds respectively. These two events had durations of 6 and 2 minutes respectively. The system controller automatically restored secondary containment.
differential pressure in both events.
In each of these events secondary containment vacuum was not maintained greater than or equal to 0.25 inches of vacuum water gauge as required by Technical Specification 3.6.4.1. While Technical Specification limits were exceeded, the resulting pressure excursion was bounded by analytical results, and thus there were no safety consequences for this event. The cause(s) for the event Is currently under investigation. A supplemental LER is planned for when testing and investigation is completed. Corrective actions will be developed based upon the
cause(s)
26158 R6 NRC Form 366 (01-2014)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEO T YOUD: NO. 31604104 EXPIRES: 018112017 (01-2014)
Esimated buen pet respon comply ith is mandatory colloction request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported less lend are Incorporled into the licening pMcess and ted bacd to knustry.
Send commernts regarding burden estimate to the FOIA, Privacy and Wtonnrlaon Collections LICENSEE EVENT REPORT (LER) knh (T-6 Fq), US. Nuclear Raepdatory Codsston,,
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1.FACILITY NAU.OOCICE
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PAGQE Colutbia Gm t tatinI YEAR SEQUEMAL REV 05M 9
YEA -01 2
OF 5
- 2014 001 00 NIARATWI Plont CoNItions Event 1: January 9, 2014 at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br /> Event 2: January 9, 2014 at 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br /> Event 3: January 15, 2014 at 0907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br /> Event 4: February 17, 2014 at 0304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br /> At the time of all events, the plant was operating In Mode 1 at 100% power. Them were no structures, systems, or components that were inoperable at the start of any of the events that contributed to the events.
Event Descipto Events 1 &2-On January 9, 2014 at 1743 and 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br /> secondary containment vacuum was not maintained while Reactor Building Outside Air (ROA) heating coil face and bypass dampers were repositioning due to outside ambient temperature fluctuation past the set point. These dampers and heating coil allow for outside air to be heated as it enters the system. These two events had durations of 3 and 2 minutes respectively. In Event 1 control room operators took manual control of the Reactor Building Exhaust Air (REA) flow in-service differential pressure controller (DPIC) (REA-DPIC-1A) to restore secondary containment vacuum to greater than 0.25 inches of vacuum water gauge. In Event 2 the REA in-service controller (REA-DPIC-1 A) automatically restored secondary containment vacuum to greater than 0.25 inches water gauge (inwg).
Event 3 -
On January 15, 2014 at 0907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br /> secondary containment vacuum was not maintained while the ROA heating coil face and bypass dampers were repositioning due to outside ambient temperature fluctuation past the set point. This event had duration of 6 minutes. In this event the REA in-service controller (REA-DPIC-1A) automatically restored secondary containment vacuum to greater than 0.25 inwg.
Event 4 -
On February 17, 2014 at 0304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br /> secondary containment vacuum was not maintained during a period of high winds. This event had duration of 2 minutes. In this event the REA in-service controller (REA-DPIC-1B) automatically restored secondary containment vacuum to greater than 0.25 inwg.
In each event described above, because Reactor Building [NG] vacuum decreased below 0.25 inches of water gauge, secondary containment was logged as inoperable in the surveillance log and Technical Specification 3.6.4.1 Action A was entered.
26158A R3 26158A R3 NRC FORM 368A (01-2014)