05000397/LER-2013-002, Main Control Room Cooler Failed Surveillance
| ML13141A288 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/01/2013 |
| From: | Javorik A Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-13-069 LER 13-002-00 | |
| Download: ML13141A288 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(0) 10 CFR 50.73(a)(2)(ix)(A) 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) |
| 3972013002R00 - NRC Website | |
text
Alex L Javodk P.O. Box 988. PE04 RWIhiWidn WA 9962-09=8 Ph. 5*9/.88 1 F. 609-3"7.2354 May 1, 2013 G02-13-069 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMSIA GENIRATINQ STATrON, DOCKET NO. W049W LICENSEE EVENT REPORT NO. 2013,400
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2013-002-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFA 50.73(a)(2)(t)(B)..
There are no commitments being made to the NRC by this letter. If you have any questions or require additional information, please oontact Ms. LL Williams at (500) 377-8148.
Respectfully, AL Javorik Vice President, Engineering Attachment: Licensee Event Report 2013-002-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C AJ Rapacz - BPA/1399 WA Horin - Winston & Strawn
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150"0104 EXPIRES 10(31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person Is not required to respond to, the Information collctio.
i. FACILJTY NAME Z DOCKET N ERP Columbia Generating Station 05000397 1 OF3
- 4. TITLE Main Control Room Cooler Failed Surveillance_
O EVNT T DATYEA
.LEAR NEUMER" RPO E
OT FACI ES INVRED MONT DAY YEAR YEAR SEQUENTIALR.
MONTH DAY YEAR FACIUTY NAME DOCKET NUMBER NUBE I NjO j0'000 FACIUTY NAME DOCKET NUMBER 03 02 2013 2013 - 002 - 00 05 01 2013 05000 1
"1 20.2201(b)
E 20.2203(a)(3)(i)
E3 50.73(a)(2)(i)(C)
E3 50.73(a)(2)(vil)
C3 20.2201(d) t3 20.2203(a)(3)(il) 03 60.73(a)(2)(UXA)
C3 50.73(aX2)(vill)(A)
E3 20.2203 (a)(1)
E3 20.2203(a)(4)
C3 50.73(a)(2)(0)(B)
E3 50.73(a)(2)(vlil)(B) 0__
O 20.2203(a)(2)(i)
E] 50.36(c)(1)(IXA)
C3 60.73(a)(2Xui)
(3 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E3 20.2203(a)(2Xii) 13 50.36(c)(1)(IXA)
Cr 50.73(a)(2){ivXA)
C3 50.73(a)(2)(x) 100 0 20.2203a)(2)(,i)
C3 50.26(C)(2)
E3 50.73(a)(2XvXA) 13 73.71(a)(4)
O 20.2203(a)(2)(iv)
C) 50.46(a)(3)(9l)
E3 50.73(a)(2)(v)(B) 0 73.71(aX5)
' 20.2203(a)(2Xv) 3 6o0.73(aX2)(l)(A)
C3 50.73(a)(2XvxC)
E3 OTHER C3 20.2203(a)(2)(vi) a 60.73(a)(2)(tXB)
- 0) 50.73(a)(2)(v)(o)
Specify In Abstract below
- - or In NRC Form 368A FACIUTY NAME TELEPHONE NUMBER (Include Area Code)
M. Hedges 509-377-8277 CAUSE SYTE COPOEN THIS-REPORTREdOTA OM O.
LNEORA CPO NTE CAUSE SYSTEM I COMPONENT FRMANUE
.E___X
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX FACTURER TO EPIX E
VI CLR PME5 Y
C3 YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
U NO T
I_
iI__
II I L
ABSTRACT (Limit to 1400 spaces, Le., approximately 15 single-spaced "ewritten lines)
In October 2012, it was determined that the Technical Specification (TS) surveillance procedure to verify that each control room air conditioning (AC) subsystem has the capability to remove the assumed heat load for TS Surveillance Requirement (SR) 3.7.4.1 did not satisfy the surveillance requirement. The methodology for the existing surveillance had been In use since 1998 around the time Energy Northwest converted to the Improved Technical Specifications. TS SR 3.0.3 was Invoked and a new surveillance procedure was developed. On March 2, 2013, while performing the new surveillance procedure, the test results revealed that the air handler thermal performance for the WA" train did not meet the acceptance criteria. This failure to satisfy SR 3.7.4.1 in March, following entry Into SR 3.0.3, Is reportable under 10 CFR 50.73(aX2)(i)(B) - Any operation or condition which was prohibited by the plant's technical specifications.
The control room AC subsystem has been cleaned, retested, and returned to operable status.
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NRC FORM M; N.
.N...
. "GATORY COMMISONO (10-2010)
LICENSEE EVENT REPORT (LER)
CONTINUUATION SHEET YEAR SEOUENTIN.
REV' Columbia Generating Station 0100039' NUMBER NO.
20F3 2013 00 -2 N A R R A.
TIV E.
.L
. L.......
NARRATIVE
PLANT CONDITIONS
At the time of event, the plant WM Opet in Mode 1 at 100% poWer.
EVENT DESCRIPTION
In October 2012, it was determined that the Technical Specification (TS) surveillance procedure to verify that each control room air conditioning (AC) subsystem [VI) has the capability to remove the assumed heat load for TS Surveillance Requirement (SR) 3.7.4.1 did not satisfy the surveillance requirement. The methodology for the existing surveillance had been In use since 1998 around the time Energy Northwest converted to the Improved Technical Specifications. TS SR 3.0.3 was invoked. An Informational test was performed on November 3, 2012, indicating acceptable performance of the cooler (CLRj. A new surveillance procedure was developed and on March 2, 2013, while perfomtig the now surveillance, the test results revealed that the air handler thermal performance for the "A" train did not meet the acceptance criteria. This failure to satisfy SR 3.7.4.1 in March, following entry into SR 3.0.3, Is reportable under 10 CFR 50.73(a)(2)(1)(B) - Any operation or condition which was prohibited by the plant's technical specifications.
IMMEDIATE CORRECTIVE ACTION
- Addition of Hydrogen Peroxide to the service water spray ponds to kill biological material in the cooling water.
" Cleaning and Inspection of the air side of the cooling coils.
" Cleaning, flushing and inspection of the water side of the cooling coils [CCL]
" Adjustment of the water flow to balance coil flow and heat removal capacity.
A final performance of the test on March 21, 2013 demonstrated heat removal capacity significantly above the minimum acceptance criteria.
CAUSE
The direct cause was determined to be macro-fouling of the water side of the tubes. The presence of large anode deposits, due to degradation of the zinc sacrificial anode, and sediment in the lower tubes of the cooling coils were blocking flow, The apparent cause was lack Of a periodic performance test. With no component specific periodic performance test specified timely identification of degradation, and subsequent action to mitigate the degradation, was not possible to prevent component failure. No routine surveillance on this cooler had been performed for 16 years.
Contributing to this failure was a lack of procedural guidance to balance flow through the cooling coils. The control room coolers are unique In that they are the only double coil coolers used for service water systems [BI]. There is no flow indication for the Individual coils, only the total flow. Thermal performance testing found that flow was not properly balanced between the coils.
Another contributing cause was a general Increase in the sediment levels of the service water system.
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4,,.
ý..'b NRC FORM *..A U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
- 1. FA NAME II NB
- 3. P AG'0 YEAR SEQUENTIAL REV Columbia Generating Station 9070003 NUMBER NO.
30F3 2013 -002-00 NARRAT.
IVEI I
IIIII NARRATIVE FURTHER CORRECTIVE ACTION The surveillance procedure for the control room cooler will be scheduled and performed on a routine basis.
Develop periodic inspection, cleaning, and anode replacement plan for all coolers.
ASSESSMENT OF SAFETY CONSEQUENCES
The main control room has two divisions of air handling units, each with the capability to maintain temperatures within the required limits during accident conditions. The main control room air coolers are required to have a minimum efficiency of 65% to provide the required cooling for a design basis event. In November 2012, the measured efficiency of the WA train AC was 67% as obtained by a maintenance test. The measured efficiency for the W,6,"
train AC in March 2013 was 62.6%. The "B" train AC efficiency was greater than 65%. The "B" train AC was fully capable of maintaining required control room temperatures. The "A" train AC was still capable of providing adequate cooling for most situations. Since November 2012 the "B" train was not been available for service on three occasions each with an outage duration of less than I day. During these times the "A" train would still have been capable of maintaining the control room within the required limits due to actual conditions being significantly less than design basis conditions (ambient temperature of 105°F and service water temperature of 77*F).
In addition to the coolers utilizing service water, the main control room AC subsystem also has the capability to be aligned to emergency chillers [KMJ, which provide additional cooling capability. Each division of the main control room air handler has two sets of coolers. One emergency cooler and one for normal HVAC.
Both emergency coolers can be lined up to either service water or an emergency chiller, a clean closed-loop system. Typically, the "A" train Is lined up to service water and the "B" train to an emergency chiller.
The safety significance of one main control room cooler having a slightly reduced efficiency was minimal.
SIMILAR EVENTS
A review of various databases at Columbia found no similar Issues of a component not being tested per surveillance.
ENERGY INDUSTRY IDENTIFICATION SYSTEM (EllS) INFORMATION COMES ENS codes are bracwed 0 Mer apic~able In the navratlve.
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