05000397/LER-2011-002, Regarding Loss of Shutdown Cooling Due to Logic Card Failure
| ML11305A078 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/25/2011 |
| From: | Sawatzke B Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-11-172 LER 11-002-00 | |
| Download: ML11305A078 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3972011002R00 - NRC Website | |
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-`11Bradley J. Sawatzke Columbia Generating Station P.O. Box 968, PE08 Richland, WA 99352-0968 r~NORTHWESTan.WA0 6
Ph. 509.377.4300 1 F. 509.377.4150 bjsawatzke @ energy-northwest.com October 25, 2011 G02-11-172 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSEE EVENT REPORT NO. 2011-002-00
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2011-002-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(v)(B) and 10 CFR 50.73(a)(2)(iv)(A). The enclosed report discusses items of reportability and corrective actions taken related to a loss of shutdown cooling event associated with a logic card failure that occurred on August 27, 2011.
There are no commitments being made to the NRC herein. If you have any questions or require additional information, please contact Mr. ZK Dunham at (509) 377-4735.
FIespecfully, S&
BJ Sawatzke Vice President, Nuclear Generation & Chief Nuclear Officer
Enclosure:
Licensee Event Report 2011-002-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C RN Sherman - BPA/1 399 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 collection.
- 3. PAGE Columbia Generating Station 05000397 1 OFF3
- 4. TITLE Loss of Shutdown Cooling due to Logic Card Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 08 27 2011 2011 - 002 - 00 10 25 2011 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 4 El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
[o 20.2201(d)
El 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
El 20.2203 (a)(1)
El 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 0 El 20.2203(a)(2)(iii)
[I 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in and ultimately fuel damage. However, the actual significance was limited due to the short duration of the SDC outage and minimal temperature rise with substantial margin to 200 degrees.
If the event had occurred earlier in the refueling outage shortly after shutdown, the significance would have been greater since the time to 200 degrees F is much shorter and could have resulted in an Unintended and unplanned MODE change from MODE 4 to MODE 3.
Had the logic card failure occurred in Modes 1 or 2, the same isolations and actuations would occur but would not be expected to result in a plant trip. The resulting isolations would require operator intervention to mitigate, but all response actions are covered by existing station procedures.
Cause of Event
The reason for the loss of RPS-B was due to a spurious undervoltage trip signal from a logic board which is part of the EPA circuit breaker for RPS-B. The spurious underivoltage signal was caused by a logic board fault, which has been identified as the direct cause of the event. The root carse is that Energy Northwest was not proactive in replacing older, obsolete logic boardswith new models recommended: by the vendor.
Similar Events
No previous occurrences involving a logic board failure leading to an EPA breaker trip have been identified at Columbia.
Further Corrective Actions At the time of the event, a total of six of the GE Mbdel-147D8652G007,logic boards were installed in the plant.
Two were replaced as part of the immediate co-rective action6s and the remaining four'will be replaced as part of the corrective actions to prevent recurrence. Analysis of the logic board by the vendor was inconclusive.
Energy Industry Identification System (EIIS) Information codes from IEEE Standards 805-1984 and 803-1983 are represented in brackets as [XX], [XXX] and [XXXX] throughout the body of the narrative.
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