05000397/LER-2013-007, Regarding Secondary Containment Pressure Exceeded During Severe Weather Conditions
| ML13310A306 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/24/2013 |
| From: | Javorik A Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-13-149 LER 13-007-00 | |
| Download: ML13310A306 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(1) |
| 3972013007R00 - NRC Website | |
text
f'ýt'Alex L Javoulk Columbia Generating Station P.O. Box 968, PE04 Richland, WA 99352-0968 N M THW EST Ph. 509.377.85551F. 509.377.4150 aljavork@ energy-northwestcom October 24, 2013 G02-13-149 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. 2013-007-00
Dear Sir or Madam:
Transmitted herewith is Ucensee Event Report No. 2013-007-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(v)(C), and 10 CFR 50.73(a)(2)(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 2013-007-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C AJ Rapacz - BPA/1 399 WA'Horin "Winston & Strawn
NRC FORI* 66 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 OF3
- 4. TITLE Secondary Containment Pressure Exceeded During Severe Weather Conditions
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIALI REV MONTH DAY YEAR FACIUTY NAME DOCKET NUMBER NUMBER NO.
I 05000 08 25 2013 2013 -007 - 00 10 24 2013 FACI0TYNAME jDOCKET NUMBER g. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMEN-S OF 10 CFR §: (Check all that appl) 1 [l 20.2201(b) 03 20.2203(a)(3)(i)
[3 50.73(a)(2)(i)(C)
[3 50.73(a)(2)(vii)
[3 20.2201(d)
C3 20.2203(a)(3)(ii) 0 50.73(a)(2)(il)(A) 03 50.73(a)(2)(vili)(A)
(l 20.2203 (a)(1)
[0 20.2203(a)(4) 03 50.73(a)(2)(i1)(B) 0 50.73(a)(2)(vilii)(B)
E3l 20.2203(a)(2)(i)
- 0) 50.36(c)(1)(i)(A)
C-50.73(a)(2Xiii) 03 50.73(a)(2)(Ix)(A)
- 10. POWER LEVEL [3 20.2203(a)(2)(11)
[] 50.36(c)(1)(li)(A)
El 50.73(a)(2)(iv)(A) 03 50.73(a)(2)(x) 100 [3 20.2203(a)(2)(Iii)
[3 50.36(c)(2) 03 50.73(a)(2)(v)(A) 0J 73.71(a)(4) rO] 20.2203(a)(2)(iv) 03 50.46(a)(3)(il)
I-50.73(a)(2)(v)(B) 03 73.71(a)(5) 0 20.2203(a)(2)(v) 03 50.73(a)(2)(i)(A)
C3 50.73(a)(2)(v)(C) 0 OTHER 0l 20.2203(aX2)(vi)
[0 50.73(a)(2)(1)(B) 1 50.73(a)(2)(v)(D)
Specify In Abstract below
_NRC or in Technical Specification secondary containment pressure is reached.
Assessment of Safety Consequences
This event resulted in an unplanned entry into LCO 3.6.4.1.A. Secondary containment pressure was above -0.25 inwg for no more than 160 seconds. The peak pressure during this event was -0.03 inwg. While the actual pressure was beyond the range allowed by Technical Specifications, the purpose of maintaining a slight vacuum is to assist in drawdown of secondary containment to support accident response of the safety related SGT system. Existing engineering analysis demonstrates that for this event, the drawdown credited in accident response could have been attained using either of the two available trains of the SGT system, thus there were no potential safety consequences. There was no actual safety consequence associated with this event since no event involving radiological hazards were experienced during the event.
Energy Industry Identification System (EIIS) Information Energy Industry Identification System (EIIS) Information codes from IEEE Standards 805-1984 and 803-1983 are represented in brackets as [XX] and [XXX] throughout the body of the narrative.
26158 R5