05000397/LER-1917-003, Regarding Momentary Loss of Secondary Containment Due to Weather
| ML17236A455 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/24/2017 |
| From: | Javorik A Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-17-154 LER 17-003-00 | |
| Download: ML17236A455 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(ix)(A) 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 3971917003R00 - NRC Website | |
text
G02-17-154 ENERGY NORTHWEST U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Alex L. Javorik Columbia Generating Station P.O. Box 968, MD PE04 Richland, WA 99352-0968 Ph. 509-377-8555 j F. 509-377-4150 aljavorik@energy-northwest.com 10 CFR 50.73
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSEE EVENT REPORT NO. 2017-003-00
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2017-003-00 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 Nuclear Regulatory Commission by this letter. If you have any questions or require additional information, please contact Ms.
D.M. Wolfgramm, Regulatory Compliance Supervisor, at (509) 377-4792.
Executed on this Z,&j'C-day of ~to17.
Respectfully, orik Vice President, Engineering Attachment: Licensee Event Report 2017-003-00 cc:
NRC Region IV Regional Admin NRC Region IV Project Manager NRC Senior Resident lnspector/988C C.D. Sonoda-BPA/1399 W.A. Horin -Winston & Strawn August 24, 2017
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 10/31/2018 (06-2016)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
~*¥.~
Reported lessons teamed are Incorporated into the licensing process and fed back to industry.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections
~
i Branch (T *5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20~001, or by e-mail
~~~
~I (See Page 2 for required number of digits/characters for each block) to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. tt a (See NUREG*1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control httg://www. nrc.govLreading-rmLdoc-collectionsLnuregs/stafflsr1022/r3[J number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Columbia Generating Station 05000 397 I OF 3
- 4. TITLE Momentary loss of Secondary Containment due to Weather
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 6
26 2017 2017 -
003 - 00 8
24 2017 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201(b)
D 20.22os(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 D 20.2201cd>
D 20.2203(a}(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203<a><1>
D 20.2203<a><4>
D so.13<a><2>(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203<a><2>
D 50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203<a><2>
D 50.36(c)(1 )(ii}(A)
D 50.73(a)(2)(v)(A)
D 13.11<a><4>
D 20.2203<a><2><m>
D so.3a<c><2>
D 50.73(a)(2)(v)(B)
D 13.11<a>
D 20.2203(a)(2)(iv)
D so.46(a)(3)(ii)
[Z] 50.73(a)(2)(v)(C)
D 13.n<a><1>
98 D 20.2203(a)(2)(v)
D 50.73(a}(2)(i)(A)
[Z] 50.73(a)(2)(v)(D)
D 13.n<a><2>
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.n<a><2><ii)
D so.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or In 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 Columbia's accident analysis 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 Reactor Building HVAC did in fact restore Secondary Containment vacuum, and there was no loss of safety function or potential for radiological release.
PREVIOUS OCCURENCES
A loss of the ability to maintain Secondary Containment vacuum greater than required by TS has occurred at Columbia three times in the past two years as reported in LERs 2015-007-00, 2016-002-00, and 2016-003-00.
ENERGY INDUSTRY IDENTIFICATION Energy Industry Identification System (EHS) Information codes from IEEE Standards 805-1984 and 803-1983 are represented in brackets as [XX] and [XXX] throughout the body of the narrative. Page 3
of 3