05000397/LER-2012-007, For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open

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For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open
ML13070A008
Person / Time
Site: Columbia 
Issue date: 02/28/2013
From: Hettel W
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-13-033 LER 12-007-00
Download: ML13070A008 (4)


LER-2012-007, For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open
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)(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)(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)(i)(B), Prohibited by Technical Specifications
3972012007R00 - NRC Website

text

W. Grover Hettel ENERGY Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509.377.8311 I F. 509.377.4150 wghettel @energy-northwest.com February 28, 2013 G02-13-033 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. 2012-007-00

Dear Sir or Madam:

Transmitted herewith is Licensee Event Report No. 2012-007-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(v)(C) and (D), which requires the reporting of any condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: control the release of radioactive material and mitigate the consequences of an accident.

There are no commitments being made to the NRC by this letter. If you have any questions or require additional information, please contact Mr. ZK Dunham at (509) 377-4735.

Respectfully, WG Hettel Vice President, Operations Attachment: Licensee Event Report 2012-007-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C AJ Rapacz - BPA/1 399 WA Horin - Winston & Strawn

P 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 OF 3
4. TITLE Secondary Containment Inoperable due to both Airlock Doors being Open
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 12 30 2012 2012 - 007 - 00 02 28 2013 05000

9. OPERATING MODE
11. THIS REPORT IS SUBMITITED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 El 20.2201(b)

El 20.2203(a)(3)(i)

[3 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii)

El 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203 (a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

-] 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL [3 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x) 100 [1 20.2203(a)(2)(iii)

El 50.36(c)(2)

C3 50.73(a)(2)(v)(A)

El 73.71(a)(4)

C3 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

C3 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

El 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

Specify in Abstract below or in provide warning to personnel outside the airlock when the airlock is in use.

2. Revise Technical Specification bases for SR 3.6.4.1.2 and SR 3.6.4.1.3 to ensure that the wording clearly identifies that Secondary Containment operability requires that one door in each airlock be closed at all times when Secondary Containment is required.

ASSESSMENT OF SAFETY CONSEQUENCES

There was no equipment damage, injuries or dose exposure to station personnel. There was no change in plant status or operating condition and there was no actual risk to the public at any time. There was no impact to public health and safety as the Primary Containment was intact, and Secondary Containment ventilation system maintained the designed negative pressure inside the Reactor Building during the event.

There was a potential significance if there had been an event where the Primary Containment was breached concurrent with a loss of coolant accident or a fuel handing accident such that radioactive materials were released to the Reactor Building. Having both Reactor Building airlock doors open would potentially provide a release path for radioactive materials to enter the external environment.

SIMILAR EVENTS

A review of various databases at Columbia found a total of 40 similar events dating back to 1995. Not all of these events resulted in a loss of Secondary Containment. Some of these events occurred during a Mode in which Secondary Containment was not required to be operable. Some were an interlock failure only and both doors were not opened simultaneously.

A review of the NRC Event Notification database found the following similar events:

Event Notification 45975, 6/3/10 at Monticello Event Notification 46155, 8/5/10 at Monticello Event Notification 46394, 11/4/10 at Monticello Event Notification 48282, 9/6/12 at Quad Cities Event Notification 48295, 9/10/12 at Cooper ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) INFORMATION CODES EIIS codes are bracketed [] where applicable in the narrative.

26158 R5