05000285/LER-2012-016, Regarding Unanalyzed Charging System Socket Welds to the Reactor Coolant System

Regarding Unanalyzed Charging System Socket Welds to the Reactor Coolant System

ML12262A317
Person / Time
Site:	Fort Calhoun
Issue date:	09/17/2012
From:	Cortopassi L Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-12-0140 LER 12-016-00
Download: ML12262A317 (5)

LER-2012-016, Regarding Unanalyzed Charging System Socket Welds to the Reactor Coolant System

Event date:
Report date:
Reporting criterion:	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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852012016R00 - NRC Website

text

L1C-12-0140 September 17, 2012 U.S. Nuclear Regulatory Commission Attn:,Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2012-016, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-016, Revision 0, dated September 17,2012. This report is being submitted pursuant to 10 CFR 50.73(a)(i)(A). The following commitments are being made in this letter.

FCS will correct the affected CVCS and waste disposal piping system socket welded fittings. This action will be completed before plant heatup.

FCS will complete thermal fatigue calculations for CVCS and waste disposal piping to ensure system is in compliance. This action will be completed before plant heatup.

If you should have any questions, please contact me.

Sincerely. ~

ouis P. Cortopassi Site Vice President LPC/epm Attachment c:

E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector Employment with Equal Opportunity

NRC FORM 366 (10-2010)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013

, the NRC may not conduct or sp onsor, and a person is not required to respond to, th e

information collection.

1. FACILITY NAME Fort Calhoun Station

2. DOCKET NUMBER 05000285

3. PAGE 1 OF 4

4. TITLE Unanalyzed Charging System Socket Welds to the Reactor Coolant System

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 7

17 2012 2012 - 016 -

0 9

17 2012 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE 5

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

SAFETY SIGNIFICANCE

The potential consequence is a small break loss of coolant accident (LOCA). The CVCS piping failure event is enveloped by the small break LOCA as described in the USAR. This type of event at power operations will cause the plant to be shut down. As previously mentioned no credit is taken for operation of the CVCS system.

The High Pressure Safety Injection (HPSI) System and the Low Pressure Safety Injection (LPSI) System would not be affected by either of these failures and would remain available to maintain reactor coolant system inventory.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does not result in a safety system functional failure in accordance with NEI-99-02.

PREVIOUS EVENTS Fort Calhoun Station has not reported any similar issues with socket welds.