05000285/LER-2013-006, Use of Teflon in LPSI and CS Pump Mechanical Seals

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Use of Teflon in LPSI and CS Pump Mechanical Seals
ML13126A121
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/03/2013
From: Cortopassi L
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-13-0057 LER 13-006-00
Download: ML13126A121 (4)


LER-2013-006, Use of Teflon in LPSI and CS Pump Mechanical Seals
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(viii)(A)

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)(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
2852013006R00 - NRC Website

text

LlC-13-0057 May 3,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2013-006, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2013-006, Revision 0, dated May 3, 2013.

This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(B), 10 CFR 50.73(a)(2)(v)(B) and (D), and 10 CFR 50.73(a)(2)(vii). There are no new commitments being made in this letter.

If you should have any questions, please contact Terrence W. Simpkin, Manager, Site Regulatory Assurance, at (402) 533-6263.

Sincerely, v-\\-.lJ} 1p~

Louis P. Cortopassi Full..

Site Vice President and CNO LPC/epm/rjr Attachment c:

A. T. Howell, NRC Regional Administrator, Region IV J. M. Sebrosky, NRC Project Manager 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 3
4. TITLE Use of Teflon in LPSI and CS Pump Mechanical Seals
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 03 04 2013 2013 006 -

0 05 03 2013 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 Remove residual heat and (D) Mitigate the consequences of an accident. This condition was initially reported on March 4, 2013 under 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition (ENS 48806).

CONCLUSION A causal analysis is in progress. The results of the analysis will be published in a supplement to this LER.

CORRECTIVE ACTIONS

A causal analysis is in progress. The results of the analysis will be published in a supplement to this LER

SAFETY SIGNIFICANCE

A causal analysis is in progress. The results of the analysis will be published in a supplement to this LER.

SAFETY SYSTEM FUNCTIONAL FAILURE A causal analysis is in progress. The results of the analysis will be published in a supplement to this LER.

PREVIOUS EVENTS A causal analysis is in progress. The results of the analysis will be published in a supplement to this LER.