05000285/LER-2013-006-01, Regarding Use of Teflon in LPSI and CS Pump Mechanical Seal

Regarding Use of Teflon in LPSI and CS Pump Mechanical Seal

ML13239A120
Person / Time
Site:	Fort Calhoun
Issue date:	08/26/2013
From:	Cortopassi L Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LlC-13-0120 LER 13-006-01
Download: ML13239A120 (4)

LER-2013-006, Regarding Use of Teflon in LPSI and CS Pump Mechanical Seal

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(8) 10 CFR 50.73(a)(2)(v)(8) 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)(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
2852013006R01 - NRC Website

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ujjjju Omaha Public Power O/slrlct 444 South 16th Street Mall Omaha, NE 68102-2247 LlC-13-0120 August 26, 2013 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Reference:

1. Docket No. 50-285

2. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),

dated May 3,2013 (LlC-13-0057)

Subject:

Licensee Event Report 2013-006, Revision 1, for the Fort Calhoun Station Please find attached Licensee Event Report 2013-006, Revision 1. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(8), 10 CFR 50.73(a)(2)(v)(8) 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.

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

S. A. Reynolds, Acting NRC Regional Administrator, Region IV J. M. Sebrosky, NRC Sr. Project Manager L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Sr. 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 sponsor, and a person is not required to respond to, the 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 3

4 2013 2013 006 -

1 8

26 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 CONCLUSION A causal analysis determined that Omaha Public Power District and its consulting engineering firm failed to specify a compatible material for the pump seals in the original construction specifications.

CORRECTIVE ACTIONS

Replacement of pump seals is scheduled to be completed prior to startup.

A review of PED-GEI-10, Material Compatibility Review, will be performed to ensure the restriction placed on the use of Teflon is appropriate.

A review of engineering change checklists will be performed to ensure the PED-GEI-10 restrictions are preserved.

SAFETY SIGNIFICANCE

Failure of Teflon seals may have hindered the pumps' ability to operate in post-accident conditions.

A failure of one or more pumps could have resulted in insufficient cooling water to keep the core and the containment cooled as to prevent core damage and minimize the radiological consequences.

The operation of the CS Pumps is required in a MSLB and the operation of the LPSI pumps is required in post-LOCA conditions. In addition, the pumps are used in Shutdown Cooling (SDC) operation. Technical Specifications limit the leakage from the Engineered Safety Features (ESF) to 3800 cubic centimeters (cc)/hour and the ESF leakage has been used as an input in the Radiological Consequences calculations for the Control Room and off-site doses as well as the Electrical Equipment Qualification (EEQ) in the Auxiliary Building.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does result in a safety system functional failure in accordance with Nuclear Energy Institute, NEI-99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6.

PREVIOUS EVENTS Twenty LERs with event dates since March 4, 2010, were identified with the same reporting criteria.

Five of the LERs, 2012-002, 2012-009, 2012-015, 2012-017, and 2013-011, are all related to Electrical Equipment Qualification program issues. However, the issues identified in LER 2013-006 are latent conditions that were recently identified and any corrective actions from these previously reported events would not have prevented this condition.