05000285/LER-2012-021, Regarding HCV-2987, HPSI Alternate Header Isolation Valve

Regarding HCV-2987, HPSI Alternate Header Isolation Valve

ML13051A455
Person / Time
Site:	Fort Calhoun
Issue date:	02/19/2013
From:	Cortopassi L Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-13-0015 LER 12-021-00
Download: ML13051A455 (4)

LER-2012-021, Regarding HCV-2987, HPSI Alternate Header Isolation Valve

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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
LER closed by
IR 05000285/2014009 (18 September 2014) IR 05000285/2016007 (11 February 2016)
2852012021R00 - NRC Website

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fjjjjjfj Om.ha Publlll'owerO/slricl 444 South 16th Street Mall Omaha, NE 68102-2247 LlC-13-0015 February 19, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2012-021, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-021, Revision 0, dated February 19, 2013. This report is being submitted pursuant to 10 CFR 50. 73( a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B).

There are no 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.

Louis P. Cortopassi Vice President and CND LPC/rjr 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 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 HCV-2987, HPSI Alternate Header Isolation Valve

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 01 29 2012 2012 021 -

0 02 19 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

CORRECTIVE ACTIONS

Repacking and testing of the valve has been scheduled. Completion of the AOV Program procedure, currently being developed, will assure that the appropriate test activities are defined and that the results are appropriately addressed. The calculations associated with valve HCV-2987 will be reviewed and revised an necessary to assure that all information is consistent.

SAFETY SIGNIFICANCE

The potential failure of valve HCV-2987 as discussed requires a loss of instrument air and would result in a reduction in the available injection paths. As discussed in USAR Section 6.2.1, the safety injection system is designed to keep the core covered for extended periods of time after initial injection. One high-pressure pump has sufficient capacity with 25 percent spillage to maintain the core water level at the start of recirculation, and during Long Term Core Cooling (LTCC). However, to mitigate control problems that may be caused by hardware limitations, procedures require that two HPSI pumps be utilized during simultaneous hot and cold leg injection. If only one HPSI pump is operable, then the alternate hot leg injection path with one LPSI pump is used challenging the operation of HCV-2987 to operate during its required mission time.

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-two Licensee Event Reports initiated since January 1, 2010, were identified with the same reporting criteria; 10 CFR 50.73(a)(2)(i)(B), Any operation or condition which was prohibited by the plant's Technical Specifications.

10 CFR 50.73(a)(2)(v)(B) Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat.

None of the Licensee Event Reports reviewed contained the same underlying concern or reason of this event, such as the same root cause, failure, or sequence of events. A number of these Licensee Event Reports are still being investigated. If the root cause, failure, or sequence of events in any of the pending investigations is found to be similar to this event, then that Licensee Event Report will include Licensee Event Report 2012-021-0 as a previous event.