05000285/LER-2016-002, Regarding Unanalyzed Condition Shutdown Heat Exchanger Isolations
| ML16189A107 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/07/2016 |
| From: | Marik S Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-16-0052 LER 16-002-00 | |
| Download: ML16189A107 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2852016002R00 - NRC Website | |
text
Omaha Public Power District LIC-16-0052 July 7, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 10 CFR 50.73
Subject:
Licensee Event Report 2016-002, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2016-002, Revision 0. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(B) and 50.73(a)(2)(v)(D). There are no new commitments being made in this letter.
If you should have any questions, please contact Brad Blome, Manager, Site Regulatory Assurance, at (402) 533-7270.
~IJJf~
Shane M. Marik Site Vice President and CNO SMM/cac Attachment c:
K. M. Kennedy, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S.M. Schneider, NRC Senior Resident Inspector 444 SOUTH 16TH STREET MALL* OMAHA, NE 68102-2247
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015) oV" ~t"""
Estimated burden per response to comply with this mandatory collection request: 80 hoLlrs.
- ~~/*
Reported lessons learned are incorporated into the licensing process and fed back to industry.
l~ 1! LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections
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Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and digits/characters for each block)
Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information co!lection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Fort Calhoun Station 05000285 1 OF 3
- 4. TITLE Unanalyzed Condition Shutdown Heat Exchanger Isolations
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 05 10 2016 2016 002 -
00 07 07 2016 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201(b)
D 20.2203(a)(3)(i)
D 50. 73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(dl D 20.2203(a)(3)(iiJ [g] 50. 73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 1 D 20.2203(a)(1)
D 20.2203(a)(4)
D 5o.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73. 71 (a)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50. 73(a)(2)(v)(C)
D 73.77(a)(1) 085 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
[8] 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
CORRECTIVE ACTIONS
Short Term Corrective Actions
- 6. LER NUMBER I
SEQUENTIAL I NUMBER 002 REV NO.
00
- 3. PAGE 3
OF An "Administrative Hold" was placed on TDB-Vlll until the issue was evaluated and corrected.
Long Term Corrective Actions TDB-Vlll will be retired to prevent further use.
SAFETY SIGNIFICANCE
This condition could have led to the inability of the Component Cooling Water (CCW) system to perform its design function of providing a cooling medium for the Containment atmosphere under Loss of Coolant (LOCA) conditions.
SAFETY SYSTEM FUNCTIONAL FAILURE This does represent a safety system functional failure in accordance with NEI 99-02, Revision 7.
The condition could have prevented the fulfillment of a safety function of Containment Cooling system by diverting flow of CCW away from Containment Coolers to mitigate the consequences of a design basis accident (LOCA).
PREVIOUS EVENTS The extent of condition identified an additional five incidents of this type at the station in 2015 and 2016. The additional occurrences are documented in CR 2016-05340.
NRC FORM 366111 -2015) 3