05000315/LER-2015-002, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump
| ML15225A467 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/12/2015 |
| From: | Gebbie J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2015-76 LER 15-002-00 | |
| Download: ML15225A467 (4) | |
| 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 |
| LER closed by | |
| IR 05000315/2017001 (1 May 2017) | |
| 3152015002R00 - NRC Website | |
text
INDIANEA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWIER One Cook Place Bridgman, Mi 49106 A unit of American Electric Power IndianaMichigan Power~comn August 12, 2015 AEP-NRC-201 5-76 10 CFR 50.73 Docket No.: 50-315 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852 Donald C. Cook Nuclear Plant Unit 1 LICENSEE EVENT REPORT 315/2015-002-00 Technical Specification Violation Due to Inoperable Residual Heat Removal Pump In accordance with 10 CFR 50.73, Licensee Event Report (LER) System, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is submitting, as an enclosure to this letter, the following report:
LER 315/2015-002-00: "Technical Specification Violation Due to Inoperable Residual Heat Removal Pump"~
There are no commitments contained in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President JEN/ams Enclosure c:
A. W. Dietrich - NRC Washington, DC J. T. King - MPSC MDEQ - RMD/RPS NRC Resident Inspector C. D. Pederson - NRC Region III A. J. Williamson - AEP Ft. Wayne
Enclosure to AEP-NRC-2015-76 LER 315/2015-002-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 0113112017 (02-2014)
.,.**.,",.%Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
=..*
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections LICENSEE EVENT REPORT (LE R)
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC digits/characters for each block) 20503. If a means used to impose an information collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Donald C. Cook Nuclear Plant Unit 1 05000315 1 OF 2
- 4. TITLE Technical Specification Violation due to Inoperable Residual Heat Removal Pump
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEUMENILR EVO MONTH DAY YEAR05 0
FACILITY NAME DOCKET NUMBER 06 14 205 21 02 001 08 1
20505000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
LI 20.2203(a)(3)(i)
LI 50.73(a)(2)(i)(C)
Lii 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A) 5 El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
E 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[I] 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20 2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
El 20.2203(a)(2)(iv)
E 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 00 E
20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER E
20.2203(a)(2)(vi)
[] 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specifyin Abstract below or in
- 12. LICENSEE CONTACT FOR THIS LER LIL*I*I*IOI=I: L*UI*I I PL. I Michael K. Scarpello, Regulatory Affairs Manager I I:LI::-flUINI: INUIVI*IjM {inciuoe/4tea L,oae)
(269) 466-2649
- 14. SUPPLEMENTAL REPORT EXPECTED Z] YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
El NO I
ABSTRACT (Limit to 1400 spaces, iLe., approximately 15 single-spaced typewritten lines)
On June 14, 2015, Donald C. Cook Nuclear Plant operations personnel identified an oil leak from the Unit I East Residual Heat Removal (RHR) pump (Train A) lower motor bearing oil reservoir. An engineering evaluation concluded that the leak rate would preclude the pump from meeting its 30-day mission time during accident conditions, thus rendering the Unit I East RHR pump inoperable. Review of oil addition logs concluded that this condition has existed, but was not recognized as such, since March 9, 2015. This exceeds the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.2, Condition A.
Concurrent with the Unit I East RHR pump inoperability while in Mode 1, the Unit 1 AR Emergency Diesel Generator (EDG)
(Train B) was inoperable for a scheduled maintenance window commencing May 18, 2015, and ending with a TS required shutdown due to EDG failure. The inoperable AR EDG required the Unit 1 West RHR pump to be declared inoperable in accordance with LCO 3.8.1, Condition B.3 - "Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable." The Unit 1 West RHR Pump was not declared inoperable within four hours as required by TS LCO 3.8.1, Condition B.3.
'The RHR pump oil leak and the EDG have been repaired and are operable. The Cause and Extent of Condition Evaluations are ongoing; a supplement to this Licensee Event Report with additional information will be submitted upon completion.
NRC FORM 366 (02-2014)
Energy Industry Identification System codes are identified in the text as [XX].
INTRODUCTION
On May 18, 2015, at 0010, the Unit 1 AR (Train B) Emergency Diesel Generator (EDG) [EK] was declared inoperable when it was removed from service for a scheduled maintenance window while Unit 1 was in Mode I at 100 percent power.
On June 1, 2015, at 0231, the Unit 1-Reactor [RCT] was shut down to comply with Technical Specification Limiting Condition for Operation (LCO) 3.8:1, Condition G.1 when EDG damage during a post maintenance run could not be repaired within the required 14-day Completion Time.
On June 14, 2015, with Unit I in Mode 5, operations personnel identified an oil leak from the Unit 1 East (Train A)
Residual Heat Removal (RHR) [BP] pump [P] lower motor bearing oil reservoir [RVR]. An engineering evaluation concluded that the leak rate precluded the pump from meeting its required 30-day mission time during accident conditions, thus rendering the Unit 1 East RHR pump inoperable. Review of operator oil addition logs concluded that this leak had existed since March 9, 2015. The unrecognized inoperability of the 1 East RHR pump exceeded the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by LCO 3.5.2, Condition A. This is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B),
Operation or Condition Prohibited by Technical Specifications. Unit 1 entered Mode 4 at 1821 on June 1, 2015, exiting the mode of applicability for LCO 3.5.2.
The inoperability of Unit 1 AB EDG concurrent with the inoperable Unit 1 East RHR Pump requires declaring the Unit 1 West RHR pump inoperable in accordance with LCO 3.8.1, Condition B.3 - Declare required feature(s)
- supported by the inoperable EDG inoperable when its required redundant feature(s) is inoperable. The inoperability of the Unit 1 East RHR pump was not recognized at this time, sothe Unit 1 West RHR pump was not declared inoperable when the Unit 1 AR EDG was made inoperable.
In retrospect, had the Unit 1 East RHR pump been recognized as being inoperable, the Unit 1 West RHR pump should have been declared inoperable within four hours from when the Unit 1 AR EDG was declared inoperable on May 18, 2015, at 0010, until June 2, 2015, at 0410, when Unit 1 entered Mode 5, exiting the mode of applicability for LCO 3.8.1, AC Sources-Operating, and LCO 3.5.3, ECCS-Shutdown. This is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B), Operation or Condition Prohibited by Technical Specifications.
The offsite power sources (preferred and alternate) remained operable and available for the duration that the U1 AR EDG was inoperable thus there is reasonable assurance that the Unit I West RHR pump remained capable of fulfilling its safety function. For this occurrence, safety function of the Emergency Core Cooling System [BP][BQ] was not lost.
In the event of a loss of offsite power (LOOP), the Unit 1 East RHR pump was available to perform its shutdown cooling function. Therefore, capability to mitigate a LOOP was not lost.
The Unit 1 East RHR oil leak has been repaired and the pump declared operable. The Unit 1 AR EDG has been repaired and declared operable.
The Cause and Extent of Condition Evaluations are ongoing; a supplement to this Licensee Event Report with additional information will be submitted upon completion.