05000278/LER-2016-001, Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function
| ML16327A051 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/22/2016 |
| From: | Pat Navin Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CCN: 16-103 LER 16-001-00 | |
| Download: ML16327A051 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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) 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) |
| 2782016001R00 - NRC Website | |
text
Exelon Generation November 22, 2016 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001
Subject:
Peach Bottom Atomic Power Station (PBAPS) Unit 3 Renewed Facility Operating License No. DPR-56 NRC Docket No. 50-278 Licensee Event Report (LER) 3-16-001 10CFR 50.73 Enclosed is a Licensee Event Report concerning a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. The loss of safety function was the result of a pipe leak in a drain line for the High Pressure Coolant Injection system.
In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations.
The specific methods that have been planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact Jim Armstrong at 717-456-3351.
Patrick D. Navin Plant Manager Peach Bottom Atomic Power Station PDN/dnd/IR 2720241 Attachment cc:
US NRG, Administrator, Region I US NRG, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland
- 8. Watkins, PSE&G, Financial Controls and Co-owner Affairs CCN: 16-103
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
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 />
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Reported lessons learned are incorporated into the licensing process and fed back to industry LICENSEE EVENT REPORT (LER)
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- 3. PAGE Peach Bottom Atomic Power Station Unit 3 05000278 1 OF 3
- 4. TITLE Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 09 26 16 2016 - 001 0
11 22 16
- 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) 1 D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1 l D 20.2203(a)(4)
D so.13(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 so.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73. 71 (a)(5)
D 20.2203(a)(2)(iv)
D so.46(a)(3)(ii)
D 50.73(a)(2)(v}(C)
D 73.77(a)(1) 100%
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
[8'.I 50. 73(a)(2)(v)(D)
D 13.n(aJ(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.11(a)(2J(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or 1n SEQUENTIAL NUMBER 001 REV NO.
0 There were no actual consequences as a result of the leak. If a design basis event had occurred, the HPCI system would have been able to perform its design function. If a failure were to occur that would have prevented HPCI from performing its design function, the Automatic Depressurization System would have reduced reactor pressure to allow the low pressure cooling systems to maintain reactor vessel level and provide core cooling.
Corrective Actions
The affected section of pipe and the orifice were replaced. The second HPCI turbine drain line was inspected, along with the two drain lines on the Unit 2 HPCI turbine, and no leaks were identified.
Additional actions are planned to perform inspections of similar drain piping that contain orifices.
Previous Similar Occurrences Based on a review of maintenance records, no previous similar occurrences of through-wall flaws of this piping have occurred. Page _3_ of _3_