05000352/LER-2018-003, High Pressure Coolant Injection (HPCI) Inoperability Due to Main Pump Inboard Seal Leak
| ML18169A237 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/18/2018 |
| From: | Libra R Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 2018-003-00 | |
| Download: ML18169A237 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3522018003R00 - NRC Website | |
text
Exelon Generation LG-18-078 June 18, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Unit 1 Renewed Facility Operating License No. NPF-39 NRC Docket No. 50-352 10 CFR 50.73
Subject:
LER 2018-003-00, High Pressure Coolant Injection (HPCI) lnoperability due to Main Pump Inboard Seal Leak Enclosed is a Licensee Event Report (LER) which addresses the inoperability of the High Pressure Coolant Injection (HPCI) system during surveillance testing at Limerick Generating Station (LGS), Unit 1.
This LER is being submitted pursuant to the requirements of 1 O CFR 50.73(a)(2)(v)(D), any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
Additionally, this LER is being submitted pursuant to the requirements of 1 O CFR 50.73(a)(2)(i)(B), Operation or Condition Prohibited by Technical Specifications.
There are no commitments contained in this letter.
If you have any questions, please contact Robert B. Dickinson at (61 O) 718-3400.
Respectfully,
~
Richard W. Libra Vice President - Limerick Generating Station Exelon Generation Company, LLC cc: Administrator Region I, USNRC USNRC Senior Resident Inspector, Limerick Generating Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0313112020 (02-2018)
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LICENSEE EVENT REPORT (LER)
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3.Page Limerick Generating Station, Unit 1 05000352 OF 3
- 4. Title High Pressure Coolant Injection (HPCI) lnoperability due to Main Pump Inboard Seal Leak
- 5. Event Date
- 6. LEA 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 04 17 2018 2018 -
003 00 06 18 2018
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)
D 20.2201 (bl D 20.2203(a)(3)(il D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 D 20.2201 (dl D 20.2203(a)(1 i D 20.2203(a)(3)(iil D 20.2203(a)(4l D 50.73(a)(2)(ii)(B)
D so.13(a)(2)(iiil D 50.73(a)(2)(viii)(B)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(il 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)(iil D 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11 (a)(4)
D 20.2203(a)(2)(iiil D so.36(c)(2)
D 50.73(a)(2)(v)(B)
D 13.11 (a)(5l D 20.2203(a)(2)(iv)
D so.46(a)(3Hiil D 50.73(a)(2)(v)(G)
D 13.77(a)(1) 012 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
[8] 50. 73(a)(2)(v)(D)
D 13.77(a)(2)(iil D 20.2203(a)(2)(vi)
[8J 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.77(a)(2)(iii)
,1 D 50.73(a)(2)(i)(G)
D Other (Specify in Abstract below or in Based on the indeterminate condition of the seal, HPCI past operability between 200 psig and rated reactor pressure could not be ensured. Although HPCI was operable based on the 200 psig HPCI Operability Verification Surveillance Testing when no seal leakage was evident, the past operability evaluation could not justify operability at the time the reactor mode changed at 0804 on 4/17/18.
Therefore, this LER is also being submitted pursuant to the requirements of 10CFR 50.73(a)(2)(i)(B),
Operation or Condition Prohibited by Technical Specifications.
IV.
Safety Significance
There was no actual safety consequence associated with this event. The reactor core isolation cooling (RCIC) system and low-pressure Emergency Core Cooling Systems (ECCS) were available during surveillance testing.
V.
Cause of the Event
Technicians performed a less than adequate inspection and did not ensure that the split ring was secured by the retaining collar.
VI.
Corrective Actions Completed/Planned The individuals were coached and the maintenance procedure for the HPCI full pump rebuild was revised to include additional technical detail with technical hold points on pump seal reinstallation.
VII.
Previous Similar Occurrences There were no previous similar occurrences in the past 5 years.
VI 11.
Component Data System:
Component:
Component number:
Man uf actu rer:
Model number:
Serial number: BJ High Pressure Coolant Injection System Pump 10-P204 Flowserve DVMX 701-S-0833 Page _3_ of _3_