05000461/LER-2018-003-01, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability

Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability

ML19042A077
Person / Time
Site:	Clinton
Issue date:	02/05/2019
From:	Stoner T Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604468 LER 2018-003-01
Download: ML19042A077 (4)

LER-2018-003, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability

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)(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)(v), Loss of Safety Function 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)
4612018003R01 - NRC Website

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7 :E.xeton*Ge:neratlon Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604468 February 5, 2019 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Subject: Licensee Event Report 2018-003-01 10 CFR 50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2018-003-01: Load Driver Card Failure Resulting in High Pressure Core Spray lnoperability. This is a supplemental report to LER 2018-003-00 submitted to the NRC on August 17, 2018. The updated information in the LER is denoted by revision bars located in the right-hand margin. This report is being submitted in accordance with the requirements of 1 O CFR 50.73.

There are no regulatory commitments contained in this report.

Should you have any questions concerning this report, please contact Mr. Dale Shelton, Regulatory Assurance Manager, at (217) 937-2800.

Respectfully, Theodore R. Stoner Site Vice President Clinton Power Station

Attachment:

Licensee Event Report 2018-003-01 cc:

Regional Administrator - Region Ill NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

3.Page Clinton Power Station, Unit 1 05000461 1

OF 3

4. Title Load Driver Card Failure Resulting in High Pressure Core Spray lnoperability

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 05000 Facility Name Docket Number 06 20 2018 2018 -

003 01 02 05 2019 05000

9. Operating Mode

11. This Report is Submitted Pursuant to the Requirements of 1 O 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(d)

D 20.2203(a)(3)(ii)

D 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 50.73(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) 099 D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

IX! 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) l\\~i.

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• T D 50.73(a)(2)(i)(C)

D Other (Specify in Abstract below or in D.

Safety Consequences

There were no actual safety consequences associated with the condition described in this report. The HPCS system provides and maintains an adequate coolant inventory inside the reactor vessel to limit fuel cladding temperatures in the event of breaks in the reactor coolant pressure boundary. The system is initiated by either high pressure in the drywell or low water level in the reactor vessel. Though the as-found HPCS injection valve position rendered the system inoperable, the Reactor Core Isolation Cooling (RCIC) system was operable throughout this event. Although no credit is taken in the safety analysis for the RCIC system, it performs a similar function as HPCS but has reduced makeup capability. HPCS is also backed up by the Automatic Depressurization System in combination with the Low Pressure Coolant Injection [BO] and Low Pressure Core Spray [BM] systems. These systems also remained operable throughout this event.

This event is reportable under the provisions of 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented fulfillment of the HPCS system (a single train safety system) to mitigate the consequences of an accident.

E.

Corrective Actions

The original load driver circuit cards were replaced.

F.

Previous Similar Occurrences There were no previous similar occurrences involving load driver card failure that resulted in HPCS inoperability.

G.

Component Failure Data

Manufacturer: General Electric Hitachi Part Number 14708455 Load Driver Card Page _3_ of _3_

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