05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System
| ML19120A333 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/30/2019 |
| From: | William Gideon Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-19-0151 LER 2019-001-00 | |
| Download: ML19120A333 (5) | |
| 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)(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) |
| 3242019001R00 - NRC Website | |
text
( ~ DUKE ENERGY April 30, 2019 Serial: RA-19-0151 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 Licensee Event Report 2-2019-001 William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.832.3698 10 CFR 50.73 In accordance with the Code of Federal Regulations, Title 10, Part 50. 73, Duke Energy Progress, LLC, submits the enclosed Licensee Event Report (LER). This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence.
This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Jerry Pierce, Manager - Nuclear Support Services, at (910) 832-7931.
[2t7 William R. Gideon SBY/sby
Enclosure:
Licensee Event Report
U.S. Nuclear Regulatory Commission Page 2 of 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Dennis J. Galvin 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net
NRC FORM 366 (04-2018)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2018)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. Facility Name Brunswick Steam Electric Plant (BSEP), Unit 2
- 2. Docket Number 05000324
- 3. Page 1 OF 3
- 4. Title Automatic Actuation of the Primary Containment Isolation System
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Rev No.
Month Day Year Facility Name Docket Number 05000 03 05 2019 2019
- - 001 00 04 30 2019 Facility Name Docket Number 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 5 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. Power Level 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4) 000 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C)
Other (Specify in Abstract below or in Page 3 of 3 system, there was no loss of Decay Heat Removal capability. The Group 8 isolation was reset and shutdown cooling was restored within approximately 10 minutes. The safety significance of this event was minimal.
Corrective Actions
The following corrective actions were completed.
The isolation signal was reset and shutdown cooling was restored at approximately 05:45 EST on March 5, 2019.
Individuals involved were coached on how to properly assess risk and develop compensatory actions.
The Model WO for the Nozzle Hydro-lase activity for both Units was revised to include a precaution not to proceed unless Operations has established compensatory actions to prevent possible PCIS Group isolations or other actuations.
The BSEP OE data base was updated to include this incident.
The corrective actions below are currently planned. Any changes to the corrective actions and schedules noted below will be made in accordance with the sites corrective action program.
Revise the Model WO for the Nozzle Hydro-lase activity to include specific references to the instrumentation associated with each penetration to be flushed as well as any additional permissions required before starting to flush higher risk nozzles. This action is scheduled to be completed by 8/22/2019.
Submit request to have a new procedure developed that will disable specific PCIS isolations and actuations during a Refuel Outage, as allowed by Technical Specifications. This action is scheduled to be completed by 5/30/2019.
Previous Similar Events
There have been no events in the past three years in which an improper risk assessment resulted in an unplanned automatic actuation of a safety-related system or component.
Commitments
No regulatory commitments are contained in this report.