05000325/LER-2018-002, Automatic Reactor Trip During Stator Coolant System Realignment
| ML18156A565 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/05/2018 |
| From: | William Gideon Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-18-0037 LER 2018-002-00 | |
| Download: ML18156A565 (6) | |
| 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) |
| 3252018002R00 - NRC Website | |
text
1_.,ouKE ENERGYGD JUN 0. 5 2018 Serial: RA-18-0037 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Brunswick Steam Electric Plant, Unit No. 1 Renewed Facility Operating License No. DPR-71 Docket No. 50-325 Licensee Event Report 1-2018-002 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. Lee Grzeck, Manager - Regulatory Affairs, at (910) 832-2487.
William R. Gideon MAT/mat
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 (02-2018)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (02-2018)
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 1
- 2. Docket Number 05000325
- 3. Page 1 OF 4
- 4. Title Automatic Reactor Trip during Stator Coolant System Realignment
- 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 04 07 2018 2018 - 002
- - 00 06 05 2018 Facility Name Docket Number 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 1 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) 100 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)(ii) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(iii) 50.73(a)(2)(i)(C)
Other (Specify in Abstract below or in Page 4 of 4 supervisory oversight) to identification, documentation, and verification of assumptions to appropriate Engineering personnel. The case study will be incorporated into backbone Design Control recurring training. This action is currently scheduled to be completed by October 31, 2018.
Procedure AD-EG-ALL-1157, Engineering of Plant Digital Systems and Components, will be revised to provide more specific guidance on evaluation of response to out-of-range or unexpected values to consider margin to achievable plant conditions. This action is currently scheduled to be completed by December 20, 2018.
Procedure AD-EG-ALL-1132, Preparation and Control of Design Change Engineering Changes, will be revised to add consideration of new or modified functions that will cause a reactor trip or Engineered Safety Feature (ESF) actuation to ensure that methods of initiating the trip or ESF actuation are evaluated for unintended actuation. This action is currently scheduled to be completed by December 20, 2018.
Previous Similar Events
A review of LERs for the past three years identified the following previous similar event where a modification introduced an unforeseen consequence.
LER 1-2016-002, Revision 1, dated August 8, 2016, reported a condition that could have prevented the fulfillment of a safety function and operation prohibited by the Technical Specifications due to inoperability of Emergency Diesel Generator (EDG) 3. The root cause of the EDG 3 inoperability was a design vulnerability, associated with relaxation of the EDG 3 fuse holder fingers, which was not properly mitigated. The corrective actions associated with LER-2016-002, Revision 1, were focused on correcting the design vulnerability and the use of fuse block devices. These actions could not have reasonably been expected to prevent the condition reported in LER 1-2018-002.
Commitments
No regulatory commitments are contained in this report.