05000325/LER-2020-002, Technical Specification Required Shutdown Due to Unidentified Leakage

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Technical Specification Required Shutdown Due to Unidentified Leakage
ML20140A004
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 05/18/2020
From: Krakuszeski J
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0112 LER 2020-002-00
Download: ML20140A004 (5)


LER-2020-002, Technical Specification Required Shutdown Due to Unidentified Leakage
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)
3252020002R00 - NRC Website

text

18

( -, DUKE

"" ENERGY May

, 2020 Serial: RA-20-0112 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 1-2020-002 John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE 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, is submitting 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 Ms. Sabrina Salazar, Manager - Nuclear Support Services, at (910) 832-3207.

Sincerely, John A. Krakuszeski SBY/sby

Enclosure:

Licensee Event Report

U.S. Nuclear Regulatory Commission Page 2 of 2 cc (with enclosure):

Ms. Laura Dudes, NRC Regional Administrator, Region II Mr. Andrew Hon, NRC Project Manager Mr. Gale Smith, NRC Senior Resident Inspector Chair - North Carolina Utilities Commission

NRC FORM 366 (04-2020)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2020)

LICENSEE EVENT REPORT (LER)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2020

1. Facility Name Brunswick Steam Electric Plant (BSEP), Unit 1
2. Docket Number 05000325
3. Page 1 OF 3
4. Title Technical Specification Required Shutdown due to Unidentified Leakage
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 24 2020 2020

- 002 00 05 18 2020 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) 022 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

Corrective Actions

The vacuum breaker associated with SRV 1F was inspected and confirmed to be operating properly. SRV 1F pilot and main valve were replaced and retested upon restart from the reactor shutdown. Additional corrective actions will be initiated following completion of the failure investigation.

Previous Similar Events

No events have occurred within the past three years in which increased drywell leakage from an SRV failure resulted in a LER.

Commitments

No regulatory commitments are contained in this report.