05000324/LER-1917-003, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable,

From kanterella
Revision as of 15:12, 8 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable,
ML17215A990
Person / Time
Site: Brunswick 
Issue date: 08/03/2017
From: William Gideon
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 17-0065 LER 17-003-00
Download: ML17215A990 (6)


LER-1917-003, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable,
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation

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)
3241917003R00 - NRC Website

text

William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.457.3698 10 CFR 50.73 August 3, 2017 Serial: BSEP 17-0065 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License Nos. DPR-62 Docket No. 50-324 Licensee Event Report 2-2017-003 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 of 10 CFR 50.73(a)(1) for a written report within sixty (60) days of a reportable occurrence.

Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

William R. Gideon SWR/swr Enclosure: Licensee Event Report 2-2017-003

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. Galen Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net

NRC FORM 366 (04-2017)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2017)

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 4
4. TITLE Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable
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 06 05 2017 2017 - 003

- 00 08 03 2017 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) 087 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 4 of 4 LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

Previous Similar Events

In the past three years, two Licensee Event Reports have been submitted to the NRC describing events in which SRVs have been found with setpoint drift which made the valves inoperable.

05000325 / 2014-005, dated July 21, 2014 (ADAMS Accession Number ML14212A031) 05000324 / 2015-002, Revision 1, dated June 26, 2015 (ADAMS Accession Number ML15196A033)

In these events, the causes of corrosion bonding were analyzed, and corrective actions were implemented in subsequent groups of SRVs being rebuilt. However, the platinum coating process is still being advanced. Previous corrective actions could not benefit from improvements which were developed later.

Commitments

This report contains no new regulatory commitments.