05000287/LER-1917-001, Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout

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Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout
ML17271A134
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 09/20/2017
From: Dunton C
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ONS-2017-064 LER 17-001-00
Download: ML17271A134 (5)
v • d • e


LER-1917-001, Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout
Event date:
Report date:
2871917001R00 - NRC Website
v • d • e

text

e.(-,DUKE

~ ENERGY ONS-2017-064 September 20, 2017 Attn: Document Control Desk U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-27 46 Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 3 Docket Number: 50-287 Renewed Operating License DPR-55 10 CFR 50.73 Ca.rrie T. Dunton Director, Nuclear Site Support Oconee Nuclear Station Duke Energy ON01VP 17800 Rochester Hwy Seneca, SC 29672 o. 864.873.3477 f: 864.873.4208 carrie. dunton@duke-energy.com

Subject:

Licensee Event Report 287/2017-001, Revision O - Unit 3 Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout Licensee Event Report 287/2017-001, Revision 0, is being submitted pursuant to the requirements of 10 CFR 50. 73(a)(2)(iv)(A) to provide a report of the subject event.

There are no regulatory commitments associated with this LER.

If there are questions, or further information is needed, contact David Haile, in Oconee Regulator}t Affairs, at (864) 873-4742.

Sincerely,

~~~+--

Carrie T. Dunton Director, Nuclear Site Support Oconee Nuclear Station Enclosure: Licensee Event Report 287/2017-001, Revision 0 - Unit 3 Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout.

NRC FORM 366 (04-2017)

ONS-2017-064 September 20, 2017 Page 2 cc:

Ms. Catherine Haney, Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey L. Klett, Project Manager (by electronic mail only)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-08B1A Rockville, MD 20852-2738 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station INPO (Word File via E-mail)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)

Estimated burcfen per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

+.~r,,.._f>.RREO(,(.pl"o LICENSEE EVENT REPORT (LER)

Reported lessons learned are incorporated into the licensing process and fed back to industry.

"t.

Send comments regarding burden estimate to the Information Services Branch (T-2 F43),

\\l (See Page 2 for required number of U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to c

'-+

OJ digits/characters for each block) lnfocollects.Resource@nrc.gov. and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If (See NUREG-1022, R.3 for instruction and guidance for completing this form a means used to impose an information collection does not display a currently valid OMB control htt1:1:/lwww.nrc.gov/reading-rm/doc-collections/nur§9s/staff/sr1022/r3[)

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

3. PAGE Oconee Nuclear Station Unit 3 5000287 1 of 3
4. TITLE Unit 3 Reactor Protection System Actuation - Reactor Trip due to Turbine Trip from Generator Lockout
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED YEAR YEAR ISEQUENTIALIREV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY NUMBER NO.

NA 5000 07 24 2017 2017

  • 001
  • 00 09 20 2017 FACILITY NAME DOCKET NUMBER NA 5000
9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 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)

Mode 1 D 20.2201{d)

D 20.2203{a){3)(ii)

D 50. 73(a){2){ii)(B)

D 50. 73(a)(2)(viii)(B)

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)

~ 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(<?)(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) 100%

D 20.2203{a)(2)(v)

D 50. 73(a)(2)(i)(A)

D 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:, 1\\"' :,.

,,~.*,,

.;.... *~

D 50. 73(a)(2)(i)(C)

D OTHER Specify in Abstract below or in

6. LER NUMBER YEAR I SEQUENTIAL I NUMBER 2017 -

001 proximity to the PCB-58 relay device) and thus the coordination and oversight of this work was inadequate.

CORRECTIVE ACTIONS

This event was entered into the Corrective Action Program (NCR 02138958) which included a cause analysis. The cause analysis corrective actions are summarized as follows:

REV NO.

00 In order to improve the application of human performance rigor and the recognition of operational risks when working in the switchyard relay cabinets;

1. Training, applicable to this event, will be provided to the necessary groups,
2. Cabinet/relay labeling will be enhanced, and
3. Interface guidance applicable to this event will be improved.

The site work planning and approval processes will be improved for work within the site switchyards that require coordination with the Transmission department.

SAFETY ANALYSIS

Loss of electrical load from 100 percent power is an analyzed event described in the ONS Updated Final Safety Analysis Report, Section 15.8. All onsite safe shutdown equipment performed as required with no complications. Therefore this event did not present a risk to the health and safety of the plant or the public.

ADDITIONAL INFORMATION

Energy Industry Identification System (EllS) codes are identified in the text as [XX].

Similar Events

None NRC FORM 366 (04-2017)

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