05000382/LER-2015-007, Regarding Both Emergency Diesel Generators Declared Inoperable

Regarding Both Emergency Diesel Generators Declared Inoperable

ML15296A464
Person / Time
Site:	Waterford
Issue date:	10/23/2015
From:	Jarrell J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2015-0074 LER 15-007-00
Download: ML15296A464 (8)

LER-2015-007, Regarding Both Emergency Diesel Generators Declared Inoperable

Event date:
Report date:
Reporting criterion:	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)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3822015007R00 - NRC Website

text

10 CFR 50.73 10 CFR 21 W3F1-2015-0074 October 23, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

Subject:

Licensee Event Report (LER) 2015-007-00 Waterford Steam Electric Station, Unit 3 (Waterford 3)

Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

On August 26, 2015, both Emergency Diesel Generators at Waterford Steam Electric Station, Unit 3 (Waterford 3) were declared inoperable, causing entry into Technical Specification 3.8.1.1 action f.

It was determined that this condition is reportable pursuant to 10 CFR 50.73(a)(2)(v)(A),

50.73(a)(2)(v)(B) and 10 CFR 21. A follow up to LER 2015-007-00 is due by February 28, 2016 to provide the safety significance determination and to allow investigation into the component failure for the ventilation system to be completed.

This report contains no new commitments. Please contact John P. Jarrell, Regulatory Assurance Manager, at (504) 739-6685 if you have questions regarding this information.

Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 jjarrel@entergy.com John P. Jarrell III Manager, Regulatory Assurance Waterford 3

W3F1-2015-0074 Page 2 Attachment: 1. LER 2015-007-00 cc:

Mr. Mark L. Dapas, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 Michael.Orenak@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov

to W3F1-2015-0074 Licensee Event Report 2015-007-00

NRC FORM 366 (02-2014)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (02-2014)

LICENSEE EVENT REPORT (LER)

(See Page 2 for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 Estimated burden 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 />.

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

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to Infocollects.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 a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Waterford 3 Steam Electric Station

2. DOCKET NUMBER 05000382

3. PAGE 1 OF 5

4. TITLE Both Emergency Diesel Generators Declared 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 08 26 2015 2015 -

007

- 00 10 23 2015 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)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)

10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 100 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 10 CFR 21 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

CORRECTIVE ACTIONS

For Failed Current Transformer on EDG A:

Completed Actions

1. Replace Current Transformer in EDG A

2. Failure analysis on the failed EDG A Current Transformer Actions

1. Replace remaining donut style transformers on EDG A and B (nine per EDG)

2. Replace Current Transformer for Generator Differential on EDG B

3. Create a preventive maintenance task to replace the EG ECT2316 C TRANSF, NB8 Current Transformer

4. Create a preventive maintenance task to replace power current donut style transformers for EDG A and EDG B

For EDG B:

Completed Actions

1. Replace Solenoid [SOL] associated with HVR-501B Based on the initial evaluation, an Equipment Apparent Cause Evaluation is being performed to determine the cause of the rapid cycling of the solenoid. Once this evaluation is completed, and depending on the determination of the testing, the root cause will be revised. This LER will be revised to include the Root Cause and Contributing

SAFETY SIGNIFICANCE

Industrial Safety: There was no industrial safety significance associated with this issue.

Radiological Safety: There was no radiological safety significance associated with this issue.

Environmental Safety: There was no environmental safety significance associated with this issue.

Nuclear Safety: The equipment apparent cause evaluation is still in progress and has not been approved by site management. The safety significance determination is not yet completed. Nuclear safety significance will be included as a planned update to this LER.

ADDITIONAL INFORMATION

Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brackets [ ].