05000382/LER-2015-005, Regarding Emergency Feedwater System Flow Oscillations and LER 15-005-00 Regarding Manual Reactor Trip Due to Low Steam Generator Levels
| ML15212A743 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/31/2015 |
| From: | Jarrell J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2015-0060 LER 15-004-00, LER 15-005-00 | |
| Download: ML15212A743 (19) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B)(1) 10 CFR 50.73(a)(2)(iv)(B)(6) 10 CFR 50.73(a)(2)(iv)(B)(8) 10 CFR 50.73(a)(2)(i) 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)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3822015005R00 - NRC Website | |
text
10 CFR 50.73 W3F1-2015-0060 July 31, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Licensee Event Report (LER) 2015-004-00, Emergency Feedwater System Flow Oscillations and LER 2015-005-00, Manual Reactor Trip due to Low Steam Generator Levels Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
On June 3, 2015, Waterford Steam Electric Station, Unit 3 (Waterford 3) experienced a loss of main feedwater to both steam generators. Entergy is hereby submitting two LERs, 2015-004-00 and 2015-005-00, for events that occurred during this transient.
LER 2015-004-00 provides details associated with a condition that resulted in a common cause inoperability of both trains of the Emergency Feedwater (EFW) System and could have impacted the past operability of both trains of the Emergency Feedwater System and the Atmospheric Dump Valves. It was determined that this condition is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(vii) and 10 CFR 50.73(a)(2)(ix)(A). A follow up to LER 2015-004-00 is due by January 28, 2016 to provide the safety significance determination that is not yet complete.
LER-2015-005-00 provides details associated with a condition that resulted in the following System Actuations: Reactor Protection System Including Reactor Trip, Emergency Feedwater System, and Emergency Diesel Generators. It was determined that these conditions are reportable pursuant to 10 CFR 50.73 (a)(2)(iv)(A); specifically: 10 CFR 50.73 (a)(2)(iv)(B)(1), 10 CFR 50.73 (a)(2)(iv)(B)(6), and 10 CFR 50.73 (a)(2)(iv)(B)(8).
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
W3F1-2015-0060 Page 2 Attachments: (1) LER 2015-004-00 (2) LER 2015-005-00
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 W3F1-2015-0060 Licensee Event Report 2015-004-00
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)
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- 1. FACILITY NAME Waterford 3 Steam Electric Station
- 2. DOCKET NUMBER 05000382
- 3. PAGE 1 OF 8
- 4. TITLE Emergency Feedwater System Flow Oscillations
- 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 03 2015 2015 -
004
- - 00 07 31 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 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 Environmental Safety: There was no environmental safety significance associated with this issue.
Nuclear Safety: The actual consequence of this event was a manual reactor trip due to loss of MFW pump A. This unplanned reactor trip did not have any nuclear safety significance, based upon the operating shifts proper and timely diagnosis of the loss of MFW Pump A, and the initiation of a manual reactor trip. Since the operating shift was able to properly analyze the event and respond by manually tripping the unit, there are no potential consequences if an additional barrier failed or response actions were delayed. The RXC during this event was not in service. Because of this condition, the plant transient would have led to a SG low level condition resulting in an automatic reactor trip.
PREVIOUS OCCURRENCES
Waterford 3 Licensee Event Report history was reviewed.
LER WF3-2013-001-00: MFW regulating valve failed closed on loss of instrument air. This caused a manual reactor trip to be initiated.
There have been no previous occurrences where a reactor trip occurred due to a FW heater normal level control valve failing closed. Previous occurrences had only caused a reduction in plant power with unit remaining on line. This is based on a search of the Waterford 3 corrective action program database.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brackets [ ].