05000382/LER-2015-008, Regarding Automatic Reactor Trip Due to Failed Circuit Card in Control Element Assembly Calculator 2
| ML15336A959 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/02/2015 |
| From: | Jarrell J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2015-0087 LER 15-008-00 | |
| Download: ML15336A959 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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)(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)(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 |
| 3822015008R00 - NRC Website | |
text
10 CFR 50.73 W3F1-2015-0087 December 2, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Submittal of Licensee Event Report (LER) 2015-008-00, Automatic Reactor Trip Due to Failed Circuit Card in Control Element Assembly Calculator 2 Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
On October 3, 2015, Waterford Steam Electric Station, Unit 3 (Waterford 3) experienced an Automatic Reactor Trip Due to Failed Circuit Card in Control Element Assembly Calculator (CEAC) 2.
It was determined that this condition is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A)
(System Actuation); specifically: 10 CFR 50.73(a)(2)(iv)(B)(1), Reactor Protective System (RPS) Including Reactor Scram or Reactor Trip, due to an automatic reactor trip, and 10 CFR 50.73(a)(2)(iv)(B)(6), PWR Auxiliary or Emergency Feedwater System, due to automatic initiation of the Emergency Feedwater System.
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.
Attachment: 1. LER 2015-008-00 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
W3F1-2015-0087 Page 2 cc:
Mr. Mark L. Dapas, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov
to W3F1-2015-0087 Licensee Event Report LER 2015-008-00
NRC FORM 366 (02-2014)
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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 5
- 4. TITLE Automatic Reactor Trip Due To Failed Circuit Card In Control Element Assembly Calculator 2
- 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 10 03 2015 2015 -
008
- - 00 12 02 2015 FACILITY NAME DOCKET NUMBER
- 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 (4)
A performance monitoring plan was developed as a mitigating action to identify and respond to potential degradation of CEAC cards.
(5)
Perform effectiveness review action by validating that there have been no plant trips due to a SPF within the CPC/CEAC system through three refuel cycles.
SAFETY SIGNIFICANCE
In this event, the CEAC sensed an erroneous subgroup deviation and conservatively generated a penalty factor which resulted in a reactor trip and subsequent forced outage. There was no loss of safety function. There were no other actual consequences to general safety of the public, nuclear safety, industrial safety or radiological safety for this event. The potential consequences to general safety of the public, nuclear safety, industrial safety and radiological safety of this event if response actions were delayed were negligible. The potential consequences to general safety of the public, nuclear safety, industrial safety and radiological safety of this event if one additional barrier becomes missing or broken is negligible since the CPC reaction is a plant trip into a safe condition. Had the CEAC failed so that a true subgroup deviation was not detected, the other CEAC would have sensed the deviation and applied the appropriate penalty factor to the CPCs to generate a LPD or DNBR trip. Based on this analysis, the risk is considered Low.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brackets [ ].