05000382/LER-2015-006, Regarding Void Discovered in Low Pressure Safety Injection System Piping

Regarding Void Discovered in Low Pressure Safety Injection System Piping

ML15230A440
Person / Time
Site:	Waterford
Issue date:	08/18/2015
From:	Jarrell J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2015-0069 LER 15-006-00
Download: ML15230A440 (8)

LER-2015-006, Regarding Void Discovered in Low Pressure Safety Injection System Piping

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(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
3822015006R00 - NRC Website

text

10 CFR 50.73 W3F1-2015-0069 August 18, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

Subject:

Licensee Event Report (LER) 2015-006-00, Void Discovered in Low Pressure Safety Injection System Piping Waterford Steam Electric Station, Unit 3 (Waterford 3)

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

Dear Sir or Madam:

On June 20, 2015, Waterford Steam Electric Station, Unit 3 (Waterford 3) identified a void that exceeded the maximum volume allowed for OPERABILITY while performing high point venting of Low Pressure Safety Injection (LSPI) system B.

LER 2015-006-00 provides details associated with a condition that resulted in inoperability of LPSI system B for 11 days, exceeding the outage time allowed by Technical Specification 3.5.2 action a. It was determined that this condition is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B). A follow up to LER 2015-006-00 is due by February 29, 2016 to provide the safety significance determination that is not yet complete.

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

W3F1-2015-0069 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 Michael.Orenak@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov

to W3F1-2015-0069 Licensee Event Report 2015-006-00

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

, 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 Void Discovered in Low Pressure Safety Injection System Piping

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 20 2015 2015

- 006

- 00 08 18 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 CR-WF3-2013-1957 documents that a void was discovered in the LPSI system that was attributed to the system depressurization where gas remained in solution following the refuel 18 shutdown and startup.

Repeated stroking of the LPSI system flow control valve during depressurization resulted in the forming of the void due to the difference in elevation of the void location and the refueling water storage pool level.

Rollup Condition Report CR-WF3-2009-4155 was performed to document an adverse trend in gas accumulation in LPSI A (40 condition reports). The cause was attributed to leakage past a flow control (FCV) and containment isolation valve with additional leakage past normally closed valves.

Significant Event Report 2-05 and General Letter 2008-01 were evaluated under CR-WF3-2008-0117.

This evaluation addressed several of the previous gas intrusion, gas accumulation and voiding occurrences at Waterford 3 along with the various procedural changes, modifications, maintenance tasks, operational tasks, periodic inspections and training incorporated at Waterford 3. The evaluation credited the existing tagout restoration process to ensure that filling and venting of the system is performed per established operations procedures following maintenance activities.

ADDITIONAL INFORMATION

Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brac