05000353/LER-2011-003, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Reactor Core Isolation Cooling System

Regarding Condition Prohibited by Technical Specifications Due to Inoperable Reactor Core Isolation Cooling System

ML112020328
Person / Time
Site:	Limerick
Issue date:	07/21/2011
From:	Maguire W Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 11-003-00
Download: ML112020328 (5)

LER-2011-003, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Reactor Core Isolation Cooling System

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
3532011003R00 - NRC Website

text

10CFR50.73 July 21, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No. 50-353

Subject:

LER 2011-003-00, Condition Prohibited By Technical Specifications Due To Inoperable Reactor Core Isolation Cooling System This Licensee Event Report (LER) addresses an event that resulted in a condition prohibited by Technical Specifications due to an inoperable reactor core isolation cooling system and an inoperable primary containment isolation valve. The cause of the inoperability was leakage through the seat of two feedwater long path flushing valves.

This LER is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(i)(B).

There are no commitments contained in this letter.

If you have any questions or require additional information, please do not hesitate to contact us.

Sincerely, Original signed by William F. Maguire Vice President - Limerick Generating Station Exelon Generation Company, LLC cc: USNRC Administrator Region I USNRC Senior Resident Inspector, LGS

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)

LICENSEE EVENT REPORT (LER)

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

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013

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

1. FACILITY NAME Limerick Generating Station, Unit 2

2. DOCKET NUMBER 05000353

3. PAGE 1 OF 4

4. TITLE Condition Prohibited By Technical Specifications Due To Inoperable Reactor Core Isolation Cooling System

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 05 23 2011 2011 - 003 - 00 07 21 2011 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE 1

10. POWER LEVEL 100

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 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) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 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

Cause of the Event

The cause of the event was the HV-041-210 valve failed to isolate the feedwater long path recirculation line due to degradation of valve internals or stem lubrication degradation.

Corrective Action Planned In-body maintenance and diagnostic testing will be performed on HV-041-210 during the next refueling outage (2R12) which is currently scheduled for the spring of 2013.

The HV-041-110 and HV-041-210 valves preventive maintenance (PM) scope will be revised to include performance of diagnostic testing and an actuator PM.

The procedure (S06.5.A) for long path recirculation will be revised to add steps which will ensure HV-041-109A, HV-041-109B, HV-041-209A and HV-041-209B long path flushing valves are properly closed when securing long path flushing and verified as closed prior to restart.

Previous Similar Occurrences There were no similar events involving conditions prohibited by TS for an inoperable RCIC system for the last 3 years.

Component data:

Equipment:

Reactor Core Isolation Cooling System Component Number:

20-S212 Manufacturer:

T147 Terry Steam Turbine Co Model Number:

GS-2 TYP Equipment:

Feedwater Line Flushing PCIV Component Number:

HV-041-209B Manufacturer:

V085 Velan Valve Corp Model Number:

B20-07054P-02WN FIG