05000352/LER-2012-008, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Isolation Instrumentation

Regarding Condition Prohibited by Technical Specifications Due to Inoperable Isolation Instrumentation

ML12318A120
Person / Time
Site:	Limerick
Issue date:	11/12/2012
From:	Dougherty T Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LER 12-008-00
Download: ML12318A120 (5)

LER-2012-008, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Isolation Instrumentation

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(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
3522012008R00 - NRC Website

text

10CFR50.73 November 12, 2012 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC Docket No. 50-352

Subject:

LER 2012-008-00, Condition Prohibited by Technical Specifications due to Three Inoperable Isolation Instrumentation Channels This Licensee Event Report (LER) addresses a condition prohibited by Technical Specifications due to three surveillance test failures. The tests failed due to exceeding the isolation instrumentation channel response time limit. This event also involved common-cause failures of independent channels.

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

There are no commitments contained in this letter.

If you have any questions, please contact Robert B. Dickinson at (610) 718-3400.

Respectfully, Original signed by David P. Lewis for Thomas J. Dougherty Vice President - Limerick Generating Station Exelon Generation Company, LLC cc: Administrator Region I, USNRC 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 1

2. DOCKET NUMBER 05000352

3. PAGE 1 OF 4

4. TITLE Condition Prohibited by Technical Specifications Due to Inoperable Isolation Instrumentation

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 09 13 2012 2012 - 008 - 00 11 12 2012 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 Corrective Action Planned The relay testing and/or replacement procedure (IC-C-11-04067) will be revised to include a step-by-step method of selecting relays with the shortest contact release times upon de-energization of the relay.

A new stock code will be created for new relays that have been response time tested and found to be acceptable for this application.

Previous Similar Occurrences On April 6, 2011, an apparent cause evaluation (IR 1186147 assignment

02) was completed regarding MSL flow response time test failures that occurred in 2010.

On April 19, 2012, Unit 1 LER 2012-001 reported 3 of 8 as-found MSIV closing stroke times exceeded the 5 second TS limit.

Component data:

System:

Primary Containment Isolation System B21H-K4A NSSS System Steam Line High Flow Relay Manufacturer:

Tyco Electronics Model:

EGPB004 System:

Primary Containment Isolation System B21H-K14A Main Steam Line Isolation Relay Manufacturer:

Tyco Electronics Model:

EGPI004