05000353/LER-2011-004, For Limerick, Unit 2, Regarding Automatic Actuation of the Reactor Protection System Due to Actuation of Turbine Control Valve Closure Logic

For Limerick, Unit 2, Regarding Automatic Actuation of the Reactor Protection System Due to Actuation of Turbine Control Valve Closure Logic

ML112082025
Person / Time
Site:	Limerick
Issue date:	07/27/2011
From:	Maguire W Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 11-004-00
Download: ML112082025 (5)

LER-2011-004, For Limerick, Unit 2, Regarding Automatic Actuation of the Reactor Protection System Due to Actuation of Turbine Control Valve Closure Logic

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 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
3532011004R00 - NRC Website

text

10CFR50.73 July 27, 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 2011-004-00, Automatic Actuation of the Reactor Protection System Due to Actuation of the Turbine Control Valve Fast Closure Logic This Licensee Event Report (LER) addresses an event that resulted in an automatic actuation of the reactor protection system due to an actuation of the turbine control valve fast closure logic. The actuation occurred during restoration of a main turbine control valve following maintenance.

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

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 Peter A. Gardner for 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 Automatic Actuation of the Reactor Protection System Due To Actuation Of Turbine Control Valve Closure Logic

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 29 2011 2011 - 004 - 00 07 27 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 Corrective Action Planned A procedure will be developed and implemented to provide specific restoration steps for turbine control, stop, and combined intermediate valves.

Previous Similar Occurrences There was no similar event in the last 3 years.

Component data:

Equipment:

Main Turbine Control Valve Component Number:

CV-001-3 Manufacturer:

G080 General Electric Company Model Number:

823E838 DWG Equipment:

Main Turbine Control Valve Operator Component Number:

CV-001-3-OP Manufacturer:

G080 General Electric Company Model Number:

944D549 DWG Equipment:

CV-001-3 RETS EHC Isolation Valve Component Number:

031-2013 Manufacturer:

W165 Whitey Company Model Number:

SS-65ESW16T Equipment:

CV-001-1 RETS Pressure Switch Component Number:

PS-001-202C Manufacturer:

B070 Barksdale Control Division /

Delaval Inc Model Number:

TC9622-3-V