text
.Zf Exelkn.
Exelon Nuclear www.exeloncorp.com Nucea Limerick Generating Station IudeaT P.O. Box 2300 Pottstown, PA 19464 1 OCFR50.73 November 18,2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39
-- NNRC Docket No. 50-352
Subject:
LER 1-05-004 Minimum Critical Power Ratio Limiting Condition For Operation Noncompliance This Licensee Event Report (LER) addresses an evaluation of the impact of a General Electric Part 21 report dated 9/20/05 which determined that Limerick Unit 1 operated in non-compliance with Technical Specification 3.2.3, Minimum Critical Power Ratio (MCPR), on two occasions when the MCPR was less than the limiting condition for operation (LCO). These periods of operation exceeded the allowance stated in the TS action statement.
Report Number:
1-05-004 Revision:
00 Event Date:
May 29,2004 Discovered Date-September 20, 2005 Report Date:
November 18,2005 This LER is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(i)(B).
If you have any questions or require additional information, please do not hesitate to contact us.
- - Sincerely, Ron Vice President-Limerick Exelon Generation Company, LLC cc: S. J. Collins, Administrator Region I, USNRC S. L. Hansell, USNRC Senior Resident Inspector, LGS D _*
C;4
SUMMARY OF EXELON NUCLEAR COMMITMENTS LS-AA-1 17-1003 Rev. 2 The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not intended as regulatory commitments.)
Commitment #1 Committed Date (or Outage): NA None
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are Incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T5 F52). U.S. Nuclear LIEN EEEV N R PO T LE )Regulatory Commission, Washington, DC 20555-001.*orb' Internet e-maillto LICENSEE EVENT REPORT (LER) lnfocollectsOnrc.gov, and to the Desk Officer. Office o Information and RegulatoryAffairs, NEOB-1 0202, (3150-0104), Office of Managementand Budget Washington, DC 20503. If a means used to Impose an Information collection (See reverse for required number of doesnotdisplayacurrentlyvalidOMB controlnumber the NRCrmaynotconduct or sponsor, and a person Is not required to respond to. the Information digits/characters for each block) collection.____________
- 3. PAGE Limerick Generating Station, Unit I 05000352 1 OF 3
- 4. TITLE Minimum Critical Power Ratio Limiting Condition For Operation Noncompliance
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE I
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR NSE RNTIAL MONTH I DAY YEAR 11I E
NADOCKETENUMBER FACIUTY NAME DOCKETNUMBER 05.
T. 29 2004 12005
- - _004-10 11 1-2005 -
I -nrnn1%
3- -
uauuuV
- 9. OPERATING MODE 1i. THIS REPORT IS SUBMITTED PURSUANT TO THEREQUIREMENTS O
F 10 CFR§:
(C heck al that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
Co 20.2203(a)(2)(i) 0 50.36(e)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
] 20.2203(a)(2)(i) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) 0 20.2203(a)(2)01i) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 94 0 202203(a)(2)(v) 0 50.73(a)(2)(1)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
SpecifyIn Abstract below or In (If more space Is required, use additional copies of NRC Form 366A) (17)
Cause of the Event
The event was caused by a deformation in the Zircaloy spacer during GE-14 ATLAS critical power testing. This deformation resulted in a non-conservative error in the test results.
Corrective Action Completed I An evaluation of Unit 1 and Unit 2 vulnerability to the Part 21 condition has been completed. No compensatory measures are required at this time.
To prevent a similar issue from occurring on Unit 2, an administrative limit was implemented to provide additional margin to the calculation of the MFLCPR prior to Unit 2 entering the portion of the operating cycle where the Part 21 issue is applicable.
Corrective Action Planned GE is currently reviewing previous cycles for Unit 1 and Unit 2, which GE will complete by December 31, 2005.
A new databank and coding will be installed in Unit 1 and Unit 2 3D Monicore. This action will be completed by March 31, 2006.
Previous Similar Occurrences There were no previous similar occurrences where noncompliance with a TS power distribution limit existed for a period that exceeded the TS action statement allowance for restoration.
A_
Component data:
Cause
System:
Component:
Manufacturer:
Type:
Model:
Reportable to EPIX:
B AC N/A G080 GE-1 4 N/A No (Design, Manufacturing, Construction/Installation)
Reactor Core System General Electric Fuel
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000353/LER-2005-001, Re Core Alterations Performed with Source Range Monitor Alarm Horn Inoperable | Re Core Alterations Performed with Source Range Monitor Alarm Horn Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000352/LER-2005-001, Re Loss of Licensed Material in the Form of a Radiation Detector Calibration Source | Re Loss of Licensed Material in the Form of a Radiation Detector Calibration Source | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000352/LER-2005-002, Regarding Offsite Source Trip Due to Water Intrusion Into Transformer Winding Temperature Switch | Regarding Offsite Source Trip Due to Water Intrusion Into Transformer Winding Temperature Switch | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000353/LER-2005-002, Regarding Unit 2 High Pressure Coolant Injection (HPCI) Inoperable | Regarding Unit 2 High Pressure Coolant Injection (HPCI) Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000352/LER-2005-003, Regarding Scram Due to Invalid Actuation of Main Generator Output Breaker Position Monitor Circuit | Regarding Scram Due to Invalid Actuation of Main Generator Output Breaker Position Monitor Circuit | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000353/LER-2005-003, Regarding Operation Exceeding License Maximum Power Level | Regarding Operation Exceeding License Maximum Power Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | | 05000353/LER-2005-004, Reactor Scram Due to EHC Malfunction That Closed the Main Turbine Control Valves | Reactor Scram Due to EHC Malfunction That Closed the Main Turbine Control Valves | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000352/LER-2005-004, Re Minimum Critical Power Ratio Limiting Condition for Operation Noncompliance | Re Minimum Critical Power Ratio Limiting Condition for Operation Noncompliance | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000352/LER-2005-005, Missed Surveillance Resulted in a Condition Prohibited by Technical Specifications | Missed Surveillance Resulted in a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
|