ML17067A413: Difference between revisions
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Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Licensee Event Report 2016-010-01 | Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Licensee Event Report 2016-010-01 | ||
* 10CFR50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2016-010-01: | * 10CFR50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2016-010-01: | ||
Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications. | Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications. | ||
This report is being submitted in accordance with the requirements of 10 CFR 50.73 and is a follow up to LER 2016-010-00 provided on December 13, 2016. Revision bars are provided in the margins to denote modifications made to the content of the LER since the previous submittal. | This report is being submitted in accordance with the requirements of 10 CFR 50.73 and is a follow up to LER 2016-010-00 provided on December 13, 2016. Revision bars are provided in the margins to denote modifications made to the content of the LER since the previous submittal. | ||
There are no regulatory commitments contained in this report. Should you have any questions concerning this report, please contact Mr. Dale Shelton, | There are no regulatory commitments contained in this report. Should you have any questions concerning this report, please contact Mr. Dale Shelton, *Regulatory Assurance Manager, at (217) 937-2800. | ||
*Regulatory Assurance | |||
Theodore R. Stoner Site Vice President Clinton Power Station KP/cac | Theodore R. Stoner Site Vice President Clinton Power Station KP/cac | ||
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Licensee Event Report 2016-010-01 cc: Regional Administrator-NRC Region Ill NRC Senior Resident Inspector | Licensee Event Report 2016-010-01 cc: Regional Administrator-NRC Region Ill NRC Senior Resident Inspector | ||
-Clinton Power Station Office of Nuclear Facility Safety-Illinois Emergency Management Agency NRC FORM 366 (06-2016) | -Clinton Power Station Office of Nuclear Facility Safety-Illinois Emergency Management Agency NRC FORM 366 (06-2016) | ||
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: | U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 LICENSEE EVENT REPORT (LER) (See Page 2 for required number of digits/characters for each block) 1. FACILITY NAME Clinton Power Station, Unit 1 4. TITLE Estimated burden per response to comply with this mandatory collection request 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | ||
10/31/2018 LICENSEE EVENT REPORT (LER) (See Page 2 for required number of digits/characters for each block) 1. FACILITY NAME Clinton Power Station, Unit 1 4. TITLE Estimated burden per response to comply with this mandatory collection request 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail lo lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection. | ||
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail lo lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory | : 2. DOCKET NUMBER 05000461 3. PAGE 1 OF 3 Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications | ||
Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection. | |||
: 2. DOCKET NUMBER 05000461 | |||
: 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE MONTH DAY YEAR YEAR I SEQUENTIAL I REV MONTH DAY NUMBER NO. YEAR FACILITY NAME FACILITY NAME 8. OTHER FACILITIES INVOLVED DOCKET NUMBER 05000 10 14 2016 2016 -010 -01 03 06 2017 DOCKET NUMBER 05000 9. OPERATING MODE. 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Checks/I that apply) D 20.2201(b) 0 20.2203(a)(3)(i) | : 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE MONTH DAY YEAR YEAR I SEQUENTIAL I REV MONTH DAY NUMBER NO. YEAR FACILITY NAME FACILITY NAME 8. OTHER FACILITIES INVOLVED DOCKET NUMBER 05000 10 14 2016 2016 -010 -01 03 06 2017 DOCKET NUMBER 05000 9. OPERATING MODE. 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Checks/I that apply) D 20.2201(b) 0 20.2203(a)(3)(i) | ||
D S0.73(a)(2)(ii)(A) | D S0.73(a)(2)(ii)(A) | ||
Line 77: | Line 70: | ||
.. , CAUSE SYSTEM COMPONENT. | .. , CAUSE SYSTEM COMPONENT. | ||
MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX. | MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX. | ||
.... 14. SUPPLEMENTAL REPORT EXPECTED 0 YES (If yes, complete | .... 14. SUPPLEMENTAL REPORT EXPECTED 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE} [8J NO ABSTRACT (Umit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 15. EXPECTED SUBMISSION DATE MONTH DAY YEAR On October 14, 2016, Clinton Power Station (CPS) determined subsequent to the 3rd Quarter NRC Exit Meeting that a condition prohibited by Technical Specification (TS) 3.7.6, "Main Turbine Bypass System," had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, testing of Main Steam Turbine Bypass Valve (TBV) Numbers 4, 5, and 6 was not performed within the required test interval and the TBVs were appropriately declared inoperable as required by TS Surveillance Requirement | ||
.(SR) 3.d.1. Thermal Limit penalties were applied as required by Limiting Condition tor Operation (LCO) 3.7.6. A Surveillance Frequency Change was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," in June 2016 to change the Frequency tor SR 3.7.6.1 from 31 days to 12 months. TBVs 5 and 6 were subsequently declared OPERABLE and the thermal limit penalties removed without performing the required SR 3.7.6.1, contrary to TS SR 3.0.1 Bases. The apparent cause of this event was determined to be that no specific requirement exists in either plant procedures or industry guidance which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval. | |||
had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, testing of Main Steam Turbine Bypass Valve (TBV) Numbers 4, 5, and 6 was not performed within the required test interval and the TBVs were appropriately declared inoperable as required by TS Surveillance Requirement | Corrective actions include testing the valves with an alternate method and completing administrative procedure changes. This event is reportable under 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. NRC FORM 366 (06-2016) | ||
.(SR) 3.d.1. Thermal Limit penalties were applied as required by Limiting Condition tor Operation (LCO) 3.7.6. A Surveillance Frequency Change was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," | |||
in June 2016 to change the Frequency tor SR 3.7.6.1 from 31 days to 12 months. TBVs 5 and 6 were subsequently declared OPERABLE and the thermal limit penalties removed without performing the required SR 3.7.6.1, contrary to TS SR 3.0.1 Bases. The apparent cause of this event was determined to be that no specific requirement exists in either plant procedures or industry guidance which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval. | |||
Corrective actions include testing the valves with an alternate method and completing administrative procedure changes. | |||
This event is reportable under 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. NRC FORM 366 (06-2016) | |||
NRC FORM 366A (06-2016)) | NRC FORM 366A (06-2016)) | ||
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: | U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 LICENSEE EVENT REPORT (LEA) CONTINUATION SHEET Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | ||
10/31/2018 LICENSEE EVENT REPORT (LEA) CONTINUATION SHEET Estimated burden per response to comply with this mandatory collection request: | Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washing1on, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. | ||
80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | |||
Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory | |||
Office of Management and Budget, Washing1on, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. | |||
: 1. FACILITY NAME 2. DOCKET NUMBER Clinton Power Station, Unit 1 05000461 YEAR 3. LEA NUMBER SEQUENTIAL NUMBER REV NO. 2016 -010 -01 NARRATIVE PLANT AND SYSTEM IDENTIFICATION General Electric-Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EllS) codes are identified in the text as [XX] EVENT IDENTIFICATION Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications* | : 1. FACILITY NAME 2. DOCKET NUMBER Clinton Power Station, Unit 1 05000461 YEAR 3. LEA NUMBER SEQUENTIAL NUMBER REV NO. 2016 -010 -01 NARRATIVE PLANT AND SYSTEM IDENTIFICATION General Electric-Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EllS) codes are identified in the text as [XX] EVENT IDENTIFICATION Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications* | ||
A. Plant Operating Conditions before the Event Unit: 1 Mode: 1 Event Date: 10/14/16 Mode Name: P?wer Operation B. DESCRIPTION OF EVENT Event Time: 0830 Reactor Power: 99 percent | A. Plant Operating Conditions before the Event Unit: 1 Mode: 1 Event Date: 10/14/16 Mode Name: P?wer Operation B. DESCRIPTION OF EVENT Event Time: 0830 Reactor Power: 99 percent | ||
* On October 14, 2016, Clinton Power Station (CPS) subsequent to the 3rd Quarter NRC Exit Meeting that a condition prohibited by Technical Specification | * On October 14, 2016, Clinton Power Station (CPS) subsequent to the 3rd Quarter NRC Exit Meeting that a condition prohibited by Technical Specification | ||
{TS) 3.7.6, "Main Turbine I *Bypass System,'' | {TS) 3.7.6, "Main Turbine I *Bypass System,'' | ||
had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, on June 6, 2016, the TS Limiting Condition for Operations (LCO) Surveillance Requirement (SR) 3.0.2 grace period of 1.25 times the normal required Frequency (31 days) for completing testing of the Main Steam Bypass Valves per SR 3.7.6.1 was exceeded for the Main Turbine Bypass System. Turbine Bypass Valves (TBV) 4, 5, and 6 were not tested within the required Frequency and the valves were declared inoperable as required by TS SR 3.0.1.Thermal Limit penalties were applied as required by LCO 3. 7.6. On July 7, 2016, a Surveillance Frequency Ch?nge was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," | had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, on June 6, 2016, the TS Limiting Condition for Operations (LCO) Surveillance Requirement (SR) 3.0.2 grace period of 1.25 times the normal required Frequency (31 days) for completing testing of the Main Steam Bypass Valves per SR 3.7.6.1 was exceeded for the Main Turbine Bypass System. Turbine Bypass Valves (TBV) 4, 5, and 6 were not tested within the required Frequency and the valves were declared inoperable as required by TS SR 3.0.1.Thermal Limit penalties were applied as required by LCO 3. 7.6. On July 7, 2016, a Surveillance Frequency Ch?nge was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," for TS SR 3.7.6.1 to change the required Frequency from 31 days to 12 months. The last performance credit date of the TBV test was April 28, 2016. This new revision changed the due date for testing the TBVs to April 28, 2017. With TBV testing performed within the new required interval, the valves were declared OPERABLE and the Thermal Limit penalties removed without performing the required SR 3.7.6.1. It was subsequently determined, however, that in accordance with TS SR 3.0.1 Bases, the Surveillance had to be met and performed in accordance with SR 3.0.2 prior to returning equipment to OPERABLE status. The failure to perform the TS SR within the test interval without applying the Actions of TS 3.7.6 . was a condition prohibited by TS. NRC FORM 366A (06*2016) | ||
for TS SR 3.7.6.1 to change the required Frequency from 31 days to 12 months. The last performance credit date of the TBV test was April 28, 2016. This new revision changed the due date for testing the TBVs to April 28, 2017. With TBV testing performed within the new required | |||
It was subsequently determined, | |||
Page _2_ of _3_ | Page _2_ of _3_ | ||
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: | U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/3112018 NRC FORM 366A (06-2016)) | ||
10/3112018 NRC FORM 366A (06-2016)) | l i LICENSEE EVENT REPORT (LER) CONTINUATION SHEET ii) ....... .. Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | ||
l i LICENSEE EVENT REPORT (LER) CONTINUATION SHEET ii) ....... .. Estimated burden per response to comply with this mandatory collection request: | Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (315(}0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection. | ||
80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. | |||
Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory | |||
Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection. | |||
: 1. FACILITY NAME 2. DOCKET NUMBER YEAR Clinton Power Station, Unit 1 05000461 2016 -NARRATIVE | : 1. FACILITY NAME 2. DOCKET NUMBER YEAR Clinton Power Station, Unit 1 05000461 2016 -NARRATIVE | ||
: 3. LER NUMBER SEQUENTIAL NUMBER 010 REV NO. -' 01 A surveillance test for TBVs 4, 5, and 6 was satisfactorily completed on September 28, 2016 I using an alternate methodology. | : 3. LER NUMBER SEQUENTIAL NUMBER 010 REV NO. -' 01 A surveillance test for TBVs 4, 5, and 6 was satisfactorily completed on September 28, 2016 I using an alternate methodology. | ||
C. CAUSE OF EVENT No specific requirement exists in either Exelon administrative procedures or NEI 04-10, "Risk Informed Technical Specifications," | C. CAUSE OF EVENT No specific requirement exists in either Exelon administrative procedures or NEI 04-10, "Risk Informed Technical Specifications," which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval. | ||
which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval. | Licensed operator staff incorrectly interpreted TS SR 3.0.1 *Bases based on the guidance provided iri OP-AA-108-106, "Equipment Return to Service." D. SAFETY ANALYSIS *. There were no safety consequences associated with the event described in this report since no thermal limits were exceeded during the time the thermal limit penalty was not invoked .. A subsequent surveillance test of TBVs 4, 5, and 6 was satisfactorily completed on September 26, 2016, using an alternate test method, demonstrating that the TBVs would have properly responded to an event. The ability of the plant to safely shutdown was not affected as a result of the conditions described in this report. E. CORRECTIVE ACTIONS Turbine Bypass Valves 4, 5, and 6 were satisfactorily tested on September 28, 2016 using an alternate test methodology. | ||
Licensed operator staff incorrectly interpreted TS SR 3.0.1 *Bases based on the guidance provided iri OP-AA-108-106, "Equipment Return to Service." | The insight gained from this event was shared with on-shift licensed operators and the Exelon Operations peer group. Operating procedure changes are being made to ensure the requirements of SR 3.0.1 are clear regarding implementation of surveillance frequency changes. F. PREVIOUS SIMILAR OCCURENCES There were no previous occurrences associated with this event. G. COMPONENT FAILURE DATA There was not a component failure associated with this event. NRC FORM 366A (06-2016) | ||
D. SAFETY ANALYSIS | |||
*. There were no safety consequences associated with the event described in this report since no thermal limits were exceeded during the time the thermal limit penalty was not invoked .. A subsequent surveillance test of TBVs 4, 5, and 6 was satisfactorily completed on September 26, 2016, using an alternate test method, demonstrating that the TBVs would have properly responded to an event. The ability of the plant to safely shutdown was not affected as a result of the conditions described in this report. E. CORRECTIVE ACTIONS Turbine Bypass Valves 4, 5, and 6 were satisfactorily tested on September 28, 2016 using an alternate test methodology. | |||
The insight gained from this event was shared with on-shift licensed operators and the Exelon Operations peer group. Operating procedure changes are being made to ensure the requirements of SR 3.0.1 are clear regarding implementation of surveillance frequency changes. | |||
F. PREVIOUS SIMILAR OCCURENCES There were no previous occurrences associated with this event. G. COMPONENT FAILURE DATA There was not a component failure associated with this event. NRC FORM 366A (06-2016) | |||
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Revision as of 23:59, 7 July 2018
ML17067A413 | |
Person / Time | |
---|---|
Site: | Clinton ![]() |
Issue date: | 03/06/2017 |
From: | Stoner T R Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
U-604334 LER 16-010-01 | |
Download: ML17067A413 (4) | |
Text
_,,, Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604334 March 6, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Licensee Event Report 2016-010-01
- 10CFR50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2016-010-01:
Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications.
This report is being submitted in accordance with the requirements of 10 CFR 50.73 and is a follow up to LER 2016-010-00 provided on December 13, 2016. Revision bars are provided in the margins to denote modifications made to the content of the LER since the previous submittal.
There are no regulatory commitments contained in this report. Should you have any questions concerning this report, please contact Mr. Dale Shelton, *Regulatory Assurance Manager, at (217) 937-2800.
Theodore R. Stoner Site Vice President Clinton Power Station KP/cac
Attachment:
Licensee Event Report 2016-010-01 cc: Regional Administrator-NRC Region Ill NRC Senior Resident Inspector
-Clinton Power Station Office of Nuclear Facility Safety-Illinois Emergency Management Agency NRC FORM 366 (06-2016)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 LICENSEE EVENT REPORT (LER) (See Page 2 for required number of digits/characters for each block) 1. FACILITY NAME Clinton Power Station, Unit 1 4. TITLE Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail lo lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET NUMBER 05000461 3. PAGE 1 OF 3 Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications
- 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE MONTH DAY YEAR YEAR I SEQUENTIAL I REV MONTH DAY NUMBER NO. YEAR FACILITY NAME FACILITY NAME 8. OTHER FACILITIES INVOLVED DOCKET NUMBER 05000 10 14 2016 2016 -010 -01 03 06 2017 DOCKET NUMBER 05000 9. OPERATING MODE. 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Checks/I that apply) D 20.2201(b) 0 20.2203(a)(3)(i)
D S0.73(a)(2)(ii)(A)
- D 50.73(a)(2)(viii)(A)
D 20.2201(dl D 20.2203(alC3l(ii)
D s0.73(a)(2)(ii)(B)
D 50. 73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.13(a)(2)(iiil D 50. 73(a)(2)(ixJ(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
- D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11cal(4)
D 20.2203(a)(2)(iii)
D 5o.3s(c)(2l D 50.73(a)(2)(v)(B)
D 13.11ca)(5)
D 20.2203(a)(2)(iv)
D 5o.4s(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 13.77(a)(1) 099 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D S0.73(a)(2)(v)(D)
D 13.11(a)(2)(i)
D 20.2203(a)(2)(vi)
[8J 50. 73(a)(2)(i)(B)
- D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50. 73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in NRC Form 366A 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT !TELEPHONE NUMBER (Include Area Code) Dale A. Shelton, Regulatory Assurance Manager 217-937-2800
-13. COMPLETE ONE LINE FOR EACH COMPONENT FAlLURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MANU-REPORTABLE
.. , CAUSE SYSTEM COMPONENT.
MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX.
.... 14. SUPPLEMENTAL REPORT EXPECTED 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE} [8J NO ABSTRACT (Umit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 15. EXPECTED SUBMISSION DATE MONTH DAY YEAR On October 14, 2016, Clinton Power Station (CPS) determined subsequent to the 3rd Quarter NRC Exit Meeting that a condition prohibited by Technical Specification (TS) 3.7.6, "Main Turbine Bypass System," had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, testing of Main Steam Turbine Bypass Valve (TBV) Numbers 4, 5, and 6 was not performed within the required test interval and the TBVs were appropriately declared inoperable as required by TS Surveillance Requirement
.(SR) 3.d.1. Thermal Limit penalties were applied as required by Limiting Condition tor Operation (LCO) 3.7.6. A Surveillance Frequency Change was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," in June 2016 to change the Frequency tor SR 3.7.6.1 from 31 days to 12 months. TBVs 5 and 6 were subsequently declared OPERABLE and the thermal limit penalties removed without performing the required SR 3.7.6.1, contrary to TS SR 3.0.1 Bases. The apparent cause of this event was determined to be that no specific requirement exists in either plant procedures or industry guidance which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval.
Corrective actions include testing the valves with an alternate method and completing administrative procedure changes. This event is reportable under 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. NRC FORM 366 (06-2016)
NRC FORM 366A (06-2016))
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 LICENSEE EVENT REPORT (LEA) CONTINUATION SHEET Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washing1on, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER Clinton Power Station, Unit 1 05000461 YEAR 3. LEA NUMBER SEQUENTIAL NUMBER REV NO. 2016 -010 -01 NARRATIVE PLANT AND SYSTEM IDENTIFICATION General Electric-Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EllS) codes are identified in the text as [XX] EVENT IDENTIFICATION Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications*
A. Plant Operating Conditions before the Event Unit: 1 Mode: 1 Event Date: 10/14/16 Mode Name: P?wer Operation B. DESCRIPTION OF EVENT Event Time: 0830 Reactor Power: 99 percent
- On October 14, 2016, Clinton Power Station (CPS) subsequent to the 3rd Quarter NRC Exit Meeting that a condition prohibited by Technical Specification
{TS) 3.7.6, "Main Turbine I *Bypass System,
had occurred associated with a failure to complete a TS Required Action within the associated Completion Time. Specifically, on June 6, 2016, the TS Limiting Condition for Operations (LCO) Surveillance Requirement (SR) 3.0.2 grace period of 1.25 times the normal required Frequency (31 days) for completing testing of the Main Steam Bypass Valves per SR 3.7.6.1 was exceeded for the Main Turbine Bypass System. Turbine Bypass Valves (TBV) 4, 5, and 6 were not tested within the required Frequency and the valves were declared inoperable as required by TS SR 3.0.1.Thermal Limit penalties were applied as required by LCO 3. 7.6. On July 7, 2016, a Surveillance Frequency Ch?nge was processed in accordance with TS Program 5.5.16, "Surveillance Frequency Control Program," for TS SR 3.7.6.1 to change the required Frequency from 31 days to 12 months. The last performance credit date of the TBV test was April 28, 2016. This new revision changed the due date for testing the TBVs to April 28, 2017. With TBV testing performed within the new required interval, the valves were declared OPERABLE and the Thermal Limit penalties removed without performing the required SR 3.7.6.1. It was subsequently determined, however, that in accordance with TS SR 3.0.1 Bases, the Surveillance had to be met and performed in accordance with SR 3.0.2 prior to returning equipment to OPERABLE status. The failure to perform the TS SR within the test interval without applying the Actions of TS 3.7.6 . was a condition prohibited by TS. NRC FORM 366A (06*2016)
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U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/3112018 NRC FORM 366A (06-2016))
l i LICENSEE EVENT REPORT (LER) CONTINUATION SHEET ii) ....... .. Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarcing burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (315(}0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER YEAR Clinton Power Station, Unit 1 05000461 2016 -NARRATIVE
- 3. LER NUMBER SEQUENTIAL NUMBER 010 REV NO. -' 01 A surveillance test for TBVs 4, 5, and 6 was satisfactorily completed on September 28, 2016 I using an alternate methodology.
C. CAUSE OF EVENT No specific requirement exists in either Exelon administrative procedures or NEI 04-10, "Risk Informed Technical Specifications," which prohibits declaring a component or system OPERABLE based solely on an extension of the required surveillance test interval.
Licensed operator staff incorrectly interpreted TS SR 3.0.1 *Bases based on the guidance provided iri OP-AA-108-106, "Equipment Return to Service." D. SAFETY ANALYSIS *. There were no safety consequences associated with the event described in this report since no thermal limits were exceeded during the time the thermal limit penalty was not invoked .. A subsequent surveillance test of TBVs 4, 5, and 6 was satisfactorily completed on September 26, 2016, using an alternate test method, demonstrating that the TBVs would have properly responded to an event. The ability of the plant to safely shutdown was not affected as a result of the conditions described in this report. E. CORRECTIVE ACTIONS Turbine Bypass Valves 4, 5, and 6 were satisfactorily tested on September 28, 2016 using an alternate test methodology.
The insight gained from this event was shared with on-shift licensed operators and the Exelon Operations peer group. Operating procedure changes are being made to ensure the requirements of SR 3.0.1 are clear regarding implementation of surveillance frequency changes. F. PREVIOUS SIMILAR OCCURENCES There were no previous occurrences associated with this event. G. COMPONENT FAILURE DATA There was not a component failure associated with this event. NRC FORM 366A (06-2016)
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