05000461/LER-2016-010, Regarding Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications

Regarding Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications

ML16351A199
Person / Time
Site:	Clinton
Issue date:	12/13/2016
From:	Stoner T Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604324 LER 16-010-00
Download: ML16351A199 (4)

LER-2016-010, Regarding Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications

Event date:
Report date:
Reporting criterion:	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)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
4612016010R00 - NRC Website

text

~* Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604324 December 13, 2016 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 2016-010-00 10CFR50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LEA) 2016-010-00: 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 1 O CFR 50.73.

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.

~Ilk Theodore R. Stoner U -

Site Vice President Clinton Power Station DRA/cac Attachment: Licensee Event Report 2016-010-00 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 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

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 />.

1. 'Alll'o"t..o Reported lessons learned are incorporated into the licensing process and fed back to industry.

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LICENSEE EVENT REPORT (LER)

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections i

j Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail

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+O (See Page 2 for required number of digits/characters for each block) 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, Washington, DG 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.

3. PAGE Clinton Power Station, Unit 1 05000461 1 OF 3

4. TITLE 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

8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 10 14 2016 2016 - 010

- 00 12 13 2016 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: {Check all that apply)

D 20.2201 (b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A) 1 D 20.2201 <d>

D 20.2203(a)(3)(iil D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203(a)(1 >

D 20.2203(al<4>

D 50.13<a><2><m>

D 50.73(a)(2)(ix)(A)

D 20.2203<a><2>0>

D 50.36(c)(1 )(i)(A) 0 50.73(a)(2)(iv)(A)

D 50. 73(a)(2)(x) 1 O. 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<4l D 20.2203(a)c2>crn>

D 5o.36Cc><2>

D 50.73(a)(2)(v)(B)

D 13.11caJ(5)

D 20.2203(a)(2)(iv)

D 5o.4e(a)(3)(ii>

D 50.73(a)(2)(v)(C)

D 13.11(a)(1) 099 D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(D)

D 13.11cal<2>

D 20.2203(a)(2)(vi)

IZ! 50. 73(a)(2)(i)(B)

D 50.73(a)(2)(vii)

D 13.n<a><2><ii) f: ". .. Y

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D 50.73(a)(2)(i)(C)

D OTHER Specify in Abstract below or in NRC Fonm 366A

12. LICENSEE CONTACT FOR THIS LEA LICENSEE CONTACT rELEPHONE NUMBER (Include Area Code)

Dale A. Shelton, Regulatory Assurance Manager 217-937-2800 CAUSE SYSTEM COMPONENT MANU-REPORTABLE K

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TOEPIX

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FACTURER TOEPIX

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14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR IZ! YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

ONO SUBMISSION DATE 02 07 17 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

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 (BPV) Numbers 4, 5, and 6 was not performed within the required test interval and the BPVs were appropriately declared inoperable as required by TS Surveillance Requirement (SR) 3.0.1. Thermal Limit penalties were applied as required by Limiting Condition for 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 for SR 3.7.6.1 from 31 days to 12 months. BPVs 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. A causal evaluation is currently in progress. The causal factors creating this condition prohibited by TS, including the corrective actions, will be provided in the next revision to the Licensee Event Report. This event is reportable under 1 O CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS.

NRG FORM 366 (06-2016)

PLANT AND SYSTEM IDENTIFICATION

YEAR 2016 -

SEQUENTIAL NUMBER 010 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: Power Operation B.

DESCRIPTION OF EVENT

Event Time:

0830 Reactor Power:

99 percent REV NO.

00 On October 14, 2016, Clinton Power Station (CPS) determined subsequent to the 3rd Quarter NRG Exit Meeting that a condition prohibited by Technical Specification (TS) 3.7.6 had occurred associated with a failure to complete a TS Required Action within the associated Completion Time.

Specifically, on June 6th, 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. Bypass Valves (BPV) 4, 5, and 6were 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 Limiting Condition for Operation (LCO) 3.7.6.

On July 7, 2016, a Surveillance Frequency Change 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 bypass valve test was April 28, 2016. This new revision changed the due date for testing the bypass valves to April 28, 2017. With BPV 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.

C.

CAUSE OF EVENT

The causal factors that created this condition prohibited by Tech Spec 3.7.6 including the corrective actions will be provided in the next revision to the Licensee Event Report.

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. The event is reportable in accordance with 1 OCFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. The follow up Licensee Event Report will provide additional discussion of the safety analysis.

E.

CORRECTIVE ACTIONS

The corrective actions for this event will be provided in the follow up Licensee Event Report.

F.

PREVIOUS SIMILAR OCCURENCES

This information will be updated in the next follow up Licensee Event Report.

G.

COMPONENT FAILURE DATA

There was not component failure associated with this event. Page _3_ of _3_