05000348/LER-2015-002, Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip

Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip

ML15183A310
Person / Time
Site:	Farley
Issue date:	07/02/2015
From:	Pierce C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-0963 LER 15-002-00
Download: ML15183A310 (6)

LER-2015-002, Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3482015002R00 - NRC Website

text

Charles R. Pierce Regulatory Affairs Director JUL 0 Z 2011 Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 I Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 Docket Nos.: 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2015-002-00 ou NL-15-0963 Technical.Specification Shutdown Due To Reactor Coolant Pump Trip Ladies and Gentlemen:

This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50.73(a)(2)(i)(A), for a plant shutdown required by Technical Specifications.

This letter contains no NRC commitments. If you have any questions regarding the submittal, please contact Ms. Julie Collier at (334) 814-4639.

Sincerely, c. fl.~

C. R. Pierce Regulatory Affairs Director CRP/jac/lac Enclosure: Unit 1 Licensee Event Report 2015-002-00 A

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U.S. Nuclear Regulatory Commission NL-15-0963 Page2 cc:

Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. D. R. Madison, Vice President-Fleet Operations Mr. B. J. Adams, Vice President-Engineering Ms. B. L. Taylor, Regulatory Affairs Manager-Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley

Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2015-002-00 Enclosure Technical Specification Shutdown Due To Reactor Coolant Pump Trip

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION !APPROVED BY OMB: NO. 3150.0104 EXPIRES: 1/31/2017 10.2010) stimated, the NRC may not conduct or sponsor, and a person is no squired to respond to, the Information collection.

3. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 348 Page 1 of3

~-TITLE Technical Specification Shutdown Due To Reactor Coolant Pump Trip

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR l SEQUENTIAL _I REV MONTH DAY YEAR FACILITY NAME pOCKET NUMBER NUMBER NO.

05 07 2015 2015-002-00 2015 FACILITY NAME pOCKET NUMBER

~- OPERATING MODE

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

D 20.2201 (bl D 20.2203(a)(3)(1}

D 50.73(a)(2)(1)(C}

D 50.73(a)(2}(vll}

1 D 20.2201 (d)

D 20.2203(a)(3}(11}

D 50.73(a)(2)(11}(A}

0 50.73(a}(2}(viii}(A}

D 2o.22oa(a}(1 >

0 20.2203(a)(4}

D 50.73(a}(2}(11)(B}

D 50.73(a}(2}(vlii)(B)

D 20.2203(a}(2}(1}

0 50.36(c)(1 )(I}(A}

D 50.73(a}(2}(111}

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

~ 0. POWER LEVEL D 20.2203(a}(2}(11}

0 50.36(c)(1 )(II}(A}

D 50.73(a)(2)(1v)(A}

D 50.73(a)(2}(x) 0 20.2203(a}(2)(111}

D 50.36(c}(2)

D 50.73(a)(2)(v)(A}

D 73.71(a}(4}

27%

D 20.2203(a}(2}(1v}

D 50.46(a)(3)(11}

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

D 73.71(a)(5}

D 20.2203(a}(2)(v}

181 50.73(a)(2}(1}(A}

D 50. 73(a}(2}(v}(C}

D OTHER 0 20.2203(a}(2}(vl}

0 50.73(a}(2}(1}(B}

D 50.73(a}(2}(v}(D}

Specify In Abstract below or In =

PLANT AND SYSTEM IDENTIFICATION

Westinghouse - Pressurized Water Reactor

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

YEAR 2015

6. LER NUMBER I

SEQUENTIAL I NUMBER 002 REV NO.

00 3.PAGE 2 of3 Energy Industry Identification Codes are identified in the text as [XX].

DESCRIPTION OF EVENT

At 0740 COT on May 7, 2015, while at 27 percent power in Mode 1, the Unit 1 reactor was shut down per operating procedures and entered Mode 3. This shutdown was required by Technical Specification (T.S.) 3.4.4 Condition A which was entered at 0509 when the 1 8 Reactor Coolant Pump (RCP) tripped. The cause of the 1 8 RCP trip was a loss of the 18 electrical bus when the transfer of station loads from 18 Start Up Auxiliary Transformer (SAT) to the 1 B Unit Auxiliary Transformer (UAT) failed due to jumpers having been inappropriately left in place during maintenance work associated with the installation of a new 1 B UAT. The 18 Circulating Water pump also tripped when the 18 bus was de-energized. The plant also entered T.S. 3.4.2 condition A for Reactor Coolant System Minimum Temperature for Criticality due to the transient in loop temperature caused by the loss of the 18 RCP. This condition was exited after 15 minutes.

In 2006 a new transformer for the 1 8 UAT was partially installed in the Low Voltage Switchyard (LVSY). It remained on a storage pad in the LVSY since that time. Factory installed jumpers were in place to protect the current transformers. During the Unit 1 refueling outage in April and May of 2015 the design package to complete the installation was implemented as a station reliability enhancement initiative. While ascending in power from 1 R26, the operating crew was transferring station loads from the 18 SAT to the 1 B UAT when an unexpected actuation of the 18 UAT protective relaying occurred resulting in the loss of the 18 bus and subsequently the 18 RCP due to the jumpers having not been removed prior to energizing the 18 UAT.

CAUSE OF EVENT

The cause of this event was that jumpers were inappropriately left in place because of a failure to adhere to station standards during the project management process for the 18 UAT design change. Lapses in standards occurred at various levels of the organization in project oversight, work planning preparation and review, and proper post modification testing.

The causal analysis for this event is still in progress. This LER will be supplemented if information in this LER is affected by the final approved causal analysis.

REPORTA81LITY ANALYSIS AND SAFETY ASSESSMENT This event is reportable as required by 10 CFR 1 50.73(a)(2)(i)(A) due to a Unit 1 shutdown required by Technical Specifications. Technical Specification 3.4.4 Condition A was entered at 0509 when the 18 RCP tripped. The abnormal operating procedure was entered for loss of reactor coolant flow. The reactor was shut down at 0740 and mode 3 was entered to complete the required TS action. All safety related equipment operated as designed in association with this event. There was no loss of safety function and no radioactive release associated with this event. There was no actual consequence detrimental to the health and safety of the public.

rmc

CORRECTIVE ACTION

, the NRC may not conduct or sponsor, and a person is not required to respond to, the Information collection.

YEAR 2015

6. LER NUMBER I

SEQUENTIAL I NUMBER 002 REV NO.

00 3.PAGE 3 of3 Immediate actions were the removal of the jumpers and the completion of extensive post modification testing.

Additional corrective actions will be taken to reinforce planning and project management standards and strengthen post modification testing development guidance.

ADDITIONAL INFORMATION

Other system affected:

No systems other than those mentioned in this report were affected by this event.

Commitment Information: This report does not create any licensing commitments

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