05000364/LER-2015-001, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue

Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue

ML15068A216
Person / Time
Site:	Farley
Issue date:	03/09/2015
From:	Pierce C Southern Co, Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-0226 LER 15-001-00
Download: ML15068A216 (6)

LER-2015-001, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(iv)(A), System Actuation 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), Loss of Safety Function
3642015001R00 - NRC Website

text

Charles R. Pierce Regulatory Affairs Director March 09, 2015 Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 Docket Nos.: 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant-Unit 2 Licensee Event Report 2015-001-00 SOUTHERN A COMPANY NL-15-0226 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due to a Design Issue 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)(B) as an condition prohibited by Technical Specifications. This is also being submitted as a condition that could have prevented fulfillment of a safety function per 10 CFR 50.73(a)(2)(v)(B).

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

Sincerely, t.1?

C. R. Pierce Regulatory Affairs Director CRP/jac/lac Enclosure: Unit 2 Licensee Event Report 2015-001-00

U.S. Nuclear Regulatory Commission NL-1 5-0226 Page 2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, 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 Mr. R. R. Martin, 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

Enclosure Joseph M. Farley Nuclear Plant-Unit 2 Unit 2 Licensee Event Report 2015-001-00 NL-15-0226 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due to a Design Issue

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-Q104 EXPIRES: 1/31/2017 (10.2010)

fs

1. FACILITY NAME LICENSEE EVENT REPORT (LEA)

Joseph M. Farley Nuclear Plant, Unit 2

4. TITLE

, the NRC may not conduct or sponsor, and a person is no equired to respond to, the information collection.

"- DOCKET NUMBER

3. PAGE 05000 364 Page 1 of3 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due to a Design Issue

5. EVENT DATE MONTH DAY YEAR 01 09 2015

6. LEA NUMBER YEAR I SEQUENTIAL I REV NUMBER NO.

2015-001-00

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR FACILITY NAME pOCKET NUMBER 03 09 2015 FACILITY NAME pOCKET NUMBER

9. OPERATING MODE

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

D 20.2201 (bl 0 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 1 D 20.2201 (d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

D 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(2)(i) 0 50.36(c)(1 )(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)

10. POWER LEVEL D 20.2203(a)(2)(ii) 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)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) 100%

0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 181 50. 73(a)(2)(v)(B) 0 73.71 (a)(5) 0 20.2203(a)(2)(v) 0 50. 73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER 0 20.2203(a)(2)(vi) 18150.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

Specify In Abstract below or in REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT

, 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 001 REV NO.

00 3.PAGE 3 of3 From November 18, 2011 through January 10, 2015 the TDAFW pump could not be relied on to start for some plant conditions in the accident analysis for a Main Steam Line Break (MSLB). Other accident analysis conditions were found to be unaffected. The TDAFW start is assumed to be affected when in mode 3 at lower steam generator pressures. Therefore, the Auxiliary Feed Water (AFW) system was not capable of performing its specified safety functions for MSLB and was inoperable for a period of time longer than allowed by Technical Specification (TS) 3.7.5. This is reportable as an operation or condition prohibited by TS per 10 CFR 50.73(a)(2)(i)(B).

During periods of time when a Motor Driven Auxiliary Feed Water (MDAFW) pump was taken out of service, with the TDAFW pump considered inoperable, the plant was inadvertently left with only a single AFW train in operation.

The TS Bases and the MSLB accident analysis require availability of at least two of three AFW pumps for the AFW system to perform its safety function. Therefore this condition is also reportable per 10 CFR 50.73(a)(2)(v)(B) as condition that could have prevented the fulfillment of a safety function of a system needed to remove residual heat.

A past operability review is being finalized and the LEA will be supplemented if information in this LEA is affected.

CORRECTIVE ACTION

A temporary modification was completed to adjust the timer to eliminate the vulnerability. This modification will be made permanent through the design change process. Design documents will be revised to add missing information regarding the basis for a timer setting which led to the design issue.

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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