05000348/LER-2015-004, Re Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band
| ML15282A592 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/09/2015 |
| From: | Gayheart C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-15-1837 LER 15-004-00 | |
| Download: ML15282A592 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2) 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)(B), Prohibited by Technical Specifications |
| 3482015004R00 - NRC Website | |
text
Cheryl A. Gayheart Vice President - Farley October 9, 2015 Southern Nuclear Operating Company, Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford, Alabama 36312 Tel334.814.4511 Fax 334.814.4575 Docket Nos.: 50-348 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 SOUTHERN<<\\
COMPANY NL-15-1837 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2015-004-00 Pressurizer Safetv Valve Setpoint Pressure Outside of Technical Specification Tolerance Band Ladies and Gentlemen:
This Licensee Even*t Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50. 73(a)(2)(i)(B), for a condition prohibited by Technical Specifications.
This Jetter contains no NRC commitments. If you have any questions regarding the submittal, please contact Ms. Julie Collier at (334) 814-4639.
Sincerely, CAG/JAC Enclosure: Unit 1 Licensee Event Report 2015-004-00
U. S. Nuclear Regulatory Commission NL-15-1837 Page2 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, 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. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley
Enclosure Joseph M. Farley Nuclear Plant-Unit 1 Unit 1 Licensee Event Report 2015-004-00 NL-15-1837 Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150..0104 EXPIRES: 1/31/2017 (10.2010)
, lhe NRC may not conduct or sponsor, and a person Is no required to respond to, the lnfonnatian coflaetion.
- 1. FACILITY NAME
~* DOCKET NUMBER
- 3. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 348 Page 1 of 3
~*TITLE Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
08 11 2015 2015-004-00 10 09 2015 FACILITY NAME
~OCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201 (b) 0 20.2203(a)(3)(1) 0 50.73(a)(2)(1)(C) 0 50.73(a)(2)(vil) 1 0 20.2201 (d) 0 20.2203(a)(3)(11) 0 50.73(a)(2)(1l)(A) 0 50.73(8)(2)(vlii)(A) 0 20.2203(8)(1) 0 20.2203(8}(4) 0 50.73(8)(2)(11)(8) 0 50.73(8)(2)(viii)(B) 0 20.2203(a)(2)(1) 0 50.36(c)(1 )(I)(A) 0 50.73(8)(2)(11i) 0 50.73(a)(2)(1x)(A)
- 10. POWER LEVEL 0 20.2203(a}(2)(11) 0 50.36(c)(1 )(II)(A) 0 50.73(8)(2)(1v)(A) 0 50.73(8)(2)(x) 0 20.2203(8)(2)(111) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) 100%
0 20.2203(a)(2)(1v) 0 50.46(a)(3)(11) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 0 20.2203(8)(2)(v) 0 50.73(8)(2)(1)(A) 0 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(8)(2)(vi) 181 50. 73(8)(2)(1)(8) 0 50.73(a)(2)(v)(D)
Specify In Abstract below or In
CORRECTIVE ACTION
The 1 B pressurizer safety valve was replaced during the May 2015 planned maintenance outage.
ADDITIONAL INFORMATION
Other system affected:
Commitment Information:
Previous Similar Events
No systems other than those mentioned in this report were affected by this event.
This report does not create any licensing commitments.
A search did not reveal any similarly reported events for Plant Farley.
Cheryl A. Gayheart Vice President - Farley October 9, 2015 Southern Nuclear Operating Company, Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford, Alabama 36312 Tel334.814.4511 Fax 334.814.4575 Docket Nos.: 50-348 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 SOUTHERN<<\\
COMPANY NL-15-1837 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2015-004-00 Pressurizer Safetv Valve Setpoint Pressure Outside of Technical Specification Tolerance Band Ladies and Gentlemen:
This Licensee Even*t Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50. 73(a)(2)(i)(B), for a condition prohibited by Technical Specifications.
This Jetter contains no NRC commitments. If you have any questions regarding the submittal, please contact Ms. Julie Collier at (334) 814-4639.
Sincerely, CAG/JAC Enclosure: Unit 1 Licensee Event Report 2015-004-00
U. S. Nuclear Regulatory Commission NL-15-1837 Page2 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, 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. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley
Enclosure Joseph M. Farley Nuclear Plant-Unit 1 Unit 1 Licensee Event Report 2015-004-00 NL-15-1837 Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150..0104 EXPIRES: 1/31/2017 (10.2010)
, lhe NRC may not conduct or sponsor, and a person Is no required to respond to, the lnfonnatian coflaetion.
- 1. FACILITY NAME
~* DOCKET NUMBER
- 3. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 348 Page 1 of 3
~*TITLE Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
08 11 2015 2015-004-00 10 09 2015 FACILITY NAME
~OCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201 (b) 0 20.2203(a)(3)(1) 0 50.73(a)(2)(1)(C) 0 50.73(a)(2)(vil) 1 0 20.2201 (d) 0 20.2203(a)(3)(11) 0 50.73(a)(2)(1l)(A) 0 50.73(8)(2)(vlii)(A) 0 20.2203(8)(1) 0 20.2203(8}(4) 0 50.73(8)(2)(11)(8) 0 50.73(8)(2)(viii)(B) 0 20.2203(a)(2)(1) 0 50.36(c)(1 )(I)(A) 0 50.73(8)(2)(11i) 0 50.73(a)(2)(1x)(A)
- 10. POWER LEVEL 0 20.2203(a}(2)(11) 0 50.36(c)(1 )(II)(A) 0 50.73(8)(2)(1v)(A) 0 50.73(8)(2)(x) 0 20.2203(8)(2)(111) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) 100%
0 20.2203(a)(2)(1v) 0 50.46(a)(3)(11) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 0 20.2203(8)(2)(v) 0 50.73(8)(2)(1)(A) 0 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(8)(2)(vi) 181 50. 73(8)(2)(1)(8) 0 50.73(a)(2)(v)(D)
Specify In Abstract below or In
PLANT AND SYSTEM IDENTIFICATION
Westinghouse-Pressurized Water Reactor
, the NRC mey nol conduct or sponsor, and a person Is not required to respond to, the lnfonnaUon collection.
YEAR 2015
- 6. LER NUMBER I
SEQUENTIAL I NllMBER 004 REV NO.
00 3.PAGE 2 of3 Energy Industry Identification System codes appear in the text as (EllS Code XX).
DESCRIPTION OF EVENT
On 8/11/15 during testing at an offsite facility the as-found lift setting for the Unit 1 1 B pressurizer safety valve (PSV) (EllS Code RV) was discovered to be 2425 psig which is outside of the Technical Specification (TS) allowable lift settings of ;:: 2460 psig and s 2510 psi g. On 5/4/15 during startup from 1 R26 with the plant in Mode 3, it was determined that the 1 B PSV was leaking into the pressurizer relief tank (PRT) based on elevated tailpipe temperatures. On 5/8/15 the tailpipe temperature leakage indication stabilized with average PRT in-leakage at 0.12 gpm. Compensatory actions were established which included increased monitoring of leak rate, PRT parameters, radiation levels, PRT venting, and decision points for re-evaluating the need to replace the valve. Based upon the continued leakage Unit 1 entered a planned maintenance outage on 5/26/15 to replace the 1 B PSV. The valve was then shipped to an offsite facility for lift testing and valve disassembly and inspection.
CAUSE OF EVENT
Visual inspections determined that the cause was seat leakage of the valve. The seat leakage resulted in 355 degree wire draw on the valve disc which reduced the setpoint to outside the TS band.
REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT This failure constitutes a condition that is reportable pursuant to 10CFR50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications." Based upon a review of relevant information (e.g., equipment history and the cause of failure), there is no firm evidence for when the failure to meet the lift setting requirements occurred prior to the time of discovery at the test facility.
The setpoint would have drifted below the allowable value at some time between startup from 1 R26 and the time of discovery.
Since the as-found lift setpoint was lower than the allowed value in the Technical Specifications, the condition did not have an adverse impact on over pressurization, and the valve continued to perform its overpressure protection function. The as-found lift pressure was 2425 psig and the valve reclosed following the lift. This is within the safety analysis assumptions that are credited for pressurizer safety valves, and the plant remained bounded by the accident analyses in the FSAR. Therefore, this condition had no significant effect on the health and safety of the public.
rmc FORM 3fifiA 02-2014)
U.S. NUCLEAR REGULA TORY COMMISSION APPROVED BY OMD: NO. 3150-0104 EXPIRES: 01/3112017 i '...,
,:*~
- \\'; -
\\.:-;_?./ LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET Esdmated burden per response to comply with this mandatory collacdon request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons teamed are lncorporaliKIInlo tha Hcenslng process and fed back to Industry.
Send commenls ragerting burden estimate to the FOIA, Privacy and lnfoonalion Collections Branch (H F53), U.S. Nuclear Regulatory Conunlsslon, Washington, DC 20555-0001, or by lntemet!HIIalf lo lnfocollacts.Resource@nrc.gov, and lo the Desk Officer, Of6ce of Information and Regulatory Affairs, NEQ8.10202, (315<Hl104), Office of Management and Budget, Washington, OC 20503. If a maens used to Impose an Information colection does not dsplay a curranlly valid OMB control nt.mller, the NRC may not conducl or sponsor, and a person Is not required Ia respond lo, the infoonaUon collection.
- 1. FACILITY NAME 2.DOCKET YEAR
- 6. LER NUMBER REV NO.
3.PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 348 I
SEQUENTIAL I NUMBER 3 of3 2015 004 00 NARRATIVE
CORRECTIVE ACTION
The 1 B pressurizer safety valve was replaced during the May 2015 planned maintenance outage.
ADDITIONAL INFORMATION
Other system affected:
Commitment Information:
Previous Similar Events
No systems other than those mentioned in this report were affected by this event.
This report does not create any licensing commitments.
A search did not reveal any similarly reported events for Plant Farley.