ML15133A320: Difference between revisions

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{{Adams
#REDIRECT [[05000324/LER-2015-002]]
| number = ML15133A320
| issue date = 05/05/2015
| title = LER 15-002-00 for Brunswick, Unit 2, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable
| author name = Gideon W R
| author affiliation = Progress Energy Carolinas, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000324
| license number = DPR-062
| contact person =
| case reference number = BSEP 15-0035
| document report number = LER 15-002-00
| document type = Letter, Licensee Event Report (LER)
| page count = 3
}}
 
=Text=
{{#Wiki_filter:eDUKEENERGY,William R. GideonVice PresidentBrunsvick Nuclear PlantP.O. Box 10429Southport, NC 28461o: 910.457.369810 CFR 50.73MAY 0 5 2015Serial: BSEP 15-0035U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555
 
==Subject:==
Brunswick Steam Electric Plant, Unit No. 2Renewed Facility Operating License No. DPR-62Docket No. 50-324Licensee Event Report 2-2015-002In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Duke EnergyProgress, Inc., submits the enclosed Licensee Event Report (LER). This report fulfills therequirement of 10 CFR 50.73(a)(1) for a written report within sixty (60) days of a reportableoccurrence.Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -RegulatoryAffairs, at (910) 457-2487.Sincerely,q 6-Q, k~. \, ýýWilliam R. GideonSWR/swr
 
==Enclosure:==
Licensee Event Report 2-2015-002j122~-
cc (with enclosure):U. S. Nuclear Regulatory Commission, Region IIATTN: Mr. Victor M. McCree, Regional Administrator245 Peachtree Center Ave, NE, Suite 1200Atlanta, GA 30303-1257U. S. Nuclear Regulatory CommissionATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector8470 River RoadSouthport, NC 28461-8869U. S. Nuclear Regulatory CommissionATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only)11555 Rockville PikeRockville, MD 20852-2738Chair -North Carolina Utilities CommissionP.O. Box 29510Raleigh, NC 27626-0510 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017(02-2014)Estimated burden per response to comply with this mandatory collection request: 80 hours.Reported lessons learned are incorporated into the licensing process and ted back to industry.Send comments regarding burden estimate to the FOIA, Privacy and Information Collections... LICENSEE EVENT REPORT (LER) Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or byminteret e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and(See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC20503. If a means used to impose an information collection does not display a currently valid OMBdigits/characters for each block) 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 3. PAGEBrunswick Steam Electric Plant (BSEP) Unit 2 05000324 1 OF 14. TITLESetpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVEDI III FACILITY NAME DOCKET NUMBERMONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000NUMBER NO. 050FACILITY NAME DOCKET NUMBER03 10 2015 2015- 02 -00 05 05 2015 050009. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)El 20.2201(b) El 20.2203(a)(3)(i) El 50.73(a)(2)(i)(C) El 50.73(a)(2)(vii)N [] 20.2201(d) El 20.2203(a)(3)(ii) El 50.73(a)(2)(ii)(A) El 50.73(a)(2)(viii)(A)Defueled El 20.2203(a)(1) El 20.2203(a)(4) El 50.73(a)(2)(ii)(B) El 50.73(a)(2)(viii)(B)_ _ 20.2203(a)(2)(i) El 50.36(c)(1)(i)(A) El 50.73(a)(2)(iii) El 50.73(a)(2)(ix)(A)10. POWER LEVEL El 20.2203(a)(2)(ii) El 50.36(c)(1)(ii)(A) El 50.73(a)(2)(iv)(A) El 50.73(a)(2)(x)El 20.2203(a)(2)(iii) El 50.36(c)(2) El 50.73(a)(2)(v)(A) El 73.71 (a)(4)El 20.2203(a)(2)(iv) El 50.46(a)(3)(ii) El 50.73(a)(2)(v)(g) El 73.71(a)(5)0E 20.2203(a)(2)(v) El 50.73(a)(2)(i)(A) El 50.73(a)(2)(v)(C) El OTHEREl 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) El 50.73(a)(2)(v)(D) Specity in Abstract below or in____________________ ___________________ ____________________ NRC Form 366A12. LICENSEE CONTACT FOR THIS LERLICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)Lee Grzeck, Manager -Regulatory Affairs (910) 457-248713. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORTCAUSE SYSTEM COMPONENT MANU- REPORTABLE IX CAUSE SY C N FAREPORTABLEIIFACTUR`ER TO EPIX CASISSEM CMPNN FACTUER TO PIXX SB RV T020 No14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEARSUBMISSION c[]YES (If yes, complete 15. EXPECTED SUBMISSION DATE) []NO DATE 06 30 2015ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)During the Brunswick Steam Electric Plant (BSEP) Unit 2 refueling outage of Spring 2015, all eleven safetyrelief valves (SRVs) were removed for as-found lift setpoint pressure testing and recertification. Three of theeleven valves were found to have lift setpoints of their pilot valves outside the +/-3 percent tolerance requiredby Technical Specification (TS) 3.4.3. The SRV pilot valves were replaced with certified spares before thestartup of Unit 2. Investigation into the cause of the event is still underway. A supplement to this report will besubmitted to provide the results of the investigation and any corrective actions to address the causes. Thesafety significance of this event is minimal. Although the SRV setpoint limits required by the TS wereexceeded (i.e., 3.19 percent high, 3.57 percent high, and 3.98 percent low), the plant condition is bounded bythe Brunswick Unit 2 Cycle 21 Reload Safety Analysis, demonstrating that the SRVs could have performedtheir safety function of limiting reactor vessel overpressure. The plant's TS require ten of the eleven installedvalves to be operable. Since only eight were operable, this event is being reported in accordance with 10CFR 50.73(a)(2)(i)(B) for operation prohibited by the plant's TS.NRC FORM 366 (02-2014)}}

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