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:eDUKE ENERGY, William R. Gideon Vice President Brunsvick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.457.3698 10 CFR 50.73 MAY 0 5 2015 Serial: BSEP 15-0035 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
 
==Subject:==
Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 Licensee Event Report 2-2015-002 In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Duke Energy Progress, Inc., submits the enclosed Licensee Event Report (LER). This report fulfills the requirement of 10 CFR 50.73(a)(1) for a written report within sixty (60) days of a reportable occurrence.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 457-2487.Sincerely, q 6-Q, k~. \, ýýWilliam R. Gideon SWR/swr
 
==Enclosure:==
 
Licensee Event Report 2-2015-002 j122~-
cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only)11555 Rockville Pike Rockville, MD 20852-2738 Chair -North Carolina Utilities Commission P.O. Box 29510 Raleigh, 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 by minteret 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, DC 20503. If a means used to impose an information collection does not display a currently valid OMB digits/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. PAGE Brunswick Steam Electric Plant (BSEP) Unit 2 05000324 1 OF 1 4. TITLE Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable
: 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED I III FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO. 050 FACILITY NAME DOCKET NUMBER 03 10 2015 2015- 02 -00 05 05 2015 05000 9. 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 OTHER El 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 366A 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)Lee Grzeck, Manager -Regulatory Affairs (910) 457-2487 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MANU- REPORTABLE IX CAUSE SY C N FAREPORTABLE IIFACTUR`ER TO EPIX CASISSEM CMPNN FACTUER TO PIX X SB RV T020 No 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSION c[]YES (If yes, complete 15. EXPECTED SUBMISSION DATE) []NO DATE 06 30 2015 ABSTRACT (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 safety relief valves (SRVs) were removed for as-found lift setpoint pressure testing and recertification.
Three of the eleven valves were found to have lift setpoints of their pilot valves outside the +/-3 percent tolerance required by Technical Specification (TS) 3.4.3. The SRV pilot valves were replaced with certified spares before the startup of Unit 2. Investigation into the cause of the event is still underway.
A supplement to this report will be submitted to provide the results of the investigation and any corrective actions to address the causes. The safety significance of this event is minimal. Although the SRV setpoint limits required by the TS were exceeded (i.e., 3.19 percent high, 3.57 percent high, and 3.98 percent low), the plant condition is bounded by the Brunswick Unit 2 Cycle 21 Reload Safety Analysis, demonstrating that the SRVs could have performed their safety function of limiting reactor vessel overpressure.
The plant's TS require ten of the eleven installed valves to be operable.
Since only eight were operable, this event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) for operation prohibited by the plant's TS.NRC FORM 366 (02-2014)}}

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