11-11-2010 | On September 12, 2010, at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> Eastern Daylight Time (EDT), a routine monthly surveillance, OPT-12.2D, "No. 4 Diesel Generator Monthly Load Test," was started on Emergency Diesel Generator No. 4 (EDG4). During the performance of the surveillance test, sparking was observed coming from the diesel generator inner ring brushes. The maximum sparking began approximately 45 minutes after EDG4 started, and remained for the duration of the diesel run. Following performance of the surveillance test, collector ring brush measurements identified abnormal wear on the inner ring brushes. Engineering determined that, due to the brush wear and excessive sparking, EDG4 would not have been able to run for its mission time. At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on September 13, 2010, EDG4 was declared inoperable. This condition is being reported as an operation prohibited by Technical Specifications (TS), due to EDG4 inoperable greater than the TS completion time.
The safety consequences of this event were minimal. The three remaining Emergency Diesel Generators were operable and available to provide emergency AC power if needed. The root cause was determined to be untimely implementation of corrective actions to a long-standing concern. The corrective actions include replacing the collector rings with an upgraded design that is not subject to corrosion. |
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LER-2010-004, November 11, 2010
SERIAL: BSEP 10-0127
10 CFR 50.73
U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, DC 20555-0001
Subject: Brunswick Steam Electric Plant, Unit Nos. 1 and 2
Renewed Facility Operating License Nos. DPR-71 and DPR-62
Docket Nos. 50-325 and 50-324
Licensee Event Report 1-2010-004
Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power
& Light Company, now doing business as Progress Energy Carolinas, Inc., submits the
enclosed Licensee Event Report (LER). This report fulfills the requirement for a written
report within sixty (60) days of a reportable occurrence.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Acting Supervisor
Licensing/Regulatory Programs, at (910) 457-2487.
Sincerely,
Edward L. Wills, Jr.
Plant General Manager
Brunswick Steam Electric Plant
LJG/lj g
Enclosure:
Licensee Event Report
Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant
PO Box 10429
Southport, NC 28461
Document Control Desk
BSEP 10-0127 / Page 2
cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II
ATTN: Mr. Luis A. Reyes, Regional Administrator
245 Peachtree Center Ave. N.E., Suite 1200
Atlanta, GA 30303-1257
U. S. Nuclear Regulatory Commission
ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector
8470 River Road
Southport, NC 28461-8869
U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)
11555 Rockville Pike
Rockville, MD 20852-2738
Chair - North Carolina Utilities Commission
P.O. Box 29510
Raleigh, NC 27626-0510
NRC FORM 366UU.S. NUCLEAR REGULATORY COMMISSION
(10-2010)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of
digits/characters for each block)
1. FACILITY NAME
Brunswick Steam Electric Plant (BSEP), Unit 1
4. TITLE
APPROVED BY OMB: NO. 3150-0104EEXPIRES: 10/31/2013
Estimated burden per response to comply with this mandatory
collection request: 80 hours. Reported lessons learned are
incorporated into the licensing process and fed back to industry. Send
comments regarding burden estimate to the FOIA/Privacy Section (T-5
F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555
0001, or by internet e-mail to infocollectssesource@nrc.gov, and to
the Desk Officer, Office of Information and 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 control number, the NRC may not
conduct or sponsor, and a person is not required to respond to, the
information collection.
2. DOCKET NUMBER 3. PAGE
05000325 1 of 5
Emergency Diesel Generator Inoperable for Greater than Technical Specification Completion TimeBrunswick Steam Electric Plant (Bsep), Unit 1 |
Event date: |
09-13-2010 |
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Report date: |
11-11-2010 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3252010004R00 - NRC Website |
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Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
Introduction Initial Conditions At the time of the event, Unit 1 and Unit 2 were in Mode 1, at approximately 100 percent of rated thermal power (RTP).
Reportability Criteria This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), as an operation or condition prohibited by Technical Specifications (TSs).
Event Description
On September 12, 2010, at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> Eastern Daylight Time (EDT), a routine monthly surveillance, OPT-12.2D, "No. 4 Diesel Generator Monthly Load Test," was started on Emergency Diesel Generator No. 4 (EDG4) [EK]. During the performance of the surveillance test, sparking was observed coming from the diesel generator inner ring brushes. The maximum sparking began approximately 45 minutes after EDG4 started, and remained for the duration of the diesel run. Following performance of the surveillance test, collector ring brush measurements identified abnormal wear on the inner ring brushes.
The generator field collector ring brush wear on two of the four inner ring brushes was significant, in comparison to historical brush wear rates.
Sparking has been observed historically on the Brunswick Emergency Diesel Generators (EDGs) and is an understood phenomenon associated with corrosion build-up on the surface of the carbon steel collector rings. Corrective actions had been established to resolve this issue, scheduled in 2011, via a project to upgrade the collector rings to a non-ferrous material and to improve the rigidity of the brush rigging design.
In the interim, a quarterly Preventive Maintenance (PM) task had proven effective, since 2005, at significantly reducing sparking events in an effort to prevent excessive dust formation from causing low insulation resistance for this equipment. The PM scope includes cleaning of the rings and brush rigging, and resetting or replacing the brushes to ensure correct brush spring pressure and adequate brush length remain. In previous diesel runs when sparking was observed, the sparking has self-corrected in full, or was diminished to the point that self-correction could be assured. It has been observed in the past that once sparking arrests, the brush wear rate also reduces to an acceptable value. Since sparking was not observed to subside for this event, it is assumed that the wear rate would continue to the point of EDG failure.
Based on the observed wear rate, and assuming there would be no reduction in that wear rate, Engineering determined that EDG4 would not have been able run for its mission time. The observed brush wear rate would most probably have resulted in a flash-over event (i.e., either ring to ground, or ring to ring) due to the sparking increasing as the spring pressures continued to reduce on the two overloaded brushes. This is Event Description (continued) expected to have occurred in less than the Probabilistic Safety Assessment (PSA) defined twenty four hour mission time. Based on this assessment, Operations declared EDG4 inoperable at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on September 13, 2010.
Brunswick TSs Limiting Condition of Operation (LCO) 3.8.1 Required Action D.4 Completion Time requires an inoperable diesel to be restored to operable status within seven days. With EDG4 declared inoperable, and the last successful performance of 0PT-12.2D completed more than seven days prior to September 13, 2010 (i.e., on August 15, 2010), this condition is being reported as an operation prohibited by TSs, due to EDG4 being inoperable greater than the TS completion time.
On September 14, 2010, at 0128 hours0.00148 days <br />0.0356 hours <br />2.116402e-4 weeks <br />4.8704e-5 months <br />, after replacement of all four inner ring brushes and successful re performance of OPT-12.2D, EDG4 was declared operable.
Event Cause The primary cause of the event was that there was untimely implementation of corrective actions to a long standing concern identified for the EDG collector rings. A contributing cause was that there was no process in place for determining the effectiveness of long-term interim actions. The quarterly PM associated with the collector rings became ineffective after a long period of time, prior to the long-term actions being implemented.
Safety Assessment The safety significance of this event is considered minimal. The three remaining EDGs were operable and available to provide emergency AC power if needed. In addition, EDG4 did not fail to start or run, and successfully ran for the duration of the surveillance test.
Corrective Actions
The following corrective actions to prevent recurrence will be taken.
- Replace collector rings with upgraded design that is not subject to corrosion (i.e., as previously tracked per Nuclear Condition report (NCR) 246046, Engineering Change (EC) 74453, and Project No. 894048). This action is scheduled to be complete by December 31, 2011.
- Establish a diesel major projects design and implementation team. This action is complete.
- Establish a Plant Health Process which adequately prioritizes and schedules equipment improvement items for the site. This action is complete.
Corrective Actions (continued) The following additional corrective actions will be taken.
- A process will be established that periodically determines the effectiveness of ongoing or long-term interim actions. This action is scheduled to be complete by December 14, 2010.
- The PM frequency for the EDG collector ring cleaning on all four EDGs will be revised to bi- monthly during the months of July to November (i.e., the time when EDG collector rings are most susceptible to dust accumulation) until the upgrade project is implemented. This action is scheduled to be complete by February 10, 2011.
- The collector ring PM procedures, OPM-GEN005 and OPM-GEN005A, will be revised to allow cleaning of the normal brush path on the ring surface if abnormal corrosion is noted. This action is scheduled to be complete by March 10, 2011.
- Re-surface the EDG4 collector ring, or perform an equivalent interim measure, to preclude the potential for a repeat failure event until the ring material can be replaced with the upgraded design.
This action is scheduled to be complete by March 1, 2011.
Previous Similar Events
A review of LERs and corrective action program condition reports for the past three years identified the following similar previous occurrences.
NCR 245313, dated September 4, 2007, DG#2 Generator Arcing and Sparking.
NCR 245783, dated September 7, 2007, DG3 - As-found Megger Readings on Collector Rings (Outside Desired Values).
NCR 245808, dated September 7, 2007, DG3 Collector Ring Sparking/Arcing During PT-12.2C Run.
NCR 246046, dated September 10, 2007, EDG Collector Rings - Adverse Trend.
NCR 247907, dated September 25, 2007, EDG#2 Sparking and Arcing on Inner Collector Ring Brushes.
NCR 253183, dated November 2, 2007, DG4 Brush Sparking During OPT-12.2D.
NCR 254280, dated November 12, 2007, DG3 Brush Inspection Meg Readings (Outside Desired Values).
NCR 355003, dated September 14, 2009, DG#4 Outer Collector Ring Brush Arcing.
NCR 409543, dated July 11, 2010, DG#3 Inner Collector Ring Brushes (Arcing and Brush Wear).
NCR 419863, dated September 2, 2010, DG 2 Auto Voltage Regulator Not Working Properly (Heavy Sparking from Collector Ring Brushes).
Although there have been a number of similar events in the past, as noted above, none of these events caused inoperability of the EDGs. An interim correction action was in place to inspect and clean the collector ring and brushes (i.e., a quarterly PM task). A longer-term corrective action had also been established to replace the collector ring. Thus, the previous occurrences could not have reasonably been expected to prevent the condition reported in this LER.
Commitments No regulatory commitments are contained in this report.
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05000325/LER-2010-001 | APR 2 7 2010 SERIAL: BSEP 10-0047 10 CFR 50.73 U. S: Nuclear Regulatory Commission ATTN: Document Control Desk Washington; DC 20555-0001 Subject: Brunswick Steam Electric Plant, Unit No 1 Renewed Facility Operating License No. DPR-71 Docket No. 50-325 Licensee Event Report 1-2010-001 Ladies and Gentlemen: In accordance with the Code of Federal RegulatiOns, Title 10, Part 50.73, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc:, submits the enclosed Licensee Event Report (LER). This report fulfills'the requirernent for a written report within sixty (60) days of a reportable occurrence. Please refer any questions regarding this submittal to Ms. Annette Pope,-Supervisor - Licensing/Regulatory Programs, at (910) 457-2184. Sincerely, Edward L. Wills, Jr. Plant General Manager Brunswick Steam Electric Plant LJG/lj g Enclosure: Licensee Event Report Progress Energy Carolinas, Inc. Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 Document Control Desk BSEP 10-0047 / Page 2 cc (with enclosure): U. S. Nuclear Regulatory Commission, Region II
ATTN: Mr. Luis A. Reyes, Regional Administrator
Marquis One Tower
245 Peachtree Center Ave. N.E., Suite 1200
Atlanta, GA 30303-1257
U. S. Nuclear Regulatory Commission
ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector
8470 River Road
Southport, NC 28461-8869
U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)
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 (9-2007) LICENSEE EVENT REPORT (LER) (See reverse for required number Of digits/characters for each block) 1. FACILITY NAME Brunswick Steam Electric Plant (BSEP), Unit 1 4. TITLE APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and 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 control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. 2. DOCKET NUMBER 3. PAGE 05000325 1 of 4 Reactor Core Isolation Cooling (RCIC) Manually Started to Maintain RPV Level Following Pre-planned Scram. | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000325/LER-2010-002 | JUN 2 3 2010 SERIAL: BSEP 10-0076 10 CFR 50.73 U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, DC 20555-0001
Subject: Brunswick Steam Electric Plant, Unit No. 1
Renewed Facility Operating License No. DPR-71
Docket No. 50-325
Licensee Event Report 1-2010-002
Ladies and Gentlemen: In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed Licensee Event Report (LER). This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence. Please refer any questions regarding this submittal to Ms. Annette Pope, Supervisor Licensing/Regulatory Programs, at (910) 457-2184. Sincerely, 14,,o4ti 0_ Edward L. Wills, Jr. Plant General Manager Brunswick Steam Electric Plant MAT/mat Enclosure:
Licensee Event Report
Progress Energy Carolinas, Inc. Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 Document Control Desk BSEP 10-0076 / Page 2 cc (with enclosure): U. S. Nuclear Regulatory Commission, Region II
ATTN: Mr. Luis A. Reyes, Regional Administrator
245 Peachtree Center Avenue, NE, Suite 1200
Atlanta, GA 30303-1257
U. S. Nuclear Regulatory Commission
ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector
8470 River Road
Southport, NC 28461-8869
U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)
11555 Rockville Pike
Rockville, MD 20852-2738
Chair - North Carolina Utilities Commission
P.O. Box 29510
Raleigh, NC 27626-0510
NRC FORM 366U U.S. NUCLEAR REGULATORY COMMISSION (9-2007) LICENSEE EVENT REPORT (LER) (See reverse for required number of digits/characters for each block) 1. FACILITY NAME Brunswick Steam Electric Plant (BSEP), Unit 1 4. TITLE APPROVED BY OMB: NO. 3150-0104E EXPIRES: 08/31/2010 Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and 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 control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. 2. DOCKET NUMBER 3. PAGE 05000325 1 of 5 Operation Prohibited by Technical Specifications - Reactor Protection System (RPS) Instrumentation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000325/LER-2010-004 | November 11, 2010 SERIAL: BSEP 10-0127 10 CFR 50.73 U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, DC 20555-0001
Subject: Brunswick Steam Electric Plant, Unit Nos. 1 and 2
Renewed Facility Operating License Nos. DPR-71 and DPR-62
Docket Nos. 50-325 and 50-324
Licensee Event Report 1-2010-004
Ladies and Gentlemen: In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed Licensee Event Report (LER). This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Acting Supervisor Licensing/Regulatory Programs, at (910) 457-2487. Sincerely, Edward L. Wills, Jr. Plant General Manager Brunswick Steam Electric Plant LJG/lj g Enclosure:
Licensee Event Report
Progress Energy Carolinas, Inc. Brunswick Nuclear Plant
PO Box 10429
Southport, NC 28461
Document Control Desk BSEP 10-0127 / Page 2 cc (with enclosure): U. S. Nuclear Regulatory Commission, Region II
ATTN: Mr. Luis A. Reyes, Regional Administrator
245 Peachtree Center Ave. N.E., Suite 1200
Atlanta, GA 30303-1257
U. S. Nuclear Regulatory Commission
ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector
8470 River Road
Southport, NC 28461-8869
U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)
11555 Rockville Pike
Rockville, MD 20852-2738
Chair - North Carolina Utilities Commission P.O. Box 29510
Raleigh, NC 27626-0510
NRC FORM 366UU.S. NUCLEAR REGULATORY COMMISSION (10-2010) LICENSEE EVENT REPORT (LER) (See reverse for required number of digits/characters for each block) 1. FACILITY NAME Brunswick Steam Electric Plant (BSEP), Unit 1 4. TITLE APPROVED BY OMB: NO. 3150-0104EEXPIRES: 10/31/2013 Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, or by internet e-mail to infocollectssesource@nrc.gov, and to the Desk Officer, Office of Information and 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 control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. 2. DOCKET NUMBER 3. PAGE 05000325 1 of 5 Emergency Diesel Generator Inoperable for Greater than Technical Specification Completion Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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