05000324/LER-2006-001, From Brunswick, Unit 2 Regarding Loss of Startup Auxiliary Transformer Results in Unit 2 Manual Reactor Protection System Actuation

From Brunswick, Unit 2 Regarding Loss of Startup Auxiliary Transformer Results in Unit 2 Manual Reactor Protection System Actuation

ML070090433
Person / Time
Site:	Brunswick
Issue date:	12/29/2006
From:	Waldrep B Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 06-0133 LER 06-001-00
Download: ML070090433 (8)

LER-2006-001, From Brunswick, Unit 2 Regarding Loss of Startup Auxiliary Transformer Results in Unit 2 Manual Reactor Protection System Actuation

Event date:
Report date:
Reporting criterion:	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)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3242006001R00 - NRC Website

text

2rProgress Energy DEC 2 92006 SERIAL: BSEP 06-0 133 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Licensee Event Report 2-2006-00 1 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.

Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager - Support Services, at (910) 457-2447.

Sincerely, B. C'. Vldrep Plant Oneral Manager Brunswick Steam Electric Plant MAT/mat

Enclosure:

Licensee Event Report Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant P.O.

Box 10429 Southport, NC 28461

_C2-7Z

Document Control Desk BSEPO06-0133 /Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region 11 ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-893 1 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MID 20852-273 8 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051

NRIC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 EXPIRES 06/30/2007 (6-2004)

Estimrated bujrden per response to comrply with this rmandatory information collection request:

50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into thre licensing process and fed back to LICENSEE EVENT REPORT (LER) industry. Send comrmrents regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Comi~cssion, Washington, DC 20555-0001, or by (See reverse for required number of internet e-mnail to infocodlects@nrc.oov, and to the Desk Officer, Office of tnformration end dgt/hrcesfor each block)

Regulatory Afaairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, digis/caracersDC 20503. It a mneans used to rmpose an information collection does not cisplay a currently valid 0MB control nunber, the NRC masy not conduct or sponsor, end a person is not required to re~spond to the information collection.

[3.

PAGE Brunswick Steam Electric Plant (BSEP), Unit 2 05000324 1 of 6

4. TITLE Loss of Startup Auxiliary Transformner Results in Unit 2 Manual Reactor Protection System Actuation

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEARI SEQUENTIAL IREV MONTHIT DAYE YEARTNUBE NUMBER NO MOTIA YE ACIR YNM OKTNME 1 1 01 2006 2006 001 00 j12 29 2006 FACILITY NAME DOCKET NUMBER

____________________________________05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one ormoe 1

1 20.2201 (b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii)

El 20.2201 (d)

[Ei 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

[I 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

[I 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

[I 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x) 100 El 20.2203(a)(2)(iii)

[I 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4)

El 20.2203(a)(2)(iv)

[E1 50.46(a)(3)(ii)

El_ 50.73(a)(2)(v)(B)

El 73.71 (a) (5)

El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

ElOTHER Specify in Abstract below El 20.2203(a)(2)(vi)

El 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D) or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)* Unit 1 and Unit 2 non-segregated bus flexible link connections will be determinated, cleaned, and inspected. A portion of the Unit 2 non-segregated bus flexible link connections will be completed during the B218RI outage (i.e., currently scheduled to begin in March 2007), if necessary, the remaining Unit 2 flexible link connections will be completed during the B219RI refueling outage for Unit 2 (i.e., currently scheduled to begin in February 2009). The Unit 1 flexible link connections will be completed during the Bi1 17R 1 refueling outage (i.e., currently scheduled to begin in March 2008).

" Infrared (IR) windows, allowing for at-power thermography, will be installed at non-segregated bus flexible link connections on Unit 1 during the B 1 17R 1 refueling outage (i.e., currently scheduled to begin in March 2008) and on Unit 2 during the B3218R1. refueling outage (i.e., currently scheduled to begin in March 2007).

Previous Similar Events

A review of LERs and corrective action program condition reports for the past three years identified the following similar events.

• LER 1-2005-005, dated September 12, 2005, documents a Unit 1 Main Turbine trip followed by an automatic RPS actuation. The cause of the Main Turbine trip was the failure of the B phase of the Main Generator No Load Disconnect Switch (NLDS). The root cause of the event reported in LER 1-2005-005 was inadequate design and testing of the NLDS by the vendor; resulting in the NLDS not meeting its nameplate design rating. The corrective actions associated with LER 1-2005-005 could not have reasonably been expected to prevent the condition reported in this LER.

Commitments

No regulatory commitments are contained in this report.