05000324/LER-2012-007, (Bsep), Unit 1, Loss of Control Room Emergency Ventilation

(Bsep), Unit 1, Loss of Control Room Emergency Ventilation

ML13052A268
Person / Time
Site:	Brunswick
Issue date:	02/12/2013
From:	Krakuszeski J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 13-0017 LER 12-007-00
Download: ML13052A268 (3)

LER-2012-007, (Bsep), Unit 1, Loss of Control Room Emergency Ventilation

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
3242012007R00 - NRC Website

text

~DukeEnergy 10 CFR 50.73 FEB 12 2013 Serial: BSEP 13-0017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325, 50-324 Licensee Event Report 1-2012-007 In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power &

Light Company submits the enclosed Licensee Event Report (LER). This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence.

The evaluation of the cause and corrective actions for this event is in progress. As such, this LER will be supplemented by April 12, 2013.

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.

Sincerely, John A. Krakuszeski Plant Manager Brunswick Steam Electric Plant MAT/mat

Enclosure:

Licensee Event Report ei-

U.S. Nuclear Regulatory Commission Page 2 of 2 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. Christopher Gratton (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 APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Brunswick Steam Electric Plant (BSEP), Unit 1 05000325 1 of 1

4. TITLE Loss of Control Room Emergency Ventilation

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER NUMBER NO.

MONTH DAY YEAR BSEP, Unit 2 05000324 FACILITY NAME DOCKET NUMBER 12 14 2012 2012-007-00 02 12 2013

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)

[1 50.73(a)(2)(vii) 1 El 20.2201(d)

Ej 20.2203(a)(3)(ii)

[] 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

[] 20.2203(a)(4)

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

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

[: 20.2203(a)(2)(i)

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

El 50.73(a)(2)(iii)

E] 50.73(a)(2)(ix)(A)

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

LI 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

LI 20.2203(a)(2)(iii)

LI 50.36(c)(2)

[L 50.73(a)(2)(v)(A)

El 73.71 (a)(4) 100 EL 20.2203(a)(2)(iv)

EL 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20.2203(a)(2)(v)

LI 50.73(a)(2)(i)(A)

[] 50.73(a)(2)(v)(C)

El OTHER IZ 20.2203(a)(2)(vi)

LI 50.73(a)(2)(i)(B)

Z 50.73(a)(2)(v)(D)

Specify in Abstract below or in NRC Form 366A

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)

Mark Turkal, Lead Engineer - Licensing (910) 457-3066MANU-REPORTABLE MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT

CAUSE

SYSTEM COMPONENT FACURER EPOA FACTURER TO EPIX FACTURER TO EPIX

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR SUBMISSION YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

[I NO DATE 04 12 2013 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On December 14, 2012, at approximately 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br /> Eastern Standard Time (EST), inoperability of both subsystems of the Control Room Emergency Ventilation (CREV) system occurred. Because Brunswick has a shared control room, this placed Unit 1 and Unit 2 in Technical Specification (TS) 3.7.3, Required Action C.1, for two CREV subsystems inoperable (i.e., be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).

At the time of the event, a modification to upgrade the Control Building fire detection system was in progress. The 2A CREV subsystem was placed in the radiation/smoke protection mode in compliance with the Technical Requirements Manual. This action prevented an auto-start of the 2B CREV subsystem and, as such, TS 3.7.3 Condition A was entered to restore 2B CREV subsystem to operable status within 7 days. During work to electrically isolate one of the fire detectors associated with 2A CREV subsystem, electrical continuity was lost sending an internal charcoal fire signal to the 2A CREV subsystem circuitry and shutting it down. With 2A CREV subsystem shut down due to the signal, TS 3.7.3, Required Action C. 1, applied for both CREV subsystems inoperable. Actions were taken to re-start 2A CREV subsystem, and TS 3.7.3, Required Action C.1, was exited within approximately two minutes. The safety consequences of this event were minimal.

The evaluation of the cause and corrective actions for this event is in progress. As such, this LER will be supplemented by April 12, 2013.

NRC FORM 366 (10-2010)