05000324/LER-2004-002, Regarding Reactor Shutdown Required by Technical Specifications Due to Containment Vacuum Breaker Not Closed
| ML042790475 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/27/2004 |
| From: | Hinds D Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 04-0106 LER 04-002-00 | |
| Download: ML042790475 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function |
| 3242004002R00 - NRC Website | |
text
Progress Energy SEP 2 7 2004 SERIAL: BSEP 04-0106 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATfN: 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 2-04-002 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. 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. Edward T. O'Neil, Manager-Support Services, at (910) 457-3512.
Sincerely, David H. Hinds Plant General Manager Brunswick Steam Electric Plant CRE/cre Enclosure: Licensee Event Report Progress Energy Carolinas. Inc.
Brunswick Nuclear Plant P.O.
Box 10429 Southport, NC 28461
-:fD2--
Document Control Desk BSEP 04-0106 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II AT'IN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 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 ATITN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051
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"..1 :
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 06/3012007 (6-2004)
, the NRC (See reverse for required number of may not conduct or sponsor, and a person Is not required to respond to the digits/characters for each block)
Information collection.
- 1. FACILITY NAME
- 2. DOCiKET NUMBER
- 3. PAGE Brunswick Steam Electric Plant (BSEP), Unit 2 05000324 1 OF 6
- 4. TITLE Reactor Shutdown Required by Technical Specifications Due to Containment Vacuum Breaker Not Closed
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR FACILITY NAME iDOCKET NUMBER NUMBER NO I
05000 J
JFACILITY NAME DOOCKET NUMBER 07 29 2004 2 4--
002 --
00 09 27 2004 FACIUTY 05000
- 9. OPERATING 1.THIS REPORT IS SUBMnrrED PURSUANTTO THE REQUIREMENTS OF10 CFR ¢: (Checkoneormore)
MODE 1
1202201(b) 202203(a)(3)(ih) 0.73(a)(2)(ii)(B)
- - 5.
3((a)(2)(
ii)(A)
- 10. POWER 202201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL 088 202203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 202203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 202203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 202203(a)(2)(iii) 50A6(a)(3)(ii)
X 50.73(a)(2)(v)(C)
_Specy In Abstract below 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)The condition that led to the vacuum breaker being stuck in the open position was most likely introduced during the spring 2003, refueling outage, when preventive maintenance was performed, which included disassembly of the pallet/hinge and replacement of the eccentric hinge bushings. Analyses postulating 2-CAC-X18D being initially closed and sticking open during either a large-break or small-break LOCA conclude that the safety function of primary containment would be maintained.
PREVIOUS SIMILAR EVENTS
A review of events occurring within the past three years has not identified any previous similar occurrences.
COMMITMENTS
Those actions committed to by Progress Energy Carolinas, Inc. (PEC) in this document are identified below.
Any other actions discussed in this submittal represent intended or planned actions by PEC. They are described for the NRC's information and are not regulatory commitments. Please notify the Manager -
Support Services at BSEP of any questions regarding this document or any associated regulatory
commitments
To prevent recurrence of this event, OPM-VBR500 is being revised to include provisions to:
- 1. Check for hinge/fit-up bushing binding whenever a disassembly inspection is performed.
- 2. Perform a more thorough post-test examination of the vacuum breakers and test actuators to detect and address erratic stroking, binding, and cylinder leaks.
- 3. Rebuild the test actuators at a set frequency.
- 4. Adjust "open" limit switches and caution personnel relative to possible interference problems if an adjustment is performed.
The revision to OPM-VBR500 will be effective by December 1, 2004.