05000324/LER-2007-002, Regarding Mode Change Made with Reactor Core Isolation Cooling System Inoperable
| ML071770130 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/18/2007 |
| From: | Hobbs T Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 07-0059 LER 07-002-00 | |
| Download: ML071770130 (7) | |
| 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 |
| 3242007002R00 - NRC Website | |
text
Progress EnergY June 18, 2007 SERIAL: BSEP 07-0059 10 CFR 50.73 U. S. Nuclear Regulatory Commission AT1TN: 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 2-2007-002 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.
Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager - Support Services, at (910) 457-2447.
Sincerely, Terry D '. Hobbs 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 07-0059 / 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, GAý 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 (Electronic Copy Only)
ATTN: Mr. Stewart N. Bailey (Mail Stop OWEN 8B 1) 11555 Rockville Pike Rockville, MID 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 1
NRIC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 0613012007 (6-2004)
Estimaeted
, the NRC rmay not conduct or sponsor, and a person is not required to respond to the infonrretion collection.
- 13.
PAGE Brunswick Steam Electric Plant (BSEP), Unit 2 05000324 j1 of 5
- 4. TITLE Mode Change Made with Reactor Core Isolation Cooling System Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITES INVOLVED MONTH DAY YEAR YEAR ISEQUENTIAL IREV MONTH DAY YERFACILITY NAME DOCKET NUMBER NUMBER NO YA 04 17 2007 2007 002 00 06 1181 2007 FACILITY NAMEDOKTNME
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 2 El20.2201 (b)
El20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
El50.73(a)(2)(vii)
El20.2201 (d)
El20.2203(a)(3)(ii)
Cl 50.73(a)(2)(ii)(A)
El50.73(a)(2)(viii)(A)
El20.2203(a)(1)
F-l 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
El50.73(a)(2)(viii)(B)
El20.2203(a)(2)(i) 0l 50.36(c)(1 )(i)(A)
[I 50.73(a)(2)(iii)
El50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0l 20.2203(a)(2)(ii)
El50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
(XIo 20.2203(a)(2)(iii)
El50.36(c)(2)
El50.73(a)(2)(v)(A)
El73.71 (a) (4)
El20.2203(a)(2)(iv)
El50.46(a)(3)(ii)
El50.73(a)(2)(v)(B)
El73.71 (a) (5)
El20.2203(a)(2)(v)
El50.73(a)(2)(i)(A)
El50.73(a)(2)(v)(C)
E] OTHER rMnAbstract below l20.2203(a)(2)(vi) 050.73(a)(2)(i)(B)
El50.73(a)(2)(v)(D) 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 NRC Form 366A) (17)The following corrective action to prevent recurrence has been established as a result of this event.
0 Time delay relays will be added to the Unit 1 and Unit 2 E51-PSL-N006 low suction pressure switches to prevent spurious trips due to momentary pressure oscillations. The engineering change to install the time delay relays is currently scheduled to be completed by September 21, 2007.
Installation of the modification will be completed during appropriate system or Unit outages.
Although not intended to prevent recurrence, the following corrective action is planned.
- An engineering change to install a high point vent or correct the Unit 2 RCIC injection piping slope inaccuracy will be developed. The engineering change is currently scheduled to be completed by September 21, 2007. Installation of the modification will be completed during appropriate system or Unit outages.
Previous Similar Events
A review of LERs and corrective action program condition reports for the past three years identified no
similar events
Commitments
No regulatory commitments are contained in this report.
NRC FORM 366 (6-2004)