05000324/LER-2007-001, For Brunswick, Unit 2, Regarding Operation Prohibited by Technical Specification 3.3.1.2, Source Range Monitor Instrumentation
| ML071510084 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/22/2007 |
| From: | Hobbs T Progress Energy Carolinas, Progress Energy Co |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| BSEP 07-0041 LER 07-001-00 | |
| Download: ML071510084 (6) | |
| 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 |
| 3242007001R00 - NRC Website | |
text
Progress Energy MAY 2 2 2007 SERIAL: BSEP 07-0041 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 2-2007-001 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.
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 07-0041 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: 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 (Electronic Copy Only)
ATTN: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007 (6-2004)
, 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 2 05000324 1 of 4
- 4. TITLE Operation Prohibited by Technical Specification 3.3.1.2, "Source Range Monitor Instrumentation"
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR I SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO 03 26 2007 2007 001 00 05 22 2007 FACILITY NAME DOCKET NUMBER
__________________05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 5
[] 20.2201(b)
El 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
El 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)
[I 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
[I 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[]
50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 000 El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[E 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
[E 50.73(a)(2)(v)(B)
E] 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER Specify in Abstract below El 20.2203(a)(2)(vi) 0] 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 NRC Form 366A) (17)* Other plant procedures which could result in a core alteration due to movement of a control rod will be reviewed to determine their adequacy. This review is currently scheduled to be completed by July 17, 2007.
Although not intended to prevent recurrence, the following corrective action is planned.
0 A license amendment request will be submitted to revise TS Table 3.3.1.2-1, "Source Range Monitor Instrumentation," to include operability requirements consistent with SR 3.3.1.2.2. The amendment request is currently scheduled to be submitted by August 16, 2007.
Previous Similar Events
A review of LERs and corrective action program condition reports for the past three years identified the following similar event.
LER 1-2005-003, dated June 16, 2005, documents operation prohibited by TSs that occurred when LCO 3.0.5 was misapplied resulting in control rod 46-15 being inappropriately re-armed. The corrective actions associated with LER 1-2005-003 could not have reasonably been expected to prevent the condition reported in this LER.