05000324/LER-2011-001, For Brunswick, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable
| ML11277A025 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/26/2011 |
| From: | Frisco J Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER-11-001-00 | |
| Download: ML11277A025 (3) | |
| 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 |
| 3242011001R00 - NRC Website | |
text
Progress Energy September 26, 2011 SERIAL: BSEP 11-0094 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 Renewed Facility Operating License No. DPR-62 Docket Nos. 50-324 Licensee Event Report 2-2011-001 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 (LER). 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 Ms. Annette Pope, Supervisor -
Licensing/Regulatory Programs, at (910) 457-2184.
Sincerely, Joseph M. Frisco, Jr.
Plant General Manager Brunswick Steam Electric Plant LJG/ljg I
Enclosure:
Licensee Event Report Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 11-0094 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (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 2 05000324 1 of 1
- 4. TITLE Condition Prohibited by Technical Specifications due to RWCU Instrumentation Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED S
I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR ISEQUENTAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 07 28 2011 2011 - 001 - 00 09 26 2011
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[I 20.2201(b)
EU 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
E U 20.2201(d)
E] 20.2203(a)(3)(ii)
Ul 50.73(a)(2)(ii)(A)
EU 50.73(a)(2)(viii)(A)
EU 20.2203(a)(1)
EU 20.2203(a)(4)
[U 50.73(a)(2)(ii)(B)
U] 50.73(a)(2)(viii)(B)
EL 20.2203(a)(2)(i)
EU 50.36(c)(1)(i)(A)
EU 50.73(a)(2)(iii)
EU 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL EU 20.2203(a)(2)(ii)
EU 50.36(c)(1)(ii)(A)
EU 50.73(a)(2)(iv)(A)
EU 50.73(a)(2)(x)
EU 20.2203(a)(2)(iii)
EU 50.36(c)(2)
EU 50.73(a)(2)(v)(A)
U 73.71(a)(4) 100 Ul 20.2203(a)(2)(iv)
EU 50.46(a)(3)(ii)
E] 50.73(a)(2)(v)(B)
U 73.71(a)(5)
EU 20.2203(a)(2)(v)
EU 50.73(a)(2)(i)(A)
[U 50.73(a)(2)(v)(C)
U OTHER EU 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B)
U 50.73(a)(2)(v)(D)
Specify in Abstract below or I_
I in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Lee Grzeck, Senior Engineer - Licensing (910) 457-2487MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACURER EPO B
CAUSE
SYSTEM COMPONENT FACURER EPOA FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION ED YES (If yes, complete 15. EXPECTED SUBMISSION DATE) [:1 NO DATE 11 25 2011 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On July 28, 2011, in response to a recent trip of the Unit 2 Reactor Water Cleanup (RWCU) System, engineering personnel performed a comprehensive review of system data and identified that the system inlet flow rate was significantly lower (i.e., approximately 18%) than the system outlet flow rate. Investigation subsequently determined that the inlet flow was inaccurate because the flow orifice for the system inlet flow element, 2-G31-FE-N035, had been installed backwards during maintenance activities performed on March 19, 2011. It was concluded that the lower flow readings from the RWCU inlet flow instrumentation would result in non-conservatism and, as a result, the RWCU system isolation on Differential Flow-High (i.e., Technical Specifications Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation,"
Function 5.a) was inoperable.
This condition is being reported as an operation or condition prohibited by Technical Specifications. The safety consequences of this event were minimal.
Corrective action was taken to reinstall the flow orifice in the correct orientation. Additional evaluation is in progress to substantiate the operability of the RWCU system instrumentation. This LER will be supplemented based on the results of the evaluation.
NRC FORM 366 (10-2010)