05000324/LER-2007-004, High Pressure Coolant Injection (HPCI) System Inoperable Due to Main Pump Seal Leak
| ML073521379 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-062) |
| Issue date: | 12/10/2007 |
| From: | Wills E Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 07-00131 LER 07-004-00 | |
| Download: ML073521379 (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 |
| 3242007004R00 - NRC Website | |
text
Progress Energy December 10, 2007 SERIAL: BSEP 07-00131 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 2-2007-004 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.
An engineering analysis is in progress to substantiate the ability of the effected system to fulfill its safety functions in the degraded condition. This LER will be supplemented, and based on the results of the engineering evaluation, may result in retraction of Event Notification 43711 and withdrawal of this LER.
Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager -
Support Services, at (910) 457-2447.
Sincerely, Edward L. Wills, Jr.
Plant General Manager Brunswick Steam Electric Plant LJG/ljg Enclosure: Licensee Event Report Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461
Document Control Desk BSEP 07-0131 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator (Acting)
Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051
i
- ;t'*
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007 (6-2004)
Estirrmated, 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 High Pressure Coolant Injection (HPCI) System Inoperable due to Main Pump Seal Leak
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL I REV MONTH DAY YEAR FACILtTYNAME DOCKET NUMBER MDOCKET NUMBER 10 10 2007 2007 -- 004 00 12 10 2007 FACILITY NAME jOCKETNUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 1 El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
[I 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[1 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0l 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 100 El 20.2203(a)(2)(iii)
[I 50.36(c)(2)
[]
50.73(a)(2)(v)(A)
El 73.71 (a)(4)
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)
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)
El 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D) or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Lee J. Grzeck, Senior Engineer - Licensing 1(910) 457-2487CAUSE SYSTEM COMPONENT MANU-REPORTABLE MANU-REPORTABLE FACTURER TO EPIX
CAUSE
SYSTEM COMPONENTEPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MO DAY YEAR SUBMISSION X IYES (If yes, complete EXPECTED SUBMISSION DATE).
NO DATE r01 31 r 2008 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On October 10, 2007, at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> Eastern Daylight Time (EDT), during performance of the High Pressure Coolant Injection (HPCI) system operability test, the HPCI system was declared inoperable due to a leak on the main pump turbine side seal. The approximate five gallon per minute leak was isolated by securing the pump and isolating the keep-fill. No automatic system isolations or actuations occurred. All Emergency Core Cooling Systems (ECCS) and the Reactor Core Isolation Cooling (RCIC) system were operable.
The safety significance of this event is considered minimal because HPCI was still available for injection, though in a degraded condition, and adequate core cooling was ensured by the operability of the redundant low pressure ECCS injection subsystems in conjunction with the Automatic Depressurization System (ADS). The RCIC system would also automatically provide makeup water at high reactor operating pressures.
The root cause of this event was an inadequate evaluation of foreign material in the Unit 2 Condensate Storage Tank (CST) performed in 1999, leading to legacy foreign material in the HPCI system seal purge piping, combined with the configuration of the line which is intolerant to foreign material intrusion. The HPCI system was returned to service following the replacement of the HPCI main pump seal, and the inspection and removal of foreign material from the seal purge water piping.
An engineering analysis is in progress to substantiate the ability of the effected system to fulfill its safety functions in the degraded condition. This LER will be supplemented, and based on the results of the engineering evaluation, may result in retraction of Event Notification 43711 and withdrawal of this LER.