05000382/LER-2005-002, Re Failure of One System of RCS Leakage Detection Instrumentation Due to Latent Human Error
| ML052220111 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/08/2005 |
| From: | Murillo R Entergy Nuclear South, Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3Fl -2005-0061 LER 05-002-00 | |
| Download: ML052220111 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 |
| 3822005002R00 - NRC Website | |
text
- Entergy Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6715 Fax 504-739-6698 rmurilleentergy.com Robert J. Murillo Licensing Manager, Acting Waterford 3 10CFR50.73 (a)(2)(i)(B)
W3Fl -2005-0061 August 08, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Licensee Event Report 2005-002-00 Waterford 3 SES Docket No. 50-382 License No. NPF-38 Gentlemen:
Attached is Licensee Event Report (LER) 2005-002-00 for Waterford Steam Electric Station Unit 3. This report documents a reportable condition due to containment fan cooler condensate flow switches not performing their specified safety function of detecting a leakage rate of orie gpm as required by the Technical Specification. This condition is being reported pursuant to 10CFR50.73 (a)(2)(i)(B) as a condition prohibited by the Technical Specification.
There are no commitments contained in this submittal. If you have any questions, please contact Michael E. Mason at (504) 739-6673.
Very truly yours, Robert J. Murillo Licensing Manager, Acting RJM/MEM/cbh Attachment
W3F1 -2005-0061 Page 2 cc:
Mr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop 0-07 DI Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Louisiana Department of Environmental Quality Office of Environmental Compliance (REP&R) Unit Emergency and Radiological Services Division P.O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers 95 Glastonbury Blvd - Suite 300 Glastonbury, CT 06033-4443 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 R.K. West, lerevents@inpo.org - INPO Records Center
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007
- 6-2004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Waterford Steam Electric Station, Unit 3 05000 -382 OF 5
- 4. TITLE Failure of One System of RCS Leakage Detection Instrumentation due to Latent Human Error
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL RNOV MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 06 09 2005 2005 -
2 00 08 08 2005 N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Checkall that apply) o 20.2201(b) 0 20.2203(a)(3)(i) a 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 3 l 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) al 50.73(a)(2)(viii)(A) o 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 0_ 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 E1 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A) a 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2) a 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)
N/A El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify 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)
During the time interval when the CFCCFS was inoperable due to not meeting the Regulatory Guide 1.45 detector sensitivity requirement, there was always one RCSLDS TS LCO detection system operable. In addition, TSSR 4.4.5.2.1, Reactor Coolant System inventory balance, was being performed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and provided RCPB leakage detection capability at much less than I gpm leakage rate. These detection capabilities coupled with the low LOCA probabilities make the safety significance of this condition negligible.
The containment leakage detection system is not modeled in the PRA. The PRA LOCA initiator frequencies are from NUREG/CR-5750, "Rates of Initiating Events at U.S. Nuclear Power Plants:
1987 - 1995." These PRA LOCA initiator frequencies would remain valid while in this condition.
Qualitatively, the low LOCA initiator frequencies and alternative leak detection methods indicate a negligible impact in Core Damage Frequency (CDF) and Large Early Release Frequency (LERF).
This condition is not a Safety System Functional Failure. Per NUREG-1022, Event Reporting Guidelines 10 CFR 50.72 and 50.73, there are four safety system functions: ability to shut down the reactor and maintain it in a safe shutdown condition, ability to remove residual heat, ability to control the release of radioactive material, and ability to mitigate the consequences of an accident. The RCSLD TS LCO meets none of these safety system functions. The system serves as one of the diverse leakage monitoring systems capable of detecting extremely small RCS boundary leakage to allow timely actions to place the plant in a safe condition.
SIMILAR EVENTS
There were no previous similar reportable events identified that involved CFCCFS or Regulatory Guide 1.45 design basis requirements.
ADDITIONAL INFORMATION
Energy Industry Identification System (EIIS) codes are identified in the text within brackets [].