05000247/LER-2003-001, Re Plant in an Unanalyzed Condition Due to Cable Routing Non-Compliance with Appendix R Separation Criteria
| ML030970091 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/02/2003 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-059 LER 03-001-00 | |
| Download: ML030970091 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 2472003001R00 - NRC Website | |
text
-- Entergy Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 PO Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations April 2, 2003 NL-03-059 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555-0001
SUBJECT:
Indian Point Nuclear Power Plant Unit 2 Docket No. 50-247 License No. DPR-26 Licensee Event Report # 2003-001-00 Plant in an Unanalyzed Condition due to Cable Routing Non-Compliance with Appendix R Separation Criteria
Dear Sir:
The attached Licensee Event Report (LER) 2003-001-00 is hereby submitted in accordance with the requirements of 10 CFR 50.73. This condition is of the type defined in 10 CFR 50.73(a)(2)(ii)(B) as an unanalyzed condition that significantly degraded plant safety. This condition has been recorded in Entergy's Corrective Action Program as Condition Reports CR-IP2-2003-00765 and CR-IP2-2003-00867.
Entergy is making no new commitments in this LER.
Fred R.Dacimo Vice President, Operations Indian Point Energy Center
Docket No. 50-247 NL-03-059 Page 2 of 2 cc:
Mr. Hubert J. Miller Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406-1415 Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Reactor Projects I/Il U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555 INPO Record Center 700 Galleria Parkway Atlanta, Georgia 30339-5957 U.S. Nuclear Regulatory Commission Resident Inspectors' Office Indian Point 2 Nuclear Power Plant P. 0. Box 38 Buchanan, NY 10511-0038
Abstract
On February 6, 2003, IPEC, Programs & Components Engineering (P&CE),
determined that the routing of Charging Pump (CHP) control cables did not meet the cable separation criteria specified in Appendix R Section III.G. On February 12, 2003, P&CE further identified that the routing of the power supply cables for the six Service Water Pumps (SWP) did not meet the separation criteria of Appendix R,Section III. G. These conditions were discovered during the validation and re-baselineing of the Appendix R safe shutdown analysis. In the case of the CHPs, the control functions for all three CHPs were determined to be vulnerable to damage by a single fire event in Fire Area F, specifically the Primary Auxiliary Building (PAB), elevation 80 ft. In the case of the SWPs, the normal and alternate power supply cables for all six SWPs were determined to be vulnerable to damage by a single fire in Fire Area J, specifically the Turbine Building (TB), elevation 15 ft. The apparent cause was the lack of rigor applied in the engineering analysis that developed the Appendix R safe shutdown analysis.
The Appendix R analysis lacks sufficient detail and/or support documentation to justify the original design configuration. The corrective actions taken were to complete the rebaselineing of the Appendix R analysis and develop procedures or modifications to resolve non-compliance with Appendix R. Upon discovery of these conditions, IPEC initiated fire protection impairment actions in accordance with Station Administrative Order SAO-703,
" Fire Protection Impairment Criteria and Surveillance," and interim compensatory measures were implemented. These conditions had no significant effect on the health and safety of the public.
NRC FURM 366 (1-2001)
(If more space is required, use addibonal copies of NRC Fonr 366A) (17)
Note: The Energy Industry Identification System Codes are identified within the brackets {}.
DESCRIPTION OF EVENT
On February 6, 2003, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, with steady state reactor power at 100%, Indian Point Energy Center (IPEC), Programs and Components Engineering (P&CE), determined that the routing of the Charging Pump (CHP) {CB}{P} control cables did not meet the cable separation criteria specified in Appendix R Section III.G. On February 12, 2003, at 1353 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.148165e-4 months <br />, P&CE further identified that the routing of the normal and alternate power supply cables for the six Service Water Pumps (SWP){BI} did not meet the separation criteria of Appendix R,Section III.G. P&CE discovered these conditions during the re-baselineing of the Appendix R safe shutdown analysis as part of a Design Basis Initiative (DBI) Project.
The CHP control cables and control functions for all three CHPs were determined to be vulnerable to damage by a single fire event in Fire Area F, specifically in the Primary Auxiliary Building (PAB){NF}, elevation 80 ft.
Panels for speed control and local/remote breaker control for all three pump controllers are located in a common hallway immediately outside the CHP cubicles.
This configuration leaves all control functions (i.e. both breaker and speed control) for all three CHPs vulnerable to damage by a single fire event in the area. Upon discovery, CR-IP2-2003-00765 was recorded in the Entergy's Corrective Action Program.
The SWP normal and alternate power supply cables were determined to be vulnerable to the effects of a single fire in Fire Area J. In the event of a postulated fire in Fire Area J, the credited shutdown methodology places reliance on the use of the "normal" safety-related electrical distribution system (ED), powered from the emergency diesel generators {EK}.
Therefore, in the event of a fire in Fire Area J, at least one SWP is credited as operated using "normal" power supply and normal controls. The specific location of the vulnerability for the SWP normal power supply cables is Manhole (MH) 23 located on the 15 ft. elevation of the Turbine Building (TB){NMI. MH 23 is covered by a checkered plate that is exposed to the 15 ft. elevation that leaves the normal power supply cables potentially vulnerable to the effects of an oil fire in that area. Upon discovery, CR-IP2-2003-00867 was recorded in the Entergy's Corrective Action Program.
These areas of non-compliance with Appendix R were identified by the DBI Project for rebaselineing the Appendix R analysis. This project will ensure that any other conditions of potential non-compliance with Appendix R separation criteria are identified, and, therefore, no additional extent of condition review was required.
(If more space is required, use addibonal copies of (If more space is required, use addibonal copies of NRC Form 366A) (17)
EVENT SAFETY SIGNIFICANCE These conditions had no significant effect on the health and safety of the public.
There were no actual safety consequences for these conditions because the plant was not challenged by an actual fire event that challenged the operability of the CHPs or the SWPs. The Fire Hazards Analysis for the PAB, 80 ft. elevation corridor, identifies active smoke detection to provide early detection. Both the PAB and TB have manual fire suppression equipment located in the area supporting the capability of rapid response by the Fire Brigade. Although these areas are not continually occupied, they are the main access for the PAB and the TB for station personnel (i.e. Health Physics, Security, Operations, Maintenance) who regularly pass through the areas during the course of their normal work routine. If conditions were to degrade, presenting a fire threat, it is likely that such conditions would be identified early and promptly corrected by station personnel preventing the occurrence of a significant fire.
The Combustible Loading Calculation identifies that the normal combustible loading in the areas is "Low" indicating that a large consuming fire capable of impacting the CHP or the SWP cables is unlikely because there are not sufficient combustibles in the area to fuel such a fire.
Also, transient combustibles for the area are controlled per Station Administrative Order SAO-701, "Control of Combustibles and Transient Fire Load," which limits transient fire loads in buildings during maintenance and modifications to the minimum amount of material practical. In the interim, compensatory measures were established and will remain in effect until required changes are implemented to establish regulatory compliance. A quantitative risk assessment was performed for a postulated fire affecting all three CHPs and the change in the core damage frequency was calculated to be 1.09 E-10. Although a complete quantitative risk assessment for the SWPs was not feasible given modeling limitations, sufficient qualitative mitigating factors exist to conclude that the actual risk associated with this condition was low. The significant sources of oil to support a fire that would challenge the SWP cables are distant from MH 23 and would likely be directed to the condenser pit or lower level of the TB. MH 23 is located at the southeast corner of the TB with the turbine lube oil system being centrally located.
The oil reservoir is located at the north end of the TB. In its as-found condition, the manhole cover plate had only a limited number of small holes, which would restrict the entry of oil and would be unlikely to admit sufficient air to support sustained combustion within the enclosed manhole.