05000311/LER-2002-003, Re Failure to Maintain Elements of Salem Fire Protection Program
| ML021650488 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/03/2002 |
| From: | Garchow D Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N02-0209 LER-02-003-00 | |
| Download: ML021650488 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| 3112002003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG JUN 0 3 2002 N0uclear LLC LR-N02-0209 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SPECIAL REPORT 311102-003-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Gentlemen:
This Special Report entitled "Failure To Maintain Elements Of The Salem Fire Protection Program" is being submitted pursuant to the requirements of Salem Unit 2 Operating License Condition 2.1.
Sincerely, D. F. archow Vice Prsident -
Operations Attachment BJT C
Mr. H. J. Miller, Administrator - Region I USNRC Region I 475 Allendale Road King of Prussia, PA 19406 Distribution LER File 3.7 95-2168 REV. 7199
Abstract
At approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on May 20, 2002, preliminary test results were obtained for tracer gas tests being performed for the Unit 1 Elevation 78 Lower Electrical Penetration Area and the Unit 1 Elevation 64' 4160 Volt Switchgear Room. Results from these tests identified room leakage sufficient to prevent the carbon dioxide system in these areas from maintaining the required concentration of 50% for a hold time of 20 minutes as required by NFPA-12. At the time the results were presented, a review of data from tests being performed in the Unit 2 Elevation 78' Lower Electrical Penetration Area indicated that similar results would be expected for this area as well. An extent of condition review was performed considering that the primary leakage was through the CO2 isolation dampers and it was determined that the Unit 2 4160 Volt Switchgear Room, and the Unit 1 & 2 460 Volt Switchgear Rooms may also be affected such that these rooms may not b capable of maintaining the carbon dioxide concentration of 50% for the hold time of 20 minutes. As a result the carbon dioxide systems for these six fire areas were impaired and fire watches were established in accordance with the Fire Protection Program.
The cause of the excessive leakage is under investigation as are appropriate corrective actions. A supplemental report will be issued by August 2, 2002 to report on the results of the investigation.
This report is being made in accordance with Unit 2 License Condition 2.1, which requires reporting any violation of the Fire Protection Program (License Condition 2.C.10).
NRC FORM 366 (7-2001)U.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET (2)
FACILITY NAME (1)
NUMBER (2)
LER NUMBER (6)
PAGE (3) l SEQUENTIAL REVISION YEAR I
NUMBER I NUMBER SALEM UNIT 2 05000311 02 0 0 3
00 q 2 OF 4
ITEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor Carbon Dioxide Suppression System (LW/-)
- Energy Industry Identification System {EIIS} codes and component function identifier codes appear as (SS/CCC)
CONDITIONS PRIOR TO OCCURRENCE Salem Unit 1 and Unit 2 were in Mode 1 at 100% power at the time of discovery.
DESCRIPTION OF OCCURRENCE At approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on May 20, 2002, preliminary test results were obtained for tracer gas tests being performed for the Unit 1 Elevation 78 Lower Electrical Penetration Area and the Unit 1 Elevation 64' 4160 Volt Switchgear Room. Results from these tests identified room leakage sufficient to prevent the carbon dioxide system in these areas from maintaining the required concentration of 50% for a hold time of 20 minutes as required by NFPA-12. At the time the results were presented, a review of data from tests being performed in the Unit 2 Elevation 78' Lower Electrical Penetration Area indicated that similar results would be expected for this area as well. An extent of condition review was performed considering that the primary leakage was through the CO2 isolation dampers and it was determined that the Unit 2 4160 Volt Switchgear Room, and the Unit 1 & 2 460 Volt Switchgear Rooms may also be affected such that these rooms may not be capable of maintaining the carbon dioxide concentration of 50% for the hold time of 20 minutes. As a result the carbon dioxide systems for these six fire areas were impaired and fire watches were established in accordance with the Fire Protection Program. Tracer gas testing has been performed in the following fire areas at Salem Unit 1 and 2:
(1) Unit 1 EL. 78' Lower Electrical Penetration Area (2) Unit 1 EL. 64' 4160 Volt Switchgear Room (3) Unit 2 EL. 78' Lower Electrical Penetration Area (4) Unit 2 EL. 64' 4160 Volt Switchgear Room The tracer gas testing was performed to determine actual field conditions for inclusion in a re-analysis of the carbon dioxide fire suppression system for these fire areas. As documented in NRC Inspection Report 05000272 & 05000311/1999010, the initial carbon dioxide concentration tests for the 4160 Volt Switchgear Rooms and the 78' Electrical Penetration Areas did not demonstrate that the requiredU.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET (2)
FACILITY NAME (1)
NUMBER (2)
LER NUMBER (6)
PAGE (3)
SEQUENTIAL REVISION YEAR NUMBER I NUMBER SALEM UNIT 2 05000311 02 0 0 3
00 3 OF 4 TEXT (Ifimore space is required, use additional copies of NRC Form 366A) (17) concentration of 50% was met for the established hold time of 20 minutes for these fire areas and subsequent test reports were not found that demonstrated this ability. The re-analysis of the carbon dioxide fire suppression is being conducted to resolve this concern. The tracer gas tests were being performed to characterize the dilution of carbon dioxide in these areas following a discharge of carbon dioxide in order to perform adjustments to the system to ensure a carbon dioxide concentration of at least 50% concentration for the 20 minute hold time.
Subsequent results from testing of the Unit 2 Electrical Penetration Area and the Unit 2 4160 Volt Switchgear Room revealed similar results to the Unit 1 data that indicate the carbon dioxide system in these areas is not capable of maintaining a 50% CO2 concentration for a hold time of 20 minutes.
Since the leakage of carbon dioxide appears to be due to excessive leakage through the Switchgear and Penetration Area Ventilation (SPAV) carbon dioxide isolation dampers, a conservative decision was made to conclude that the carbon dioxide system in the remaining area, the Unit 1 and 2 460 Volt Switchgear Rooms, within the SPAV ventilation system should also be declared inoperable.
On May 20, 2002, the carbon dioxide systems in all six of these fire areas (Unit 1 & 2 - 4160 Volt Switchgear, 460 Volt Switchgear, and 78' Electrical Penetration Area) were considered impaired.
Compensatory measures in the form of fire watches were established in accordance with the Fire Protection Program.
Failure to meet the carbon dioxide concentration is a violation of the Fire Protection Program, License Condition 2.C.5 (Unit 1) and 2.C.10 (Unit 2). In accordance with Unit 2 License Condition 2.1, failure to meet License Condition requires a 24-hour report and a follow-up 14-day special report.
CAUSE OF OCCURRENCE The cause of the excessive leakage from these fires areas is still under investigation. However, based on preliminary information, the excessive leakage appears to be from leakage through the Switchgear and Penetration Area Ventilation (SPAV) C02 isolation dampers (with the system fans continuing to run).U.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET (2)
FACILITY NAME (1)
NUMBER (2)
LER NUMBER (6)
PAGE (3)
SEQUENTIAL REVISION YEAR I
NUMBER NUMBER SALEM UNIT 2 05000311 02 0 0 3
00 4 OF 4 PRIOR SIMILAR OCCURRENCES The cause of occurrence is still under investigation; upon completion of the investigation this section will be revised to determine the extent of any prior similar occurrences.
SAFETY CONSEQUENCES
Although leakage from the ventilation supply and exhaust dampers affects the ability to achieve or maintain the carbon dioxide design concentration in accordance with NFPA-12, the carbon dioxide discharge into these areas still provides a fire suppression function until manual fire suppression activities can be initiated. Fire watches have been placed in these areas in accordance with the Fire Protection Program. These fire watches, along with the automatic early warning (ionization) fire detection will alert the dedicated onsite fire brigade who will respond and extinguish any fire using manual fire suppression methods. The fire brigade can manually activate an additional carbon dioxide system discharge as necessary to assist with the control or extinguishment of a fire. Based on the above, there is reasonable assurance that Salem Units 1 and 2 can achieve and maintain safe shutdown in the event of a fire in the 4160 Volt Switchgear Rooms, the 460 Volt Switch Rooms and the Electrical Penetration Areas.
CORRECTIVE ACTIONS
As an immediate corrective action, fire watches were established in accordance with the Fire Protection Program.
The development of appropriate corrective actions to address the cause of the leakage is ongoing.
Information regarding any corrective actions will be submitted in a supplement to this special report.
The supplement to this Special Report will be submitted by August 2, 2002
COMMITMENTS
The corrective actions cited in this Special Report are voluntary enhancements and do not constitute
commitments