ENS 40636
ENS Event | |
|---|---|
08:00 Apr 3, 2004 | |
| Title | High Pressure Coolant Injection System Inoperable |
| Event Description | During plant startup from the Brunswick Unit 1 Refueling Outage, the High Pressure Coolant Injection (HPCI) System was declared inoperable due to pump data not meeting the acceptable value of OPT-09.2, HPCI System Operability Test. With pump flow established at the reference value of 4550 gallons per minute, the actual turbine speed was 2530 rpm, outside the acceptable range of 2485-2515 rpm.
Initial Safety Significance Evaluation: Minimal since the Automatic Depressurization System (ADS), the Low Pressure Coolant Injection System (LPCI), and the Core Spray System are Operable. In addition the Reactor Core Isolation Cooling System (RCIC) is Operable. Corrective Actions: Engineering to evaluate the test results and determine corrective actions. The licensee will notify the NRC Resident Inspector.
The following information was obtained from the licensee via facsimile: The purpose of this call is to retract the notification (Event Number 40636) made by the Brunswick Steam Electric Plant, Unit No, 1, Docket No. 50-325 / License No. DPR-71, on April 3, 2004, at 0549 hours0.00635 days <br />0.153 hours <br />9.077381e-4 weeks <br />2.088945e-4 months <br />. On April 2, 2004, at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />, the High Pressure Coolant Injection (HPCI) system was declared inoperable for scheduled testing performed in accordance with 0PT-09.2, 'HPCI System Operability Test.' 0PT-09.2 includes, in part, Technical Specification (TS) Surveillance Requirement (SR) 3.5.1.7, to verify that, with reactor pressure < 1045 and > 945 psig, the HPCI pump unit could develop a flow rate > 4250 gpm against a system head corresponding to reactor pressure. The testing also includes in part, In-service Test (IST) program requirements for HPCI pump performance (to test for pump degradation). During this testing, water is circulated from the Condensate Storage Tank (CST) through the HPCI pump and back to the CST through a 'Bypass to CST' valve. Motive force for the pump is provided by reactor steam being routed through the HPCI turbine into the suppression pool. Due to the heat energy being deposited in the suppression pool, time for HPCI turbine/pump testing is limited. When tested, the HPCI pump passed the TS SR 3.5.1.7 pump pressure and flow rate test requirements. However, when HPCI turbine speed was set to the IST-required value of 2,500 rpm, as indicated by the control room indicator 1-E41-C002-4 (the preferred indication), the IST required system flow of 4,550 gpm could not be attained. Turbine speed was then adjusted, using a portable speed indicator, to attain 4,550 gpm system flow. The portable speed indicator read 2530 rpm, high, outside the acceptable range of 2,485 to 2,515 rpm. The unsatisfactory test indicated potential pump degradation. The IST program requires the equipment to be declared inoperable until unsatisfactory test results are evaluated. On April 3, 2004, at 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br />, the HPCI system was declared inoperable due to the unsatisfactory test. At 0549 hours0.00635 days <br />0.153 hours <br />9.077381e-4 weeks <br />2.088945e-4 months <br />, the NRC was notified (Event Number 40636) in accordance with 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. During the testing with the portable speed indicator, it was noted that the control room indicator 1-E41-C002-4 was reading high (i.e., 1-E41-C002-4 was reading 2,600 rpm compared to 2,500 rpm on the portable speed indicator). Turbine speed indicator 1-E41-C002-4 was adjusted back to within required accuracy in accordance with Work Order 306977. After the initial test, a thorough review of pump data, instrument calibration data, and IST program guidance was conducted. It was determined that there was no indication of pump degradation and no indication of a flow indicator problem. Having corrected a speed indicator problem, sections of 0PT-09.2 were performed on April 5, 2004, to test for pump degradation using the preferred speed indicator 1-E41-C002-4. Test results were satisfactory and demonstrated that the pump performance met the IST program requirements. The HPCI system was declared operable on April 5, 2004, at approximately 0521 hours0.00603 days <br />0.145 hours <br />8.614418e-4 weeks <br />1.982405e-4 months <br />. Investigation of this condition is documented in the corrective action program in Action Request (AR) 123551. NUREG-1022, Rev. 2, Section 3.2.7 (page 56) lists types of events or conditions that are generally not reportable under 10 CFR 50.72(b)(3)(v) and 10 CFR 50.73 (a)(2)(v) criteria. The list of not-reportable conditions includes: - Removal of a system or part of a system from service as part of a planned evolution for maintenance or surveillance testing when done in accordance with an approved procedure and the plant's TS (unless a condition is discovered that could have prevented the system from performing its function) On April 2, 2004, the HPCI system was removed from service for testing in accordance with an approved procedure 0PT-09.2. The system was declared inoperable due to the test results discussed above, and since the HPCI system is a single train safety system, an ENS notification was made. However, no condition was discovered that could have prevented the HPCI system from performing its functions. Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., has determined that this event does not meet the 10 CFR 50.72 or 10 CFR 50.73 reporting criteria and the notification for Event Number 40636 is retracted. The resident inspector has been notified. |
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+-2.18 h-0.0908 days <br />-0.013 weeks <br />-0.00299 months <br />) | |
| Opened: | William Woodbury 05:49 Apr 3, 2004 |
| NRC Officer: | Mike Ripley |
| Last Updated: | May 6, 2004 |
| 40636 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (22 %) |
| After | Power Operation (22 %) |
Brunswick with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
WEEKMONTHYEARENS 559972022-07-16T00:20:00016 July 2022 00:20:00
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Mitigate the Consequences of an Accident High Presure Coolant Injection System Inoperable Due to Maintenance ENS 407142004-04-29T02:30:00029 April 2004 02:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Hpci System Inoperable Following Planned Maintenance ENS 406362004-04-03T08:00:0003 April 2004 08:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection System Inoperable ENS 403182003-11-13T03:22:00013 November 2003 03:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection System Isolation During Testing 2022-07-16T00:20:00 | |