05000285/LER-2010-003, Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable

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Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable
ML13176A045
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/10/2010
From: Reinhart J
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-10-0063 LER 10-003-00
Download: ML13176A045 (5)


LER-2010-003, Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(v)(8)

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
2852010003R00 - NRC Website

text

August 10, 2010 L I C-1 0-0063 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2010-003, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2010-003, Revision 0, dated August 10, 2010. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73 (a)(2)(v)(8).

No regulatory commitments are contained in this submittal. If you should have any questions, please contact me.

JARlepm Attachment c:

E. E. Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center Employment with Equal Opportunity

NRC FORM 366 U.S. NUCLEAR REGULATORYCOMMISSION (9-2007)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Fort Calhoun Station
2. DOCKET NUMBER 05000285
3. PAGE 1 OF 4
4. TITLE Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTI AL NUMBER REV NO MONT H

DAY YEAR FACILITY NAME DOCKET NUMBER 05000 04 06 2009 2010

- 003 -

00 08 10 2010 FACILITY NAME 05000

9. OPERATING MODE 1
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b)

20.2203(a)(3)(i)

50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d)

20.2203(a)(3)(ii)

50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1)

20.2203(a)(4)

50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)

50.36(c)(1)(i)(A)

50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)

10. POWER LEVEL 100 20.2203(a)(2)(ii)

50.36(c)(1)(ii)(A)

50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii)

50.36(c)(2)

50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv)

50.46(a)(3)(ii)

X 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v)

50.73(a)(2)(i)(A)

50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi)

X 50.73(a)(2)(i)(B)

50.73(a)(2)(v)(D)

Specify in Abstract below or in

EVENT DESCRIPTION

On April 6, 2009, FW-10 tripped off while performing Attachment 1 of OI-AFW-4 (FW-10 Turbine-Driven AFW Pump Operations) per OP-ST-AFW-0004 (Auxiliary Feedwater Pump FW-10 Operability Test). FW-10 tripped approximately one minute after it was successfully started. FW-10 discharge pressure switch (PS-1122) white indicating light was found lit on control panel AI-279 (Auxiliary Feedwater Pump FW-10 Discharge Overpressure Control Panel). This light indicates the pump tripped on high discharge pressure. In response to FW-10 tripping off, the control room operators entered TS 2.5(1)B which requires the inoperable pump to be restored to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A troubleshooting plan was initiated to perform calibration of PS-1122 using IC-CP-01-1122 (Calibration of AFW Pump FW-10 High Discharge Pressure Shutdown Switch PS-1122) and to determine if calibration of the switch was within tolerance. The calibration verified the pressure switch was within tolerance, measuring 1464 pounds per square inch gage (psig) (acceptance criteria 1450 psig plus or minus 35 psig). Pump discharge pressure and speed were measured. The highest observed pump discharge pressure was approximately 1280 psig. The highest pump speed measured was 7927 revolutions per minute (rpm). The initial troubleshooting plan did not find the cause of the pressure switch actuation. Additional troubleshooting activities were performed, but the highest discharge pressure measured was less than 1290 psig, and steady state pressure was observed at 1240 psig. In addition, the pumps minimum recirculation valve FCV-1369 remained open during multiple pump starts.

On February 26, 2009, Facility Design Change Request (FDCR) 45607 (Revise the Acceptance Criteria in EC 45105) revised the acceptance criteria in Engineering Change (EC) 45105 (FW-10 Speed Limiting Governor Setting) to allow the discharge pressure to be increased beyond the 1170 to 1210 psig target range prescribed in the EC 45105. A new maximum pressure limit of 1280 psig was prescribed to ensure the typical minimum flow recirculation mode pressure was well below the surveillance test limit.

On April 6, 2009, it was concluded that the discharge pressure increase on February 26, 2009, may have contributed to this event, and it was recommended to increase the pressure switch setpoint from the current 1450 psig to 1600 psig. The setpoint was subsequently increased to 1600 psig on April 6, 2009. The event is documented in condition report (CR) 2009-1611.

During an NRC inspection the operability of FW-10 was questioned, during the period the speed limiting governor for FW-10 was increased until the discharge pressure trip was increased. Subsequently, on June 11, 2010, it was determined that FW-10 was inoperable from February 26, 2009, until April 6, 2009. The event was determined to be reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B).

This event is being reported per 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B).

CONCLUSION The root cause of this event was that EC 45105 (FW-10 Speed Limiting Governor Setting) and FDCR 45607 (Revise the Acceptance Criteria in EC 45105) reduced the discharge pressure margin to trip setpoint resulting in FW-10 becoming more susceptible to tripping on high discharge pressure.

On February 26, 2009, FDCR 45607 revised the acceptance criteria in EC 45105 to allow the discharge pressure to be increased beyond the 1170 to 1210 psig target range prescribed in the EC 45105. A new maximum pressure limit of 1280 psig was prescribed to ensure the typical minimum flow recirculation mode pressure was well below the surveillance test limit. It should also be noted that FDCR 45607 was implemented after maintenance adjusted the speed of the pump to approximately 7900 rpm. The 7900 rpm pump speed resulted in a steady state discharge pressure of approximately 1240 psig. Based on interview, it was decided that re-adjusting the speed to obtain a 1210 psig pressure would take too much TS limiting condition for operation (LCO) time. FDCR 45607 revised the maximum discharge pressure limit for FW-10 from 1210 psig to 1280 psig. This revised limit resulted in a 170 psig margin to the trip setpoint of 1450 psig (PS-1122 trip setpoint).

The reduction in the pressure margin to trip from approximately 290 psig (before EC 34435, June 2008) (1450 psig [PS-1122 setpoint] - 1160 psig [FW-10 discharge pressure before EC 34435]) to approximately 170 psig (1450 psig [PS-1122 setpoint] - 1280 psig [FW-10 discharge pressure after FDCR 45607]) after FDCR 45607 resulted in the pump tripping on April 6, 2009. The EC process did not identify or analyze this reduction as adverse because engineering personnel made the judgment that a 170 psig margin to trip was adequate. Engineers did not have the operational pressure data to conclusively determine if 170 psig was adequate.

CORRECTIVE ACTIONS

The setpoint for the AFW Pump FW-10 High Discharge Pressure Shutdown Switch PS-1122 was increased from 1450 psig to 1600 psig. Additional actions are being addressed by the stations corrective action system.

SAFETY SIGNIFICANCE

As previously described, any of the three auxiliary feedwater pumps are capable of supplying water to the steam generators to remove heat following potential accident scenarios at the station. For a short period of time the emergency power source for FW-6, Diesel Generator (DG)-1, was inoperable during routine surveillance testing.

Had DG-1 been needed for operation it could have been quickly returned to service. Periodic testing of FW-10, by starting the pump, prior to, and after the failure, demonstrated that the pump was likely to start as designed.

In addition, FW-54, although not safety related, was functional and able to supply water to the steam generators if needed. Therefore this event had very little impact on the health and safety of the public.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does result in a safety system functional failure in accordance with NEI-99-02.

PREVIOUS SIMILAR EVENTS

No previous incidence of inadequate margin for the auxiliary feedwater pumps has occurred. PRINTED ON RECYCLED PAPER