05000461/LER-2014-005, Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions
| ML15005A385 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/30/2014 |
| From: | Newcomer M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| U-604194 LER 14-005-00 | |
| Download: ML15005A385 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 |
| 4612014005R00 - NRC Website | |
text
A ExeLon Generation.
Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604194 10 CFR 50.73 December 30, 2014 SRRS 5A.108 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Licensee Event Report 2014-005-00 This letter corrects an error in the Licensee Event Report (LER) submittal letter U-604190 dated 11/13/2014 for LER 2014-005-00. The letter dated 11/13/2014 incorrectly stated that the LER was being submitted in accordance with the requirements of 10 CFR 73.71. The 11/13/2014 letter sho Id have stated that the LER was being submitted in acc~ordance with 10 CFR 50.73. The a~tachment to the submittal letter was correct as submitted.
Enclosed is Licensee Event Report (LER) No. 2014-005-00: Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions. This report is being submitted in accordance with the requirements of 10 CFR 50.73.
There are no regulatory commitments contained in this report.
Should you have any questions concerning this report, please contact Ms. Kathy Ann Baker, Regulatory Assurance Manager, at (217) 937-2800 Respectfully, M. M. Newcomer Site Vice President Clinton Power Station RSF/cas
Enclosure:
Licensee Event Report 2014-005-00 cc:
Regional Administrator-NRC Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - IEMA Division of Nuclear Safety
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014) 9*
w.-O Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections L
E E
EEPORT
(
R Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by LICENSEE EVENT REPORT (LER) internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid 0MB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Clinton Power Station, Unit 1 05000461 1 OF 3
- 4. TITLE Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MNHNUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 09 16 2014 2014 -
005
- - 00 11 13 2014 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[_
50.73(a)(2)(vii)
[-
20.2201(d)
E 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
LI 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
E 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
LI 50.73(a)(2)(viii)(B)
[E 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[_
50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[] 50.73(a)(2)(iv)(A)
[1 50.73(a)(2)(x)
[]
20.2203(a)(2)(iii)
[1 50.36(c)(2)
[1 50.73(a)(2)(v)(A)
LI 73.71 (a)(4) 09 20.2203(a)(2)(iv)
[1 50.46(a)(3)(ii)
F1 50.73(a)(2)(v)(B)
LI 73.71(a)(5) 097 LI 20.2203(a)(2)(v)
LI 50.73(a)(2)(i)(A)
LI 50.73(a)(2)(v)(C)
LI OTHER
[]
20.2203(a)(2)(vi)
Li 50.73(a)(2)(i)(g)
[
50.73(a)(2)(v)(O)
Specify in Abstract below or in
PLANT AND SYSTEM IDENTIFICATION
General Electric -- Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EIIS) codes are identified in text as [XX].
EVENT IDENTIFICATION Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions
A. Plant Operating Conditions Before the Event
Unit: 1 Event Date: 9/16/14 Event Time: 1905 Central Time Mode: 1 Mode Name: Power Operation Reactor Power: 97 percent
B. DESCRIPTION OF EVENT
On 9/16/14 at approximately 1905 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.248525e-4 months <br />, Operators were performing an operability test of the Shutdown Service Water (SX) [BI] system. The Division 3 SX pump [P] (1 SX01 PC) was started to support the 2-year Comprehensive Pump Test and tripped off after approximately 36 seconds due to motor [MO] thermal overload protection. There was no evidence the pump had rotated, and oil was coming down from the top of the motor shaft, forming a puddle on the horizontal part of the bottom of the motor.
Operators immediately declared the Division 3 SX, Division 3 Emergency Diesel Generator (EDG) [EK], Division 3 Inverter [EF], Division 3 Direct Current Distribution [EJ], Division 3 Alternating Current Distribution [ED]
systems and the High Pressure Core Spray (HPCS) [BG] system inoperable due to the pump trip. Operators entered the Technical Specification Actions Requirements for Limiting Conditions for Operation (LCO) 3.7.2, Division 3 SX Subsystem; LCO 3.8.4, DC Sources - Operating; LCO 3.8.7, Inverters - Operating; LCO 3.8.9, Distribution Systems - Operating; and LCO 3.5.1, ECCS - Operating. Operators verified within one hour that the RCIC system was operable, and entered the action to restore HPCS to Operable status within 14 days.
Initial troubleshooting found the pump breaker [BKR] on and not tripped, and the motor thermal overloads were tripped. There was no physical damage visible at the breaker cubicle. The pump motor windings tested satisfactory and a 500 volts megger test was performed with acceptable results. Engineering determined that motor thermal overloads tripping in 36 seconds was consistent with expectations for a locked rotor condition.
At 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, Operators completed an 8-hour non-emergency notification to the NRC (Event Notification 50463) under 10 CFR 50.72(b)(3)(v)(D) due to the loss of a single train safety system, that is, the loss of the HPCS system function. This event is also reportable under 10 CFR 50.73(a)(2)(v)(D) due to a condition that could have prevented the fulfillment of the safety function needed to mitigate the consequences of an accident.
Maintenance personnel were able to rotate the pump and motor assembly by hand with the assistance of a 2-foot pipe wrench, but the assembly was very hard to turn. The shaft had a steady drag that was consistent the entire rotation and did not loosen with additional revolutions. With the pump packing removed, the shaft was rotated with the same results. With the pump uncoupled from the motor, the motor turned freely. The motor was run uncoupled from the pump with acceptable results. Motor inspections and a successful uncoupled run eliminated concerns about the oil discovered at the bottom of the motor. The decision was made to replace the pump assembly with a new assembly from stores.
Issue Report 2381871 was initiated to document this event and an equipment apparent cause evaluation was performed.
C. CAUSE OF EVENT
The pump was removed and sent to the supplier for failure analysis. Preliminary information from the supplier indicates the suction bell bearing has extreme damage. The most probable cause for this event at this time is degradation of the pump suction bell bearing.
D. SAFETY CONSEQUENCES
The purpose for the Division 3 SX system is to provide cooling water to Division 3 cooling loads including the HPCS pump room coolers [CLR], the Division 3 EDG and the Division 3 Switchgear Heat Removal System (VX).
The Division 3 SX header is normally supplied by cooling water from the non-safety related Plant Service Water System (WS) [KG]. Under design basis event conditions such as Loss of Offsite Power (LOOP) or Loss of Coolant Accidents (LOCAs), a Division 3 SX pump start signal is generated and the cross-tie valve [V] (1 SX01 4C) from the plant service water system closes. At this point the Division 3 SX pump would be providing cooling water flow from the lake to the Division 3 SX cooling loads.
Divisions 1 and 2 safety-related equipment are fully capable of mitigating the consequences of an accident and were available during the period of this event.
The failure of the Division 3 Shutdown Service Water Pump results in loss of Division 3 Emergency Diesel Generator safety function and a loss of the High Pressure Core Spray System safety function.
E. CORRECTIVE ACTIONS
A new pump was installed and post maintenance testing was completed with acceptable results on 9/21/14.
The Division 3 SX system, including the Division 3 EDG and HPCS were declared operable at 17:42 hours on 9/21/14.
F. PREVIOUS SIMILAR OCCURRENCES In 1990, during an attempt to start 1 SX01 PC for a quarterly pump operability surveillance, the pump motor energized but the pump did not turn and subsequently tripped. The pump was disassembled, cleaned and reassembled. The bearing enclosure tube and bearing flush water piping were found to be filled with silt which was determined to be the failure cause. Corrective actions included running the pump more frequently and monitoring coast down time. Also a modification was developed to provide a clean source of bearing flush water or a pump that does not require bearing flush water (similar to the Divisions 1 and 2 SX pumps).
In 1995, due to a decrease in the pump coast down time, the pump was disassembled and excessive amounts of silt were found in the bearing enclosure tube and bearing flush water piping. No damage was observed at that time. The pump was cleaned and reassembled as a redesigned pump using a modification kit provided by the pump supplier. The kit contained all the parts necessary to eliminate the bearing enclosure tube, change the bearings to a bronze design and eliminate the bearing flush water piping. The pump was re-assembled under the supervision of a vendor representative. A protective Belzona coating was applied to the pump and some repairs were performed using Belzona 'R' metal. This is the pump design that was in place at the time of the recent pump failure.
G. COMPONENT FAILURE DATA
The Division 3 SX pump is a Sulzer model 8X1 4A VCM pump with a Siemens-Allis type RGV motor. The pump is a vertical two-stage deep well pump that consists of a discharge head, six columns and a bowl assembly to extend 30 feet below the floor elevation. The pump is driven by a 75 horsepower, 1800 RPM 480 volt motor.