05000280/LER-1998-011, Forwards LER 98-011-00,per 10CFR50.73.Commitments Made in Ltr,Encl
| ML18152B618 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/06/1998 |
| From: | Grecheck E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18152B617 | List: |
| References | |
| 98-667, NUDOCS 9811160006 | |
| Download: ML18152B618 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2801998011R00 - NRC Website | |
text
e November 06, 1998 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Dear Sirs:
10CFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 Serial No.:
98-667 SPS: BAG Docket No.: 50-280 50-281 License No.: DPR-32 DPR-37 Pursuant to 1 OCFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.
Report No. 50-280,*50-281/1998-011-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.
Enclosure 9811160006 981106 PDR ADOCK 05000280 S
PDR Very truly yours, E. S. Grecheck Site Vice President
~-
I
Commitments contained in this letter:
- 1.
An ACE has been initiated to determine the cause of the failure of the overspeed.
trip device. Recommendations from the RCE will be implemented when the evaluation is complete.
cc:
U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRG Senior Resident Inspector Surry Power Station
e e
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 EXPIRES 06/30/2001 (6-1998)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER 121 PAGE/31 SURRY POWER STATION, Unit 1 05000- 280 1 OF 4 TITLE (4)
Inoperable Fire Pump Due to Faulty Overspeed Device Results in TS Violation EVENT DATE (5)
LER NUMBER 6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED 8)
FACILITY NAME DOCKET NUMBER I
SEQUENTIAL REVISION Surry Unit 2 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR 05000 -- 281 FACILITY NAME DOCKET NUMBER 10 08 1998 1998 -
011 --
00 11 06 1998 ni:-nnn OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR !i: (Check one or more) (11)
MODE (9)
N 20.2201(b) 20.2203(a)(2)(v)
X 50.73(a)(2)(i)
- 50. 73(a)(2)(viii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2Hiil 50.73(a\\(2)(x)
LEVEL 10 91%
20.2203(aH2Hil 20.2203(aH3Hiil 50.73(aH2Hiii) 73.71 t
20.2203(a)(2)(ii) 20.2203(a)(4)
- 50. 73(a)(2)(iv)
OTHER 20.2203(a)(2)(iii) 50.36(c)(1)
- 50. 73(a)(2)(v)
Specify in Abstract below or 20.2203(aH2Hivl 50.36(c)(2)
- 50. 73(a)(2)(viil in NRG Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
E. S. Grecheck, Site Vice President (757) 365-2000 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
COMPONENT REPORTABLE l~!i REPORTABLE
CAUSE
SYSTEM MANUFACTURER TO EPIX
CAUSE
SYSTEM COMPONENT MANUFACTURER TO EPIX X
KP Pumo Peerless Pumos y
It!~
t~
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR jYES Ix SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE).
NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On October 8, 1998, with Unit 1 at 91.5% and Unit 2 at 100% reactor power, the diesel driven fire pump failed to start during the performance of its monthly operability test.
The pump was declared inoper~ble and a 7 day Technical Specification {TS) action statement was entered. An evaluation determined that the diesel overspeed trip device had actuated when it failed during the shutdown evolution of the previous operability test. This actuation did not result in an alarm or an indication of an overspeed trip when the diesel was secured. The overspeed trip device was replaced and following satisfactory completion of the operability test, the pump was returned to service. Procedures were modified to verify that the overspeed device is not tripped following a diesel shutdown. A root cause evaluation was initiated to determine the cause of the overspeed trip device failure.
No conditions adverse to safety resulted from this event. The pump was determined to be inoperable greater than the allowable TS action statement resulting in a violation of TS 3.21.B.2.a.1. Therefore, this event is being reported pursuant to 1 OCFR50.73(a)(2)(i)(B).
9811160006 981106 PDR ADOCK 05000280 S
PDR NRC FORM 366 (6-1998)
- U (6-1998) e FACILITY NAME (1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION D0CKET(2)
SURRY POWER STATION, Unit 1 05000 -- 280 TEXT (If more space is required, use additional copies of NRG Fann 366A) (17) 1.0 DESCRIPTION OF THE EVENT e
U.S. NUCLEAR REGULATORY COMMISSION LER NUMBER 6)
PAGE (3)
I SEQUENTIAL REVISION YEAR NUMBER NUMBER 1998 -
011 01 2
OF 4 On October 8, 1998, the monthly surveillance test O-OPT-FP-009, Diesel Driven Fire Protection Water Pump 1-FP-P-2, was conducted to demonstrate operability of the diesel driven fire pump [EIIS-KP-P]. After initiation of the diesel auto start, the engine turned over but failed to start. A Diesel Fire Pump Trouble annunciator was received in the Main Control Room and the overspeed light lit on the local control panel. After the fifth attempt by the diesel to start, the start failure light on the local control cabinet illuminated. The diesel driven fire pump was declared inoperable and a 7 day Technical Specification (TS) action statement was entered at 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br /> on October 8, 1998 to return the inoperable fire pump to service.
Upon investigation, it was determined that the overspeed trip device [EIIS-KP-P-12]
actuated prior to the initiation of the October 8, 1998 monthly surveillance test.
The activation did not result in an alarm or an indication of an overspeed trip condition during shutdown of the diesel. Engineering verified that when the diesel driven fire pump control switch is taken to the "OFF" position, the control circuit is de-energized. Therefore, if the overspeed trip device actuated after the switch is taken to the "OFF" position, no alarm signal would be generated.
- The overspeed trip device was determined to be faulty and was replaced. The diesel driven fire pump was tested and the overspeed trip device was verified not to be actuated. The pump was declared operable and the 7 day TS action statement was exited at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> on October 10, 1998.
A review of the surveillance test procedure indicated that after verifying the operability of the diesel driven fire pump, the diesel is shutdown manually by placing the control switch in the "OFF" position. During the previously completed operability test, the overspeed trip device was presumed to have failed during the shutdown procedure and an alarm or indication of an overspeed trip did not occur due to the method of shutdown. The last operability test was performed on September 22, 1998. The diesel was not operated until the start failure on October 8, 1998. It was concluded that the diesel_ driven fire pump was inoperable from September 22, 1998 until the overspeed device was repaired and the pump returned to service on October 1 O, 1998. The inoperability of the diesel driven fire pump for more than 7 days is a violation of TS 3.21.8.2.a.1 and is therefore being reported pursuant to 1 OCFR50.73(a)(2)(i)(B).
.. (6-1998)
- - LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION,
U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)
DOCKET (2)
LEA NUMBER (6)
PAGE (3)
'YEAR I SEQUENTIAL I REVISION NUMBER NUMBER SURRY POWER STATION, Unit 1 05000 -- 280 1998 -
011 01 3
OF 4 TEXT (If more space is required, use additional copies of NRG Form 366A) (17) 2.0
SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS
The water suppression fire protection system consists of two fire pumps each with an independent power supply and each capable of supplying the demand needed. An electric motor driven fire pump, powered from the normal station electrical system, will start first to maintain fire water pressure.. If required, the diesel driven fire pump will operate as a backup and will start automatically.to maintain fire water pressure. The diesel driven pump will also automatically start upon loss of ac control power.
During this event, the diesel driven fire pump was considered inoperable for 18 days, exceeding the 7 day TS action statement for an inoperable fire pump. If a loss of ac power to the electric driven fire pump occurred during this event, the diesel driven fire pump would not have automatically started and performed its designed safety function.. However,*during the period when the diesel driven fire pump was inoperable, the electric driven fire pump remained operable and no loss of ac power occurred. Therefore, this event did not result in conditions adverse to nuclear safety.
3.0
CAUSE
_The most probable cause of the event was a faulty overspeed trip device that actuated during a previous shutdown of the diesel. The method used to secure the diesel contributed to the failure to detect the overspeed condition that existed after the shutdown.
After the diesel driven fire pump was verified operable, the test procedure directed the Operator to place the main control switch in the "OFF" position. The trip of the overspeed device was presumed to occur while the switch was in this position, and because the control circuit is de-energized, no alarm signal was generated.
A root cause evaluation (RCE) was initiated to determine the cause of the overspeed trip device failure.
4.0 IMMEDIATE CORRECTIVE ACTION(S)
The diesel driven fire pump was declared inoperable and a 7 day TS action statement was entered at 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br /> on October 8, 1998. A station deviation report was submitted.
~
e i U.S. NUCLEAR REGULATORY COMMISSION 11 (6-1998)
FACILITY NAME (1)
LICENSEE EVENT REPORT (LEA)
TEXT CONTINUATION D0CKET(2)
SURRY POWER STATION, Unit 1 05000 -- 280 TEXT (If more space is required, use additional copies of NRG Form 366A) (17)
5.0 ADDITIONAL CORRECTIVE ACTIONS
LEA NUMBER 6)
PAGE (3)
I SEQUENTIAL REVISION YEAR NUMBER NUMBER 1998 -
011 01 4
OF 4 The overspeed trip device was determined to be faulty and was replaced. The diesel driven fire pump was tested and the new overspeed trip device was verified not to be actuated.
The pump was declared operable and the 7 day TS action statement was exited at 221 O hours on October 10, 1998.
Procedures used to test and operate the diesel driven fire pump were revised. to verify the status of the overspeed trip device prior to placing the main control switch to "AUTO".
An RCE has b~en initiated to determine the cause of the failure of the overspeed trip device.
6.0 ACTIONS TO PREVENT RECURRENCE*
Recommendations from the RCE will be implemented when the evaluation is complete.
7.0 SIMILAR EVENTS
None