ML20028H784: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 24: Line 24:
Respectfully, COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION r
Respectfully, COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION r
: f. A W %,r(}e          n R. L. Bax Station Manager RLB/MJB/jmt Enclosure cc: R. Stols T. T=f.or INPO Records Center NRC Region III 9101300054 910123                                            a PDR        ADOCK 05000254                                    A S
: f. A W %,r(}e          n R. L. Bax Station Manager RLB/MJB/jmt Enclosure cc: R. Stols T. T=f.or INPO Records Center NRC Region III 9101300054 910123                                            a PDR        ADOCK 05000254                                    A S
[[90 ('; Qrg  3290H                                                                          l
((90 ('; Qrg  3290H                                                                          l


i LICENSEE EVENT REPORT (LER)
i LICENSEE EVENT REPORT (LER)

Latest revision as of 05:23, 15 March 2020

LER 90-032-00:on 901224,1/2A Diesel Fire Pump Taken out-of- Svc on 901217 & Not Returned to Svc Before Seven Day Time Allotment Expired.Caused by Mgt Deficiency.Fire Pump Successfully Tested & Returned to svc.W/910123 Ltr
ML20028H784
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 01/23/1991
From: Bax R, Smith E
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-032, LER-90-32, RLB-91-15, NUDOCS 9101300054
Download: ML20028H784 (5)


Text

s C:mm:nw alth Edis:n

, ouad Cities Nuclear Power Station 22710 206 Avense North Cordova, Ithnots 61242 9740 Telephone 309/654 2241 RLB-91-15 January 23, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER)90-032, Revision 00, for Quad Cities Nuclear Power C+ation.

This report is submitted in accordance with station Technical Specifications 3.12.B,2 and 6.3.A.1; with inoperable fire pumps, restore the equipment to operable status within 7 days, or prepare and submit a report to the Commission pursuant to 10CFR50.73 within the next 30 days outlining the plans and procedures to be used for the loss of redundancy in the system.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION r

f. A W %,r(}e n R. L. Bax Station Manager RLB/MJB/jmt Enclosure cc: R. Stols T. T=f.or INPO Records Center NRC Region III 9101300054 910123 a PDR ADOCK 05000254 A S

((90 ('; Qrg 3290H l

i LICENSEE EVENT REPORT (LER)

, , F Rs 24 Facility Name (1) Docket Number (2) Pace (3)

Quad, Cities unit one of El 01 01 01 21 51 4 1 !of!0 l4 Title (4) 1#A Diesel Fire Pump _Qgt._gt,_.1grvice GrgAler Than 7 DJys for Personnel Protection to Perf orrn Insp_qction Event 03te (5) LER NU'!! bat ML) Repart Date (7) Other Facilities Involved (8)

Month Day Year Year // Sequential j/ //jj Revision Month Day Year Facility Names _DE).gt Number f s )

,/j

//

/, Nutgr /Rh mugr Quad Cities 01 El 01 01 01 21 61 5

~ ~

J2 21 4 91 0 91 0 013 12 010 011 21 3 91 1 01 51 01 01 01 I l THIS REPORT !$ $UBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR DPWW Gbn k one or more of the followino) (11) 1 20.402(b) _ 20.405(c) _ _ , 50.73(a)(2)(1v) _ 73.71(b)

POWER __ 20.405(a)(1)(1) 50.36(c)(1) _, 50.73(a)(2)(v) _ 73.71(c)

LEVEL _ _ _ 20.405(a)( 1)( t i) 50.36(c)(2) _ 50.73(a)(2)(vti) 1 Other (Specify (101 0 ! d0 _ 20.405(a)(1)(iii) _ 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) in Abstract

- 2 * "*"'"'" - 5 "" * " 2 " " ) - 5 ""*"2nvinno eeio,and in (Offffffff'GHfffffffffff WoNe,HHHHHHH 20.40naninvi _ 50.73(a)(2)(iiii ._ 50.73(a>(2)(-) Text)

LICENSEE CONTACT FOR THIS LER (121 . . , , , _

Name TELEPHONE NUMBER AREA CODE E. Havden Smith. Technical Staff Ext. 2156 3 10 l 9 615141-l2121411 COMPLETE ONE LINE FQR EACH COMP FAILURE DESCRIBED IN THIS RE80RT (13)

CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS .

TURER TO NPROS I I 1 l l i I I I I l l 1 l l l 1 1 I I I i i i I i l 1 1 SUPPLEMENTAL REPORT EXPECTED f14) Expected Month I Day i Year.

Submission l lyes flf ves. comalete EXPECTED sVBMISSTQ!LDATE) X l NO l l I ABSTRACT (Limit to 1400 spaces, i.e. approximately fifteen single-space typewritten lines) (16)

ABSTRACT:

At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on December 24, 1990, Unit One was in the SHUTOOWN mode at 0 percent

' of rated core thermal power and Unit Two was in the RUN mode at 97 percent of rated core thermal power. At this time, the Technical Specification 3.12.B.2 seven day reporting criteria for an inoperable fire pump [P) [KP] was exceeded. The 1/2A Diesel Fire Pump had been taken out-of-service (00S) on December 17, 1990 for personnel protection so an inspection of the Unit 1 Circulating Water Pump [P]

, intake bay could be performed. The inspection had been completed but the fire pump l was not returned to service before the seven day time allotment had expired.

The 1/2A Olesel Fire Pump was successfully tested and returned to service on December 24, 1990, at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />. Corrective actions will include a revision to 005 4100-07 and including any out-of-service diesel fire pump on the Plan of the Day.

This report is being submitted to comply with station Technical Specifications 3.12.B.2 and 6.3.A.1, i

l 3244H

LICENSEE EVENT' REPORT fLER) TEXT RONT QUM,1(N ' Farm Rev 2 4 ,

FACit!?Y NAME (1) DOCKET NUMBER (2) LER NUMBER f6) Pace (3)

Year /// sequential // Revision

  1. p/p/j

/ Number

,///,/ , Number

_.0uadtitir.jnit'One '01 4

~

0151010 l 0121 El 4 9l 0 - 0 l3 12 - 01 0 01 2 0F

TEXT Energy Industry. Identification system (E!!s) codes are identified in the text as (xx]

PLANT ~AND SYSTEM IDENTIFICATION:

General Electric - Bolling Hater Reactor - 2511 MHt rated core thermal power.

EVENT-IDENTIFICATION: 1/2A Diesel Fire' Pump Out of Service Greater Than 7. Days for ,

Personnel Protection to Perform Inspection.

A :. CONDITIONS PRIOR TO EVENT:

Unit: .One .

Event Date: December 24, 1990 Event Time: 1000 Reactor Mode: 1 Mode Name: SHUTDOHN Power Level: 0%

This report was initiated by Deviation Report D-4-1-90-147 SHUTDOHN Mode-(1) - In this position, a reactor scram is initiated power to the control rod drives is removed, and the reactor protection trip syrtems have been deenergized for 10 seconds prior to permissive for manual reset.

LB. DESCRIPTION OF EVENT:

At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on December 24, 1990, Unit One was in the SHUTDOHN mode at 0 percent of rated core thermal power. Unit Two was in the RUN mode at 97 perce.it of rated.

core thermal power. At this t_ime, the Technical Specification 3.12.8.2 seven day-

' reporting criteria _for an inoperable fire pump [P] (KP] was exceeded. -The~l/2A:

Diesel: Fire Pump had'been taken out-of-service (OOS) on_ December =17, 1990, for personnel protection so-an inspection of the Unit 1 Circulating Hater (P) intake

. bay-could be performed under work requests Q80215 and 088711. The 1/2A Diesel ~ Fire '

Pump takes suction from this bay. QOS 4100-07, Single Fire Pump / Hater Supply Outage Report, was initiated. 3 Technical-Specification 3.12.B.2. states that with inoperable fire pumps or associated water supply, restore the inoperable equipment to operable status within seven days or prepare and submit a report to the: commission pursuant to Specification 6.3.A.1. within the next 30 days outlining the plans and procedures to-be used-to provide.for=the loss of-' redundancy in this system.

The 1/2A Diesel Fire Pump was successfully tested by completing Q05 4100-1,- Monthly Diesel Fire Pump Test, and returned to service on December 24,'1990, at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />.

The 1/2B Diesel Fire Pump was operable during the time that the 1/2A Diesel Fire Pump was out-of-service (00S).

C. APPARENT CAUSE OF EVENT:

This report.is being submitted to comply with the requirements of Technical

- Specification 3.12.B.2. which references Technical Specification 6.3.A.l.

Technical Specification 6.3.A.l. requires that the commission shall be notified and a report submitted pursuant to the requirements of 10CFR 50.73.

3244H

6 LIG.Qiil [VINi F[POE(LEP1 TIxf ffl%ILEAIIDN F0trr R@y._ld_

FAc!LITY NAME (1) DOCKET NUMBER (2) JiLEutiillR (6) ... Page f31 Year /// sequent 161 /j/j/ Revision

,,p/

// Numker j//

/ k JmktL.,

Duad Citics Unit one ol5 l o I LLL.LILsl 4 9Io -

o I 3 L2 -

o1 0 of 3 or el 4 TEXT Energy Industry Identification system (E!!s) codes are icentified in the text as [xxl The primary cause of this event is management deficiency. The inspection of the intake bay was completed with ample time to return the 1/2A Diesel Fire Pump to service.

The return to service following the work requests that involved the 005 of the diesel fire pumps was not given enough priority to ensure that the seven day time allotment was not exceeded.

D. SAFETY ANALYSIS OF EVENT:

The safety consequences of this event were minimal. Technical Specifications allow one of the two diesel fire pumps to be inoperable for seven days. If the time exceeds seven days, a report will be submitted to the NRC within the next 30 days outlining the plans and procedures to be used to govide for the loss of redundancy in the system.

During the time that the 1/2A Diesel Fire Pump was 00S, the 1/2B Diesel Fire Pump was operable. If the 1/2B Diesel Fire Pump had failed to operate, the service water [BI] crosstle would have been opened in accordance with station procedure 00A 4100-2, Fire Protection System Failure. The service water crosstle can be electrically opened from the 912-1 panel (PL) in the control room [NA] tc feed the fire protection water system, This system is capable of supplying adequate amounts of water to the fire system piping, but at a slightly lower pressure. This reduction in pressure would cause the sprinkler discharge pattern at a remote system to be reduced to a small extent. To provide the additional fire header pressure needed, the station has two backup diesel driven pumps, one of which is required by procedure to be tied into the designated fire main hydrant [HYD]. Each of these pumps is rated at 140 ps) which satisfies the most demanding fire system pressure requirement of 100 psi and satisfies the Technical Specification requirement for a cackup fire suppression system.

E. CORRECTIVE ACTIONS:

The immediate corrective action was to successfully test the 1/2A Diesel Fire Pump and return it to service by completing QOS 4100-1. This was completed on December 24, 1990, at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />.

Subsequent corrective action will be to revise 005 4100-07 to notify the Fire Marshal of a diesel fire pump being taken out of service. This will enable the Fire Marshal to notify the appropriate people of the importance of the required return to service. (NTS 2542009014701)

This event will be discussed with the personel involved with this 005 in order to stress the _lmportance of returning a diesel fire pump to service before exceeding the alloted time. Also, any out-of-service diesel fire pump will be treated as other Limiting Conditions for Operation (LCO) and will be tracked on the Plan of the Day (POD) to improve interdepartmental communication. (NTS 2542009014702)

F. PREVIOUS EVENTS:

I The previous events involving having one fire pump out of service for more than seven days were:

3244H

4 WIR$ff [ VENT REPMT f LER) VEXT CONTIH4AVIDN Form Rev RJL i

FAc!Li?Y hAME (1) DOCKET NUMBER (2) LER NUMBER f6) _ fage (3)

Year /,,/ /,

Sequential /,/p,/ Revision

/// Number /// Number-

_ Quad [ities Unit One 0 I$101010 121514 910 - 0 13 12 - 01 0 01 4 .0 F DW TEXT Energy Industry Identification System (EIIs) codes are identified in the text as [xx]

1. Deviation Report 4-1-87-099, 1/2A Diesel Fire Pump inoperable due to intake being emptied for maintenance activities, (LER 87-021).
2. Deviation Report 4-1-86-46, 1/2A Diesel Fire Pump inop greater than seven days to protect maintenance personnel while working on the trave'ing screens.
3. Deviation Report 4-1-85-97, 1/2B Diesel Fire Pump Outage of Greater Than Seven Days for pump overhaul.

Of the previous events, only Deviation Report 4-1-86-46 is similar in nature, therefore, there is no trend being established by this event.

G. COMPONENT FAILURE DATA:

There was no component failure involved in this event.

I l

l l

3344H