ML20084B435

RO Re Mods to Condenser Pump Room as Result of Flooding.All Equipment & Procedures Will Be Available & Enforced on & After 720711 Until Const of RHR Diesel Cooling Water Pump Vaults Completed

ML20084B435
Person / Time
Site:	Quad Cities
Issue date:	07/10/1972
From:	Butterfield L COMMONWEALTH EDISON CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084B161	List: IR 05000254/1972010 ML20084B159 ML20084B182 ML20084B191 ML20084B202 ML20084B211 ML20084B243 ML20084B415 ML20084B435 ML20084B442
References
NUDOCS 8304060440
Download: ML20084B435 (14)

Text

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(2I Commonwealth 3dison Company ONL FIRST NATIONAL PLAZA CHICAGO, ILLINCIS Addr.sa N.p, re.

f PO5T OFFICE 80s 747

• CHICACO, I L ilN O IS 60690

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a

?.y July 10, 1972 s

U[j f, ] '* <' -

N Mr. John F.

O' Leary, Director

' 'jI' Directorate of Licensing

/j.

jQ' U.S. Atomic Energy Cor.unission i

x.., - K \\ "

Wauhington, D.C.

20545

',( q, s

Subject:

Interim Report on Ccndenser Pump Room Modifications for Quad-Cities Unit 1 AEC Dkt 50-254

Dear Mr. O' Leary:

Attached is an Interim Report concerning the modifications to be made to the condensate pump roc.;a as a result of the flooding and subsequent evaluation conducted by your staff and Commonwealth Edison.

This report supple-monts our 10-day letter reporting the incident dated 7 une 14, 1972 and answers questions which resulted from the J

q June 30 meeting between the AEC staff and Commonwealth Edison.

A final report will be issued on this subject at the end of July.

If further information is required, please do not hesitate to call on us.

Very truly yours, M51M 6

L. D.

Butterfield, Jr.

Nuclear Licensing Administrator 8304060440 720901 PDR ADOCK 05000254 PDR i

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l Qund Citios Station Units 1 te 2 1

j Condensate Pump Room Flooding Report i

A

. Introduction l

The purpose of this report is to supplement our letter dated June 17, 1972 concerning this subject b'/ describing l

in noro detail correctivo action and ovaltmtions of plant safoty.

l Thoso details ucro roviouod with your staff in Bothosda j

June 30, 1972.

j j

These doccriptions includo details of the interim and J

final actions to isolato the condenser circulating unter system l

from the condensato pump room and intorin plans for assuring adoquate water is availablo for shutdown cooling in the ovent of condonsato pump room flooding from a failuro within tho

room, 4

i j

Isol_ntion of Circ ulatint.: Vater System from Condensate Pumn Room The arrangemont of the main condensor arcas, which contain tha circulating water sys tcm piping, and the condensate

{

pump rocna are shown on Sargent Ec Lundy's drauings M-6, H-8 and M-1;40, included in this report.

As described in our Jtmo 17, 1972 lottor, the following corrections havo bocn mado.

i 1.

The door to the condonsor hotwoll area has been j

scaled and mado water tight.

2.

Tuo 4' x 4' ventilation opening that connect j

tho area tuider the condensor with the condensato pump room have been scaled off with steel plato.

4 3

A levol alarm has boon installed under the condonsor that annunciatos in the control room.

The designs of the prosent sealed door and ventilation j

opening seals are shown on Figuros 1 through 5 of this report.

Both seals uill withstand combined sciemic and water loada due to a circulating water system failuro.

4 The reinforced concroto wall separating the condonsor area and tho pump room has previously boon analysed under soirmic loads and will maintain its intocrity.

This wall has boon further analysed for conditions of combined scionic and water load duo to a circulating water system failuro.

The i

wall is adoquate to withstand the combined loads and restrict leakago into the condcnsato pump room to less than the capacity i

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of the cump pteip cyo tons.

The dyurnic forecc en tho unll and scaln voro calculated accordinr; to United States Atocaic Pner~,y,

Corrainnion TJD-7024, Huclear Rcactors and JIrthenakca, Chapter u, Dynamic Prec o tu o on Fluid Containers.

A unter depth of 27' 6" uaed in the onalynia which corresponds to tho elevation of uan tho Hincincippi River at high level.

A Follouing are the final corrective noacures planned to precludo circu3n tinf unter entering the condenn ato ptrip rooma.

1.

Replace the existing noaled door uith a unter tight buli:ho nd door.

This door vill bo don 16 nod to uithstand com.binoa scinnic and unter loods.

Tho dolivery schedule for ch$ n door is four to six nonths.

The present soal uill bo maintained until this door in available.

2.

Tho procontly installed ventilation opening scals vill be maintainod as a permanent dosign.

3 A ny stem of level cultchen uill be inatt11cd under the condensor to indicatc and control flooding of the condoncor area.

The following suitchos aro planned.

_Lovel Function _

(1) 18-0" (1 Suitch)

Alarm, Pnl. 901-7 "Hi Water Condoncer Fit (2) 38-0" (1 Suitch)

Alam, Pnl. 901-7 "Hi Cire.

Water Cond. Fit (3) $'-0" (2 Suitc hos) Alar.n and Cire. Ue ter Pump Trip Loyol (1) indicates unter in the pit from either the condonsate/hotuell or circulating unter system.

Lovel (2) is above tho hotuell capacity and indicatos a probable circu3nting unter failuro.

Lovel (3) consis ts of 2 suitches.

Either of theco suitches vill alarm on pnl. 901-7 and tho actuation of both suitchec simultanco'.'cly vill trip a3'l operating circulating unter pumps on tho affected unit.

Tho system as describod consists of IIngnotrol level suitches and is ccmpletely testable during plant operatiorts.

It is not designed to IEEE Standards.

1.

!V,/

Installation of thoco alarna and trips will bo comploted by itu;;ust 1,1972.

It is our conclunion that both the precent and final isolation of tho condena cr arca and pttnp roan are adcquate to procludo flooding of the pump room via the circulating unter A

system.

hlternato Sourco of H'iR S totem tmd Diocol Gcnerator Coolinc Unter An doccribed to your staff June 30, 1972 in Bethecda, Maryland uc aro in the proccc.- of denicn and construction of unter tight Claca I vaulte to isolate the RHR service unter pu.up and diccol Lencrator coolin:, unter pttnps from all other equipment in the condensa te pttmp rooms.

This final correctivo action la expected to 'co completed by Hovcaber 1,19'/2.

During thic conc truc tion period, the follouing steps vill be tahon to assure that adoo,tato cooling uator is available for plant shutdoun.

1.

All items deceribed in the proceding acetion to procludo flooding from a circulatin;3 unter synten failure vill bo provided.

2.

In the hichly unlikely event the ptrap room ucro flooded by a failure of either the condencate, condensato transfer or clean deninaralized unter systcas, means for coolin.3 the IdiR heat cxchanr; ors and dicac1 end diccol gonoratorn uill bo provided.

To servo this func ti'on a 6" cronc connection has boon provided '.61ch can be readily inctalled on the service unter lino relicf valve flanco of Em heat exchanger 1B and 2A.

Thic connec tion allous uno of t uo 1012 servico unter ptr.ps on tho unaffected unit for shutdown cooling the affected unit.

In addition to this, the cross connection will have a l-inch noncle to sup/ ply cooling water using a iI -inch hose to the 1 2 diccel concrator in the tovent it is needed.

The dioscl generator cooling unter uill be connected into an existing 4" bolted flange connec tion.

Tho necessary 4" x o" reducers for the IUIR heat exchanger cnd the 4" flango to hose diesel generator cooling connection are at the si'to.

In addition to this, a back up supply of cooling untor is provided for the 1/2 dicac1 generator using one 2000 gpm diosol driven ptunp in series with one 1000 gpn diesel driven ptunp connect 3d through hocca to the 4" hoso connection on tha 1/2 dioscl generator cooling water system.

A second 2000 gpm dicsel driven pu:np is provided to -

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(g i

v supply cooling unter through hoacs to cither the Unit 1 or Unit 2 diccel gonarator cooline; unter cycton.

A cocond 1000 (;pa diccol pump will also be availablo on-site.

Thesc four (l.) diesel driven paapo uill be stored l

in the U-l reactor building traciniay alon;; with g

the hocen.

Fuel oil will be supplied to the portable diccola from the dicucl firo punp day tanks in the intake by cravity through hosos.

Figure 6 ic a nimplified sketch of the equipnent layout described above.

Thoco alternato cooling; sourecc vill cupply minimum coolinc, unter of 3500 cpm to the IUU1 system and 900 gpm to onc of the diecol t;cnc ra tors.

Station emercency operatinr; procedures will detail inctallation and oporat,lon of thone alternabe cooling syctens in addition to outlining chutdoun proceduros in the ovent of condensato pump room flooding.

All oquipment and proceduros will be available and enforced on and after July 11, 1972 until construction of the Rllit dional cooling uator pump vaults la completed.

It is our conclusion that adecuato provisions have bocn nado to ausure a cafo shutdoun and provido sufficient sepply of unter for cooling, purpouca in the ovent of condencate pu.,p room floodint; for any reason.

4 i

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~ tr: 72-117 <l .N June 17, 1972 C 3,, i " Mr. Edward J. Bloch, Acting Director Directorate of Licensinr U. S. Atomic Energy Cccmission Washington, D. C. 20545 Re ference : Licence DRP Quad Cities Nuclear Power Station Unit 1 - Appendix A Se ction 6. 6. A. 3 and 6. 6.B. 3

Dear ??r. Bloch:

l The purpose.of this let ter is to inform you of an abnormal occurrence on Unit 1 at Quad Cities Nuclear Power Station June 9, 1972, at 5: 05 p.m. This occurrence was reported by telegram on June 10, 1972. DESCRIPTIO!! OF I!! CIDE IT Due to problems experienced with the main condenser flow reversing valves drif ting out of position, a modification was approved to provide for mechanical blocking of these valves. .On June 9,1972 the condenser circulating water flow was to be reversed in order to move all 8 valves to the opposite position to connlete the modification. Af ter the pins had been removed from some of the valves it became necessary to start the hydraulic unit in order to move the valves which had drifted against several of the pins preventine their removal. The hydraulic system had recently been filled with clean oil, however, and thus required ventinr of the headers to remove entraoped air. As this air was i being vented by 1.oosening a hydraulic fitting, one of the 10 foot butterfly valves on the northeast water box ~sTah.med closed. Three circulating water pumps were in l ~ opeFation at the time with flow in the Torth direction. The shock from this rapid closure caused a rupture of. the rubber expansion j oint located about 16 feet above the valve at the bottom water box connection. River i water from the circulating water system bestan floodine the condensate pumn r_com_ in the3urbi_ne BuildinJ basement ~ l(El. 5r47')".~Th'e 'oasement eventually filled to a depth of 15 feet, 6 inches (El. 562'6") t 3 4 $"'I 6 0 p-Opo _3333 g() i

o a "r. E cis rt rd J. Bloch June 17, 1972 IF"EDI ATE CCRRECTIVE ACTION The men working in the condensate pump room evacuated the area 2nd reported the situation to the control room. The operator immediately shutdown all scinculat.inityater pumps which automatically closes the purpJscharve valves', ' T?is supply breaRiirs on all major electrical equipment in the area were racked out of service within about 6 minutes of the start of flooding. The Unit 1 circulating water discharge ' head works gates were also closed and the ice melting gate was opened to prevent backflow to the condenser and lower the discharge pool level. Representative samples were taken of the water in the basement prior to and during the pump out and the activity was found to be typical of river back-ground. Temporary pumos and hoses were set up within a few hours. One pump was lined up to skim the oil film from the surface and discharge to the oil. separator. The remaining pumps discharged direct'lv to the canal j ust below the weir and upstream of the composite canal sampler. Samples were also taken at least hourly throughout the discharge period. The station standard laboratory procedures were used to count these samples. The results are shown in Table 1. These samples con-firmed that the activity level remained at the river background level and well below the maximum allowable Technical Specification limit. for concentration in the discharge canal. DAMAGE ASSESSVENT AND REP AIR ST ATUS The following equipment was damaged as a result of the occurrence: 4 PHRS Service Water Pumps 2 Diesel-Generator Cooling Water. Pumps (#1 and 1/2) 4 Condensate - Condensate Booster Pumos Condensate Transfer Pumps Seismic Detector 4 Equipment and Floor Drain Sump Pumps Hvoochlorite S >c tem Analvter and Sample Puce Circulating water valve hydraulic power unit. a

o o "r. 9d mrd J. Bloch June 17, lo72 The 1/2 diesel, one condensate transfer pump, and seismic detector were returned to service prior to-the Unit 2 startup on June 12, 19 72. Instrumentation subjected to the flooding consists primarily of condensate system presuure gauges and transmitters. These inntruments are being cleaned and re-calibrated. All electrical T.otors, with the exception of one RHF service water pump were removed for drying and should be re-installed by June 16, 1972. The motors are being mergered in the shop..and again following installation of power cables. Operational testing and control checks will be completed prior to startup. Flow rate tests will also be conducted en the RHRS service water pumps. The estimated date for completion of repairs and testing is June 17, 1972. One MIR service water pump motor requires re-winding. Wiring for the motor is being flown in from Schenectady, New York to the' General Electric Comoany Service Shop in Chicago, where the coils will be wound. Installation in the motor will then be performed at the General Electric shop in the Quad-Cities.. All work is proceding on a 24 hour a day basis and it is esti-mated that this service water pump will be tested and returned to service on June 19, 1972. EVALUATION OF OCCURPSNCE AMD CORPECTIVE ACTION At the time of the occurrence the Unit 1 reactor was in the hot shutdown mode at 50 psig and 281 F., The reactor was in the eighth day of a7rahned maintenance oulage. The Residual Heat Removal System (RHRS) "as not required for decay heat and was not in service. The Unit 2 reactor was in the startup mode at 22 MWt holding 250 psir with a search for condenser air leakage in progress.- Immediately following the occurrence all control rods were inserted. Safety _r. elated systems rende~ red inoperable by the flooding consisted of the Nos. l and 1/2 diesel tenerators and the' Unit l'. containment cooling mode of the 9HR System. The occurrence was discussed with Fessrs. D. Honeycutt, and D. Boyd of Eegion III Compliance at the station on June 10, 1972. The samole records were reviewed along with the immediate and planned corrective action. It was concluded that no uncontrolled release of radio-aesivit; a3 made tc the environ ent as a result of fne occurrence. 'Y

O O Mr. Edward J. Bloch June 17, 1972 Corrective action being taken to prevent a repetition of the occurrence includes a new main-tenance procedure for venting the circulating water valve hydraulic system. This procedure requires that all butterfly valves will have their lock pins in l place prior to venting. Another new procedure has been written to crescribe operator action required during flooding of the condensate cumo room. The response to the occurrence by operators on shift with-out any procedure was deemed excellent by s tation management. The interim corrective measures to be performed i prior to Unit 1 startup are as follows: 1. The door to the condenser hotwell area will be sealed and made water tight. 2. Two 4' 1c 4' ventilation opening that connect the area under the condenser with the condensate pump room will be sealed off with steel plate'. 3 A level alarm will be installed under the condenser that will annunciate in the control room. I The two drain sumps located in the condensate pump room already contain high hiFh alarms which in-dicate abnormal water level in this room. These two. alarms annunciate in the control room. These interim corrective measures are also being installed on Unit 2 since it was shutdown for a scheduled outage on June 15, 1972. This work will be completed prior to the Unit 2 startup on June 17,. 1972. The final corrective measures to be performed during our next scheduled outage on each unit are as follows: 1. Replace the existing sealed door with a water 4 tight bulkhead door. 2. Extend the ventilation openings to a level that would. preclude flooding. 3 Install two alarms at different levels to indicate flooding under the. condenser. ,....x.. .-.. T' -

l o o Mr. Edward J. Bloch June 17, 1072 4. Inntall a very high level tria for the circulating water pumps, under the condenner. t i 5. Inventirate and install if feanible a steel guard bellown around each of the four existing rubber expansion j oint bellows. 6. One additional alarm will be inntalled in the condennate ouro room an a back un to the exintinh nu'mo oumo alaren. This' alarm will l also annunciate in the control room. Items 1 and 2 above will meet Class I seinmic criteria. Items 3 and 4 will meet the IEEE-279 criteria. The Station Review Board reviewed this occurrence and approved startup of each unit baned on the interim and final measures described above. Due to the unusual nature of this occurrence, the Station Review Board requested the Nuclear Peview Board (NEB) to review the occurrence and the corrective measuren. The NEB reviewed this occurrence on June 16 & 17, 1972 and concurred with the SPB action. A final report on this occurrence will be submitted within 30 days. Very truly yours, COMMONWE ALTH EDISON COMP ANY Quad Cities Nuclear Pcwer Station j - % %. 4 de.j /- F. A. Palmer Superintendent FAP/zm l

TABLE I Samplo Beta Activity Alpha Activity Change in Date Tim uci/ml uei/ml Water Lev. 1. 6/9 1750 5.0 x 10-3 2.5 x 10-9 0 ft. 2. t/9 1750 < l.3 x 10-10 1.3 x 10-Y 0 3. 6/9 1750 2.2 x 10-8 2.5 x 10-9 0 4. 6/9 1750 1.8 x 10-8 2.5 x 10-9 0 5. 6/9 1750 3 0 x 10-8 5.0 x 10-9 0 6. 6/9 1750 4.0 x 10-8 1.3 x 10-9 0 7. 6/10 c030 1.1 x IC-8 2 5 x 10-9 1 8. 6/10 0115 2 3 x 1C-8 < 1.3 x 1C-9 1.5 9. 6/10 C215 3.3 x 10-8 2.5 x 10-9 25

10. 6/10 0315 3.8 x 10-8 3.7 x 10-9 3.5

11. 6/10 0415 25x178 3.7 x 10-9 4.5

12. 6/10 0540 4.0 x 10-8 6.3 x 10-9 5.5

13. 6/10 0640 2.1 x 10-8 3.7 x 10-9 7.5

14. 6/10 0720 6.3 x 10-8 1.3 x 10-9 9.5

15. 6/10 0840 1.8 x 10-8

< 1.3 x 10-9 11.5

16. 6/10 0930 1.1 x 10-8

< 1.3.x 10-9 13.75

17. 6/10 1030 4.2 x 10-8

<1.3 x 10-9 14.75 Composite over entire 4.8 x 10-8 1.9 x 10-9 discharge period 4.4 x 10-8 1.9 x 10-9 NOTE: All gamma scans showed no significant photo peaks. 24 HCUR RIVER C0!&CSITE SAMPLES Sample Date Beta nei/ml Alpha uci/ml Inlet 6/9-6/10 8.1 x 10-9 2.5 x 10-9 Outlet 6/9-6/10 1.3 x 10-8 1.25 x 10-9 Inlet 6/10-6/11 3.4 x 10-8 3.1 x 10-9 Outlet 6/10-6/11 2.8 x 10-8 1.9 x 10-9 RADIATION SURVET (Log Book Entry) Date: 6/10 Ilme_: 1140 Location: Turb. Bldg. 547' RESULTS : < 1 mr/hr @ surface <100 cpn/ft2 smearable e &}}