Text

Submits Info Required for NRC Generic Rept on BWRs & in Response to NRC 790717 & 0727 Ltrs.Oversized Charts & Three Oversized Drawings Encl
	ML19276H069
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/07/1979
From:	Linder F; DAIRYLAND POWER COOPERATIVE
To:	Ziemann D; Office of Nuclear Reactor Regulation
References
	TASK-15-19, TASK-RR LAC-6486, NUDOCS 7909130245
	Download: ML19276H069 (69)
	v • d • e

DatIIt YLAND 1*0%'EIt C001*Elt.t TIVE Sa Groue, 0)hcornin 54601 September 7, 1979 In reply, please refer to LAC-6486 DOCKET No. 50-409 Director of Nuclear Reactor Regulation ATTN:

Mr. Dennis L.

Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 ADDITIONAL INFORMATION REQUIRED FOR NRC STAFF GENERIC REPORT ON BOILING WATER REACTORS

REFERENCES:

(1)

NRC Letter, Ziemann to Linder, Dated July 17, 1979.

(2)

NRC Letter, Ziemann to Linder, Dated July 27, 1979.

(3)

NRC Letter, Ziemann to Linder, Dated July 31, 1979.

Our response to Reference (1) as modified by Reference (3) is submitted as Enclosure (1) of this letter.

Our response to Reference (2) is submitted as Enclosure (2) of this letter.

Mr. Kane was contacted by the LACBWR Superintendent and acknowledged that submittal of this 3ponse on September 7,

1979, would be satisfactory.

If there are any further questions, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE i;tLL 5'

(fth Frank Linder, General Manager FL:FD: abs Enclosures 79 09130 $kyfif

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ENCLC20RE 1 - CONTAINMENT ISOLATION SYSTEM INro. NEEDED FOR C.I.S.

PENETRATTON NUM11ER M-15 M-19 M-13 M-12 S.D. Vent -

SYSTEM NAME (rapped)

Off Gas Station Air Control Air FTlTTD CONTATNEp Gases Air Air E.S.F. SYSTEM (YES/NO)

No No No 93-26-002 (I D)

ISOT ATION VAT,VE a 62-25-003 70-26-027 93-26-001 (OD) til-3 00-0 8 8 111-300-088 141-300-088 141-300-088 TTGITRE OR DRAh'TNG i:

Rev.O Pe. 1 i >e. 1 Pc, 1 Pc. 1 (Attachment H)

VATNE I,0 CATION (TD/ODI 10 TD ID.

0.D.

VAINE TYPE Auto check Checks yTNE OPERATTON Air PRIMARY ACTUATION Auto SECONDARY ACTI'AT10N Remote NORMAT, VAINE POS TT ION Sbut SliUTD0'4N VAINE POSITION Shur POST ACCIDENT VAINE POS TTT ON Shut POWER FA II,l'RE VATNE POSITTON Shut CONTAINMENT ISOI.ATION:

See PARAMETERS -

T.S. 3/il6-9 SET POINT -

See T.S.

3 / 11 6 - 9 VAINE CT.0SURE TIME None POWER SOIJRCE 125 v. DC VAI,VE IOS. INDICATOR (DIRECT /INDTRECT)

Indirect 21 -

1 ENCLOSURE 1 INro. NEEDED TOR C.T.S.

PENETRATTON NUMBER M-11 MR M-28 M-6 Reactor Cavity SYSTEM NAME Domin iho II. P.S.W.

Purce A ir M. Steam PLUID CONTAINED II20 Demin.

Water Air Steam E.S.F. SYSTEM (YES/NO)

Yes Yes No No ISOT.ATION VAT,VE =

G7-26-001 75-26-003

5-26-006 64-30-001 41-300-088 41-300-088 41-300-088 111-300-088 FIGURE OR DRAWING =

PR.1 Pe. 1 PC. 1 Pc. I VAT VE LOCATTON (ID/0D1 ID TD OD TD VALVE TYPE Check Check Check Plue-rock Hydraulic (H20)

_ VALVE OPERATION H\\'A - Auto <hur PRIMARY ACTITATTON Auto SECONDARY ACTUATION Manual n en NORMAL VALVE POSTTTON o

Sl!UTDOWN VALVE POSITION Shur POST ACCIDENT VALVE POSITION Shur POWER FAILURE VATNE POSITION Mbut CONTAINMENT ISOLATION:

PARAMETERS -

Groun 1

<1,000 lb Stm/IM SET POINT -

<-12" Water Levt1

<19.5 in. lle.

VALVE CLOSimE TIME

< 10 S ec.

Reactor POWER SOURCE 125 v.

D.C.

VALVE 12 INDICATOR Indirect (OIRECT/TNDTRECT)

ENCLOSURE 1 TNTO. NEEDED "0R C.T.S.

,T'ENETRATTON NtMBER M-7 M-9 M-10 M-17 Component Component Decay ifeat SYSTEM NAME reedwater Cooline Cooling Removal Il 0 ll20 II20 II 0 2

2 rT,UTD CONTAINED E.S.F. SYSTEM (VES /NO)

Yes No No No TSOLATTON VATNE a 65-26-001 Closed Loop Closed Loop 56-25-001 41 - 3 0 t J -il 88 141-30U-088 41-300-088 41-300-088 FIGURE OR DRAh'ING =

Pe. 1 Pe. 1 l'c. 1 PC. 1 VAINE LOCATTON (TD/0D) 1D TD VATNE TYPE Check Globe VALVE OPERATION Air PRIMARY ACTI'ATTON Auto SECONDARY ACTUATTON Manual NORMAL VALVE POSITTON Shut SifUTP')h'N VAINE POSTTTON Shur POST ACCIDENT VAINE POSITION Shur POhTR I AILi'RE VATNE POSITTON Shur CONTAINMENT ISOLATION:

PARAMETERS -

Group 2 SET POINT -

-12" Reactor II 0 Level 2

VALVE CLOSITE TIME

< 10 Sec.

P0h'ER SOURCE 120 v.(NI) AC VAINE M)S. INDICATOR (DIRECT / INDIRECT)

Indirect

_ 23 _

ENCLOSURE 1 INFO. NEEDED FOR C.T.S.

PENETRATTON NINRER M-18 M-26 M-26 M-22 lleating Steam Condensate SYSTEM NAME Seal Inject lleating Steam Return Waste Water (Non-Radioacti; e)

II 0 Steam iip 0 II20(Radioactive)

FLifTD r0NTAINED 2

C.S.r. SYSTEM (YES/NO)

No No No No ISOLATION VAINE =

2-26-039 73-26-00; 73-2;-021 511-2;-006 161-300-088 111-300-088 Ill-300-088 141-300-088 FIGITRE OR DRAWTNG =

Pu. 1 Pe. 1 Pg. 1 Pg. 1 VATNE LOCATTON (T D/0D)

T0 OD OD TD Diaphragm -

VATNE TYPE Check Check Globe Globe VATNE OPERATION Air Air PRTMARY ACTI'ATTON Auto Auto SECONDARY ACTI'ATTnN None Manual NORMAL VALVE POSITTON Open Open SillTFDOWN VAINE POSITION Open Open/ Closed POST ACCIDENT VAINE POSITION Shur Shur POWER FAILl'RE VALVE POSITTON Shur Shut CONTA!NMENT ISOLATION:

PARAMETERS -

Group 5 Group ;

SET POINT -

>5 psig

> 5 psig (Containment)

VAINE CLOSURE TIME

< 10 Sec.

< 10 S ee.

125 v.

DC (Reactor Pl.)

POWER SOURCE 125 v. DC 115 v. AC (Gen. Plant)

Rx MCC IB VALVE IUS. INDTCAf0R (DTRECT/TNDTRECT)

Indirect Indirect ENCLOSURE 1 INFO. NEEDED FOR C.I.S.

PENETRATION NITMBER M-25 M-27 M-23 M-29 Off Gas SYSTEM NAME Waste Water Waste Water Resin Sluice Vent - Chimney (Hadioactive)

(hadioactive)

(Radioactive)

(Radioactive) 11 0 Resin - 11 0 Gas II 0 2

2 FLUID CONTAINED 2

E.S.F. SYSTEM (YES/NO)

No No No No I S OLAT T ON VA T."E =

514-25-006 514-25-006 Su-26-006 55-25-003 111-300-088 111-300-088 111-300-088 111-300-088 FIGURE OR DRAWING =

Pg. 1 Pg. 1 Pt. 1 PC. 1 VATNE LOCATION (1D/0D1 ID TD OD ID Diaphragm -

Diaphragm -

VAINE TYPE Globe Globe Check Globe VAINE OPERATION Air Air Air PRIMARY ACTI'ATION Auto Auto Auto SECONDARY ACTI'ATION Manual Manual Manual NORMAL VALVE POSITTON Open Open Shur SlII.'TDOWN VAINE POSITTON Open/ Closed Open/ Closed Shur POST ACCIDENT VAINE POSITION Shur Shut Shut PONER FA ILURE VAINE POSTTION Shur Shut Shur CONTAI NMENT ISOLATION:

PA RAMETERS -

Group 5 Group 5 Group li (Containment)

SET POINT -

> 5 psig

>1325 psig (Rx)

VALVE CLOSURE TIME

< 10 Sec.

< 10 S ec.

POWER SOURCE 115 v. AC 115 v. AC 120 v. (NI) AC kx MCC IB Rx MCC IB VAINE 10S. INDICATOR (DIRECT / INDIRECT)

Indirect Indirect Indirect ENCLOSURE 1 INFO. NEEDED TOR C.I.S.

PENETRATTON NifMilER 1A M-334 M-32 M-36 Aux. Core SD Condenser Spray Steam -

SYSTEM NAME II. P. S.W.

Atmosph.

Vacuum Relief Vacuum Relief FT,17ID CONTA INED

!!20 Steam Air Air E.S. P. SYSTEM (YES/NO)

Yes No No No 38-26-001 TSot.ATION VALVE m 38-26-002 N/A 37-27 001 37-27 002 til-300-088 141-300-088 fil-300-088 111-300-088 FIG 11RE OR DRAWTNG =

Pe. 2 Pg. 2 Pg. 2 Pg. 2 VALVE LOCATTON (TD/0D)

ID (both)

ID ID VATNE TYPE Check Globe Globe VATNE OPERATION Mechanical Mechanical PRTMARY ACTITATION Self Self SECONDARY ACTUATION None None NORMAL VAINE POS TTTON Shur Shur SHUTDOWN VAINE POSITION Shur Shur POST ACCIDENT VAINE POS TTION Shur Shur POWER FA TLliRE VALVE POSITTON Shur Shur CONTAINMENT ISOLATION:

Positive Conta inment Pressure PARAMETERS -

t. Inside to Outside Pressure SET POINT -

.2 in. ifG.

g iull Open to 33 Stcrt at.; in. HG VALVE CLOStrRE TTME None None POWER SOURCE None None VALVE 11)S. INDICATOR (DIRECT / INT)IRECT)

None None ENCLOSURE 1 INFO. NEEDED FOR C.I.S.

PENETRATION NITMBER M-31 M-21 M-33 1-A Ventilation Ext. for Ventilation Exhaust Control of Cont. Bldg.

SYSTEM NAME Supply Damper Cont. Spray Drain Suction ELUID CONTAINED Air Air N/A II20 E.S.P. SYSTEM (YES /NO)

No No No 73-25-001 73-25-005 38-23-009 ISOLATION VAINE =

73-2;-002 73-2;-006 38-23-010 til-3 00-08 8 141-300-088 161-300-088 FIGliRC OR DRAWTNG :s Pg. 2 Pg. 2 Pc. 2 VALVE LOCATION (T D/OD)

ID ID OD Hut terfly Butterfly VAINE TYPE 20" Damper 20" Damper Care VATNE OPERATTON Air Air Manual PRTMARY ACTI'ATION Auto Auto Manual SECONDARY ACTUATION Manual Manual Manual NORMAL VAINE POSITION Open Open Shur SIIUTDOWN VATAT POSITION Open Open Shut POST ACCIDENT VAINE POSITION Shut Shut Shut POWER FA ILIPE VATAT POS TTION Shut Shur N/A CONTAINMENT ISOLATION:

PARAMETERS -

Group 3 Group 3 Nono

> 1325 Rx psig

> 1325 R'x psig SET POINT -

> 5 lb. Cont.r6 > 5 lb. Cont. ps

g None

> lli cont. Actid >lli cont. Activi

.y VAIAT CLOSimE TDIE

< 10 S ec.

< 10 Sec.

Nono POWER SOIPCE 120 v.(NI) AC 120 v. (NI) AC None VAINE IUS. INDICATOR (DIRECT / INDIRECT)

Indirect Indirect None 27 -

INFO. NEEDED FOR C.T.S.

PENT.TRAT TON N11MBER M-30 M-281 M-20 M-15 SYSTEM NAME 1" Cap l';" Cap 1" Can 1" Cao FT.111D CONTAINED E. S. F. SYSTEM (YESA?01 ISOT.ATTON VAINE d TTGlill OR DRAWTNG =

VATNE I,0 CATION (ID/0D1 VATAT, TYPE VATNE OPERATTON PRIMARY ACTUATION SECONDARY ACTUATION NORMAL VAINE POSITTON SIIUTDOWN VALVE POSITTON POST ACCIDENT VATNE POSTTION POWER FAILURE VAINE POS TTT ON CONTAINMENT ISOLATION:

PARAMETERS -

SET POINT -

VATNE CT,0SURE TIME POWER SOURCE VALVE IY)S. INDICATOR (DIRECT / INDIRECT) l ENCLOSURE 1 INFO. NEEDED FOR C.I.S.

PENETRATION NINBER Pen IA M-1 fi M-lis Pen 2B Cont. Bldg.

Cont. Bldg.

1 sol. IIPSW Cont. Illdg.

Cont. Bldg.

Isol. IIPSW SYSTEM NAME Diesel Start I,evel (l")

Level ( 3/il")

Diesel Start Fr.itTD CONTAINED Air Water Air Air E.S.F. SYSTEM (YES/NO)

Yes Yes Yes Yes 37-28-001 37-28-008 ISOT.ATTON VAIAT

37-28-002 17 74-n10 37-28-003 37-2R-012 til-300-088 111-300-088 111-300-088 til-3 00-0 8 8 FIGITRE OR DRAWING d Pg. 2 PR. 2 PC. ?

Pe. 2 VATNE I,0 CATION (TD/0D)

OD OD OD OD VATNE TYPE Globe Globe clohe Globe VATAT, OPERATION Manual Manual Manual Manual PRTMARY ACTI'ATTON SECONDARY ACTUATION s,

v v

n en Onen NORMAL VATNE POSITTON Open Open o

Silt 1TDOWN VAINE POSITION Open Open POST ACCIDENT VATNE POSTTION Open Open s,

PohIR FAILURE VATNE POS TTT ON N/A N/A N/A N /A CONTAINMENT ISOLATION:

PARAMETERS -

None None None None SET POINT -

None None None None VATNE CLOSURE TIME None None None None POWER SOURCE None None None None VALVE POS. INDICATOR (DIRECT /TNDIRECT)

None None None None ENCLOSURE 1 I NI'O. NEEDED l'OR C, I.S.

PENETRATION NISTRER Main Airlock SYSTES1 NAME 1" Capped I'T.I'Ill ('ONTA IN1'.D E.9.P.

< YS TE'1 OT9 60) 1907.ATTON VATAT =

FIGl'RE OR DRAh'ING =

VATAT T,0CATTON (TD/0DI VATAT TYPE VATAT OPER AT TON PR INiiRY ACTI'ATTON SECONDARY ACTi'AT10N NOR\\ TAT, VATAT, POS TT TON Stil'TDOWN VATAT. POS ITTON POST ACCIDENT VA I AT. PO4 T T T ON IONER l'A IIER E VA TAT. POS T T ! ON CONTA1NMENT I SOI.AT ION :

PA RANETER 9 -

SET IV) TNT -

VAINE CT,091'RE T TMI:

PohTR sol'RCE VAI,VI: IUS. INDICATOR (DIRECT / INDIRECT)

ENCLOSURE 1 NRC ITEM:

II.

Discues the dceign requiremente for the containment isolation barriere regarding:

a.

The extent to chich the quality standarde and eeismic design claesification of the containment isolation provisione follou the recommendatione of Regulatory Guides 1.26, " Quality Group Claceifications and Standarde for Water, Steam, and Radioactive-Water-Containing Componente of Nuclear Pouer Plants," and 1. 29, " Seismic Design Classification";

b.

Assurance of the operability of valves and valve operatore in the containment atmosphere under normal plant operating conditione and postulated accident conditione.

Qualification of cloced eyetems inside and outside the c.

containment as isolation barriere; d.

Qualification cf a valve as an isolation barrier; c.

Required isolation valve closure times; f.

Mechanical and electrical redundancy to preclude common mode failures; g.

Primary and secondary modes of valve actuation.

DPC RESPONSE:

a. (1)

The following barriers are quality classified in accordance with the recommendations of Reg. Guide 1.26, however, all were classified subsequent to the plant design and construc-tion.

(a)

M-19 (b)

M-11 (c)

M-6, M-8 (d)

M-7 (e)

M-9, M-10 (f)

M-17 (g)

M-18 (h)

M-23 (i)

Penetration lA a.(2)

No containment barrier has a seismic classification.

ENCLOSURE 1 b.

All valves and their associated operators are designed and tested for operability and leakage on a routine basis under conditions simulating normal plant oparating conditions.

The following barriers are designed to function under postulated accident conditions:

(1) 62-25-003 on M-19 (2) 64-30-001 and 64-25-001 on M-6 (3) 56-25-001 and 62-25-017 on M-17 (4) 73-25-021 on M-26 (5) 54-25-006 on M-22, M-25 and M-27 (6) 55-25-003 on M-29 (7) 37-27-001 and 37-27-002 on M-32 and M-36 (8) 73-25-001 and 73-25-002 on M-31 (9) 73-25-005 and 73-25-006 on M-21, and in addition, all check valves.

c.

There are only two such systems:

the Component Cooling Water to and from containment i.s checked for containment atmosphere leak-age into the system regularly, and no leakage has ever been detected.

The other system:

Heating Steam and Heating Steam condensate is checked regularly - and has leaked prior to the in-sudlatien of an automatic isolation valve in the condensate return line, d.

As indicated in a. (1) above, no valve was required to be qualified by the plant design, however, every valve is leak tested regularly.

Leakage is measured and if excessive, the valve is immediately repaired or replaced.

e.

The following valves were designed for a limiting closure time.

They are tested regularly to meet or exceed this limit.

(1) 64-30-001

< 10 seconds (2) 73-25-001, -002, -005, -006

< 2 seconds f.

The.following penetrations have redundancy features:

(1)

M-12, two check valves in series.

(2)

M-6, valve 64-30-001 has redundant electrical closing signals from each of low steam header pressure, low reactor water level and low condenrer vacuum to two redundant closing solenoids from a stored energy hydraulic system capable of at least 3 complete cycles of operation.

Valve 64-25-001 has the same electrical signals to two other redundant closing solenoids to release air from the valve operator and allow spring closure.

ENCLOSURE 1 (3)

M-22, M-25 and M-27; valve 54-25-006 has a redundant electrical signal from two containment pressure switches to two solenoid valves to vent air from valve operator.

(4)

M-29, valve 55-25-003, has two electrical signals from each of two parameters to two solenoid valves to vent air from spring closing operator.

(5)

At penetration lA, two check valves in series.

(6)

M-31 and M-21 each has two valves in series, which have electrical signals from each of two parameters to two solenoids which vent air from spring closing operator.

(7)

At penetration lA, manual valves 38-23-009 and -010 are closed valves in series.

g.

The foDtwing valves have a secondary method of closure by manual air controller in control room:

(1)

M-19, 62-25-003 (2)

M-6, 64-30-001, 64-25-001 (3)

M-17, 56-25-001 (4)

M-31, 73-25-001, -002 (5)

M-21, 73-25-005, -006 The following valve has a push button closing station in the tunnel and in waste disposal building.

(1)

M-22, M-25, M-27, 54-25-006 The following are valves which have no automatic closing signals but may be closed remotely to provide a redundant containment barrier:

(1)

M-6, 64-25-030 (2)

M-7, 65-22-001 (3)

M-29, 55-25-004 33 -

ENCLOSURE 1 NRC ITEM:

III.

Discuss the provisions for detecting leakage from a remote manually controlled system (such as an engineered safety feature oysten or essential line) for the purpose of deter-nining Uhen to isolate the affected systen or system train.

Specify the parametere sensed, their set pcint, and procedure for initiation of containment isolation.

DPC RESPONSE:

The plant operating procedures specify that whenever a containment isolation valve closes (or is required to close) that the manual actuator will be operated to close and/or the remote manually operated valve will also be closed.

This procedure thereby uses all the required parameters at their normal setpoints.

NRC ITEM:

IV.

Discuss the design provisicne for testing the operability cf the isolation valvee.

DPC RESPONSE:

There is no one parameter that isolates containment.

1.

High containment building ressure of >- 5 psig closes the following penetrations:

]

(a)

M-26 (partial) by valve 73-25-021 (b)

M-22, M-25, M-27 by valve 54-25-006 (c)

M-29 by valve 55-25-003 (d)

M-31 by valves 73-25-002, -001 (e)

M-21 by valves 73-25-005, -006.

2.

High reactor vessel pressure of > 1325 psig closes the following penetrations:

(a)

M-29 by valve 55-25-003 (b)

M-31 by valves 73-25-002, -001 (c)

M-21 by valves 73-25-005, -006.

3.

High radiation levels of containment atmosphere by immediate j

particulate, delayed particulate, or gaseous closes the following penetrations:

(a)

M-31 by valves 73-25-002, -001 (b)

M-21 by valves 73-25-005, -006 1

1 i

] l 4

ENCLOSURE 1 4.

Low reactor vessel water level < 12 inches below nominal closes the following penetrations:

(a)

M-6 by valves 64-30-001 and 64-25-001 (b)

M-17 by valve 56-25-001 The operability of items under 1, 2 and 4 above are verified each refueling shutdown.

The operability of items under 3 above are verified every 2 weeks.

NRC ITEM:

V.

Identify the codes, standards, and guides applied in the design of the containment isolation system and system componento.

DPC RESPONSE:

The containment building was designed and constructed to the applicable requirements of the 1962 edition of the ASME Boiler and Pressure Vessel Code,Section VIII, Unfired Vessels, and appliccble code cases, per Allis-Chalmers (Sargent and Lundy) Specification 41-438.

Forgings conform to ASTM A350, LF1, and piping conforms to ASTM A333.

Containment vessel plates and reinforcements and their welded attach-ments, conform to the applicable requirements of ASTM A201 (" Standard Specification for Carbon-Silicon Steel Plates of Intermediate Tensile Ranges for Fusion-Welded Boilers and Other Pressure Vessels") for Grade B steel.

Plates also meet the applicable test requirements for ASTM A300

(" Standard Specification for Steel Plates for Pressure Vessels for Service at Low Temperatures").

The containment system is not a separate system operating independent of the other systems in the reactor plant; but rather it utilizes components, such as valves, detectors, and inerlocks, in other systems to complete its function of containment.

This dependence has two causes:

The conditions which require containment must be sensed in the appropriate systems and the resulting isolating action must be performed in the necessary systems which penetrate containment boundaries.

Therefore, the operation of the containment system con-sists of the operation of these devices in other systems.

The piping that penetrates the containment was designed and constructed to Allis-Chalmers (Sargent and Lundy) Specification 41-585.

The piping, including valves, conformed to the Power Piping Code ASA B31.1, and in addition met the requirements of modifications of this code as defined by the Nuclear "N" Code Cases in effect at that time.

35 -

ENCLOSURE 1 NRC ITEM:

VI.

Discuse the normat operating modes and containment isolation provision and procedures for linea that transfer potentially radioactive fluida out of the containment.

DPC RESPONSE:

The normal operating modes and containment icolation provisions and procedures of lines that contain or transfer potentially radioactive fluids out of containment are as follows:

1.

M Air-ejector vent from shutdown condenser.

This line is normally closed during reactor operation by valve 62-25-003.

Upon a signal for shutdown condenser operation (which coincides with one of the signals which isolate other containment pene-trations), the valve opens automatically, remains open for two minutes, then automatically closes.

Subsequent opening is accomplished under operational procedures.

2.

M Main Steam.

This line is norraally open during reactor operation.

Upon a signal from low reactor vessel water level, low steam line pressure or low main condenser vacuum, valves 64-30-001 and 64-25-001 close automatically and remain closed.

Subsequent opening is accomplished under operational procedures.

3.

M Feedwater.

This line is normally open during reactor operation.

This line is isolated by check valve 65-26-001, which prevents flow in the feedwater line from containment.

Backup valve 65-22-001, is pneumatically operated from the control room.

No signal is used to automatically isolate this line as there may be occasions where it may be undesirable to cut off feedwater flow and therefore it is controlled under operational procedures.

4.

M Decay Heat removal startup water to main condenser hotwell.

Valve 56-25-001 is normally closed, but valve 62-25-017 is normally open during reactor operation.

Valve 56-25-001 remains closed and/or closes automatically upon a low reactor vessel water level signal.

Valve 62-25-017 auto-matically closes when the shutdown condenser automatically operates and valve 62-25-017 automatically reopens when the shutdown condenser is removed from service.

5.

M Seal Injection Water.

This line is normally open during reactor operation. The line is isolated by check valve 52-26-039 which prevents flow from contaim..ent.

This line is essentially a 400 psig rated closed system back into the condensate deminer-alizers.

No remote operated backup valves exist, although other check valves exist in the line upstream.

ENCLOSURE 1 6.

M-22, M-25 and M Radioactive Waste Water Lines.

The lines are normally closed by manual valves 54-24-016, -017 and -018 as well as 54-25-006.

Valve 54-25-006 and one of the manual valves may be open when the reactor is operating for the duration of waste transfer.

Valve 54-25-006 is auto-matically closed on a high containment building pressure of 1 5 psig.

Subsequent opening of 54-25-006 is controlled by operational procedures.

7.

M Resin Sluice.

This line is normally closed during reactor operation by manual valves 54-24-020, -022, -036 and

-037.

One of the three lines to M-23 may be open when the reactor is operating for the duration of resin transfer.

Other valves in the system upstream are manually closed during the resin transfer operation.

8.

M Off-Gas Vent to Chimney.

This line is normally closed under operational procedures by manually operating valve 55-25-004 to close during reactor operation.

Additionally, there is an automatic diversion valve upstream of open valve 55-25-003 which is diverting vent header gases through the containment ventilation filter system during reactor operation.

The diversion valve opens to vent the line to the chimney when-ever the containment ventilation valves close; however, valve 55-25-004 remains closed until operational procedures causes its opening.

Valve 55-25-003 automatically closes on high reactor vessel pressure of 1 1325 psig or high containment pressure of 1 5 psig.

Valve 55-25-003 will reopen automatically upon removal of its closing signals.

9.

At Penetration lA - Auxiliary (Alternate Core Spray.

This line is normally closed by check valves 38-26-001 and -002.

They open only when the Alternate Core Spray pressure at the valves is higher than the water pressure in the reactor vessel.

10.

M Shutdown condenser Shell Side Steam.

This line is open during reactor operation.

The steam that would emanate from this line is from the shell side of a tube heat exchanger.

During reactor operation the tube on the reactor side of the heat exchanger is depressurized and at ambient temperature.

When the shutdown condenser becomes pressurized, due to loss of all other primary steam heat sinks, then a tube leak would con-taminate the shell side steam.

A radiation monitor and regular testing of the condenser is used to assure no tube leak during shutdown condenser operation.

11.

M-31 and M Containment Ventilation.

These lines are normally open passing approximately 5000 cfm of air during reactor operation through valves 73-25-001, -002, -005, and -006.

All valves automatically close upon either a high reactor vessel pressure of 1 1325 psig, high containment building pressure of 1 5 psig, or high airborne radioactivity in the containment exhaust air.

Operating procedures require that the valves control be operated to close upon any automatic actuation, and subsequent reopening is under operational procedures.

ENCLOSURE 1 12.

At Penetration lA - Containment Building Drain Suction.

This line is normally closed by manual valves 38-23-009 and -010 during reactor operation.

They are operated to open under operational procedures involving the containment building integrated leak test and as the line to remove radioactive water after the containment building has been flooded due to actuation of alternate core spray actuation after a major accident.

- 38

ATTACHMENTS TO ENCLOSURE 1 Attachment A LACBWR Operating Manual Volume II, Reactor Process Systems Pgs. 5-22, 5-23, 5-24; Dwg. No. 41-300-084 (Shutdown Condenser System Flow Diagram)

Attachment B LACBWR Operating Manual Volume II, Reactor Process Systems Pgs. 8-11; Dwg. No. 41-300-080 Attachment C LACBWR Operating Manual Volume V, Service System Pgs.

7-9, 17-17, 17-18; Dwg. No. 41-400-237 (Aux. Core Spray System Flow Diagram).

Attachment D LACBWR Operating Manual Volume II, Reactor Process Systems Pgs. 7-12, 7-13; Dwg. No. 41-300-083 (Decay Heat Removal Flow Diagram)

Attachment E LACBWR Operating Manual Volume II, Reactor Process Systems Fig. 15.2, Reactor Building Spray System Flow Diagram Attachment F LACBWR Operating Manual Volume III, Turbine Generator Systems Pgs. 10-17, 10-18, 10-19, 10-20, 10-21; Fig. 10.1, Main Condensate System, Dwg. No. C/LR-70.

Attachment G LACBWR Operating Manual Volume III, Turbine Generator Systems Pgs. 12-13, 12-14, 12-15; Fig. 12.3, Reactor Feed-water System, Dwg. No. b/LR-53.

ENCLOSURE 1 - ATTACHMENT A LACBWR Operating Manual Revised Volume II, Reactor Process Systems July 1979 SilUTDOWN CONDENSER SYSTEM VALVE CIIECKLIST VALVE NO.

NAME POSITION BASEMENT FLOOR 62-24-002 Condenser Condensate Outlet Valve 1A Isolation LO 62-23-032 Condenser Condensate Outlet Valve lA Dcwnstream 7

Drain C

i i + 62-2 3-0 40 Valve 62-24-002 Lanterr Gland Leakoff O

M g 62-24-014 Condenser Condensate Outlet Va lve 1A Air Supply O

f0H 62-23-005 Condenser condensate Sample C

m 62-23-006 Condenser Condensate Sanple Shutoff C

I;!

62-24-035 Condenser Condensate Outlet talve 1B Isolation LO h k 62-23-034 Cendenser Candensate Outlet Valve IB Isolation lil l

Valve Body Drain C

62-23-033 Condenser Condensate Outle t Valve 1B Dcwnstream jgI h Drain C

.C I ] 62-23-041 Valve 6 2-2 4-3 35 Lantern Gland Leakoff O

-?;

i 62-23-035 Ccndenser Condensate Outlet Valves lA and 1B f-Downstream Drain Shutoff C

Y' 62-24-040 Condenser Condensate Outlet Valve 1B Isir Supply 0

62-23-016 Condenser C mdensate

.7 : a : r O

J 62-23-017 Condense r C _ dens a tt.

>dr chatof f Control Valves O

t. '.,g.,6 2 - 2 5 - 0 0 2 Candenser C c ac-m a,

.lve 1A outlet Manual i!andwhee l LO 62-24-047 Hja-, Test C ar.e t i ~

C

- g 62-25-012 2 mdense r C ncensate Valve 13 Outlet *'anual

!!a r.dwhee 1 LO 1

k GRADE TLOCF 6

62-28-005 Fl"x Tr,ns t*

- !! gh !P 1 t:cn 0

' G2-28-006 r1 Tr ms-

.er Low rno'--

n O

62-24-046

, ou t l.; t sh;t fr Valve O

^

INTER"EDIATE l'LOOR A

62-23-022 Samole Co;ler 62-0i-001 Sample Outlet C

. k,-62-23-023 S,r.ple Coo le 03-001 S a m'n le Blowdown C

n

- S 62-23-021 Sanple Coole: 63-03-002 Sample Vent C

- - ~ 23-024 Sample Cooler 63-03-002 Sample Outlet C-62-23-0?5 Sample Cooler 63-01-002 Sample Blowdown C

62-24-041 Steam Line Trap Shutoff Valve O

62-24-042 Stean Line Trap St.utoff Valve O

62-24-043 Trap Inlet Isol

..or Valve O

3 62-24-044 Trap outlet Isolation valve O

r*

62-24-045 Trap Bypass Valve C

' d

- ~

ej F@*lD *D'Tll' f%M o

_ ll hi 52

LACBWR Cperat ing M-nua1 ite v i:.c a Volume II, lieactor Placess Syst ems July l'179 S!!UTDOWN CONDENSER SYSTEM VAld'P_ClirC1RIST (Con t '.i)

VALVE NO.

NAMM POSITION MAIN FLOOR iq 62-23-007 Condenser Tube-Side Drain

(

IN 62-23-008 Condencer Tube-Side Drain Shut of f C_

1% % 2-24-012 Condenser Shel1-S de Pra1n C- - ~ ~ ~ - -

62-23-048 Condenser Shell-Side D ra. n *:S ute t' f C

6.'-23-003 Condenser Shell-Ste.e sample chut.it :

C_

p

.i e

l' S!it'l'DOWN CONDEN.SE R _P_L__ATFORM

'l f.,

- 2 4 - 0 01 Condense: Stcam inlet va ve 1A 1.olation 1.0 6 62-24-029 Valve 62-24-001 Dypass C-

} 62-24-036 Condense r St eam Inlet Valve ! !'

l wlat : en IO

.i 6

62-24-037 Valve 62-24-036 liypass C- - - ~ " -

62-24-013 Condenser Ste.un Inlet Valve I It la y pa :-

c- - - ~

62-24-039 Condenser 4 tram inlot valve 1 14. ';'e t a t r Ai r :upply

-~

a b 2-2 4-0 30 CondenSol Steam Inlet Valve :A 0 et at er Ai r Wi ply 0

62 '4-016 Condenser 8 team In! t Valve 0

-t*ol Ai: Su ply 0 ~ ~ ~ ~

', 4 f 2 - 2 3- 0 01

3toam Inlet 7.i re ivint Drain C'--~~-~

_ ][, 7: 2.'3-002 Stean

't!"t 1.e w r. : nt Dr.i t -

hi.'.it*

C ~ ~ ~ ~ ~ ~

N 2

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M.

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LACBWR Operating Manual Revised Volume II, Reactor Process Systems July 1979 SilUTDOWN CONDENSER SYSTEM VALVE CliECKLIST - (Cont'd)

POSITION VALVE NO.

NAME SHUTDOWN CONDENSER PLATFORM - (Cont ' d) 62-24-013 Cont. Air Supply to Condenser Shell Side Level Controller O

Demineralized Water Supply Cont. Valve Inlet

, %y 62-24-006 Isolation LO j%

'(

62-24-007 Domineralized Water Supply Cont. Valve Outlet b

Isolation LO h

62-24-032 Demineralized Water Supply Control Valve Operator O

Q Air Supply 7

E 62-24-008 Demineralized Water Supply Cont. Valve Bypass C

s E

62-23-042 Condenser Demineralized Water Supply lii Pt. Vent C

0 62-24-009 H.P.

Service Water Supply Cont. Valve Inlet 5

is b

Isolation LO R-f 62-24-010 H.P.

Service Water Supply Cont. Valve Outlet

'?;

Isolation LO f

' 62-24-011 H.P.

Se r'. ice Wa te r Supp li Cont. Valve Bypass C

1 62-24-031 li. P. Service Wate: Supply Valve Operator Air Supply 0

2.

62-25-013 P.eactor Emergency Flooding Vent Valve 1A (Ibnd Jack)

LO

_f 62-25-014 Reactor Er.ergency Flooding Vent Valve 1B (Ifand Jack)

LO L 62-25-013 Reacto: Emergency Flooding Vent Valve 1A C

,2 9 2-25-014 Re.tctor Nergenc'; Placding Vent Valve 1B C

62-25-015 Der.nc: a'..rea Water Header Isolation In-Servi 62-25-004 Dem neta. :ed Water Inlet Ccntrol Valve In-Service 62-25-005 illah Pressure Service Water Inlet Control Valve In-Service CONTROL ROO".

l Centrol sw:tch for tives 62-23-002 and -012 (Shutdown

] Condenser Ccnd<.sa.e ' 2 tc Valves) in auto.

AUTO s Control switch fu 62-25-003 (Of f-Gas vent Automatic Valve)

AUTO

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RE.". ARES :

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ENCLOSURE 1 - ATTACHMENT B Revised J. e LACBVR Opera ting Manual Ju'.y 1979 Volume 11, Reactor Process Systems EMERGENCY CORE SPRAY SYSTEM VALVE CHECKLIST-Vafve No.

Name - -- -_ _. _ _ _ _

__. Quad.____Pos i t ion ~

2 INTERitEDIATE FLOOR 53-24-007 High Pressure Service Vater Control Valve 53-25-004 NV LO A

Inlet k

3-23-004 Instrument Air to Crankcase Blecdoff NW C

% oi; 3-24-008 H.P. Service Water Control Valve 53-25-004 Outlet NV LO Y 53-23-003 Instrument Air to Crankcase Bleedoff NW C

53-24-009 H.P. Service Water Control Valve 53-25-004 Bypass Nw LC NV C

53-23-002 H.P. Service Vater Tell-Talc Drain 5.k 53-24-010, Control Air Supply to Valve 53-25-004 la o

E A 53-24-002 Cor.t rol valves 53-25-002 and 53-25-008 Bypass NE LC SE LO 7

53-24-003 Pump 1A Suction SE LO b

53-24-004 Pump 10 Suction SE LO I"

53-24-005 Pump 1A Discharge SE LO j

53-24-006 Pump 10 Discharge A 53-24-012 Pump 1A Plunger Spray Supply Shutoff SE O

>j!

i 53-24-013 Pump 1B Plunger Spray Supply Shutoff SE O

~~

d 53-28-COI Core Spray Pu ps Suction Header Pressure Cauge Iso.

SE O

M 53-28-003 Pump I A Dis.narge Pressure Gouse Isolation SE O

I 53-28-002 P u.mp IB Discharge Pressure Gauge isolation SE O

,1 d

53-24-016 Pump 1A Crcnkcase Centrol Air Shutoff SE O

53-24-017 P uc p IB crankcase Control Air Shutoff SE O

SE C

E 53-24-015 Test

'l 53-28-004 Pump 1 A Crankcase Pressure Indicaticn Shutof f SE O

53-28-005 Pump 1B Crankcase Pressure Indication Shutoff SE O

SE C

E.

53-23-001 Drain to Rotention Tanks t

~

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C MlS;Q Core Spray Pumps Ocmincralized Water inlet 0

53-25-002 0

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53-25-004 Service Water to Emergency Core Spray Pumps C

0 1

53-25-008 Core Spray Pumps Deminerellred Water inlet Shutoff Y

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gq s F}. ; ' gag REACTOR CORE SPRAY

'$SFv7

'f

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Ti!!%WT PUMPS b;t.n s

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&s

,%s< nt im

.or w i

.g3rm, SEPARATION

W+M L3'?

rure.:,casta CHAMBER DRAINS

8 DRAIN TO

~

TO FLOOR DRAIN RETENTION TANKS SYSTEM a"* W ALLI3 - CM A LM E RS un. usa.mme. cease

a. mule d.90LGAS Pewee GWaafase ?

asumenes seesemersub sk e, LACBWP REACTOR PLANT CORE SPRAY SYSTEM m/.

J FLOW DIAGRAM

= = 4 l-300-080

"'"1

( ODF 9P9AV CV97F AA EI AW Of ACO A 44 I

ENCLOSURE 1 - ATTACHMENT C_

~

Revised

- LAC 3WR Operating Manual June 1979 Volume V, Service System m

TABLE 7-1

(%l

~ ~ ~ ~ '

_: _m; H.P. SERVICE WATER SYSTEM VALVE CHECKLIST NOmM =

START AND:

VALVE NO.

NAME LOCATION OPERATION 75-24-049 North Header Isolation Valve T.B. North LO 75-24-050 Fire Hydrant Isolation T.B. North 0

75-24-051 Fire Hydrant Isolation T.B. North O

75-24-052 Fire Hydrant Isolation T.B. North O

o 75-24-053 South Header Isolation Valve T.B. South LO y

75-24-054 Fire Hydrant Isolation T.B. South O

75-24-055 Fire Hydrant Isolation T.B. South O

8 75-24-067 IB Screen Wash Isolation Crib House O

E 75-24-068 1A Screen Wash Isolation Crib House O

75-28-036 Screen Wash 13 Pressure Switch Isolation Crib House O

75-28-037 Screen Wash 1A Pressure Switch Isolation Crib House O

g

'd NOTE:

Check Diesel Fire Pumps lined up according to Alternate Core Spray System, Volume II, Section 17.

a 3

TURBINE BUILDING A

f

==

75-24-034 HPSW Pump suction Grade O

4R 75-24-035 HPSW Pump Discharge Grade O

j q[

75-24-036 Spray Nozzle Supply Oil Storage Room Grade O

4 75-24-088 HPSW to Demineralized Water System Grade LC 75-23-026 HPSW to Demineralized Water System 3

Tell Tale Grade O

E 75-24-089 HPSW to Demineralized Water System Stop Grade C

75-24-037 H.P. Service Water Hose Connection Grade C

~

75-24-038 Fire Hose Connection Grade C

5

\\ 75-24-041 Spray Nozzle Supply Alternate Core fg}

Spray Valve Area Mezzanine O

i 75-24-044 H.P. Service Water Hose Ccnnection Grade C

n 9

75-24-045 Fire Hoce Connection Grade C

c j gg75-28-022 HPSW Pump Suction PI L-22 Isolation Grade O

75-28-023 HPSW Pump Discharge PI L-21 Isolation Grade O

p 75-28-024 HPSW Pump Discharge PS-12 and PT D-39 Isolation Grade O

j ~d 75-28-025 HPSW Pump Discharge PT D-39 Isolation Grade O

b 75-23-021 Spray Nozzle Strainer Drain Grade C

=

5 75-23-022 Spray Nozzle Strainer Drain Grade C

]

75-24-080 HPSW to Radiation Monitor Eductor Grade C

12 3

75-24-087 HPSW to Diesel Generator Building J

E Isolation Mezzanine 0

-a B

75-24-046 Service Water Tank Supply and Discharge Mezzanine 0

i f 75-24-047 H.P. Service Water Hose Connection Mezzanine C

u 75-24-048 Fire Hose Connection Mezzanine C

g 75-28-026 Service Water Tank PS-13, Isolation Mezzanine O

._w 75-28-027 Service Water Tank Gauge Glass Isolation Mezzanine O

75-28-028 Service Water Tank Gauge Glass Isolation Mezzanine 10 75-28-029 Service Water Tank High Alarm Isolation Mezzanine O

75-28-030 Service Watar Tank High Alarm Isolation Mezzanine O

L 116 7-9

Revised

~

LACDWR Operating Manual Volume II, Reactor Process Systems July 1976 r,3 ALTERNATE CORE SPRAY VALVE CHECKLIST _

i 4

POSITION _

V__A_ LVE NO.

NA_ME TURBINE BUILDING O

Flow Transmitter Iligh Isolation y 38-28-001 Flow Transmitter Low Isola' ion O

M 38-28-002 O

A 38-28-006 Pressure Switch 1 s o l a t-i on C

5

~

38-23-014 liign Point Vent 38-23-001 Valve 38-24-001 Rody Drain C_

C 1

38-23-002 Valve 38-24-002 Body Drain 2 4 38-24-001 A-C Motor-operated Valve Isolation Valve LO 38-24-002 D-C Motor-ope rat ed Va lve Isolation Valve LO y

g AUTO t

y 38-30-001 A-C Motor-operated valve AUTO g

? 38-30-002 D-C Motor-Operated Valve O

38-28-003 Pressure Indicator Isola + ion LC o

38-24-004 6-Inch Test Valve

)q LO 38-24-003 Alternate Core Spray Isolation i

C

.} } 38-24-005 Alternate Core Spray Isolation Bypass C

3 38-23-003 liiyh Point vent Root Valve C

33-23-004 liia n Point vent valve CONTA I1. ':gr_ BU ! LD r NG w

n :-

C 38-23-016 Alternate Core Cpray IIeader Drain 38-23-017 Alternate Core Spray Header Drain Shutoff C_

y C

Low Point Dr ai n Foot Valve

,j g 38-23-005 C

j ':

4 38-23-006 Law Point Dra in valve

~

C~

9 33-23-007 After-Check Drain Root Valve f,

)

38-23-008 After-Check Drain Valve C_

u 38-23-012 After-Check V nt Root Valve C

C 18-23-013 Af ter-Check V< nt Valve 38-23-009 Containmont 'N' A D r a i n Foo t Valve C~

C

38-23-010 Contaircont McA Drain valve

{

~~~

k 38-23-011 Containrent 'rA Drain Valve Test Connection C

o

,n P I_P E T t'iN EI; jS m,-

N 37-28-003 Co tainnent Level Transmitters Isolation O

)

Ig.!

37-28-004 Containment Pressure Transmitt er Isolat ion O

y {

37-28-005 containment. Pressure Trancmitt er Drain C

e 37-28-006 Containrent Pressure Indicator / Transmitter Isol.

O j [

37-28-007 Containment Level Transmitter Upper Isolation O

37-28-009 rontainmont Lovel Tr ansmitt er Upper Isolation O

3 )

u o

37-28-010 Containment Lovel Transmi tt or Lower Isolation O

E 37-28-008 Containment Level Transmitt er Lower Irolation O

N 2 G.,

by v y no o rw yns

'"5 AIM J ChL, 1,_17

LACBWR Operating Manual Revised Volume II, Reactor Process Systems July 1979 ALTERNATE CORE SPRAY VALVE CHECKLIST - (Cont'd)

NAME POSITION VALVE NO.

39-24-006 Diesel Pump 1A Discharge O

38-24-016 Diesel Punp 1A Unicader Isolation O

38-24-007 Diesel Pump 1A Strainer Backflush Supply C

3S-24-00S Diesel Pump 1A Strainer Backflush Supply C

l4' 38-24-009 Diesel Pump 1A Strainer Backflush Discharge C

i I 38-24-010 Diesel Punn lA Strainer Backflush Discharge C

I7 18-24-012 Supply to Cooling Water Valve O

Fj 38-24-013 Supply frem Cooling Water Valve O

[7 38-24-011 Cooling Wacer Valve Bypass C

38-24-015 Gear Box Oil Cooling Supply O

p if 38-28-0C4 Diesel Pump 1A Discharge PS-38-35-701 Isolation O

E 38-28-005 Diesel Pump 1A Discharge Pressure Gauge Isolation O

38-28-007 Diesel Pump 1A Auto Start Pressure Isolation O

6!j38-24-017 Diesel Engine lA Fuel Oil l ump Supply O

l((h 1-I 38-24-018 Primary Tank Fuel Oil Supply to lA Diesel Engine O

?>

75-24-056 Diesel Pump 1B Discharge O

d {75-24-057 Diesel Punp 1B Unloader Isolation O

I 75-24-053 Diescl Pump 1B Strainer Backflush Supply C

75-24-059 Diesel Pump 1B Strainer Backflush Supply C

, 75-24-060 Diesel Punp 1B Strainer Bakcflush Discharge C

-( 75-24-061 Diesel Pung 1B Strainer Backflush Discharge C

- ('"5-24-063 Supply to Coaling Water Valve 0

2 4 75-24-064 Supoli. fran Ccoling Water Valve O

~

75-24-065 Cooling Water Valve Bypass C

~

75-24-066 Gear Box Oil Couling Supply O

I 75-28-033 Diesel Pump 1B Discharge PS-10 Isolation O

75-28-034 Diesel Pump 1B Discharge Pressure Gauge Isolation 0

-( 75-28-035 Diesel Pump 1B Auto Start PS-14 Isolation O

75-24-014 Diesel Engine 1B Fuel Oil Pump Supply O

~ + 75-24-095 Prining Tank Fuel Oil Supply to 1B Diesel Engine O

I OUTSIDE OF TURBI:E BUILDI;G h

\\

75-24-049

o-th Fire Header Isolation LO l@iw&I D ' 3Q}A P$K i, D

Lo 75-24-053 Scuth Fire Header Isolation i]QREMARKS:

a

->: l d' i DATE PEPTORMED BY (Operator) ik : :l C$

APP?OVED BY

!lN (Shift Supervisor)

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Date Oper. Pev. Com A pprova t D_a.-_t_e__l' P. Brawlies 177[79

-l

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BASEMENT Z 56-24-001 Decay llea* Pump Inlet NW O

i N

56-24-003 Decav lieat Pump Byliass NW O

.s

=-

56-23-006 Decay lieu t Pump Vant.

NW C

m 56-23-007 Decr2 licat P um; > V. ' n t Shut.u t t NW C

.0,%

s 4 56-23-008 Decay lieat P t.r' p Drain NW C

e 7-N 56-23-009 Dccay i! cat tNnp O'ala Shitotf NW C

~

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'l / 56-28-003 I:e ca,

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NK O

56-28-004 reea lica t amp r T r a nsa.t t ter (iii )

N.i O

LI' g 56-24-022 De,a3.iea: Pur ;..' hec k Va l v.'

itypar,s NW C

!c! y Decay IIcat r u- ; 01scharce NW O

k ',

56-24-002 56-2 -301 Decay lleat '. tr e:

Je n t

':W C

31 56-23-32?

c c m3 2 Rat syste.r ven+ Shutoff NW C

h l6 T.

56-24-006 Dec..y lie.t Joo l.': Bypass NW C_

.?! ' 56-24-U04 Ceca; :e n t a'e-

!.le-NW O

1

! 56-24-005 Decay w t w 1. r Outlet

';W C_

i ', l,.'i\\

' 56-2 3-c 0 3 1: eca-iieat ' s s t e-I.t n-Point Drain

W C

i 56-23-304 Dc cal ri.

. S... t. t e i. :,. U o i n t Drain Shutaff NW C

at ia'le, m.c i l Dra.n NW C-l:Q 24-1 E s - o m.'

^

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July 1977 DIh? A's !!I:f.T COOLING S i bTI-:M V Ai. 'l: Cill;C KI. A ST Folt 16 ACTO R OP ERAT ION - (Cont'd)

LOCATION VALVE NO.

NAMis QUADRANT POSITION CONTI0L ROOM

~ry 5 6-2'*-001 D e c.v.

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SHJ TDCWN

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1 ENCLOSURE 1 - ATTACHMENT E Revised

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ENCLOSURE 1 - ATTACHMENT F Revised

LACDWR Operating Manual volume III, Turbine Generator Systems August 1976 r

TABLE 10-1 CONDENSATE SYSTEM VALVE CHECKLIST POSITION VALVE NO.

NAME CONDENSATE PUMP AREA In-&nvice R

Hotwell Gage Glass In-Sexice E 3 90-42-711 Hotwell Level Transmitter In-Service

$ 5 ' 90-42-710 Hotwell High Alam In-Service 90-42-713 Hotwell Low Alam Y

Condenser Makeup Level Columns In-Service g

Emergency and Normal 4

Condenser Overflow Level Columns g

In-Service

}

Emergency and Normal C

g 90-23-003 Condenser Hotwell Drain C

u 90-23-040 Condenser Hotwell Hose Connection 90-28-001 Condenser Pressure Gage 1A Isolation Suction O

E h 90-28-002 Condenser Pressure Gaae 1B Isolation Suction O

O E l 90-24-001 1A Cond,' sate Pump Suetien valve o

3 h ' 90-24-002 1B Condensate Pump Suction Valve g \\

90-28-003 1A Condensate Pump suction Pressure Gage Isol.

O

/- ^ gs 90-28-004 1B Condensate Pump Suction Pressure Gage Isol.

O g

90-23-001 1A Condensate Pump Vent Isolation O

g 90-23-002 1B Condensate Pump Vent Isolaticn O

90-25-003 1A Condensate Pump Seal Water Solenoid Valve Pe. Avail.

% \\'

90-25-004 13 Condensate Pump Seal Water Soler.oid Valve Tvr.1 hall.

$ j 90-25-005 1A Condensate Pump Seal Water Solenoid Valve Pwr.1hrail.

E ;.90-25-006 1B Condensate Pump Seal Water Selenoid Valve Ivr.; heil.

2 90-24-005 Condensate Pumps Seal Water Common Isolation O

90-24-006 1A Condensate Pump Seal Water Isolation O

E '.' 90-24-007 1B Condensate Pump Seal Water Isolation O

N 90-28-005 1A Condensate Pump Discharge Pressure Gage Isol.

O j $j 90-28-006 1B Ccndensate Pump Discharge Pressure Gage Isol.

O O

,c 1A Condensate Pump Discharge Valve

.Litg 90-24-003 la Cor.densate Pump Discharg.e Valve O

6L 90-24-004 C

90-24-008 Condenser Makeup Manual Bypass

( },J O

90-24-009 Condenser Nornal Makeup Stop O

9 90-24-010 Cor.done,er Norral Makeup Stop l[;f O

90-24-011 Condenser Enorgency Makeup Stop O

e 90-24-012 Condenser Emergency Makeup Stop

]

90-22-001 Condenser Normal Makeup Regulating Valve In-9uwice o

90-22-002 Condenser Emergency Ktkeup Regulating Valve In-Sentice C

2 u

90-24-013 Condenser Overflow Manual Bypass O'

B S 90-24-014 Condenser Normal Overflow Stop O

? I 90-24-015 Condenser Normal Overflow Stop C

i $

90-24-016 Condenser Emergency Overflow Stop C

90-24-017 Condenser Emergency Overficw Stop j g r

L 116

LACBWR Operating Manual Revised Volume III, Turbine Generator Systems August 1976 TABLE 10 CONDENSATE SYSTEM VALVE CHECKLIST - (Cont'd)

VALVE NO.

NAME POSITION CONDENSATE PUMP AREA - (Cont'd) 90-22-003 Condenser Normal Overflow Regulating Valve In-Servi 3 3 90-22-004 Condenser Emergency Overflow Regulating Valve In-Service 90-28-133 Condensate Pump Discharge Header Press. Isol.

O a w i

90-24-018 Condensate to Exhaust Hood Spray and RFP Seals O

90-37-302 Condensate Flow Transmitter f/Recire. Valve In-Service 3

$90-23-043

1 FWH Sample Cooler Inlet C

{ $ 90-24-041

1 F *H Sample Cooler Cooling Water Inlet O

.)I90-23-045 90-24-043

1 FWII Sample Cooler Cooling Water Outlet O

j,;

42 FWii Sample Cooler Inlet C

l' 5 )90-24-042

2 FWii Sample Cooler Cooling Water Inlet O

' 90-24-044

2 FWH Sample Cooler Coolina Water Outlet O

[

90-37-701 Condensate Flow Transmitter' In-Service 3 g NOTE:

Ensure at least one condensate domineralizer bed lined up for operation.

[NO. 3 FEEDWATER IIEATER AREA m

90-24-045 Condensate to 4500 Waste Tank C

Condensate to 4500 Waste Tank Hose Connection C

,_ l *]a 9 0-2 3-0 41 Condensate Recirculation Isolation O

.?;1,90-24-019

'Ej)90-25-001 Condensate Recirculation Valve In-Ser/ ice

.it 90-23-006 Water Storage Tank Drain C

90-98-004 Reheater Level Control Chamber Gage Glass In-Service j! 'Sj90-42-702 Reheater Level Control Chamber Level Alarm In-Servim j

90-42-703 Reheater Level Control Chamber Level Column In-Service 90-98-003 Water Storage Tank Gage Glass In-Service 2 %:

Water Storage Tank Level Alarm In-Service h.A90-42-701 i

90-42-722 Water Storage Tank Normal Level Control Colurn In-Service 90-42-723 Water Storage Tank Emergency. Inwl (bntrol Colu n In-Service

% 65-98-001 s3 FWII Gage Glass In-Service 3; 3 90-42-705 h 3 FWii Level Alarm In-Service D

90-42-712

3 FWil Normal Level Control Column In-Service I90-42-713 83 FWH Emergency Level Control Column In-Service t

90-23-011 43 FWH Startup Vent C

y 90-23-012

3 FWH Operating Vent Stop O

5 g 90-23-013

3 FWii Operating Vent Shutof f O

2 y 90-23-009 43 FWil Shell Side Drain C

90-23-010

3 FWH Shell Side Drain C

B ll 3 ja *

,?

_ e.

r

( 116 10 - 1 E'

LACBWR Operating Manual Revised volume III, Turbine Generator Systems August 1976

-o TABLE 10 CONDENSATE SYSTEM VALVE CHECKLIST - (Cont'd)

VALVE NO.

NAME POSITION MEZZANIME LEVEL CONDENSER REAR C

f yd 90-23-020 Air Ejector Inter Condenser Drain C

!> 3' 90-23-021 Air Ejector Af ter Condenser Drain C

,A N 90-23-022 Air Ejector Inter Condenser Drain C

_1 90-23-023 Air Ejector After Condenser Drain 9

Gland Steam Condenser Outlet Header Drain C

90-23-024

@ ' 90-23-025 Gland Steam Condenser Inlet Header Drain C

O lE } 90-24-020 al FWH Inlet 0

j[

90-24-021

1 FWH Outlet C

90-24-022 81 FWH Bypass i_

C lb 90-23-026

1 FWH Tube Side Vent 90-29-025 el FWH Inlet Pressure Gage Isolation O

N 90-23-027 il FWH Tube Side Drain C

90-23-030 41 FWH Shell Side Drain C

5 il FWH Outlet Sample Isolation O

b)i?90-23-042 O

90-23-018 31 FWH Operatino Vent C

f=4(90-28-141 s1 FWH Shell Pressure Transmitter Isolation O

90-23-019 s1 FWH Operating Vent Bypass

. 3 ty i 90-28-135

=1 FWH Shell Pressure Transmitter Stop O

~i

.-g$90-23-039 21 FWH Shell Fressure Transmitter Drain C

31 FWH Nor..al Overflow Isolation O

s 90-24-036

~

._'I \\1 90-22-014 il FWH Normal Overflow Regulating Valve In-Service fi1 90-24-035 al FWH Emergency Overflow Isolation O

2: 4 90-22-013 s1 FWH Fmergenc'/ Overflow Regulating Valve In-Service 90-24-223 82 FWH Inlet O

[.l90-24-C24 32 FWH Outlet O

C i

2 FWH Bypass

!$ p 90-24-025 90-28-026 s2 FWH Inlet Pressure Gage Isolation O

L 90-23-044 22 FWH Outlet Sample Isolation O

)[pf'y 90-23-0283 2 FWH Tube Side Vent C

--*w 9 0 - 2 3 - 0 2 9 s2 FWH Tube Side Drain C

4 %b 90-23-031

2 FWH Shell Side Drain C

O j

s2 FWH Operating Vent 1;p,l90-23-015 90-23-016 42 FWH Operating Vent Bypass C

,l 90-28-142 42 FWH Shell Pressure Transmitter Isolation O

$' ; 90-28-136

2 FWH Shell Pressure Transmitter 3 top O

'5 90-23-038 42 FWH Shell Pressure Transmitter Drain C

i e 90-24-034 82 FWH Normal Overflow Isolation O

{ j 90-23-035 Gland Leak Off Isolation For 90-24-034 0

3 90-22-012 82 FWH Normal Overflow Regulating Valve In-93rvio3 o

l} 2 90-24-033

2 FWH Emergency Overflow Isolation O

90-23-034 Gland Leak Of f Isolation For 90-24-033 O

j[2g 90-22-011

2 FWH Emergency Overflow Regulating Valve In-Service 90-22-007 Reheater To Flash Tank Regulating Valve In-&nrd ce 90-28-071 Reheater To Flash Tank Pressure Transmitter Isolation O

11 r, 10-10

Revised LACBWR Operating Manual August 1976 Volume III, Turbine Generator Systems 7

(Cont'd) 10-l_ - CONDENSATE SYSTEM VALVE CHECKLIST _ -

TABLE POSITION NAME VALVE NO.

MEZZANINE LEVEL CONDENSER REAR - (Cont ' d)

Water Storage Tank to $3 FWH Flcw Transmitter

--~~~

90-28-058 O

Isolation 3

90-28-059 Water Storage Tank to #3 FWH Flow Transmitter O

s Isolation O

8 Water Storage Tank Emergency Overflow Isolation s*

90-24-028 5

90-23-037 Gland Leak Off Isolation For 90-24-028 O

90-22-005 Water Storage Tank Emergency Overflow

._3 In-Service Regulating Valve

$,(g Water Storage Tank Normal Overflow to #3 FWH 90-24-029 O

1 Isolation l

90-23-036 Gland Leak Off Isolation For 90-24-029 0

a 90-22-006 Water Storage Tank Normal Overflow to 4 3 FWH In-Service g

E [

Regulating Valve In-Service Flash Tank Gage Glass

?

)

In-Service

h 90-42-601 Flash Tank Level Alarm In-Service k

90-42-724 Flash Tank Level Control Column O

N 90-24-047 Flash Tank Vent to #3 FWH O

90-28-129 Flash Tank Vent to 8 3 FWH Pressure Gage 90-28-131 Flash Tank Vent to #3 FWH Pressure Transmitter O

Isolation O

g N 90-24-030 Flash Tank to #3 FWH Isolation 0

i 90-23-032 Gland Leak Off Isolation For 90-24-030 C

t 90-24-031 Flash Tank to #3 FWH Regulat.ing Valve Bypass

'2 R

In-Sezvice 90-22-008 Flash Tank to #3 FWH Regulating Valve 4

O 5

l 90-24-032

3 FWH Emergency Overflow Isolation u

90-22-009

3 FEI Emergency Overflow Regulating Valve In.-Ser/ ice E

g-90-25-002 83 FhH Normal Overflow Isolation O

i In-Service 90-22-010

3 FWH Normal Regulating Valve 90-23-033 Gland Leak Off Isolation For 90-25-002 D

[

~

O o

1 90-28-081 Flash Tank Pressure Transmitter Isolation t MEZZANINE LEVEL CONDENSER FRONT 3 *s 90-35-307 Extraction to il FWH Fressure Transmitter In-Service 90-35-308 Extraction to 42 FWH Pressure Transmitter In-Service C

a 90-23-017 il PhH Shell Drain C

y 90-23-014 42 FhH Shell Drain In-Service 90-42-714 91 FWH High Level Alarm g

c, In-Service y

a 90-42-321 81 PhH Normal Level Control Column In-Service 3 $

90-42-323 41 FWH Emergency Level Control Column In-Service y g 90-98-001 41 PhH Gage Glass In-Service g y 90-42-704 0 2 FWH High Level Alarm In-Service e

90-42-320

2 FWH Normal Level Control Column

^

o 90-42-322

$2 FWH Emergency Level Control Column In-Seryice In-Servim t'

90-98-002 02 PhH Gage Glass t 116 10-20

Revised LACBWR Operating Manual volume III, Turbine Generator Systems August 1976 C

TABLE 10 CONDENSATE SYSTEM VALVE CHECKLIST - (Cont'd)

POSITION NAME VALVE NO.

REACTOR FEED PUMPS _

90-35-303 Reheater to Flash Tank Pressure Transmitter In-Service e

90-37-301 Water Storage Tank to #3 FWH Flow Transmitter In-Service C

90-35-304 Flash Tank Vent to 83 FWH Pressure Transnitter In-Service In-Service e

j **w 90-35-305 Flash Tank Pressure Transmitter 90-28-134 RFP's Common Suction Header Pressure Gage O

Isolation E

4 k

T

,}

TURBINE FLOOR WEST SIDE 4

O I

90-24-048 Exhaust Hood Spray Regulating Valve Inlet O

90-24-049 Exhaust Hood Spray Regulating Valve Outlet C

g 90-24-050 Exhaust Hood Spray Regulating Valve Bypass O

90-24-051 Exhaust Hood Front Spray Header Isolation j

j 90-24-052 Exhaust Hood Rear Spray Header Isolation O

90-25-007 Exhaust Hood Spray Regulating Valve In-Service O

90-28-143 Exhaust Hood Spray Header Pressure Gage Isol.

C

/, yy REMARKS:

4 E

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}

DATE PERFORMED BY (Operator) y o

r APPROVED BY y

t (Shif t Supervisor) g g REVIEWED BY 1 +

(Operations Supervisor) e ss

(

L 116 10-21

LACBVR Operating Manual, Volume Ill, Turbine Generator Systems Revised August 97

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ENCLOSURE 1 - ATTACHMENT G LACBWR Operating Manual Revised Volume III, Turbine Generator Systems January 1975 TABLF 12-1 REACTOR FEEDWATER PJMP VALVE CHECKLIST Normal No.

Name Position h

lA Reactor Feedwater Pump d d 90-24-026 1A Feed Pump Suction Valve O

90-28-027 1A Flow Transmitter Isolation O

j 90-28-028 1A Flow Transmitter Isolation O

p$.(

90-28-034 1A Suction Press Transmitter Isolation O

i 90-23-004 1A RFP Suction Strainer Drain C

'?

90-28-035 1A RFP Suction Press Trip & Gage Isolation O

g

]

65-24-024 1A RFP Warmup O

65-24-025 1A RFP Recirculation Stop O

c s

65-25-001 1A RFP Recirculation Valve C

1 65-24-026 1A RFP Recirculation to Condenser O

2 65-28-001 1A RFP Discharge Press Gage Isolation O

j m 65-28-010 1A Discharge Press Transmitter Isolation O

65-24-030 1A Feed Pump Discharge Valve O

~~

65-24-032 1A RFP Discharge Bypass C

y i

S lA RFP Flow Transmitter In Service r

S' )

1A RFP Suction Press Transmitter In Service L-

1A RFP Discharge Press Transmitter; In Service N

98-23-001 lA Oil Sump Drain C

lb; 98-28-001 1A Oil Sump Gage Glass Isolation O

!k }

98-28-002 1A Oil Sump Gage Glass Isolation O

d.'

98-23-003 lA Oil Filter Drain C

'{

1A Oil Press Switches (3 Switches)

In Service k

1A Bearing Oil Supply Flow Meters (7 Valves)

Set for Flow

y 98-24-023 1A outboard Motor Bearing oil Supply 0

i 98-23-005 1A Coupling Water Sump Drain C

{,,,

98-28-011 lA Coupling Water Sump Gage Glass Isolation O

o 98-28-012 1A Coupling Water Sump. Gage Glass Isolation O

1A Coupling Water Cooler Outlet Vent C

98-23-007 i R 98-24-003 1A Coupling water Outlet 0

iS 2; 98-24-005 1A Oil Cooler LPSW Temp Reg (98-22-001) Isol.

O

'- R 98-24-007 1A Oil Cooler LPSW Temp Peg (98-22-001) Isol.

O s

98-24-009 1A Oil Cooler LPSW Temp Reg (98-22-001) Bypass C

7 98-24-025 RFP 1A Seal Water Icolation O

r 98-24-035 Sealing Water from RFP 1A O

j 98-23-009 RFP 1A Seal Water Sample C

y 3 l 98-24-015 1A Cooling water Outlet to Standpipe O

7 98-24-017 1A Cooling Water Supply Isolation O

g a 98-25-001 1A Cooling Water Supply valve In Service g

98-24-019 1A Cooling Water Supply Isolation O

o 98-24-021 1A Cooling Water Supply Bypass C

L 116 12-13

LACBWR Operating Manual Revised Volume III, Turbine Generator Systems January 1975 Table 12 Reactor Feedwater Pump Valve Checklist (Cont'd)

Normal No.

Name Position IB Reactor Feedwater Pump

(

90-24-027 IB Feed Pump Suction Valve O

F 90-28-038 1B Flow Transmitter Isolation O

90-28-039 1B Flow Transmitter Isolation O

4 o

90-28-045 1B Suction Press Transmitter Isolation 0

90-23-005 IB RFP Suction Strainer Drain C

90-28-046 1B RPP Suction Press Trip and Gage Isolation O

jj a

?.

65-24-027 IB RPP Warmup O

j.?

65-25-028 1B RFP Recirculation Stop O

65-25-002 1B RPP Recirculation Valve C

b 65-24-029 1B RFP Recirculation to Condenser O

65-28-002 1B RFP Discharge Press Gage Isolation O

1 Q

65-28-012 1B Discharge Press Transmitter Isolation O

h

'3 65-24-031 1B Feed Pump Discharge Valve O__

65-24-033 1B RFP Discharge Rypass C

g 1

1B RFP Flow Transmitter In Service

k lS 1B RFP Suction Press Transmitter In Service P"

1B RFP Discharge Press Transmitter In Service

'S i 98-23-002 1B Oil Sump Drain C

L-98-28-003 1B Oil Sump Gage Glass Isolation O

N 98-29-004 1B Oil Sump Gage Glass Isolation O

l! 4 98-23-004 1B Oil Filter Drain C

i 1B Oil Press Switches (3 Switches)

In Service 18 Bearing Oil Supply Flow Meters (7 Valves)

Set for Flow d

g 98-24-024 1B Outboard Motor Bearing Oil Supply O

v 98-23-006 1B Coupling Water Sump Drain C

98-28-013 1B Coupling Water Sump Gage Glass Isolation O

.g i

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ls 98-23-008 IB Coupling Water Cooler Outlet Vent O

yij 98-24-004 1B Coupling Water Cooler Outlet O

98-24-006 1B Oil Cooler LPSW Temp Reg (98-22-002) Isol.

O

& Q 98-24-008 1B Oil cooler LPSW Temp Reg (98-22-0v2) Isol.

O io S 98-24-010 1B Oil Cooler LPSW Temp Reg (98-22-002) Bypass C

p-ty 98-24-026 RPP IB Seal Water Isolation O

e 98-24-036 Scaling Water From RFP 1B O

I 98-23-010 RFP 1B Seal Water Sample C

y r

98-24-016 IB Cooling Water Outlet to Standpipe O

j 98-24-018 1B Cooling Water Supply Isolation O

y g g 98-25-002 1B Cooling Water Supply Valve In Service 98-24-020 1B Cooling Water Supply Isolation O

e p

98-24-022 1B Cooling Water Supply Bypass C

5 d n

L 116 12-14

Revised LACBWR Operating Manual Volume III, Turbine Generator Systems January 1976 TABLE 12 REACTOR PEEDRATER VALVE CHECKLIST - (Cont'd)

~

NORMAL VALVE NO.

NAME LOCATION POSITION RFP 1A OR RPF IB O

98-24-037 Scaling Water From RFP's To Condenser W

65-23-033 No. 3 Feedwater IIcater Inlet Sample TB GRADE O

3

. 65-23-034 No. 3 Feedwater lieater Inlet Sample Shutoff TB GRADE C

N 8 h/65-24-003 No. 3 Feedwater licater Sample Cooler CCW TB GRADE C

]

Inlet L

65-24-004 No. 2 Feedwater IIcater Sample Cooler CCW

\\

TB GRADE C

_7 Outlet

\\ 65-23-024 Feedwater Discharge Test Cont.ection Isol. TB GRADE C

[

65-23-025 Feedwater Discharge Test Connection Isol. TB GRADE C

65-28-014 No. 3 lleater Outlet Fressure Gauge

3 IIEATER In-Service y

65-24-041 Feedwater Recirculation to No. 3 Heater

3 IIEATER C

u k'

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& \\

65-23-020 No. 3 !! eater Recirculation Drain

3 HEATER C

r 1 65-22-001 Reactor Feed Flow Control Valve

3 HEATER O

S i 65-23-028 No. 3 Ileater Tule Side Drain

3 IIEATER C

(

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., 65-23-027 Feed Line Drain Shutoff TUNNEL C

s R 65-28-003 Feed Flow Transmitter liigh Point Isol.

TUNNEL O

8 3 65-29-004 Feed Flow Transmitter High Point Isol.

TUNNEL O

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V-PEMARES:

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DATE PERFORMED BY u

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REVIEWED BY (Operations Supervisor)

L 116 12-15

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ENCLOSURE 2 f

NRC ITEM 1.

Describe all cuenta that rcoulted in a complctc lose of main feeduater over the last three years of operation.

Include as a minimum, the (citoving information:

date, initiating event, pouer level, and a short description of the subecquant actions.

DPC RESPONSE:

One incident in the last three years has resulted in a complete loss of main feedwater.

Date and Time of Incident September 30, 1976 0 0545 Description of Incident Running equipment is shifted weekly; while shifting auxiliary oil pumps on the 1A Reactor Feed Pump, the feed pump tripped.

The feed pump was restarted, however, reactor vessel water level was decreasing rapidly and the reactor operator manually scrammed the reactor to prevent cecrease to the low level scram point.

Operating Conditions at Time of Incident Reactor at 91% power.

Turbine-Generator connected to DPC grid.

Immediate Evaluation, Corrective Action and Results The scram was responded to in accordance with approved procedure.

The shifting of running equipment is done to equalize the hours among similar equipment.

The operato.r started the standby pump and waited approximately 15-30 seconds prior to shutting off the running pump.

No further immediate corrective action was required.

Permanent Corrective Action The reactor feed pump trip on low bearing oil pressure is supposed to have a 5 psig setpoint.

Automatic start of the standby oil pump occurs at 10 psig.

The setpoint for reactor feed pump trip on low bearing of.1 pressure was found to be set at between 9-10 psig.

The discharge pressure of the #2 oil pump (the shif t was from #1 to #2) was found to be 14 psig after the filter.

The pressure desired at this point with one pump running is 17 psig.

The housing of the pressure switch was found to be distorted from some outside contact which occurred during the period of operation since August 23, when the switches were calibrated.

1 -

ENCLOSURE 2 - (Cont'd)

The transient of oil pressure which occurs during pump shift was enough to reach the reactor feed pump trip setpoint.

The setpoint was returned to 5 psig for the reactor feed pump low lube oil pressure trip and the pump discharge pressure adjusted to 17 psig downstream of the filter.

An Operations Memorandum (No. 69) was issued to require the operator to visually confirm the discharge pressure of the standby pump being started before securing the operating pump.

No further corrective action is necessary.

NRC ITEM 2.

Describe all evente that have resulted in the operation of the pover-actuated relief valves and the safety / relief valves utilized by the reactor pressure relief systems over the last three years of operation.

Include as a minimum, the follouing informa tion:

date, initiating event, pouer level, and a short description of the subsequent actions.

Ensure that your description includes valve actuatione cauced by:

(1)

Instrumentation and control failures (2)

Trancient events (3)

Other causes such an manual, testing, etc.

DPC RESPONSE:

LACBWR has no power-actuated safety relief valves.

There have been no events over the last three years of operation resulting in operation of safety / relief valves at LACBWR.

O JOCJV EN

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ML19276H069

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