Text

Forwards Revised Pages 42 & 43 of Tech Specs,Valve Checklists from Operating Manual & Other Matl Re Application for OL Amend Re Inservice Insp Program
	ML19331B641
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/14/1980
From:	Linder F; DAIRYLAND POWER COOPERATIVE
To:	Crutchfield D; Office of Nuclear Reactor Regulation
Shared Package
ML19331B642	List: ML19331B641; ML19331B645;
References
	LAC-7025, NUDOCS 8008120527
	Download: ML19331B641 (100)
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LA CROSSE. W1SCONSIN S4601 (608) 788-4000 July 14, 1980 In reply, please refer to LAC-7025 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:

Mr. Dennis M. Crutchfield, Chief THIS DOCUMENT CONTAINS Operating Reactors Branch No. 5 Division of Operating Reactors P0OR QUAUTY PAGES 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 APPLICATION FOR AMENDMENT TO LICENSE

References:

(1) DPC Letter, LAC-6280, Linder to Ziemann, dated May 11, 1979 (Tech. Spec. Submittal). (2) DPC Letter, LAC-6429, Linder to Ziemann, dated July 27, 1979 (Program Submittal). (3) NRC Letter, Reid to Madgett, dated January 10, 1978 (Guidance - NRC). (4) License Amendment Fee, Check #21046, dated July 10, 1979. (5) DPC Letter, Linder to Ziemann, dated December 7, 1979 (Pumps Reliefs). (6) DPC Letter, Linder to Ziemann, dated January 21, 1980 (MSIV Bypass Valve Relief). (7) DPC Letter, Linder to Ziemann, dated January 24, 1980 (Additional Information - Class I, II & III). (8) DPC Letter, Linder to Ziemann, dated January 30, 1980 (Core Spray Valves). (9) NRC Letter, Nerses/Shea to DPC (LACBWR), dated May 9, 1980. Gentlemen: An application to amend Provisional Operating License No. DPR-45 was requested in Reference 1. The requested amendment involved proposed changes to Technical Specifications for the La Crosse Boiling Wrter Reactor (LACBWR) which deal with the Inservice Inspection ProgrE... Reference 2 submitted the plans and requests for relief of the in-service testing and inspection programs for the La Crosse Boiling Water Reactor. Subsequently, on March 25 and 26, 1980, NRC repre-sentatives and their consultants met with LACBWR representatives to s27 s f 8008120 'Q f

Mr. Dennis M. Crutchfield, Chief LAC-7025 Operating Reactors Branch No. 5 July 14, 1980 discuss the program submitted in Reference 2. Based on the above meeting, several areas noted in the program require revisions. References 5, 6 and 8 revised various portions of the program previously submitted in Reference 2. However, during the course of the meeting, some of the relief requests were deemed unjustified and others required additional information for relief justification. Additionally, valves which were not considered by LACBWR to perform a safety related function (specifically Category "E" valves) were requested to be incorporated into the program. It was determined during the meeting that the two diesel-driven alternate core spray pumps can be tested on a monthly schedule as a fixed resistance system; therefore, the Request for Relief presented in Reference 5 on these two pumps is hereby withdrawn. Additionally, Reference 5 uses the phrase " reduces system redundancy" as a second reason for not testing the high pressure core spray pumps. Based on the discussions at the working meeting, reduction in redundancy is not a suitable justification; therefore, this reason is deleted as justification for not testing the high pressure core spray pumps. However, reasons 1 and 3 in Reference 5 remain applicable. The two high pressure core spray pumps will be tested each cold shutdown, but not more often than every month, versus testing the pumps after accumulating ten (10) hours of pump run time as stated in Reference 5. However, to obtain vibration readings and bearing temperatures, these' pumps must run for an extended period of time, pumping water into the reactor vessel, thus creating conditions of high reactor water level. Because the removal rate is approximately one half of the injection rate, the potential exists for overpressurizing the reactor vessel with cold water. Therefore, the quantities of bearing temperature and vibration reading will be taken during refueling outage testing only. Revised pages of the Examination Plan for Pumps, reflecting these changes for the affected pumps; Emergency Core Spray Pumps lA, 53-06-001 and 1B, 53-06-002, Alternate Core Spray Pump, 36-06-001 and High Pressure Service Water / Alternate Core Spray Pump, 75-06-002 are enclosed. Other information in Reference 5 remains valid. In the interest of making this a complete package, the relief request bases of Reference 6 is included herein. The information of Refer-ence 6 remains valid. Included herein also are revised pages of the enclosures to Reference 8. Reference 8 is hereby superceded in its entirety. l t <

Mr. Dennis M. Crutchfield, Chief LAC-7025 Operating Reactors Branch No. 5 July 14, 1980 Reference 7 contained four enclosure pages that may be discarded. A revised, complete, LACBWR Class I Inservice Inspection Plan and a complete Table of Requests for Relief for Class I Components is included herein. The answers to questions given in Reference 7 remain valid. In summary: Reference (1) - Remains valid in its entirety. Reference (2) - The information in the body of the letter and Appendix A of Enclosure 1 remains valid. The two tables of Enclosure 1 are superceded in their entirety by the enclosed tables of the same title. remains valid in its entirety. Enclosures 3 and 4 are to be replaced entirely by the enclosures herein. Reference (5) - The requested revisions are incorporated herein. Reference (6) - The requested revision is incorpo* rated herein. Reference (7) - The tables have been superceded and completely revised tables are included herein. Reference (8) - The requested revisions are incorporated herein. Enclosed are valve checklists, which are pages from the LACBWR Oper-ating Manual, showing locked open or locked closed valves in safety related systems. This information is included as a result of Reference 9. Revised pages 42 and 43 of the LACBWR Technical Specifications (Attachment B) are enclosed to comply with recommendations of Reference 9. Sections 5.2.7, 5.2.8, and 5.2.9 on these pages have been changed to comply with NRC staff " Guidelines for Excluding Exercising (Cycling) Test of Certain Valves During Plant Operation". The fee for the review of this license amendment was forwarded by Reference 4. /

e Mr. Dennis M. Crutchfield, Chief LAC-7025 Operating Reactors Branch No. 5 July 14, 1980 If you have any questions regarding this matter, please contact us. [ Very truly yours, DAIRYLAND POWER COOPERATIVE V hc l WL Frank Linder, General Manager FL: HAT:af Enclosures cc: J. Keppler, Reg. Dir., NRC-DRO III STATE OF WISCONSIN ) ) COUNTY OF LA CROSSE) 7h Ra.9usT Personally came before me this day of 3S131, 1980, the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same. SW1j ,4

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F INSERVICE INSPECTION FOR PUMP 3 'id Quantities to be measured are listed below. OUANTITY MEASURE OBSERVE Speed, N X Inlet Pressure, Pi X2 Differential Pressure, tJ' XI Flow Rate, Q X1 Vibration Anplitude, V X Proper Lubr: ' ant Level or Pressure X Bearing Tempccature, Tb X IIn a fixed resistance system, it is required to measure AP or Q, not both. In a variable resistance system, both shall be measured. 2 Measure before pump startup and during the test. Each pump shall have an inservice test performed monthly during operation where applicable. During shutdown conditions the testing should be per-formed, but is not mandatory. The allowable ranges of quantities measured are stated in Table IWP-3100-2. ()) Initial testing of the pumps will establish the reference quantities re- [ quired to conduct future tests on the pumps. Pump Test shall be performed by establishing system conditions necessary to obtain the required data to determine the pump's operability with reference to the quantities established in the initial test. The duration of the test when bearing temperature is not required is 5 min. under stable conditions; then take data. When bearing temperatures are required, the data shall be taken when three successive bearing temperature readings taken at 10 min intervals do not vary by more than 3%. Pumps to be tested are:

1) liigh Pressure Core Spray Pump 1A 53-06-001

2) liigh Pressure Core Spray Pump in 53-06-002

3) Alternate Core Spray Pump 1A 38-06-001

14) liigh Pressure Service Water Pump IB 75-06-002

5) Demin. Water Transfer Pump 1A G7-06-001 G) Demin. Water Transfer Pump 1B 67-06-002

7) Component Cooling Water Pump 1A 57-00-001

8) Component Cooling Water Pump in 57-00-002

r I 1 G ) All quantities that are measured for a test shall be reviewed and analyzed within 96 hours of the test. If any of the quantities are outside of the acceptable range, that quantity will be in either the Alert Range or Required Action Range. To detennine which range the quantity is in, and what action is to be taken, refer to ASME Boiler and Pressure Vessel Code, Section XI Article I W P. Table IWP-3100-2 and Paragraph IWP-3230,,1974 Edition wit Sumer 197 ddenda. 1 v4 0-i I

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IACROSSE iltF ' DT, ifATCit itEACTOR O ELVIINATIOM l'IAN l'Olt l>!911 S j I Nw !1TT i t d! I NTi;tM.f.S T E ,97 gg j j3,3 d-, -f34 a 1 2 1 3 4 6 / -3 / 8 / -10 8 3 4 3 4WTO: TEST MONTHS Dare Date Da t e_ Da t e Da t e 31a t e RDIARFS -1 I III ALTERNATE CORE SPECIAL

1. To be accomplished j SPRAY SYSTEM OR OPER'L 2

i 36-06-001 1 A monthly during lWorthington 3 plant operation. S.N. VIP 18824 ~~

2. If not done during plant shutdown, I

l' then test must be i (, done within one week of plant startup. 8 9

3. Test data may be obtained during 10 noranal pump opera-t tion if reference 13 conditions can be 12 established.

13 l'i 15 16 { 17 18 19 i 20

LACROSSI: Ih\\ ING WATI:lt itCACTOR U I:NMilNATifIN l'IRI l'fil! l'I911'S 1 Ns l'ITT I ON I NTI:!(V,'. l.S 2 5 I I 1 ' -3 / l,j-5 5 -f,2/ r,2,;3 j1 3 j,yg 1 1 0 -1,j j3 3 3 5 -i 4';83:3: TEST MONTHS D.i r e lhte

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thte na t e l'.te T;I:Wil:I(S 1 III HIGH PRESSURE SPECIAL

1. To be accomplished SERVICE WATER OR OPER'l 2

l PUMP monthly during !75-06-002 la 3 plant operation. l Wor thing ton 11

2. If not done during iS.N. VTB 10285 plant shutdown, then test must be j

(, done within one 7 week of plant startup. 8 4 9

3. Test data may be obtained during 10 normal pump opera-11 tion if reference conditions can be 12 established.

6 13 lil 15 16 17 4 18 20 i i

n LACROSSI: 11( 1 lNG WATI:R HIMCTOR I:LVIINATION l'IAN l'OR l I':!!S I Ns el:<.T i os I Nri:Im.i.s 2 I I I I 2 1/ -3 / ~4 / - % - 1,2/ r,2/-3/ 3 / -10 0-1 /3 3 4 3 3 3 4 3 7 ~wTot TEST MONTHS Hare fhte Da : ",_, Date D. i tm IOte RI::'ARFS l III DEMIN. WATER SPECIAL

1. To be acconplished

' TRANSFER PUMP 1A OR OPER'l 2 monthly during (67-06-001) plant operation. 3 Allis-Chalmers S.N. 1- 01796-1-1 81

2. If not done during plant shutdown, e

then test must be l 6 done within one week of plant startup. 8

3. Test data may be g

obtained during l 10 nonnal pump opera-tion if reference 11 conditions can be 12 es tablished. 13 lli 15 16 l 17 IR 19 20

IACR(ISSI: II(li,,NG WATl:l! Hl: ACTOR C ~ I;XA>l! NATION l'i.AN l'OR l'ltilS I NH !'ifT IIIN I N i t:RVA; s 0-1 /3 'g - 3 4 'i f- ;

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((4-M 4 34-10 2 I l I I SY.4T131 TEST MONTHS ila re tia r e n it e fin t e Da t e ita t e I:l:>%i:les I 1 !!I l0EMIN. WATER SPECIAL

1. To be accomplished

' TRANSFER PUMP IB OR OPER'l 2 monthly during .(67-06-002) plant operation. 3 .Allis-Chalmers S.N. 1-01796-1-2 'l ~

2. If not done during plant shutdown, e

3 then test must be ' 0 done within one I week of plant s ta rtup. ~~

3. Test data may be obtained during 10 normal pump opera-

~~ r tion if reference 11 i conditions can be l 12 established. l 13 i 1 88 15 16 17 i 19 f 6 20 +

~' f.ACROSSC lla 'NG L'ATI:l RCACTOR .a I:N.VilNATION IV.AN l'OR l'IDils I NN 'l:CTI >N 1;;I'l:RW.I.S T E 2 1 t i3_1 f3 aj3_3 j4 4,g _ g 3_ g,2/ r,2 _3 /

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.it e I laat e Date ite t e I:I:.'Gims I

III COMP 0NENT C00LINC SPECIAL

1. To be accomplished!

~ lW(ATERPUMP1A rnonthly during OR OPER'l 2 57-06-001) plant operation. 3 l Allis-Chaltrers l S.N. 7-1907-1-1

2. If not done during plant shutdown, then test must b l

6 done within one week of plant = s ta rtup.

3. Test data may be obtained during i

10 normal pump opera-tion if reference 11 conditions can be 12 established. 13 1 4 1 81 15 16 17 18 19 20 I

m IACRt1SSI: lai ~ ' - t, 'NG hATI:l; iti: ACTOR >V I:\\W1iN,\\TI()N l'I.AN ~ l'a il: 1 :':li s ~ ~ ~~ } I N !1:("I' li e, 1 :l i r.lW.',I..s i. TYPE " - l,#'3 I i3!i i

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i'. t e I:I::iAr:Vs I III lCOMPONENTC00LINGSPECIAL

1. To be accomplished iWATER PUMP 18 OR OPER'L 2

(57-06-002) monthly during 3 plant operation. iAllis-Chalmers iS.N. 7-1907-1-2

2. If not done during plant shutdown, I

then test must be (, done within one week of plant s ta rtup. 8

3. Test data may be 9

obtained during l 10 normal pump opera-11 tion if reference conditions can be l 12 established. 13 a i 1 81 15 16 l 17 1R 19 20

j PUMP INSERVICE INSPECTION DATA SEET r

iSYSTEM PUMP NO.

~ ~ ~ ~ Dsto ALLOWABLE CALIBRATION INSTRUMENTS USED ERROR DUE DATE V t 5% of Full Scale T 5% of Full Scale AP ! 2% of Full Scale Pi 12% of Full Scale Q I 2% of Full Scale N ! 2% of Full Scale OUANTITIES ~ ~ ~ EFERENCE ACCEPTABLE ~~~ MEASURED R d If Measured Quantities Lxceed Acceptable Quantitie V Refer To Table-IWP-3100-2, And Paragraph IWP 3230 Of Q Subsection IWP ~ of Section X Of ASME Boiler. And Fressure aP Vessel Code For Requirement-For Corrective Action. 2Tb PERSON CONDUCTING TEST: Signature 3 ANALYSIS SHIFT SUPERVISOR NOTIFIED OF RESULTS. TIME DATE g, I ANALY7,CR'S SIGNATURE: ' Prior to and a f ter start up. 2 Temperature required yearly on bearings. 3A11 data is requirul to be analyr.ed seithin 96 hours of test completion. ,.,__-.,,,,-3

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CORRECTIVE ACTION REPORT: ,. J~ U,. e** + g l s yg: ; '. ,y i --. z.s,,... i x E - ^-- 4 '. \\- c., {( 3,e. ' M( - s --9 '.-f i..?.. h,e ;.., ' IJ sU SIMERY OF CORRECTIVE ACTION --+- -- /-fue/b: -- -.., - .... =. .a? fs .s .:yi.',,:.. . c.,. i 1 2. ~ l SIGNATURE OF PERSON RESPONSIBLE IDR CORRECTIVE ACTION: .,c ACCEPTANCE TEST RESULTS DATE .a, - ::. ,. 4,'!- . r.- t [ t l .~. a t,..;. ; :y P2 l ,. j. ;; 4?. s[ #f',",m.. 5 t --o - e,.; -., 7,, _ 4 .,1-e. l s-1. VERIFICATION SIGNATURE: -,--,,-v-

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O' TNSERVICE INSPECTION R VALVES Valves Inservice Inspection Program for safety-related Class 1, 2 and 3 valves is established in accordance with ASME Boiler and Pressure Vessel Code,1974 Edition, and 1975 Summer Addenda, Section XI, Subsection IWV.

The Inservice Inspection Program for Valves is intended to verify opera-tional readiness of safety-related valves in Class 1, 2 and 3 systems on a continuing basis. Valves used for operating convenience such as manual vent, drains, sample, instrument test, and valves used for maintenance only are excluded from the requirements of Article IWV of the ASME Code. To determine the test requirements for applicable valves, there are five (5) categories, and each valve will fall into one (1) or more categories. If a valve has more than one (1) category, that valve will meet the require-ments for each category. The five (5) categories will be defined as: Category A - valves in which a limited seat leakage is specified in the closed position to fulfill their function. ) Category B - valves in which seat leakage is inconsequential for the fulfillment of their function. Category C - valves which are self-actuating by some system characteristic. Category D - valves actuated by an energy source capable of only one (1) operation. Category E - valves which are normally locked, or sealed, closed or open. Tests which require a measured characteristic of a valve (such as stroke time or seat leakage,) will have a data sheet to document the test results. For power-operated valves which require stroke time, the full stroke time is the time required for a valve to travel in the direction required to fulfill its function, from full shut to full open, or full open to full shut (etc.) In the case of power-operated valves which do not have an assigned stroke time, the first test performed on these valves will be used to determine the stroke time for future tests. The operational readiness during the first test for the above-mentioned valves will be determined by operating experience. } l i

O To maintain the current status of valve testing and exercising, each valve is listed under the applicable category heading, and the date of the last test or cycle shall be entered. The test frequency is detemined from the appropriate IW Article of the ASME Code. The test frequency is dependent upon category, type of test to be performed, and type of valve to be tested. This testing program for valves will be performed using a 20-month inspec-tion interval for the service life of the valves. The first inspection interval will begin November 1,1979. l If a leak rate for category "A" valves 6 in. and larger exceeds the I previous test by an amount that reduces the margin between the measured rate and the maximum permissible rate by 50% or more, then the test fre-quency shall be doubled until the valve is repaired. When a test shows that the leak rate is increasing with tims, and a projected leak rate using three or more test shows that the next test will exceed the maximum permiscible leakage rate by 10%, the valve will be repaired or replaced before being returned to service. $ I c

l ) LIST OF ABBREVIATIONS CONT. C NTROL VALVE DIA. DIAPHRAM OPERATED REL. RELIEF VALVE 1 S.C. ACTUATED BY S WE SYSTEM CHARACTERISTIC SOL. SOLENOID 0PER7TED EL ELECTRIC ACTUATION ROTO ROTOPORT VALVE MO. MOTOR OPERATED SAF. SAFETY VALVE DAMP. DAMPER OR BUTTERFLY TYPE VALVE AIR PISTON ACTUATED BY AIR GA. GATE VALVE GL GLOBE VALVE MAN. MANUAL OPERATOR V.L. VALVE LINE-UP CITECKLIST Q. P.S. QUARTERLY PARTIAL STROKE 1 - ~ _.. _. _ _. _

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4 .i ALTERNATE CORE SPRAY SYSTEM h w 4 \\ %s Q g l h A'fMMM'3 T 3' h 4 k N h (A@f IV of u!fD FM A! EP'&tss3)' n 9 eq T r { b i y M /g ) ' O' T foffGt'Af g%e Q Q 9 ,a h g h t re O N g R 4 15 ke.vE <3/s 'I A a e o a 5 DIESEL ENGINE COOLING WATER SUPPLY FOR PUMP 38-06-001 I! O 1 1 SCL DIA. 39-25-031 3 l .DI..ES.E.L_EN_GI.N_E C.O.O..L_I.N.G. W. A_T.E_R SU.PPLY FOR PUMP-_75-06-002 ~ _.. _.. ~ ~ X 1 ett.. DIA, Q 75-25-c21 1

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C CV X CS REACTOR VESSEL ALTERNATE CORE SPRAY SUPPLY CHECK .. __.a i I~ I I LT.. _ ^ . I t '- M 'X %3. s.C..C CV 4..Cp_ _PEACTOR vEsSEr. ALTERNATE CORE SPRAY sUPPLT CIIECM BACRUP '3-2s-032 2 LT I i ALTEsotATE CORE SPRAY SUPPLY RELIEF = _ - . _.. _...p 3e-27-oot 3 1t 1 - t ! 14 m2 s.C. SR ...1 I f I M.1 i ! i i j4_ g s Cs.- s. ,._,.PunP_3 8.os: col. dis.CnARcE, REL.!Er -i i A 22-9e2 3 t ! I I t _.sR(_. __.. PUMP. 75..06._002. DISCHARGE RELIEF...,, i-i ! X I, a =+ e,C, .J p.27.c22 1 i t I j l =_ .? f d2-M1 3 --k._,N !. SAi' UEL M.Q..C Q. X_ Gs, .pERCrom VESSEL ALTERN ATE CORE SPRAY. SUPPLY,,,,,,,, _ ... -. _! t !. I 3 . nt _ _ s.ce.Stroko Time.. ' h. c ...;..L. .= _. _. = w ..a J....

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_r RELIEF REQUEST BASIS VALVES: 32-98-001 thru 32-98-029 (LOWER CONTROL ROD DRIVE MECHANISMS) CATEGORY: B CLASS: 2 FUNCTION: TO ACTUATE LOWER CONTROL ROD DRIVE MEC11ANISMS HYDRAULIC MOTORS WHEN SCRAM SIGNAL IS INITIATED TEST REQUIREMENT: Exercise valves for operability every three months. BASIS FOR RELIEP: Exercising these valves requires inserting the control rods, requiring plant shutdown. ALTERNATE TEST: The valves will be exercised for operability .g ,/ each cold shutdown.

) RELIEF REQUEST BASIS VALVE: '38-26-001 CATEGORY: A/C CLASS : 2 FUNCTION: BACKUP PREVENTION FOR BACKFLOW OF REACTOR COOLANT TO ALTERNATE CORE SPRAY SYSTEM TEST REQUIRDENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Any exercising of this valve would require isolating the primary system from the Alternate Core Spray System, thus placing the Alternate Core Spray System inoperative. Full stroking these valves can only be performed by in-jecting river water into the stainless steel clad reactor vessel causing possible corrosion and chemical problems requiring extensive clean-up. Disassembly for mechanical testing does not justify breaching a reactor coolant pressure boundary on a routine basis when the valve can be periodically partial stroked with demineralized water. ALTERNATE TEST: The valve will be part-stroke exercised with demineralized !! 0 for operability each cold shutdown and refueling outage, 2 but not more often than every 3 months. I

o ) RELIEF RE00EST BASIS j i VALVE: 38-26-002 CATEGORY: A/C CIASS: 2 FUNCTION: BACKUP PREVENTION FOR BACKFLOW OF REACTOR COOLANT TO ALTERNATE CORE SPRAY SYSTEM TEST REQUIREMENT: Exercise valve for operability every three months. l BASIS FOR RELIEF: Any exercising of this valve would require isolating the Primary System from the Alternate Core Spray System, thus placing the Alternate Core Spray System inoperative. I Full stroking these valves can only be performed by in-jecting river water into the stainless steel clad reacter vessel causing possible corrosion and chemical problems requiring extensive clean-up. Disassembly for mechanical testing does not justify breaching a reactor coolant pressure boundary on a routine basis when the valve can i be periodically partial stroked with demineralized water. ALTERNATE TEST: The valve will be part-stroke exercised with demineralized ) iip 0 for operability each cold shutdown and refueling out-age, but not more often than every 3 months. p . ~,.

RELIEF REQUEST BASIS VALVE: 38-26-003 CATEGORY: C CLASS: 3 FUNCTION: PREVENTS BACKFLOW THROUGH PUMP FHEN PUMP IS IN STAND-BY, ALSO REQUIRED TO OPEN WHEN DIESEL PUMP STARTS FOR ALTERNATE CORE SPRAY TEST REQUIREMENT: Exercise valve for operability every 3 months. BASIS FOR RELIEF: The only full-flow / full-stroke flow paths in this system are to the reactor or recirculation back to the river. The path to the reactor would introduce river water to the reactor vessel,and recirculation back to the river requires isolating the Alternate Core Spray System which, in turn, places the Alternate Core Spray System inoperative. ALTERNATE TEST: Valve will be part stroked during power operation and full stroked each cold shutdown and refueling outage, but not more often than every 3 months. I i i f

1 [] RPLIEF REQUEST BASIS 1 VALVE: 38-30-001 CATEGORY: B CLASS: 3 FUNCTION: TO OPEN UPON INITIATION OF THE ALTEPSATE CORE SPRAY SYSTEM TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Exercising this valve during power operation would intro-duce river water into the alternate core spray piping. The flushing of this piping requires isolating the j Alternare Core Spray System from the reactor, thus plac-ing the system inoperative. ALTERNATE TEST: The valve will be exercised for operability each cold shutdown and refueling outage, but not more often than -y every 3 months, s 1 l l l

) RELIEF REQUEST BASIS VALVE: 38-30-002 CATEGORY: B CLASS: 3 FUNCTION: TO OPEN UPON INITIATION OF THE ALTERNATE CORE SPRAY SYSTEM TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Exercising this valve during power operation would intro-duce river water into the alternate core spray piping. The flushing of this piping requires isolating the Alternate Core Spray System from the reactor, thus plac-ing the system inoperative. ALTERNATE TEST: The valve will be exercised for operability each cold shutdown and refueling outage, but not more often than every 3 months. i

\\ / RELIEF REQUEST B4 SIS l VALVE: 52-26-009 CATEGORY: A/C CLASS: 3 FUNCTION: TO CLOSE ON CONTAINMENT PRESSURIZATION AND TO OPEN AND ALLOW MAKE-UP FLOW TO THE SEAL INJECT RESERVOIR TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: The only safety related position for this valve is shut, and the only way to verify velve closure is during leak rate testing at refueling outages. ALTERNATE TESTING: Valve will be verified shut (safety related position) during leak rate testing performed at refueling outages. i e I I l l

RELIEF REOUEST BASIS VALVE: 53-25-001 CATEGORY: B CLASS: 2 FUNCTION: LOW PRESSURE CORE SPRAY SUPPLY ISOLATION TEST REQUIREMENT: Exercise valve for operability every three months. 4 BASIS FOR RELIEF: This valve 2d to operate at low plant pressure (30#); to e, . rhis valve during plant operations could cause an overpressure condition in the system which supplies the valve and depressurization of primary through one check valve. In addition, to open this valve, it would require initiating 30# pressure signal and. reactor low level, which will also actuate a reactor scram, IGIV closure, and auto start of the High Pressure Core Spray Pumps, which will thermal shock the core spray nozzle by injecting cold water into the reactor vessel. Also, the pressure between 53-26-001 and 53-25-001 is unknown. ALTERNATE TESTING: This valve will be exercised at each cold shutdown and refueling outige, but not more often than every 3 months. r I t

i I ' ) RELTEF REQUEST BASIS I VALVE: 53-25-002 CATEGORY: B CLASS: 2 PUNCTION: CORE SPRAY PUMP SUCTION WATER SUPPLY TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: This valve is in the ECCS path and is normally open. Operating this valve during reactor operation for in-service testing renders the High Pressure Core Spray System inoperative by isolating pump's suction line from the overhead storage tank. ALTERNnTE TESTING: Valve to be exercised at each cold shutdown and refueling outage, but not more often th3a every 3 months. 's l I t

( RELIEF REQUEST RASIS VALVE: 53-25-003 i CATEGORY: B CIASS: 1 FUNCTION: CORE SPRAY PUMP DISCHARGE TO CORE SPRAY BUNDLE -TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: This valve is in the ECCS path and is normally open. Operating this valve during reactor operation for in-service testing renders the High Pressure Core Spray System inoperative by isolating the pump discharge from the reactor vessel. ALTERNATE TESTING: Valve to be exercised at f.ach cold shutdown and refuel-ing outage, but not more often than every 3 months. _) ) J 1 s' l' /

) RELIEF REQUEST BASIS VALVE: 53-25-0014 \\ CATEGORY: B CLASS: 3 FUNCTION: ISOLATE !!IGH PRESSURE SERVICE WATER FROM TIIE CORE SPRAY SYSTEM TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Exercising this valve during plant operation would introduce river water into the Core Spray Pump suction line. This exercising will require isolating and flush-ing this portion of the system which, in turn, places a backup water source for the High Pressure Core Spray System inoperative for sa extended period of time. ALTERNATE --} TESTING: This valve will be exercised at each cold shutdown and refueling outage, but not more often than every 3 months, t V

) RELIEF REQUEST BASIS f VALVE: 53-25-008 l CATEGORY: D CLASS: 2 h TUNCTION: CORE SPRAY PUMP SUCTION SUPPLY STANDBY TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: This valve is in the ECCS path and is normally open. Operating this valve during reactor operation for in-service testing renders the High Pressure Core Spray System inoperative by isolating pump's suction line frem the overhead storage tank. ALTERNATE TESTING: Valve to be exercised at each cold shutdown and refueling outage, but not more often than every 3 months. ) 4

.) RELIEF 'EQUEST BASIS VALVE: 53-26-001 CATEGORY: C CLASS: 2 FUNCTION: PREVENT EACKFLOW FROM REACTOR PIANT TO CVERHEAD STORAGE TANK TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Establishing flow through this valve would require open-ing 53-25-001 by initiating reactor pressure (30#) and lo water level signals, which would trip the reactor and close the MSIV. In addition, to obtain flow through q this check valve, the reactor pressure is required to be below 30 psig. ALTERNATE TESTING: This valve will be exercised at each cold shutdown and -}; refueling outage, but not more often than every 3 months. { 1 l t l

RELIEF REQlEST RASIS VALVE: 53-26-002 CATEGORY: C CLASS: 1 FUNCTION: PUMP 53-06-002 DISCIIARGE CIECK VALVE TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Any exercising of this valve would require injecting cold high pressure core spray water into the reactor vessel, resulting in therral shock to the core spray nozzle and cold water insertion to the reactor. ALTERN.TTE TESTING: This valve will be exercised each cold shutdown and refueling outage, but not more often than every 3 months. _) 4 Y

n i 1 RELIEF REQUEST BASIS I VALVE: 53-26-003 CATEGORY: C CLASS: 1 TUNCTION: PUMP 53-06-001 DISCHARGE CHECK VALVE TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Any exercising of this valve would requir6 injecting cold high pressure core spray water into the reactor vessel, resulting in thermal shock to the core spray f nozzle and cold water insertion to the reactor, o ALTERNATE TESTING: This valve will be exercised each cold shutdotm and refueling outage, but not more often than every 3 months. l .1 i l l Y

'] ) RELIEF REQUEST BASIS VALVE: 53-26-0084 CATEGORY: C CLASS: 2 FUNCTION: TO ALLOW FLOW FROM IIIGli PRESSURE SERVICE WATER SYSTDI TO THE liIGli PRESSURE CORE SPRAY SYSTEM AND PREVENT BACKFLOW FROM OVERiiEAD STORAGE TANK TO IIIGli PRESSURE SERVICE WATER SYSTEM TEST I REQUIREMENT: Exercise valve for operability every 3 months. l BASIS l FOR RELIEF: Full stroke exercising this valve would introduce river water into the stainless steel Core Spray System supply 1 line, which would require flushing to clean up the ~ system to preclude conditions susceptible to stress l corrosion. The 9bove-stated problems apply to any plant condition. In addition, mechanically full stroking ') this valve by disassembly is impossible because this valve cannot be isolated from the overhead storage tank. 'i ALTERNATE TESTING: Valve will be part stroked with demineralized water each cold shutdown and refueling outage, but not more often than every 3 months. '1 me

RELIEF REQUEST BASIS VALVE: 55-25-003 CATEGORY: A CLASS: D FUNCTION: TO ISOLATE CONTAINMENT VESSEL FROM OFF GAS SYSTEM TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: To exercise this valve during plant operations would require inserting a high Containment Building pressure signal which could cause other safety system actuations and place the plant in an unsafe condition. ALTERNATE TEST: Valve will be exercised for operability each cold shutdown. . _ _. ~. _,._

l RELIEF REQUEST RASIS VALVE: 60-25-001 CATEGORY: B l CLASS: 3 FUNCTION: BORON TANK OUTLET i TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Valve 60-25-001 is in the Boron Injection System path and is normally closed during reactor operation. To test this valve, manual valve 60-24-004 must be closed, in order not to allow boron solution to be injected into the reactor coolant system by the Emergency Core Spray pumps. Subsequent steps after testing of 60-25-001 requires closing manual valves 60-24-003 and 60-24-009 and fluahing with demineralized water through the flow ( path consisting of open valves 60-23-002, 60-25-001, J ) 60-24-004, 60-24-010, 60-25-005 and out 60-23-005. Both Core Spray Pumps must be turned to "off" while testing j and flushing valve 60-25-001, which places the Boron ( Inject System and the High Pressure Core Spray System inoperative. 1 ALTERNATE TESTING: Valve to be exercised at each cold shutdown and refuel-ing outage, but not more often than every 3 months, t t

i RELIEF REQUEST BASIS VALVE: 60-25-002 CATEGORY: B CLASS: 1 FUNCTION: BORON VALVE TO PRIMARY SYSTDI FROM CORE SPRAY Palp DISCHARGE TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Valve 60-25-002 is in the Boron Injection System and is normally closed during reactor operation. To test this valve, it requires turning both Emergency Core Spray Pumps to "off" and during the test, this valve allows a flow path that eliminates Emergency Core Spray, which places the Bonon Inject System and the liigh Pressure Core Spray System inoperative. ) ALTERNATE TESTING: Valve to be exercised at each cold shutdown and refuel-ing outage, but not more often than every 3 months. L

L )- RELTEF REQUEST BASIS VALVE: 60-25-005 CATEGORY: B CLASS: 3 FUNCTION: BORON TANK OUTLET STANDBY TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Valve 60-25-005 is in the Boron Injection System path and is normally closed during reactor operation. To test this valve, manual valve 60-24-010 must be closed, in order not to allow boron solution to be injected into the reactor coolant system by the Emergency Core Spray pumps. Subsequent steps after testing of 60-25-005 requires closing manual valves 60-24-003 and 60-24-009 and flushing with demineralized water through the flow path consisting of open valves 60-23-002, 60-25-001, 60-24-004, 60-24-010, 60-25-005 and out 60-23-005. Both Core Spray Pumps must be turned to "off" while testing and flushing valve 60-25-005, which places the Boron Inject System and the High Pressure Core Spray System inoperative. ALTERNATE TESTING : Valve to be exercised at each cold shutdown and refuel-ing outage, but not more often than every 3 months. o h )

f i I f RELIEF REQUEST BASIS 5 VALVE: 60-25-006 CATEGORY: B CLASS: 1 FUNCTION: BORON VALVES TO PRIMARY SYSTEM FROM CORE SPRAY PINP DISCHARGE TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Valve 60-25-006 is in the Baron Injection System and is normally closed during reactor operation. To test this valve, 't requires turning both Emergency Core Spray Pumps :.o "off" and during the test, this valve allows a flow path that eliminates Emergency Core Spray, which places the Boron Inject System and the High Pres-sure Core Spray System inoperative. ) ALTERNATE TESTING: Valve to be exercised at each cold shutdown and refuel-ing outage, but not more often than every 3 months. s o 4 i l

. ) RELIEF REOUEST BASIS VALVE: 60-26-001 CATEGORY: C CLASS: 2 FUNCTION: TO ALLOW FLOW FRCN BORON SOLUTIN TANK TO THE SUCTION OF THE HIGH PRESSURE CORE SPRAY PUMPS AND TO PREVENT BACKFLOW FROM THE OVERHEAD STORAGE TANK TO THE BORON SOLUTION TANK DURING VALVE CYCLING TEST REQUIREMENT: Exercise valve for operability every 3 months. BASIS FOR RELIEF: Cycling this valve during plant operation would render both the Boron Inject and High Pressure Core Spray Systems inoperative. Furthermore, full stroking this valve at any time would inject boron solution with the high pressure core spray pumps into the reactor coolant system. The reactor coolant system does not contain boron during normal operation. ALTERNATE TESTING: Valve will be part stroked with demineralized water each cold shutdown and refueling outage, but not more often than every 3 months. P

1 v RELIEF REQUEST BASIS VALVE: 62-214-005 CATEGORY: A/E CLASS: 2 FUNCTION: TO BYPASS SHUTDOWN CONDENSER VENT TO OFF-GAS VALVE 62-25-003 L TEST REQUIREMENT: Exercise valve for operability every three months. DASIS FOR RELIEF: This valve is nonnally locked in the closed position and is a passive valve,not requiring a change in position for any plant conditions. ALTERNATE TESTING: This valve will be leak tested and verified locked, in accordance with the ASME Code requirements for categories A and E. _) ?

RELIEF REQUEST BASIS VALVE: 62-25-001 CATEGORY: B CLASS: 1 i FUNCTION: TO ISOLATE THE SHUTDOWN CONDENSER FROM THE MAIN STEAM SYSTEM AND TO OPEN DURING PLANT MANUAL DEPRESSURIZATION TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: This system is not designed to operate during plant operations; therefore, exercising this valve would place the plant in an un-stable condition. ')h ALTERNATE TEST: The valve will be exercised for operability each cold shutdown. I

.. 9 RELIEF REQUEST BASIS VALVE: 62-25-011 CATEGORY: B CLASS: 1 FUNCTION: TO ISOLATE THE SHUTDCXfN CONDENSER FROM THE MAIN STEAM SYSTEM AND TO OPEN DURING PLANT MANUAL DEPRESSURIZATION TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: This system is not designed to operate during plant operations; therefore, exercising this valve would place the plant in an unstable condition. ) ALTERNATE TEST: The valve will be exercised for operability each cold shutdown. + - - -, .na nn

RELIEF REQUEST RASIS VALVE: 62-25-013 CATEGORY: B CLASS: 2 FUNCTION: TO OPEN DURING PLANT MANUAL DEPRESSURIZATION TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: Exercising this valve during plant operations could cause plant depressurization into containment if any of the following conditions actuate the Shutdown Con-denser System: 1) MSIV closure 2) Turbine Building steam isolation valve closure 3) 1325# reactor pressure ALTERNATE I TEST: The valve will be exercised for operability each cold shutdown, but not more often than every three months. 1 l 1

RELIEr REQUEST RASIS VALVE: 62-25-014 i CATEGORY: B 1 CLASS: 2 FUNCTION: TO OPEN DURING PLANT MANUAL DEPRESSURIZATION i TEST REQUIREMENT: Exercise valve for operability every three months. ~ BASIS FOR RELIEr: Exercising this valve during plant operations could cause plant depressurization into containment if any of the following conditions actuate the Shutdown Con-denser System:

1) MSIV closure -

2) Turbine Building steam isolation valve closure-

3) 13254 reactor pressure ALTERNATE

~) TEST: The valve will be exercised for operability each cold shutdown, but not more often than every three months. r

} r-

n. >

RELIEF REQUEST BASIS 1 VALVE: 64-25-001 CATEGORY: A CLASS: 1 FUNCTION: To allow bypassing the Main Stems Isolation Valve (64-30-001). TEST RE-QUIREMENT: Exercise valve for operability every.three months. BASIS FOR RELIEF: To exercise this valve during plant operations would require inserting a signal which would also actuate the Main Staam Isolation Valve, resulting in a scram. ALTERNATE TEST: The valve will be exercised for operability each cold shutdown. l

r i e l l s RELIEF REQUEST BASIS _ VALVE: 64-30-001 CATEGORY: A 1 CLASS: 1 FUNCTION: TO ISOLATE MAIN STEAM LINE INSIDE THE CONTAINMENT BUILDING TEST REQUIREMENT: Ex~ercise valve for operability every three months. BASIS FOR RELIEF: Movement of this valve from full open will-initiate a full scram. ALTERNATE TEST: Valve will be exercised each cold shutdown.

') RELIEF RE W T W U VALVE: 65-26-001 CATEGORY: A/C CIASS : 1 l FUNCTION: TO CLOSE ON CONTAINMENT PRESSURIZATION AND TO OPEN AND ALLOW MAKE-UP FLOW TO THE FEEDWATER SYSTEM TEST REQUIREMENTS: Exercise valve for operability every three months. BASIS 1 FOR RELIEF: Exercising this valve during plant operations would require stopping feedwater flow to the reactor, thus placing the plant in an unstable condition. The safety related function of this valve is shut, and the only way to verify valve closure is by leak testing, which is beyond the scope of normal cold shutdown testing. ALTERNATE 1 TESTING: This valve will be verified shte during leak rate test-ing at refueling outages. i

I ~ RELIEF REQUEST BASIS VALVE: 69-26-001 CATEGORY:. C CLASS: 2 FUNCTION: PREVENT BACKFLOW FRG1 IIIGli PRESSURE SERVICE WATER OR REACTOR PLANT INTO OVERilEAD STORAGE TANK (OHST) TEST REQUIREMENT: Cr.ercise valve for operability every three months. BASIS FOR RELIEF: Exercising this valve would require establishing full flow through the Core Spray System to the reactor, causing thermal shock of the core spray nozzle and cold water insertion to the reactor. ALTERNATE TESTING: This valve will be exercised each cold shutdown and refueling outage, but not more often than every 3 months. I i l

~1D RELIEF REQUEST BASIS VALVE: 73-25-021 CATEGORY: A CLASS: D FUNCTION: TO ISOLATE CONDENSATE RETURNING TO HEATING STEAM SYSTEM UPON A IIIGli CONTAINMENT BUILDING PRESSURE TEST REQUIREMENT: Exercise valve for operability every three months. BASIS FOR RELIEF: To exercise this valve during plant operations would require inserting a high Containment Building pressure signal which could cause other safety system actuations and place the plant in an unsafe condition. ALTERNATE TEST: The valve will be exercised for operability each cold shutdown. ]h

y e RELIEF REQUEST BASIS VALVE: 75-26-023 C CATEGORY ~ N s CLASS: 3 FUNCTION: PREVENTS BACKFLOW THROUGH PUMP WHEN PmiP IS IN STAND-BY, ALSO REQUIRED TO OPEN WHEN DIESEL PUMP STARTS FOR ALTERNATE CORE SPRAY TEST REQUIREMENT: Exercise valve for operability every 3 months. BASIS FOR RELIEF: The only full-flow / full-stroke flow paths in this system are to the reactor or recirculation back to the river. The path to the reactor would introduce river water to the reactor vessel and recirculation back to the river requires isolating the Alternate Core Spray System which, j in turn, places the Alternate Core Spray System inoperative. l -} ALTERNATE TEST: Valve will be part stroked during power operation and full stroked each cold shutdown and refueling outage, but not more often than every 3 months. i i i I

F. CATEGORY A VALVP. LEAK RATE TEST DATA SIIEET VALVE ID SIZE DATE TYPE "C" TEST DATA SIIEET: PART T LEAK MEASUREMENT Permissible Leak Rate SCril Measured Leak Rate SCrl! If Valve < 6", go to Sununary. If valve 16", complete Parts 2 and 3. PART T T MARGIN CALCULATION MR Maximum Permissible R = MR - T,R, Leak Rate MR - PR LR Measured Leak Rate R > 0. 5 PASS (this test). R105 FAIL PR Measured Leak Rate (previous test) ) PART TIT PROJECTION CAT.CULATION Estimate Projected Rate fer Next Test if: (1) At least 3 successive tests have passed, and (2) Leakage rates increase with time Projected Leak Rate for Next Test N/A SCrl! Projection below 1.1 x MR PASS Projection above 1.1 x MR FAIL SIDNARY OF RESULTS PASS FAIL N/A Part I 16" ( Part II Part-III ADDITIONAL C0'NENTS: S I GNiT1"ti: OF PI:iNON roNI.u't'T I Nr; T!!!'. it ? ;T __ _ _ Y

F. Pohl:R OITRATED VALVE o i STROKE THIE I)ATA Si[EET VALVE ?RPIDER DATE RANGE POR ALLOh'ABLE STR0!a; TIME: SEC. FEASURED STROKE TIME: SEC. Loss of air / nitrogen, valve: OPEN CLOSE Required: Loss of power, valve: OPEN CLOSE Required: REMARKS : f CALCIILATION: INCREASE IN STROKE TIMP I4easured Stroke Time (this test) Sec., R = Measured Stroke Time (previous test) Sec. IF ALLOh'ABLE STROKE TIME 1 10 SEC., R< l.5 Pass R 2 1.5 Pail IP ALLOh'ABLE STROKE TIME > 10 SEC., R < 1.25 Pa s s R2 1.25 Poil SIGNATIME OF PERSON PI:Rror:1!::(; YALVI: CYCL,1N(;: I

CORRECTIVE ACTION REPORT SHEET DATE REASON FOR CORRECTIVE ACTION: 1 CORRECTIVE ACTION TAKEN: l l 2 4 . SIGNATURE OF PERSON RESPONSIBLE FOR ACTION: DATE t 9 l

r LACBWR Oparnting Manual Ravicsd Volumm XI, R2rctor Cont 0inment Building May 1976 DATA SHEET 3.5.14 TYPE "C" LEAK TESTS Primary System Containment Isolation Valves GAUGE NO. TEST PRESSURE N 3 3 REACTOR MAIN STEAM ISOLATION AND BYPASS VALVE (M-6) G 4-30 -col A 2 0 8 Q 64-15-cci m TEST DATA: l/ Time At Start of Leakage Measurement i g y Time At Completion of Leakage Measurement 4 c 4 j Meter Reading Final Meter Reading Initial j COMPUTATIONS AND EVALUATION: Total Length of Test Hours s 3 Difference In Meter Readings SCF = g 3 Leak Rate Standardized SCFH o g I FEEDWATER CllECK VALVE (M-7) yc

,._ y f i

TEST DATA: i E , Time At Start of Leakage Measurement { Time At Completion of Leakage Measurement L g Water Collected Liters a?' d COMPUTATIONS AND EVALUATION: 8 _[ Total Length of Test Hours O 3 ', Leak Rate Liters / Hour jo i Leak Rate Standardized SCFH _2 9 Leak Rate (SCFil) Leak Rate (Litern/ilour) x.160' g = s 2 r ACCEPTANCE CRIT j j 22.4 7 SCFl! - Total for MSIV, PSIV Bypass, and Feedwater Check valves. B REMA RKS : ? i d DATE PERFORMED BY E (Operator) S2 APPROVED DY (Snif t supervisor) REVIEWED IlY (Operations Supervisor) t - t i ti Sheet 1 of 5 V

LACZWR Op3 rating Manual Revised Volume XI, Rscctor Contoinm$nt Building May 1976 DATA SHEET 3.5.14 - Primary System Containment Isolation Valves - (Cont'd) B DECAY HEAT j!iLOWDOWN AND STEAM TRAPS DRAIN TO HOTWELL CONTAINMENT ISOLATION VALVES (M-17) 56-15-008 4nn,31 - 2.5-oi r - q TEST DATA: E 2 Z Time At Start Of Leakage Measurement 5

Time At Completion of Leakage Measurement 5

Water Collected Liters $c 9 COMPUTATIONS AND EVALUATION: E M k Total Length Of Test Hours $. \\ Leak Rate Liters / Hour 3 g" Leak Rate Standardized SCFH ~ 3 Leak Rate (SCFH) Leak Rate (Liters / Hour) x .1603 = g N ACCEPTANCE CRITERIA: . 375 SCFH (

Reference:

Tech. Spec. 5.2.1.3(b)) } } If total leakage for both valves exceeds.375 SCFH, the individual g t leak rates must be determined or the valves repaired or adjusted as

T necessary to reduce total leakage to <.375 SCFH.

Technical Speci-fications permit.375 SCFH through each valve but this test does f ;jnot provide for individual measurement. h e ! REMARKS: R h ' O Y o,,- ^ 4 k U DATE PERFORMED BY {y (Ope rator) m j APPROVED BY 5 E (Chif t Supervisor) E t B f REVIEWED DY j (operations Supervisor) Z .21 "O Sheet 2 of 5 P

LACBWR OpOrcting Manual Revised Valume XI, Racctor Containment Building Mny 1976 ^ ~b t/ DATA SHEET 3.5.14 - Primary System Containment Isolation valves - (Cont'd) SHUTDOWN CONDENbER VENT TO OFF-GAS (M-19) 61-1F-0 03 ~ 3 TEST DATA: Time At Start Of Leakage Measurement w ] Time At Completion Of Leakage Measurement 9 L e Meter Reading Final E 1 4 Meter Reading Initial 5 s ' COMPUTATIONS AND EVALUATION: E , Total Length Of Test Hours 3 Difference In Meter Readings SCF

== o n 4~ j b Leak Rate Standardized SCFH A-ACCEPTANCE CRITERIA: .375 SCFH (

Reference:

Tech. Spec. 5.2.1.3(b)) 5 I ". ) REMARKS : g U D 1 h a E o gm O DATE PERFORMED BY ~ 3t (Operator) J ? APPROVED BY j (Shift Supervisor) 2 B REVIEWED BY y ', (Operations Supervisor) 2 1 4 C's U L u6 Sheet 3 if 5 i

LACBWR Operating ManuG1 Rovised i volume XI, R0cctO Centninment Building May 1976 DATA SHEET 3.5.14 - Primary System Contafnment Isolation Valves - f (Cont'd) 33-2 c - oO f ANC S f-a g _ CQ 1 ALTERNATE CORE SPRAY CHECK VALVES (1-A) -~] TEST DATA: 3 Time At Start Of Leakage Measurement -it Time At Completion of Leakage Measurement n i Water Collected Liters l k COMPUTATIONS AND EVALUATION: 5 "I u g q Total Length Of Test _ Hours E 3 Leak Rate Liters / Hour 2 N O l Leak Rate Standardized SCFH = e( $ Leak Rate (SCFH) Leak Rate (Liters / Hour) x .1603 = ACCEPTANCE CRITERIA: . 375 SCFH (

Reference:

Tech. Spec. 5.2.1.3 (b) ) a s TEST PASS k

- RETEST
FAIL

{ u b ) }3 REFERENCE : Type "C" Leak Test - Technical Specification 5.2.1.3. x w o n i

If test is observed to be f ailing after several data points, o so extend to ensure six (6) sets of data are taken.

j 3 (

Reference:

Technical Specification 5.2.1.5) -Of *

List repairs performed before retest including MR No.

+ >m 3 REMARKS: 5 E a i B f Y k DATE PERFORMED BY j 4 (Operator) APPROVED BY (Shift Supervisor) REVIEWED BY (operations Supervisor)

LACCHR Opar0 ting Manunl Revingd valume XI, Rerctor Ccntninment Building May 1976 DWfA SHEET 3.5.9 TYPE "C" LEAK TEST Ventilation Discharge Dampers (M-21) 7 3-2 7-CO S ^*J o 73-1r - CC6 TEST DATA: h Initial Reading Af ter 1 Hour After 2 Hours j( Time -h Temperature OF oF OF j t Pressure Gauge No. 1 PSIG PSIG PSIG "g $ 3 Pressure Gauge No'. 2 PSIG PSIG PSIG 4 ) . COMPUTATIONS AND EVALUATION FOR VENTILATION DISCHARGE DAMPERS: g Pressure Change Pressure Change Leak Rate y Over 2 Hours Per Hour (SCFH) j ~ Pressure Gauge No.1 - O Pressure Gauge No. 2 =r (Pressure Change Per Hour) (3.9977 ft ) Leak Rate (SCFH) 3 = _E Q ACCEPTANCE CRITERIA: . 373 SCFH Pilximum (Paf.: Tech. Spec. 5.2.1.2(b)4) TEST

- RETEST PASS
FAIL j N 1

k i TYPE "B" LEAK TEST U k i 2 \\ Soap bubble test of outside flange of outside damper shows no leakage. TEST

- RETEST PASS
FAIL __

[ Cap of test connection between discharge dampers is in place.

a D l_R
If test is observed to be failing af ter several data points, extend points to ensure six (6) sets of data are taken.

(

Reference:

Technical Specification 5.2.1.5) E y a* List repairs performed before rotest including MR No. c & 1 5 REMARKS : e a t 2 o DATE PERFORMED BY I (Operator) APPROVED BY 7g (Shif t supervisor) g REVIEWED BY_ L MG (Operations Supervisor) Sheet 1 of 2 f

LACIWR Oparating Manutl R3 vised Volume XI, Rerctor Cantninment Building May 1976 DATA SHEET 3.5.9 c TYPE "C" LEAK TEST Ventilation Inlet Dampers (M-31) 73-15-oo a eo 73-ly-oos.. TEST DATA: Initial Reading After 1 Hour After 2 Hours j Time Temperatpre } ( Pressure Gauge No. 1 2 1 g Pressure Gauge No. 2 ) b ' COMPUTATIONS AND EVALUATION FOR VENTILATION INLET DAMPERS: U Pressure Change Pressure Change. Leak Rate E { Over 2 Hours Per Hour (SCFH) A 3 Pressure Gauge No. 1 Pressure Gauge No. 2 ( ressure Change Per Ho n) (3.9977 ft ) Leak Rate (SCFH) 3 = o 14.7 g q j l ~ } ACCEPTANCE CRI'.ERIA: . 375 SCFH Maximtun (Ref. : Tech. Spec. 5.2.1.2(b)4) O b TEST

- RETEST PASS
FAIL

), i TYPE "B" LEAK TEST Soap bubble test of outside flange of outside damper shows no leakage. E F y TEST

- RETEST PASS
FAIL e

Q R Cap of test connection between discharge dampers in in place. ~ I-g

If test is observed to be failing after several data points, extend points to ensure six (6) sets of data are taken.

3 (

Reference:

Technical Specification 5.2.1.5) 5

- List repairs performed-before retest including MR No.

2 REMARKS: B DATE PERFORMED BY i1 (Operator) APPROVED BY (Shift Supervisor) / REVIEWED BY t 116 (Operations Supervisor) Sheet 2 of 2 1.

LAC 2WR Operating Manunl Revised Volumo XI, Rstcter Containment Building May 1976 )b {]) DATA SHEET 3.5.12 TYPE "C" LEAK TEST Containment 7 g - ? r-o u ' Condensate Valve (M-26) q "EST_ DATA - HEATING STEAM: E 2 ; Time Gas Meter Reading 5 D One Hour Later 2 Initial Difference of Gas Meter Readings SCFH 5 TEST DATA - CONDENSATE: E 3 Time Gas Meter Reading 2 O One Hour Later e s Initial 3' i h Difference of Gas Meter Readings SCFH 2 ACCEPTANCE CRITERIA: Heating Steam Leakage---- .375 SCFH g l Condensate Leakage-------- .375 SCFH M l (

Reference:

Technical Specification 5.2.1. 3) J TEST PASS 8 O

- RETEST
FAIL

= 3 C o ;

If test is observed to be failing af ter several data points, extend points to ensure six (6) sets of data are taken.

s (

Reference:

Technical Specification 5.2.1.5) 3

- List repairs performed before retest including MR No.

5E e a b $ REMARKS: ? a DATE PERFORMED BY e I.2 (Operator) '* } (Shift Supervisor) j L.116 (Operations Supervisor) I

LACBWR Oparcting M nuG1 Rsviced Volume XI, Racctor Containment Building Mny 1976 h DATA SHEET 3.5.11 TYPE "C" LEAK TEST 23' Reactor Vent Header Valve Seat (55-21-003) (M-29) ~] TEST DATA: ~ g 3 Initial Reading After 30 Minutes Af ter F0 Minute: E Time [3f Tempe raturE OF OF O' Pressure Gauge No. 1 PSIG PSIG PSIs o Q Pressure Gauge No. 2 PSIG PSIG PSI < t COMPUTATIONS AND EVALUATION: Pressure Change Leak Rate i Over 60 Minutes (SCFH) j h} Pressuge Gauge No. 1 Pressure Gauge No. 2 =m b R Ek Leak Rate (SCFH) ( ressure Change Per Hour) (2.9061 ft3) = q 14.7 m

y g

ACCEPTANCE CRITERIA: .375 SCFH (Pcference: Tech. Spec. 5.2.1.2(b) 4) I T y f TEST PASS u g i

- RETEST
FAIL k k i

g e Test connection caps have been replaced. O % *If test is observed to be failing after several data points, ,y y extend points to ensure six (6) sets of data are taken. Lp (

Reference:

Technical Specification 5. 2.1.5) g

List repairs performed before retest including MR No.

E { REMARKS : c E $ h DATE PERFORMED BY D (Op era to,r) 1 o e APPROVED BY f_ Il (Shift Supervisor) REVIEWED DY {g) (Operations Supervisor) 1 116 l

.LACBWR Operating MInuni Ravicsd Volume XI, R:cctor Centainment Building May 1976 i DATA SHEET 3.5.17 TYPE "C" LEAK TEST Demineralized Water Containment Isolation Valva (M-ll) r g TEST DATA: R S Z Test Pressure / Gauge No. 5 5 Time At Start Of Leakage Measurement -,5 h 3 4 Time At Completion Of Leakage Measurement E $ I i Water Collected Liters { M COMPUTATIONS AND EVALUATION: E 1 Total Length Of Test Hours D 3 Leak Rate Liters / Hour f Leak Rate Standardized SCFH o q s b Leak Rate (Liters / Hour) x .1598 Leak Rate (SCFH) = k ) ACCEPTANCE CRITERIA _: .375 SCFH (

Reference:

Tech. Spec. 5.2.1.2(b) 4) h l TEST PASS f

- RETEST
FAIL i f o

2 R ,8 2

If test is observed to be failing after several data points, 4

cxtend points to ensure six (6) seta of data are taken. g (

Reference:

Technical Specification 5.2.1.5) 1

- List repairs performed before retest including MR No.

c 2 t REMARKS: 5 2 7 i DATE PERFORMED BY (Operator) j 4 APPROVED BY (Shift Supervisor) HEVIEWED BY (Operat1ons Supervisor) L-116 [}

LACEWR Op3 rating Manual-Reviced Volume XI, Racctor Containment Duilding May 1976 i l ~} DATA SHEET 3.5.18 l TYPE "C" LEAK TEST Condensate Demineralizer To Seal Injection Reservoir Makeup Line Containment Isolation Valve (M-18) if! TEST DATA: 2 n j R Test Pressure / Gauge No. Y -l Time At Start Of Leakage Measurement 7. t ( Time At Completion Of Leakage Measurement I Water Collected Liters 5 e U 4 s COMPUTATIONS AND EVALUATION: E y Total Length Of Test Hours Leak Rate Liters / Hour ~ { Q Leak Rate Standardized SCFH l N a Leak Rate (SCFH) Leak Rate (Liters / Hour) x .1598 = 4 ACCEPTANCE CRITERIA: .375 SCFH (

Reference:

Tech. Spec. 5.2.1.2(b)4) l TEST PASS

- RETEST
FAIL n n j b
If icrt is observed to be failing after several data points, extend to ensure six (6) sets of data are taken.

(

Reference:

Technical Specification 5.2.1.5) ey

- List repairs performed before retest including MR No.

O e j 1 REMARKS: D 2 v { ci DATE PERFORMED BY (Operator) y 12 APPROVED BY (Shift Supervisor) l itEVILHED BY (Operations Supervisor) L 116 i

F LACBWR Operating Manus 1 Revised Volume XI, REcctor Cantainment Building May 1976 ) DATA SHEET 3.5.20 TYPE "C" LEAK TEST HPSW Containment Isolation Valve (PF8) TEST DATA: A1 Test Pressure / Gauge No. n m Time At Start Of Leakage Measuremeni Time At Completion Of Leakage Measurement j Water Collected Liters ( f 4 COMPUTATIONS AND EVALUATION: u i Total Length of Test Hours Leak Rate Liters / Hour I Leak Rate Standardized SCFH % E 7 7 Leak Rate (Liters / Hour) x .1598 - 9 Leak Rate (SCFH) = 1 7 e t R S ACCEPTANCE CRITERIA: .375 SCFH (

Reference:

Tech. Spec. 5.2.1.2(b) 4) { TEST PASS u

- RETEST
FAIL

{a 2p o o

If test is observed to be failing after several data points, 3 0 extend to ensure six (6) sets of data are taken.

_5 (

Reference:

Technical Specification 5.2.1.5) I

- List repairs performed before retest including MR No.

E REMARKS: B 9 7 I DATE PERFORMED BY (Operator) g o APPROVED BY e .2 (Shift Supervisor) REVI EWED BY (Operations Superv2 sor) t n r>

LACnVR Opsratin9 Hanual Revised Volume ll, Reactcr Process Systens July 1979 l ) EMERGENCY CORE SPRAY SYSTFM VALVE CilECKLIST Val've No. Name Quad Posttton INTERitEDIATE FLOOR 53-24-007 Higli Pressure Service Water Control Valve 53-25-004 l l.A} _ _ ___.__._ Inlet NV _LO 3-23-004 Instrument Air to Crankcase Bicedoff IN C E 3-24-003__II.P._ Service Vater Control Valve 53 -2 5-004._0u t.l c t. _._ tw LO % 53-23-003 Instrument Air to Crankcase Bice.:!of f i;V C 53-24-009 H.P. Service Water Control Valve 53-25-c04 Bypass tN LC ~ i 53-23-002 H.P. Service Vater Tell-Talc Drain NW C 53-24-010, Control Air Supply to Valve 53-25-004 tw 0 E 53-24-002 Control Valves 53-25-002 and 53-25-0G8 Bypass i:E LC ~ ~ ' ~ SE LO 3 1 53-24-003 Pump _.l_A Suction _~ SE LO 53-24-004 Pump IB Suction h o gy 24-005__ Pump _lA Discharge [i~~ '._ SE L0 v b r~ SL LO lj 53.2_4 _006 Pump _ID Discharge l> 53 24-012 Pump 1A Plunger Sprof Supply Shutoff SE O G J 53-24-013 Pump IB Plunger Spray Supply Shutoff SE O ~ i3 53-28-c01 Core Spray Pucps Suction Hender Pressure Gauge Iso. ,SE O 53-28-003 Pump IA Discharge Pressure Guusc isolation SE O 2 Pump 10 Discharge Pressure Gauge isolaticn SE O ,- Q* 53-28-002 53-24-016 Pu p IA Crcnkcase Control Air Shutoff SE O ) '.-4 53-24-017 Pur.p 1B Crankcase Control Air Shutoff SE O 1 53-24-015 Test SE C ~

?

53-28.-004 Pump 1A Crankcase Pressure Indicaticn Shutoff SE O [ [.l.j 53-28-005 Pump IC Crankcase Pressure indication Shutoff SE O 4.< 53-23-C01 Orain to Rctentica Tanks SE C f[ FAILED FUEL LOCATI0ff HEA3EP. PLATF0P.M 'di FN LO 53-24-001 H.P. Service _and,_ Demineralized Vater in.let_ fM' O ~: 53-24-01' Centrol ry '. pply to Valve 53-25-001 r ,3 CCt: TROL ROSti

* '.y 5.

c. sl. 53-25-001 Low Pressure Ce.crgency Cor e Spray S ron Tonk Drain NE lc 60-24-001 ~

60-24-002 Bori>n TonfOutlet N~E lo NE lo 60-24-003 Control Volve 60-25-001 Inlet -NE~ lo 60-24 004 ~ConEl'V 17e~60-25-00 Tout'let ~ ~~ ~ 1 ~~ ~~ ~- ~ ~ ' ~ ~ Control Volves 60-25-001 oni60 25-005 60-24'005 BYPASS NE Ic NE lo 60-24-006 Sodium Pentoborate_ System Isolation _ NE c ( 24-007 Boron Tonk Demin. Water Supply 60-24-008 N2 Supply for Scienoid Volves 60-25-003 and -004 NE o 60-24-009 Ccarrol Volve 60-25-005 INLET NE lo 60 76010 CorItroTV lve 60 25-005 OUTLET NE lo ~ 60-24-011 Air Supply f r S len id Volves 60-25-007 and NE o nd -008 60-24-012 60-28-001 Boron Tonk Level Gauge Shutoff NE o i 60-28-002 Rcron Tgnk Level % witches Shutoff NE o l CONTROL ROOM 60-25-001 Core Spray Pump Boron Solution inlet Bench E c 60-25-002 Core Spray Pump Boron Solution Outlet Bench E c 60-25-005 Core Spray Pump Boron Solution inlet Bench E e 60-25-006 Core Spray Pump Boron Solution Outlet Bench E c J Date Time Shift Supervisor r 9-17
(- \\ LACBWR Operating Manual Ravised Volume II, Reactor Process Systems October 1979 j ) ALTERNATE CORE SPRAY VALVE CHECKLIST - (Cont'd) VALVE NO. NAME POSITION LO 38-2 4- 00 6__ Diesel _ Pump _lA Dis _qh_ar_ge___ O 38-24-016 Diesel Pump 1A Unloader Isolation 38-24-007 Diesel Pump 1A Strainer Backflush Supply C 38-24-008 Diesel Pump 1A Strainer Backflush Supply C rqpR 38-24-009 Diesel Pump 1A Strainer Backflush Discharge C Diesel Pump 1A Strainer Backflush Discharge C i g]k38-24-010 O f38-24-012 Supply to Cooling Water Valve v O S tX 38-24-013 Supply from Cooling Water valve C 38-24-011 Cooling Water Valve Bypass ~ 0 38-24-015 Gear Box Oil Cooling Supply h 38-28-004 Diesel Pump 1A Discharge PS-39-35-701 Isolation O $iN 38-28-005 Diesel Pump 1A Discharge Pressure Gauge Isolation O j j36-20-007 Diesel Pump 1A Auto Start Pressure Isolation O 5 q 38-24-017 Diesel Engine 1A Fuel Oil Pump Supply O M i 38-24-018 Primary Tank Fuel Oil Supply to lA Diesel Engine O 1 75-24-056 Diesel Pump 1B Discharge LO
f. ? ET~(T57'-~ Diesel Pump 1B Unloader Isolation O
75-24-058 Diesel Pump 1B Strainer Backflush Supply C ld. 75-24-059 Diesel Pump 1B Strainer Backflush Supply C 75-24-060 Diesel Pump la Strainer Bakcflush Discharge C e i.75-24-061 Diesel Pump 13 Strainer Backflush Discharge C OR,15-24-063 Supply to Cooling Water Valve O [;gy'75-24-064 Supply frca Cooling Water Valve O Cooling Water valve Bypass C j) 75-24-065 75-24-C66 Gear Box 011 Ccoling Supply O 75-28-033 Diesel Pump la Discharge PS-10 Isolation O l 75-28-034Diesel Pump 1B Discharge Pressure Gauge Isolation O i%1 ![ 3Jl 75-28-035 Diesel Pump 1D Auto Start PS-14 Isolation O ld ? 75-24-084 Diesel Engine IB Fuci Oil Pump Supply 0 [ l 75-24-085 Priming Tank Fuel Oil Supply to 13 Diesel Engine O l$~ OUTSIDE OF TCP. DINE BUILDING l, .E pi 75-24-049 North Fire Header Isolation LO 75-24-053 South Fire Header Isolation LO
2 JC s
h h REMARKS: m o ~ 3 PEPIORMED BY j DATE (Operator) ?# APPROVED BY r. (Shift Supervisor) k b if DEVIEWED DY g (Operaticns :iu pe rvi so r J '^
F. LACIWR Operat ing Manua1 Revised Volume II, Reactor Process Systems July 1976 ALTEHNATE CORE SPRAY VALVE CllECKLIST VALVE NO. NAME POy1 TION TURBINE BUILDING 38-28-001 Plow Transmitter Iligh Isolation O R 38-28-002 Flow Transmitter Low Isolation O .9 A 33-28-006 Preisurc Switch Isolation O-~ C Is C, 38-23-014 liigh Point Vent - 3 38-23-001 valvo 38-24-001 Dody Drain C__ 38-23-002 Valve 38-24-002 Dody Drain C 1 -3,j, 18.- 2.4. Q.01 A-C_f.o.to_r.-Onc.. rated Valve Isolat ion Valve LO~ D-C Ijp,t0,r _O_p_qrg.tej Va lve Isola t ion Va lve LO O g i, 38-24-002 AUTO a 38-30-001 A-C Motor-operated Valve ~ g l 38-30-002 D-C Motor-Operated Valve AUTO 38-28-003 Pressure Indicator Isolation O u 38-24-004 6-Inch Test valve LC q E 1 38-24_-0_03 Alternato Core Sprav Isolation LO .j h 38-24-005 Alternate Core Spray Isolation Bypans C_ 38-23-003 thgh Point Vent Root valve C g i-38-23-004 liign Point Vent Valve C, _ M -l-$ CONTAIN:'ENT BU!LDTNG -q{ n 33-23-016 Al ternate Core Spr ay IIcador Drain C. 38-23-017 Alternate Core Spray IIcader Drain Shutof f C 38-23-005 LCa Point Drain Foot Valve C~ ,[ t 38-23-006 Low Point Drain valve C" 38-23-007 After-Check Drain Root valve C[, [ l 38-23-008 Af ter-Check Drain Valve C_ _ v 38-23-012 After-Check Vent Root Valve C_ g 38-23-013 Af ter-Check Vc nt Valve C k 38-23-009 Containment MCA Dtain Foot valve C[ -~ J Containment MCA Drain valve C k , 38-23-010 Contair.nont TA Drain valve Test Conn < et ion C'~ o !I-38-23-011 &g P1 PE TtJNNEL jt"> ~ N 37-28-003 Co: t a i nment. Level Transni t. tern Inolation O ib !g, 8 37-28-004 Con ta i r.me rit Prennure Transni t t er Inolation O ~~ ~' ~ y 37-28-005 Containtoent Prennure Transmitter Drain C 9 U 37-78-096 Cor.t a i r.rr.ent Prensu re inelicat or/Transmi t ter ino). O ~ - - ~ ~ ~ C E 37-?3-007 t'on t a i rir.3on t f.evel Tr annmi t ter Upper Tuolat ion O " d. 37-78-009 Cor.t a i nme nt f.evol Trannmitter Upper Inolat ion O ~ ~ ~ ~ - ~~ U $ 37-23 010 ('on t a i r. men t f."vol Trannmi t"r T.ower Inolation 0 ~ ~ ~- 'I f 37-?H-003 Fr.n t a i rcr.ent Trvol Tran rii t t e r f.owor inolat ion O l l. !'f
<. !!n f
l
I LACilWR Operat ing M..nual lieviteu Volume 11, Reactor Process Syct.cm3 July 1979 i( ' SilUTDOWN CONDENSER SYSTEM val.VE CHECKLIST - (Cont 'el) W,VE NO. N A MtM, l'OS IT I_ON_, MAIN FLOOR q 62-23-007 Condenser Tube-Sido Drain C__ N 62-23-008 Condenser Tubo-Side Drain Shuror f C i; 24-012 Condenser Shell-Side Drain C .5l s 62-23-048 Condenser Shell-Side Drain Shutef f C 6'-23-003 Condenser Shell-Side Sampic Shutoff C g .j SlitT1'DOWN CONDENSER PLATFORM .I' i 62-24-001 Condenser Steam Inlet Valvo 1A T r.ola t. ion LO .I b 02-24-029 Valve 62-24-001 Dypass C ,l ] 62-24-0:16 Condenser St. cam Inlet valve in isolat ion IO .I 6 e2-24-037 Valve 62-24-036 Bypass C -.l 62-24-030 Condensor Steam Inlet Valve ID l'ypar: 62-24-039 Condenser Steam Inlet valve ID operat.or Air ::upply 0 b2-24-030 Condenser St eam Inlet. Valve 1 A Ol' erat er Air Supply O 62-24-016 Condenser Steam Inlet Valves Centrol Air Sul' ply 0 in 12-23-001 Steam Inlet Low Point Drain C' ..% b 2.' 3- 0 0 2 Steam Inlet. I.ow Point. Dratn Shutoff C '. T,N b 2.' 3 - 0 0 4 Steam in!ct liiyh I'o i n t. Ven t C 1 .If2 ti2-21 010 Stean Inlet lii oh l'o i n t Vent Shut nt f C-j e2.'3-030 Steam Inlet.Ilt9h I'o i n t ve n t. C i e h2-2 3-0 31 St eam Inlet liigh l'oint Vent Shut of f C .i fi2-24-019 Condensate liiyh Piont Vent. O .;g ti 2 - 2 4 -015 } 62-:'4-003 S! ut down condenser 811 f-t:au Vent V.ilve Ai r Supply 0 Shutdown Condenser of (-Gau Valvc Inb t I: olat i.on LO 'l r 62-24-On4 Shut.down Condense r Of f -e!.is Val ve: Outlet I soj a ': i on I. O . I e.. ? - 2 4 0 0 '. Shut.down condernie r uf f-8:an Va l v.-. Ily pan n C [ f,7-J H- 01.4 Want.e Gan floader l's essitre Gau'n* luolation O - 62.'8-001 Condenser Shel1 Sie!" IJpt'c Gauso Gl are l';olat ion (top) 0 N f.7-11-049 Second.t ry l'rersuuro i;auge luolatson O_,____ y e./. 2 9-c :2 conelenne r Sheel l S i el.* isppe r Caues.' t.;lar,n I t.ola tion (b it t.. rt) O i, e.J - 11 f,14 Shell S i t te Uppe r Hande Glars's lis a in U d c;
e. ' 'a-on i Conci"nne r Shol 1 :li'l" i.ow"r Cau se f:lasa luolatton i
(trp) O '!lf2-7H-fst!4 Contlenner S! ell Seele loower Gau.fo Glasn Inol.it ion ~ 9 (Ls it te rn) O__ l I ('*-23-015 Shell S i 'I !.ow' r daisite fila.as Isr.i i n C- '3i
r. 2 - / 9-41 1 condenner :.hel l S i'!" l ev"1 t'on' r olle r i nolat ion (top) 0 "~~~-~
l'.' l - ~~ (.' 78-012 r:o nele n r.c i 310 11 S ist" I." V" I '.'"n ' ' o l l e r inolatson ,.I tiottew) O
. / ~ /.! - o l l s'nnei..nno r She l l S

l" I.e ve' l C'en t e n t l e r nrainn
'Z
. -)
i n,.
Reviosd LACDWR Operating Manual Volume V, Service Syct 3 Jun3 1976 t) TABLE 5-2 VALVE LINEUP DEMINERALIZED WATER SYSTEM ~ l VALVE NO. NAME POSITION GRADE FLOOR R D 3 67-24-030 Demineralized Water Supply 0 O 3 g,,67-24-031 1A Pump _ Supply, 67-24-012 1B Pump Supply O j l 67-24-034 1B Pump Discharge q 67-2E0)37A Pump]Discha~rge_. O ~ ~ O 67-28-020 ~1A Di5 charge Gauge a y 0 3 67-28-021 1B Discharge Gauge 2 67-28-027 Root Isolation Valve For PT-F-37 0 h 67-28-022 PT-F-37 Isolation Valve O a 67-28-023 PS 7 Isolation Valve O i k) 67-28-024 PS 8 Isolation Valve O i g 2 1 67-24-060 Domineralizer Pumps Recirculation O 8,N 67-24-055 To Condensate Demineralizer System O 2 C 0 Y. 67-24-059 1B Coupling Fill C 1 67-24-052 1A Coupling Fill 2 R 67-24-043 Isolation For Machine Shop and Demineralized m/ ' 3 S Water Heater O To Sink and Demineralized Water Heater 0
--g 67-24-044 1
67-24-048 Cold Domineralizer to Washers O 67-24-046 Domineralized Water Heater Inlet O I 4 N 67-24-047 Domineralized Water Heater Outlet O E 1 67-24-049 Hot Demineralized Water To Washers -O g { 67-24-014 To Donkey Boiler (No. 3 FWH Areal C U TURBINE BUILDING MEZZANINE FLOOR j C p 67-24-041 Supply To condensate Storate Tank C 6 67-24-042 Supply To Virgin Storage Tank 0 O ' TURBINE PLOOR 3 2 i C s 67-23-020 Virgin Tank Drain I 67-23-021 Condensate Storage Tank Drain C, g; y 67-23-022 Condensate Storage Tank Fill From Virgin Tank C 2 j TUNNEL O 67-24-056 Plow Meter In O 67-24-05p Flow Meter Out C ) _R 67 2T 658 Plow Meter Bypass ,67-24-069 To Waste Water Pump Seals O ~ 67-24-068 To lA Waste Water Pump O j U 67-24-070 To 1D Waste Water Pump O 6,7 24-011, Demineralized Water to_ Containment O L ll6 5-18
LACBWR Operating Manual Reviced l Volume V, Service Sycte2 Juno 1979 .) TABLE 7 H.P. SERVICE WATER SYSTCM VALVE CHECKLIST - (Cont'd) NORMAL START AND f VALVE NO. NAME LOCATION OPERATION 'EURBINE BUILDING - (Cont 'd) 75-28-031 Service Water Tank Low Alarm Isolation Mezzanine O 75-28-032 Service Water Tank Low Alarm Isolation Mezzanine O 75-23-023 Service Water Tank Gauge Glass Drain Mezzanine C o 75-23-024 Service Water Tank High Alarm Drain Mezzanine C y 75-23-025 Service Water Tank Low Alarm Drain Mezzanine C 75-24-039 H.P. Service Water Hose Connection Main Floor C g 75-24-040 Fire Hose Connection Main Floor C g 75-24-042 H.P. Service Water Hoso Connection Main Floor C 675-24-043 Fire Hose Connection Main Floor C ri 75-24-069 H.P. Service Water Supply Containment G ~ Building Pipe Tunnel O s 75-24-070 if.P-~ Service Water Supply WastF" ~ rE $ Treatment Building and Gas Vault Pipe Tunnel O 75-24-019 HPSW to Backup Air Compressor Pipe Tunnel O y y 3 575-24-020 Backup Air Cor: pressor Return to-Standpipe Pipe Tunnel O j "y 75-24-083 containment Building and Waste Disposal Turbine Floor O __ S S Building Isolation ~ E T -p75 2F0'28"~TGbi~ns Oil'fank Fire Spray Flushing Connection C 75-23-029 Oil Storage Room East Header Flushing C Connection 75-23-030 Oil Storage Room West Header Flushing E C N Connection 75-23-034 Turbine Grade Fire Spray Header Flushing [4 y Connection C u h-75-23-035 Turbine Grade Fire Spray !!eader Flushing C Connection q Turbine Grade Fire Spray 1Mader Flushing 75-23-036 E C k Connection o 75-23-037 Turbine Grade Fire Spray Header Flushing i ]S C Connection s 8 % 75-23-038 Alternate Core Spray Valve Area Fire Spray C -D Header Flushing Connection j; 75-23-039 Alternate Core Spray valve Area Fire Spray Heador Flushing Connection C y r 75-23-040 Turbine Mezzanine Imvel Fire Spray Header C j Flushing Connection 75-23-041 Turbine Mezzanine Imvel Fire ' Spray Header 3 C y Q Flushing Connection d 75-24-090 Turbine Lube Oil Tank, Turbine Building f Grade and Mezzanine Sprays Isolation Valve O d 7-10 t u; t _ _ - - _ _ - _ - _ _ _ _ _ _ _}}

ML19331B641

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ML19331B641

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