ML20217R150

Rev 58 to OP-3C, Hot Shutdown to Cold Shutdown

ML20217R150
Person / Time
Site:	Point Beach
Issue date:	09/27/1993
From:	Shelet T WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20217Q567	List: L-97-526, Provides Suppl Info for GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217R145 ML20217R146 ML20217R148 ML20217R150 NPL-97-0526, Provides Suppl Info for GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves
References
NUDOCS 9709040262
Download: ML20217R150 (86)

Text

{{#Wiki_filter:}f 'W'"*%YT$t jf{ OPOC V PODir BEACH NUCLEAR PLA?TT MAJOR OPERNUNO PROCEDURIS } o. I Revision 58 IlOT S11UrDOWN TO COLD SIIUTDOWN Date 9 2'7 'f3 1.2 CORD ?SN$il"m%$NONNLENES"lsINT Unit c. DSS .LQW ' ~$"h b tlY[lA$hfltf _DM l.0 PURPOSE This procedure descrites the cooldown and depressuritation from short term cold shutdown through a refueling shutdown. 2.0 IECAttrlONS AND LIMrrATIONS Asterisk (*) indicates a Techrwxu krofication requiremem. NOTE: 2.1 Reds Do'not secure CRDM cooling until the reactor coolant temperature is 2.1.1 telow 200'F or any time the mechanism coils are energized. CRDM(s) will not te energized unless at least cat RCP is in operation. If O no RCP is in operation, all control rods will te insened and all CRDMs 2.1.2 deenergized as soon as possible. An exception is made for approved tests that specify scattor trip breakers shut and no RCP operating. 2.2 RCP5 All RCP operations must te perfonned within the requirements of OP~413, 2.2.1 ' Reactor Coolant Pump Operation.' ne charging line flow control valve must tw adjusted as necessary to 2.2.2 maintain the RCP seal flow to about 8 gpm. When the reactor is suttritical and the average RCS temp. is > 350'F. o 2.2.3' except fcr tests, at least one RCP shall be in operation. Both RCPs may te secured provided: )

a. No RCS boron dilution operations are pennitted,

.ak b, RCS sutsooling is mainte.ined a10'F, and L

c. The reactor trip btrakers are open.

Page 1 of 10 $5.. 9709040262 970827 PDR ADOCK 05000266 P PDR ^* " W M IG N M t5 K d; Q

ary3 ' ytp. ypn~x, ;Qb h ...p t! CP 3C [d: 'e' POINT BEACKNUCLEAR PLAW htAJOR OPERATING PROCEDURES }e Revision 58 IlOT SIIUTDOWN TO COLD SIIUTDOWN Date 9-2 '7 'f 3 1.3 CORD NUniiLE"S=$5'iYeNYEE!lNEllL'?$ Unit L DSS .th W _ "h b ~lsA$hflfY .Dnt ilYt 2 " ~ 1.0 PURPOSE nis procedure describes the cooldown and depressurization from short term cold shutdown through a refueling shutdown. 2.0 PPECAirrlONS AND LIMrrATIONS Asterisk (*) liuticate.1 a Tethrwas kafication requirement. NOTE: 2.1 Reds Do'not secure CRDht cooling until the reactor coolant temperature is 2.1.1 telow 200'F or any time the mechanism coils are energized. CRDht(s) will not te energized unless at least cat RCP is in operation. If O Do RCP is in operation, all control rods will te insened and all CRDhts 2.1.2 deenergized as soon as possible. An exception is made for approved tests that specify reactor trip breakers shut and no RCP operating. 2.2 RG3 All RCP operations must te performed within the requirements of OP-411 2.2.)

• Reactor Coolant Pump Operation.'

t The charging line flow control valve rnun be adjusted as necessary to 2.2.2 maintain the RCP seal flow to about 8 gpm. When the reactor is subcritical and the average RCS temp. is > 350'F. 2.2.3* except for tests, at least one RCP shall te in operation. Both RCPs may be secured provided: l 3

a. No RCS bomn dilution operations are permitted.

fv-

b. RCS subcooling is maintained a10'F, and

c. The reactor trip breakers are open.

Page 1 of 40 'pb 9709040262 970827 PDR ADOCK 05000266 P PDR s M QQW

' ~ ~ ~ ~ ~ - - _. _ _ 3., ... mg ,.. + pc A OP 3C PLANT MAJOR i /- Revliion 58 M >/ ' 4. . infNIING~ ""/ *'#! # 1' July 29,1993 r*' 4

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]/ , J@ya s g iihf,h,IITIDOWN 'IU COLD:SHtTrDOWN ~ An RCP shall not te started when RCS temperature is < > IIOTtSI ylp ~ y 2.2.4' ..,3,.ww t s. i the steam ('

s. There is a pressure absorbing volume in the pressurizer or n

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'gfeneraldr tute bundles, or b

b. Secondary water temperature of each steam generat

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/ .g 'ste temo'erature of the RCS. ~ At least o$e RCP abou!d te kept in service during ope + uf... If pump system during periods of little decay heat with a solid RCS 2.2.5 d on operation is secured, colder water will accumulate in the lo be restarting an RCP, a transient will occur. The RCP should no g" restarted la this condition unless absolutely necessary. Iffan RCP needs to be started under this condition, -,.i &. [ ? procedure should te fo!! owed: 9 -a[l%y%RIfR system temperature to rise to that equ [.

-y-Atto estimated steam generator metal temperature.

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b. blinimir'e the charging flow rate.

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c. Open allletdown orince isolation valves and maximize ltt d

from the RIIR system Just prior to r. tarting the RCP.

d. Reduce pressure to minimum required to start an RCP.

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c. Restart an F CP and observe pressure.

y CS For a shutdown other than refueling 1}f d ( 2.2.6 CS depressurized. temperatures, the RCPs should te secured j i R i h((,. from the core to the steam generators. q'3 $)j- + Eltam Genemtor/RiiR .= 2.3 During cooldown, both steam generato { 4 g 2.3.1 1 ip. secondary side, 9p O Page 2 of 40 ($k m. EY.bn.,. .ht?, [J> .M c ~"-~ -~

wn m *%+f kl.yw gen ~"wv"l 0 I y .....w N 4 dA._ m,,,e OP3C hF .,, -:,f,, POINT BEACH NUCLEAR PLANT MAJOR (, (" OPERATING PROCEDURES Revision 58 t July 29,1993

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}3p IlOT SIIUTDOWN TO COLD SHUTDOWN 'm When RCS temperature is > 350*F: t ,[ 2.3.2* {

n. De motor driven auxiliary feed pump discharge MOVs AF-4021 and AF 4023 (AF-4020 and AF 4022) muil be in the automatic con h,

mode. i

b. At least one main feedwater pumps control switch must te in NEUTRAL at all times to ensure automatic initiation of the auxiliary feedwater system on tal.o 50 level.

g Ensure water is available in the CSTs to provide for feed in case the u cooldown is performed on the atmospheric steam dump. If alternate 2.3.3 sources of water are required and the water treatment plant is not h'; available, the condenser hotwells should te pumped to the CST. As a last ,i g j; resort, the service water supplies to the auxiliary feedwater pumps should y be used. j O r When the ACS is on RIIR and in the temperature range of 350*F to M N 200*F, one irain of high head Si should be readily available for manual 2.3.4 t a, actuation fron' tl'c Control Room. F De RIIR system must not be placed in service until the hCS temperature b is s350'F arm the RCS pressure is about 400 psig. Flow through the 2.3.5 RllR system must bs initiated slowly to avoid thermal shc:ks. ? An RCS pressure interlock prevents the opening of Ril 7 2.3.6 H RCS pressure is <425 psig. ,s Y The upper pressure limit for F 'IR operatbn is 415 psig, which is the 2.3.7 [ LTOP actuation setpoint. De component cooling system temperature may te allowed to rise to g; 125'F for a maximum of two hours if necessary, during a cooldown while 2.3.8 I using the R;1R system h To maintain redundant decay heat removal capability, at least one RCP i must remain operable, including its suppon systems (CCW, seal injection, 3.9 f; ventilation) until the reactor has teen subcritical for > 65 hours DB single train of RIIR has demonstrated the ability to maintain the unit at / cold shutdown (<200'F) with RilR flow sl500 rpm and CCW flow through only one Rl!R 11X. 2.4 TemneraturellNmurt he max,imum cooldown rate for the pressuriier is 200*F/ hoar. 2.4. l

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~ - - - - - - 5h p.u,.* ,p;;f ' OP 3C e,A PIANT MAJOR p.. k G AOCEDURES' 'l T J1 1 3 ^ [ b F ~ >'HO?sugwCWN/ID COLD SHUTDOWN ~~ 4 De maximuin cooldown rate for the RCS is 100'F/ hour pi,y* ren y, u 3 4 'h M2.4.2* When RCS tcmp'erature is <360'F, the ad .gg Q .ik;;py: y a' 'Y92.4.3 be exceeded onif w!!h prior concurmnce of the DSS and DC l The reactor coolant temperature and pressure must be m 3 1 and to the right of the applicable cooldown rate curve, Figure. 2.4.4* "he beatup/cooldown curves are based on a uniform co cooling down, avoid step cooling the RCS. 2.4.5 De RCS,pressum must be <1765 psig and SI manua ,W. 7 i An exception the secondafy" side steam pressure is reduc (J 2.4.6 'A .? { . SAkL :7he RC5 h open to the armarphere when arry one j f: -NOTE: condizions k satigied: . }.

a. At least one primary marmoy is remowd.

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b. 'One PORV is maintained open.

i j p c, The reactor w.tsel hmd is unbolted. v PP6su'om snArt;' s' stas n>:m.ase'. 0 TOP When the RCS is <360*F and not open to the atmospher , k' '-rg tgf c* bpd 9 y3)% ~ 2.4.7

• system must be operable and enabled.

p{ When the RCS is not open to the atmospheir and either co temperature is 5275'F, no more than one high head f 2.4.8' 60 volt breaker operable, ne inoperable pump shall have p d .) The maximum pressurizer spray nozzle AT is 320*F. 2 A.9* 5*F If the T.,, coastdown resistors are installed, maintain G " h steam to prevent.the main feedwater system (mm " slugging t e 2.4.10 d T j 4 generators in response to a reactor trip, i p. To prevent thernial stratification of th f i e } 2.4.11 h line AT is displayed on the PPCS, RCS heatup/ coo!dow {j lower right hand corner q se Page 4 of 40 A.,. Y '- * ...e I. Mis;w l%&

<e m n w w .g w:w er r ym. s.a y.y RPi) Mf:%y <6th& ,c . g qQ, OP 3C A' ., lADENUCLEAR MAJOR, ? g TDW FROCEDURES Revision 58J V July 29,1993 IMr:MIFIDOWM10 COLD SHUTDOWN ..,2. During the RCS cool,%wn, the pressurizer to hot leg AT increases above y 2.4.12 j. normal operating' AY(&T limit is s210'F). The affect of a pressurizer s g insurgeloutsurge with a large AT is to tapidly cool, then reheat the pressurizer lower head (as level is raised and then lowered), insurges } .L should be svolded as much as possibk by anticipating the effect operator ' f,. actions will have on'the RCS Recovering level slowly following an d insurge, and by mElalg 22 banks of PZR backup beaters on during s tN cooktown with a bubble established. Maintaining the heaters on will - 1" I~ ! minimize tae effect'or a small insurge. v When the RCS cold leg temperature is sl60*F, only one RCP may be in if. s 2,4.13 operation. This is'to ensure the LTOP setpoint of 415 psig adequately .f'( protects the reactor vessel from an overpressuit condition when the AP across the core is taken ino account. The core f P with I pump running is g g 25 psid and with 2 pumps onning is 63 psid. To ensure adequate protection is provided.11 RCP shall have its control switch red tagged in c. pullout or its breaker red ti;ged out whenever RCS cold leg tempenture is ; sl60*F.' O.y s f b L. 4"i 2.5 SW Marcin/BotaftnD Whenever possible following a change in RCS boma concentration, in b 2.11 excess of 100 ppm, the boron concentration in the pressurizer and RCS [~ should be equalized to within 100 ppm by increasing spray flow through the pressurizer. Sprap ikiw can be increased by energizing additional ,s g: heaters (preferred) or adjutting spray valve position. j$ 3 , ' 3:W,V De RCS must be borated to a xenon-free 3% shutdown margin for a RCS j 2.17 temperature of 350*F prior to commencing cooldown. q 1 At least one RCP or RIIR system should be in service during boron 25.3* concentration changes or degassing operations. An RCP or RIIR pump must be in operation during dilution. _d c 3 3 De effect of boric acid addition should be observed in terms of the 2.5.4 detenor response' rate and prompt corrective action taken if the count rate j increases for unknown reasons, A For a shutdown. ther than refueling, boration should be programmed to ~ o 2.5.5 ? suit reactivity control.nceds (shutdown margin) and to minimize radiation levels in the steam generators. Avoid an excessive shutdown margin and. 4 W v' minimize the time spent cooling dowri below 300*F because RCP operation under these conditions transports core corrosion prodocts, k, s M e Page 5 of 40 h .5 irNigg, J Nh ,f' +' 3

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~ ~ .uW!?, e# .g,,. ;... o @} , PLANT'., OP 3C ~ MAJOR; SJ. OCEDURES Revision 58 KQ. J'E July 29,'1993 a 2~ h' COLD SHUTDOWN ~ 4 ~ H e w. ,x E f g ,Q Containment integrity is required whenever RCS temperature is a200'F. g Containment closure (per CL.lE) is required whenever there is fuel in the n+ e' 2) core and containment integrity is not maintained. k f. t'.: " % g b 'Ihe RHR to letdown crossconnect valve CV 369A must rem y ] P '2.6.h the RCS temperatum is <200'F. .h 2.7 Mishellaneous used during the cooldown, use .A d 2.7.13 mIf the atmospheric steam umps are t dy d N! ' d CHP-70, " Contaminated Atmospheric Ste e a )p$ _ N7 ~ @ calculation of radioactive releases. \\ ,' ; - 5; ( fib. N'l 2M The letdown gas stripper should not be rem u$W... ) LF .Ty[.92.7. i ,( W i'%

• opening of the RCS (s5 cc/kg hydrogen and 50.05 pc/cc Xe 133 radg J

N p.g i During extended outages with the reactor vessel head in place, water le 3.-. 9:/,, in the vessel should be kept at the vessel flange level or lower to preclude 2.7.3 suspended solids from reaching the CRDM latch assemblics. (Reference

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WNSD TB 77-14), dy INITI ALS _ [ e h( INITIAE CONDITIONS 3.0 s mp,The reactor is in the hot shutdown condition. - An exception is the je - w. 3.1 yL physics tests per Reactor Engineering procedures. g' J 3.2 ' At least one RCP is in operation. 3.31.g.Sgassing is required, then the leidown gas stripp 'If a refueling shutdown condition is required at EOL, then A i 3.4 5,'000 gallons of boric acid are available. 73.5 M Functional test of the LTOP system within the last 31 days has een?j ...- E o b 1 2 4 Cperformed by I&C. ~ . j-4 id ~ - - - - ~ - _ _ _ _ _ _ _ _ _ _ _. _

OP 3C Y POINT BPACH NUCLEAR Pl. ANT hWOR OPERATING PROCEDURES Revision 58 0 July 29,1993 IlOT SHUTDOWN TO COLD SilUTDOWN INmALS The testing referenced in this procedure and listed below (IT, ORT, 3.6 CL, special tests) has been identified as a requirement during the cooldown. Itt! Qeck M if reauirrd / CL-4D v TS 35 (36) / 1900 psid IT-200 (205) IT 210 (215) IT 24' (245) IT 250 (255; / / IT-270 (275) / IT 290 (295) IT 300 (305) / / IT-310 (315)* IT-320 (325) / i / IT-330 (335) 9 / IT-360 (365) / IT-5203 (525B) / IT-530 '535) IT-1030 (1035) 4 -~ / ORT 11 Initially called up in OP 13B or 01-79 Issue r, red tag series to the DSS for the components referenced in this 3.7 + procedure and the red tag list of Attachment A, A cooldown of the RCS will tend to lower containment pressure. NO7E: Do not allow contauunent pressure to become negatin dwing the RCS cooldown. Verify containment forced vent is secured if containment pressure 3.8 51 psig. If containmers pressure > 1 psig and a forced vent is in progr:ss, secure the forced vent per OP 9C when containment pressure reaches I psig. u q

9 x

[ 'Page 7 of 40 h

~- .. s e r.. . e m,s. OP 3C POINT BEACH NUCLEAR PLANT hiAJOR OPERATING PROCEDURES Revision 58 July 29,1993 9 HOT SHUrDOWN TO COLD SHUTDOWN INITIALS 4.0 PROCEDUPI 4.1 Prior to Cooldown A procedural sequence in performing Steps 4.1.1 through NOTE: 4.1.12 is not required. l Steps unhin Scaion 4.1 may be performed in corjunaion NOTE: suh EOL physics test on a noninterference basis. Determine the desired primary demineralizet configut 4 tion 4.1.1 and the desired purification flow rate from Chemistry. Then place the demineralizers m service per OP-SD, o# Og eM Section E. i,06 Circle, as appropriate, the demineralizers in service for the

• J

( 8,,, cooldown and update the status imid: Mixed Bed .%fA [dV ting Increase the pressurizer level program serpoint on TC-401C 4.1.2 in instrument rack C-107 from 20% to 30% in the manual b mode. Maumum letdown capability of the leidown gas suipper is NOTE: M gpm. Establish and maintain the desired purification flow rate f )h/ 7 4.1.) during the sutNquent cooldown per OP-5A, Section C. If required, initiate degassing of the RCS in accordance[ l' 4.1.4 with OP-5D, Section C. If regt -ed, perfort.: CL-4D. " Outage Valve inspection __ 4.1.5 .s - Checklis:." ~ If not performui during OP-3A and if required. then 4.1.6 perform IT-290 (295), " Inservice Testing of Auxiliary. k-4^^ Oi Feedwater System Check Valves and Flow Indicators? Page 8 of 40 y TQ9'h"Q7 p} N.7 e 3 m,,j.ygg ., jgu..=g,, <a aa.w:p o -__.. a_,4

~r-OP 3C f,

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POINT BPACH NUCLEAR PLANT v. MAJOR OPERATING PROCEDURES Revision 58 July 29,1993 I!OT SHUTDOWN TO COLD SIRJTDOWN IN111AL if17 200(205) is required, it should be completed prior to NO1E: requiring LTOP. Perform IT 200(205), " Inservice Test of PORVs and Block((4v 4.1.7 Valves," if required. 4.1.8 If not perfonned previously: g/fg

a. Perform a -cactor shutdown per OP 3B.

b. When all control rods are inserted, depress the reactor trip pushbuttons. Verify the reactor trip breakers and bypass breakers open.

k 52RT,sCX-52 BYA _d $2RTB W ' 52 BYB t'4 7 t NOTE: Reference Precautioru andlimitatforu 2.3.J. I G Borate the RCS to a Xenon-free 3% shutdown margin for a 'I 4.1.9 f RCS temperatute of 350*F or to the concentration specified j by reactor engineering, whichever is greater. A'_\\ f i Required boron concentration _A 57 ppm i 4.1.10 Verify proper blender operation:

a. Set the blender mode selector switch for " Auto M/M i

Makeup." ='

b. Adjust the blender controllers for the desired boren p/'7/D roncentration.

c. Divert to the HUT until sutu. c..no is enabled, gh#

d. Sample and analy2e the bend.r t ryt.

fo

e. Adjust ble:xict output as.equired O

r 4 Page 9 of 40 bn n., u, I u vs.r .e j ; g.a d.*.* %. + 4 y *,.rs;... pg gggggg f n w w

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OP 3C ' POINT BEACll NUCLEAR PLANT h1AJOR sr. OPERATING PROCEDURES Revision 58 July 29,1993 /" 3 I!OT SHUTDOWN TO COLD SIILTDOWN INITIALSS. .,,j' For a refueling shutdown only, and if the B IIUT has ) 4.1.11 (sufficient) level (-25% is required) of -5% B/A concentration availabic, commence a slow boration of the 0' 7] RCS to refueling shutdown per Attachment B Leave the blender set up for the boten concentration determined in b_ Step 4.1,8 If the purge supply and exhaust system will be requimd when RCS temperature is <200*F or the RCS is to be 4.1.12 drained, then perfonn TS-35 (36), " Local leak Test of e(.. i Containment Purge Valves," if required. 4,2 Cnoldcum to 400*F ^ A COOLDOWN TO <490*F WILL INITLtTC AUTO SI FROM STEAh! LINE LOW LOW ' CAUTION

• PRESSURE AT 530 PSIG UNLFES SI IS hiANUALLY BLOCKED, s

TIIE MAXIMUM COOLDOWN RATE FOR [ 1 l

• CAUTION *

/ TIIE RCS IS 100*F/IIR. e i g T11E RCS MUST BE BORATED TO A [ ' CAUTION

• XENON FREE 3% SI1UTDOWN h1ARGIN FOR A RCS TEMPERATURE OF 350*F PRIOR TO i'

COMMENCING COOLDOWN. s I NOTE: During the RCS coo 6-a ': A. Maintain the steam generators level @ 20-50% nan ow h range. l B. Ifpossible, maintain steam gerrator blastlours unless \\ othervise directed. i Commence manual plotting of the cooldown per 01-105. i/ 4.2.l RCS lleatup/Cooldown Plotting. 0 Pap 10 of 40 ,= ,n_ n, ^ - - -_.-__: ~ ~--~~ w.

OP-3C POINT BEACII NUCLEAR PLANT MAJOR 4 OPERATING PROCEDURES Revision 58 July 29,1993 O IIOT SilUTDOWN TO COLD SilOTDOWN ,LNITIA11 If the condenser is available, commence a cooldown to 490*F via the condenser steam dump by selectmg " manual" 4.2.2 on the condenser steam dump mode selector. switch and adjusting the output of condenser steam dump controller. PC-484, in the manual mode as required to attain the[ desired cooldown rate. Cooldown na the armorpheric steam dwnps will require a larger solwne ofs:condary makeupfrom muer treatment NOTE: and/or a reduction in SG blowlown rate of the unafected unit. If the condenser is unavailable, commence a cooldown to 490*F via the atmospheric steam dump by adjusting the j 4.2.3 [ output of atmospheric steam dump controllers, HC-468 and llc-478, in the manual mode as required to attain the A / Z y desired cooldown rate. e Secun: secondsty systems not required for the cooldown, [ C 4.2.4 jk per OP 13B as required. ,f}h )

E f

Stop the cooldown at an RCS temperature of 490*F. '4 4.2.5 READ AND UNDERSTAND ENTIRELY, SECTION 4.3 . j.

• CAUTION
• PRIOR TO DEPRESSURIZING TIIE RCS.

4.3 Denressuri7ation and IHock of SI Y Place the pressurizer pressure controller, IIC-431K, in the /g' / Y manual mode and adjust controller output to 50%. 4.3.1 h SPRAYING DOWN TIIE PRESSURIZER TO A f SYSTEM PRESSURE OF s1735 PSIG WILL

• CAUTION
• RESULT IN AUTO SI INITIATION UNLESS SI IS MANUALLY BLOCKFE, Place the controller for one pressurizer spray valve in an operating loop RC-431 A or B, in manual and adjust the 8/b 4.3.2 output for a controlled depressurization rate to 1800 psig.

At 1800 psig manually energize one bank of pressurizer 4 4.13 backup heaters. / 7 Ibge 11 of 40 i h q,y.;, ' wyg,Mhf }, 441 .;. iq .' $ f.:l$1b :f,f f

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gury y .... m < - 7 f = ' y.y7Ag,1, s OP-3C PLANT /. I MAJOR URES Revision 58 c

• ?

kly 29,1993 .e' INE-CIED SHUTDOWN INTTIALS 6 %sion an operator at C-01 to bkriSt when blocking/ //61 G: confitions are met. DO NOT DEPRESSURIZEBE2DW 1750 PSIG

• NMEP WITIIOUT VERIFYING S BIDCKED.

5kwly adjust the spray flow in the==ul mode for the Sow path selected in Step 4.3.2 :ani a maxjmum rate of 25 psig/ min. pressure decrease is drrned in the pressure /M f page of 1800 to 1750 psig. + [ Block both trains of SI when <!M psig and the "I.o Pzr y; Psess Block SI* permissive lightisenergized by positioning -Gr both the A and B tsain switches sete block position, then ((D p Am them to return to center pm6ian. Verify 'SI Blocked T 'in A* and W Blocked Train B",-1/ E EI" ?. Eghts are energized b 'e dw...g to, <1750 psig. / p. Q SI WILL AUTO UNBLDCK IF PRESSURIZER

• ETEre

{ PRESSURE IS ALLOWID'IU INCREASE ABOVE 1775 PSIG. MEELD TIIIS OCCUR, t,4 l. TIIEN REPEAT STEFS 43.2 TIIROUGII 4.3.7. K Continue depressurizing and sdbiEu at a pressure of I D' I 1200-1400 psig. Operate pressmixr spray and heaters as,/-1/ff 1 p quired. [: TIIE MAXIMIDI COOLDOWN RATE FOR 'TMIMP' [ THE RCS IS 100'T/IIR. y JEEE hing de remamder of the cooldown, iris desimble to = 22 bunk.s of pre.uurizer hexnan en when there is a This is to monumme a positin ourflow sn6Er he she preuurizer. jihannepressurizer into the RCS k she sage fire to lessen the des af a P2R irtsurgeloursurge on nr.*2R leur head.. M Enuns se following: 'i Tum on 22 banks of Pl R basur heaters while utilizing M[D --&-1 9 PZR spray to control RCS pres / b Page 12 cie [J, ; ppche,.m r I r,' ) ., t *[ ' M ' I rm j b-4 ..165 ,a p. , [,.j y, p, 4 ,s.

OP-3C POINT BEACH NUCLEAR PLANT MAIDE . r... OPERATING PROCEDURES f[l. nes Jd 25L FS f f llOT SHUTDOWN TO COLD SIlUTDOWN j 5 7 IN1'nALS (( Continue manual plotting of the cooldow pG-15 /A 2, 4.4.2 "RCS IIcatup/Cooldown Plotting.' ."j 4/ Continue to cooldown the RCS to 400'F.amt sabitte 4.4.3 temperattite at 400'F. /[~ dk 4.4.4 Depressurite the RCS to 1000 psig. This tut must be done with the pressuri:er solid no mamma:ar h NOTE: pressurizer liquid space to hot leg ATto <210'T Unit 2 Ontv Primarv to Secondary Interrity Test a lAUPue S 4.5 Applicable to Unit 2 only and in conjunction with Eddy th==r testing. The intent is to dislodge any entrapped im,+imme l sleeve pottion which might mask tejectable indicatimus dudug3mm y ( Current testing. (Reference 813 G5 K. P. Crowleyas J. C. Reisenbucchler memo PBPB 85 246) I ,#6 W' 4.5.1 Maintain RCS tempemture at 400*F (+5 -#g. i .g-EAit/ n 4.5.2 Verify normal letdown in service. ih 4.5.3 Bypass the low-low steam line pressure 53 sigsmig 3htV t k ICP 10.7. 7 After the prusuri:er i: solid, do not opne SrW o NO7E: spray wins to cool the pressurizer beanneapen completion of this 500 psid tut, a pirandwhdi&il be reestablished. f 4.5.4 Place the charging pump (s) in manual and adese 5 fi. pressurizer solid while maintaining theEC5pr

==-1t M 'i -1000 psig. C/ NOTE: Once the pressurizer is solid, it is no Innpranarannur maintain 22 banks ofpressurizer heatens an gnan s i Step 4.4.1) until a bubble is rentabli:.indkehrtSK A 4.5.5 Using the charging pumps, raise the RC3 peanne-ar W 1600 psig. f i i e i 6tidi$ hi.:_r . J.** N + ,4 ,p g,. c 4. M. %:,,,.

OP-3C ~ T POINT BEACH NUCLEAR PIANT MAJOR OPERATING PROCEDURES Revision 58 July 20.1993 HOT SIIUTDOWN TO COLD SHUTDORY ] INITIALS 4.5,6 Verify that the BCE e ---- -- - hs been maintained at ^ 400*F (+5 -0) far al hour tds: proceeding. ' CAUTION

• LOW PENOLIZDL FRESSURE SI AUTO UNBlJOG5 AT 1775 79G.

' CAUTION

• TIIE MAtansV AVIEnGE TEMPERA'I1JRE CIIANGEOFTHERGDURLNG AN INSERVKEIEAY TISY IS s10'F/IIOUR.

TIIIS 5 A TECHNICAL SPECIFICATION REQUIEDIEhT. h 4.5.7 Slowly raise RG ysessere toIMD psig. _ C/ 4.5,8 Maintain 22(D psig 0900 paid ymimary to secondary) for w 5 minutes,

• CAUTION
• DO NOT DDRESSLEEZE IIELOW 1750 PSIG

%TITRET TDtDYIEG TilAT S.I IS S BLOCEED '4.5,9 Reduce RCS purseme by =&=a charging pump speed control and, g i

a. Block SI sees <l765 p4gand the "Lo Pzr Press M

Block SI* pc:ammune ligkisenergized. f i ' CAUTION

• TES CHOEIT WILL AUTO b

CmOcxw PRtsSuRt ,t 3 CREASES ABOVE 1775 PSIG. C b, Verify *SINededToin A* and *SI Blocked Tmin B' lights ar: mmitdoedLpressurizing to W g < 1750 psy ,ig

• CAUTION
• 15 ACrnarI ATOR WILL INJECT IF y

BCS PimgERE REDUCED TO 0 <We PSE. )

c. Stabilize RC5;gessere sete range of 800-1000 psig.

%/ V O Pac 14 d 4) hp... s,.w.o ..a a.ar ~.. .e .,*Yc',. ls~ l =1 ^% ,,y n. _, t,, ~ [ r _ ~ " -r__

- :1Q , yr. OP 3C BEAC11 NUCLEAR PLANT htAJOR PERATING PROCEDURES Revision 58 C 4 July 29,1993 6 N

EstSHUTDOWN TO COLD SHUTDOW INITIALS

d. Establish a bubble in the pressurizer while maintaining t

RCS pr:ssure at 800-1000 psig and reduce pressurizer (3, O level to -50%. ~. S' {

e. Increase the pressurizer level pmgram serpoint on f

TC-401C in instrument rack C 107 from 30% to the T[ high end of the program (-50%) in the manual mode. g 5 ?

f. Return one of the charging pumps to auto, if desired.gk

3. blaintain a2 banks of PZR backup heaters on after stabilizing PZR level and utilize PZR spray to control d[

RCS pressure. (Reference Step 2.4.12) ~ h

h. Return the low-low steam line pressure SI signal to Y_

j, - normal per ICP 10.7. r - ( ~"~F[ Open CV 386, RCP No. I seal bypass valve. 3 r 4.6 /k Inservice Testing with RCS at 400'F h 4.7 Perfonn IT 300 (305), " Inservice Test of hiain Feed Line 0 4.7.1 E[ Check Valves," if required. Perform IT-240 (245), " Inservice Test of SI Accumulator,Td ?..' 4.7.2 i-Valves," if required. [ Perform IT 520B (525B), " Leakage Reduction and /Or Mao d o v: 4.73 1 Preventive hiaintenance Program Test of the SI Pump f.

1. r Tws 7tn (t L Suction Valves," if required,

% sa m

• urn l

Perform IT 530 (535), "I2akage Reduction and Preventive 4.7.4 hiaintenance Program Test of the RHR System," CPyb I Sections 4.0, and 5.0, if required. i t b 6 o Page 15 of 40 R;. I 4 a., e'

• $i

,, 7;, y4 - yg .p ?,eks [, i 4

,. 79 OP 3C POINT BEACH NUCLEAR PLANT MAJOR OPERATING PROCEDURES Revision 58 July 29,1993 HOT SHUTDOWN TO COLD SHUTDOWW _lhllMLS. Steps 4.&5, 4.&7, and 4.&B require entry into containment and NOTE: should be coordinated so only one entry is required. Reduce and maintain RCS pressure; < 1000 psig if IT-240 (245) was performed, or between 800 psig and 1000 psig if IT 240 (245) was 4.8 NOT performed and then perfonn the following: j Verify shut, the Si accumuktor isolation MOVs. 4.8.1 Shut If SI 841 A Shut '7 SI-841B s9 Do not exceed 760psig in the accumulators shen p NOTE: performing thefollowing step. Shut A train SI isolation valves. I 4.8.2 o Shut SI-878B Shut Fl # _ M 4 SI 878D 5% RB AND adjust S1 accumulator levels to 80 ( 760 psig, whichever occurs first,

1. f[

4 7 A accumulator pr/ h B cecumulator Red tag SHUT the following valve control, witches 4.8.3 ( I Red Tag Shut _ SI-835A A accumulator Red Tag Shut N_, SI-835B B accumulator Red Tag Shut C&\\. SI-839A Test line isolation <t[ Red Tag Shut % SI-839B Test line isolation Red Tag Shut h _ SI 839C Test line isolation Red Tag Shm c:w SI-839D Test line isolation { Y v i "O s 1 Page 16 of 40 Y. ( $$( 6d4N$$$isy,:s.. a s&

..% g,, 1 1* V d a., p,, o,, er "Il}.y w :m,,.

W.,,,, 3, ' q >4

'q e ~vunypu.. OP 3C .e. g POINT BEACH NUCLEAR PLANT MAJOR OPERATING PROCEDUPIS Revision 58 July 29,1993 ] 9 HOT SHUTDOWN TO COLD SHlTTDOWN _ INITIALS Per DSS / DOS direction, perform the following to cilher 4.8.4 P 15A or P 15B, safety injection pump P/3k M Pump selected to be removed from service Racked Out Qk _ Selected pump 4160 volt breaker racked out Racked Out ML _ + Selected pump 4160 volt breaker red tagged Selected pump 4160 volt breaker operating Ink Instelled mechanism, lock installed Pe form the following for 51 accumulator outlet MOVs. 4.8.5 Locked Open% SI 841 A bicaker locked open Red Tag Open%b SI-841 A breaker red tagged I ocked OpenGb'r - SI-841B breaker locked open Red Tag Open 6t-, SI-841B breaker red tagged Red Tag Shut @ SI 841 A handwheel ird tagged shut Red Tag ShutN.i _ ~ SI 841B handwheel red tagged shut Yq f Energize the digital' pressurizer /RCS pressure indicators on 4.8.6 C-04. ,[ Energized PI493 Energized gg PI-420 Perform IT 320 (325), " Inservice Test of CVCS Valves," if [V_ 4.8.7 h required. Phee the LTOP Systern.in Service / Commence SIG Hot Finsh 4.9 f TIIE MAXIMUM COOLDOWN RATE

• CAUTION
• FOR TIIE RCS IS 100*F/IIR,

[ Continue manual plotting of the cooldown per 01-105, I 9, 4.9.1 "RCS IIcatup/Cooldown Plotting " y(( Cooldown the RCS to a temperature of 370Y 380*F. jd 4.9.2 350-400 psig. 4.9.3 Reduce RCS pressure to Page 17 of 40 4- '-~i_i _ f ' ~ ~ ~' " g.. - - y,g g .7 <r -? -, g V

ewg . g,,. M OP 3C POINT BEACH NUCGAR PLANT MAJOR

r <.

OPERATING PROCEDURES Revision 58 i s' ' , l; July 29,1993 -j HOT SHUTDOWN TO COLD SHUTDOWN i 3 pg.. INITI AI.S_ 1 7,, - To prevent a single failure from affecting both PORVs. 7N 4.9.4 jf disable the high pressurizer pressure PORV actuation. y Y Mll-Red tag open slider TPI l1 in Riser 10 for PORV-430 3 A,j Red tag opea slider TPI 12 in Riser 10 for PORV 430 3 / .[a. Red tag open slider TAF 9 in Riser 9 for PORV-431C T f Red tag open slider TAF 10 in Riser 9 for PORV-431C Umt 2 P h __ Red tag open slider TNP-5 in Riser

• for PORV 430 Red tag open slider TNP-6 in Riser.'I rm PORV-430- C%.

Red tag open slider TAF 9 in Riseri for PORV-431CM Red tag open slider TAF-10 in Riser 56 for PORV 431C W__ 4.9.5 Verify RC 515 PORV block valve is open. ) 4.9.6 Verify RC-516 PORY block vaive is open. M_ 4.9.7 Verify RC-430 PORV control switch is in auto. Xd 4.9.8 Verify RC-431C PORV control switch is in aute. L Check the bistable status light "UT O/P PCV-430" OFFT[ -- 4.9.9 (reset). Ih Check the bistable status light "UT O/P PCV 431C" OFF NTA 4.9.10 (reset). 0 Arm I train of LTOP by turning the key operated switch G/b 4.9.11 for RC-430 to ON checking red armed light lit. + E 7 Arm the second train of LTOP by tuming the key operated switch for RC-431C to ON checking red armed light lit.$8, 4.9.12 v. }, TT-200 (2%) properly aligns the nitrogen and instrument air NOTE: nus solvesfor the FORVs for LTOP. osa T f 9 /is /+ 3 was not completed, then complete CL-4C. e 4.9.13 If IT-200 (205) 4c. Leap \\S.ODS ( EWN. U6e Sk+ Du+- k RC M Pag of40 0 1 kww , ~ ~;v. s pg r,.) : - 7 4, Y f__

4 OP 3C 700@ BRACH NUCLEAR P!. ANT MAJOR OPERATING PROCBDUKBS Revision 58 July 29,1993 9 H_0T 5HUTDOWN TO COLD SHUTDOWN No@ Chunistry that 5/0 hot soak has tegun, as length of soak may be offustet dependent on contaminant remomi. N01E.' Commence 12 hour S/0 hot soak at a temperatun specified Q 4.9.14 by Chemistry, if required. Time Staned __. Placo the RHR system in operation. 4.10 iteference Precautforu and umitations 2.3.4 NO7E: With high head St aligned per CL 7A. perform the 4.10.1 following modified !!neup: Pullout 84_

a. P 15A control switch Pullout Ed

b. P 15B control switch Shut EX"7 6.,

c. SI 827A normal BAT outlet Shut "R, 6; __

d. $1 E278 standby BAT outlet Open at:;g_

O

c. SI 825A RWST/S! suction MOV Shut

'M6 f'.

f. SI 866A P 15A discharge MOV Shut

_TC

g. SI 8668 P 15B discharge Mov

h. Place an operator aid plaque on C-01 betv.eenPlaque Installed g the SI 866 control switches Perform the preliminary system and valve li'neups of v-4.10.2 OP 7A with the exception of tl.e RHR train wannup.

i l. T11E ADMINISTRATn'E COOLDOWN LBIIT 4

• CAUTION
• OF 50*Fi110URIS IN EFFECT WIIEN RCS Si TEMPERATURE IS <360'F. TIIE ADMINISTRATIVE LBUT OF 50'F/IIR MAY BE EXCEEDED ONLY WITH PRIOR

}/, CONCURRENCE OF THE DSS AND DCS. THE TECII SPEC LBIIT OF 100'F/IIR SHALL [ NOT BE EXCEEDED. { Continue manual plotting of the cooldown per 01105, i 4.10.3 "RCS Heatup/Cooldown Plotting." I Cooldown the RCS to <350'F using any combination of steart dump,50 blowdown, and auxiliary feed while 4,10.4 maintaining SG tevel 20-50% narrow range. s,, Page 19 of 40 .< p ferwea,, "..;,g., 1 -'_- -____ N * ' ' M 'y Q 'ityy ; g +

. mim e, - y.- OP-3C POINT BEACH NUCLEAR Pl ANT MAJ.OR OPERATINO PROCEDURES Revision 58 July 29,1993 O !!OT SHUTDOWN TO COLD SHUTDOWN INIT1All When the RCS is <3'iO'F. warmup the RHR system per 4.10.5 OP 7A. Place the PIIR system in operation on the RCS per OP 7A. 4.10.6 NOTE: Refer to Step 4.9.13for completien of S/G sink requiremeras.

• CA UTION
• DO NOT EXCEED A PRESSURIZER I.IQUID SPACE TO IIOT LEG AT OF 210'F. THE PRESSURIZER MUST BE TAKEN SOLID PER STEP 4.10.10 PRIOR TO APPROACIIING THIS 13HT REFERENCE PRECAUTIONS AND 3,

IEfITATIONS 2.4.11. ' CAUTION

• ONE RCP MUST BE SECURED AND ITS

[ CONTROL SWITCH RED TAGGED IN p PULLOUT QB ITS BREAKER RED TAGGED j. RACKED OUT WHEN THE RCS COLD LEG i C TEMPERATURE IS c:160'F. h 4.10.7 Establish a desired cooldown nte of <50*F per hour on- ~ RHR. f ired in s 4.10.8 Secure the secondary systems when no langer tr4 u l'. accordance with OP 13B. l 4.10.9 U not completed per OP-13B or 01-79. then perform 4 .;,i; iT 310 (315), " Inservice Test of Main Steam Line f; Nonreturn Valves,* a cold shutdown requin. ment. If completed p r OP-13B or 0179, this step is N/A. f.-- {. t The preferred method ofRCS pre.tsure contro! when the NOTE: RCS is solid a to adjust the nuto serpoint of CV-135 low pressure letdoust controlkt to the ekstred RCS pressure while contivliing charging pump (s) speed in the nunual y mode. Take the pressuriter solid by manually controlling charging 4.10.10 pumps while cooling the pressurizer wuh spray flow ham 9 the operating RCP(s). y Page 20 of 40 W n 5. u. >;,n. 8 .h i j ', e' ., gg *, [ ,,j, ,4 ,3 s e.;,,y ',' ;Q.Q. Qy *. 3{p. %a . (.. ;- M* ~.

,,u u p, r OP 3C POINT BEACH NUCLEAR PLA. T MAJOR V OPERA 11NO PROCEDURES Revision 58 C* ( July 29,1993 ~ HOT SIIUTDOWN TO COLD SHUTDOWN =_ JNITIALS 1he cation may han been placed on line at normal NO7E: opemung temperature per Chemistry request. 1 7 3 When the RCS is <250*F, and for a refueling shutdown e 4.10.11 only, verify the cation deminetalizer has been placed in <f-fr k l l wrvice per OP 5D. Section E. j-Containment clasure is not required if containment integrity NOTE: b is to be maintainedfor the duration of the outage. ^ Commence monitoring containment closure per CL lE. 4.10.12 i " Containment Closuit Checidist." ik WTSE system opemtion when a containment ELRTis NOM? planned, is outlined in ORT 9 and ORT 17, When RCS temperature is <200'F and the VNPSE system 4.10.13 is to be operational, then perfonn the following. Step A is f' not required to be completed prior to B C, & D. Steps B, ,I C, & D must be completed in the order given. (N/A ,.[c',,y/ 4.10.13 substeps when an ILRT is phnned/ scheduled.) A(I c /* J %d E &C to complete ICP 3.11 Appendix B, (pdf y, #,

a. Q_,otif

" Containment Ventilation isolation Circuit Continuityj,/a/d(Ah f Check." J [ I

b. OI-(>t A, Section 4.0, " Removal of Purge Valve gDgb 1

Component Bypass Lines." a'

c. IT-360 (365), " Inservice Testing of Purge Supply and g

/M [ Purge Exhaust Valves."

d. OP-9C. Section B, " Purge Exhaust Valves and

(/Ik Containment Purge Supply and Exhaust Fans " a Clear the red tags on the main feed pump contiol switch (es) 4.10.14 and place both control switches to PULLOUT. Of e ,b4 Y previously performed, then N/A this step.) Control Switch Pullout t. P-28A Comrol Switch Pullout V 9 P 28B G Page 21 of 40 b n u.m.- ' U lGe f &, g, f y? f f d,

3 > hy "'* M t WMmrC*S?qT' +~ OP-3C POINT BEACH NUCLEAR PLANT MAJOR 4 OPERATING PROCEDURES Revision 58

1. f.

R July 29,1993 HOT SHUrDOWN TO COLD SHUTDOWN ? INIT1 ALS - Prior to reducing the RCS cold leg temperature to s160'F, .Cp 4.10 3 L secure one of the RCPs. _,_ N f}! Red tag the idle RCPs control switch in pullout QE its 4.10.16 / f breaker red tagged racked out. N Red tag shut SI 831B sodium hydroxide common supply / e 4.10.17 valve to prevent inadvertent loss of sodium hydroxidep 7 y during the outage, U When the RCS temperature is s180'F (preferred range 160*F-180'F) 4 A i. perform the fellowing RCS cleanup and purging operations, if 4.!!

required, g

The letdounflow path should be lep byr.using the VCT sia S-NOTE: y CV-110B&C after degas is complete.

• ^

2 k ' 4 Secure from the degas line:;p per OP SD Section C. 4.11.1 l $ Red tag shut CV 261 A H: supply to the VCT. Red tag g lj. W 4.11.2

shut, jj i

4.11.3 Align N: to the VCT with the N: PCV-114 set at M 30-40 psig. ~V Set the fine control regulator PCV-158 to supply N: to the d 4 H 4.l l.W h* VCT at -25 psig. 4 ll.JV Perform a purge of the VCT gas space to the vent header S h k f" bg4 by: 4

a. Start a wa~e gas compressor.

L e. l p (( (*^ p A

b. Open the VCT vent valve to the vent header cv 1%

C L/ J S 6 O N co y p1I4$ Li 7

c. Raise the VCT level to 90-95% by blending to the VCT k'.;

at a concentration equal to or greater than specified in h J // Step 4.1.9 while venting to the vent header. 0 Page 22 of 40 Y kMduOw.,. ,, p ri *',ic.A -. 5 ~ ~,., 'J

• n.

9... ;y. "" 3.M M Q, 1

,Y..

vA4 l OP 3C POINT BEACH NUCLEAR PLANT A. h!AJOR OPERATINO PROCEDURES Revision 58 i' July 29,1993 ~ f HOT SHUTDOWN TO COLD SIIUTDOWN '.ir INITIALS j

• CAUTION
• MAINTAIN Tile VCT PRESSLRE a20 PSIG FOR RCP SEALS WHEN RETURNING LEVEL TO NORh1AL.

d. Return the VCT level to normal by diverting to the M

i N__ HUT while backfilling with N:. N h __ 4.11.6 Cleanup of RCS per CAh!P-110-Sample, then purge the PRT per OP 4C prior to RCS 4.11.7 draindown if: p;

a. PRT H concentration is > 10%, or 2

b. With the VNPSE system not available (as prior to an ILRT and the PRT H concentration is >4% or the Yk) f radgas concentration is > 1x10E-3 c/cc Ne-133.

. + 4.12 Conduct Inservice Testine s Perform IT 530 (535), "Le. sage Reduction and Preventive jf, 4.12.1 Maintenance Pmgram Test of the RHR System." [ 47 4 Sections 6.0 and 7.0, if required. 'p 4 a-NOTE: Complete 17-530 (535) Sections 6.0 and 7.0 prior to .{ shifting letdownfrom RX-7021703 to RX-715C/CV-369L y 0 Lesdounflow control should be uith CV-135. RHR letdown Y NO7E: isolation uthes, RH-715C and CV-369.1 should be side open and not used as throttle va!>cs. THE FOLIDWING STEP WIIIINCREASE I a.

• CAUTION' t

LETDOWN FLOW AND CAUSE RCS PRESSURE TO DECREASE DUE TO THE i n HEAD OF THE RIIR PUMPS ON THE k LETDOWN SYSTEM. CV-135 SHOULD BE j F ADJUSTED AS NECESSARY TO MAINTAIN AN RCS PRESSURE OF -300 325 PSIG, p F fg e ji 1 9 ) Page 23 of 40 ( $Uhrdidh%m R

• 99

>If T, e*[{* 'f '. K /,. y$ .,. j,

1. ,$ : \\ -'

' j'l% 'q:;,(f. l, .g.

i 77p y a,y. o. OP 3C PODfT BEACH NUCLEAR PLANT MAJOR OPERATING PROCEDITRES Revision 58 July 29,1993 O" IIOT SIIUTDOWN TO COLD SIIUTDOWN INITIAll TITE RIIR TO LETDOWN CROSSCONNECT

• CAUTION
• VALVE CV-369A MUST REMAIN CLOSED UNTIL TIIE RCS TEMPERATURE IS <2G 'F, To maximize purification flow, establish letdown from 4.12.2 RIIR by positioning the following valves.

RII715C Slowly Open CV 369A Slowly Cyn CV-427 Shut CV-371A Shut b Perform IT-270 (275), " Inservice Test of SW 2880, SW h(T 4.12.3 /,3 Supply to the Turbine IIall,' if required. J Perform IT-1030 (1035), *ASME Section XI,40-MonthM g 4,12.4 Inservice Test of Auxiliary Coolant System," if required. p 4.13.Securine RCPN When the RCS temperature is s160'F, one RCP

• CAUTIONa l

must be secured. Reference Step 2.4.13. '.)' The RCS temperature must be reduced to 200-110*Fprior NOTE: to securing the last RCP nhm a contamment LLRTis gs t,

planned, tis *F G

The RCS temperature should be reduced to 50-M0"F prior \\y NOTE: to securing the last RCP to allowfor safe access to the RCS n M, fy)fi'1 for nvaintenance UNil'SS a higher temperature is spedfied for testing DE the Major item Work Ust specipes securing L ,3 pumps at a higher temperature. j { Prior to securing the last RCP s M; 4.13.1

a. Notify Chemistry to verify that the Co 58 activity is less K5_

t than i microcurie /cc. p I I i //4 [ t

b. Reduce RCS temperature to 90.WPF and maintain L

ld temperature for al hour iTNLESS a higher temperature i ? g is required for testing QB is specified in the Major item ~- Work List. Page 24 of 40 a g i @tz, E- ,jt ,j' O*!<m!& fg ' t, g 4 y..,. i 4/g.. - ' ,s 2 s.

,.. j-OP-3C 'O POINT BEACH NUCLEAR PLANT MAJOR OPERATING PROCEDURES Revision 58 e. July 29,1993 IIOT Sl!UTDOWN TO COLD SIUTDOWN lN_ m ALS_

c. Tag out the charging pump (s) per REI 19.0.

d. Arm the 'Potenth! Diluuon in Pmgress' alarm.

e. Note the position of HC Ill RMW to blender _ _

output. 11 a.my be necenary to increase the output of NOTE: 11C-111 to recche the annundator.

f. Test the " Potential Dilution in Pmgres: Alarm" by placing CV-Ill control switch to OPEN.

n-TEST SAT _ K UNSAT__ + {h

g. Return CV-Ill control switch to AUTO.

9 = h'v

h. Return HC Ill to the position noted in Step e.

Secure the last RCP, if desired. i. Ifit.thould become necenary to restart a RCP, pmceed per Precaution 2.2.4 and 2.2.5 of this procedure sud OP-4B. NOTE: b Adjust HCV-142 as required to maintain a #sitive n.- 4.13.2 labyrinth seal AP. g To prevent spurious alanns on the loose pans monitoring t 3 system when the RCPs are to remain secuted, decrease the 4.13.3 s gain of each of the six appropriate channels by rotating the ) F.S. range switch on the signal conditioner modules from ?,' 10 to 300 at C 25. y( l !} w e n. J th ( g b g g, f,f e J+ p,g g.- d u, 7.,, s; < gj. (, um

n . ~ ~ ~ ~.w,

s. u av

.OP 3C ~ INT BEACH NUCLEAR PLANT hiAJOR S . (T OPERATING PROCEDURES Revision 58 e, fc July 29.1993 IlOT SIIUTDOWN TO COLD SIIUTDOWN INITIALS _ Remove the RCPs from service by perfonning the 4.13.4 following: f 1 Verify that the reactor has been suberitical for >65 hours OR demonstrate that a single train of RIIR is capable of maintaining the unit at cold shutdown (<200'F) prior to remcving both RCPs from service. For demonstating single train capability, RIIR flow should be sl500 gpm and j, CCW flow through only one RHR IIX. m tTa. <m A RCP 4160 volt breaker - rack out Racked Out o.- A RCP 4160 volt breaker - red tagged ~ B RCP 4160 volt breaker - rack out Racked Out B RCP 4160 volt breaker - red taggt J 4.14 Continue the cooldown of the RCS to the desired system temperature. .g; When a containment ILRT is planned, a stable RCS temperature of 100-110,'F is required. 4.15 Denrrssurize the RCS to 100 nsic and then: 4.15.1 Shut CV-386, No. I seal bypass. 4.15.2 Shut the RCP No. I sea! leakoff isolation valves. Shut CV 270A Shut .n CV-270B m NO1F.: Reference Step 4.16 and IT-250 (255)for testing requirement. 4.15.3 Shut the RCP seal return containment isolation valves. Shut l h CV 313 Shut CV 313A l [ 4.15.4 If desired, depressurize the RCS to atmospheric pressure. PI-493 will indicate approximately 10 psig when the RCS is a. 4 at atmospheric pressure. i i Page 26 of 40 ~ g j ~.,h. ~ ] hW ' ' ' ' ~ * * ' Y yg, a ~ p,

OP 3C POINT BEACH NUCLEAR PLANT MAJOR OPERA'11NG PROCEDURFS Revision 58 HOT SHUTDOWN TO COLD SHUTDOWN ] INIT1 ALS_ e If the B HUT was used for boration during the cooldown 4.15.5 and if not previously done, complete the realignment of the [_ HUT recirc pump (P-9) per Step 1.6 of Attachment B. Isolate Manual Service Water Valves from Containment (Refueling 4.16 Ou: age Only) Isolate only the equipment listed betw. Red tag the control switches for containment fans in the 4.16.1 PULLOUT position with the series issued to the DSS, to prevent fan operation without cooling water to the motor. W 1 A1 Containment Fan Control Switch Red Tag Pullout e W 1BI Containtnent Fan Control Switch Red Tag Pullout. e_ W lCl Containment Fan Control Switch Red Tag Pullout sw W-1Di Containment Fm Control Switch Red Tag Pullout e 4.16.2 Verify SW shut to the affected unit. c SW 2907 em _ _ SW-2908 Record throttled n11ve ponnon ofSW-144 (U2 SW-273) on NOTE: red tag.theet. .c. 4.163 Shut SW-144 (U2 SW-273) and red tag. .c Shut SW 173 (U2 SW-280) and red tag. n N Shut SW 176 (U2 SW-272) and red tag, If at any timefan openstion becomes nece.uary, open either NO7E: f SW-2907 or SW-2908 to a. afected unit, clear red tag (s) i on control switch (es) and operarefan(s) as required. i-9 4.17 Post Cooldown y Perform ORT 11," Stroke Test of Primary System Check W L: l I 4.17.1 Valves,' if required. , f Perform IT 250 (255), " Inservice Test of CVCS and CC l h 4.17.2 ' / Valves," if regt.aed. p. E Page 27 cf 40 OR - . t.:4:Wa;# u -- 1 ,t.

W3e,

.,, a?L'a'.4+y"'%****. a,,,x. <a 4 f' .m

.~ um y .,p~~ y... ha, s-OP 3C POINT BEACH NUCLEAR PLANT MAJOR _r { OPERATINO PROCEDURES Revision 58 j' July 29,1993 IlOT SHUTDOWN TO COLD SHUTDOWN INITIALS _ i b':: 4.17.3 Perform IT 330 (335), " Inservice Testing of Containment Isolation Valves," on the SC and radiation monitoring M. l systems, if required. 4.17.4 Perform IT-210 (215), " Inservice Test of SI and Spray w ,1 Valves," if requimd, i 4.17.5 Perform 0178, " Preparation of Secondary System for @/ - [' Major Outage," as required. 4.17.6 Inform I&C to perform ICP 10.37 (Compensating temperature voltage input for RVilS) if the reactor vessel M head is to be removed. -{ 4.17.7 Hail 2_QDly, set TC-40ic in instrument rack C 107 at 30% in manual mode. T l-4.18 If draining of the RCS is requimd, proceed to OP4D. 'l 1 A//) g If the shutdown is for an extended period (> 1 week) drain down to // 4.19 s the vessel flange level or below, to uncover the CRDMs. n 1y o

i.,

,?

e t

,, P Page 28 of 40 'Adm < /..+4W& kin l

• .., 'ty M q'c'

.4 o

4..

r>.. _, 4. e_'. e ' g.,,,,.. ~=1 & & ?,,P

• > ~

g,$g *.F.*(, . yjg, t

.n m n mte:r.#y Ir.-

- : Es2 &

5 n-u m ~ 5R,. -.. a f fl n = ~ 0 i -i tn Q3 j 11EATUP & COOLDOWN LIMITAT ONS EFFECRVETIIROUGII IS.I; EFFECTIVE FULL POWER YEARS. APPROX. JANUARY,1995 Figure 1: 9' 4 .1 z O q QE

• 8 -'

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• F Pat 15tstitle w'f N vf $1f1 Pt f At i(#.
• 3 The above cune is a cornposite of the enost conarvative values for t!:e A.

is <ro*8 Q .o 15.3 1-1 & 2. ,g. 1110 and C/D ctines iiiT.S. For exact salues, see Figure C b L: &k .g. I h

OP 3C ~ POINTEEACH NUC!IMR PLANT MAJOR e p' OPERATING PROCED',LES Revision 58

• E July 29,1993 IlOT S!!UTDOWN TO COLD SIIUTDOWN

~ _ TTAcitMENT A A RED TAG llSI 7his anachment requires three stjurate tag series to l>e issued as twted. NOTE: Remow Anachment C and attach it to the Red Tag Serie.s. NOTE: Steo References P_cillica Commnent Red iagging CV-26]C is required in OP-SD. NOTE: OP-5D Section C Shut CV 261C T-4 VCT Cryogenic Retum 4.8.3 Shut SI-835A A accumulator fill valve 4.8.3 Shut ?. SI-835B B tecumulator fill valve Ffj@. Shut 4.8.3 A accumuhtor test line isolation g 3 SI-839A 4.8.3 Shut Loop A cold leg test line isolation SI-839B 4.8.3 Shut B accumulator test line isolation SI 839C 4.8.3' ,,7.. Shut Ixop B cold leg test line isolation SI 839D 4.8.4 Racked Out - q Breaker on A-05 or 6 9 P ISA or B 4.8.5 LO A. SI-841 A Breaker on B-32 4.8.5 Shut S SI-841 A-Local handwheel 4.8.5 1 ;, LO SI-841B Breaker on B-42 4.8.5 Shut p' - SI-841B Local handwheel 4.10 Shut Sodium hydroxide common supply

4

.U l SI 831B 4.11 Shut 11 supply to the VCT $[ l CV 261 A 2 4.13.1 & REI 19.0 Pullout 'ne l P-2,,,,& _, Charging pump control switch U A Racked Out 4.13.4 ![ \\ P-I A Breaker on A-01 w 4.13.4 w Racked Out 5Q. }P-1B Breaker on A-02 i5 K bge 30 of 40 ~,y. ~Whssa4MMe.. ~ ' I* p y. . < !..., o.# W,.,&,y;.faj. 4 b _ t 3, 4 s ~~ s r

w ec. ~.~ w +3r g _~ " c t. " ~ sypg ", "" ~ D' ,W %':: % wta:*' OP-3C POINT BEACH NUCLEAR PLANT MAJOR .u,- ,,,. ~n. O.a 4 OPERA'!ING PROCEDURES Revision SS E July 29,1993 t.- HOT SHUTDOWN TO COLD SHUTDOWN Attachment A (Cont.) R@ TAG UST Sten Referenec Builica Comoomal Disable the pressurizer high press PORV actuation Unit 1 ONLY 4.9.4 Slider TPI il in Riser 10 (IC@) Open 4.9.4 1RC-430 Slider TPI 12 in Riser 10 (IC@) Open 4.9.4 IRC 430 IRC-431C Slider TAF-9 in Riser 9 (IC-04) Open 4.9.4 iRC-431C Slider TAF-10 in Riser 9 (IC@) Open g QF f Unit.? ONLY 4.9.4 2RC 430 Slider TNP 5 in Riser 55 (2C@) Open s 4.9.4 4*"5 Slider TNP-6 in Riser 55 (2C-04) Open 4.9.4 2RC 430 2RC 431C Slider TAF 9 in Riser 56 (2C@) Open 4.9.4 2RC 431C Slider TAF-10 in Riser 56 (2C@) Open KO Additional tags are per OP-4D. ?V NOTE: 4.2 [ Switch on C 01 Shut f l RC 538 4.2 Shot k, l RC 539 Switch on C-01 Racked Oin 4.2 Breaker on B-01 IQ l TIA 4.2 i Racked Out I T l T 1B Breaker on B-02 Racked Out 4.2 t 6 Breaker on B-03 ! Q l T lC Racked Out ' 4.2 l T ID Breaker on B@ Racked Out 4.2 { lT-1B Breaker on B@ 4.23 Shut l WG 1786 Switch on C-59 t-4.23 Shut i l WG4 t7 ' Switc;> on C 59 i 4.23 e Shut !-[ l 'WG 1788 Switch on C-59 4.23 Shut f l WG 1789 Switch on C-59 l $k k Page 31 of 40 h, I ,m: M:L- <* ,o f',*' .i ' r ' ' \\ o. ~ f" Q %-- <n 3, e e av w ~

'n mm.,nw,.. [r,'Y " POINT CH' NUCLEAR PUMT f p 0?IRATINO PROCEDURES on 58 hly 29,1993 HOT '.HiriDOWN TO COLD SIIUTDOWN ~~ Attachment A (Cont.) RED TAG llSI Sten References EmilkD Comg'qtal NOTE: Adaltional tags per OP-7A s].851 A Sump B to RIIR control switch 4 St.851B Sump B to Rl!R control switch Shut /Mid Position 4.1.4 @C01 Shut 4.1.4 stb 51A Sump B to RIIR handwheel Shut 4.1.4 SI 851B Sump B to RIIR handwheel 6 ~ st.37] A P 14A suction from RIIR control Sidt/Mid P Siti " switch @ C 01 P 1 AD suction from RIIR contiel D. SI871P Shut /Mid Position sw:t;h @ C 01 St 871 A P 14A suction fi m RIIR handwheel Shut SI 871B P 14B suction from RIIR handwheel Shut NO75: Additional tags are per OP4D. The follouine tags are to be issued 3nder a sevatwtsag2an (not combined suh NOTE: to emure opembility ofLT447/447A. the tags abow). Tag series purpose: 4 4.17 j l RC* BOA PZR vent bolation valve Open l RC 580B PZR vent isolation valve Open 4.17 [ \\ RC 570A Rx vessel head vent Open 4.17 h@ l RC 570B Rx vessel head vent Open 4.17 ,..i j RC 525 itx vessel level cross connect ischtion shut 4.17 l RC 500Q LT 447 A reference leg isolation (men 4.17 l SC 950 PZR steam space sample isolation Open 4.17 9 f,t Page 32 of 40 ( ' k w.,,v d uli M ifE 4 0.:- c. ,w pg ,.,,. 3 .,. y j ' ? ' ~ 1' ' ' J ' 'Y. s y p.

q .y j.sc yyym~rw f ,.r OP 3C g.,. .v ,..YY y ' PO'D{tBEACH NUCLEAR PLANT MAJOR .D' OPERATING PROCEDURES Revision 58 f July 29,1993 110T SHUTDOWN TO COLD SIIUTDOWN Attachment A (Cont.) E211tica 51rp Refstencr3 Comoonent 4.17 l RC 535 PZR to gas vent system isobtlon Open p 4.17 p l RC 576 PZR vent orifice bypass Open Y 4.17 l RC 577 PZR vent orifice bypass Open 4.17 l RC 573 Reactor head vent isolation Open 4.17 i.,k,, l RC 572 Reactor head vent orifice bypass Open 4.17 j, l RC 571 Reactor head vent odfice bypass Open 4.17 ,[) l RC 587A LT447 reference leg isolation Open 4.17 L; j RC 579 LT447 reference leg isobtion Open 4.17 Open l RC 578 PZR vent isohtion 4.17 l RC 500 Reactor head vent isolation Open e 7 4.17 _i 1.; l RC 500D Reactor vessel level vadable leg isolation Open 4.17 i LT 447/447A variable leg isolation Open l RC 500J ) 4.17 1 l RC 500K LT-147/447A varhble leg isolation Open i .?

t.,

R Q sq$ v b - m'/Page 33 of 40 &:y&,%. M' + . a.w m a u ~- v.m ; w,w,,, a.m __ + .c

> ;-y,yg - n . r-x g i,. 't w 4 OP 3C , A. f r CLEAR PLANT

ip

• POINT P

.' + MAJOR p' OPERA 1 4 .'.EDURES Revision 55 July 29.1993 110T SIIITTDOWN TO COLD SIIUTDOWN - + Attachment A (Cont.) }Ule TAG 111T ,h N01E: A&fitimal tags per OP-3C 1htJclumine raes are to Eduwd seultr a secamit tar serie.1 (not comb NOTE: tags alme. };*> Place the follov ing note on the red tag series: 4 if at any timefan operation become.s nece.ssary, open either SW 2M7 or SW-2908 to Q No1E: the afected unit, clear red tag (s) on control suitch(s) and operatefan(s) as required. w. EcihlCD Sten Refen neg3 6 Comtenent W lAl Containment accident rectre fan Pullout 4.16 f W 1Bl* / bontainment accidant rectre fan Pullout 4.16 9. W lCl Containment acek-w im fan Pullout 4.16 W IDI Containment accident recim fan Pullout 4.16 Tums open Note the position of following valve _ a Shut 4.16 SW 144 (SW 273) IIX 15A D retum throttle valve Shut 4.16 SW 173 (SW 280) IIX 30A/B retum isolation 3 hut 4.16 SW 176 (SW 272) RE-216 retum inlet ,4 l@ 's " age 34 of 40 if Wl% e &* b Y lI _ ft,' (, A e l * ';g,s g, k y f 1y T y

~~ ~ , wu eqGiw ~ Op-3C [J *** POINT BEACH NUCLP.AR PLANT hlAJOR OPERATING PROCEDURES Revision 58 I' ' July 29,1993 IlOT SIIUTDOWN TO COLD SilUTDOWN \\ W., /QIACID,fENT B j pF S 1he blinder should be set upfor the boron corcentration detennined h NO7E in Sep 4.1.8. 1he intent ofAnachment B is to haw the RC5 O22tXQppm boron NO7E-( - concentration, utilizing the B HUT, den the RCS cooldoun is -e completed. .( ,1NIIJALS. Align P-9 IlUT recirc pump to recirc the B IIUT. 1.0 y i Shut BS Ill3 P 9 suction from A IllTT n (~ Shut BS 1127 P 9 suction fmm C ITUT Shut St 785B Transfer canal to P-9 suction L Shut SF 785C P 9 return to transfer canal Shut SF 785A P-9 return to SFP Shut P 9 IIUT rectre pump discharge BS Il09 Shut "d BSIl04B Inlet to B IIUT Shut V/ [ ICV 361 A P-9 to Ut VCT drain hdr Shut /'// 2CV-361A P-9 to U2 VCT drain hdr S$ ut /87 ) ICV 361 UI VCT drain to IIUT 7 j Shut 2CV M1 U2 VCT drain to I!UT SF-810 P 33 RWCP combine suction imm CVCS Shut '/ Shut / l ISI-828 Ut blender to UI RWST Shut 2SI 828 U2 blender to U2 RWST Shut SF 804C SFP pumps to RWCP aross<onnect /V/ BS 1126 P-9 suction fmm B CVCS HUT 0;en l s BS 1112 P-9 common suction Open 'E/. Throttle '/ BS-1119 P-9 retum to B IIUT I k: Open the VCT drain for the desired unit I 1.1 Open y 1(2)CV 264 VCT Drain r Start P 9 and adjust BS 1119 as necessary to prevent p' ump runout, l.2 N~ Y 1.3 Check 1(2)CV ll2A letdown divert valve in auto. // .\\ Since there is noflow indicadonfrom the B HUT to the VCT, NOTE: theJ1ow rate can be deternuned by VCT lewi rise ss, time {fnos s \\ cooling dann the RG. ji 'Thmttle open the desired units P-9 to VCT drain header isolation 1.4 1(2)CV-361 A to attain a flow rate st/2 of letdown flow. // M Y ,i 6 Page 35 of 40 .u 3.. %%%gis,kl2fXh. ,, u 4 . j j '~ g j [ ,k 3 N*; G D v.":, E ,4

.gwynww*o :4 OP 3C E.# - "%hBEACH NUCLEAR PLANT j ff,. - OPERATING PROCEDURES pe s 0n 58 ) R July 29.1993 IIOT SIIUTDOWN TO COLD SilmDOWN Attachment B (Cont.) ,1NITI ALS _ Notify Chemistry to periodically sample the RCS to determine rate of l.5 boron inertase ~llhocr initially (first 2 samples) then as deemed M_ appropriate by the DSS. u !! may be nece.tsary to temporarity stop the bomtion and restart NOTE: 11 again prior to completing th* cooldown, depending on RCS bomn concentmtion, time duntionfor cooldoun auf mie ef D flUTo&utica. When cooldown is completed and RCS loron is at the desired 1.6 concentration, realign the IIUT recire pump " 6# P 9 IlUT rectre pump Stop W 1CV-361A P-9 to UI VCT drain hdr Shut 2CV 361 A P 9 to U2 VCT dmin hdr Shut Shut BS lll9 P-9 return to B IIUT Shut BS Il26 P-9 suction from B IIUT (igC-O Shut ICV 2M UI VCT drain Shut 2CV 2M U2 VCT drain O Page 36 of 40

my. - my i,

m-m ? og n vm.o OP4C PODR BEACH' NUCLEAR PLANT s"' N..,, OPERATING PROCEDURES MAJOR I Revision 58 IlOT SHUTDOWN TO COLD SHUTDOWN ATTAC11hfENT C RED TAG 11ST M ATTACll TO RED TAG SERIES Poiklon Reason For Taegina, T Comoonent .F SI 835A A accumubtor fill valve Shut Prevent LTOP operation f SI 835B B accumulator fill valve Shut Prevent LTOP operation SI-839A A accumulator test line isolation Shut Prevent LTOP operation g SI 83?B leop A cold leg test line isobtion Shut Prevent LTOP operation SI 839C D accumubtor test line isobtion Shut Prevent LTOP operation SI 839D leop B cold leg test line isolation Shut Prevent LTOP operation a 3 P liA or B Breaker on A-05 or 6 Racked Out ' Technical Specifications r. SI 841 A Breaker on B 32 LO Prevent LTOP operation .( SI 841 A Local handwheel Shut Prevent LTOP opemtion SI 841B Breaker on B-42 LO Prevent LTOP operation y y.. SI 841B local handwheel Shut Prevent LTOP operation ( il P 2_&_, Charging pump control switch Pullout REI 19,0 V . tj P lA Breaker on A 01 Racked Out Protect RCPs 1 p-P lB Preaker on A 02 Racked Out Protec' RCPs si h SI-831B Sodium Ilydroxide Common Supply Shut Prevent Sodium Ilydmxide from Entering RCSIRWST Q 9 i. ? Page 37 of 40 n s.n e. g I = i, -.$ h a4 g ** e g

og - p-1 ,,^4 W. ;,xR', OP 3C j ' // 19NT BEACII NUCLEAR PLANT MAJOR l ,P' OPERA *!ING PROCEDURES ^ Revision 58 July 29,1993 9 IlOT SIIUTDOWN TO COLD Suth.';WN Attachment C (Cont.) RED TAG LIST '? Position Reason For Taccing Comtenent Disable the oressurlier hlch oress PORV actuation l Unit i ONLY h IRC-430 Slider 1TI ll in Rher 10 (IC-04) Oivn Single failure protection for LTOP 1RC 430 Slider TPI 12 in Rhe.- 10 (lC-04) Open Single failure protection for LTOP IRC 431C Slider TAF 9 in Rher 9 (ICol) Open Single failure protection for LTOP t Slider TAF 10 in Rher 9 (IC 04) Open Single failure protection for LTOP 1RC-431C ) Unit 2 ONLY .i 2RC-430 Slider 1NP-5 in Rher 55 (2C 04) Open Single failure protection for LTOP 2RC 430 Silder TNP-6 in Rher 55 (2C-04) Open Single failure protection for LTOP 2RC-431C M Slider TAF-9 in Riser 56 (2C48) Open Single failure protection for LTOP Slider TAF-10 in Rher 56 (2C44) Open $8.ngle failure protection for LTOP O. 2RC-43tC t! 'te 4 I t g. S f: Page 38 of 40 1, " '+ ; q. a % Q u y f ,,, p 43 ,, s i 1 'D '.W

• /

,t_.. ., _.. _ g.

q,;L YW{l ? ; T' # OP 3C , /I ' POINT BEACII NUCLEAR PLANT htAJOR

• V OPERATINO PROCEDURES Rev!sion 58 July 29,1993 N.

IlOT S!!UTDOWN TO COLD SlitnDOWN Attachn.;nt C (Cont.) PED TAG LIST p Position Erason For Tagging Component NOTE: Additional tags cue per OP-4D. Prevent vent header gas release RC 538 Switch ou C 01 Shut Prevent vent header gas release RC 539 Sw!!ch on C-Ol Shut 4 T1A Dreaker on B 01 Racked Out Prevent heater damage k T lu Dreaker en D 02 Racked Out Preve6t heater damate 'L T lC Breaker on B 03 Racked Out Parvent heater damage y T l D.' Breaker on B-04 Racked Out Prevent heater damage fl T 1E Breaker on B-04 Racked Out Prevent heater damage Prevent vent header gas release WG 1786 Switch on C 59 Shut Prevent vent header gas release Switch on C 59 Shut ) WC 1787 Prevent vent header gas Irlease y,y WG l?88 Switch on C 59 Shut Prevent vent header gas release Q T-WO 1789 Switch on C 59 Shut

f' l (

NOTE: Additional tags twr OP-7A ! G' Sump B to RilR control L SI 851 A Shut /htid Position Prevent LOCA when on RilR L' switch O C-01 h. i / SI 85tB Sump B to Rl!R control switch 0 C-01 Shut /htid Position Prevent LOCA when on Ri!R 4 [i SI851A Sump D to RHR Prevent LOCA when on RIIR handwheel Shut SI 851B Sump B to RIIR Prevent LOCA when on RilR i handwheel Shut ' { d,, Page 39 of 40 ~ i @4s%%5 t#se igg '(. '1 .. t ), r ,d.-

..,9~'"' ,, y ~~sq;w por e v ,.,,,.;T ' h!NT RACII NUCLEAR PLANT OP3C 2 f A

• Y' OPERNnNO PROCEDURES I

Revis on 58 July 29,1993 !!OT S11UTDOWN TO COLD SIIUTDOWN Attachment C (Cont.) RED TAG LIST M NE Component SI 871 A P-14A suction from RilR control switch O C-01 ShudMid Position Prevent LOCA when on Rl!R 51 87111 P-14B suction from RIIR P control switch O C-01 Shut /Mid Position Prevent LOCA when on RilR t, SI-871 A P 14A suction from RilR handwheel Shut Prevent LOCA when on RilR st.871B P 14B suction from RIIR k,. < handwheel Shut Prevent LOCA when on RalR -a t i. rf 14ge 40 of 40 %.kiidk&VC,&& vv.-

i Js

• O wr,. -

NITACilMENT 3 l'ORY lilock Valve Teging Informa11s Unit Valve Test Open l'orgue Close Torque Close Stem Unwedging Number Date Switch Setting Switch Setting Thrust at Load (Ibs.) Torque Switch Trip (Ibs.) 1 RC 515 5/i6/92 2.0 2.0 8376 5589 i RC 516 5/16/92 1.75 1.75 8316 3836 2 RC Sl5 10/31/92 1.25 1.25 10000 6532 2 RC 516 10/31/92 1.25 1.25 10000 7283 6 / i I-

NITACllMENT 4 i e d iiiiiiiii

s January 23, 1997 MEMORANDLH TO: Ricnard H. a s$ nan Chief Mechanical Engineering Greecn y Division of Engineering L Office of Nuclear Reactor Regulation .y -3. FRCM: MichotlE.Mayfield. Chief M 'A [lectrical. Meter 1415 and Mechanical .e [ngingef'ing Branch Division of Engineering Tecnnology. RES

SUBJECT:

TRANSMITTAL OF PREL.!M! vat PGESSLSE LOCK!9G DATA FROM DOUBLE 0:5C GATE VALVE TE$f$ The attacrM nt Ibe subject date in tre attachment il tran$m'tted tr your recuest al50 incluce5 inforu t*cn about the velv that was tested it

• ,*e lcato Nationai En910eering LAD 0fatory' the Step 5 for ter8 ratteg tPe tests, dN 5/fi.4rtes of tre test result $.

The data gnd the f t9wfe! I:e5;"'01PG the test rWits dre preltm'rary $1Dee tDe final report.111 nct te catcletec / til FeCrA ry M97 Mcwever, tre cate Can De util12ed for detecting V6h e tre*C5 And tendViCr$ '/icer Orel$a e lecting r condit10n$ If you have 6ny awestions ce tre attac w nt :leale call Ger1 : w n'e:cername : G. 1 6015) of my staff Attar w r.t' As stated s M e n e,s) Pom TW 85 m a emmesa taar,1 sena 4 Doctam(T Neest. GiASIDes%fLTWate02 't' e ( 97** N M W owe +3

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ft mehe a egy W We % tWhums W 9e tesi *C' e Co, semA enspwwe eme Mr. meaus, ' . La*"l* M _OL\\l& A M..r .IE CatesS %. J I 1 ,g Eveham pr-4.- J vers E 1 M is usew W Imats its oss 2148 ouAF98 0011 Fr ( CFFC C E N curv m yW im8m M N ~ \\ a

AiiAC M NT Pressure Locking Test Results,6 inch Anchor /Dafling Valve na U.S. Nuclear Angulmory Commission (NRC), offles of Nuclar Regulatory Raear.h, recomuy fundel tesserch at the Idaho Nulonal Engineering Laboratory GNEL) to provide technical Information to support NRC's evaluations of indstry reposes to Generic Lemt 95 07, 'Preuure Locklag and nemal Bladlag of Safety.Related Power Opersed due Valves.' Pressure locking and thermal binding are potential operational phenomena ht can prevent a closed gate valve from i openias, l'ressure loshing can be either hydraul!: ally or thermally induced. Hydraulltally Indocad presswo locklas ces occur whos operating seguances leave fluid at bish preuwe trapped in the j beans aAw the upseroom and downsueam s6 des beve been depteuurlaad;ibermally inducef preuure locklag can occst whea a temperature lacrease causes fluH trapped in the bonnet to preuurias (as a result of thwmal espansica). Either way, the effect is to cause the pressure of the fluid la de bonnet (and, la acts valves, between the discs) to be higher than the presure os the opetteam and downsuem siwa of the disc assembly. This high fluid pressure forces the discs agalut both suu, maklag the disc asaanbly harder to unsev man anticipated by the typical design calculsions, whleh generally somider frietional effa;u a only one of se two dise/ stat interfacas. I ne oba tives of the INEL de valve presaute locking research inelude the following: ee b 1. $rady the relawnship i,etween N eresure in the bonnet and the opening thrust, both with ec valve sold anI with the vahe hot 2. Evaluate tree impact of temperature changes in the bonnet region on the rate of bonnet preuuriaation 3 Evaluate the effect of vahe leakage for mitigatirig or eliminatin; prusure toeking 4, Evaluate the effect of entrapped air for mitigating or eliminating pressure loekirg. Test Setup ne apt program constated of testing two see valvu 41 various presure toeking condithns. ne first v4he tated was a 6 in.,600-lb,;las Walmonh flesible weise gate valve squipped wtth s Litrutorque $MS4:5 anxor setuator. Preliminary resulu from those tesu were reported cattler (avtalable m the NRC Public Docum<nt Room, Accouien Number 9606270097). De second vilve tested wu a 6,nca,900 Ilselus Arwhor, Darling double dise gate valve equipped with a Limitorque SMS 160 rrwtar aeruasor. nis paper reports the results from the tenu of the Anchor / Darling velve. Imponant specific informalon about the Anehor/ Darling v Ahe is liuol below-L'pstrum maan seat 41ammer 3.594 in Downstrearn mean seat diameter 5.413 in. . 5:ero diasmoser 1.50 in. 25' internal wedge angle - Disc and disc guide maurial A315 70 w'COCR Dix and body sent hardfeeing Stellite 6 Internal wedge hardfwng Stelhte6 ^ l

h6 valve was tested in the laboratory *is the upstrum and dowstrum flanges capped, ne valve was intrumented to provide mesuremonu of Horn force, upuream, bonna, and dowstrum pesuures md temperatures, and other parameters. De wat lukage for this valve, u it was tweisel from the manufmurw wu well below weepted limiu No seat resonditioning was required. Before any testing, se valve we uroked many thmen (preconditloalas of sliding surfaces) to provide uable dlu to mat kletion facwts. De valve was subjected to two tot uquence: cold pressure locking tests, and hot pewsure locklag teau, 80th the cold tests and the hot tais paadned the relationship beween bonnet preuure and the unwedging load, Pressure la the bonnet was limhed to 1200 pois, la addhios, se hot testing evalumed to telulonship between bonast temperature and bonnet pressure (as lasus reized to thermally induced preuvre locklag) and the e#ects of air ensrapped la the bonast. Tempermure for the hot preuvre locking tais was llmited to 290'F. Cc!d Pressure Locking Tests ne mid presure locking tests evalustal the relatiomhlp between the fluid iressures oceutting at various iocations la the valve and tne valve opening erust. De test matris consisted of various upstrensa, domstream, and bonnet pressures w repreent the Mi range of possible condittom. De test maarts also includal periodic valve struke throughout me toti, i provided baseline informulon on the seming versus umesting relmionship, the upstream and downstream seat friction values, and the load due to packing friction. De beeline str. km lacluded a stmle valve closlag and opening cycle and two diffwential preuure opening nokes, one with the dowstream side and $e bonnet presurtrad, and one wie the upuream side and We bonnet preuurbed. Two dinaent methods were used to simulate pressure toeking conditions. De firu meshod began wie the valve la the open posilloa, and the entire valve wu presurumi to 1200 psig. De valve was een closed, and the presures in 2e uputoam leg, downstream leg, and bonaat were - reduced to the desired tot valusa, hea the valve was subjected to an opening stroke, with measuransess takes of the nem force required to entract the valve disc. De second mesod began wie the valve in the open postalon and depressurized. De valve was closed, and the pressure in $e upaream leg, downsueam leg, and bonnet were increased (ulns a high pressure pump) to the desired tot values. As before, the valve was sen subjected to an opening uroke, wie measurements taken of es staat force required to attact $e v61ve disc. Dere was no distingulahable difference in the resulu between the two mahods De resulu of se teu are l'sted in Table 1, corresponding with tent aurabers 201 through 229. De table shows te maalmum nem force measured during se opeaang stroke (F,,,), along with the upstrease, bonnet, and downtroam pressure that correspond la time wkh me F.,, measurement. Where the nem packing load wu mesured la a natic test, that value is also shown. As additional set of cold presure locking tenu was performed after the hot tats were completed, to provide Laforutation os $s repeatability of the musurements. De results of those teu are included in Table 1, corraponding with tot numbers 401 $ rough 409. j a.._-.a_ _ _ _ _ _ _,, _

Hot Pressure Lociting Tests Tata sindlat in those described above were performed on se valve at olevued temperatures. Like the cold testa, ease hot tests examland the reladonship bawma bonnet preuure and de thrust regutted to unseat the disc during openir,1. Also, a part of the but test pris, twu were performed to evaluate the impact of temperature change on the rate of bor. net preuurtration, and to evaluate the eMeets of sit entrapped la the bonr,et. Testing was perfacmed wlah es valve bessed boe internally ud uternally, For the toss 'vi.th toucnal heating, se heater la the upstrum leg of es valve bened the Auld at approttmately 501 per hour until the sputoam fluid temperasure reached 290'F or until se bonna preuvre reached 1200 peig; the upareem pressure wu controlled at 50 peig. Discharge frota the downstream side of I. the valve was amated as as indicwinn of Inkage from the boats 10 the dowMtream side. For enternal beating, heat tape wrapped niound the valve body was used to best the fluid la the valve. As before, the targd benaq rue wu 30'F per hour, the fluid tempernevre wu limited to 290'F, me bonnet pressure wu limited to 1200 psig, and the upstream pressure was controlled at 50 pils. De bonnet preuure was monitored d,artag the bestup am! compared to the meuvred leakage,o staudan the teldaonship be,*een lukage and thermally trWuesd bonna prenuria..',on. If and when the bonnet pressure ruchej approximately 1200 psig, the hearup wu terminated and the valve wu sub;ested to an operung stroke, with meuurements taken of the stem load required to entract the dise. Sit heacup tesu were performa! Four of those teau produesd bonnet preuures capable of causing pressure locking loada, for me oder two tau, the bonna preuute wu increued by other suas ta high preuure pump) betere the valve wu stroked open; this uruegy allowed mea..rement of the operdag stem load as hot prmsure locking condidons for all sin tsau, ne resulu of all the tenu in the hot test seria are listed in Table 1, correspoMing with ten numbers 301 through 333. De 312 br.arup tests were imaneJiately followed by preuure locking tesu, identined u test twmbers 306,313,331,144, MI, and 375. De luk rues meuvred during the sin tuu are suntmarized in Table 2. ne sin hearup tesu included atYeru to evabte the relationship between me incremar honne temperature and the bonnet pressure, and to determ.ac ce effect of entrapped air on the bonnet pressure during beacup. The rew.u of those encru we doetibed in the following pungraphs. The boana ternperature and preuure were morutored duritig hurup, and the heatup wu terminata1 when the bonnet pressure was stablished si about 1200 psig, or when the upstream tempercure reached aoout 290'F. Temperature Versus Pressure Figste i shows valve bonnet preuute verius bonnet nuid tempecuure for the Orit three hearup tats. For these tesu, the valve *u bestal u a rata of approximately 80'F per 1,o. using the enternal bemers (heet tape). Test i begna at 300 psig bonnet preuvre; the Juration of the heatup wu 1.9 hours (the bonnet prmsure reached me targe of 1200 psigh The lont.et preuvrired rspidly after reachirig 100'F. Tat 2 began u 0 psig aM,du not prenurire, because of slight seat leakage. The durados of the haarup wu 2.9 hourt. Tat Twu terminated whta the uputta Ouid temper Aturd

reached 290'F. Test 3 began at 600 psis ard presaurued rspidly, as in Tat 1 The duration of me beemap was 1.6 hours. Effsets of Entrepped Air ne last three hwup tests (Tests 4 $. and 6) were performed to duermine the effects of entrapped air on the bonnet pressure with the valve saposei! to thermally induced preuure losking condl. ions. Tenu were pettirmed wie alt pockou reprewetlag 0% v4 2.0% of the bonnet volume, ne alt pochess were stablished by dralalag a known volume from the lower valve body drsin line whee allowleg alt to r.nur $ rough $e high bonnet vem. Once the appropriate alt volume au essablished, the ve've was hensed, u before, until the upsuurn Guld temperuure ruched 290'F or umail the boanet preuvre rowhed approalmately 1200 psig. Figure 2 shows boense pressure versus bonom duld temperature for $ese '.esu. Test 4 wu conducied widi no entrapped alt and latenial duid heedna only, with a targa heuup rate of 80'F per hour, ne durulos of the bestup was 1.3 hours. Tes: $ had 2.0% entrappel alt ud Imernal nuid bandag only (with the same beanup tus). De bonna did not preuurire, ne durunoa of the hearup was 4.1 hours, and the heerup was terminated when the upstrum duld temperature ruched 290'F. $ light valve leakage, pouibly sombinal with the effects of $e alt bubble, contributal to the failute to preneurtas. Test 6 had 2.0% entrappal air but used all heaters, both interul and enternal, so the bonnet besied more quisuy than in the other 'wo tesu. De duration uf ce hearup was 2.3 hours A comparlaos of the resulu from Tesu 4 and 6 illustrates the effect of entrappal air With air trappal in the valve bormt, rapid pressurl:ation Jue to heating ts delayed until a higher ternperature is rexhed. 4 l }

2e Prelimitwy Talde 1. $urr.nuty of presure locking test tesulu Tat mesuremenu Packing load Disc Tot Tat Tat sember type' temp,6 P. P. P F= (Ib) factor (pAlg) (pild) (Plig) (lb) 201 cold 8 4 3726 1357 202 HD cold 1058 1060 +$ 9420 0.403 203 HU cold 3 1010 1003 10599 0.446 204 5 cold 0 3 .I 3807 1350 205 PL cold -4 231 3 66:6 2M PL cold -4 496 4 12588 201 PL cold 4 77$ 18128 208 PL cold 4 1071 5 23165 209 PL cold 4 1085 298 20490 210 PL colJ 4 1119 592 19922 211 Pl. aid -) 1100 378 15429 212 HU cold 3 1025 1018 11396 0.473 213 ' 5 cold 3 1 2HS 1318 214 HD cold ille til7 3 11057 0.451 215 PL cald - 307 1024 4 21276 216 PL ' cold 609 1082 4 19437 217 PL sold 927 101) l$291 _. 218 HD cold 1104 1111 4 12739 0.518 219 PL cold 606 1071 288 17579 220 PL cold 307 1066 2% 21356_ 221 PL cold 4 208 5 8248 222 PL cold 4 ell 14739I 223 PL cold -4 774 5 2306,f 224 { PL cold 4 1021 5 29277 225 5 cold 0 2 2 4066 1402 220 HD colJ 1063 'l066 5 13281 0 554

== Preliminuy Table 1. (continual) Tatmouuremenu Pukirig Tat Test Test load Diu numbw IW temp.' F* P P Fw (lb) factor (psis) (psis) (pois) (16) 227 HL' cold 2 1014 1007 12126 0.304 228 5 _mid 0 1 2 $743_ 1386 229 PL cold 0 l_0M 1 24238 301 3 cold 189 191 186 2425 1383 302 HD cold 1002 1004 45 t$07 0.400 M3 HU cold $5 1011 1011 10099 0.447 304 30$ beeny hot 306 PL hot 49 1046 4 26627 39, S N 90 93 18 3077 1383 30s HD hot 1090 1092 $2 10509 0.458 109 HU hot $4

992, 986 10814 0 489 lli S

cold 244 241 742 2723 1346' 313 HD cold 1049 1912 49 10265 0.44 9 313 HU cold $1-1047 1040 11737 0.$03 114 317 hearup hot 318 PL hot 44 1025 4 28$96 319 5 hot $7 60 55 3232 1421 320 HD hot 1123 1126 45 12:31! 0.511, 321 HU het $9 1018 1010 12518 0.551 323 5 cold 2 4 0 3330 146$ 324 HD cold 1050 1053 0 11291 0.479 325 HU colo 5 cold 164 168 162 2257 1354 326 327 HD cold 1079 tott 54 10475 0.+63 328 HU cold 52 1095 1084 10719 0.443 329-)M hearup hot 331 PL hot 52 1065 -4 26417 6

Prelimirwy Tatde 1. (continued) Tat manutemenu Pack;ng Test Tat Test load Din awabet type' temp.6 P, P. P F= (Ib) faaet (p613) (psl8) (pel81 Ob) 332 5 bot 140 142 137 3057 1423 333 HD but til6 till 44 10937 0.43 3)4 t(U hot $2 1022 1013 11224 0.490 3M h cold 2 4 0 3213 1468 337 HD cold 1802 1105 0 120 4 0.411 338 HU cold 3 1137 1130 12616 0.474 339 5 cold 347 330 344 3548 1389 340 HD onid 1086 1090 50 11304 0.492 34l HU cold 53 1108 1101 11740 0 478 342 343 hump hot 344 PL hot 47 1105 -4 28301 345 S hot 281 254 278 1264 1151 I 34 HD hot IM8 il01 4 13020 0.557 ! 347 _HU hot $3 1089 1082 12357 0 $11 l 349 cold 0 t 1 3555 1417 350 HD wid 1091 1($) 0 14154 0.580 351 HU. cold 3 1130 1122 12875 0.486 352 mld 287 292 284 1661 1384 353 HD cold 1108 till SI 14234 0603l 334 !!U cold $l 1094 1087 12674 0.519 i 335 360 heatun bot Mi PL hot 61 1096 3 32$40 r M2 5 bot 1.,1 793 787 1020 1868 363 HD bot i124 1127 4 10765 0.43 364 HU' hot 139 1083 1075 1348 0.351 366 5 mld 4 6 2 2597 1373 10123l 0.420 l 367 HD cold 1092 1095 4 I 7 1

Pt Minary q Table 1. HominucJi T e.t naugtvinents P4sking Tot Test Test Iv4J Dise P. P P. F. gity yo, i nur.ht t)pt temp (p Igt (pog) <psigl tihs 368 HU cold .) %) 956 7831 0.348 369 co!J __ 63) 636 69 !!49_ 1274 )?0 HD eoid 1827 1829 $1 10511 0,449 371 HU colJ 31 997 N0 78 1 0.360 372 374 heerup hot 375 PL ho 5) 1105 25479 376 5 but 377 hut 1:18 12:1 1:14 -4 ) I 1880 = 378 HD hot __l090 IW) 64 8078 0.370 379 HU h. 66 44 )62 7454 0 162 381 cold il 13l 4 1626 !)$1 1080f 38: HD I enlJ 1078 4 1640 0 330 183 _ _ HU e iJ. .i 1006 ' PN 6584 0 287 l 163) 1328 f 401 eold 2 I M70 HD eulJ 1036 1038} 5 609 0 307 40) HU evid 4) 10h 1024 59 0 l 0255 404 Pl. colJ -4 10:d dI i,3'1I I I l 1880) j l !W4 } 405 PL sotJ 4 4 406 PL .i J i 4 le! I $i 1?"4 407 colJ l 1 l l lit 4 127) 0192 f 408 HD sutJ l104: I IWS ! -) l 9474 409 HL' .old } -) 488l ha l 740 l 03:9I

a. Tat Type S = statie operun tat (no intern J prmur:, HU = hyJ. suiie opening test 4 erst s

the upstream sut, HD = hydrasutie uten.ng test heats the dowrutre4m wt PL = pressure lock opemns tot, b Cold (ambient) terrtef atures *:f t betacen 70 cd Wi. but tempr4Wres ranged from II) to 2 21 'F.

Ptclimiuty TsW 2.1.uk rates for leakage from the vahe boMet 49tirig hearup tests Manimum Averas Muimum Average luk4g# w lukue w leakage'te Inkes' to upsitum slJe untrum side downstrurn side downstrurn side Test (em'/ min) tsm'!mm) (sm'/ min) (ca'!mla, ownber t 6.266 2.67 0 688 0.13 2 41.637 $ 97 2.27$ 0.60 3 1.724 0 70 0.540, 0.l$ 4 1694 0.35 1.059 0.49 5 47.313 9 22 10.711 2.60 6 1.414 0 27 boiling octunal bolling occurtsJ a 1.enhage vtWume wu meaural at 15. minute mtervals during the heatup, Values refortal here represent the led rate Ihr the l$ mm.te si.ter..it trom which the irgest volume was solledaj. ~ 4 s 9

Preliminyy '

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'er : era:e,e t ; Figure 1. Resolu from Tesu i through 3, showing the inercase in tonnet pressure u the bonnet tempetuute inctesas. 10

Prelimir.ary e I!cc ~ 5: 4 es: ( e )y A N 8g 1CCC - [ = / v .e 5 ) a 5s -5 ~$ J } 5:0 - b ~ f f ec s / W r _ _6 2 f u, 1 ~1 5; 'C 't; 4

g,3.,.9 'g Figure 2. Resulu hom Tesu 4 through 6, showing the sticcu of entrappal Jar on the pressurestamperture relatmunip; Test 4 t J no enuapped air, sad Test 6 had 2.0% entrapped air.

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( M CLL %k PoulA 16LslNL % t Nil N; 11 M POR 00 C Q,ihid,Mi % h %lt WPlu n t { %0TL: REFE R TO Pit 0CElsl'RE $P I. ) FOR Gulls 4 %CT 10 (0\\ltii TT THIS I OR \\l i i !KC NtfMillfVi!Til OP " 7A ' l LAD HU / r cl% N M "_jJo h l L~ ml' N a *

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• PBNP (For $l CL' RID' Pt.A%

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+ DESCitillt DESiltED 11t\\lSING Olt 110Q1'111ED REAlllNG, INCLUDING lti:SPONSillLE GitOUP tif.ipplicabici: e.eenig* v TiulNING CONTACT: .. f f(h M!Yf f#d shf Ib mkOm k $* 6' d 6 kt d'* k' Y d Ilf dt e' dblD + iniuah P fiF a u t,*f,;. :a 't : 2-:____--__

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- / / /,- Nam. Pnnu r/ signa:ur:... _ _. _ _ ._./ -.,4-I Reucu ed b) M55 Reuen Manager PDNP Approval-Dai .Name ( Prinu signature !n heu of MSS and Manager signuure. atta;h PBF aOJ if sena!::ueu has been ;enju;;,:d ':5s and a 1 approsak at not ne: sun for a determman:n af men irra mim icI inn _ t citl~ l's I s G .">sene; ute prero;;. ung:.: : es;'enm;. :n;...:e :nteram,, n6guranen, et.. nam; na Two ; hang:s 10 0F '9 ^Remeung Rai; a. i' Rancu. sy nem "m 0;mana ace : acc

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i. the steps for re Lann; R!iR through S iafen mg.1:en Pumps 'u ;'ra..:ur; acmd :.es; mr .. 3 Sh0rt pe!10d :gt:l t.HJ if thJ P-13 %:::'O itar* ;..? pump weuij N ' as;J ;0! sa.. . t; ' 1.! a.13.a ,s.. s.. were : hanged te ensure a rump su: Den rath :ma at a;; nmes The se;ond pro::aure hange imch ed rnMune ib: preuare te;smg m :,, aw;:ated w:" * ; 4 c'..d OP Cal;ulation w "oc Tuo new 5::ps uer aad:0:; m e prm : w : : s;..E"', t..: F. s * - bs entenn; the apprepnated ' C0 far e..cna;nn. m er 4 4 np,..aun: .. 'nu a n e n:,1% . ; losing the asse uncd 5M" a ah .EC e. 4ne 5: c 3.a. ' n.

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.. B ' List relesant current h::nsmg basis (CLB r and :nd: pendent Spem Fu:15terage installanen 15F51, h;ensing basis documents and se:nons Tc:hmeal Spe::0:anons 1.4 3 i FSAR 6 4 ~ d Does thiproposed change. test or aspenment imbh a enang, w any ::nm a: spe;m;aner. r at T the 15FSI the Te:hm al spe:tfi;anons rend:: th CtruS; ate rf Cem;, tan;: 'f a :na :g::s required, bn: fly des:nb u hat the ;nang: should b: and wn) ;

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4 Discuss;on of Revision 2 to_ Calculation 96-Q_0_62 P Calculation 96 0062, " Evaluation of SI 871's, SI 860's, SI 857's, and RC 515!516's Bonnet Pressurization", dated 07/02/96 is being revised. The revision is required to perform a more precise ] evaluation of the SI-871 valves. The operation of those valves has been reinstated in the EOP's (Emergency Operating Procedures: With this ieinsertion, these valves naed to be re-evaluated for pressure locking concerns. One change in the S1871 calculation section is the use of a 0.45 gear train pullout officiency. The calculation was using a value of 0.40. This value may have been read off the Limitorque gear ef ficiency chart incorrectly. Ti.e value for-this parameter is 0.40 for 1800 rpm motors. The motor on the SI-871 valves is a 3600 rpm motor. The second change to the SI 871 calculation section involves evaluating each of the 4 valves separately and incluc'ing specific 'nformation from each (1SI 871 A,1SI 871B, 2SI 871 A, and 2SI-8718) The calculation was using the most conservative parameters from each of the 4 valves. Another change in this calculation is to evaluate conditions more representative of the actual system conditions the SI-871 valves will exponence during the accident when they are required to open (LOCA). The two conditions evaluated are when the valve bonnets are depressurized and preasurized prior to '.he accident. As of this date, modifications have been made to the Unit 2 SI-857A and 8 valves to eliminate their susceptibikty to bonnet pressunzation. The titic of this calculation is also being changed to " Pressure Locking of MOV's" No other sections of this calculation are affected in revision 2 to calculation 96-0062. Calculation 96 0062 Povision 1 Table of Contents Pages Description 2-3 Evaluation of SI 871 valves i Evaluation of SI 660 valves c-Evaluation of SI 857 valves ~O Evaluation of RC 515,516 valves p ~- Appendir A Pressure Lucking Calculation Method (from ES8U/WOG 96-022 ~ ' memo) n s

+ ~ Pressure Locking of the Containment Spray Pump Suction Valves from the Residual Heat Removal System (SI 871 valves) Purnosca --] To calculate the affects of bonnet pressurization on the required opening thrust for the containment spray pump suction valves from RHR (SI 871 MOV's). TNs calculation uses a simp'ified, more conservative version of the method developed by Brian Bunte of Comet. and summarized in Westinghouse Owners Group memos ESBU/WOG-96-022 and 050 which are Appendix A and 8 of this calculation. The required opening thrust determined by this calculation will determine if these valves can be opened withe their bonnets pressurized or if they will pressure lock. Assumotions2_ This calcuistion assumes that the total seat contact area is equal to the load resulting from the bonnet pressure acting over the disk area. The disk area for this calculation includes the hub are;. which is a conservative assumption. This calculation assumes the unseating load for the SI-871 valves is equal to the packing friction while opening since these valves are parallel seat dot.ble wedge gate valves. One part of this calculation assumes that a valve bonnet pressure of 207 psig. has develoced in the SI 871 vaives. Th.s prusure is due to two f actors. The first is the RHR pump developed head of 145 psig. The other is due to the maximum conta ment pressure during containment sump recirculation which would pressurize the $1871 valve bonnets. Another part of this calculation assumes a valve bonnet pressure of 415 psig, based on an RHR discharge pressure of 415 psig, when RHR is aligned to the RCS for low temocrature low presst.re operation (cold shutdown). Both parts of the calculation assume O psig, on the downstream disk wnich is containment presssure. This pressure would be the boundinC case. Containment spray on containment sump recirculation would be expected to be aligned at a higher containment pressure. Both pris of this calculation also assume 145 psig. on the upstream disk which is the RHR pump discharge pressure. This pressure is based on the assumption above of 0 psig. cor.tainrrent pressure. Ref erences: Component Maintenance Progrcm (CMP) 2.2.8 - MOV Design Basis Review PBNP MOV database and signature analysis software pressure locking calculation method contained in ESBU/WOG-96-022 and -050 e PBNP QP calculation 90-C17 calculation 94-005 Roark's Formula's for Stress and Strain - 6th edition - 1989 PBNP FSAR Section 6 Engineered Safety Features PBNP calculation N-93-80 OP 78, Removing Residual # eat Remova! System from Operation 5

L ADPJ2L'u stem diameter = D.,,,, = 1.5 in. tfrom calc. P 94 005) seat diarneter = 0,,,,, =' 6.532 in. (from caic. P 94-005) - valve factor = 0.55 ;from calc. P 94 005) available stem pullout thrust = 9751 lbs, (151871 A) 9595 lbs. (2SI 871 A) 10325 lbs. (1S18718)- 9831 lbs. (2SI 87'B) packing friction 1700 lbs. (1St 871 A) ' 700 lbs; (2SI-871 A1 800 lbs. (1SI 871B) -1600 lbs. (2SI 8718) pressure upstream of St.871 valve,s = 207 psig. (from calc. N 93-80) pressure downstream of SI 871 valves = 0 psig. i m h 4 ...n= __m_

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b Results: Margin with bonnets depressurize' d prior to accioent: - 1SI-871 A = 65% ISI 8718 = 75% 2SI-871 A = 74% 2SI 871B = 66%- = Margin with bonnets pressurized prior to accident: - 1SI 871 A = 0% 1SI 871B = 0% 2SI 871 A = 0% 2SI 8718. = 0% Maximum allowable bonnet pressure based on a 20% openino marnin without considerina Diston effect: - c.' <T6 psig. ' 7D ' '., 1SI871A=)Jcc Conclusions; When the bonnets are depressurized prior to the accident, sufficient margin exists for the valves to open. A 20% margin is recommended in ESBU/WOG-96-022 and.050. This condition is the normal differential pressure condition evaluated previously calculation P 94-005 and the design basis review (CMP 2,2). The S! 871 valves are not susceptible to pressure locking in this case. When the bonnets are pressurized prior to the accident, msufficient margin exists for the valves to open based on a 20% acceptance criteria. This condition would occur after operating the RHR - system _for low temperature-low pressure RCS heat removal (OF 78). To eliminate th:s condition, - procedures may need to be revised to cycle the S1871 valves after OP 78 or modifications made to the valves. It is recommended that the procedure changes be made. With these procedure changes, the SI 871 valves will also not be susceptible to pressure locking due to thermalinduced - pressurization of the bonnet. ~ Thermalinduced pressurization of the valve bonnet cc ild occur when the trapped water in the valve . bonnet is heated. Without,a relief path, the bonnet pressurc will rise.--_ The SI 871 valves are not susceptible to this condition since the procedure changes will remove any built up bonnet pressure before proceeding to normal operation. After the valves are cycled, the only pressure increase inside the bonnets would be due to the hot contamment sump water during recirculation and no thermalinduced pressure increase would occur. ~The water from the containment sump af ter the ' RHR pumps would be at a higher pressure than the water inside the bonnets. pgv;Oy w.wN.M E N r b!H? SE C;.4 C :. L + ~h O ) rt-AnA W " OW* ~ r# ~h ^'WW'M '" M ' ' AI' Y ' ' A _ ez y _ gx A r tve-it A AW a n'g' y',pg4 ekM - f: k ot:) 9A,M W<W Vh __ Pu wtya ^ F.uM.QA TJ 59 A.h Y ' h St.d 19 $ /j? ? I** W E j9 'g p,whd L84 NNW [! yr t w r ii> M ~ NLvt p pgg, 49{ d(WI C' hrHi Qu.:a skb R "" ' "! N yk ; 3.y

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RESPONSE TO RAI DATED 10 97 " PRESSURE LOCKING AND TilERMAL BINDING OF SAFETY RELATED POWER-OPERATED GATE VALVES"

1. Pressuri/cr Power-Operated Rehef Vahe Block Vahc Each unit at PBNP has 2 pressurtier power-operated rehef vahe block vahegPORV block vahci which

, I arc designated RC-515 and RC-516. All four vahes are identical. They are 3 in Ocxible wedge gate vahesmanufactured by Velan#Limitorque SMB00 operators with 10 ft lbs motors are installed on the valves. The valves are normally maintained open These valves do not base any automatic opening or closing safety functions The design basis safety function of the RC-515 and RC-516 valves is to manually shut to maintain reactor coolant system (RCg :.tegrity. Aside from being cycled shut and open for inservice testing, the PORV block valves would,lIc shut during normal power operation to isolate a q j downstream PORV which had unacceptable leakag or failed open The normal, expected conditions when a PORV block valve would be shut to isolate a PORV at power are 1985 psig. and approximately 630'F. Steam would be the medium Howmg through the PORV block vahes To summan/c the requirements of Techmcal Specifications relating to the PORV block sahes. if ~ q l one or more PORV,bleet' valves are inoperable due to unacceptable seat leakage than the associated block i valvc(s) are shut or the unit is placed in hot shutdown if a PORV is inoperable due to problems other . } than seat leakage, then the associated block vahe is shut and power is remosed from the block valve A PORV block vahe shut due to an inoperable PORV may be shut up to the next refueling outage A PORV block sab e shut dunng normal power operation would be opened w hile a umt is transitiomng from hot to cold shutdown These conditions would be approximately 400 psig and 3bo*F in the RCS The PORV block vahes arc opened to support the low temperature. over pressure protection (LTOP) of the PORVkahw when the RCS is less than 355"F s All four PORV block vahes have a history of being shut to isolate a leaking PORV during normal power operation and then opened while achieving cold shutdown Attached are operating procedures and control operator log entries detailmg two occurrences w hen a PORV bioek valve was shut at normal plant operating condiuons and then opened after coohng down dunng shutdown One of the attached procedures is identified as OP 3C. and is the procedure used to bring a unit from hot shutdown to cold shutdown The PORV block vahes remain shut from normal power operation to hot shutdown Other attached procedures include IT-200 and IT 205 which are the valve stroke test procedures for the PORV and PORV block vahes These inservice tests are performed just pnor to enabling LTOP, when the RC- $15 and RC 516 valves are opened and remain open while reaching cold shutdown The attached control operator logs detail more specific times and operatmg conditions u hen the PORY block valves are shut and opened in the attached documentation, the general Dow of events is PORV found leakmg at normal RCS conditions the associated PORV block valve is shut. the plant is shutdow n. then the PORV is opened while transitiomng from hot to cold shutdown As mentioned earlier, the four PORV block valves and operators are identical. The torque and hnut suitch settings on the four motor-operated valves (MOV's) are set insing the same ranges Their switch settings may not be idemical. A table is attached providing torque switch settings and stem force measurements as recorded during the latest diagnostic tests No modifications has e been made to these valves to m:ke them more susceptible to thermal binding or to affect their operation since these tests wcre performed.

/ Point Beach Nuclear Plant (PBNP)is continutng to make preparations to replace all four PORV block valves The replacement valves will be a parallcl seat gate vahe which are not susceptible to thermal bmdmg Both the Umt I and 2 valves are currently scheduled for replacement m 1998 2 Containment Spray Pump Suction Valves from the Residual Heat Removal System The containment spray pump suction vahes from the residual heat removal system are designated 1(2)SI 871 A and 1(2)SI-871B. There are two of these valves in cach unit. The SI-871 valves are 6 in, double disk wedge gate valves manufactured by Anchor Darling. These valves were determined to be susceptible to pressure locking based on their design and the system conditions these valves experience during a design basis accident. The system conditions wiuch make the SI-871 valves susceptible to pressure locking are containment pressure on one side of the valec, residual heat removal system pressure on the other side of the valve, and a higher pressure in the bonnet of the sahe. The calculation methodology used to evaluate if these valves may pressure lock is the method developed by the Westinghouse Owner's Group (WOG) The WOG methodology includes a 20% minimum margin for acceptance criteria PBNP did not perform any specific validation testing for this calculation methodology since it is based on the WOG methodology. In addition, the valve opemng margins determined in the calculation wetc over the 20% margm The calculated margins varied from 65 - 75% in July 1997, the SI 871 A and SI-871B calculation was revised to include effects of a higher bonnet pressure than origmally assumed The original, postulatea bonnet pressure was 210 psig, which was based on 60 psig containment pressure and 150 psig deseloped head of a residual heat removal (RilR) pump. These pressures are based on the accident scenarios uhen contamment spray is aligned for suction from the containment sump through the RiiR pumps in these scenarios, the St 871 A and SI-871B valves may be opened after experiencmg a maumum of 210 psig. on the RilR side of the valve, which is also assumed to be in the bonnet of the S1-871 valves Containment spray from contamment sump recirculation is procedurally aligned if containment pressure increases after containment spray injection has occurred and the RHR system is operatmg on antainment sump recirculation in the latest revision (7/97) of the pressure locking calculations, the SI-871 vahes u here re-evaluated by assummg a bonnet pressure of 415 psig. The upstream and downstream pressure remained the same as the onginal calculation This higher bonnet pressure could occur when transitioning from operating the RHR system in the low temperature, low pressure condition to normal powcr operation The maximum bonnet pressure of 415 psig. is the PORV low temperature, over pressure protection set point. With this higher bonnet pressure, the SI-871 vah es were determined to be susceptible to pressure locking. As a result, the operatmg procedure which removes the RHR system from operation was revised to include steps to cycle the normally shut S1-871 valves to relicse any built up bonnet pressure after the RHR pumps have been secured and prior to escalating power. The cychng of these vahes after removing the RHR system from operation further demonstrates that they will not pressure lock durmg a design basis accident. After RHR is removed from operation, as explained above, the bonnets of the SI-871 valves could be at a pressure of 415 psig The downstream and upstream sides of the vahe are at or very near a pressure corresponding to the head of the refuchng water stora e s tank. Since the vah es open under these conditions, the valves are capable of upening during the accident conditions of 210 psig. in the bonnet (60 psig. containment pressure + 150 psig, RHR pump developed q pressure),150 psig on one side of the valve (RHR pump descloped pressurc). and 0 psig on the other side f (contain'iii6t pressure) 8 The SI 871 valves are not susceptible to thermal mduced bonnet pressure mercase h During umt start-up, after thc RHR system is remosed from operation the bonnets of the SI-871 vahes are not pressuriecd

since they have been cycled After umt start up, if an accident occuned which required containment sump recirculation to be aligned to the suction of the containment spra) pumps. the SI 871 salve bonnets would be at a maximum pressure of 210 psig, as explamed presiously The temperature of the water which pressuriteri the bonnets would be at the highest expected dunng the accident The SI-871 vahes are downstream of the RHR heat exchangers Smcc no mercase in temperature at the SI 871 saltes will occur after containment sump recirculation is in operation. a thermally induced bonnet pressure increase will not occur. The pressure locking testing report referenced m the Request for Additional Information dated July,10 1997, was reviewed This report, accession number 97012M039 in the NRC public document room, does not contam any new, applicable information relating to the SI 87I valves When required to open, the SI-871 valves will have a depressunzed downstream disk and a bonnet pressure equal to the pressure on the upstream disk with no thermal transients With thcsc conditions and the 65 75% opening margins, there are no pressure locking concerns No vahe leakage was assumed in the evaluation af the SI-871 salves. Attached is the portion of the latest resision to the pressure locking calculation pertaining to the SI 871 valves Also attached is the operating procedure used to remove the RHR sy stem from operation uhere the 51871 valves are cycled The basis for determining that the SI 871 vahes will not pressure lock are the high opening margms determined in the calculation, the operation of the vahes following RIIR system operation, and that no thermal induced bonnet pressunzation occurs.

ATTAril %1 FXI S 1 I etter to Rich.ird R Gngg. dated Juh 10.1997 " Request for Additional Information Re Genene Letter 95-07 Pressure Locking and Thermal ihnding of Safet3 Related Power-Operated Gate Vah es" 2. Operatmg documentation desenbing an esperience when a Umt ! PORY block sahe (IRC 516) was shut dunng normal power operanon and then opened while transitioning from hot to cold shutdown Pagg Degrintion 1 Control room shift tog page w hen the leaking PORV was discovered 2 Control room shift log page w hen the PORY block s ah e was shut 3-4 Control room shift tog pages uhen the PORY blosk vahe was opened 54) Control roort narrata e log pages u hen the PORV block s ah e was shut 10 Cornol room narratne log pages uhen the PQRV block sahe was opened 11 29 iT 200 Pressun/cr Power-Operated Rehef Vahes and Block Vahes 30-81 OP-3C. Hot Shutdown to Cold Shutdown 3 Operating documentation describing an espenence when a Umt 2 PORY block vahc (2RC-516) is shut uhile a umt is lowering power in preparations for a refuchng outage and then opened while transitiomng from hot to cold shutdoun Page Ds 5enpt}on 1-2 Control room shift log pages a hen the PORY block vahe was shut due to a leaking PORY 3 Control room cold shutdown tog pages u hen the PORV block s ah e is opened 4 10 Control room narratne log pages u hen the PORY block s ahe is shut and then opened u hile transitiomng to cold shutdown Il-30 IT-205. Pressunfer Pwe,-Operated Rehef Vahes and Block Vahes 31-71 OP 3C Hot Shutdown to Cold Shutdown 4 PORV Block Vahe Testing information 5 Niemorandum to Richard H Wessman, dated January 23.1997 "Transnuttal of Prehmman Pressure Locking Data from Double Dise Gate Vahe Tests" 6 Operating Procedure for Remosing Residual Heat Remosal System from Operation. OP-7B 7 Section of calculation 96-0062. dated 07/07,97, pertaining to the S1-871 s ahes !}}