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Discusses Plant IST Programs for Pumps & Valves.Informs That Relief Request VR-12 for Plant Has Been Changed from Rev 4 to Rev 4A.Provides Description of Changes
	ML20098D166
Person / Time
Site:	Byron, Braidwood
Issue date:	03/20/1989
From:	Hunsader S; COMMONWEALTH EDISON CO.
To:	Murley T; Office of Nuclear Reactor Regulation
References
	NUDOCS 9205280058
	Download: ML20098D166 (109)
	v • d • e

{{#Wiki_filter:, i / C:mmonw alth Edison 9fi!M N8TO^La_ CMap. iMN Accress Rep'y to Post Omce Dos 767 Chitago. Ilono s 60690 Hatch 20, 1980 j Dt. Thomas C. Murley, Director Office of 11uclear i<eactot Regulat ion ll. S. 11 u c l e a t Regulatory Commission Washington, DC 20$$5 Attne Document Control Desk Subject Draldwood Station tlnits 1 and 2 Inservice Testing (IST) P r og r arn s for hunpa and Valves llFC_ Dmlke k!1Vs._S0-4 SfL orvLD0:4 bt References (a) Sept einbei 15, 1988, L. fl. Olshan letter to it. E. Blass (b) December 21, 1988 R. Chrranowski letter to T.E. Murley (c) August 31, 1987 S.C. Ilunsader lett er to T.E. Murley (d) January 31, 1989 S.C. Ilunsader letter to T.E. Murley Dear Di. Hurleyi Reference (d) provided the Di aldwooc' St at ion (IST) P r og r aus f oi Pwnps (Revision 4) and Valves (Revision 4) that included changes based on the meeting held in response to refeier.*ce (a) at the 11RC White F11ttl Offices on October 27, 1988, and per t.he comments prasented lu the teleconference held on December 12, 1988. These revisions included changes paesented in reference (b) for Dyron Station as they apply to Draidwood Station. tipo n f-dnet teview, Commonwenith Edison has determined that. a change needs to oc made to Relief Request VF-12 to mnke it more consistent. with the Relief Pequest submitted for Dyson Station. As a result, Hellef 8< e q u e s t VF-12 for Draldwood Station has been changed from Revision 4 to Revision 4A. The Valve Relief Request VR-12, Revision 4A, deletes valves 1/2Rr026 and 1/2Rr027 since they no longer apply and includen a rewording in the alternative testing section to match the corresponding Byron Station Relief Request. For the ense of review by the IJRC Staff, the IST Proginm Revision 4/4 A t hat now includet the new VR-12 Relief Request in 'eing transmitted in its ent is et y. tic changes hnve Ieen made to ot he r patt3 of the IST Programs. Attachment A to this letter describes the differences between the Dyron and Draldwood programa. Attachment D to thin letter presents the l differences or changes made between Revision 3 which had been submitted pieviously in teference (c) for Di aldwood St ation and Revision 4/4 A t r provided herein. T' r/ ^; > b 9aosaeoo5e e90320 by/ a h~

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. P ump. O r 99 itm As ruted in pievious submittals, the I ST Pump Pi og r am for braldvood consists of a t abula listing of the pwers which nie i d e nt. l f i ed in the flyt on/fti nidwood "F SAP nc Act ive, and thnt have an emesgency powes sources plus a settes of tiot e s atul Pelief Heque s t fe. Act ive pumps at e defined as those ptunps enlled on to pel f orm a saf ety f unction at; well as to accomplish h and mnint ain a saf e teactor s hut down. The only exception etc the diesel drive auxiliary feedwater punip s ( 1/ 2 Af 0 ll'li) which are included in the e pr ogr am although they at e not supplied by nn emer<jency powet

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Two (2) essent inl seivice water mnkaup pumps (OSX02PA, O SX 02 Pit ) are included in the Byron ptogram. These pumps supply mnkeup water for the n e, s. n n t. i n 1 service wnt er cot'l i ng tewei3 !>ue to n difference in der, ion, litaidwood does not have these cooling t ower s, nnd hence doen not have these nps. s Veilve_.Pt091om The IST Valve P r og t am for Danidwood consists of a tabuln: listing of ASMP Section Class 1, 11, and 111 volves which have been assigned a , sciien of notes and relict requesta. npeci f ic Code ent egory, plus Volves USXU28A nnr*. 11 nre part of the essentini service water makeup system and like the two ptmps listed above, nie pntt of the Byton instnljntion but are not inrtalled at Bialdwood. Becaune of differonens in valve sttore times, the volven 1ist ed in VP-12 (the fast. ncting volves) are different. Byron Station includes the vnives 1/2PR066 and 1/2S(8811 while Braidwood Station does not. These ptograms nre being submitted ior f1RC revlew and eccept noce Please address nny questions you rnny hnve regniding these programs to this office. very t :uly your s, / (s- '/, '. h*/ < t a r w t' u /; S.C. Hunsades rin c l e n t 1,1 censing Admi ni s t i nt e r 3 / sci:0031V: 1-2 cce s Sands-11PP Pesident I ns pec t or -it s a i,twned .fulinn liinds-Poqion l!! t(

- -. _. - - _ _ - - - ~.. - - - - -. - - - - - ~ -. ~. - -.. -. _.. ~. ATIACID4EllL"A'.' IST PROGRAM Pl4Att DYROt1/DRAIDWOOD DiFPERENCES The f ollowing presents t he dif f erences ' t. sn the Dyson and o Draldwood Pump and Valve IST Program Plans: A) 11yron Pump Program (Rev. 7) Di aldwood Ptump Progr am ( Hev. 4) l l .llyron prograre includes -N/A, since Uraldwood does not have j EX Makeup Pivnps. SX Makeup Piuaps or the related OSX028A and D valves. i -Dyton Control Volume (CV) .-fireldsood Control Volume (CV) Pumps are included in PR-$ Ptumps have penteanent.ly installed flow measurement devices and, t hu tt do riot regtnire the use of an ultrasonic flowmeter la PR-3, 11 ) 11yron Valve Program (Rev. 8) Draldwood Valve Program (Rev. 4/4A) -Byron pcogram includes fo -tir aidwood progr tun includes a 15 valves 1/2CS019A,fi a Stroke second stroke tirne t line of 30 seconds, to more closely match the responne tline surveillance r equi r erne n t s. -Dyron program includes -Dr aldwood progreen does. not include valves with fast acting certain valves previour'y in sttoke times, per VR.12. this relief request that have a slower atsoke time histoty and have beer, deleted. I i i l' i /sc1:0031V 3 - -.-., -...~.-. -

_~_.m-m.___.__,__.._..-,_.___ e 'e ATTAOl!4EHL."E" DRA1! MOOD IST PROGRAM P1,Ali REVIS1(44 3 TO REV1Sl(N 4 /4 A D? fTEREliCES AliD CilAflGES The privnary dif f erence between Revision 3 and Revision 4/4A ls the ad".tlon of Draldwood Unit 2 Pump and Valve EPil's to the Tables, llotes and P lief kequests. Other changes made are as follows: A) l'wnp f. 1) Page 3-9 added a statement for vertical line shaft pumps to more clearly define test methodology, par ASMC OM 6, 2) Page 3-12 deleted Control Volume (CV) pumps flott. PR-3. These pumps have permanently Inst alled flow measur ement equipment and thus do not. use the ultrasonic flow rneter, D) YalVDs 1) Removed XT designation for 1/2CS008A,D in 5 of 42 tables, as this was inadvertently left in, In Revision 3. VR-4 st ates pattial stroking using air Is not practical. 2) In 5 of 42 tablen, for 1/2CR019A,D revised ranximtun stroke tirne of 30 seconds to read 15 seconds to coincide with response time requirements. 3) For t.he following valves, far,t acting valve Rollef Request VR-12, no longer applies. ElW _l'e y e _. 1/2cV8152 7 of 42 1/2CV8160 7 of 42 1/2PR066 20 of 42 1/2SD005A-D 31 o f 4 2 1/2510871 34 of 42 j 1/2518880 34 of 42 1/2818064 36 of 42 1/2518888 34 of 42 4) In 7 of 42, 1/2CV8481A,D and 1/2CV8546 have Re11ef Request VR-15 designated. tiote 8 has been removed from 1/2CVB481A,D as it no longer applies, 5)- In D of 42, revised 1/2DG5185A,D and 1/2DG5184A.D valve categoty from-Type D to Type C, typo. 6) In 15 of 42, revised 1/2]A065 and 1/21A066 for ST and FT in FR as per Vi<-10 r6 visions. 7) In 17 of 42, revised st.roke times of 1/2MS018A-D to reflect VR-12 requirements. 8) .In 21 of 42, revised stroke times of 1/2PS228A,D, 1/2PS229A,D and 1/2PS230A,8 to reflect VR-12 requitements. Revised 1/2PS231A,D valve category to AC. _. -. - - _ - _ _ _ _ _ _ _.. _ _ _ _ _.., _. _ _ _ _ _ _ -.. - _. -. _ -...,. -... ~. _ -., _. _. _ - _. _ _.,. -.

ATTACllMLill_"D" (cont'd) VLVoltes %9ntanued 9) In 24 of 42, revised stroke times for 1/2RE9156, 1/2ho9159A,H and 1/?RE9160A,D per Vk-12. 10) In 25 of 42, revised stroke times per VR-12. 11) In 20 of 42, revised 1/2RH8705A,B valve category to AC. 12) In 33 of 42, revised typo for 1/2S18819A-D so t hat test inode is RR. ] 13) in 34 of 42, revised typo for 1/2S18905A-D so that test mode 1s RR. 14) in 35 of 42, revise 1/2518949A-D no that test mode la RR. j 15) in page 3% of 42, deleted soferer.ce to XT for valves 1/2S189480,D as it wes n typo. 16) In the note section page 4-11 f or tiote 8 deleted ref erence to 1/2CV8481A,D valves as ther,e are now i n VR -15. 17) In page 4-12, foi flute 12, corrected typo on valve EMi's. 18) In the Reljef Request section for VR-1 page 4-18 added a clarification of section Xi testing for leak rates. 19) In VR-4 page 4 21, added more justification for not teetlag the affected valves during operations or cold shutdown. 20) In VR-12, page 4-29, delet ed valves 1/2CVB152, 1/2CV8160, 1pR066, 1/2SD005A-D, 1/2518871, 1/2S18880, 1/2S18888, 1/2818964. Rewrote alternate testing to clarlfy testing trending requiremonts. 22) In VR-15, page 4-34, added 1/2CVB481A,B ond 1/2CV8546. Revised wording to clarify basis for relief, alternate testing and justification. -23) in VR-16, page 4-36, rewrote basis for relief and justification. 4- /scit0031Vt4 5

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Revision 4' Table of Contents - 3.0 Pr6 service / Inservice Testing Program for-Pumps-Page 3.1 Program Description 3-1 -3.2 Progrtm Tables 3-3 3.3 Notes 3-5 Note 1 Pump Bearir,$r 'Shaf t Bearit 3-6 Note Pumps Lubricated by Pumpet F 3-6 Note 3 DELETED 3-6 l 3.4 Relief Requests 3-7 PR-1 LPump Vibration 3-B-PR Pung Bearing Temperatures 3-10 PR Ultrasonic Flowmeter usage 3-12 FR Differential Pressure 3-14 h ( h 4 3-11 l 0629m(010989)/2-l

Revision 4 4 4 I 3.1 PROGRAM DESCRIPTION 3-1 0629m(310999)/3 l

...m._.- _._.m >-._..--._..._.__.y_ _ - -. _ _. _.. _..... _ _. _ _ _. ~ _ Revision 4 l Program Description The Pump Preservice/ Inservice Test ng Program for Braidwood Nuclear Power i - Station Unit 1 and Unit _-2, is-implekented in accordance with the requirements of Subsection IWP of Section XI of the ASME Boller and Pressure Vessel Code, 1983 Edition, Where these requirements are-determinea to be impractical, specific relief is requested. Additional pump relief requests may be necessary and these will-be identified during subsequent inservice _ tests. The pumps subject to !SI testing are-those - pumps whic?. are identified in the Braidwood FSAR as Active. and have uan emergency power source. Active pumps are defined as those which are called on to perform a safety function as well as to accomplish and maintain a safe reactor. shutdown. The only_ exception are the diesel driven auxiliary feedwater pumps, 1/2AF0lPB which are included in the program although they are not supplied by an emergency power source, j Pump referer.ce values shall be determined f rom the results of a preservice test, which may be run during preoperational testing, or from the results of the-first inservice test run during power operation. Reference values shall be at points of operation readily duplicated during subsequent inservice testing. Additional reference values may be necessary and these-wil. be taken in accordance with IWP-3111 and 3112. In the. event a pump must be declared inoperable as a result of inservice testing, limitations on plant operation will be as stated in the Technical Specifications. Section XI of the ASME Boiler and Pressure Vessel Code shall not + construed to supersede the requirements of any Technical Specification. 4 3-2 0629m(0126891/4 i _.,. ~...,.... _ _ _ _.,

Revision 4 3.2 PROGRM TABLES 4 3-3 l l. 0629m(010939)/5. f l 1 i m r a w r --+---.e-

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___m-_ 1 Revision 4 Table Destription l The following information is included in the summary tables: J The first four columns include the unique *raidwood Station Equipment Piece Number, the Pump Name, the Code Class, and the PLID en which the i pumps a co located. Speed: Speed will be measured by a tachometer or stroboscope for variable speed drives. Inlet pressure: Inlet pressure will be measured via permanently installed gauges or other means, provided the

uipment accuracy meets the requirements of IWP-4150. This is to be measured both before pump startup and during the test.

Differential pressure: Differential pressures will be measured using calibrated differential pressure gauges or by recording the difference between calibrated inlet and outlet pressure gauges. Flow rate: Flow rates will be measured using permanently installed instrumentation or other means, provided that equipment accuracy meets the requirements of IWP-4150. Vibration: Vibration measurement shall be made using portable or hand held instruments at locations as marked on the pumps. Bearing Temperature: Bearing temperature will be measured by permanently installed devices where such devices are present. Portable measurement devices will be used where temperature wells are provided. Per IWP-3300. bearing temperatures are required only once per year. Braidwood Station takes the data for bearing temperatures once per year during suver testing. Test Interval: An inservice test shall be run on each pump nominally every 3 months during normal plant operation, in accordance with IWP-3400. Lubrication Level: Lubrication level will be observed through sight glasses for the pumps listed in the program. Revision: The current revision of the program is listed. Table Page: The table pages are numbered sequentially and show the total number of pages. 3-4 0629m(010989)/6 i'

l'. Revision 4-3.3 NOTES 4 L 4 3 3-5 0629m(0109B9)/11

Revision 4 NOTE 1 The Diesel Oil Transfer (ID00lPA-D and 2000lPA-01. Re:;idual Heat Removal - -(lRHolPA,B and 2RH0lpA,B)'and Containment Spray.(ICS0lPA,B and 2CS0lPA,B) pu:tps cannot be measured for lubrication level. These pumps are. lubricated by the fluid pumped and hence have no indication for -lubrication level. NOTE 2 The Component Cooling pueps (OCColP, ICColPA,2 and 2CC0lPA,B) Essential Service Water Pumps (ISX0lPA,B and 2SX0lPA.B), and Control Room Chill --Water Purnps (CWO0lPA,B) are in systems which are in continuous operation. The idle inlet pressure for these pumps cannot be obtained without interrupting normal system operation and causing system transients. The idle inlet pressure will be recorded only if.the pump to be tested is not-in operation at the start of the test. Proper pump .l operation is assured by continuous pump operation as well as quarterly-monttoring of the remaining ISI pump parameters. NOTE 3 -DELETED-l l l 1. 3-6 0629m(010989)/12

.. ~... ........... -.. ~. -. - - _. - - -. - - - - -... - -. -. .. ~... Revision 4 't i 3.4 RELIEF REQUESTS f l-I. l -': I-i. l' I l l' 3-7 0629m(010989)/13 l 2 I-

s . Revision.4-i \\ RELIEF REOUEST NO. pR-1 1. PUMP NUMBER: All pumps in the program plan. - i 2. ltf)MBER OF_ ITEMS: 39 pumps. 3. ASME CODE CLASS: 2-& 3 4. - ASME CODE, SECTION XI REQUIREMENTS: In reference to Table IWp-3100-2, " Allowable Ranges of Test Quantities"; pump vibration is to be measured in and compared to values given in mils. displacement. 5. BASIS FOR RELIEF: The measurement of pump vibration is required so that developing problems can be detected and repairs initiated prior to a pump becoming inoperable. Measurement of vibration only in displacement quantities does not take into account -frequency _ which is also an important f actor in determining the severity of the vibration. 6. . ALTERNATE TESTING: The ASME Code minimum standards require measurement of the vibration' amplitude in mils (dtsplacement). Braidwood Station proposes an alternate-program of measuring vibration velocity (inches per second) which is more comprehensive than that required by Sectton XI. This technique is an industry-accepted method which is much more meaningful and sensitive to-small' changes that are indicative of ' developing mechanical problems. These velocity measurements detect not-only'high amplitude vibration, that indicate a major mechanical problem such as misalignment or unbalance, but also the equally harmful. low amplitude, high frequency vibration due to bearing wear that usually.go undetected by simple displacement measurements. The allowable ranges of vibration and their associated action levt;s will be patterned after the guidelines established in ANSI /ASME CM-6 Draft 8,' Table 6100-1 and Figure 6100-1. These ranges will be used to assess equipment operational readiness for all components. i b 3-5 - 0629m(010939)/14 4 v p y + -,4 ., a w g e e' w .w-w,. erso w-

L 1 Revision 4 l l 1The acceptable performance range will be 1 0.5 times the 1 reference valus,-not to exceed.325 inches per second. The alert range, at which time the testing frequengv_would be doubled,1will be > 2.5 to 6-times the reference value, not to ( exceed.70 inches per second. 2.ny libratin; velocit u reater than 6' times the reference value or greater than.70 inches per second will require correc.tive a_ctions to be performed on the af f ected component. Vibration measurements for all pumps will be obtained and recorded in velocity, inches per second, and will be broadband unfiltered peak measurecents. The monitored locations for v:bration analysis will be marked so as to permit subsequent duplication in both location and plane. The frequency response range of the vibration transdu:ers and their readout system shall be capable of frequency responses from one-third minimum pump shaft rotational speed to at least one thousand herte. The Vertical Line Shaft Punps in the program will have vibration measurements taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction. 7 JUSTIFICATION: Measurement o vibration in mils displacement is not as sensitive as velocity measurements to small changes that are indicative of developing mechanical problems. Therefore, the proposed alternate of measuring vibration amplitude in inches /second provides added assurance of the continued operability of the pungs. 8. APPL! CABLE TIME PERIOD: This relief is requested once per quarter during tne first inspection interval, l l. i. 3-9 0629m(010939)/15 l l l

.~.. - --.- -.--- - .. ~. Revision 4 REL!EF REQUEST NO. PR-2 1. ' PCMP ffUMBER: OCC0lP,-1CC01PA&B,-2CC0lPA&PS, ICS0lPA&B. 2CS0lPASPB, 1RH0lPA&B, 2RHOLPALPS.1D001PA-D, 2D00lPA-D, CW301FA, 0WC0lPB 2.- h"JGER OF ITEMS: 23 pumps 3. ASME' CODE CLASS: 0&3 4. ' ASME CODE. SECTION XI REQUIREMDJTS: Per IWP-3100, Inservice T-st Procedure pwrp bearing temperatures are required to be measured to detect-any change in the mechanical characteristics of a bearing,- IWP-3500(b) requires three successive readings taken at ten minute intervals that do not vary more than 3%, .5. BASIS FOR RELIEF: a. These punps' bearings are not provided with permanent temperature detectors or thermal wells. Therefore, gathering data on bearing temperature is impra:*1 cal, b. The only temperature measurements possible are f rom the bearing housing. To detect high bearing temperature =at the bearing housing would require that the bea rings in question be seriously degraded. c. Measurement of housing temperature on these pumps does not I provide information on bearing condition or degradation. For example, the bearings on the Diesel Oil Transfer Puaps, ~(ID00lPA-D, 2D00lPA-D) are cooled by'the fluid pumped. Therefore, any heat generated by degraded bearings is carried away by the cooling fluid and would not be i directly measured at the bearing housing. l.~ 3-10 0629m(010939)/16 =,. ~,,. _,.,,,. ..,-,n..

Revision 4-5.~ ALTERNATE TESTIN0: No direct alternate test is proposed for bearing -temperatures. -However, measurement of hydraulic parameters and vibration readings do provide a more positive method of monitoring pump condition and bearing degradation. 7. JUSTIFICATION: Sy reasuring pump hydraulic parameters and vibration velocity, (as described in PR-1), pump operability and the trending of techanical degradation is assured. Also, since these_ parameters (i.e., Hydraulic parameters and vibration) are measured quarterly, the pump mechanical condition will be more accurately determined than would be possible by measuring bearing temperature on a yeerly basis. 8. ApFLICABLE TING FERIOD: This relief is requested once per year. -f during the first inspection interval. h I 1 i l l 3-11 0629m(010989)/17 l

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..--.~_------~~ Revision 4 t.- RELIEF REQUEST NO. PR-3

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PUMP NUNTER: OCColP, ICColPA&B, 2CC01PA&B, ISX0lPA&B, 2SXOlPA&B, 1DOO1PA-D,-2DOO1PA-D--

2. -NUMBER OF ITEMS:'

17 pumps 3. A E _ CODE CLASS: 2&3 4. ASME CCDE, SECTICN XI REQUIREMENTS: Per IWP-4120, the full scale range of each instrument shall be three times the reference value or less. BASIS FOR RELIEF: The full scale range of ultrasonic flowmeters. used to collect Section XI flow data, exceed three times the reference value. 6. ALTERNATE TESTING: Ultrasonic flowmeters, with digital readouts and totalizer features will be util22ed to obtain Section XI flow data. 7. JUSTIFICATION: Ultrasonic flowmeters provide an accurate means of measuring flowrate. They utiliza a digital display wnose accuracy is independent of the full scale range. The ultrasonic flowmeter is well within the requirements of IWP-4110 and IWP-4120, which refer to an-instrument accuracy of f 2% of full scale for an instrument with a range of one and one-half to three times the reference value. The following examples uill illustrate _this point. The component cooling pumps (OCC01P, ICC0lPA, and ICC01PB) have a reference value of approximately 4500 gpm. Using the Code requirements, an inr.trument with a full scale range of 13,500 gpm (3 x 4500 gpm), the acceptable instrument accuracy is 270-gpm (,02 x 13500 gpm). Using the ultrasonic flowmeter, with an accuracy of : 3% of the indicated reading, provide an instrument accuracy of 2 135 ( 03 x 4500 gpm). The diesel oil transfer pumps (1D00lPA-D) have a reference value of approximately 25 gpm. Using the Code requirements, an instrument with a full scale of 75 gpm (3 x 25 gpm) the acceptable instrument accuracy is t 1.5 gpm (.02 x 75'gpm). Using the ulttasonic flowmeter with an accuracy of 3 3% of indicated reading will provide an instrument accuracy of 1 0.75 gpm (.03 x 25 gpm). 3-12 i 0619m(012689)/18 l l n t

__m.. Revision 4 + J RELIEF-REQUEST NO. PR Use of an ultrasonic flowmeter, with totali:er and integrator feature, instead of other instruments allowed by IWP-4110 and -IWP-4120, wil. provide more precise and accurate flow measurements. 8. APPLICABLE TIME PERIO;D: This relief is requested once per quarter, during the first inspection interval. e w l~ l l l { l. 1-3-13 0629m(010989)/19 i -I

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__._....___.__..._m. i Revision 4= r IRELIEF-REQUEST-NC. FR.- 1. = PUMP NUMEER: -ID00lPA-D,- 2DC0lPA-0. -2. UUMBER OF ITEMS: 3 pumps 3. ASME CDDE CLASS: 3 e-4. A y CODE, SECTION XI RE1UIREMENTS: Per IWP-3100, differential pressure shall be measured on all pumps that are tested. '5. BAS!S - F0h RELIEF: These pumps are positive displacement-Diesel Oil Transfer Pumps. The pump differential pressure is not a factor affecting pump performance, but rather dependent only on the inlet pressure-to the pump. As the pump discharge pressure is constant, and the inlet pressure varies with tank level, the differential pressure is not a valid operational parameter. 6. _ ALTERNATE TESTING: Pump discharge pressure for positive displacement pumps is a valid operational parameter.. This will be used to evaluate the Diesel Oil Transfer Pumps performance. 7. JUSTIFICATICN: Using pump discharge pressure in lieu of pump differential pressure will provide meaningful pump performance data for evaluation of operational readiness of the Diesel Oil Transfer Pumps. 9. APPLICABLE TIME PERIOD: This relief is requested once per quarter during the first inspection interval. . 14-0629m(010989)/20 I

4 INSERVICE TESTING PROGRAM PLAN UNIT O,l1, 2 t 1 ASME CLASS 2 & 3 PUMPS i BRAIDWOOD NUCLEAR POWER STATION REVISION TABLE PAGE l '.4 .I Of 4 C TEST PARAMETERS L A LUBRI-l S SYSTEM INLET DIFF FLOW BEARING TEST CATION .j PUMP _!EJMBER _ PUMP ytAME S P,& ID SPEED PRES J gES _ RATE._ VIBRATION TEMP _ INTERVAL _, _ t EVEL. _ RD1ARFE _ .[ ~ 1Ar0lPA Auxiliary feedwater 3 tb37 No-Yes Yes Yes PR-1 Yes Quarterly Yes Pump i .APOIPB Auxiliary Feedwater 3 M-37 Yes Yes Yes Yes PR-1 Yes Quarterly Yes Pump (Dresel) [ t 2AF0lPA Auxiliary Peedwater 3 M-122 No Yes Yes Yes PR-1 Yes Quarterly Yes l Pwnp } j-2Al'01PB Auxiliary Feedwater 3 M-122 Yes Yes Yes Yes PR-1 Yes Quarterly Yes l 4 Pump .1 OCC0lP Component Cooling 3 M-66 No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Note 2 ( Pump ICC01PA Component Cooling 3 .M-66 No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Nute 2 Pump 4 ICC01PB Component Cooling 3 M-66 No Yes Yes PR-3 PR-1 PR-2 Qua rterly Yes Note 2 Pump '2CC0lPA Component Cooling 3 'M-66 No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Note 2 Pump i 2CC0lPB Component Cooling 3 M-66 No Yes Yes PR-3 PR-1 FR-2 Quarterly Yes . Note 2 Pump ICS01PA Containment Spray 2 M-46 'Ho Yes Yes Yes PR-1 PR-2 Quarterly No . Note 1 Pta p r { ICS01PB Containment Spray 2 M-46 No Yes Yes Yes P,k-1 PR-2 Quarterly No Note 1 Ptep f 0629m(010989)/7 I I 'I

lliI g; ! f er' [: r ir L!jI ' 3 !I l E{ i! {! i! ? . 2 1 S s K 1 I 1 1 1 1 1 , 0 RA e e e a e e e T E t t t. t t t t 4 I G D o o o o o o o , N A R N N N N N N N , U P' E '4 Lf B o A - NO 'L T2 IRI E BTV s 3 s s UAE o o e r e o o o o o LCL N N Y Y Y N N N N N y y y y y y y y y y y L l l l l l l l l l l l A r r r r r r r r r r r TV e e e e e e e e e e e SR t t t t t t t t t t t EE r r r t r r r r t r r TT a a a o a a a a a a a N N u u u u u u i u u u u h O I Q Q Q Q Q Q ( Q Q Q Q I S G' I4 N V I P E RM 2 2' 2 2 2 2 2 R AE s s s s ET R R e e e e R R R R R B P P Y Y Y Y P P P P P N N O i O I 1 1 1 1 1 1 1 1 1 1 1 R I T E T S _ A k R R R R R R R R R R P A R R P P P P P P P P P P {' ST E B M PS T _ I A M L V R UR M G PE A HE 3 3 3 3 3 O W R 1T s s s s s s R 3O A A e e e e e e R R R R R f .P P P PR Y Y Y Y Y Y P P P P P 6 G R T FS 4 4 4 4 4 N ,A S FE s s s s s s I 2E E _ I R e e e e e e R R R R R T - L T DP Y Y Y Y Y Y P P P P P S SC E SU r T AN L* S L LE s s s s s s s s s s s C CD iR e e e e e e e e e e e t C O I P Y Y Y Y Y Y Y Y Y Y Y I EO V MW D ~ R SD E E E AI . S A P o o o o o o o o o o o N R S N N N N N lI N N N N N I B c MD l EI i 9 8 8 0 T 2 2 4 4 3 3 0 0 0 0 3 S& 1 1 6 6 1 1 5 5 5 5 1 Y SP M M M M M M M M M M M g CLASS 2 2 2 2 2 2 3 3 3 3 3 g g g g n n n n r r r r r i i i i e e e e e y y g g g g f f f f f a a r r r r s s s s s r r a a a a n n n n n E p p h h h h a a a a a M S S C C C C r r r r r A T T T T T N t t l l l l n n a a a a l l l l ' l P e e g g g g i i i i i M m m u u u u O O O O O U n n f f f f P i i i i i i l l l l l a a r r r r e e e e e t p t p t p t p t p t p sp sp sp sp sp nm nm nm nm nm nm em em em em em u i u i u 8 ou ou eu eu eu eu i u 2 u i CP CP CP CP CP CP DP DP DP DP DP / ) 9 R 8 E 6 B 2 M 1 U A B A B A B A B C D A 0 N P P P P P P P P P P P ( l l l l 1 l 1 1 1 l 1 m P 0 0 0 0 0 0 O 0 O 0 O 9 M S S V V V V O 0 O 0 O 2 U C C C C C C D D D D D 6 s P 2 2 I I 2 2 I I I I 2 0 i - g

l l
4 4

j' i]' I ,l 4

r, if4 y((;ili lll > i r! :f ,fl!. f t i j n 2 1 S O R 'l 1 1 I 1 I .1 K A e e' e e e e e T E M t t' t t t t t G E o o o o o o o I N A R N N N N H N N U P 4 ELf Bo A - N T3 I OL RI E BTV s s UAE o o o o o o o e e LCL N N N N N N N Y Y y y y y y y y y y L l l l l l l l l l .A r r r r r r r r r TV e e e e e e e e e SR t t t t t t t t t EE r r r r r r r s r TT a a' a a a a a a a N N u u u u u' u u u u O I Q Q Q Q Q Q Q Q Q I S G I 4 N V I P E RM 2 2' 2 2 2 2 2 R AE s s ET R R' R R R R R e e B F P P P P F P Y Y N . N' O N O I 1 1 1 1 1 1 1 1 1 A I T L T S ,A R R R R R' R R R R P A' R R F P P P P P P P P T E B M SS' N I A P V R MR M G UE A WE 3 3 3 O PW R OT s s s s s s R O A LA R R R e e e e e e P 3P P FR P P P Y Y Y Y Y Y G &R T FS 4 4 4 N A S FE s s s s s s I 2E E I R R R R e e e e e e T L T DP P P P Y Y Y Y Y Y S SC E SU T T AN' ES L LE s s s s s c s s s E CD NR e e e e e e e e e C O I P Y Y Y Y Y Y Y Y Y EO I V MM D R SI E E AI E S A P o o o o o o o o o N R S N N N N N N N N N I B MD EI 0 0 0 7 7 . S &_ T 3 3 3 2 2 3 3 1 1 1 1 1 6 6 1 1 6 6 Y SP M M M M M M M M M CLASS 3 3 3 2 2 2 2 2 2 r r r e e e f f f s s s n n n n n o o E a a a i i M r r r t t t t t t A T T T sp ap ap ap c c l l l u u lem em e e em N ieos l I u u j j P i i i l P P P I P n n l l M O O O l l l l I I U al al al a1 P l l l ua ua ua ua y y e e e d v d v d v d v t t i o i o i o i o ep ep sp sp sp em en en s m sm sm sm f m f m u u u iu i t i t e e ee ee ee au at 9 DP DP DP RR RR RR RR SP SP / ) 9 R 8 E 6 B 2 M 1 y B C D A B A B A B 0 P P P P P P P P P ( J 1 l I l i 1 l l m '1 P 0 O 0 O 0 I O 0 0 9 l l 0 i M 0 O 0 i I i I I 2 U 0 D D R k R R S S 6 l' 2 2 Z I I 2 2 I I 0 i

1 INSERVICE TESTING PROGRAM PLAN UNIT 0. 1,. 2 a ASME CLASS 2 & 3 PUMPS BRAIDWOOD NUCLEAR POWER STATION __RENISION TABLE PAGE__ __ _ _... _. _ _ _ u_ 4 4... o f 4 j C TEST PARAMETERS .j L. n.._._ .2. A LUBRI-S SYSTEM 1NLET DIFr FLOW BEARING-TEST CATION ~ PUMP NUMBER PUMP NAME S P & ID. SPEED PRES PRES RATE VIBRATION TD4P ' INTERVAL LEVEL REMARKS ~ 2SIO1PA Safety' Injection 2 M-136 No Yes Yes Yes PR-1 Yes. . Quarterly Yes Pump 2S101PB -Safety Injection 2 M-136 No Yes Yes Yes PR-1 Yes harterlf Yes. Pump 'f Yes' . Note 2 ISX0lPA Essential Service 3 M-42 No Yes Yes PR-3 FR-1 Yes Quarterly. Water Pump ISXOlPB Essential Service 3 M-42 No Yes Yes PR-3 PR-1 Yes Quarterly Yes Note.2 Water Pump 2SX0lPA -Essential Service 3 M-42 No Yes Yes PR-3 PR-1 Yes Qthirt e rl y Yes . Note 2 Water Pump 2SX0lPB Essential Service 3 M -42 No. Yes Yes PR-3 FR-1 Yes Quarterly Yes Note 2 i Water Pump OWOOIPA Control Roma 3 M-118 No Yes Yes Yes PR-1 PR-2 Quartetly Yes Not"e 2 Chilled Water OWOO1PD Control Room 3 M-118 No Yes Yes Yes PR-1 PR-2 Quarterly. Yes Note 2 [ Chilled Water 4 P I t t .t e 0629m(010989)/10 i a

__m_ - - _.......... _......-._ _. _.. - -. - _ _ _ _.. -. _.. _ = l..+ -. ' 6 l~ Revision 4/4A' 4.0 PRESERVICE/ INSERVICE TESTIllG PROGRAM PLA!1 FOR VALVES 4-1 s - 0629m(010989)/21 e v -s c ..,-r. =,,

Revision 4 . Table of Contents 4.0 Preservice/ Inservice-Testing Program ~ Plan for Valves Page 4.1. Program Description-4-1 4.2; Program Tables 4-3 -4.3 Notes 4-9 Note 1 Main Steam Isolation Valves 4-10 Note 2 CV System Boric Acid injection check valve 4-10 Note 3 Main Feedwater Isolation Valves 4-10 Note 4 CV system letdown and make-up isolation valves 4-10 Note 5 RRR pumps suction isolation valves 4-10 Note 6 Intersystem LOCA_ check valves 4-11 Note 7 Reactor Vessel vent valves 4-11 Note 8 CV,-RHR pump discharge check valves 4-11 Note 9 CV, RHR ECCS check valves 4-11 Note 10 Main Feedwater waterhammer prevention valves 4-12 Note 11 VQ Purge Supply and Exhaust Isolation valves 4-12 Note 12 AF Suction and Steam Generator Check Valves 4-12 Note 13 CV High Head Injection Isolation valves 4-12 Ncte 14 SVAG Valves 4-13 Note.15 Deleted 4-13 Note 116 Main reedwAter Fegultting Valves 4-13 Mote 17 Main F',edwater Regulating Bypass Valves 4-13 Note 18 Fe-# ieter Temperina Flow Control Valves 4-13 Note 19 Delettd 4-13 -Note:20 Remote Position Indication of Solenoid Valves 4-14 Note 21 Process Sample Check Valve Stroke Test-4-14 4.4 Relief Rvgues s 4-15 VR-1 Appvndix J valves 4-16 VR-A Corta nment spray NaOH additive check valves 4-19 14

ECCS injection check valves 4-20 i R-4 Containment Spray ring header check valves 4-21 VR-5 Accumulator discharge check valves 4-23 VR-6 _SI Pump Suction check valve 4-24 VR-?. DELETED 4-25 VR-8 Component Cooling RC Pump thermal barrier valves 4-26 VR-9 RC pump seal injection CV check valves 4-27 VR-10. Instrument Air. Containment Isolation Valves 4-28 VR-11 DELETED 4-30 VR-12 Valves stroking normally in two seconds or less 4-31 VR-13 Diesel Generator Starting Air Solenoid Valves 4-33 VR-14 DELETED 4-35

1

-VR-15 DCCS Check Valve Stroke Testing 4-36 VR-16 Containment Sump Outlet Isolation Valves 4-38 VR-17 SX Solenoid talve Stroke Testing 4-40 4-ii 4 - 0629m(016689)/22 l

.... ~. . l -a, Revision 4 l 4.1 i r PRCGRM DESCRIPTION 4 4 d i ' a 4-1 0629m(010989)/23 . - - - =.

, ~ ~ -.. -. - -.. -.. -. ~ ~ -. ~... Revision 4-l. 9-program Description a The Preservice/ Inservice Testing Program for Class 1, 2, & 3 valves

neets the requirements of' Subsection IWV of the_ASME Section XI Code, 1983 Edition. Where -code requirements are det ernined to be impractical, specific requests for relief are written, referenced, and included with.the tables. Additional valve relief requests may be necessary and these will be identified during subsequent insarvice tects. : The tables list all code Class 1, 2 & 3 valves

- which have been assigned a specific code category as directed by Subsection IWV of Section XI. The tables are organized by system and further identified by code class and' code category, using PLID references. Af ter installation and prior to service, all valves. identified in this program will be tested as required by Subsection IWV-3100 of Section XI of the ASME-Code. These tests will be conducted-under conditions similar to those to be experienced during subsequent inservice tests. W' hen a valve or its cortrol system has been replaced or undergone maintenance that could affect its performance, . it will-be retested.. prior to its return to service, to demonstrate that all performance paraneters are within acceptable limits. i. In the event a valve must be declared inoperable as a result of inservice testing, limitations on plant operations will be as stated in.the Technical Specifications. - Section XI of the-ASMI Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of the Technical Specifi. cations. l.: I I I l l t 4-2 p 0629m(010989)/24 l l 1 -r m y r -*,y e-.w,-~,,-.n %.y y .,,.-,-m----y.- .w..- ,.. y ,w p-. 9-, - -.

.. _ _ _ _. _ _ _ _ _.. _. _ _... _. ~. _ _ _, _. Revisto, 4 4, PROGRAM TABLES g 4 4 F S {. s l e i 4-3 0629m(010989)/25 i _. - -,..~

,,.-........e.. . _... ~. ~~..:~.--.-.-..-~ = -. _. _.... Revision 4 Table Description The following information is included-in the summary tables: A. SYSTEM The system in which a valve is located is denoted by the abbreviated system-identification. B. REVISION The revision corresponds to the current revision of the program. C. PAGE The pages are numbered sequentially and show the total number of pages. D. VALVE NUMBER The valve number references the unique Braidwood Station equipment piece number (EPM). This specific valve number identifies the unit and system. E. P & ID The P & ID column references the specific P & ID number and sheet. number, which the valves are located on. F. CLARS The class refers to the ASME class assigned to the specific valve. - G. VALVE CATEGCRY-The valve category identifies the valve category defined in [ subarticle IWV-2200 of ASME Section XI. l - n. VALVE Size i' The valve size lists the nominal pipe size of each valve in

inches, 4-4 0629m(010939)/26 l-

.n Revision 4 LI, VALVE TYPE = The valve type categorizes the valve as to its valve design. The following abbreviations will be use6 to identify specific valve types: Gate GA Globe GL Butterfly BTF Check CK Safety Valve SV Relief Valve RV Power Operated Relief Valve pORV Diaphragm' Seated D Plug P Angle AN J. ACT' TYPE The actuator type identifies the valve actuator. The -following abbreviations will be used to designate specifte types o't valve actuators: Motor Operated M.O. Air Opera:ed A.O. Hydraulic Operated H.O. Self Actuated S.A. Manual M Solenoid Operated 5.0. K. NORMAL POSITICy Normal positior, identifies the normal operating position of a specific valve. O for'open and C for closed. L. STROKE DIRECT. The stroke direction identifies the direction :he valve -actuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function. O for-open, and C for closed. This identifies the direction the valve stem will move when tested. Note: Exercising of power operated valves will involve-stroking the valves to both its open and closed positions. The valve will'only be timed, however, in the direction designated to perform its safety function. Therefore, the program plan specifies only the direction in which valves must be stroked to be timed. l^ 1 I 4-5 0629m(010939)/27 l i l

Revision 4' M. TEST-METHOD The test eethod column identifies specific tests which will be performed on specific valves to fulfill the requirements of Subsection'IWV of Section XI. The tests and abbreviations used-are as follows: Seat Leakage Test (Lt) The seat leakage tests will meet the requirements of I'V-3420 for Category A valves. On these valves, seat w leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function. 2. Full Stroke Test (St) Valve exercising tests of Category A and B valves will be performed in accordance with INV-3410. The test will include full st.oke testing to verify operability in the direction required to fulfill the required safety function. 3. Check Valve Exercise Test (Ot) The check ialve disc will be exercised to the position required to fulfill its safety function in accordance with INV-3520, 4. Safetv Valve Setpoint Check (Rt) Safety valve setpoints will be verified i, accordance with IRV-3510 of ASME Section XI. 5. Fail Safe test (F11 Valves.with fail safe actuators will be tested to verify the-valve operator moves the valve stem to the required fail safe position upon loss of actuating power in accordance with IWV-3415. This will be accomplished during the normal stroking of-the valve. Upon stroking a valve out of its fail position, the solenoid operator is de-energized causing air to be vented which, in. turn,-allows.the spring to move the: valve to.its fail position. This condition simulates loss of actuating power (Eiectric and/or Air) and hence satisfies the fail test requirements of IWV-3415, 6. Position Indication Check (IT) Valves which are identified to require a Position 'ndication Test (IT) will be; inspected in accordance with IWV-3300 of ASME Section XI. 6 0629m(010989)/?8-I eww e 7 wi2 e-g- -w.m .y -~. s.m'

.4+4e'i

%e .4-e w : y m v--er r wm

Revision 6 7. Eari.sireke Tagt.fft1 If only limited cFeration is practical during plant operation, the valve 4 shall be part-stroke (Xt) exercised during plant operation.nd full-stroke exercised during 1 cold shutdowns, in accordance with IWV-3413 or IWV-3522. N. MM STRO::t TIME for power operated valves requiring a fall stroke test (St), in order to meet the requirements of IRV 3413, the maximum allowable stroke tine is specified in seconds. N/A 2ndicates that tine is not a factor affecting valve operability. O. TEST MOEr Denotes the frequency and plant condation necessary to perfo;n a given test. The fol'* wing abbreviations are used: 1, No rma l,,_Oge r a t i on_LC pl Tests designated CP will be done once every 3 months, except in those modes in which the valve is not recuired to be operabis. 2. Semiannual (S1 Tests designated (D) will te condacted once every 6 months, except in those nodes in which the valve is not required to be operable. '3. Cold Shutdown J 3) Valves that cannot be operated during plant operttion shall be full etroke exercised during cold shutdowns. Valve testing will commence withia 48 hours after shutdown, with conpletion of cold shutdown valve testing not being a prersquisite to plant startup. Valve testings which are not completed during a cold shutdown shall be completed during subsequent cold shutdowns to meet the code specified testing frequency. For planneM shutdowns, where ample time is available, and testing all the valves identified for cold shutdown test frequency in the ISI Program will be accomplished, e'ceptions to the 48 hours may be taken. In case of frequent cold shutdovns, valve testing need not be performed nore of ten than once daring any three-month period. 4. Reactor Refueling (RR1 Tests with this designilion will be conducted durino reactor refueling outages only. 4-7 0629m(010989)/29 l

. _ -. ~ _. ~ ~. -. _ _ _ _. _ - - -. -. i Revision 4 I P. RELIEF REOUEST i Rtlief requests reference a specific request for relief from code requarcaents. All relief requests are included immediately following the presentation tables. i Y I t L I t f ? f I 4-8 [. 0629m(010989)/30 i l 6 1 _... - _.... _ _. _.... _,. _ _. ~. _.,.. _ _ _,.. _. _ _ _. _. _,.. -.. _..,

Revision 4 4.3 tJDTFS ~ 9 4-3 0603r(0109o9)/31 l

Revision 4 u -, E,. av. C;osure of the Main Steam isolation valves, IMS201A-D ant 2MS201A-0. during unit operat ten would result in reactor trip and safety in;ection actaatien. To tvoid this transtent, these valves will be partially stro4ed every three -onths. Tull strose test;ng will be done during Mode 4, 5 o; 6 as plant conditione a;1ow per IWV-3412. NOT._E 2 The testing of any e.tergency boration flowpath valves during unit operation it not pra:tical. Str:4e test'.ng ICV 8104/2CV31:4 (Born: AAd Injection Isolation Valves). One:k valves ICVC442/2CVE442, 1CVA546/2CVB546 (RWST to CV Pu,Tp Suetion Valsea), ICVBB21A/20VBB04A (LH to CV Pump Su: tion Iso Valves), or ICV 112D.E/ ICV 112D C (RWST to j CV Pump Su: tion :so Valves) :ould caure boration of the R23 resulting in a cooldown transient. Aligning the system in tnis :onfiguration, even for a shott duration, is therefore unae:eptable. These valves will be stroke tested during cold shutdown in a:Cordan:e with IWV-3412. NCTE 3 These valvet are the Ma:n reedwater isolation valves, irW209A-D. 20WD09A-0 and cannot te fully stroked during operation as feedwater would be terminated causse.g a reactor trip. They will, however, be partis 11y stroke tested during operation as well as full stroke tested during cold shutdown per the requirenents of IWV-3412. NOTE 4 Closure of these letdown and makeup valves, ICV 1128-C/2CV112B-C. 1CVB105/2CV2125. ICVE126/2CV3126, 1CVEiS2/2CV2152 and ICVE162/ICVB160 during normal unit operation wouli :ause a loss of chargin: flow wht:n would ressit in a reactor coolant inventory transtent, and poss bly, a satsequent reactor trap. These valves will be full stroke exercised during cold shutdown as required by IWV-3412. N,_C_T E5._ The 1RES7DIA,B, 1RH8702A,B, 2RH8731A,B, 2EMB702A B valves are the isolation boundary between the Residual Heat Removal Purps and the Reactor Coolant Systen. Opening one of these valves during unit operation will leave only one valve isolating RHR from the high RCS pressure. This would place the plant in an undesirable condition. Therefore, the valves wi,1 be full stroke tested during cold shutdown, per IWV-3522. 4-10 DE29m(010959)/22

Revision 4 y2K 6 The f ollowing valves have been ident;f aed er ntersyster L3;A valves. They form a pressure roundary between tne R;S and other essential congonents in order to protect these enponents f rom damage, inese val es will te leak tested in a::ordance witn the Braidwood Technical 5;ecift:ations. I ' RHB701 A-B

RH S 70; A-E 1 REB 701A,3 1RHB7: 2A,B 1RHB7:5A,B 15!?.915
REB 70$A-B 251&B15 i

151BB1BA-D 15139:5A-D 251BBIEA-D SIB 905A-D j 1519B19A-D ISTB94BA-D SIBB19A-D

S1894BA-D IS18B41A,3 151!949A D 251BE41A.B
S18949A-D ISIB9: 0A-D 15:B956A-D 2 SIB 900A-D SIB 956A-D N0it 7 The reactor pressure wssel vent valves, IRC014A-D and ;R;014A-D, cannot be stroked during unit operation as they provide a pressure boundary between the Rea: tor Coolant system and contairrent atmospnere, failure of one of these valves in the open positior would result in leaving only one valve as the high pressure boundary. These valves will be stroked when the RCS pressure is at a minimum during Cold Shutdown, per !W'V-3412.

N_;I_ E_B The Resadual Heat Renoval Punp disenarce check valves, 1RHB73;A,B, and ;RHB730A.B cannot te full stroke exercised during unit operat;on due to the nigh RCS pressare. These :he:k valves will be partial stroke tested, however, on a quarterly basts and full stroke exercised during cold shutdown This is :n accordance with WV-35:2. N_ O.T._ E_9 Due to RCS preszare, the : heck valves listed below :annct t+ full 4 stroke eFer:15ed d6 ring unit operation: ISIBB1BA-D, ;5IBB'!A-D RHR Cold Leo Injection ISIB9tBA-B, ; SIB >oBA-D RWST to RHR Punp Su: tion These valves will be full stroke exer:2 sed curing cold shutdown, in accordance with IWV-35;;. 4-11 0629c(310939)/33

_ _ _ _ = _ _ _ _ -. _ _ _ _ Reviston 4 MOTE 10 The IrWO39A-D and LFWO39A-D valves cannot be stroke tested during unit operation as.losure of these valves would result an termination of the waterhaiter prevention feedwater flew. This woald result in undesirable affects on the Steam Generators. These valves will be full stroke tested during cold shutdown per IWV-3412. MEIE.11 The Primary Containment-Furge Supply and Exhaust Valves, IVQ001A,B, IVQ002A,B, 2VQ001A,B, 2VQOO:A,B, and cannot ce stroke timed during unit operation. These 43 inen valves are the only isolation points between the containment atcosphere and the environment. Streking these valves at any time other than node 5 or 6 would be a v4olation of the Braidwood Technical Specifications. Thtre valves will te full stroke tested during cold shutdown in accordance with !WV-3412. These valves will be leak tested semi-annually in accordance with Braidwood Technical Specifications. The Primary Containment Mini-Purge and Exhuast Valves: iVQOO4A,B. IVQ005A-C, 2VQOO4A-B, 2VQ005A-C, and the Post LO2A Purgo Oxhaust Valve IVQOO3, 2Vg003 will be leak tested every 3 months in accordance with P-aidwood Station Technical Specifications. UEIE_15 The Auxiliary reedwater check valves, 1Ar001A B, 1Ar003A-8, lAT014A-H, 1AF029A-B, 2Ar001A-B, 2Ar003A,3, 2AF014A-H, 2Ar029A,B, cannot be full stroke tested during unit operation, as this would induce potentially damaging thermal stresses in the upper feedwater nozzle piping. The IAT001A-B, 1Ar003A-B and 2Ar001A-B, 2AF003A-B valves will be partially stroka tested during operation, and all valves full stroke tested during cold shutdown. This will be performed per Teen Spec. 4.7.1.2.2 and as in accordance w;th l IWV-3522. UCTC_LI The High Head Injection Isolation Valves, ISIB801A,B and 29I8801A,B cannot be stroke tested during unit operation, These valves asolate the CV system from the ROS. Opening them during operation would enable charging flow to pass directly into the RCS, bypassing the regenerative heat. exchanger. The temperature difference of the charging flow and the RCS could result in damaging thernal stresses to the cold leg nozzles as well as causing a reactivity change which would, in turn, cause a plant tr.ensient. These valves will be full stroke tested during cold shutdown in accordance with IWV-3412. 4-12 l l 0629m(010989)/34 l c I l l

EeVitton 4 M !E _14_ The safety in:ection system SVA3 (Spurious Valve A:tuation Group) valves, ISISB02A,3. 15I8306. ISIE?O9A.B, 1513B13, 15:i"35, 15I8543, ISIE802A,B, 2S13!06, 25:!!09A.B. 25!9S13. 25:2325. and ;5:354:.

annot be stroke tested durtn; unit creratien.

!nere valves are required by the Tecnnical Spectf; cations to be deenergized ;n their proper positions during unit operation. Stroking tnen would te a violation of the Te:hnical Specift ations as well as defeattng tne de-energized SVA3 valve principle. These valves wt?. te strode tested during :old shutdown wnen they are not requ red to te de-energized. This is in a::ordance with I' V-3410. J M. - m n --+TE 15 m -o - DELETED - N__;T_E _16.. The :losure of the Main reedwate: Regulating Valves. IrW513, 1F4500, 1F4530. IrW540, 2r4510, CTW5;.".. ;F4530 and 2rW540, durtn; unit operation would cause a loss of feedwater to the steam gerierators, resulting in a plant transient with a possible reactor trip at a result. These valves will te fail safe tested 'rt) per the Eraadwood Technical Specifi:ataens. These valves are noncode valves and as such, do not require the full scope of Se: tion XI required tasting. They are included in the program for cperability trac <ing

urposes only.

N:!E.17-The closure cf the Main reedwater Regu;ating Bypass Valves. 1TW510A, 1TW520A. IrW53;A, 1TW540A, IrW51CA. OrW520A, Or"*'OA, and CFW540A during unit operation wo213 require the Maan ree,Ater Regalating Valves to correct for ty;assed f;ow and could result ia a plant transient with a possible reactor trip as a result, Inese valves will be fail safe tested (rt) per the Braidwood Ternntral Specifications. There valves are noncode valves and as such, do r.ot require the full scope of section XI required testing. Th+y are included in the program for operett11ty tracking purposes on]y. N_O._T._E I_S. The reedwater Tempering Flow control valves IrWO34A-D and IrW334A-D will be tr'ted per the Draidwood Technical Specifications. These valves are ncncode and as auch do not require the full scope of ASME Section XI required testing. They are included in the program for operabiltty tra: king purposes or.ly. NOTE 19 - DELETED - (Incorporated into NOTE 34) 4-13 06;9t(010959)/35 i

m.. .-s. ._m...__ ._-_._-.= _.-_ - _ _._ _ _._.... - - - __ - - _ _ _ _ _ _ _ _.. Rovision 4 l 1 tjoTE to j The remote position indicator for these valver -car.not be otserved directly due to_the encapsulated design of the solenotd valve body. 1 During the indication test, indirect evidence of the ne:essary valve disk move. ment shall b. used in ac:ordance with IW-3412(b). The valves affe:- ted are listed below: i ICV!114 1PS230A,B IFS 228A,B 1CV8116 1RC014A-D 2FS229A.B i iPS22BA.B 2*VB114 2FS230A,B iPS229A,3 2CV9116 2RC014A-D NOTE 21 Per ITRC mandated augeented testing requirements, the 1FS231A,B and i 2FS231A,B neck valves shall_be stroke tested open (Ot), to ensure post ae:tdent operability of the Hydrogen Monitoring System, i i t P r i 4-14 0629m(0109391/36 i k 0 m me r -vwe-9--3-r-w y-s+-g p r,--T*- r-sy--w- ,-vy-*7 ~vrrew--*-~ +y-,--'r--w--w-y v iro-- wv- =v -t+v=w%=re+v wy ws r--er w

ww r'-w=weer um

=vww-- w -ew----m--n r=--

Revision 4 1 i 4.4 i RE'.,IEP RI2UESTS j l i 1 4 4 1 J t 1

)

J 1 I t t' t d e f t n t 4 ) T l 4 L i L h 4-15 I 0609m(310909)/37 e l. P =>-enwe-a--=w*.eesv w-weene --e. wweavw.,,.=wers,w,=we,,m,+,...w..wwcm.e-w.w.usav.. ww,,. .,.,-cw.ww.,v2,. w.,,%,gw:,.y .y.,im*,-ac,e.-7%+.,-,wn.e w yre,-m ,ww. ,a w res--wr

Revision 4 e VR-1 1. Valve Number; All primary containment isolation valves an this program are listed as Category A: VALVE a VALVE a VALVE s 1) ICC685 45) IFS 9354A 89) 1VQ002A 2) ICC9413A 46) 1PS9354B 90) IVQOO2B 3) ICC9414 47) 1FS9355A 91) 1VQ003 4) ICC9416 4B) 1FS9355B 92) 1VQ004A 5) ICC9438 49) 1PS9356A 93) 1VQ004B 6) ICC9486 50) IFS 9356B 94) 1VQ005A l 7) 1CC9518 51) IPS9357A 95) ivQ00$B 8) ICC9534 52) 1FS9357B 96) 1VQ005C 9) 1CS007A 53) 1RE9157 97) IVQOl6 -10) IC5007B 54) 1Rt9159A 98) 1VQ017 11) ICS00BA 55) 1RE9159B 99) 1VQO18 12) IC5008B 5() 1RE9160A 100) 1VQ019 13) ICVE100 57) 1RE9160B 101) 10M190 14) 1CVS112 58) 1RE9170 102) IWM191 15) ICV 8113 59) 1RE1003 103) IWOOO6A 16) 1CVB160 60) 1RF026 104) IWOOO6B 17) 1CV8152 61) 1RF027 105) 1WOOO7A 18) 1FC009 62) 1RY8025 106) 1 won 07B 19) 1FC010 63) 1RY8026 107) IWOO20A 20) 1FC011 64) 1RY8028 108) 1 WOO 20B 21) 1FC012 65) 1RYB033 109) 1 WOO 56A 22) IIA 065 66) 1RY8046 110) 1W0056B 23) IIA 066 67) 1RY8047 111) 1PR002E 24) IIA 091 68) ISA032 112) IFR002G 25) 10G257A 69) ISA033 113) 1PR033A 26) 10G079 70) ISD002A 114) 1PR033B 27) 10G080 71) ISD0028 115) 1PR002F 28) 10G081 72) ISD002C 116) 1FR002H 29) 10G082 73) ISD002D 117) 1PR0330 30) 10G083 74) iSD002E 118) 1PR0330 31) 10G084 75) ISD002F 32) 10G085 76) 1SD002G 33). 1FR001A 77) ISD002H 34) 1PR001B 78) ISD005A 35) 1FR032 79) 150005B 36) IFR066 80). ISD005C 37) IPS228A 81) ISD005D 38) 1FS228B 82) ISIB871 39) 1FS229A 83) 15I8880 40) 1FS229B 84) ISIBB88 -41) -1FS230A 85) 15I8964 42) IPS230B 86) ISI8968 43) 1FS231A 87) 1VQ001A 44) IFS 231B 88) 1VQ001B 4-16 0629m(010989)/3S i l . ~.. . -. _ _. _ _ _.., - -..,. _. ~. _ _.,..,

Revision 4 VR-1 1. Valve !h d er: ( c ont i n.;e 3 ) VALVE = '[ALVE_n VALyt a 119)

CC6!5 163) 2PS9354A 207) 2VQDO A 120)
C09413A 1641 2FS9354B 20E) 2VQ00;B 121)
CC9414 165) 2PS9355A 209) 2VQ: 03 122)
CC9416 166) 2PS9355B 210)
VQOO4A 123) 2CC942B 167) 2FS9356A 211) 2VQ004B 124) 2CC94!6 16B) 2PS9356B 212) 2VQ005A 125) 2C09518 169) 2PS9357A 212)
VQC05B 126)
C29134 170)

IFS 9357B 214)

VQ0052 127) 2C5007A 171) 2kE9157 215)
VQOl6 12B)
CSC07B 172) 2RE9159A 216)
VQ017 129)
C500BA 173) 2RE9159B 217)
VQ31B 130)

ICS002B 174) 2RE916;A .19) IVQ019 131)

CV5100 175) 2RE916: B 215)
WM190 132)
CVB112 176) 2RE917' 2 C) 2WM191 133)

ICVBil3 177) 2RE1002 221) 2W3006A 134)

Cv8160 173) 2RF026 222)
WOOOCB 135)

CV8152 179) 2RP027 223)

W0007A 136)
rC009 190)
RYS: ;5 224) 2WOOO7B 137) 2FC010 151) 2RYB:26 225)
WO320A 139)

IFC011 1E;) 2RYEC;E 226) 2WOS2CB 139) 2rC012 153) 2RYS033 227) 2 WOO 56A 140) 2:A065 184) 2RY3046 228) 2 WOOS 6B a 141)

1A056 125) 2RYSO47 229) 2PR002E 142)

IIA 091 186) 2SA032 230) 2PR002G 143)

OG057A 187) 2SA033 231) 2PR033A 144)
OG079 153) 2SD000A 232)
PR033B 145)

ICGOBO 189) 2SD00;B 233)

PR00;F 146)

CG0il 190) 23D002C 234)

PR00;H 147) 20G082 191) 2SDO: 2D 235)

ZFR 330 ~ 148) 20G093 192) 2SD002E 236) 2PR033D 149) 20G024 193) 2SD002F 150)

OGOE5 194) 2SD002G 151)
PR001A 195) 2SD002H 152)
PR001B 196) 2SDOCEA 153) 2PR032 197) 2SD005B 154)

IFR066 19B' 2SD005C 155) 2PS228A 199) 2500C50 156) 2PS228B 200) 2518871 157) 2PS229A 201) 2518880 153)

PS229B 202) 2SI5285 159)
PS23CA 203J 2 SIB 964 160) 2PS230B 204) 2 SIS 968 161) 2PS231A 205) 2VQ001A 162) 2PS231B 206) 2VQ001B 4-17 2624m(0109E9)/39 1

Revision 4 2. N.v--t e r o f...:.t. e r._: 226. 3-AldS_COILQale;ppy._ A. 4. A3ME Code. Se:t;on X Eequarerents: Seat I.eakage Measurenent pe r IW-3 420. 5. Easis for E111ef: Pr: nary cntaannent isolation valves will te seat lea < tested in ac:ordance with 10 CTR to. Appendix J. For these alves. Section XI testing require: tents are essentially equivslent to those of Appendix J. 6. Mtvinate T+stjn;; Primar/ :entainment isolation valves will be seat lea < tested in accordar.ce with the Appendix J requiren nta of 10 TR 50. The results of such leak rate sneasurements shall te analyzed and corrected, as necessary in aucrdance witn the guidelines set forth in ASME Ccde Section XI, Subsection IW, Faragraphs IW-3426 and IW-34:7 (A). 7 Justification: No additional infernat n concerning valve leakage would be gained by performan; separate tests to both Sect:en XI and Appendix !. !.terefore, everall plant safety is not affected. A plicable Iqe Fenod;, 3. J This reilef is requested once per two fe. irs dur:ng the first inspection interval. "1 4-13 C629t(010933)/40

Revision 4 VR-2 1. Valve Number: 1:S CA 20502A .seen..B s S..- B .av i. 2. Nunber of Iters : 4 3. ASME Code Category. C 4. ASME Tode. Se: tion XI Recuirerer.ts: Exer::se for operabality (Ct) ef check valves every 3 months, pe r I'n'V 35:1. 5. Basis for Relief: These : hec 4 valves in the spray additive system cannot be stroked without introducing Na:H into the 23 system. 6. Alternate Tesjing! These valves will te disnantled each refueling outage in order to demonstrate operability. In addition to this, tney will be a full flow tested once every five years, p9r Braidwood Technical Specifications. The f ull flow test ray be perf ormed in lieu of dismantling the valves, if des: red. 7. Justification:_ This alternative will adequately maintain the systam in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves os often as is safety poss;ble. 8. Apclicable Tire Fertod: This relief is requested once pe quacter during the first

nspection interval.

4-19 06:4m(0109E9)/41 '1 l

... _ -.... - - ~... _ _., - - - - - - -.. - - _. -. e, Revision 4 VR-3 1. Valve Nambe': ISI!9;2A,3 2 SIB 92;A.3 j 0. Number of :temsj 4 3. ASME Code Categpryl C 4. ASel Code, Section,,];L Requarements: Exercise for operability (Ct) of check volves every 3 months. per IVV-3521. i 5. Basis for Relief: These check valves cannot be full flow tested daring operation as the shutoff-head of the Safety Injection pump is lower tnan the reactor coolant system pressure. Ferformance of this test 4 with the RCS depressurized, but intact, could lead to j inadvertent overpressurization of tne system. The alternate method of protecting agasnst oserpressurization by partaally draining the RCS to provide a surge volume is not con idered a safe practice due to concerns of maintaining edequate water level above the reactor core, i 6. Alternat:vo Tesiing_: t These valves will be full stroke tested during refueling outagec. 7 Justification: This alternative will adequately maintain the system in a state of operational readiners, while not sacrifican; the safety of the plant. by testing the valves as of ten as safely possible. i 3. Applicab'e Time Period: This relief is requested once per quarter during the first inspaction interval. 4-20 0629m.(010983) 5 P -, m _ _ _,,,. _,.... _... _ _ _ _... _... _., ~., _, _,.. _,. _ _...

Revision 4 VR-4 1. Valve Number: ICS00!A, B

CSODBA,B 1CS003A, B 2CS003A B 2.

Nunter of itens: B 3. AS1'.E.Coje_ Caiego ryt AC & C 4. ASME Code, Section XI Regut.rements: Exercise for operability (Ct) of check valves every 3 cenths, per 1WV-3521 and IWV-3412. 5. Basis for Reisef: The full flow testing of these eneck valves during pertods of cold shutdown, using the CS purps, would fill the Reactor Refueling cavity with contaminated water from the Refueling Water Storage Tank. The filling of this cavity, via temporarily installed large bore piping connected at spool piece hookups, would by neccessity require the removal of the reactor "essel head so as to preclude equipment damage from borated water. Currently, full flow recirculation flow paths do not exist f rom the discharge at the CS pwnpa through the afore noted chock valves to the Refueling Wat(r Storage Tank. The addition of such flow paths would require extensive p. ant modifications to existing plant designs, to ard include penetrating unit contaircent integrity. These valves cannot be full flow tested during unit operation as water from the CS pumps would be discharged througn the CO ring headers causing unde.irable ef f ects on system camp nents inside contair. ment. Fartial stroking of the ICS008A,B and 2CS008A,B valves using air does not provide adequate 2nsurance of valve operability and may be detrimental for the follos.ing reatens: a. There is no correlation between air flow and angle of disc movement. b. Venting and draining the appropriate piping quarterly may cause deposition of boric acid residue which could in turn promote binding of the check valve internals. 6. Alternate Testing 1 The ICS00BA,B and 2CS008A,B valves will be either full flow tested, or dismantled to dencastrate operability each refueling outage. 4-21 0629m(012ES9)/43

~ ~ - - _. ~ - - - - - - . ~. Revision 6 VR-4 The 103003A,3 and C5003A,B va'ver will te partial stroke tested during the quarterly purtp surveillance and full flow tested, or disnantled, to demonstrate operability, each refueling outage. 7. Justification: This alternative will adequately maantain the system in a state of operational readiness, while not sacrificine the safety of the plant, by testing the valves as often as safely possible. 3. Alpjicable Time Fer:od: This relief is requested once per quarter during the first inspectson interval. l ll 1 P t l l \\ i l p 4-02 0629m(010939)/44 i [ l L. 2-,_...__... ..a__...,_.,_.,_...-....

Rev ston 4 -1 VK-! 1. Valve !!arber; ISI!95sA-; 15:3941A-? 25139 eda-; S!?)4!A-3 'lunbe r :( Iters t 16 3. ASME Code Cate:orv: A0 4. ASME Code, Section XI Re:uir* rents: 1 Exercise for operability (Ct) of ne:k valves every 3 ronths, l pe r Itiv-3t:1 snd l'iv-34;;. 1 5.

nsis fer Relief; The accumulator che:% valves cinnot be tested during unit I

operatten due to the pressure differential between the accurulators (tS3 psig) and the reattor coolant system (;235 psig). Full stroke exer:tsing of these valves ::uld occur only with a rapid deprersurt:stion of the reacter cociant system. 6. Alternate T*stina: Braidwood Station Te:hnical 5;e:tfications require leak testing to be perfor ed on tnese valves if the unit is in rold shutdown and if such leak rate testan; has cet been perf orced within nine months. Therefore. Braidwood Station will full i stroke exor:tse (Ot) these ene:< valves on the sore senedule. This will be accoeplished by provadan; a surge volu.me in the pressart er and "burpin7" the a::unulator dischargo valves. As a minimum, the a::a.mulators will be dtzenarged into the reactor vessel during refueline outaces to perfore a full stroke exer: se (Ot) of these valve:. Fost;;ve veriftention of valve operability will be ty noting s enange in ac:urulator level. 7 Joe.t i f i ca t ion : Stroke exer;tsing tne check valves en the sa~e s:hedule as their required Technical Spe:tfication leak rate testing will adequately maintain the system in a state of operatiensi readiness without causing ur.necessary personnel radiation

exposure, B.

Apriicable Time Period: This reliuf is requested once per quarter daring tne first inspeetton interval. 4, $$ hT()1 9$3)/4b I, m - E.,,. _.. ._,_+.._,_.--,~,,,,-,,..r,.....,- Y,,,.-._,.m,_ ,m..-,.-.-,_~,,,,ry.. ..,_m. ,r..,--,

wee,

.r,U

Revision 4 VR-6 1. ' Valve Numberi 1 SIB 926 2S:5926 2. Qumber of_ Items: 2 3. ASME Code Category 1 C 4. ASME_ Code, Se: tion _XI Requirenents: Exercise for operability (Ct) of :he:k valves every 3 months, per IWV-3521. 5. Basis for Relieff Tull stroke exercising of the Safety In;e: tion pump suction valves cannot be den:onstrated during unit operation as the reactor coolant system pressure prevents the punps from reaching full flow inje: tion conditions, performance of this test with the reactor coolant system depressurtzed, but intact could lead to an inadvertent overpressurization of the system. The alternate method of protecting against overpressurization by partial draining of the reactor coolant systsm-to provide a surge volume is not considered a safe practace due to concerns of maintaining adequate water level above the rea: tor core. 6. Al t e rna t e _ _ Test ino : The 1516926 and 2S19926 valves will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode. Full Stroke exercising for this valve will be done during refueling outagen at a minimum. but no more frequently than on:e per quarter. 7. Justiftsstion; This alternative will adequately maintain toe _ system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible. B. Applicable Tine Periodi This relief is requested once pes quarter during the first inspection interval. 4-24 0629m(010989)/46 l

.. - - - - ~. .. - - -. _. -. - _ _ -.. _ -. -.. ~. -. - -. -. -. _ -.. -. Revision 4 ) i VR-? r i -DELETED-e Incorporated tr,to Valve R,;2el Request VR-12 and t'R-17. i I i t i-t i 5 1 4-25 0629m(010989)/47 l i. 4 4 .I ...4

= I e, Revision 4 1 VR-3 l 1. Valve Nunter: 1 C(85

CC9438 2C09 914 t

1CC9413A 1CC9426 2C09416 i IC09414 2C0685 2C09438 f 1009416 2CC9413A 2CC9486 i i 2. flun be r of __ I t ec s : 12 3. ASME Code Categgry A 4. A_SMT Code, Se;tlen XI Requirements: Exercase for operability (St) of Category A and B valves every 3 months, per IW-3411. 5. Basis for Relieft l Component-cooling water flow to the reactor coolant pumps is required at all titres while the pumps are an opera: son and for an extended period of time while in cold shutdown. Ta11ure of one of these valves in a closed position during an exercise test would result in a loss of cooling flow to the punps and eventual pump damage and/or trip. 6. Alternate Cestin2:, Chese valves will be exercised during cold shutdowti, provided all of the reactor coolant pumps are not in operation. Chis testing period will be each rifueling outage as a minimum, but t no more frequently than once per quarter. Check valves 1CC9466 and 2C09486 will be stroke tested (Ct) closed on the sane frequency as the seat leakage test per IW-3430. This frequency is at least once per two years, to be performed during reactor refueling outages. 7 lustification: Chas Alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible. I Stroke exercising check valves ICC9486 and 2CC9486 on the same ( schedule as their leak rate testing will adequately maintain l: the system in a state of operational readiness without causing unnecessary personnel radiation exposure or possible damage to i l the Reactor Coolant Pumps. { 8. Applicable' Time Period: Chis relief-is requested once per quarter during the first inspection interval 1 I 4-26 0629m(0109B9)/4B t j .~. __5.,

Revision 4 VR-9 1. yaiye fJuntert 1CV3100 2CVB100 1CV3112 2CVS112 2. thnber of _Itensi 4 3. ASME Code Category: A 4. ASMr_ Code. Section XI Requirerents: Exercise for operability (St) of Category A L B valves every 3 months per IRV 2411. 5. Basis __for _ Relief: TheFe Valves Cannot be tested during unit operation a3 seal water flow to the reactor coolant punps is required at all times while the paaps are in operation. Teilure of one of these valves in the closed position during an exercise test would result in seal water flow being diverted to the PRT by lifting a relief valve upstrean-of the isolation valves. 6. Alternate Testing: These valves will be exercise tested during :old shutdown, providing all reactor coolant gunps are not in operation. This testing period will te each refueling outage as a minimum, but no more frequently than once per quarter. 7. Justification This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant. by testing the valves as often as safely

possible, B.

Applicable Tine Periodi This relief is requested once per quarter during the first inspection interval. 4-27 0629m(010989)/49 l

Revision 4 VR-10 1. Valve Number: 1!A066 22A066 IIA 065 2IA065 2. Number of IteJ E 4 3. ASME Code Category: A 4. ASME_ Code,.Section XI Requiremento: Exercise for operability (St and Tt) of category A and B valves every 3 months pe r IWV-3411. 5. Basis for Relief:. Stroke testing of these valves during plant operation or cold shutdown would, by design. isolate the air operated instruments and valves inside the containment building. 6. Alternate Testing: These valvas will be exercised during refueling outages. This testing period will be each refueling outage as a einimum, but no more frequently than once per quarter. 7. Justification: The full stroke exercising of the instrument air containment isolation valves during unit power operations or cold shutdowns, introduces the possibility of causing major opera:Ang perturbations and/or personnel safety concerns should these valves fail to re-open during testing activities. The failure of these valves in the closed position, as a result of testing activities during plant operation or cold snutdown, would subsequently isolate the air operated instruments and valves incide the containment building thus resulting in one or more of thee following scenarios: A) Loss of Pressurizer pressure Control The pressurizer spray valves 1/2 RY455B & C and the pressurizer auxiliary spray valve 1/2 CVS145 would fail closed and not be available for pressurizer pressure control. 4-28 0629m(0109E9)/50 h --,2i.. ,,-, -..,.i....;-~._----...-.-,...--,,,--.,.-- -- ., -. - -... - -,..,, ~.. -,, - -.. ~, -. - -,. - -

a, Revision 4 VR-10 B) Loss of Chemt:a1 Volune Control System Let Down Tiow (both normal and excess) and Charging Tiow The loss of instrument air would cause a disruptien in the unit letdown flow paths resulting in pressurizer level increases. Such valves as the letdown orifice containment outlet header isolation valve 1/2 CVS160, the letdown line isolation valves 1/2 CV459 and 1/2 CV460, the letdown orifice outlet isolation valves 1/2 CVB149 A, B & C. the excess letdown heat exchanger inlet isolation valves 1/2 CV8153A & B, and the regen heat exchanger letdown inlet isolation valves 1/2 CVB389 A &. would go to their fail closed positions. Additionally, the ability to nornally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal boration/ dilution) would also be lost as the regenerative hest exenanger inlet isolation valves 1/2 CV8324 A & B would fail to their respective closed positions. C) Loss of Component Cooling to Containment penetrations - The loss of instrument air supply would cause the penetration cooling supply flow control valve 1/2 CC053 to go to its fail closed posttion. The loss of penetration cooling would result in elevated temperature being imposed on the penetrations being supported by the component cooling system. D) Loss of Personnel Breathing Air - The loss of instrument air supply to the service air downstream isolation 31ve 1/2 SA033 would cause this valve to go to is fail closed position. This loss of service air in the containment building would elininate the normal source of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated radiological environnent. 8. Applicable Time Period: This relief is requested once per quarter during the first inspection interval. i l 4-29 0629m(010989)/51 l l

. ~.. _ _ _.. _ _ _.. _ _... _ _ _... _ _. --._... _ _ _ __ _ _ _ _. _.___ _. _...__ _.. Revision 4 . i-I VR-11 e ( k ). - DCLCTED - e k 3 e w 4-30 0629m(010983)/52 l

_.. - -.-. - -. -.--- -.- _ _.- _.__ - _.~- t Revision 4A ? VR-12 i 1. Valve number: Valves that notaally stroke in 2 seconds or less: Valve a Valve a Valve a Valve o IMS018A-D 1RE9160A,B 2M5018A-D 2RE9160A,8 1PS22BA,B iPS228A,3 h, IPS229A,B 2PS229A.B IPS230A,B 1RYB033 2PS230A,B 2R*8033 1RC014A-D 2 RC014A-D 1RE9157 2RE9157 1RE9159A B-2RE9159A,3 2. fjumber of Items: 40 3. ASME Code Category: A&B 4. ASME Code, Section XI Requirements: 1 Verification, by trending of power operated velve times, that an increase in stroke time of 50% or more, from the previous test, does not occur. per IWV-3417(a). 5._ Basis for Reitef: Minor timing inaccuracies, with small stroke times can lead to substantial increases (percent wise) in stroke tines..For example, a valve with a stroke time of I second in an initial test, andfl.6 seconds in'the subsequent test, has experienced an apparent 60% increase in stroke time. L If the accuracy requirements of IWV-3413(b) are utilised, it could be argued that stroke times between 1 and 2 seconds could constitute as much as a 100% increase in stroke time when in fact, only a 0,2 second increase occurred. For instance, if the initial stroke time was 1.4 seconds, _(which neasured to the L nearest second is 1.0 seconds) and the next stroke time is 1.6 L seconds,.(which measured to the nearest second is 2.0 seconds) l the percent increase is 100>.. 6. Alternate Testsng: Fast-acting valves can be defined as those valves that normally stroke in seconds or less. No trending of stroke times will ,gj be required and upon exceeding 2 seconds, corrective action shall be taken immediately in accordance with IWV-3417(b). l t 4-31 l 1 1 0629m(030189)/53 1 e -- w..-. .___,.-,.._m...

Revasion 4A VR-10 7 Justification Tor short stro<e tite $. the trending requirerents are too stringent for the a::ura:1es spe::fted in the : ode. The alternative specified will adequatel/ maintain the systen in a state of operationa'. readinest,, wn11e not miosang undue hardsh p or sacrift:ing the safety of the plant. 8- ?II.119 @lt_Itce_.Pe_rt @ This re'lef is requested once per quarter, during the first inspe:tson interval. C. k C 4-32 0629a(;30159)/54 i'

Revision 4 t/R-13 1. 'la l'e e Er: e r s : 1DG5122A B 2DG51?;A.B 1DG5133A,3 2DG51?3A,B IDG513 4 A,3

D351!4A,B IDG5185A,3

D351!5A,B Hunb r cf.:lexa: 16 3

3. ASME Cojp_ Category: B 5, 0 4. ASME Code Section C Re n troten*s: T' 4e valves are not withan the scope of ASME Code, Section X1, Sulzection IRV requarenents. However, the requirements for stroke tin-ang and trending of the valves ass:ctated witn the Diesel Aar Start System are teing mandated by the 130 as an aa;raented testing requirement pursuant to 132rk50.55 (a) (g). Therefore, valves associated with the Diesel Air Start System shall be exercised to the position required to fulfill their function during plant operation per 1RV-3412 and IWV-3522. Additionally, the stroke testing of power operated valves shall be measured to the nearest second and such stroke times trended to docanent continued valve operational readiness per IWV 3413 (b) and I'4V-3417. 5. Easis_fer Et tef: i The monthly Diesel Generator testing ; ' gram, outlined in Braidwood Station's Tecnnical (necificht;ons and implenented by station operating procedures, exceeds the intent of the quarterly valve testing program which would te required by ASME Code, Section XI. Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start Systen is impractical due to the fast actaation of these valves. 6. Alternate Certing: G The performance of Braidsood Station's Diesel Generator operability monthly surveillance will verify the operational readiness of the valves associated with the Diesel Air Start System. This surveillance testing will require the recording of the air pressures contained in both trains A & B of the Diesel Generator Air Start Receiver Tanks both before and immediately af ter diesel generator start. By the comparison of these values between starts, the satisfactory operation of the power opetetad and self-actuated check valves associated with the Diesel Air Start System can te adequately demonstrated. 4-33 0629m(OlC939)/55 )

. _. ~. - _ .. _ _ _ _. - _ ~ _.. ~ - _ _ _ Eevisten 4 VR-13 7. J__u s.t..i _f : c a t i on Proper valve ope. tion will be demonstrated on a monthly basic ty the vertft:at;on of liesel generator air start :apabill:. j Suen verification will :ompare the air pressures contained in tne receiver tanks toth 'efore and alter tne d2esel generator start, thus verifying the operabiltty of tne air start centrol valves. !ne proposed testan; rathodology at tne 2n:reartd frequen:y satisfies the intent of the Se: tion.C requ.recents withcut posing undue hardships or d2fficulties. 3. 1pplicable Time Period: This relief is reivested once ;e quarter dur:ng the first ins;ection interval. 4 4-34 C629m(01;959)/56 I

_._._7.._..- _. _... -. _.. ~. -. - - -... _.... __., _ _ _ _. _ - - _ _ _. ~ ~. _ _. _. _.. ,evision 4 .s 1/Mn .944. C 4 -ft i - DELETED - 4-35 C629m(010389)/57 J l, 4 ...a,--~ ,+ w,, --.e ,,-s y e .-n-a +

lC Kevision 4-VR I 1. Valve Numbert 1CVS4BlA,B 2CV8481A,B ICVSS46 2CV8546 ISISS15-2518815- _f 11SISB19A-D 2518819A-D ISI8841A,B-2SI8841A,B ISIB900A-D 2 SIB 900A-D ISIB905A-D 2 SIB 905A-D IS!S949A-D 2 SIB 949A-D 2. Number of _ Valve, 44 i 3. ASME Code Categt AF 2 4. AiME Code, Sectit.i XI-Requirements: Check valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3412 and ZWV-3522, 5. B_ asis for Relief: The full itroke exercicing of checx valves not stroked quarterly is required-to be performed during cold _ shutdowns. dcuever, the stroking of check valves ISI8815, 1SI8900A-D, 1 SIBS 41A-5, 2 SIB 815; 2S18900A-D and 2SI2841A,3 associated with Emergency Core Coeling System, during cold shutdowns will induce thermal stresses on their tespecti re reactor vessel noccles as tne Reactor Coolant Sys tem (maintained approximately 180 F) is injected with_ water from *.he Refueling Water 7torage Tank (maintained approximately 65 F). This also applies to the stroking of check-valves 1/2 CV8545 and 1/2 CV8481A,B because the fu.1 stroke of these check valves causes stroking of the 1/2 SI8815 and 1/2 SIS 900A-D located in the full flow path. Additionally, Braidwood Station Technical Specifications require all Safety -!n]ection pumps ant all._ but one Charging punp to b) inoperable during Modes 4, 5 and 6, except when the reactor vessel head,ts removed. This requirement minimices the possibility of low temperature overpressucitation of the Reacror ' Coolant System. Therefore; check valves'lSISB19A-D, ISI8905A-D, ilSI8949A-D, 2SI8819A-D, 2 SIS 905A-D, and 2SI8949A-D, cannot be full _ stroke exercised during routine Mode 5 cold shutdowns as rcquired by_IWV-3412 and IWV-3522. In add'. tion'to the stroke test exercise used to verify operational readiness of these check valves, the act of such stroking cause the necessity for Technical Specification required leak rate testing of these valves prior to unit criticality. This_ testing,;in conjunction with the stroke exercising of these check valves; adds approximately one week to the daration of any outage and additional radiation exposure to . orkers who must connect flowmeters and differential pressure w gauges directly to pipes containing radioactive fluids. 4-36 06 9m(012689)/58 e: .. ~

Revision 4 VR-15 6. Alternate Testing; Braidwood Stations's Technical Spec.fications require leak rate j testing to be performed on nese valves if the unit is in cold shutdown and if such leak rate testing has not been perforned within nine nonths. Inerefore, Dra:dwood Station vill stroke exercise eneck valves ISIBE15, ISIS 900A-D. ISISS41A-B, 2SISB15 2 SIB 9:0A-D, and 2SISB41A,3 on the same schedule. To p revent unnecessarv strokir.g of : heck valves 1/2 SIB 315 and 1/2 S!S90CA-0, che:k valves 1/2 SIS 546 and 1/2 CVS4BlA,3 will be stroke exercised cn the sane schedule as check valves 1/2 5I8215. li: SIB 903A-D and 1/2 SIS 841A.B. Strcke exere rang of eneck valves 1575319A-D, 15!?905A-D. 1SI S 94 9 A-D, 2 SIB El9A-D, 25!3925A-D. and 2S;3949A-D :an onli be saf ely perf ormed in mode 6 with the reactor vessel head removed. Fall stroke exercising of these check valves will be performed as plant tenditions . g pgf allow, but at a minimum f requency of once ea:n refuel 2n; outage. -m c ' 3e 7. Justificatio_n: ti g.r4 Stroke exere: sing the 15I3515, 1 SIS 900A-D, ISIS 841ALB. 25I3315, S. W. *~T,9-2 SIS 900A-D, and 2SISB41A5B, check valves on the sane schedule as s . sc. ? ~ their requared Techn: cal Spe:if::ation leak rate testing, will ' ' Sh,9 adequately maintain the system in a state of operational I i "[,^ readiness w:thout creating additional undue nardsnip. Valves 1/2 SIS 943A-D, 1/2 S 39:5A-D and 1/2 S:SS19A-D can not be stroked during cold shutdown wi'.hout exceeding Technical Specift:ation 1:mittng condttion for operation (LDD 3/4.5.3). Since strok:ng these valves requires starting an 51 pump. Stroke exerctsing neck valves IS!ES'9A-D, 1SIE905A-D. 1 SIS 949A-D. 2SISS19A-D. 2SIi925A-D. and 25:8949A-D. at least once per reactor refuel:n9 wil' :nsure compliance with Bra:dwood Station Technt:al Spectiteations and minimize the posa;hil t. of low tempe rature ove rpresset 1:st ion of the reactor Cociar.: System. 8. Acc11 cable Time Period: This relief is requested once per quarter during the f;rst inspection interval. 4-27 0629 ( 12cs )/59 l

Revision 4 VR-16 1. Valve NurjeIs : 15:5311A, S 25!5S11A. B 2. Murbe r of...Va lves : 4 3. ASME Code Category: 3 4. ASME Code. Section XI Recuiremants: Valves that ca r.no t be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised during cold shutdowns per !WV-3412. 5. Basis for Relief: 1 The full stroke exercising of valves not stroked quarterly is 4 required to be performed during cold shutdowns. However, the stroking of the Containment Sump Outlet Isolation Valves, 1 SIS 811A.E requires the nuction of the Residual Heat Removal Pumps to be drained, tnus rendering one train of the system inoperacle. For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Removal declared inoperable. Braidwood Station's Technical Specifications require two steam ger.erators witn a secondary side narrow range water level greater than 41% (Unit 1) and greater than 18% (Unit 2). However, if the cold shutdown was necessitated by a pLoblem requiring draining of the secondary side of the Steam Generators (i.e. tube leaks), Braidwood Station's Technical Specification 3.4.1.4.1 would preclude the testing of the contain ent s amp ) outlet isolation valves until such tice as the affected steam generators had been ref211ed. For Cold Shutdown operations with the Reactor Coolant Loops not filled (i.e. drained down to suport Reactor Vessel Incore Seal Table, Loop Stop Valve, Reactor Coolant Punp and Seal Maintenance or primary leaka;e), Braidwood Station's Itchnical Specification 3.4.1.4.2 would preclude the testing of the Containment Sung Outlet Isolation Valves as it mandates that "two residual heat removal (RHR) Loops shall be operable and at least one RHR Loop shall be in operation. 6. Alternate Testing: Braidwood Station will full strok exercise the Containment Surp Outlet Isolation Valves, 1/2 SIB 811A, B during refueling outages vice cold shutdown. 4-33 OE29m(010939)/60 9

m._. s.. Revision 4-l VR-15 7. 7ustification: The full stroke testing of the 1/2 SIBSilA,B v6lves; 2n conjunction with system draining, filling and venting of each i train, accounts for an additional six days (3 days per train) of scheduling requirenents and increased radiation dose to operators and radiological control personnel. Process g of thousands of gallons of contaminated water and subsequent required liquid effluent discharges would also result from the draining, refilling and venting of the RHR system. This tine duration required to perform the surveillance testing of tha Contair. ment Samp Outlet 1 solation Valves during Cold Shutdown activities, could, as a result, cause a violaiton of the action I raguirements for Braidwood Station's Technical Spec:f: cations 3.4.1.4.1 and 3.4.1.4.2. -The violations would occur since these action statements require (as noted in their respective foot note sections) the return of the inoperable residual heat removal-loop to service within 2 hours, if such loop was removed for surveillance testing provided the other RHR Loop is operable and in operation, -In addition, NRC Generic Letter 38-17, Loss of Decay Heat I Removal, highlights the consequences of a loss of RH during l -reduced Reactor Coolant System invsntory (below three feet below i the reactor vessel ~ flange). If the operating RH pump is lost i due to air entrainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat removal. Under worst conditions, bniling in the core'would occur in approx:aately 10 einutes, the core would be uncovered in approximately 30 minutes, and fuel damage would occur in approximately 1 hour. Given the' apparent disparity between the Technical Spe:2fication time requirments for an inoperable RHR Loop return to Lervice (2 i hours) and-the time required to perform surveillance stroke testing of the Containment Sump Cutlet !solatica valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity will adequately maintain the -system in-a state of operational readiness, wh'ile not imposing undue hardships or sacrificing the safety of the plant. S. Applicable Time Period: This relief is requested once per quarter, during the first inspection interval. i 4-39 0629x(012689)/61 i

- - ~ _.. ~. ~ _ _ - -. - Revision 4 l VR-17 1. Valve Numbers: - 15X1 CIA 2SX101A 2. Number of Valves: 2 L 3. -ASME Code Category: B 4. ASME Code, Soction XI Requirements: Stroke time and trend the stroke time for power operated valves per. IWV-3413 nd !WV-3417, 5. Basis for Relief: ISX101A and 2$X1 CIA are the essential service water outlet isolation valves'for the motor driven auxiliary feedwater pump lube oil coolers. These valves are completely encapsulated per design and do not have local or remote position :ndicators which could be used to time the valve stroke, 6. Alternate Testinc: ISX101A and 2SX101A will be verified to open dur:ng each quarterly surveillance of the. motor driven auxiltary.feedwater pumps. -No stroke timing or trendirg.will be performed. 7. Justification: These valves will be stroke exercised to their required safety . position each quarter during the applicable motor driven auxiliary feedwater pump ASME surveillance. These pumps are also tested ~ monthly for proper equipment operation per ' Technical Specification requirements. This testing will adequately maintaan the systems in a state of operational read: ness, while not sacrificing the safety of the plant. S. App.licable Time Period: This relief is requested once. per quarter during the first inspectron interval. l l. I t' t l 4-40 0629m(01C989)/62 1 i f I l

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