ML19325C967
| ML19325C967 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/01/1989 |
| From: | Noonan T DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML19325C208 | List: |
| References | |
| PROC-890901, NUDOCS 8910180229 | |
| Download: ML19325C967 (218) | |
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' INSERVICE TESTING PR00R'd4 FOR PUMPS AND VALVES -)
APPROVAL SHEET Unit 2 - IST Program - a s i ISSUE 1 u c-
.... Unit Nuclear Oper. Supvr. OSC Approval 1 . Rev. Review Rep.ew- tffeetive No. . Pages Issued Initial /Date Date Signature Date -Date.
3 Pages 1'- 158 (NOTE:'Sidebars in the M BV2-0SC-t 38-88
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left margin mark editorial changes, and 12/1/88 +
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sidebars in the right margin mark te,chnical' q b$ changes. . Sidebars include Revision 2 and 3 per NRC . instructions) , 1 g 3A- Pages 3.5.13,14,21,22, (c // M BV-OSC , S [ L k 23,24,27,28,43,45,47,48, 49,51,53,57,59,63,65,69-14-89 6/23/89' ff h 71,81,87,90,91,96,112, , 119,122,130,131 4 Pages I - 166 th lJ t i i
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INSERVICE TESTING FROGRAM y <
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- PUMPS AND. VALVES l! i 1
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} 'Section'I. PumpiTesting Requirements . . .- .- .-
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;, , g Section II: , -Pump Testing Outlines . .. .-- . -., . ..: . . . .. .. . 7:
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Section-III- Pump Testing Relief Requests):.
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- v. ;, , .Section IV Valve Testing? Requirements . . -. . .. . . . : . - - ., . . ' ' . .'56L .
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- Sectdon VL Valve Testing Outlines- , ...-.: .. - . . . . . . . .: . 55
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, 1 Section VI- :: Valve Testing Cold Shutdown Justifications:.. .- . .
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. . Section VII- TValve. Testing Relief Requests..c--. .- . . -. . .- . .s.- .13 4 ~.
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, - SECTION I.- PUMP TESTING REQUIREMENTS. ;
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BVPS-2 IST' PUMP TESTING REQUIREMENTS ,
.The Inservice Test (IST) Program for pumps at Beaver Valley Power Station ,
(BVPS), Unit 2, is based on subsection IWP - Inservice Testing of Pumps of ' the. ASME: Boiler and Pressure Vessel Code, Section XI, 1983 edition through the, summer 1983 addenda (the code) and Generic I,etter No. 89-04,- " Guidance on Developing Acceptable Inservice Testing Programs". The pumps s sluded ! in this program'are all ASME'" class 1, 2 or 3 centrifugal or displacement !
. type pumpr. that are required to perform a specific function in shutting.
down the reactor or in mitigating the conseq' uences of an accident,- and' that M are provided with an emergency power source at BVPS, Unit'2. The requirements-of the code will be followed=at all. times unless specifica relief has been granted by the NRC.: An inservice tests,run? quarterly, . to measure - or observe the test quantities listed in Table IWP-3100-1, below, is required for all pumps in the IST Program by the code. 3 .= TABLE IWP 31001 l INSERVICE TEST QUANTmES Quasety Mesmre Olmerve - i-s 50 sed N taf vanabit speed) / L 3 . ,s ,e ,
/(u DiMerenoas are.ure AP - / ,
Fiow rate Q / vitrauen arnpiitude V l- / " Preser autritant iewed er N / scanne temmerence r. /
- j NOTE:
(1) Weesure before mario surtsp and eenne tat. Table IWP-3100-2 shows the' allowable ranges for test results that will be used to determine if corrective action is required following performance of - BVPS-2 Surveillance Tests. The test data will be compared to the ranges L ' - applied to the reference values for each parameter. If these ranges.cannot be met, reduced range limits that allow the pump to fulfill its function l-t, will be used in lieu of the ranges given in Table IWP-3100-2. TASLE IWP 3100 2 ALLOWASLE RANGES OF TEST QUANTmES Alert Range I Required Action Range [ Note (1)l [ Note (1)l Test Quanoty Acceetatie Range Low values Mign vaives Low va#wes Mign vaivei 8, [ Note (2)] [ Note (2)] [Nate(2)l (Note (2)! 27 (Note (21) 0 93-1.02 AP, 0 9C.0 93 AP, 1.02 - 1.0 3 AP, <090&#, > t 03 AP, G 094-1020, 0 90 0 04Q, t 02. 4 03Q, < 0 90 Q,
*aea 0 s V, s 0 5 miss > t 0 3 3,
- 0. L mit None 1-1.5 miss None > t 5 miss V *aen 0.5 mils < V, s 2 0 cmis 0 2V, miss None 2 V,- 3 V, mils Noat > 3 V, mits V ween 2 0 mits C V, s 5 0 cmis 0.(2
- V,) mils None 12
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- V,1 mies None >(4 . v',a m.ig V waen V, > 5 0 smts 0-14 V, miss N on. 14V,-18V, mits None > t 8 V, mies
- f. [ Note ()ll [ Note f)ll (Note (3)l l Note (3)l [ Note ()ll N0ft$:
(1) See IWP 3230. (2) 7. Fail De wen the hemts soecAed Dy the heer in tne recorg of tests (lWP4000) (3) F, ea.1 De *.tnin trie hmits toecified By the Ow in tne recora of tests (IWP 0000). 3 ISSUE 1 REV 4
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& Corrective action shall;be taken if necessary using the following:' ,
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- 1. If.' deviations f all.within the " Alert Range" of Table IWP-3100-2,
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the frequency of testing shall'be doubled until the'cause -of the deviation is determined. and corrected: and either the; existing ) reference values reverified or'a new set established. ) 2' . - If the~ deviations' fall-within the " Required Action Range"'of Table ;
, IWP-3100-2,.the. pump shall be declared inoperative immediately.and~ l
- an . evaluation of the pump's- condition fwith respect to system
, ' operability and technical specifications shall be made as-follows: '
I a. .If the inoperable pump is specifically identified in the-technical specific'ations, then .the applicable technical specification ~ action statements must be followed. q b.- If .the inoperable pump is in a system. covered by a technical i specification, an assessment of its condition must be made to. ! determine if it makes tha system inoperable. Ifi the-- <
' condition of the pump renders the system inoperable,.then the j applicable : system technical specification action statements.
must be followed.
- c. Corrective action shall be either replacement'or repair per
'IWP-3111, or shall be an analysis to demonstrate that. the-
-condition does not impair pump operability and.the.c the pump '
will still fulfill its function. A new set of reference values shall be established after such analysis,
- d. Nothing in the ASME Beiler and Pressure Vessel Code shall be t construed to supercede the requirements of. any technical T specification.
- 3. When -tests -show deviations -greater than allowed' (see Table .
IWP-3100-2), the instruments involved may be recalibrated and the test rerun. This is an alternative to replacement or repair, not an additional action that can be taken before declaring the pump inoperable.
- 4. The pump shall not be returned to service until the condition has been corrected. The corrective action shall be considered .
completed when a satisfactory inservice test has been conducted in accordarce with IWP-3111. 4 ISSUE 1 REV 4
7$ L' BVPS-2 IST-
* ' Per. IWP-3500 eachL pump shall run at least 5 minutes under conditions as ! stable as the system permits prior to measurement of the specified parameters (when bearing temperature measurements are not required). When bearing temperature measurements are required, each pump shall be run until the Learing . temperatures. ' stabilize prior to: _ making the specified' measurements. A bearing temperature .1 considered stable when~ three successive readings 1 taken at 10 minute intervals do not vary by more than 3%. Bearing temperature measurements are required annually. (normally. in August).
Records: of the results of- inservice tests and corrective actions as. required by subsection IWP-6000 are trended in graphic and tabular form. Pump performance characteristics will be examined:for trends.
- The following.two sections of this document are the " Pump Testing Outlines" and " Pump Relief Requests"' sections. . The." Pump Testing Outlines" sectionL is -a listing of 'all the pumps in the .IST Program, .their testing ,
requiremonts,'and 93 - Jrl specific relief request -reference. numbers. The- 1 pumps are arranged according to system and pump mark number.. The following abbreviations and designations are used on the Pump Testing. Outlines and throughout the IST Program for pumps: -!
- 1. Under-Parameter column 1
- a. (N) -
Speed o b. '(P1) - Inlet Pressure I ( c. (AP) - Differential Pressure
- d. (Q) -
Flowrate i e. (V) - Vibration L L
- f. '(Tb) -
Bearing Temperature
- g. (L) -
Lubricant Level or Pra.ssure i 1 i L l l L 5 I S S t '. 1 REV 6
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,' -2.' LUnder OST S column ,
' (OST) - Operating' Surveil 1 Lance Test.
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- b. .( BVT) - Beaver Valley Test' !
'c. (M) . Monthly Test Frequency
, d. . (Q); - Quarterly Test Frequency
, e,- (A) - Annual Test Frequency
- f. (R)- - Refueling Test Frequency
- g. ~(NA)- - Not' Applicable
- 3. Under Rea'd column ,.
-L a . .(RR)'- Relief Request c
1-- [b. (X) - Meets or exceeds ASME. requirements-
- c. . (E) - Exempt- ,
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- d. (NA)'- Not Applicable The " Pump- Relief Requests" section contains. the detailed technical:
description of particular conditions 'and equipment. installations i prohibiting .the testing; of. some of the characteristics of safety-related-pumps. An alternate test method and the frequencyLof revised testing is also: included to meet the intent of 10CFR50.55a. The relief request (s) for a specific pump is referenced by the number (s) listed on the pump's testing outline: sheet, c-
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PUMP TESTING OUTLINE' Pump Pump . - Coce - Name: 21 A Cha rg ing Pump Number: 2CHS*P21A Class: 2 System: 7. Chemical and Volume C6ntrol-Function: 10 provide normal RCS inventory makeup, Seal Remarks: See RR1 and RR2 Injection and High Head Safety injection Pa rame te r OST Req'd Comments - ( F requency; N NA NA Conste it speed induction motor . Pi 2.7.4 X Pump Suction Pressure Indicator [2CHS*Pl151A], local (Q) AP 2.7.4 X Calculated using Pump Discharge Pressure indicator [2CHS*P11518]- and Pump Suction ' (Q) Pressu re, local Q 2.7.4 i Summation of flow rate f rom flow indications 12CHS*F t 122A, .124A, 12TA,.130A, 160, (Q) 170]. V 2.7.4 X Portable monitoring equipment - F ixed vib ra t ion p robe (Q) lb 2.7.4 RR2 Control Room computer address points for thermocouples provided for each (A) pump end and thrust bea ring. - Inboa rd ' Pump Bea ring ( TO110A), Outboa rd Pump Bearing (TO111 A), Pump Thrust Bea ring (10102A) L 2.7.4 X Lubricant pressure gauge [2CHS-Pl421 A] (Q) Lubricant level gauge on Lube Oil Reservoi r [2CHS-l.1420A] O. . 8 ISSUE 1 REV 4 1
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- PUMP TESilftG OUTLINE Pump Pump . Code Name: 21B Cha rg ing Pump Numbe r: 2CHS*P218 Classi 2 . System: 7 Chemical and Vcluse Contrul function: To provide normal RCS inventory makeup, Seal Remarks: See RRt and RR2 Injection and High Head Safety injection Pa ramete r OST Req'd Comments-(Frequency)
NA NA Constant speed induction motor Pi 2.7.5 X Pump Suction Pressure indicator l2CHS*Pl152A), local- ~ (Q) , AP 2.7.5 K Calculated using Pump Discharge Pressure Indicator { 2CHS*P11$28) and Pump Suction (Q) Pressure, local Q 2.7.5 X Summation of flow rate f rom flow indications (2CHS*F t 122A, 124A, 127A, 130A, 160, (Q) 170l
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v 2.7.5 X Portable monitoring equipment - Fixed vibration probe (Q) Ib 2. T.S RR2 Control Room co.aputer address points for thermocouples provided for each (A) pump end and thrust bearing. nboard Pump Bearing (TO120A), Outboard Pump hearing (TO121 A), Pump Thrust Bea ring (TO104A) ~
~ L 2.7.5 X Lubricant pressure gauge [2CHS-Pl421B]
(Q) Lubricant level gauge on Lube Oil Reservoir [2CHS-LI4208] 9 3SSUE 1
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.L Pump Pump Code Name: 21C Charging Pump Mumber: . 2CHS*P21C Class: 2 System: 7 Chemical and Volume Control Function: To provide normal RCS inventory makeup,NSeal Rema rks: See RR1 and RR2 Injection and High Head Safety in.lection -
Pa ra mete r OSI rg'd Comments ( F requency) N NA NA Constant speed induction motor Pi 2.7.6 X Pump Suction Pressur7 Indicator [2CHS*Pl153Al, . local (Q) ... AP 2.7.6 X - Calculated using Pump Discharge Pressure indicator [2CHS*P11538) and Pump Suction (Q) P re s su re, local-Q 2.7.6 x Summation or flow rate from f low indications [2CHS*F t 122A, 124A,'12TA, 130A3 .160, -- (Q) 170] V 2.7.6 X Ptertable monitoring equipment - Fixed vibration probe (Q)
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Ib 2.7.6 RR2 Control Room computer address points for- thermocouples provided for each (A) pump end and thrust bearing, inboard Pump Bearing (10130A),. Outboar d .
- Pump Bea ring _ (T0131 A), Pump Thrust Bearing Oil (10106A)
L 2.7.6 X - Lubricant pressure gauge [2CHS-Pit:21C) (Q) , Lubricant Icvel gauge on Lube Olt Reservoir [2CHS-LI420C] i i l l l l 10 .!lSSUE 1-RLY 4
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1. BVPS-2 IST-PUMP TESTING OUTLINE Pump 22A Boric Acid Transfer Pump , Code Name: Pump . Numbe r: 2CHS*P22A ' - Class: 3 . System: 7 Chemical >and Volume. Control Function: Chemical Shim and Emergency Boration Supply Remarks: Pa rame te r OST Reg'd Comments (Frequency) N NA NA Constant speed induction motor Pi 2.7.1 X Pump Suction Pressure Indicator [2CHS-P1123A), local (Q)
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AP 2.7.1 X Calculated using Pump Discharge Pressure - Indicator { 2CHS-P1105) and Pump Suction (Q) Pressure, local Q 2.7.1 X' Flow indicator 12CHS-F1123A), local. ~ (0) v 2.7.1 X Portable Monitoring Equipment .- Fixed vibration probe (Q) Ib 2.7.1 X Portable monitoring equipment requi red ( i .e. , Contact Pyremeter) (A)
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L 2.7.1 X Bearing housing provided with oil levet rese rvo i r i nd i ca to r, locas. (Q) e 11 1SSUE 1 REV 4 l - i I e " 9 + -
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' PUMP TESTING OUTLINE .
Pump 22B Boric Acid Transfer Pump Code. . . Name: Pump Number:'2CHS*P228 Class: 3 System: 7 Chemical and Volume Control Function: Chemical Shim and Emergency Boration Supply : Rema rks: Pa ramete r OST Req'd - Comments - ( Frequency) a N NA NA Constant speed induction motor - Pi 2.7.2 X Pump Suction Pressure. Indicator (2CHS-Pl1238),' ' local (Q) __ AP 2.7.2 X. Calculated using Pump Discharge Pressure Indicator-(2CHS-P1110] and Pump Suction ~ * (Q) Pressure,.locai Q 2.7.2 X flow i nd icator. (2CHS-F t 1238 ), . loca l (Q) V 2.7.2 X Portable Monitoring Equipment - f ixed vibration probe (Q) Ib 2.7.2 X Portspie moni toring equipment . requi red ( i .e. ,- Contact Py.-ter) . (A) L 2.7.2 X Bearing housing provided wi th oil ' level reservoir indicator, local (Q) 12- ISSt/E 1 ._
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- PUMP TESTING OUTLINE Pump 21A Residuai Heat Remova1 Pump- Code Name: Pump. Number: 2RHS*F21A Class: 2 System: 10 Residual Heat Removal function: Long term decay heat removal Remarks: See RR1, RR2, and RR3. Pump.is tested during Cold Shutdown and. Refueling outages.
Pa ramete r OST - Reg'd Comments
! Frequency)
N MA NA Cons ta tst speed induction motor Pi 2.10.1 X Pump Suction Pressure Indicator . [2RHS-P1603A), Ma in Control Room (Q)
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AP 2.10.1 X Calculated using Pump Discharge Pressure Indicator [2RHS-P1602A) and Pump Section . Pressure, Main Control Board
-e (Q)
- Q 2.10.1 X Recirculation Line Flow Indicator [2RHS-Fl60TA), f4ain Control Board, Return Line Flow Indicator to Cold Leg 22 [2RHS-F1605A] Letdown Line Flow [2CHS-F1150],
(Q) Ma in Con t ro l Boa rd . V 2.10.1 X Motor equipped with vibration sensors wired 'to a remote . location outside - - f. (Q) containment Ib 2.10.1 RR2 Pump bearings in the driver. Control Room computes address points for 1 (A) thermocouples provided for bearings. Upper motor Dea ring ( TO687A), lower motor bearing (TO686A) d J L 2.10.1 X Motor bea rings upper and l owe r . -- o i l sight gauge - local (pump and driverr , bea rings integ ra l in motor)- e (Q) l l l i 13 ISSUE 1
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Pump 218 Residual Heat Removal - Pump Code ..
.2' Plame: Pump Numbe r: 2RHS*P21B Class: ' System: 10 Residua!. Heat Remove 1- -
Function: Long term decay heat remova l Remarks: See 'kR1,'RR2, and RR3. Pump is tested during Cold Shutdown and Refueling outages. Pa ramete r OST . Reg'd Comments (Frequency) N NA NA Constant speed induction motor Pi 2.10.2 X Pump Suction Pressure indicator [2RHS-P16038), Main control Room (Q) g 2.10.2 X Calculated using Pump Discharge Pressure Indicator (2RHS-P1602B] and Pump Suction (Q) Pressure, Main Control Boa rd Q 2.10.2 X Recirculation Line Flow Indicator (2RHS-F 1607B), Main Control Board, Peturn Line (Q) Flow Indicator to Cold Leg 22 (2RHS-F1605BI Letdown Line Flow (2CHS-Ft150), Main Control Board V 2.10.2 X Motor equipped with vibration sensors wired to a sm vte location outside (Q) containment Ib 2.10.2 RR? PJap bea ri ng s i n the d ri ve r. . Control Room computer address points for - (A) thermocouples provided for bearings. Upper motor bearing (10697A), lower motor bear ~ng (10696A) L 2.10.2 X Motor bearings upper and lower - oil sight gauge .- local (pump and driver (Q) bearings integral in motor) Its ISSUE 1
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BVPS-2 IST . . _ PtMP . TESTING OUTLINE Pump 21A Low Head-Safety Pumo -- Code - Name: Injection Pump Numbe r: 2 SIS *P21A Class: 2 System: 11 Safety injectior* - ._ Function: Low Pressure - High Volume Safety injection Rema rks: ~See RR2 and Long Term Recirculation - Comments Pa rameter OST Req'd (Frequency) m _ N NA NA Constant speed induction motor Pi 2.11.1 X Pump Suction Pressure Indicator [2 SIS-P1938], . local (Q) . AP 2.I1.1 X Ca1cuIated using Pump Dischsrge Pressure indicator [2S1S-P19ts3] and Pump Suction (Q) Pressure, local Q 2.11.1 X . Flow Indicator Switch [2 SIS *FIS970A), local indication (Q) , V 2.11.1 X - Portable monitoring equipment.- Fixed vibration probe (Q) Ib 2.)1.1 RR2 - Control Room computer address points for thermocouples provided for. bearings. (A) Inboard bearing (T2676A), outboard bearing (T2677A) -i i L 2.11.1 X Oil level i nd i ca to r, local (Q) m , 15 ' I SSUE 1 . REV N
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Name: Injection Pump Number: ~ 2 SIS *P218 - Class: 2- Systemi 11 Safety injection _, kunction: Low Pressure - High Volume Safety injection - Remarks: .See RR2 , and Long - Term Reci rculation Pa rameter OST Reg'd Comments " ( F requency) NA Constant speed . induction motor I N NA Pi 2.11.2 X Pump Suction Pressure indicator [2 SIS-P1939), ' local
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AP 2.11.2 X Ca lculated using . Pump Discharge Pressure Indicator (2 SIS-P1944 l and Pump Suction. ' ' (Q) Pressure,' local , Q 2.11.2 X F low Indicator Switch [2 SIS *F IS9708), local indication (Q) - V 2.11.2 X Portable monitoring equipment - Fixed vibration probe
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(Q) Ib 2.11.2 RR2 Control Room computer address points for thermocouples provided for bearings. , (A) Inboard bearing -( T2678A), outboard oesring (T2679A) L 2.11.2 X Oil level i nd ica to r, local
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BVPS-2 IST s pup *P TESTIIeG OUTLINE Pump Pump Code esme: 21A Quench Spray Pump 9eumber: 2QSS*P21A Ctess: 2 System: 13 Conteinment Depressurization Function: To provide berated water f rom the RWST to the Remarks: . Containment Spray Header for depressurization foitowing a DBA. Pa rameter OST Reg'd Comments (Freqoency) M 90A NA Constant speed induction motor Pi 2.13.1 X Pump Suction Pressure Indicator {2QSS-P1102A) Control Room (Q) AP 2.13.1 A . Cniculated usirg PtrkDischarge Pressure indicator (24SS-P810'.Al Control Room (Q) 'nd Pump Suction Pressure Q 2.13.1 X ~ e low Indicator [2QSS*F IS101 A), local (0) V 2.13.1 X Portable monitoring equipment - Fixed vibration probe (Q) Tb 2.13.1 X Portable monitoring equipment required ( 6.e., Contact Pyrometer) (A) L 2.13.1 X Level indication provided at the constant level oi s er ( Ioca l ) on escts (Qi bearing bousing 17 ISSUE 1 REV Is
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_. .) BVPS-2 IST PUMP TESTING OUillfet Pump Pump Code - Name: 21B Quench Spray Pump Stunbe r: 2QSS*P218 C8sss: 2 Systee: 13 Conteinment Depressurl28 tion Function: 10 provide borated wFter from the RWSI to tre Reserks: - . . Containment Spray Heeder for depressurizatIon - following a DBA
'Pa ramete r OSI Reg'd Comments-(Frequency)
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N tea ISA Constant speed induction motor Pi 2.13.2 X Pump Suction Pressure Indicator [2QSS-P81028) Control Room (Q) AP 2.13.2 x CaicuIated using Pump Discherge Pressure Indicator (20SS-PI1018) Controf Roem (Q) and Pump Suction Pressure Q 2.13.2 X Flow Indicator { 20SS*F IS1018l, 60 cal (Q) V 2.13.2 x Portsbee monitoring equipment - Fixed vibration probe (Q) - '- ib 2.13.2 x Portable monitoring equipment reg' sired ( i.e., Contact Pyrometer) (A) L 2.13.2 X Levet indication provided at the constant level oi ser ( tocall on each ' (Q) bearing housing 9 18 ISSUE 1 REV 4 < -. _ - , ... . - . . , , . . . ~ . - . . r,,.,,--. _ . _ . . . , . . , . . . _ _ _ _ . .
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p i BVPS-2 iSi PUMP TEST 8seG OUitiNE Pump 28:A ChemiCsI injection Pump Code Name: Pump stumber: 20SS* P28s A class: 2 System: 13 containment Depressurization Function: Chemical injection during containment Remarks: See RR8. depressurization r. Pa rameter OST Reg'd Comments <f ( F requency)
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M faA ftA Constant speed induction motor Pi 2.13.10A X Pump Suction Pressure . Indicator (2QSS-Pl110Al, local (Q) 4 AP 2.13.10A RR8 . Based on Pump Discharge Pressure Indicator l2QSS-P1111 A), locas (Q) Q 2.13.10A X Local flow indicator [20SS*FIS10$Al (Q) V 2.13.10A X Portable monitoring equipment (Q) Tb 2.13.10A X Portable monitoring equipment required ( 4.e., contact pyrometer) (A) L NA NA Pump bearing is grease lubricated via gresse fitting - no oD5ervable 3ubrication level 19 *SSUE 1 REV as
_.._---- . ,.; _, -:- _ . = - _ . - - _ . - . BVPS-2 MT PUMP TESTit AITLINE fPump 2h8 Chemical injection Pump Code Mame: Pump Numbe r: 2QSS* P21sB Class: 2 Systew: 13 Containment Depressurization function: Chemical injection during containment Remarks: See MR8. depressurization Pa rameter OSI Reg'O Comments (Frequency) N MA MA Constant speed induction motor Pi 2.13.10B X Pump Suction Pressure indicator { 2QSS-PI1108), local (0) AP 2.13.10B RR8 Based on Pump Discharge Pressure Indicator l2QSS-Pl111Bj, local (Q) Q 2.13.10B X Local flow indicator [2QSS*F IS10*>B) (Q) V 2.13.10B X Portable monitoring equipment (Q) Ib 2.13.108 X Portable monitorins egoipment required (i.e., contact pyrometer) (A) L MA NA Pump bea ring is grease lubricated via grease fitting - no observable lubrication level 20 8SSUE 1 REV 4
BVPS-2 IST PUMP TESTING OUIL890E
, -8 Pump 21A Reci rculation Spray Pump- Code Name: Pump flumber: 2RSS*P21A Class: 2 System: 13 Containment Depressurization function: Circulate containment sump water for song Remarks: See RR1, RR2, RR4, and RR$. Pump is nor1aa,4y tested dry term containment depressurization in Modes 1 through 4, and with flow during Refueling outages finly.
Pa ramete r OST Req'd Comments (frequency) N NA NA Constant speed induction motor 2.13.3 RR4 Pump run dry stopped as soon as pump start is verified, pump not run more. 1Q) . than 60 seconds. Pi 2BVT 1.13.5 X Test connectitwo for local pressure gauge or Rx blog. sump level also (R) provided { 2RSS*t_8151 A(Bil (See RRS). 2.13.3 RR4 P: mp run dry stopped as soon as pump start is veri ric-8, pump not run more ign than 60 seconds. AP 2BVi 1.!!.S X Ca sculated using Pump Discharge Pressure lesdicator [2RSS-Pl156A) Main Control Board (R) and local Pressure Cage or sump level (See RRS). 2.13.3 RRis Pump run dry stopped as soon as pur., start is verified, pump not run more lui than 60 seconds. Q 2BV1 1.13.5 x Flow Rate Indicator [2RSS*F1157Al Mair. Control Board (R) 2.13.3 RR4 Pump run dry stopped as soon as pump start es verified, pump not run more [ql than 60 seconds. V 2BVi 1.13 . ', X Portable monitoring aquipment - fixed vibration probe (R) 2.13.3 RRes Pump run dry stopped as soon as pump start is verified, pump not run more IA) thar. 60 seconds. Att pump bearings are exempt since located-Ib 2BVi 1.13.3 RR2 Pump and motor i nteg ra l unit. (R) in the main flow path. Control Room computr address points for theripocouples provided for motor bearing - inboard bearing (TO701A) L sea NA Motor bearings gresse lut.ric.ted no observabic level, f%ep has self-lubricated bearing - internal ptmap fluid porting not observable. i ,. 21 ISSUC 1 l REV 4 i i l
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3.____, = . _ _ . ,_ 7 _. q _ j PvPS-2 IST PUMP TEST IllG OUTLlilE Pump 218 Recirculation Spray Pump Code Name: Peup Museber: 2RSS*P21B Class: 2 System: 13 Containment Depressurization Function: Circulate Containment sump water for long Remarks: See RR1, RR2, RR4, and RRS. Pump is reorsally tested dry term containment depressurization in Modes 1 through 4, and with flow during Rsfueling outages only. Pa ranater OST Reg'd Comments (Frequency) N NA NA Constant speed induction motor 2.13.4 RR4 Pump run dry stopped as soon as pump start is verified, ptsap not run more (Q1 than 60 seconds. P3 2BVI 1.13.5 X Test connection for local pressure gauge or Rx bldg sump level (R) also provided {2RSS*Ll151A(Bl}'-(See RRS). 2.13.4 RR4 Pump run dey stopped as soon as pump start is verified, pump not run more (gl than_60 seconds. AP 2BVI 1.13.5 X Calculated using Pump Discharge Pressure Indicator (2RSS-P11568) Main Control board (R) and local Pressure Gage or sump level.(See RRS). 2.13.4 RRes Pump run dry stopped as soon as pump start is verified, pump not run more LQ1 than 60 seconds. Q 2BVT 1.13.5 X Flow Rate Indicator (2RSS*F11 STB) Main Control Board (R) 2.13.4 RR4 Pump run dry stopped as soon as pump start is verified, pump not run more _lQ ) than 60 seconds. V 2BVI 1.13.5 X Portable monitoring equipment - Fixed vibration probe (R) 2.13.4 RFA Pump run dry stopped as soon as pump start i s ve ri f ied, pump not run more (Al - than 60 seconds. Tb 2Bvi 1.13.$ HR2_ Pump and actor integral unit. All pump bearings are exempt since located (R) in the main flow cath. Control Room computee address poirits for thermocouples provided for motor bearing - inboard bearirwy (TO711A) L. NA '~MA Motor bearings grease lubricated no observable level. Ptg has ~ self-lubricated bearing - internal pump fluid porting not observable. 22 8 SSUt- 1 REV is t
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'i BVPG-2 IST h PUMP TESTING OUTI.lME. ,
jPump 21C Reci rculation Spray Pump Code Name: Pump Mumber: 2RSS*P21C Class: 2 System: 13 Contal.sment Depressurization Function: Ci rculate containment ssemp water for long Remarks: See RR1, RR2, RR4, and RR$. Pump is reormally tested dry term contairement depressurization and long in Modes 1 through 4, avid with flow during Refuell.wp - term core recirculation outages only. Pa rameter OST Reg'd Comments (Frequency) N NA MA Constant speed induction motor r 2.13.5 RR4 Pump run dry stopped as soon as gwJap start i s ve ri f ied, pump no t run more _ LQL_ than 60 seconds. Pi 28VI 1.13.5 X Test connection for local pressure gauge or Rx bldg. sump leve[ 7 so (R) provided (2RSS*L1131 A(8)) (See RRS). _ 2.13.5 RR4 Pump run dry stopped es soon as pump start to verified, pump not run more 1Q) than 60 seconds. - AP 2BVi 1.13.5 X Calculated using Pung Discharge Pressure Indicator 12RSS-P1156Cl Main control Boa r18 (R) and Local Pressure Cage or sump level (See RRS). 2.13.5 RR4 Pump run dry stopped as soon as pump start is verified, pump not run more (QI than 60 seconds. Q 2BVI 1.13.5 X F low Rate Indicator (2RSS*Fl157C) P34fn Control Board (R) 2.13.5 RR:s Pump run dry stopped as soon as ptmp start is verified, pump not run more IQ) than 60 seconds. V 2BVI 1.13.5 X Portable monitoring equipment - F ixed vibration probe (R) 2.13.5 RPte Pump run dry stopped as soon as pump start i s ve ri fied, pump rset run more (Al than 60 seconds. Ib 2b /1 1.13.5 RR2 Pump and motor integral unit. All pump bearings are exempt since located (l") in tive main flow path. Control Room computer address points for thermocouples
, provided for motor bearing - inboard bearireg (TO721A)
L MA NA Motor bearings grease lubricated no observable level. Pump has self-lubricated bearing - internal pump fluid porting not observable. 23 ISSUE 1 PEV 4 _ _ . _m_- _ . _ . ~ . _ . 3
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PUplP TEST 1f,G OUTt.1NE
- ump Pump CA Je '~
Plame: 21A Component Cooling 1 dater Mumber: 2CCP*P21A Class: 3 System: 15 Primary Component Cooting Water function: Provide Cooling Water to Resid: sal Heat Removal Remarks: See RR1 and RR2 Heat Exchangers and Rx Plant Components l Pa rame te r UST Reg'd Comment * ( Frequency) M MA NA Constant speed induction motor Pi 2.15.1 X Suction Pressure Indication (2CCP-PS150Al, incal (Q)
// 2.15.1 X (Q) Calculated and Pump Suction using Discharge Pressure Pressure Indicator (PCCP-P1145Al. Mein Con +.rol Board, Q 2.15.1 X -~ -Containment Cooling Water Styply Header flow Indicator (2CCP*F111TA2l on (Q) Main Control Board.
V X 2.15.1 Portable monitcring equipment - F ixed vibration probe (4) Tb 2.15.1 RR2 (A) Control room computer address points for therme.;ouples provided for PLep Beating Oil (T(438A). l_ 2.1$.1 X Sight glass on reservoir (Q) 25 iSStK 1 REV 8:
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SVPS-2 IST PtM9P-TESTING OUTLINE Pump Pump Code O plame: 218 Component Cooling Water Numbe r: 2CCP*P218 Class: 3 System: 15 Primary Component Cooling Water Function: Provide Cooling Water to Residual Heat Removal Remarks: See RR1 and RR2 Heat Exchangers and Rx Plant Components Pa rameter OST Reg'd Commensts ( F requency) M MA NA Constant speed induction motor Pi 2.15.2 X Suction Eressure Indication { 20CP-Pl1500], local ~ (Q) AP 2.15.2 X Calculated using Discharge Pressure Imlicator (2CCP-P114SB), Main Control Board. (Q) and Pump Suction Pressure Q 2.1$.2 X Containment Cooling Wa' er Supply Header F low Indicator l2CCP*F l11782l on (Q) Main Control %s ' $ . Nenregenerative Heat Exchamper Branch Local Flow Indicator [2CCP-Ft103). Seat Water Heat Exchanger Branch Local Flow Indicator [2CCP-F t102). V 2.15.2 X Portable monitoring equipment - Fixed vibration probe (Q) Tb 2.15.2 PR2 Control room computer address points for thermocouples provided for Pump (A) Bearing oil (10648A). L 2.15.2 Sight glass on reservoir (Q) 26 sSSut 1 REV as t _
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BVPS-2 IST PUMP TESit80C OUit lME Pump Pump Code Name: 21C Component Cooting Water Numbo.. 2CCP'P21C C? ass: 3 System: 15 Primary Component Coot ing water Function: Provide Cooling Water to Residual Heat Removal- Remarks: See RRt and RR2 Heat Exchangers and Rx Plant Components Pa rameter OSI Req'd Comments (Frequency) N MA NA Constarit speed induction motor Pi 2.1$.3 X Suction Pressure Indication {20CP-P1150C), . local (Q) AP 2.15.3 X Calculated using Discharge Pressure Indicator (2CCP-P114sSC), Mein Control Boa rd, (Q) and Pump Suction Pressure Q 2.1$.3 X Containment Cooling Water Supply Header Flow Indicator l20CP*f 811 TA2,82) on ~ (Q) Main Control Board. Monregenerative Heat Exchanger Branch Loca*' Flow Indicator 12CCP-Ft103). Seal Water Heat Exchanger Branch Local Flow Indicator [2CCP-Ft 102). V 2.15.3 X Portable monitori.^.g equipment - F ixed vibration probe (Q) Ib 2.15.3 RR2 Control room computer address points for thermocouples provided Ior Ptemp (A) Bearing Oil (10658A). t_ 2.15.3 X Sight glass on reservoir g (Q) 27 _ ISSUE 1 rey as
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BVPS-2 1ST PUMP TEST 198G OUTLIME Pump Steam Driyt,n Auxiiia ry Pump Code riame: Feed Pump Mumbe r: 2FWE*P22 Class: 3 Syt.em: 24 Auxiliary Feedw.ter i Function: Provide emergency makeup to Steam Ger.erator Remarks: See Rpt2. Pu:np is tested monthly during loss of normal feedwater Pa r ame te r OST Reg'd Comments (frequency) 91 2.24.4 X Tachometer provided with steam turbine, local or portable monitoring equipment (M) Pi 2.24.4 X Pump Suction Pressurv Indicator [2f wE-P1156), local
.(M) 6P 2.24.4 X Calculated using Pump Discharge Pressure f ndicator [2f wE-P'1$3) and Pump Suction (M) Pressure, local Q 2.24.4 X F low Indicator [2fWE-f l155l, local (M) i V 2.24.4 X Portable monitority; equipment -. f 4xed vibration probe (M)
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Ib 2.24.4 RR2 Control Room computer address points for thermocouples proviued for eech (A) pump end and thrust bearing. Inboard pump bearirr) (T2652A), outboard pump bearing (T2653A), thrust bearing (12404A) L 2.24.4 X Visual (;i.ec k of oi l Level in Reservoir Tank (M) sSSUE 1
' 28 REY 4
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BVIS-2 IST' PUMP TEST 8NG OUILINE Pump Motor Driven Auxilia ry Pump Code Name: teed Pump 23A N;'abe r: 2fWE*P23A Class: 3 System: 24 Auxillary Fredwater funcc io 1: Provide emergency makeup to Steam Generator Rema rks: See RR2. ** ump is tested untin'Y. during any loss or norma t feedwater ipa rameter 8 OSI Reg'd Comments (Frt%uency) N NA NA Constant speed induction motor Pi 2.24.2 X Pump Suction Pressure Indicator { 2FWE-P1136A), local (M) AP 2.21s.2 X Calco s ated using Pump Cischarge Pressure Indicator { 2fWE-P1155Al and Pump Suction (M) Pressure, locai , Q 2.24.2 X FImr Indicator (2FWE-F 1155Al, local (M) V 2.24.2 X Portable monitoring equipment - Fixed vibratior probe (M) Ib 2.21s.2 RR2 Control Room computer address points for thermocouples provided for er.ch (A) pump end and thrust bearing. Inboard pump bearing (12332A), outboard pump bearing (T2333A), thrust bearing (T2402A) L 2.2ta.2 X Visual check or oil eevel in Reservoir Tank (M) 29 8SSUE 1 i REV 4 l i I
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.N 8VPS-2 1ST PUMP 1ESTING OUTLINE Pump Motor Driven Aux e iiary Pump Code
- Mame: Feed Pump 238 Numbe r: 2FVE*P238 Class: 3 System: 24 Auxillsry Feedwater Function: Provide emergency makeup to Steam Generator Remarks: See RR2. Pump is tested monthly, during any loss of nonws feedwater Pa rac te r OSI Req'c Commen;s
( F requency) N NA NA Constant speed induction motor Pi 2.24.3 X Pump Suction Pressur- Indicator [25WE-Pl1568), 80eal (M) 6P 2.24.3 X Calculated usireg Pump Discharge Pressure Indicator (2fwE-PI1558) and Pump Suction (M) Pressure, local Q 2.24.3 X FIow Indicator [2FWE-Fi1558J, loca I (M) V 2.24.3 X P9rtable monitoring equipment - Fixwl vibrat. ion probe (M) Tb 2.24.3 RR2 Control Room computer address points for thermoccupla s s provided for erch (A) pump end and thrust bearing. Inboard pump bearing ( T2392A), outboard pump bea ring (T239 A), thrust bearing (T2403A) l_ 2.24.3 X Visuai check or oi8 Level in Reservoir Tank (M) 30 8SSUE 1 REV 4
r BVPS-2 IST PtMP TESilNG OUTLINE
. Pump Pump Code Name: 21A Standby Service Water Number: 2SWE-P21A Class: MMS System: 30 Standby Service Water Function: lo provide cooling water to reactor plant heat Remarks: - See RR1 and RR%
exchangers and compor=ents af ter total loss of normal Service Water ( i.e. loss or intake structure) Pa ramete r OST Ree:'d Comments. (Frequency) N NA NA Constant speed induction motor Pi 2.30.1A RR$ No installed instrumentation to meanore suct ion pressure. (Q) Calculate Pi using Intake Water Level Indicator ILR-CW101]. AP 2.30.1A X Calcolated using Pump Discharge Pressure indscator [2SWE-P1112A) and (Q) Intake Water Level Q 2.30.1A X Test connections for pressure differential across Restrictieve Urifice (Q) [RO-RW109) v 2.30.1A X Portable monitoring equipment (Q) Ib NA E Pump shaf t bearings are located within the main flow path ( Re f'. 9WP-8s310) pump and motor vert ically mounted. L 2.30.1A X Pump begrings water lubricated, motor Ocarings upper and lower oil level ll (Q) gauge, local 1 31 4SSWE i REV as
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BvPS-2 iSr PUMP TESTiteG OUTLINE Pump Pump Code Name: 218 Standby Service Water Numbe r: 2SWE-P218 Class: NMS System: 30 Standby Service Water Fu mtion: 10 provide cooling water to reactor plant heat Remarks: See RR1 and RR$. excleangers and components af ter tota l loss or normal Service Water (i.e. loss or intake structure) Pa rame te r OST Req'd Comments ( F requency) M MA MA Constsnt speed induction motor - Pi 2.30.18 RR$ Mo installed instrumentation to measure suction pressure. (Q) Calculate Pi using intake Water Level Indicator { LR-CW104 l. AP 2.30.18 X Calculated using Pump Discharge Pressure Indicator (2SWE-P81128) and (Q) Intake Water Level Q 2.30.1B X Test conneccions for pressure differential across Restriction Oritice (Q) {RO-RW109] V 2.30.18 X Portable monitoring equipment (Q) Ib MA E Pump shaf t bearings are located within the main flow path (Ref. t WP-8 310) pump and motor vertical f y mounted. L 2.30.18 X Pump bearings water lubricated, motor bearings upper and lowe r o i l level (Q) gauge, local 32 ISSUE 1 REV as
+.
BVPS-2 IST PUplP TESTING OUTLillE . Pump Pump Code Name: 21A Service Water Pump llumber: 25WS*P21A Class: 3 System: 30 Service Water Function: Provide cooling water to Remarks: See RRI, RR2, and RRS. Recirculation Spray Heat Exchangers and Reactor Plant components unde r norma l and emergency conditions Pa rameter OST Reg'd Comments { frequency) N NA llA Constant speed induction motor Pi 2.30.2 RR$ No installed instrumentation to measure suction pressure. (Q) CaPculate Pi using Intake Water Level Ind ica to r [ LR-CW101 ) . T 2.30.2 X Calculated using Pump Discharge Pressure Indicator [2SWS-f 8101Al local and (Q) Intake Water Level Q 2.30.2 X~ Portable f low Indicator l2SWS-7 t T100) (Q) V 2.30.2 X Portable monitoring equipment - (Q) Ib 2.30.2 RR2 Pump and motor vertically mounted unit. Pump shaft bearings exempt since (A) located within main flow p,G. Control Room computer address points for thermocouples provi6ed for motor, upper guide bearing (TOTSTA), thrust bearing (TO732A). L 2.30.2 X Upper motor bearings oil level sight glass, bottom motor bearing grease (q) lub rica ted, bottom pumo bearing grease tubricated and sealed at factory. Shaf t bearing freshwater lubricated and can be observed with Suppl r Pressure Indicator { 25WS-Pi1OSA), local 33 ISSUE 1 REV % i
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BVPS-2 iST Pl#tP TESTING OUTLI::E Pts p Pump Code Mame: 218 Service Water Pump 96 umber: 2SWS*P218 Class: 3 System: 30 Service Water Function: Provide cooling water to Hemarks: See RR1, RF2, and RR), Recirculation Spray Heat Exchangers and Reactor Plant components under noraaI and esergency conditiuns Pa rame te e OST Req'd Comments ( F requency) M MA 86A Constant speed induction motor
~
F: 2.30.3 RR$ No installed instrumentation to measure suction pressure. (Q) Calculate Pi using Intake Water l_evel Indicator { LR-CW101l. AP 2.30.3 X Calculated ufeng Pump Discharge P-essure Indicator 12SWS-P11018] tocal indication (Q) and Intake Water Level Q 2.30.3 X Portable F low Indicator l2SWS-f lT100) (Q)-
- V 2.30.3 X Portable monitoring equipment (Q)
Tb 2.30.3 RR2 Pump a**d motor vertical ty mounted unit. Pump shaf t bearings exempt since (A) located within main flow path. Control Room computer address points for thermocouples provided for motor, upper guide bearing ( TO761 A), thrust bearing ( TO762A). L 2.30.3 X bpper motor bearings oi t leve! sight glass, bottom motor bearing grease (Q) tubriceted, bottom pump bearing grease lubricated ano sealed at factney. Shaf t bearing frestrwater lubricated and can be observed witiv Suppiy Pressure indicator [2SWS-P11038), local 3fs ISSUE-1 REV as
- - , . ~ . . - _ _ - . - . - - . . _ _ _ = . .-.___._._.-_.__.-_-..a
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BVPS-2 IST PUMP TESTING OUTLINE IPump Puer Gode 'Peame: 21C Service Water Pump Number: 2SWS*P21C Class: 3 System: 30 Service Water function: Provitfe cooling water to Rer.a rks: See tR 1, RR2, and RR5. RecircuIa* ion Spray Heat
. Exchangers and Reactor Plant components under norma t and emergency conditions Pa ramete r OST Reg'd Comments (Frequency)
N MA NA Constant speed induction motor Pi 2.30.6 RR5 No installed instrumentation to measure suction pressure. l-(Q) Calculate Pi using f ntake Water Level Ind ica tor ( LR-CW101 ).
- AP 2.30.6 X Calculated using Pump Disci'.arge Fressure Indicator 12SWS-P8101Cl local indication (Q) and Intake Water Level Q 2.30.6 X Portable f low indicator { 25WS-F 8 T100]
(Q) V 2.30.6 X Portable monitoring equipment (4) Ib 2.30.6 RR2 Pump and motor vertically mounted unit. Pump shaf t bearings exempt since (A) located within main riow path. Control Room computer address points for thermoeouples provided for motor, upper guide bearing ( T0771A), thrust traring ( T0772A1 L 2.30.6 X Upper motor bea rings oil level sight glass, bottom motor bearing greate i. (Q) f ubricated, bottom pump bearifvt gresse lubricated and sealed at factory, Shaf t bearing freshwater lubricated and can be observed with Supply Pressure Indicator 12SWS-P1105Cl, local 35 8SSUE 1 REV as
BVPS-2 IST' PtplP TESTING OUil_lNE tump 21A Fuel Oii ifansfer Pump Code
,Mame: Pump 100mbe r: 2ECT'P21A. Class: 3 System: 36 Diesel Fuel Oil System function: T ransfer Fuel f rom senderground storage tank Remarks: See RR6 and RRT. Pump is normetly tested bi-mor.thly, to the day tank Pa rame te r OST Req'd Comments (Frequency)
N lik NA Constant speed induction motor Pi 2.36.1 RRT No suction pressure indication provided. Suction pressure will remain (Q) almost constant.
& 2.36.1 RRT Based on pump Discharge Pressure Indicator [2EGF-F1201A), local (Q)
Q 2.36.1 RR6 No instrumentatson provided - l_evel change ever time in the day tank will (Q) . be measured and converted to flowrote. V 2.36.1 X Portsole monitoring equipment - Fixed vibration probe l (Q) - Ib NA E Pump bearings located within main flow path (IWP-4310) L MA s4A Self-lubricated bea rings, internal pumped fluid lubrication 36 3SSUC 1
- REV 4
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BVPS-2 IST . PUMP TESTING OUTLINE Pump 21B fue1 0ii iransfe r Pump Code Name: Pump Number: 2EGF
- P218 - Class: 3 System: 36 Diesel Fuel Oil System.
Function: Transfer Fuel f rom underground storage tante Remarks: See RR6 and RRT. ' Pump it normeley tested bi-monthly, to ti.e day tank Pa rame te r OST Req'd i Comments (Frequency) N NA NA Constant speed induction motor Pi 2.36.1 RRT No suction pressure indication provided. Suction pressure will remain (Q) almost constant. I SP 2.36.1 RRT Cased on pump Discharge Pressure Indicator (2EGF-Pl2018l, local (Q) Q 2.36.1 RR6 No instrumentation provided - Level change over. time in the day tank will (Q) be measured and converted to flowrate. V 2.36.1 X Portable monitoring equipment - Fixed vibration probe (Q) I t, MA E Pump bearings located within main flow path (IWP-4310)
- 8. NA NA Self-lubricated bearings, internal pumped fluid lubrication 37 ISSUE 1 REY 4 i
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u BVPS-2 IST PUMP TESTING OUTLINE. _ Pump 21C Fuel Oil T ransfir Pump Code ._ . Name: Pump Numbe r: 2ECf*P21C Class: 3 . System: 36 Diesel Fuel Oil System i Function: T ransfer fuel from undergroun storage tank Remarks: See RR6 and RRT. Pump is normally tested bi-a,nthly, to the day tank Pa ramete r OSI Req'd Comments (Frequency) N MA MA Constant speed induction motor Pi 2.36.2 RRT No suction pressure indication provided. Suction pressure will remain (Q) almost constant. AP 2.36.2 RRT Besed on pump Discharge Pressure Indicator l2EGF-P1201C), local (Q) Q 2.36.2 RR6 flo instrumentation provided - Level change over time in the day tank will (Q) be measured and converted to flowrote. V 2.36.2 X Portable monitoring equipment - f e xed vibration probe (0) Ib MA E Pump bearings located within main flow path ( SWP-4310) L NA NA Self-lubricated bearings, internal pumped fluid tubrication e 38 8SSUE 1 REV 4
1 BVPS-2 IST PUNP TESTING OUitiflE Pump 21D Fuel Oil T ransfer Pump Code - Name: Pump Numbe r: 2EGF
- P21D Class: 3 System: 36 Diesel Fuel Oil System function: T ransfer Fuel f rom unde ground storage tank Remerks: See RR6 and RRT. . Pump is normally tested bi-monthly.
to the day tank Pa rceeter OST Req'd Cominents ( F requency) N NA "A Constant speed induction motor Pi 2.36.2 RRT flo suction pressure indication provided. Suction pressure will remain (Q) almost constant. AP 2.36.2 RRT Based on pump Discharge Pressure Indicator (2EGF-PI2010), local (Q) Q 2.36.2 RR6 No instrumentation provided - Level changer over time in the day tank will (Q) be measured and converted to flowrate. V 2.36.2 X Portable monitoring equipment - Fixed vibration probe _ (Q) Tb NA E Pump bearings located within nain flow path (IWP-t:310) L MA NA Self-lubricated bearings, internal pumped fluid lubrica t ion 39 85S0E 1 REV N i l
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s i i f. 4 I t l. p? t E j. S, o i SECTION TII. PUMP TESTING RELIEF REQUESTS ! t 4 l L
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F, L . > o , F L BVPS-2 IST f REI.IEF REQUEST 1 i' Pump Mark No(s).: 2CHS*P21A 2RSS*P21A 2CCP*P21A 2SWE P21A , 2CHS*P213 2RSS*P21B 2CCP*P21B 2SWE-P21B i 2CHS*P21C 2RSS*P21C 2CCP*P21C 2SWS*P21A , 2RHS*P21A. 2RSS*P21D 2SWS*P21B 2RHS*P21B 2SWS*P21C
. Code Test Requirement:- "The resistance of the system shall be varied until either the measured differential pressure or the ,
measured flow rate equals the corresponding ; reference value. The other test quantities shown , in Table IWP-3100-1 shall then be measured or observed and recorded." Basis for Relief: Plant conditions may preclude returning to the same point on the pump curve for each pump surveillance test. Relief is, therefore, requested to use a pump curve, which is the fixed response of the pump to various conditions. Alternate Test: A pump curve will be used to compare flowrate with developed hecd. RELIEF REQUEST 2 Pump Mark No(s).: 2CHS*P21A 2 SIS *P21A 2RSS*P21D 2FWE*P23A -l 2CHS*P21B 2 SIS *P21B 2CCP*P21t. 2FWE*P23B 2CHS*P21C 2RSS*P21A 2CCP*P21B 2SWS*P21A 2RHS*P21A 2RSS*P21B 2CCP*P21C 2SWS*P21B 2RHS*P21B 2RSS*P210 2FWE*P22 2SWS*P21C Code Test Requirement: The full-scale range of each instrument shall be three times the reference value or less. , Basis for Relief: Due to the accuracy of a thermocouple and the wide range of most digital readouts, relief is requested from this requirement when a thermocouple input is used in conjunction with a digital readout device. Alternate Test: Bearing temperatures will be obtained using installed thermocouples and read using Control Room computer .Jdress points. 41 ISSUE 1 REV 4 i 1
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[ o . BVPS-2 IST j. RELIEF REQUEST 3 , Pump Mark No(s).: 2RHS*P21A ! 2RHS*P21B Code Test Requirement: ' Quarterly pump testing. t Basis for Relief: These pumps are not required to be run at power or j '. fulfill any safety function to mitigate a design- ; basis accident. Possible overheating of the pumps could occur during pump testing on recirculation ; only and could . compromise the system integrity. The system has no associated. surge tank and the only available expansica protection is the system relief valve. Test personnel would have to make a , containment entry to properly monitor pump operation. . Alternate Test: These pumps will be tested during cold shutdowns and refueling outages per OST 2.10.1(2). t b i k 42 ISSUE 1 REV 4
7 BVPS 2 IST t RELIEF REQUEST 4 _ Pump Mark No(s).: 2RSS*P21A 2RSS*P21C 2RSS*P21B 2RSS*P21D Code Test Requirement: Quarterly pump tests. Basis for Relief: The function of these pumps is to take suction on
. the containment sump and discharge to the, sprav rings on the containment ceiling during a DBA. in order to test these. pumps, a temporary dike must be installed in the containn.ent around the safeguards sump to ensure adequate NPSH for each pvmp. -
Quarterly testing at tewer in this manner is a-safety concern since it would block off the sump from the containment in the event of an accident. Pump testing during cold shutdowns, while not involving the same safety concern, would increase paraonnel radiation exposure, create additional radioactive liquid waste, divert maintenance from higher priority items, and could extend the length of a plant shutdown due- to the extensive preparatory work required to properly install the dike. Alternate Test- Dry run quarterly per OST 2.13.3, 2.13.4, 2.13.5, and 2.13.6 for not more than 60 seconds and stopped as soon as pump start is verified. Also, run on test line r6 circulation per 2BVT 1.13.5 during Refueling Outages. 1 l l l l 43 ISSUE 1 RE'l 4
o y BVPS-2 IST RELIEF REQUEST S-Pump Mark No(s).: 2RSS*P21A 2SWE-P21A s2SWS*P21A 2RSS*P21B 2SWE-P21B 2SWS*P21B 2RSS*P21C 2SWS*P21C 2RSS*P21D Code Test Requirement: Measurement of pump suction pressure before pump . startup and during test.
. Basis for Relief No installed instrumentation exists to measurs suction pressure for these pumps, therefore, relief-es requested from this requirement.
' Alternate Test: The static head of the Recirc Spray Pumps temporary dike and containment sump level, or the Ohio River
. water level for Service Water Pumps will be used to calculate suction pressure, once per test.
RELIEF REQUEST 6 Pump Mark No(s).: 2EGF*P21A 2EGF*P21B 2EGF*P21C 2EGF*P21D Code Test Requirement: Flow rate shall be measured using a -rate or quantity meter installed in the pump test circuit. Basis for Relief: There is no installed instrumentation prcyided to measure flow rate for these pumps, therefore, , relief is requested-from this requirement. Alternate Test: Flow rate will be calculated by measuring the level l change over time of the diesel fuel oil- day- tank- :j and converting -this data to diesel fuel oil # transfer pump flow rate, a i i 44 ISSUE 1 ! REV 4 s
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R' BVPS-2 IST 3 i 4 RELIEF REQUEST 7 m> Pump. Mark No(s).'t. 2EGF*P21A
.2EGF*P21B 2EGF*P210-2EGF*P21D t Code' Test. Requirement: Measurement of- pump suction pressure (before pump
- k. startup and during' test) and delto P.
Basis tor Relief: There is no installed instrumentation provided to measure, suction pressure for these' pumps. Suction
- pressure is . dependent on the level-in the diesel generator fuel bil storage tank. Dae to the minimum . technical specification level permitted in '
the. tank (91.2%), suction- pressuro will ' remain-almost constaat (within _1/2 psig). 'The pump performance is dependent on flowrate. and delta-P. t Since suctina messure will remain almost- constant, f any pump degradation due to changes in.: delta-P ' would solely be dependent on discharge pressure. l Alternate Test: Discharge pressure will be' recorded and trended as an indication of pump performance-in-OST 2.36.1 and -( o OST 2.36.2. i RELIEF REQUEST 8 , Pump Mark No(s).: 2QSS*P24A , 2QSS*P24B Code Test Requirement: Measure pump suction pressure, AP and flow. Basis for Relief: The function of these pumps is to provide a NaOH water solution to the suction of the quench spray ; puaps during an accident. Since these pumps are rotary positive displacement pumps, flow rate and differential pressure are independent variables. Unlike centrifugal style pumps, it is not necessary to measure both parameters to assess the hydraulic parformance of these pumps. Alternate Test: Pump discharge pressure and flow rate will be utilized for evaluating pump performance in OST 2.13.10A and OST 2.13.10B. 45 ISSUE 1 REV 4
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; SECTION'IV., VALVE TESTING REQUIREMENTS
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.The. Inservice Test (IST) Program for valves at Beaver Valley Power Station' (BVPS). ' Unit. 2,. is~ based on subsection IW - Inservice Testing of Valves of the ASME' Boiler and Pressure Vessel Code, Section XI, 1983 edition through the summer 1983 addenda (the code) and Generic Letter No. 89-04, " Guidance on fDeveloping Acceptable Inservice Testing. Programs". The valves' included in this section are all-ASME " Class-1, 2, or 3 valves (and their actuating-and position- indicating systems) which are required to perform a specific i functiontin shutting down the reactor to cold shutdown or in mitigating the consequences of an accident" at BVPS, Unit 2.
The requirements of the code will be followed at all times unless specific relief has been granted by the NRC. I A.. Category A valves are valves for which seat leakage in the closed l- position is-limited to a specific me,ximum amount- for fulfillment of their-function. Category B valves are va'.ves for which seat leakage in .; ' the ' closed position is inconsequential for fulfillment of their
^
function. Category A and B valves will be exercised at least once every three months to the position required to fulfill. their function unless such operation is not practical during plant operation. If only- 1 l limited operation is practical during plant operation, the valves will l D be part-stroke exercised at power and full-stroke exercised during cold i shutdowns. Valves that cannot be stroked at power will be-full-stroked l during cold. shutdowns. In the case of frequent cold shutdorins, these j p valves need not be tested more often than once every three months. For J L a valve in a system declared inoperable or not required to be operable, I the exercising test schedule need'not be followed. Within 30 days , prior to return of the system to operable status, the valves shall be l exercised and the schedule resumed. i E - The time to full-stroke exercise _each power operated valve will also be ! measured and compared to a limiting ' stroke time. Full-stroke time . is j ' that time interval from initiation of the actuating signal to the end of the actuating cycle. The stroke time of all power operated valves shall be measured to at least the nearest second, for stroke times 10 sec or less, or 10% of the specified limiting stroke time for i full-stroke times longer than 10 sec, whenever such a valve is full-strcke tested. Position indication lights on the Control Board are used for valve stroke indication for all testing of power operated l valves with remote position indicators. In addition, valves with l remote position indicators will be observed at least once every 2 years to verify that valve operation is accurately indicated. 47 ISSUE 1 REV 4 l
m; , 1 d BVPS-2 IST Sxception; is taken.to part-stroke' timing motor-operated _ valves, unless specifically~ stated. This. is necessary. becauseL'the motor-operated l valve circuitry -prevents throttling of these valves.. -Under normal-
- operation, the valves must travel to either the' full 'open ,or shut position prior to reversing direction.
The necessary valve disk movement shall be determined by exercising the valve while observing an appropriate indicator,- which signals the required. change of disk positien, or observing indirect evidence (such'
- as changes in' system pressure, flow rate, level, or temperature), which reflect stem or disk position.
All valves with fail-safe actuators (ie. Air Operated' Valves) that are applicable to'this program are tested from the Control Room by the remote operating switch. By placing. the control switch to the closed position, or de-energizing the control power, air is vented off of the-valve actuator thus positioning the veive in the fail-safe position. Corrective action shall be taken if necessary, using the following:
- 1. . If the stroke time of a power-operated-valve exceeds its previous stroke time by 25% for valves with full-stroke time' greater .than 10 seconda, or 50% .for valves with full-stroke tir es less than or equal.to 10 seconds, the test frequency will "be increased to I' monthly. Corrective action on a valve identified as rapid-acting l per Relief Request No. 30 is not required unless its stroke time .l; exceeds the limiting value of 2 seconds established for the valve.
Stroke times of-the valves'will be examined for trends. During the trend review, it will be determined if corrective action is necessary for any valve based on its stroke time history. -When either the corrective action is complete or the. review datermines L it is unnecessary, the original test frequency will be resumod. a 1. p .2. If -a. valve fails to exhibit the. required change of salve stem or L disk' position or exceeds its specified ASME limiting value of ' ! full-stroke time,. then the valve -5 alt be declared inoperable. immediately and an evaluation of .ne valve's condition with respect to -system operability and technical specifications shall be made as follows: f? a. If the inoperable valve is specifically identified in the " I technical specifications, then the applicable technical specification action statements must be followed. l l l l l i 48 ISSUE 1 l l REV 4 l l 0 1 l l
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- b. If the inoperable valve is in a system covered by'a technical.
l' , specification, 'an assessment of its condition must. be made to , determine! if lit i makes ' the system inoperable. -If the condition of the valve renders the system inoperable,.ithen
.the applicable' system technical -specification' action- '
s statements must be-followed.
- ' c. . Corrective , : action' (le. , MWR) sh'all be initiated ;immediately.
- j. d; ~Nothing ~in the ASME Boiler and Pressure Vessel Code'shall be-L construed to supercade the requiraments of- any'. technical- =;
specification. I
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,. e. If the- valve is not covered by any technical specifications 4 and the condition of the valve cannot be' corrected within 24-hours, then the valve shall be declared inoperable per ASME.
- 3. When - a valve or'its control system 'has been replaced or repaired 1/ ' or 'has . undergone maintenance that could affect .its performance, i
-and--prior to the- time; it is returned to service, it;shall be tes*ed'to demonstrate that the performance parameters, which coald? ,
bo.affected by the replacement, repair, or maintenance, are within j 0 . acceptable limits.- Examples of . maintenance ithat could affeet valve performance parameters ' are: adjustment cE S. tem packing; ' h- , removal of the bonnet, stem assembly, or ' actuator; 'and disconnection of hydraulic or electrical lines .
.i The ASME limiting valve stroke time is based on tt.e following criteria:-
- 1. .The Technical Specification value. '
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l 2. ESF Response Time requirements. , t
- c. 3. .. Establishing a two (2)second limit for valves with stroke times :
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- under one (1) second. (rapid-acting valves) - f; l' Y
- 4. The average of put stroke times plus.100% for valves with stnke L
times less than or equal to ten (10) seconus.
- 5. The average of past stroke times plus 50% for valves with stroke times greater than ten (10) seconds.
l l l 6. The design time listed in the UFSAR. l l i 4 In addition, Category A valves are leak rate tested at the same (or greater) frequency as scheduled refueling outages, not to exceed every 1 two years. If the leak rate exceeds the allowable limit, the valve 1 will be repeired or replaced. -) l l 49 ISSUE 1 REV 4 __m_ _ - . .-~,
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l + s BVPS-2:IST. 4 l :p S., B '. Category C valves are valves =which are self actuating'in response to ,T .some system characteristic, such-as pressure-(relief-: . valves) or' flow / ' direction -(check valves). Categoty C valves, are divided into two' groups; safety'or' relief valves and check valves.
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' Safety and relief. valves are setpoint tested in accordance with ASME L PTC 25.3-1976 at least once every five-(5)' years, with a portion of the
' valves from each' system included in the IST Program tested during each' refueling outage. If any valves fail the setpoint test, additional, valves from that system must be tested in accordance~with-Table IWV-3520-1. If a safety or relief valve' fails to ' function properly i during a test, it will be repaired or replaced, o l
' Check valves will be exercised. to the position required to fulfill their function every three months. unless -such' operation is- not-i practical ~ during' plant operation. ~ If only limited operation is l practical during plant operation, the check valve will be part-stroke exercised at power and full-stroke exercised.every cold shutdown, not L
to exceed more than once every three months. Check valves' that are F p normally open- during plant operation' and whose function is to prevent-p reversed flow shall be tested-in a-manner that proves 'thati the disk' l travels- to the seat promptly ca cessation or reversal of flow. Check ll valves that are normally closed during plant : operation and .whose i, function is to open on reversal of pressure differential sha'.1 be l' tested by proving that the. disk movet promptly away from the seat when , L the closing pressure differential is removed and. flow through the valve 1 is initiated. or when a mechanical opening force is applied to 'the - disk. If a check valve fails to exhibit the required change of disk position 1: 'by this testing, then the check vain shall be declared inoperable immediately and an evaluation or the check valve's condition with l respect to system operability and technical specifications shall be. I made as follows:
- 1. If the inoperable check valve is" in a system . covered by a l- technical specification, an assessment of its condition must be l made to determine if it makes the system inoperable. If the condition of the check valve renders the system inoperable, then the applicable system technical specification action statements must be followed.
L MWR) shall be initia*.ed immediately for I
- 2. Corrective action (ie.,
the check valve's repair or replacement. l
- 3. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supercede the requirements of any technical specification.
50 ISSUE 1 REV 4
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- BVPS-2 IST-
;g 4.- If' the check valve is not covered by'any technical _ specifications'-
and the condition of:the check valve etnnot be corrected within 24 hours, then the;aheck valve shall be declared inaperable per ASME. i Before'-returning the check valve to service after' corrective action,-a retest showing acceptable operation will be run.. r
-C. Category D valves are valves which are actuated by an ene.gy seurce capable of only '
- operation, such as rupture disks _-or explosively Y
.here are no ASME Class 1, 2, or 3 Category D valves
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actuated valve. s .at Beaver Valley Power Station, Unit 2. j r2 A11'the inservice testing requirements for each different category of valve ;' in the IST Program are summerized in Table IWV-3700-1.
- This table lists
'the subarti les-of the code that apply to each different type of valve.
TABLE IWV 37001 INSERVICE TEST REQUIREbENTS$ Valve ' Esercise Special i Function t.eak Test Test . . Test
' s Category (!WV 2100) Procedure Procedure Procedure .
~A Activt IWV 3420. lWV.3410 - None A- Passive IWV.3420 None None
- Active None IWV 3410 : None
- i. C-$4fety '
& Relief Active None IWV 3510 None C-Chec'4 Active None IWV.3520. None -
0 Active None None IWV.3600 NOTE: - (1) No tests rerwired for Category 8, C, and C passive valves. u Passive valves are valves which are not required to change position to l accomplish a specific function. .As stated in the table, passive valves are not required . to be exercised. Therefore,- relief is not required from L' t exercising any passive valve and no testing requirement is listed in 'the 1
- outline section.
1.- j Certain exemptions from the valve testing requirements of the ASME code defined by subsection IWV-1200 are listed below:
- 1. Valves used only for operating convenience (ie., manual vent, L drain, instrumsnt and test valves);
- 2. Valves used only for system control-(ie., pressure regulating ,'
valves, flow control valves); h 3. Valves used only for maintenance; and ,. p 4. External control and protection systeras responsible for sensing " plant conditions and providing signals for valve operation. E 51 ISSUE 1 REV 4 l 1
, /
, BVPS 2_ISTl kecords of' the results of- inservice tests 'and corrective actionsJas-required by subsection IWV-6000'are maintained in tabular form. Stroke times of valves will be reviewed for developing trends.
If a question on valve testability exists, the IST program.should be the-controlling document since each component is 'individua11y' assessed for testability and--inclusion in the IST Program. If a valve is specifically- ,
= called-out in the Tech. Specs. (ie., specific valve mark number or uniquely specified by valve nomenclature) to be tested at;one frequency _and the IST- , Program; endorses another frequency, then the^.more- restrictive test i frequency would be applicable.
The follow'ing three- sections of this document are the " Valve Testing Outlines",'" Cold Shutdown Justifications" and " Valve Relief Requests"'
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sections. A. The- " Valve Testing Outlines" sectioa is a listing of all the valves _in the IST Program,- their class, category, NSA, drawing number and coordinates, testing requirements, specific cold shutdown justification reference numbers, relief request reference numbers and test _. procedure 2 ' numbers.
- 1. The valve class will be 1, 2 or 3, corresponding to the safety classifications, f
- 2. The category of the valve will be A, B,.C or D in accordance with, ,
the guidelines of subsection IWV-2200. In addition, combinations of categories may be utilized. If the valve _is not required to change position during an accident or bring the reactor down.to a cold shutdown condition, the fact that it is Passive (P) will also be indicated. For example, a containment isolation check valve that does. not change position would be a category A/C/P valve. From the valve mark number given, the type of valve can be determined-from the list of abbreviations below: A0V - Air Operated MOV - Motor Operated FCV - Flow Control PCV - Pressure Control l l HCV - Hand Control RV - Relief l~ HYV - Hydraulic SOV - Solenoid 1
- LCV - Level Control SV - Safety p,
l 52 ISSUE 1 REV 4
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- 3. The 'normali system- ' arrangement will be. listed .using: the
.' abbreviations-below:
NSA ' Normal System Arrangement 0: - Open - 1S - Shut A - Automatic .." T - Throttled- ' ADC;- Administrative 1y Controlled (ie,: locked, sealed)- ;
- , LO - Locked-Open LS . Locked Shut -t' SS' - Sealed Shut
- 4. The - drawing' number and c.oordinates will be the ones used in the : '
Operating Manual. ;
'5. The' tesc. requirements will be listed using the abbreviations.
below: QS. - Quarterly Stroke [ QST - Quarterly Stroke & Time LT - Leak Rate Test SPT - Set Point 1 Test . LM - Leakage Monitoring [ POS!- Position Verification NA - Not Applicable
. . . . J
. 6. The specific Cold Shutdown Justification'(CSJ) reference number or the' relief request (RR) reference number-will be ILsted.
- 7. - The specific test procedure number, frequency, type of testing, and any comments will be listed using the abbreviations below:
OM - Operating Manual 1 L 2BVT ' Beaver Valley Test (Unit 2)- OST - Operating Surveillance Test l: CMP - Corrective Maintenance Procedure CSD - Cold Shutdown R - Refaeling - b Q - Quarterly
- Monthly M
FS - Full Stroke e
; PS - Partial Stroke FD - Forward Direction l RD - Reverse Direction 53 ISSUE 1 REV 4
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'B. The- " Cold ShutdownT' Justification" section 'contains the detailed i technica1' description of conditions prohibiting the roquired_ testing cf -
s af'ety-related valves and an=' alternate. test method to be performed- :. during cold shutdowns.- 1 Cold Shutdown valve testing wil1~ commence } within 48 hoursof reaching cold' shutdown conditiono, but need not be- ; completed more.often.than once every 92 days. ' Attempts will be m'ade to'
; complete ; testing prior to entering. Mode 4' . Howevur, completion _will .
not be a Mode 4-requirement. .The testing will' resume where- left off 6 'when next _ entering Mode 5. For planned cold shutdowns, where ample
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'. Etime'is available to complete testing on all valves. identified for the-
- cold shutdown test frequency, exceptions to the'48 hour requirement'can
-be'taken._
Beaver Valley ; Unit _2freactor containment is maintained subatmospheric as. required byLtechnica1' specifications,. The subatmospherici condition presants:- a hazardous working environment,for. station personne1'and is-
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-i considered 1naccessible for surveillance testing. Surveillance testing 1
that- requires reactor _ containment - entry will be performed at cold. shutdown and' refueling. 1 + ; C. The- " Valve Relief Requests" .section contains-the detailed technical--
-i description of conditions - prohibiting the 1 required- testing _of (
safety-related _ valves', : an ' alternate test method and frequency of
.rovised testing. j 1.'
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- 3, SYSTEM NAME: Reactor Coolant SYSTEM NUMBER: _6_ -.
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M a rk Drawing D rawi ng Test Relier Number Class NSA OM No. Coo rd. Requirement Request Comments A B C D P 2RCS*68 a X X 6-2 E-2 QS CSJ1 __ CST 2.1.10-F3.RD (CS01 LT RR1 2BVT 1.47.5-Leak Test (R) ___ 2RCS*72 2 X X 6-2 F-2 QS CSJ2 OST 2.1.10-FS.RD (CSDI LT kR1 2BVT 1.47.5-Leak Test (R)
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2RCS*HV100 2 X X 6-2 G-2 SPT- 2BVT 1.60.5-fR) L) RRI.RR28 ggVT 1.47.5-Leak Fest (kl 2RCS*AOV101 2 X 6-2 E-2 ' QST OST 2.47.3Af 3BI-St roke & Time' f ol LT RR1 2BVT 1. 4 7. 5-Leal-: Test [R) 2RCS*SOV200A 1 X S 6-2 E-6 QST RR33 OST 2.6.9-Stroke & Time (R) 2RCS*SOV2008 1 X S 6-2 F-6 QST RR33 OST 2.6.9-Stroke & Time (R) 2RCS*SOV201A 1 X S 6-2 E-6 QST RR33 OST 2.6.9-St roke & Time IRI 2RCS*SOV201B 1 X S 6-2 T-6 QST RR33 OST 2. 6.9-S t roke & T i me ( R ) 2RCS*llCV250A 2 X S 6 G-6 QST RR33 OST 2.6.9-Stroke & Time (R) 2RCS*HCV250B 2 X S 6-2 G-6 QST RR33 OST 2.6.9-Stroke & Time fR) 2RCS*PCV455C 1 X A 6-1 F-1 QST CSJ4 OST 2.6.8-St roke & Timo ' f CSDI 2RCS*PCV455D 1 X A 6-1 F-1 QST CSJ4 OST 2.6.8-Stroke & Time ICSD) 2RCS*PCV456 1 X A 6-1 E-1 QST CSJ4 OST 2.6.8-Stroke & Time (CSD) 2RCS*AOV519 2 X S 6-2 F-1 ____QST OST 2.47. 3ALIBJ-St roke' fc Time f ol; l LT RR1.RR26 2BVT 1.47.5-Leak f est (R) 2RCS*MOV535 1 X 0 6-1 F-2 QST- OST 2.6.6-St roke k Tice 101 2RCS*MOV536 1 X 0 6-1 E QST OST 2.6.5-Stroke & Time IQ1 2RCS*MOV537 1 X 0 6-1 F-C QST' 'OST 2.6.6-St roke & Time 101 2RCS*RV551A 1 X 6-1 D-3 SPT 2BVT'1.60.5-fR) 2RCS*RV5518 1 x 6-1 P-3 SPT 2BVT 1.60.5-fRl' ' .
.X 6-1 D-4 I EPT 2BVT 1.60.5-fR1 2RCS*RV551C 1 56 - ' ISSUE.15
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VALVE. TESTING OUTLINE SYSTEM NAME: Chemical and Volume Control SYSTEM MUMBER: 1-Valve l Valve Ca tego ry CSJ or Ma rk Drsving ' Drawi ng 1 Test Relief Number Class -NSA OM No.. - Coo rd . Requirement Request Comments. A 8 C D P 2CHS*22 2 X 7-1' C-8 QS OST 2.7,4-PS. FD (91 o0S OST 2.7.Sf61-FS.RD 101 QS RR3 OST 2.11.14-rS.FD (R) 7-1 OST 2.7.5-PS.FD (Q)
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2CHS*23 2 X C-10 QS QS OSI 2.7.4f61-FS.RD (Q1 QS- RR3- OST 2.11.14-FS.FD (R) 2CHS*24 2 X '7-1 C-9 QS OST 2.7.6-PS.FD (Q) QS OST 2.7.4151-F_S,RD (Q)
-QS RR3 OST 2.1?.14-FS.FD (R) 2CHS*31 2 X X 7-1 B-6 QS' CSJ5 OST 2.1.10-FS.RD (LSD)
LT 2BVI 1.47.11-Leak Test (R) 2CHS*75 3 X 7-2 B-3 QS OST 2.7.1-FS.FD (31 2CHS*76 3 X 7-2 F-3 QS OST 2.7.2-FS.Fb'(Q) 2CHS*84 3 X 7-2 E-7 OS CSJ7 OST 2.7.13-FS.FD (CSDI 2CHS*FCV113A 3 X A 7-2 E-7 QST OST 2.47.3Af381-Stroke & Time (Q) 2CHS*LCV115B 2 X A 7-1 F-8 QST OST ' 2.47.3Af 361-Stroke & Time (Q) 2CHS*LCV115C 2 X A 7-1 C-J -QST CSJ6 OST 2.1.10-St roke & Time ICSDI 2CHS*LCV1150 2 X A l-1 F-10 QST OST. R;47.3Af 331-stroke & Time (Q) l' 2CHS*LCV115E 2 X A 7-1 C-7 QST CSJ6 OST 2.1.10-St roke & Time (CSD) 2CHS*136 2 X 1-2 E-8 QS CSJ7 OST.2.7.13-FS.FD (CSDI 2CHS*t41 2 X 7-2 F-9 QS CSJ7 OST 2.7.13-FS.FD (CSD) S 7-1 F-1 QST: OST 2.47.3Af 381-Stroke & Time (Q) l _.
- 2CHS*HCV142 2 X LT RR1 2BVT 1.47.5-Leak Test (R)
_PCHS'i32 2 X 7-1 8-7 09 OST 2.7.ft-FS F9 (Q) 2CHS*153 2 X _
'7-1 D-7 _JG 3 OST 2.7.5-FS.FD (01' 2 X 7-1 D-7 QS i OST 2.7.6-FS.FD iQl' 62CHS*154
.37
. ISSUE 1 REV 4
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s - Valve Valve Ca tego ry . CSJ or - Mark Drawing D raw a r.g Tesi Relier: Number Class NGA OM No. Coo rd. Requirement Request Comments A B C D P 2CHS*FCV160 2 X X S 7-1 B-7 LT 2BVT 1.47'11-Leak Test (R) 2CHS*RV160 2 X 7-1 A-7 SPT 2BVT 1.60.5-fRl' 2CHS*ADV260A 2 X S 7-1 0-1 l QST OS,7 2.47.3Af3BI-Stroke & Time'(Q1" ..
- LT RRI.RR2.RR24 2BVT 1.47.5-Leak Test (R1 3 "
2CHS*ADV2008 2 X 0 7-1 D-1 2' QST- OST 2.47.3Af3B1-Stroke & Time fel ~l LT RR1.RR2.RR24 2BVi 1.47.5-Leak Test (R) 2CHS*ADV200C 2 X S 7-1 E-1 QST OST 2.47.3Af 381-Stroke & Time (01 l LT RRI.RR2.RR24 2BV , 1.47.5-Leak Test (R) 2CHS*RV203 2 X X 7-1 E-1 SPT 2BVT 1.60.5-fR) LT RR1 2BVT 1.47.5-Leak Test-IRI OST 2.1.10-Stroke & Time (CSD)
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2CHS*AOV204 2 X 0 7-1 G-2 QST CSJ8 1.T RR1 2BVI 1.41.5-Leak Test IR) 2CHS*SOV206 2 X S 7-2 E-8 QST OST 2.47.3Af 381-Stroke & Time (0) 2CHS*RV260A 2 X 7-3 B-4 SPT 2BVT 1.60.5-(R) 2CHS*RV2608 2 __ X 7-3 E-3' SPT 2BVT 1.60.5-fR1 2CHS*RV260C 2 X 7-3 G-4 SPT 2BVT 1.60.5-fR1 2CHS*MOV275A 2 X 0 7-1 F-6 QST OST 2.47.3Af 3BI-Stroke & Time f 01 2CHS*MOV275B 2 X 0 7-1 F-7 QST OST 2.47.3Af 381-Stroke & Time (QI 2Cf:s*MOV275C 2 X 0 7-1 F-7 QST OST 2.47.3Af3BI-Stroke & Time 101 2CHS*MOv209 2 X O 7-1 B-6 QST CSJ9 ' OST 2.1.10-St roke & Time (CSD) LT 23VT 1.47.11-Leak Test (R) 2CHS*MOV308A 2 X 0 7-3 'B-3 ' QST CSJ10' OST '2.1.10-St roke & Time (CSD). LY 2BVI 1.47.11-Leak Test (R) 2CHS*MOV308B 2 X 0 7-3 -D-3 QST CSJ10 OST 2.1.10-St roke & T ime (CSDI LT 2BVT 1.47.11-Leak Test (R) 2CHS*MOV308C 2 X 0 7-3 C-3 QST CSJ10 OST 2.1.10-St roke & T ime (CS01 ' LT - 2BVT 1.47.11-Leak Test IRI 58 - ISSur 1 REV 4
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VALVE TESTING OUTLINE' SYSTEM 98AME: Chemical and Volume Control SYSTEM NUMBER: __~f _ Valve [ j Valve Ca tego ry l- ! CSJ or Mark . Drawing Drawing Test Retter Number Class NSA OM No. Coo rd. Requirement Request Comments A B C D P 2CHS*MOV310 2 X 0 7-1 A-9 QST CSJ11 OST 2.1.10-st roke & Time (CSDl'
'CHS*MOV350 2 X S 7-2 F-8 QST OST 2.47. 3Af 3BI-St roke &' Time (01 ' - l?
2CHS*MOV373 2 X 0 7-3 F-10 -QST CSJ12 OST 2.1.10-St roxe & Time _f CSol 2CHS*MOV378 2 X 0 7 E-8 'QST CSJ13' OST 2.1.10-3troke & Time (CSol'- LT RRI.P.R23 2BVT 1.47.5-Leak Test (R) 2CHS*MOV380A 2 y S 7-1 D-6 QST OST 2.47.3Af3BI-Stroke & Fine f01 _2CHS*MOV3808 2 X S 7-1 E-6 QST OST 2.47.3Af 381-St roke & Time (Q1 2CHS*MOV381 2 X 0 7-3 F-8 QST- CSJ13 OST 2.1.10-Stroke & Time (CSDI - LT RRi 2BVT 1.47.5-Leak T2st (R) 2CHS*RV382A 2 X 7-3 ~ C-8 SPT 2BVT 1.60.5-fR)- 2CHS*MOV383A 2 X 0 7-1 D-6 QST OST 2.47.3Af 3Bi-Otroke & Time f 01 2CHS*MOV383B 2 M O- 7-1 F-6 'QST 0ST 2.47.3Af 38)-Stroke i Time to) 2CHS*RV450A 2 X___ 1 D-6 SPT '2BVT 1.60.5-lR1 2CHS*RV4500 2 X ~7-1 E-6 SPT 2BYT 1.60.5-fR1 2CHS*LCV460A 1 X 0 7-1 A-1 QST CSJ14 OST 2.1.10-St roke & T !ae (CSD) - 2CHS*LCV460B 1 X 0 7-1 A-3 ~~ QST
- CSJ14 OST 2.1.10-St roke a Time (CS01 2CHS*472 2 X X X 7-1 B-7 LT '2BVT 1.47.11-Leak Test (R) 2CHS*473 2 X X 7-3 E-8 QS _
CSJ15 OST 2.1.10-FS.FC.RD (CSD) LT RRI.RR23 2BVT 1.4 7.5-Leak Test (R) 2CHS*474 2 X X 7-3 B-4 QS CSJ16 OST 2.1.10-FS.RD (CSDI LT 2BVT 1. 4 7 c11-Leak Test (Rl 2CHS*475 2 X X 7-3 G-4 QS CSJ16 " OSL 2.1.10-FS.RD ( CS01 - LT 2Bei 1.47.11-Leak Test (R) 2CHS*476 2 X X .7-3 D-4 QS CSJ16 OST 2.1.10-FS.RD fCSD) LT 2BVT 1.47.11-Leak Test (Rl-59" ISSUE 1 _ R EV 4 - _ _ . - _ _ _ - _ . . _ - - . - - _ _ _ _ . _ _ . _ . ,. , . , .- .. ; . _ . _-._m. _
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VALVE TESTING OUTLINE SYSTEM NAME: Chemical and Vo.ume Control SYSTEM NUMBER:. 1 1 Valve Valve Category CSJ or Mark Drawing D rawi ng . Test' Relief Number Class NSA OM No. Coord. Requirement Request. Comments A B C D P 2CHS*MOV8130A 2 X LO 7-1 E-9 QST CSJ17 OST 2.1.10-Stroke & Time (CSDl ' 2GHS*MOV8130B 2 X LO 7-1 E-9 QST OSJ17 OST 2.1.10-Stroke & Time (CSD)' 2CHS*MOV8131A 2 X LO 7-1 E-9 QST CSJ17 OST 2.1.10-Stroke & Time (CSDI 2CHS*MOV8131B 2 X LO 7-1 E-10 QS_I CSJ17 OST-2.1.10-Stroke & Time iCSOI 2CHS*MOV8132A 2 X LO 7-1 C-9 QST CSJ17 OST 2.1.10-Stroke & Time ICS01 2CHS*MOV8132B 2 X LO 7-1 C-9' QST CSJ17 OST 2.1.10-Stroke & Yime (CSDI 2CHS*MOV8133A 2 X LO 7-1 C-9 QST CSJ17 OST 2.1.10-Stroke & Time (CSD) 2CHS*MOV81338 2 X LO 7-1 C-9 QST CSJ17' OST 2.1.10-Stroke & Time ICSD) 2CHS*RV8144 2 X 7-1 A-5 SPT 2BVT 1.60.5-fR)' 60 ISSUE 1
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- LT RR1 RR2.RR28 2BVT 1.47.5-Leak Test (R) 2RHS*107 2 X X LS 10-1 D-7 LT RRI.RR2 2BVT 1.47.5-Leak Test' (R) l OST 2.10.3-St roke, - T ime k .
2RHS*FCV605A 2 X T '10-1 B-5 QST CSJ19 Fall Closed (CSD) , OST 2.10.4-St roke, T ime & 2RHS*FCV605B 2 X T 10-1 T-5 QST CSJ19 Fall Closed (CSDI 2RHS*MOV701x 1 X S 10-1 C-1 QST CSJ20 OST 2.10.3-St roks_ & Time (CS01' LT OST 2.10.5-Leak Test tH) 2RHS*MOV701B 1 X S 10-1 D-1 QST CSJ20 OST 2.10.4-Stroke & Time ICSOl LT OST 2.10.5-Leak Test ( R) 2RHS*MOV702A 1 X S 10-1 C-1 QST CSJ20 OST 2.10.3-Stroke & Time ICSDI LT OST 2.10.5-Leak Test (R) 2RHS*MOV7028 1 X S 10-1 D-1 QST CSJ20 OST - 2.10. 4-St roke & T i me ( CSo l Li OST 2.10.5-Leak fest (R) 2RHS*MOV720A 1 X S 10-1 ~C-8 QST CSJ20 OST 2.10. 3-St roke & Time (CEDI LM Continuously Monitored by.. OM 54 Station too L5-120 . 2RHS*MOV7208 1 X S 10-1 'F-8 QST CSJ20 OST 2. *0. 4-St roke & T i me (CS01 ' LM Cont inuous ly Mon i to red by - l OM 54 Station Lee LS-120 i ( 2RHS*RV721r 2 X 10-1 C-1 SPT 2BVT 1.60.5-(R) 2RHS*RV7218 2 X 10-1 ' E-1 SPT 2BVT 1.60.5-iR) i l i i 62 ~ ISSUE 1' REV 4' .o l l f
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m . BVPS-2 e ST .: vat.VE. TESTING OUTLINE SYSTEM MAME: CaFety iniection SYSTEM MdMBER: 11~ i Y Valve Valve Category . CSJ or Mark Drawi ng Drawing Test Relier Numbe r Class NSA OM No. Coo rd. Requi rement Request Comments A B C D P ; 2 SIS *6 2 X 11-1 E-4 QS OST 2.11.2-FS.RD (Q1 .E QS RR4 OS1 2.11.14-FS.FD (R)
~
2 SIS *7 2 X 11-1 G-4 0S OST 2.11.1-FS RD (Q) QS RR4 OST 2.11.14-FS.FD (R) 2 SIS *27 2 X 11-1 F-1 QS RRS' OST 2.11.14-FS.FU (RI' 2 SIS *41 2 X X S 11-2 C-2 LT RRt.RR28 2BVT 1.47.5-Leak Test (R) 2 SIS *42 2 X X 11-2 E-2 QS CSJ22 OST 2.1.10-FS.RD (CSD) lLT RRl 28VT-1.47.5-Leak Test (Rl 2 SIS *46 2 X 11-1 F-5 QS CSJ53 OST 2.1.10-FS.FD.RD (CSD) 2 SIS *47 2 X 11-1 D-5 QS' CSJ53 OST 2.1.10-FS.FD.RD (CSD) 2 SIS *83 2 X X 11-1 A-4 QS CSJ23 OST-2.1.10-FS.FD RD (CSOl' LT 2BV1 1.47.1)-Leak Test (R) 2 SIS *84 2 X X 11-1 B-4 QS CSJ23 OST 2.1.10-FS.FD.RD (CSD) LT 28VT-1.47.11-Leak Test (R) 2 SIS *94 2 X X 11-1 D-6 QS CSJ23 OST 2.1.10-FS.FD.RD (C3DI LT 2BVI 1.47.11-Leak Test (Rl 2 SIS *95 2 X X 11-1 C-6 QS CSJ23 'OST 2.1.10-FS.FD.RD (CSD) LT 2BVT 1.47.11-Leak Test (R) 2 SIS *107 1 X X 11-1 C-9 QS RR6 OST 2.11.14-FS.FD (Rl' LT OST 2.11.16-Leak Test (R) 2 SIS *108 1 X X 11-1 E-9 QS RR6 OST 2.11.14-FS.FD (R) ~ LT OST 2.11.16-Leak Test (R) 2 SIS *109 1 X X 11-1 F-9 QS1 RR6' OST 2.11.14-FS.FD (R) LT OSI 2.11.16-Leak Test (R) X 11-1 A-7 QS- RR7 "OST 2.11.14-FS.FD (Rl' 2 SIS *122 1 2 SIS *123 1 X 11-1 A-7 QS RR7 ' OST 2.11.14-FS. FD (R1 _ X 11-1 A-7 OS RR7 OST 2.11.14-FS.FD (R) 2$1S*124 1 64 ISSUE 1
'REV 4
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BVPS-2 eST. VALVE TESTING OUTLINE SYSTEM MAME: Safety in.iection SYSTEM NUMBER: li Valve-Valve Ca tego ry " - CSJ or Mark Drawing D rawi ng Test Relier Number Class NSA OM No. Coo rd. Requirement Request Comments J A B C D P 2 SIS *125 1 X 11-1 B-7 QS RR7 OST 2.11.14-FS.FD (R) 2 SIS *126 1 X 11-1 B-T QS RR7 ' OST 2.11.14-FS.FD fR)" 2 SIS *127 1 X 11-1 B-7 QS RR7- OST 2.11.1 -FS.FD (R) 2 SIS *128 1 X X 11-1 .B-8' QS_ RR8 OST 2.11.14-FS.FD fRI LT OST 2.11.16-Leak Test (R) 2 SIS *129 1 X X 11-1 B-10 QS RR8 OST 2.11.14-FS.FD (R) LT OST 2.11.16-Leak-Test IR) 2 SIS *130 2 X X 11-1 F-9 QS CSJ24 OST 2.1.10-FS.FD.RD (CSDI LT 2BVT 1.47.11-Leak Test IRI 2 SIS *RV130 2 X X 11-2 D-2 SPT 2BVT 1.60.5-(Rl' LT RRt.RR28 2BVT 1 4LS-Leak Test (R) 2 SIS *132 2 X X 11-1 F-9 QS CSJ24 OST 2.1.10-FS.FD.RD ICSDi' LT OST 2.11.16-Leak Test (R) 2 SIS *133 2 X X 11-1 E-9 QS CSJ24 ' OST 2.1.10-FS.FD.RD (CSD) LT - OST 2.11.16-Leak Test IR) 2 SIS *134 1 X 11-1 C-9 QS RR9 OST 2.11.14-FS.FD (R) 2 SIS *135 1 Y 11-1 D-9' QS RR9 OST 2.11.14-FS.FD (R) 2 SIS *136 1 X 11-1 D-9 QS RR9 OST 2.11.14-FS.FD (R) 2 SIS *137 1 X 11-1 C-9 QS RR9 OST 2.11.14-FS.FD (R) 2Sts*133 1 X 11-1 C-9 QS RR9 GST 2.11.14-FS.FD tR) 2 SIS *139 1 X 11-1 C-9 QS RR9 -OST 2.11.14-FS.FD [R) 1: 2 SIS *141 1 X X 6-1 E-6 QS RR10 2BVT 1.11.3-FS.FD (R) LT OST 2.11.4-Leak Test (R) 2dVT 1.11.3-FS.FD (R) 2 SIS *142 1 X X 11-2 F-9 QS RR10 LT OST 2.11.5-Leak test IRI . 2 SIS *145 1 X X 6-1 D-6 QS RR10 , 2BVT 1.11.3-FS.FD [R) LT I -OST 2.11.4-Leak Test (R) 65 ?lSSUE 1
.REV 4
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VALVE TESilNG OUTLINE _ SYSTEM MAME: Safety in.iectien SYSTEM NUMBER: 11' Valve Valve Ca tego ry .. . CSJ o r - Mark Drawi ng Drawi ng Test Relic! Number Class NSA OM No. Coo r1. Requi rement .Recuest Comments A B C D P
,. 4 2 SIS *147 1 X X 11-2' F-7 QS RR10 2BVT 1.11.3-FS.FD (R)' .
LT OST 2.11.5-Leak Test (R) . 2 SIS *14S 1 X X 11-2 F-4 QS RR10 29VTLI.11.3-FS.FD (R1 LT OST 2.11.5-Leak Test (R) 1 2S:S*151 1 X X 6-1 D-5 QS RR10 2BVT 1.11.3-FS.FD (R1' LT -OST 2.11.4-Leak Test (R1 L 2 SIS *RV175 2 X X 11-2 ~F-1^ SPT 2BVT 1.60.5-(R) LT RRt.RR28 2BVT 1.47.5-Leak Test (R) 3 SIS *545 1 X 11-1 A-9 QS RR11 OST 2.11.14-FS. FD ( R) __ 2 SIS *546 1 X 11-1 A-9 QS RR11 OST 2.11.14-FS. FD ( R) 2 SIS *547 1 X 11-1 A-9 QS RR11 OST 2.11.14-FS.FD (R) 2 SIS *548 1 X 11-1 A-10 OS RR1R OST 2.11.14-FS.FD (R) 2 SIS *550 1 X 11-1 A-10 QS Rhi2 OST 2.11.14-FS.FD (R) 2 SIS *552 1 X 11-1 A-10 OS 'RR12 OST 2.11.14-IS.FD (R) 2 SIS *MOV836 2 X S. 11-1 D-5 QST CSJ25 OST 2.1.10-St roke & Time (CSD1 ' LT 2BVI 1.47.11-Leak Test (Al 2 SIS *HOV840 2 X S 11-1 C-5 QST ' OST 2.47.3A(381-Stroke & Time (Q) l LT BVT 1.47.11-Leak Test (R) 2 SIS *MOvg41 2 X 0 11-1 B-2 QST' ' OST ' 2.47.3A( 3B1-St roke & Time (Q1 2 SIS *MOV842 2 X O 11-2 F-2 QST OSi J.47.3Af 381-St roke & Time (Q) LT RR1 28VT 1.47.5-Leak lest (R) X 11-2 D-4 SPT -2BVT 1.60.5-(R; 2 SIS *RV858A 2 2 SIS *RV858B 2 X 11-2 0-7 SPT ~ 2BVT 1.60.$-{R) 2 X 11-2 0-10 SPT 28VT'1.60.5-(R) 2 SIS *RV858C 2 SIS *MOV863A 2 X S 11-1 0-7 QST OST 2.47. 3A( 381-St roke & Time (Q1 - 2 SIS *MOV863B 2 X S 11-1 'F-6 QST OST 2.47.3A(381-Stroke & time-(Q) 66 ISSUE 11
'REV 47
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[ R f ;9 E-~ BVPS-2 8T. VALVE TESTING OUTLINE SYSTEM NAME: Sa fety inlection SYSTEM NUMBER: It' Valve i Valve Ca tego ry . l CSJ or - Mark Drawing Drawi ng Test Relief-Number Class NSA OM No. Coo rd. Requirement Request. Comments A B C D P 2 SIS *MOV8887A 2 X 0 11-1 F-7" QST OST 2.47.3Af 3B1-Stroke & Time f el 2 SIS *MOV8887B 2 X 0 11-1 E-8 QST' OST 2.47.3Af 381-St roke & Time (Q1 _ 2 SIS *MOV865A 2 X X jl, 11-2 F-4 POS OM 54 LOG L5-35 Position Verified' 2 SIS *MOV8658 2 X X 0 11-2 F-6 POS OM 54 LOG LS-35 Position. Verified 2 SIS *MOV865C 2 X X 0 11-2 - F-9 POS - OM 54 LOG L5-35 Position Verified 2 SIS *MOV867A 2 X S 11-1 B-2 QST OST 2.47.3Af3B1-Stroke & Time tot 2 SIS *MOV867B 2 X S 11-1 C-2 QST OST 2.47.3Af 3B1-Stroke & Time (Q) 2 SIS *MOV867C 2 X S 11-1 C-6 'QST OST 2.47.3ALJB1-Stroke & Time (Q) . _ _ LT 2BVT 1.47.11-Leak test (R) 2 SIS *MOV867D 2 X S 11-1 C-5 QST OST 2.47. 3Af 381-Stroke & Time ' f Ol - -l LT 2BVT 1.47.11-Leak Test (R) _ 2 SIS *HCV868A 2 X S 11-1 D-5 QST OST 2.47. 3Af 3B1-St roke &' T ime (Q) 2 SIS *HCV8688 2 X S 11-1 B-3 QST OST 2.h7.3Af3B1-Stroke & Time'fel 2 SIS *MOV869A 2 X 'S 11-1 A-3 QST CSJ26 OST 2.1.10-St roke & T ime (CSD) LT 2BVT 1.47 11-L?ak Test (R* 2 SIS *MOV8698 2 X S 11-1 B-3 QST CSJ26 OST 2.1.10-St roke & Time (CSDI LT 2BVT 1.47.11-Leak Test (Rl 2 SIS *AOV889 2 X S 11-2 F-1 QST OST'2.47.3Af2BI-Stroke & Time (Q) l. LT RRI.RR28 2BVT 1.47.5-Leak Test (R) 2 SIS *894 2 X 11-1 E-3 QS OST 2.11.1-FS.FD (Q) QS OST 2.11.2-FS.R0 (Q) 2 SIS *895 2 X 11-1 F-4 QS OST 2.11.2-FS.FD (Q1_ QS __ OST 2.11.1-FS.RD (Q) 2 SIS *MOV8809A 2 X O- ^11-1 E-1 QST OST 2.47.3Af 3Bl-Stroke & Time (0) - 2 X 0 11-1 C-1 QST OST 2.47.3Af 381-S+ roke & Time (Ol ' 2 SIS *MOyg&Q28 2 SIS *MOV8811A 2 X S '11-1 E-5 QST - 0ST 2.47.3Af 381-Stroke & Time f el.. 67- ISSUC 1~ REV 4 v- -i y 4 = .m~ g m a- 'l-r.,. , + e.. ....pg-eg y eg+ sh p. ,-.,w y p p- -yi-%.g=s.-g. min egs ., gre .Waei.F..,
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BVPS-2 .ST - VALVE. TESTING OUTLINE-SYSTEM NAME: Safety i n.iect lon__ . SYSTEM MUMBER: 11 Valve- - ' Valve . Category . CSJ or Mark . Drawing Drawing . Test Relier . . Number Class . NSA OM No. Coo rd . Requirement Request Comments-A B lC D P 2 SIS *MOV88118 2 X S 11-1 F-5 'QST OST 2.47.3Af381-Stroke & Time (Q) 2 SIS *MOV8888A 2 X 0 1 ' -1 E-8 QST' OST 2.47.3Af381-Stroke & Time (Q) Li- 2BVi 1.47.11-Leak Test (R) 2 SIS *MOV88888 2 X 0 11-1 G-8 QST 'OST 2.47 1Af3Bl-Stroke & Time'(0) Li 28Vi 1.47.11-Leak Test (R) 2 SIS *MOV8889 2 X S 11-1 F-8 OST CSJ27 'OST 2.1.10-Stroke & Time fCSDI LT 28VT 1.41.11-Leak Test IRI _2_ SIS *MOV8890A 2 X S 11-1 F-te QST OST 2.47.3Af381-Stroke & Time fol 2 SIS *MOV88908 2 X S 11-1 F-4 QST OST 2.47.3Af3BI-Stroke & Time (Q) _2S;S*RV8864A 2 X 11 - F-7 SPT 28VT 1.60.5-fR1
.9 2 SIS *RV88648 2 X 11-1 G-6 SPT 2BVT 1.60.5-t '
J2S.l S*RV8865 2 X 11-1 F-7 'SPT E3VT 1.60.5-fR) 68 ISSUE 1-REV 4
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' VALVE TESTING OUTLINE SYSTEM MAME: Gaseous Nitrogen -SYSTEM NUMBER: _11, i
Valve Vanve ' Catego ry . CSJ or Ma rk D rawing D rawing Test Relier-Number Class MSA OM No. Coo rd . Requirement Request- Comments A B 'C D P . 2GNS*A0V101-1 2 X n '11-2 C-3 QST OST 2.47.3A[JBI-Stroke & Ties (01 ' l-LT RR1 2BVT 1.47.5-Leak Test (R) 2GNS*AOV101-2 2 X 0 11-2 C-3-. QST DST 2.47.3Af 381-St roke & Time (0) l; LT RR1 2BVT 1.47.5-Leak Test (R) 2CNS*SOV853A 2' X S 11-2 D-4 'QST OST 2.47. 3Af 381-St roke & Time f el - , 2CNS*SOV853B 2 X S 11-2 C-6L QST _0ST 2.47.3Af 3B1-st rote & Time f 01 2GNS*SOV853C 2 X S 11-2 C-9 QST OST 2.47.3Af 3Bl-Stroke & Time (Q t 2GNS*SOV8530 2 X S 11-2 C-4 QST OST 2.47.3Af 381-Stroke & Time (Q) 2CNS*SOV853E 2 X S 11-2 C-6 QST OST ' 2.47.3Af 3B1-St roke & T ime f 01 2CNS*SOV853F 2 X S 11-2 0-9 QST OST 2.47.3Af 381-Stroke & Time f 01 2GNS*.SOV854A 2 X S '11-2 C-2 QST OST 2.47.3Af 381-Stroke & Time (Q1 2GNS*SOV854B 2 X S 11-2' D-2 QST OST 2.47.3Af 381-Stroke & Time IQI a 4 69 - ISSUE 1
. REV 4 y-- nr w w=w>y-.y iscg : .,ge- -, r .- ,s,--<*-+ r -- ~w p-w j ga a _a_-.2 ._e 3
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'BVPS-2 IST VALVE TESTING OUTLINE SYSTEM NAME: Containment vacuum SYST0M NUMBER: '12
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Valve Valve Catego ry . CSJ or ' - j-Mark Drawing' Drawing . Test . Relief . . Number Class NSA OM No. Coo rd. Requirement Request Comments A B C D P 2CVS*93 2 X X 12-1 E-2 QS RR13 2BVT 1.47.5-FS.RD (R) LI RR1- 2BVT 1.47.5-Leek Test (R) 2CVS*SOV102 2 X 0 12-1 E-3 QST CSJ 52 ' OST 2.1.10-Stroke & Time (CSDI Li JR1 2BVi 1.47.5-Leak Test (R) 2CVS*151 2 X X LS 12-1 A-2 LT RR*,RR2' 2BVT 1.47.5-Leek Test' (R) 2CVS*151-1 2 X X LS 12-1 A-3 LT RRI.RR2 2BVT 1.47.5-Leak Test (R) .. 2CVS*SOV151A 2 X 0 12-1 C-4 QST OST 2.47.3At 3BI-Stroke & Time i01 l LT RR1 2BVT 1.47.5-Leak Test (R)
~
2CVS*SOV151B 2 X 0 12-1 0 QST OST 2.47.3A( 381-Stroke & Time f GI l LT RR1 2BVT 1.47.5-Leak Test (R) lI 2CVS*SOV152A 2 X 0 12-1 C-5 'QST OST 2.47. 3Af 3B1-St roke & Time (Ol ' LT RR1 2BVT 1.4T.5-Leak Test (R)
~
2CVS*SOV152B 2 X 0 12-1 D-4 ~ QST OST 2.47.'3At 3Bl-St roke & Time (Q) l' LT RR1 2SVT 1.47.5-Lesk T'e:t (R)- 2CVS*SOVtS3A 2 X O 12-1 F-3 QST CSJ52 OST 2.1.10-St roke & T ime (CSD) ~ LT RR1 2BVT 1.47.5-Leak Test (R) 2CVS*SOV153B 2 X ~O 12-1 F QST CSJ52 OST 2.1.10-Stroke & Time (CSDI LT RR1 2BVT 1.47.5-Leak Test (R) 70- ISSUE 1
.REV 4
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SYSTEM NAME: Leak Monitorina . SYSTEM hUMBER: 12' Vaive Valve Ca tego ry - CSJ or -
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Mark , Drawing . Drawing . - Test Retler-Number Class NSA OM No. Coord. l Requirement Request Comments A 8 C D P 2LMS*51 2 X X SS- 12-2' E-6 LT RR1 2BVT 1.47.5-s_eak Test'(R) 2LMS*52- 2 X X SS 12 E-6 LT- RR1- 2BVT 1.47.5-Leak Test (R) 2LMS*SOV950 2 X X 0 12-1 F-9 NA NA > 2LMS*SOV951 2 X- X 'O 12-1 E-9 NA NA ' 2LMS*SOV952 2 X X 0 12-1 C-9 NA' NA ' 2LMS*SOV953 2 X X O 12-1 B-9 -8tA NA
'71 8SSUE 1-
- REV 4
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4 - VALVE TESTING OUTLINE ~ - SYSTEM NAME: Quench SpraV -SYSTEM NUMBER: 13 Vaive ~ ' Valve Category CSJ or. " Mark Drawa ng Drawing - Test- Relief' Number Class NSA OM No. Coo rd. Requirement Request- Comments " AjB C D' P _ 2QSS*3 2 X X '13-2 LE QS' CSJ28 OST 2.1.10-FS.TD.R0 (CS01 LT- RRI.RR2- 28VT 1.47.5-Leak Test-(Rn . 2QSS*4 2 X X 13-2 C-9 QS CSJ20' OST 2.1.10-FS.FD.RD (CS01' LT RR1.RR2 28VT 1.47.5-Leak Test (RI 20SS*MOV100A 2 X 0 13-2 A-8 QST OST 2.47.3Af381-Stroke & Time (Q) 20SS*MOV1008 2 X 0 13-2 G-8 QST OST 2.47.3Af381-Stroke & Time (01' 2QSS*SnV100A 2 X S 13-2 0-7 QST C3.;29 OST 2.1.10-Stroke & Time (CS01 LT RR1.RR27 2BVT 1.47.5-Leak Test (R)
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2QSS*SOV1008 2 X S 13-2 E-7 QST' CSJ29 OST 2.1.10-Stroke & Time (CSDI LT RR1.RR27 2BVT 1.47.5-Leak Test (R) 2QSS*MOV101A 2 X 0 13-2 C-9 QST OST 2.47.3Af381-Stroke & Time (Q1 li
- t. T IN).RR2.RR28 28VT 1.47.5-Leak Test iR1 2QSS*MOV1018 2 X 0 13-2 D-9 QST OST 2.47.3Al381-Stroke & Tlme'fG1 l -.
L T -- RR1.RR2.RR28 28VT 1.47.5-Leak Test iR1 2QSS*RV101A 2 X- X 13-2 C-9 SPT' 28VT 1.60.5-fR1 - LT RRt.RR2.RR28 28VT 1.47.5-Leak Test (R) 2QSS*RV1018 '2 X X 13-2 E-9 SPT 2 PVT-1.60.5-IRI' L1 RR1.RR2.RR28 2BVT 1.47.5-Leak Test iR1 _2E S*SOV101A 2 X 0 13-2 D-7 QST OST 2.47.3Af3BI-Stroke'& Time (QI OST 2.47.3Af381-Stroke & Time (Q) 20SS*SOV1018 2 X 0 13-2 E-7 QST
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2QSS*MOV102A , X S 53-2 "B-5 QST OST 2.47.3Af381-Stroke & Time (01' 2QSS*MOV1028 /, X S "13-2 E-5' '-OST OST-2.F7.3Af381-Stroke f & Time (01' 20SS*RV102A 2 X 13-2 C-6 SPT 28VT 1.60.5-IR) 20SS*RV4026. ; 2 X 13-2 E-6 - SPT 2BYT 1.60.5-(R) _ ' OST 2.47.3Al381-Stroke,1 Time'(Q) 2 X 0 13-2 D-7~ QST 20SS*SOV10.N 0 13-2 E OST OST 2,47.3A QBI-StrgkA p T.,,pa i (0) 2C5S*SOV1028l 2 X ~ l l ' 72 - CSSUE 1
' REV 4 '
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SVPS-2 .8T: VAtVE TESTING OUT1.INE SYSTEM MAME: Recireueation Sc, ray SYSTEM ffUMBER: 13 Valvv Valva Category CSJ or Mark Drawing Drawing Tert Relief Number Class NSA OM 900. Coord. Requirement Regaest Coauments A B C D f* 2RSS*29 2 X 13-1 B-2 QS CSJ31 OST 2.1.10-FS.FD (CSDI 2RSS*30 2 _ __ X 13-1 B-9 QS CSJ31 0ST 2.1.10-FS.FD (CSDI 2RS!*31 2 X 13-1 B-4 QS CSJ31 OST 2.1.10-FS.TD (CSDI 2RSS*12 2 X 13-1 B-7 QS CSJ31 OST 2.1.10-FS.TD (CSD) 2RSS*RV101C 2 X 13-1 C-4 SPT 2BVT 1.60.5-(R) 2RSS*RV101D 2 X 13-1 C-7 SPT 2BVT 1.60.5-fR) 2RSS*MOV154C 2 X S 13-t C-4 QST OST 2.47.3A(3_B1-Stroke & Time (QI 2RSS*MOV154D 2 X S 13-1 C-7 QST OST 2.47.3Af 381-Etroke_4 Time (G) 2R5S*MOV155A_ 2 X 0 13-1 G-4 QST OST 2.47.3At3BI-Stroke & Time 101 2RSS*MOV15$8 2 X 0 13-1 C-7 QST OST 2.47.3Af3B1-Stroke & Time (0) 2RSS*MOV155C 2 X 0 13-1 F-5 QST OST 2.47.3AO BI-Stroke & Time tel 2RSS*MOV1550 2 X 0 13-1 F-6 QsT OST 2.47.3A(JBI-Stroke & Time _ig! 2RSS*MOV156A 2 X e 13-1 B-2 QST OST 2.t7.3A(3DI-Stroke _k Time (Q) 2RSS*MOV156B 2 X 0 13-1 B-9 CST OST 2.47.3At381-Stroke & Time tOI 2RSS*MOV116C 2 X 0 13-1 B-4 QST OST 2.47.3Ai391-Stroke & Time f el 2RSS*MOV156D 2 X 0 13-1 0-7 QST _OST 2.47.3Af381-Stroke & Time 101 2RSS*RV156A 2 X 13-1 B SPT 2BVT 1.60.5-fR1 2RSS*RV1568 2 X 13-1 B-9 SPT 2BYT 1.60.5-fR) 2RSS*RV156C 2 X 13-1 6-4 SPT 2BVT 1.60.5-fR1 2RSS*RV156D 2 X 13-1 B-7 SPT l 2BVT 1.50.5-tRI 74 ISSUE 1 REV 4 i
. _ _ _ _ .. - ~ _ _ _ _. -. :_._...__ _. _ _ _ . _-. - . _ . , - - _ _ .
SvPS-2 IST VALVE TESTING OUTLINE SYSTEM MAME: Reactor Plant Semple SYSTEM NUMBER: 14A ' Valve .. Valve Ca tego ry CSJ or Mark Drawing Drawing Test Relief Number Cidss RSA OM Mo. Coord. Requirement Request Comments Al 8 C D P , 2SSR*A0V100A-1 2 X 0 14m-1 C-9 QST OST 2.47.3A1381J-S rohe & Tlee tel l LT RR1 2BVT t.4T.5-Leek Test _fR1 __ 2SSR*A0V100A-2 2 X e 14A-1 D-9 QST OST 2.47.3A(18)J- troke g Time tel l Li RR1.RR28 2FYi 1.47.?-teak Test (R) 2SSR*ADV102A-1 2 X O 14A-2 C-1 QST OST 2.47.3Aj)BO-roke 3 Time fel l Li RR1 28Vi 1.4 7.5-Leak Test (R) 2SSR*ADViO2A-2 2 X O 14A-2 D-1 QST OST 2.4T m 3A1]pdf- troke g Time ti? !! s LT RR1.RR28 2BVi 1.41.5-Leek. Test (R) 2SSR*A0V109A-1 2 X O 14A-1 C-7 QST OST 2.47.3A(J8] J-S roke & Time (Q) -l Li RR1_ 2SVT 1.47.5-Leak Test (R) 2SSR*AUV109A-2 2 4 0 14A-1 D-7 QST OS_T 2.47 2 ]ALJB1-Stroke & Time tel l LT RM1.RR28 29VT 1.47.5-Leak Test _tRI PSSR*AOV112A-1 2 X O 14A-1 C-8 QST OST 2.47.3AL18]-Stroke & Time fel I Li RR1 2SVT 1.47.5-Leek lest (R) 2SSR*A0V112A-2 2 X D 14A-1 D QST OST 2.4L 3A118J-Stroke t Time _ t01 l~ LT RRt.RR28 2SVT 1.41.5-Leek Test (R) 2SSR*ADV117A 2 X 0 14A-1 8-2 QSY OST ?.47.3At 381- Stroke & Time f el 2SSR*AOV117B 2 X 0 14A-1 6-4 QST OST 2.47.3At 381-Stroke &_ Time 101 2SSR*A0V117C 2 X 0 14A-1 B+5 QST OST 2.47.3At 3BI-Stroke & Time f el 2SSR*RV117 2 X X 14A-1 D-7 SPT 28VT 1.60.5-(Rl LT RRI.RR28 2BVT 1.41.5-Leak Test (R) 2SSR"RV118 2 X X 14A-2 C-1 SPT 2BVi 1,60.5-(R) LT RRI.RR28 28VT 1.4T.5-Leak fest (R) 2SSR*RV119 2 X X 14A-1 D-9 SPT 28VT 1.60.5-IR1 LT RR1.RR28 28VT 1.47.5-Leek Test (R) 2SSR*RV129 2 X X 14A-2 C-2 SPT 28VT 1.60.5-{R1 Li RR1.RRR8 28VT 1.4T.5-Leak Test (R3 2SSR*RV121 2 X X 14A-1A O-8 SPI 28YT 1.$Q.5-(R) Li RR1.RR28 2BVT 1.47.5-Leak fest (RI 75 ISSUE 1 REV 4
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BVPS-2 .4T VALVE TESTING OUTLINE j SYSTEM MAME: Reactor Pf ar.t Sample SYSTEM HUMBER: 14A Valve. Valve Category CSJ or Mark Drawing Drawing Test Reller Number Class MSA OM Mo. Cooro. Requirement Pequest Commsmts A 8 C D P 2SSR*RV122 2 X X 14A-2 C-3 SPT 2BVT 1.60.5-(R) LT RR1.RR28 2BVT 1.4T.5-Leak fest (R) PSSR*SOV128A-1 2 X 0 14A-2' B-3 QST OST R.47.3 A[18J-Stroke .g Time (ql l~ LT RR1 2BVi 1.41.5-Leek fest (R) 2SSR*SOV128A-2 2 X 0 14A-2 D-2 QST OST 2.4 7. 3 AL181-St robe _g,1171 (Q) l LT RR1.RR28 2BVT 1.47.5-Lee-k Test (R) 2SSR*SOV129A-1 2 X 0 14A-2 B-4 QST OST 2.47.3All_81-Stroke & Time 101 l Li RR1 2SVT i.47.5-Lesfiest (R) 2SSR*SOV129A-2 2 X 0 14A-2 D-2 QST OST 2.47.3AL)SJ J-S roke 4 Tlee (Ci l Li RRI.RR28 2UYi 1.4T.5-Leek Test (R) 2SSR*SOV130A-1 2 X 0 14A-2 B-10 CST OST 2.47.3A118J StrA.ce & Time tel l
' Li Rat 29VT 1.4T.5-Lese lest (Rt 2SSR*SOV130A-2 2 X 0 14A-2 C-10 QST -
OST 2,4T2 )A[381-Strohe_4 Time fel l Li RR1 28VT 1.4T.5-Leah Test (R) 76 ISSUE 1' REV 4
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v- - A, BVPS-2 iST VALVE TESTING OUTLIIDE- c SYSTEM MAME: Post-Accident Sample' SYSTEM IIUMBER: 14C
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Vaive Valve Category CSJ or Mark Drawing . Drawing Test Retier-Ntrebe r C1 ass NSA OM feo. Coord. Requirement
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Request Comments A B C D P 2 PAS *SOV105A-1 2 X S 14C-2 A-2 QST RR1 OST 2.47.3AU S)-Stroke 4 Ties tel 2BVT 1.47.5-tesk Test fell l. LT l
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2 PAS'SOV105A-2 2 x S 14C-2 .A-3 QST OST 2.47.3AD R1-11ro _ke Tless iet LT RM1 28VT 1.4 T.5-Leek Test ( ) I 77 ISSUC 1
- REV 4 '
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e BVPS-2 IST VALVE TESTimo OUTLtME s SYSTEM NAME: Component Coolino SYSTEM NUMBER: 15 Valve Valve Category CSJ or Mark Drawing Drawing Test Relief Numbe r Class MSA OM No. too rd. Requirement Request Comments A 6' C D P 2CCP'" 3 X 15-1 8-5 QS CST 2.15.1-FS.FD RO tel 2CCP*5 3 X 15-1 F-5 QS OST 2.15.2-FS.fD.RO fel _2CCP*6 3 X 15-1 D-5 QS OST 2.15.3-FS.FD.RD.fG1 2CCP*2TA 3 X 0 15-1 C-6 QS OST 2.15.1-Stroke Only 101 2CCP'27B 3 X 0 15-1 E-6 QS OST 2.15.2-Stroke Only (Q1 2CCP*RV102 2 X X 15-2 D-4 SPT 28VT 1,6Q,}-1RJ LT RRI.RR2.RR28 2BVT 1.47.5-Leak Test (Rl 2CCP*RV103 2 X X 15-2 0-5 SPT 28VT 1,60.5- t R 1' LT RR1.RR2.RR28 2SVT 1.4L 5-Leak Test (R) 2CCP*RV10t 2 X X 15-2 D-4 _ SPT 28VT 1.6t.5-fRI Li RR1.RR2.RR28 2FYI_1.4's.5-Leak Test (R) 2CCP*RV105 2 X X 15-2 E-4 SPT 28VT E1-j R ) L1 RRI.RR2.LR28 29VI 1.4T.5-Leak Test (Ri 2CCP*AOV107A 3 X 0 15-3 C-5 QST CSJ32 OST 2.1.10-Stroke, Time & Fall Closed (CSDI 2CCP*A0V1078 3 X 0 15-3 F-5 QST CSJ32 OST 2.1.10-Stroke, Tlee & Fall Closed (CSD) 2CCP*A0V10TC 3 X 0 15-3 F-10 QST CSJ32 OST 2.1.10-Stroke, itse & Fait Closed (CSDI 2CCP*MOV112A 3 X S 15-2 D-8 QST OST 2.47.3AL}81-Stroke & Time (Q1 _2CCP*MOV1128 3 X S 15-2 F-9 QST OST 2.47.3At 381-Stroke _t Time tel
. 2CC P*RV116A 3 X 15-3 C-2 SPT 28VT 1.60.5-IRI 2CCP*RV116B 3 X 15-3 F-1 SPT 28VT 1.60.5-tR) 2CCP*RV116C 3 X
- 15-3 F-6 SPT 28vi 1.60.5-(R) 2CCP'MOV115 3 X 0 15-2 I _E. 4 QS7 OST 2.47.3A(J8J-Stroke & Time (91 2CCP*MOV119 3 IXi 0 15-2 C-2 QST 00T 2.47.3Af381-Stroke & Tlee 101 78 ISSUE I REV 4
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r BVPS-2 eST VALVE TESTsNG OUTLINE SYSTEM NAME: Component Cooling .-YSTEM NUMBER: 15 i Valve Valve Category CSJ or M;rk Drawing Drawing Test Relief'- Number Class !tSA OM 900. Coord. Requirement Request Comments A' 8 C D P ECP*MOV176-1 3 X 0 15-5 A-5 QST OST 2.47.lAf381-Stroke & Time tel PCCP*MOV176-2 3 X 0 15-5 A-5 QST OST 2.47.3ftL381-Stroke & Time del 2CCP'MOV177-1 3 X 0 15-5 G-5 QST OST 2.47.3At3BI-Stroke & Time 10. 2CCP'MOV177-2 3 X 0 15-5 G-5 QST OST 2.k7.3Af381-Stroke t Time tel PCCP*MOV178-1 3 X O 15-5 G-5 QST. OST 2.47.3Af3BI-Stroke & Time (Q1 2CCP*MOV178-2 3 . __1 0 15-5 G-5 QST OST 2.47.3A(381-Stroke & Tlee 101 2CCP*289 3 X 15-3 C-1 QS RR*4 28VT 1.60.6-FS.R0 (R) 2CC P*290 3 X 15-3 T-1 QS RR14 28VT 1.60J d s.RD (R) 20CP'299 3 X 15-3 F-6 QS RR14 28VT 1.60.6-FS.RD (R) X 0 15-1 8-0 05 OST 2.15.1-stroke Only (Q) 2CCP'321 3 2CCP*322 3 ?. O 15-1 r-3 QS VST 2.15.2-Stroke only (0) 2CCP*323 3 X 0 15-1 C-3 QS OST 2.15.1-Stroke only (0) X 0 15-1 E-3 QS OST 2.15.2-Stroke Only (0) 2CCP*32*: 3 1 3 X 0 15-1 C-3 QS OST 2.15.1-Stroke Only (Q) _?CCP*J25 3 X 0 15-1 E-3 Q$ OST 2.15.2-Stroke Only (QI E Cf*}26 X 15-2 A-2 QS RRIS 28VT 1.60.t,-FS.RD (R)- 2CCP*352 3 2CCP*354 3 X 0 15-1 E-8 QS OST 2.15.2-stmke Onlyj Qi X O 15-1 D-9 QS _ OST 2.15.1-Stroke Onfy IQl 2CCP*355 3 , 80 ISSUE 1 REV as
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BVI-S-2 IST _ VALVE TESTIIeG OUTLINE
~
SYSTEM ftAME: Fuel Pool Cool itus - SYSTEM peUMBEP: 20 Valve vatve Ca tegory .
. CSJ or Mark Drawing Drawing Test Relief Number CIass MSA OM 800 Coo rd. Requirement Reguest Comuments
__.A B C D F._ j , 2fMC+9 2 X X LS 20-1 E-2 LT- RR1.RR2 29VT_1.47.5-Leak Test (R) 2FNC*38 2 X X LS 20-1 E-2 LT RR).RR2 29VT 1.47.5-Leak Yest fM1 2FNC'121 2 X X LS 20-1 D-2 LT RRt.RR2 29VT 1.47.5-Lesk Test (R) 2FNC*122 2 X X . LS 20-1 i F-2 LT RRI.RR2 29Vf 1.47.5-Leak Test (R) 81 8SSUE 1 REV 4
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- 1 1 1 A B C 2 2 2 A r C A B C A E 0 0 0 1 1 I 0 0 1 0 21 2 2 3 3 3 4 M 1 1 1 0 0 O 1 0 0 0 0 0 0 0 A V V V 1 1 t V V V 1 1 1 1 1 1 1 M 8 9 O O 0 O V V V O O O V V V V V V V r 1 1 2 A A A S S S A A A S S S S S S S M e e * * * * * * * * * * * * * * * * * *
- E vkb S S S S S S S S S S S S S S S S S S S T
S l aau rm S M S M S M S M S M S M S S MM S M S M S M S S M M S S MM S M S M S S MM Y VMN 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 _ S 2_
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._ o SVPS-2 iST VALVE TESTINC OUTI.INE SYSTEM MAME: _ Main Steam SYSTEM NUMBER: A Vaive va4ve Ce tegt. ry ,
Mark CSJ or " Number Class-Drawing Drawing Test Relief' NSA OM No. Coord. Requirement Request A B C D P Comments 2 MSS *SV1048 2 X 21-1 _ C-4 ^SPT 28VT 1.21.1(21-tR1 2 MSS *SV104C 2 X 21-1_ , A-4 SPT 28VT 1.21.1(21-tRI 2 MSS *SOV105A 2 X S 21-2 D-1 QST OST 2.24.4-Stroke & Time fel _ 2 MSS *SOV1058 2 4 __ _jd_Jh2 C-2' QST OST 2.24.4-Stroke & Time (Gl 2 MSS *SOV105C 2 t 3 S . 21-2 A-1 QST OST 2.24.4-Stroke & Time.f01 4 2 MSS *SOV10$Q 2 'X S 21-2 D-2 Obi OST 2.rt.4-Stroke & Time 101 2 MSS *SOV105E 2 X S 21-2 C-2 QST OST ?.24.4-Stroke & Time (Q)
.gMSS*SOVIOSF 2 X S 21-2 A-2 QST OST 2.24.4-Stroke 3: Time fel 2 MSS *SV105A 2 X 21-1 F-3 SPT 28VT 1.21.1(21-1R_1 2 MSS *SV105B 2 X 21-1 C-1 SPT 28VT 1.21.1(21-(R) ?*tSS*SV105C 2 X 21-1 A-3 SPT 28VT 1.21.1t21-(R) 2 MSS *196 3 X 21-2 0-3 QS RR16 28VT 1,60.6-FS.RD (R)
QS CSJ34 OST 2.24.4-PS.fD (Mi/FS.fD (CSDI 2M O *199 3 X 21-2 C-3 .. . QS RR16 QS CSJ34 2BVT 1 60 1-T1 R0_(RI OST_2.24.4-PS.fD iM1/FS.7D iCSDA 2 MSS *352 3 n 21-2 A-2 QS RR_16 2Byi 1. 60. 6-F S RD ( R ) I 2 QS CSJ34 OST 2.24.4-PS.fD (MI/FS.ftr iCSD) i 83 8SSUE 1 REV 4
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BVPS-2 IST VALVE .ESTIIF; 00TLINE - SYSTEM NAME: Steam Drain SYSTEM 80 UMBER: 21 Valve Vaive l Category CSJ or Mark Drawing Drawing Test Relief'. Number C: ass NSA OM 900 Coord. ' Requirement Request Comments A 8 C D P 2SDS*A0V111A1 2 X 0 21-3 8-4 QST OST 2.47.3At381-stroke & Time (01 2SDS*ADV111A2 2 X 0 21-3 8-4 QST OST 2.47.3At381-Stroke & Time fel 2SDS*AOV11181 2 X 0 21-3 , 8-6 QST OST 2.47.3Af381-Stroke & Time fel 250S*A0V11182 2 X 0 21-3 8-6 QST OST 2.47.3A(381-Stroke & Time (QI 2SDS*A0V111C1 2 X 0 21-3 B-8 QST OST 2.47.SA(!B1-Stroke & Time fel _2SDS*A0V111C2 2 X 0 21-3 8-8 QST OST 2.47.3At381-Stroke & Time tel 2SDS*AOV129A_. 2 X 0 21-3 C-1 QST OST 2.47.3AL181-Stroke & Time f el 2SDS*A0V1298 2 X 0 21-3 8-1 QST OST 2.47.3Af381-stroke & Time fel l 84 ISSUE 1-REV 4
b 9 1 - Eas U Sy - SE 1 R - I l I I D O D D S S S S . C C C C ( ( ( ( _ e e e c . I ) I i m i m i s i m 1D )D )D T T T T RS RS RS r s C (C (C a t a t e a t t ( ( ( n e JO RD D D k e k e k e k e m R. D R.Df o o c o - _ m Sf. SF. S . r r e r o FS FS FS S t t S S t t S C .
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_' _j BVPS-2 iST VALVE TESilffC OUTLINE SYSTEM MAME: Auxiliary Feedwater SYSTEM feUMBFR: R4 VaIve Valve Category Mark CSJ or Drawing Drawing Test Reflef' Number Casss MSA' OM No. Coord. Requirement Request Comuments Al8 C D!P 2FWE*42A 2 X 24-3 A-8 QS CSJ40 OST 2.24.6-FS.FD RD (CSDI 2FWE*42B 2 X 24-3 8-8 . QS CbJ43 OST 2.24.6-FS.FD.RO (CSD) 2FWE*43A 2 X 24-3 C-8 QS CSJ40 OST 2.24.6-FS.FD.RD (CSDI 2FWE*43B 2 X 24-3 C-8 QS CSJ40 OST 2.24.6-FS.FD.R0 (CSDI 2FWE*44A 2 X 24-3 D-8 CS C?J40 OST 2.24.6-FS.FD.RD (CSDI 2FWE*44B 2 X "i-3 E-8 , QS CSJ40~ OSF 2.24.6-FS.FD RD (CSDI 2FWE*90 3 " LS .-3 D-2 QS OST 2.24.1-Stroke On'y (M) 2FWE*91 3 X LS _24-3 L-2 QS OST 2.24.1-Stroke Only (Mt
.lF_WE*92 3 X LS 24-3 F-2 QS OST 2.24.1-Strole Onist (Mt 2FWE*99 2 X 24-3 B-10 .___ _ . OS RR19 I QS CSJ41 OST 2.24.6A-FS.R(L1R]
1 OST 2.24.6-FS.FD (CSDI 2FWE*100 2 X 24-3 C-10 RR19 QS OST 2,24.8A-FS.RDJ R1 QS CSJ41 OST 2.24.6-FS.FD ICSD1 2FWE*HCV100A 2 X 0 24-3 D-7 QST OST 2.24.1-Stroke jr Time (fil 2fWE*HCV100B 2 X 0 24-3 E-7 QST OST 2.24.1-Stroke & 'ime (QI 2FWE*HCV100C ? X C 28t-3 C-7 OST OST 2.24.1-Stroke & Time (Q1 2FWE*HCV1000 2 X 0 24-3 C-7 QSi OST 2,24.1-Stroke & Time (Q) 2FWE*HCV100E 2 X 0 24-3 A-7 QST OST 2.24.1-Stroke & Time.f01 2FWE*HCV100F 2 X.. _O 24-3 B-7 QST ' OST 2.24.1-St roke & Time (Q1 2FWE*SOV10e* 3 X X S 24-3 D-2 NA 86A 2FWE*SOV1008 3 X X S 24-3 D-2 MA NA-2FWE*101 2 X 24-3 E-10 QS RR19
. _ Q3 CSJ41 .I OST 2.2L8A-t S.RD iRI ._
OST 2.24.6-F S.FD TCSDI l 2FWE*RV101 3 X 24-3 D-5 _ _ . _ _ SPT 29VT 1.6G.5-(R) l 87 ISSUE 1 i REV 4 i
*G
< =
e w-
-BVPS-2 fST ._
VALVE TESTING OUTLINE SYSTEM NAME: Auxiiisrv Feedwater . SYSTEM MUMBER: 24. Valve i Valve Category . CSJ or Mark Drawing Esawing Test Relief Number Ciass NSA OM No. Coo rt!. Requirement Request Coassents A' B C D' P 2FWE*FCV122 3. X 24-3 E-S 95 OST 2.24 4-FS Open IMI (Note 1) QS CSJ42 OST 2.24.4-FS Closed l_C301 X QS CSJ42 __OST 2.24.4-fS.fpl CSq l QS CSJ42 OST 2.24.6-FS.RD ICSD I 2FWE*FCV123A 3 X 24-3 F-6 _ .QS ;_ OST 2.2 h2-?S Open (MI ( L ,ie 1 ) QS CSJ42 ('ST 2.24 trS Cigsed 1 C501 X QL CSJ42 OST Zo2 h tfSd Dj CSOl QS CSJ42 Osi 2.24.6-fS.RD (CSD i 2FWE*FCV1233 3 X 24-3 G-6 QS OST 2.24. 3 _FS Op_en__LM] (Note 1) _ _ _ QS CSJ42 OST 2,24 f-FS Closed I CSO) x QS CSJ42 OST 2. ME -t S. I D (CW l QS CSJ42 05T 2.24 t-JS.RD ES0I Note 1: Yarway automatic recirculation control volve acts as bo h a flow control valve and check valve. i f a gg ISSUE 1 REV 4
-ql f
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e e e e e t t 9 ( t f t 0 1 Q e f e fe t
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' BVPS-2 57 VALVE TESilleG OUTt_IIeE SYSTEM MAME: _Auxilitry Stese sysTLM 3eungER: _ g 7.. '
~
Vaive ~ vafwe- Category Ma rk CSJ or Mumber Class Drawing Drawing . Test Relief' MSA opt No. Coord. Requirement Reque*1t ' -J A B C 0 P Comments. 2 ASS *AOV130A 3 X 0 2 ? T-4 QST 2 ASS *AOV1300 OST 2.47.3Af3Cl-Steeke & Ties fel 3 X 0 27A-1 I F-4 QST OST 2.47.3Af381-Stroke a Time fel 4 90-
. ISSUE 1 REV 4
>s.
a
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, ,_q SVPS-2'IST val.VE TEST 180G OUTLINE SYSTEM MAME: Service Water SYSTEM petr9BER: 30 ..
VaIve vaive Catege n CSJ or Mark Drawing Drawing Test Relief Number Class NSA OM No. Coord. Requirement Reques.t Coeusents A B C DjP . 2SWS*29 3 X 39-2 D-5 QS OST 2.7.6-FS.FD (Q) 25WS*$7 3 X 30-1 C-3 qs CSJ43 OSY__LJ0.2-FS.TD_{Q cr CSDI QS CSJ 4 '. CST 2.30.6-FS.RD (Q cr CSDI 2SWS*S8 3 x
- 30-1 D-4 QS CSJ43 ___ CS T 2, 230 3- F S, T Dj Q o r CSD)
QS CSJ43 ._ OS T 2. 30.6-FS.RD ( Q or CSDI 2SWS*59 3 X 30-1 G-3 QS CSJ4! CST 2.30.6-FF.f D.RD (Q or CSD) 25WS*MOV102A 3 X 0 30-1 C-4 QST CSJ44 OST 2.30.fs-Stroke & Time f 0 or CSDI
~
2SWS*MOV1028 3 X 0 30-1 D-4 QST CSJ44 OST 2.30.6-Stroke 4. Time IQ or CSD3 2SWS*MOV102C1 3 X S 3 t+- 1 G-4 QST CSJ44 OST 2.30.6-Stroke & Time 10 or CSDI 25WS*MOV102C2 .5 X S 30-1 G-4 QST CSJ44 OST 2.30.6-Stroke & Time 10 or CSDI 2SWS*MOV103A 3 X S 30-1 C-7 QST RR20 OST 2.30.13-Stroke _t Time (Rt 25WS*MOV1038 3 X S 30-1 C-6 QST RR2O OST 2.30.13-Stroke..& Time IRI 25WS*MOV104A 3 X 0 *0-3 A-1 Q3T OST 2.t6(.3AU BI-Strche & Time (Q1 _25WS*MOV1048 3 X 0 30-3 E-1 QST OST 2.47.3Af3BI-Stroke a Time (ql 2SWS*MOV104C 3 X 0 30-3 C-1 QST OST 2.47.3Af381-Stroke & Time fel 2SWS*MOV104D 3 W O 30-3 0-1 QST OSY 2.47.3Af 381-stroke e Time (Q1 . 2JW3*Moy_105A 3 X 0 30-3 A-2 QST OST 2.47 3AJJBI-Stroke & Tirs (QI 2SWS*M W1058 3 X 0 30-3 E-2 QST OST 2.4T.3Af3BI-Stroke & Time.fel 2SWS*MOV105C 3 4 0 30-3 C-2 O*T OST 2.47.3Af3BI-Stroke t J oe fel 25WS*MOV105D 3 Xi O 30-3 D-2 QST 031 2.47.3AL381-Stroke & Time 101 l' I OST 2,30_JL3)(6J-gS,vD tot QS . 2SWS'106 3 X 30-1 A-6 QS RR29 OST 2.3%JJ-FS,fD [R1 QS CSJ45 OST 2.3C.8-FS.RD ICSD) 2SWS*MOV106A 3 X 0 30-1 C-7 QS; CSJ46 OST 2.1.10-Stroke & Time (CSD), Also ' durine OST_2.30.13-Stroke & Time (R3 91 ISSUE 1 REV 4
.=- -
1
'1 BVPS-E di VALVE TESilMG O'87LINE _
SYSTEM NAME: Service Water. SYSTEM 90 UMBER: $g , Vaive { Valve Category CSJ or Mark Drawing Drawing Test Relief
- Number Class NSA OM 900. Coord. Requirement Request Consertts A B C D P 2SWS*MOV1068 3 X 0 30-1 C-6 QST CSJ46 G5T 2.1.10-Stroke & Time (CSD), Also
*furine OST 2.30.13-Stroke & Time fRI QS_ . OST 2 J L2tU 161-PS,FD 101 2SWS*107 3 X 3'> ' A-7 QS RR29 OST 2.30.13-fS,FD_iRI QS CSJ45 OST 2.30.3-F S.RD (CSDI 23WS*MOV107A 3 X 0 30-1 F-7 QST CSJ47 OST 2.1.10-Stroke.t Time (CSDI 25WS*MOV1078 3 X 0 30-1 F-7 QST CSJ47 OST 2.1.10-stroke & Time ICSDI 2SWS*MOV107C 3 Xo O 30-1 F-6 QST CSJ47 OST 2.1.10-Stroke t Time (CSD) 2SWS*MOV107D 3 X 0 30-1 F-6 QST CSJ47 OST 2.1.10-Stroke e Time (CSD) 25WS*110 3 X X 30-2 C-8 NA *fInternet inspect ion se r CMP ( 5 vee rs 1]
4 2SWS*111 3 X 30-2 C-8 QS OST 2. 36.1- F S. F D ( M)
*ftoternet inspection ser CMP (5 weersl]
25WS*112 3 X 30-2 E-8 QS OST 2.36.2-FS,fn (M)
*fInternal Inspection _ per CMP f 5 veersil X X 30-2 E-8 NA 't Inte rna l Inspectio*. per CMP f 5 veers))
25WS*113 3 _ 2SWS*MOV113A 3 X S 30-2 C-8 QST OST 2.47.3Af381-Stroke & Time 101 l-2SWS*Mov1138 3 X X S 30-2 E-8 NA NA 3 X F S 30-2 C-8 90A stA__ 2SWS*MOV113C X S 30-2 E-8 QST OST 2.47.3Af381-Stroke & Time (Q) l 25WS*MOV1130 3 2SWS*/.JV118A 3 X 0 30-1 8-1 QST OST 2.30.1T* Stroke & Time fel 2,pdS*ACV1188 3 X .O 30-1 E-1 QST OST 2.30.17-Stroke & Time fel 25WS*FCV1204 3 X X 0 30-2 A-6 flA ISA 2SWS*FCV1208 3 X X O __30-2 G-6 NA ISA 25WS*SOV13DA 3 X A 30-1 A-4 QST OST 2,30.17-Stroke & Time fel Performed by CMP-2-75-CLOW CHECK-1M to verify valve ititegrity per IE OcIletin 83-03.
*Not required by ASME.
i 92 ISSUE 1 REV 4 l j
- m. k BVPS-2 IST s'
VALVE TESTimG OUTLINE SYSTEM MAME: Service Watel SYSTEM NUMBER: 30 Valve l Valve Catego ry I CSJ or Mark Drawing Drawirg Test Relier Number Class NSA OM Mo. Coord. Requirement. Request Comments A B' C D P 2SWS*SOV1308 3 X A 30-1 E-4 QST OST 2.30.17-Strokt & Time (01 25WS*142 3 X S 30-2 A-1 QS OST P sje.4-Stroke Open & Closed fGI 25WS*143 3 X S 30-2 F-1 QS OST 2.30.5-St roke Open & Closed (03___ _2SVS*MOV148A 3 X S 30-2 B-4 QST OST 2.47.3A( 3C1-Stroke & Time .tQl . _. 2SWS*MOV1488 3 X S 30-2 T-4 G1L, OST 2.47.3A(381-Stroke & Time (0) 25WS*RV152 2 X X 29-4 A-2 SPT 2BVT 1.p2 5-(R) LT RRI.RR2.RR28 20VT 1.4T.5-Leek Test (R)
~
25WS*MOV152-1 2 X 0 29-4 A-2 QST 93J 2.4MA[JB1-Stroke t Time (Q1 .. l LT RR1.RR2.RR28 2BVT 1.4T.5-task Test (R) 2SWS*MOV152-2 2 X 0 29-4 A-2 QST OST 2.47.3ALJBj-Stroke & Time (Q1 l LT RR1.RR2 zBvi 1.4T.S-Leek Test IRI 2SWS*RV153 2 X X 29 C-2 SPT 2BVT 1.60.5-fRl' LT RR1.RR2.RR28 2BVT 1.47.5-Leek Test (R) 2SWS*MOV153-1 2 X 0 29-4 C-2 QST OST 2.47.3ALJB1-Stroke & Time (Q) l LT RR1.RR2.RR28 2BVT 1.47.5-Leek Test (R) 2 X 0 29-4 C-2 QST OST 2.47.3At 381-Stroke & Time (01 l 25WS*MOV153-2 ' LT RRI.RR2 2BVT 1.4T.5-Leek Test (R) 25WS*RV154 2 X X 29-4 D-2 SPT g8VT 1.60.5-(R) LT RRI.RR2.RR28 2SVT 1.4T.5-Leek iest (R) 2SE *MOV154-1 2 X 0 29-4 D-2 QST OST A81,JALJB1-Stroke _& Time IQ1 l LT RRI.RR2.RR28 28Vf 1.4T.5-Leak Test (R) 2SWS*MOV154-2 2 X 0 29-4 D-2 QST OST 2.47,3A11BJ-St roke .t Time (Q) l LT RRt.RR2 2BVI 1.4T.S-Leek Test (Rl
~
PSWS*RV155 2 X X 29-4 G-2 SPT 28V( 1,60.5-(R) LT RRI.RR2iRR28 .jdf/T 1.47.5-Leek Test IRI 25WS*MOV155-1 2 X 0 29-4 G-2 QST QST 2<47 2 ]ALJBj-11roke & Time fGI l LT RR1.RR2 RC28.2BVT 1.4T.S-Leak itst TR) t 93 ISSUE 1-REV 4 e n , a , , , , , - , . , , e.- --
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s BVPS-2 IST VALVE TESTING DUTLINE SYSTEM NAME: Fi re Protection SYSTEM NUMBER: 33 Valve Valve Ca tego ry CSJ cr Ma rk Drawing Drawing Test Relief Number Class NSA OM No. Coord. Requirement Request. Comments A 3 C D P il 2FPW*AOV204 2 X S 33-10 C-4 QST OST 2.4?.3ALJ81-St roke & T_ime (QI l-LT RR1 2BVT 1.4T.5-Leek Test (Rt 2FPW*ADV205 2 X S 33-1D F-g QST OST 2.47.3 ALJB1-Stroke 4 Time (Q1 l LT RR1 2BVT 1.41.5-Leek Test.fR) 2fPW'AOV206 2 X S 33-ID D-4 QSi OST 2.47._3A( 381 Etroke t Time (0) l LT RR1 28VT 1.41.5-1?sk Test (R) 2F PW'A0V221 2 X S 33-1D A-4 QST OST 2.472JA[}8J-Stroke 4 Time COI l LT RR1 2BVT T.4T.5; Leak Test (Rt 2FPW*382 2 X X 33-10 C-4 QS CSJ49 OST 2.1.10-FS.fD.RD_[QSD) LT RR1 28VT 1.41.5-Leak Test (R) 2frW'388 2 X X 33-1D A-4 QS CSJ49 OST 2.1.10-FS.fD.RD (CSDI LT RR1 2BVT 1.47.S-Leon Test (R) 2FPW*753 2 X X 33-1D F-4 QS CSJ49 _OST 2.1.10-FS.FD,RD_{CSD) LT RR1 2BVT 1.47.5-Leek Test _(R) 2FPW'761 2 X X 33-1D D-$ QS CSJ47 OST 2.1.10-FS.f D.R9 ( CLDI LT RR1 2BVT 1.47.5-Leak Test (R) 96 ISSCE 1 REV 4 l l i l l L -
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BVPS-2'IST 3 i VALVE TESTING OUTLINE' SYSTEM MAME: Diesel Air Start SYSTEM NUMBER: 36 Vaeve Valve Category CSJ or Mark Drawing Drawing Tesa. ReIler Number Class NSA OM 900. Goord. Requirement Request Coeuments A B C D P a OM 54, Log L4-29, D/G start air . 2EGA*100 3 X 36-3 E-4 QS header pressure maintained verifying [ check va Ive open ( lW-34141. OM 54, tog L4-29, D/G start air 2EGA*101 3 X 36-3 F-4 QS header pressure maintained verifying check valve open f IW-34141. OM *A, Log L4-32, D/G start air 2EGA*130 3 X 36-3 E-9 QS he eder pressure mair.tained verifying c:ack velve open f IW-34141. OM 54, tog th-32, D/G start air 2ECA**31 3 X 36-3 F-9 QS header pressure maintained verirying check vaIve open f iW-34141. 2EGA*SOV202-1 3 X 36-3 A-5 QST RR22 OST 2.36.1 Stroke & Time IMI 2EGA*SOV202-2 3 X 36-3 8-5 QST RR22 OST 2.36.1-Stroke 4 Time IMI 2CCA*SOV203-1 3 X. 36-3 A-10 OST RR22 OST 2.36.2-Stroke & Time (MI 2EGA*SOV203-2 3 X 36-3 8-10 QST RR22 OST 2.36.2-Stroke & TIN f;il 2EGA*RV205 3 X 36-3 E-_4 SPT 29VT 1.60.5-(R) 2EGA*RV206 3 X 36-3 E-9 Sf'T 29VT 1.60.5-(R) 2EGA*RV207 3 X 36-3 F- b SPT 28VT 1.60.5-fR)
- SPT ESVT 1.60.5-fRI 2EGA*RV208 X 36-3 T-9 99 - 8SSUE 1 REV 4 m i
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, s.q VALVE TESTipsG OUTLINE -
- ,44 SYSTEM MAME: 'Diesef Fuet Oil SYSTEM feUMBER: 36 .
VaIve ._.-. Vaive Category . CSJ or Mark DrewIng Drawing Test MeIlef' Mumber Class MSA. OM No.. COord. Requirement Request Coeuments _. A B C D P 2EGF*T 3 __ X 36-1 F-1 QS' OST 2.36.1-FS.FD.RD (M) - 2EGF*8 3 X 36-1 E-6 QS OST 2.36.?-IS.fD.RD (M) 2ECF*9 3 X 36-1 E-1 - QS OST 2.36.1-fS.FD.RD (M) 2EGF*10 3 X 36-1 E-7 QS OST 2.36.?-FS.fD.RD IM) ISSUE 1-
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Valve Valve Category , CS6B or Ma rt. D rawi ng . Drawing fest- Relief Num h-- Class NSA OM Mo. Coord. Requirement Requesc t,omments - A B C D P 2HVC* MOD 201A 3 X 0 44A-2 D-2 RST QST 2.47.3A(381-Stroke & Time fel 2HVC*MOLS018 3 X 0 44A-2 ' D-2 OST OST 2.47.3At 381-Stroke & Ties f Ql' 2HVC*M00201C 3 X S 44A-2 C-2 - QST- OST 2.47.3A(381-Stroke & Time tel.. 1HVC* MOD 2010 3 X S tet:A C-2 QST ' OST 2.47.3Af3BI-Stroke & Time fel 2HVC* MOD 20t:A 3 X S 44A-2 F-2 . . _ SST OST 2.t:7.3Af381-Stroke & Time (Q)
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VALVE TESTING OUTLINE
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' Drawing . Drawing Test- Relief-Number Class NSA OM No. Coo rd. Requirement Request. Comments A B C D P ".-
2HVR*M0023A 2 X LS -44C-2 .B-5 OST ' CSJ51 OST 2.1.10-Stroke & Time iCSDI LT- _, RR1.hR2.R925 2BVT 1.47.5-Lea k _.ierst (Rn 2PNR* MOD 238 2 X LS .. 44C-2' B OST CS851 OST 2.1.19-Stre e & Time ICSDI LT R2 .RR2 E M 28VT 1.47.5-Leak Trst (R) .<. 2HVR* MOD 25A 2 X LS ' '44C-2 ' C-5 'QST CSJ51 OST 2.1.10-Stroke & Time (CSDI LT RRt.RR2 RR26 2BVT 1.4T.5-Leak Test (R) 2HVR* MOD 25B 2 X LS 44C-2 C-7-' OST CSJ51 OST 2.1'.10-Stroke & Time (CSDI - L T .- RRt.RR2.RR26 28VT 1.47.5-Leak Test tR1 2HVR*DMP206 2 X .X LS 44C-2 D-6 LT RRI.RR2.RR26 28VT 1.47.5-Leak Test (RI-
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- OS ' OST 2.47.3AL3BI-Stroke Only (0) l 2HCS*111 2 X LS 1 C-2 LT RR1 2BVT-1.47.$-Leak Te,st (R) 2HCS*MOV112A 2 X S 46-1 C-6' QST OST 2.47.3Af 381-Stroke e 'i jne (Q) 2HCS*MOVi1E? 2 X . S 46-1 f-6 QST OST 2.47.3Af 381-Stroke & Time (Q1- [
2HCS*SOV114A 2 X S 46-1 B-2 QST OST 2.8 _.3Af 381-Stroke & Time (Ql- , LT RR1 - 2BVT 1,47.S-Leak Test (R1 2HCS*SOV1148 2 X S .46-1 F-2 QST RR1-OST 2.47.3Af 381-Stroke g Time (Q) .l LT 2BVT 1.47.S-Leak Test fRI 2HCS*50V115A 2 X S 46-1 G-2 QST OST 2.47.3Af 3Ol-St roke & Time ' tQl ' l~ LT RR1 2BVT 1.47.5-Leak Test (R) 2HCS*SOV115B 2 X S 46-1 F-2 QST OST 2.f7.3Af381-St'roke & Time (Q) }' LT RR1- 2BVT 1.47.S-Leak Test (R) 2HCS*MOV116 2 X S 46-1 D-1 QST OST 2.47.~ 3Af 381-St roke & Time' (01 ' !. LT RR1 2BVT 147.5-Leak Test (R) 2HCS*MOV117 2 X S' 46-1 G-1 QST OST 2.47.3Af 3B1-St roke & Time (01 l_ LT RR. 2BVT 1.47.S-Leak Test (R) 2HCS*MOV120A 2 X S 46-1 D-7 OST OST 2.47.3Af381-Stroke & Time (Q) 2HCS*MOV1200 2 X S 46-1 G-6 QST OST 2.47.3Af301-Stroke & Time (Q) 2HCS*SOV133A 2 X S 46-1 A-1 QST OST 2.47.3Af 381-St roke & Time 101 LT RR1 2BVT 1.47.S-Leak lest (R) 2HCS*SOV133B 2 X S 46 ' E-1 ' QST" OST 2.47.3Af3Bj-Stroko & Time'f01 l~ LT RR1 2BVT 1.47.S-Leak Test (R) 2HCS*SOV134A 2 X S 46-1 A-3 QST OST 2.47.3Af 381-St roke & Time (Q) 'l'" LT RR1 __ 2BVT.1.47.S-Leak Test (R) 2HCS*SOV134B 2 X S 46-1 D-3 QST OST 2.47,1A118]-Stroke & T'ine (Q1 l-Li RR1 2BVT 1.47.S-Leak Test (R1 103 - ISSUEzl
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SYSTEM MAME: Hydrocen Control- SYSTEM NUMBER: 46 Vaive Vaive -Category ~
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CSJ or Mark' Drawing Drawing . Test Re t lef" Number Class . NSA OM No. Coo rd. Requirement Request Comments A B C D P _
~
2HCS*51V135A 2 X S '46-1 lE-1" OST - OST 2.47.3Af381-Stroke & Time (Q1 l - LT RR1 2BVT 1.47.5-Leak Test (R) 2HCS*SOV135B 2 X S 46-1 E-2 OST OST 2.47.3Af3BI- k roke & Time (Q) l2-LT RR1 2BVi 1.4 7.5-Leak Test (R)
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2HCS*SOV136A 2 X S 46
- B-1 QST OST 2.47 3Af3BI-Stroke &' Time (Q) ~ l"'
LT RR1 2BVT 1.47.5-Leak Test (Rn 2HCS*SOV136B 2 X S 46-1 8-3 QST OST 2.47.3At381-Stroke & Time 101' -l LT RR1 2BVT 1.4T.5-Leak Test (R) _a
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VALVE TESYlNG OUTLINE LSYSTEM NUMBER: 47 1 SYSTEM NAME: Containment ._
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- 2; Vaive Valve Category .
. CSJ or Mark Drawing Drawi ng ' ' Test Relier Number Class NSA . OM No. Coo rd. Requirement Request- Comments A B ClD P .-:.
l . 28VT 1.47.8-Type B Leak Test 2PPS*100 2 X X S 47-1 f-47 LT RR31 (Semi-Annually!
. 28VT 1.47.8-Type B Leek Test 2PHS*101 2 X X S 47-1 F-2 LT RR31 (Semi-Annually!
2BYT 1.47.8-Type B Leak Test 2PHS*110 2 X X S 47-1 E-4 LT RR31 (Seel-Annustly) 2BVT 1.47.8-Type B l_eek Test ~ 2PHS*111 2 X X -S 47-1 E-4 LT RP3s ( Sem i- Ar'nua t iv l 2BVT 1.47.8-Type B Leak Test-2 X 47-1 E-2 LT RR31 (Semi-Annually) 2PHS*112 X S 207 1.47.8-Type 8 Leek Test' 2PHS*113 2 X X S 1 E-2 LT RR31 (Semi-Annustly! ' 2BVT 1.47.10-Type B Leat:. Test : 2PHS*201 2 A X S 47 B-9 LT RR32 (Semi-Annually) ~ 2BVT 1.47.10-Type B Leak Test 2 X S 47-1 LT- RR32 (Semi-Annually) 2PHS*202 X ' B-8 f 105 8SSUE 1: ' REV 4
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SECTION VI~.-VALVE TESTING COLD SHtfrDOWN JUSTIFICATIONS W3
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COLD SHUTDOWN JUSTIFICATION 1
-t' Valve No.:: 2RCS*68.
Cutegoryf 'A/C . Class 2 L
'r _ . Function': Inside centainment isolatica check valve on the nitrogen ;
supply to the Pressurizer. Relief Tank [2RCS-TK22].- '
- Test Requirement:- Quarterly full stroke Basis'for CSJ: Valve. is normally closed and is opened during nitrogen f makeup to the Pressurizer Relief Tank. -Safety position is closed.,for containment isolation. Full stroking can.
only be verified by cycling the weight loaded arm or leak testing. Because this valve is located inside cantainment, it is not accessible during normal' operation. < Alternate-Test: Full stroked closed per OST 2.1.10 COLD SHUTDOWN JUSTIFICATION 2 Valve No.: 2RCS*72
- Category: A/C _
Class 2 Function: Inside containment isolation. check valve on the primary. 9 grade water supply to the Pressurizer . Relief Tank (2RCS-TK22). s Test. Requirement: ' Quarterly full stroke Basia for CSJ: Valve is normally closed and is opened during primary grade water makeup .to the Pressurizer -Relief Tank. Safety position is closed for containment isolation. Full stroking can only be verified by cycling the weight loaded arm or leak testing. Because this valve is located inside containment, it is not accessible during ! i normal operation. !
' Alternate Test: Full stroked closed per OST 2.1.10.
107 ISSUE 1 REV 4 G 4_
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' COLD SHUIDOWN JUSTIFICATION' '4
-Valve ~No.:' 2RCS*PCV4550 i
~2RCS*PCV455D P 2RCS*PCV4%
- n
' Class '
s
' Category Bi m
, ~ p.- iFunction: ! Pressurizer Power.0perated' Relief Valves
.. Test. Requirement:: Qu'arterly full stroke and time' a 1:,
, d Valves- are normally closed. -The. safety _.functiot. is'to j
' . Basis' for C3J: '
~
provide overpressure protection for the Reactor. Coolant l System.- Since--'thess- . valves have. shown a high
. probability of' failing open, cycling during . normal
_ operation is.. not practica1'. In addition, safety grade-over. pressure protection at. power is provided by the pressurizer coda safety. valves. AlhrnateTest: Full stroked and timed per OST -2.6.8. 'dection H.1 under - !'
, " Valve Testing Requirements" does not apply to' these valves. (i.e. .PORV's will be tested at each CSD,'but ;
r ' not more often than once every 92 days) l i l '.i ' l ! r
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1; 108 ISSUE 1 I REV 4
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- Valve No.: 2CHS*31 ~
- Category' A/C Class 2' Function: Charging header inside concainment-isolation check valve- ,
Test Requirement: Quarterly full stroke , 6 Basis for CSJ: This valve is normally- open, but is required to be closed for containment isolation.- Full stroking can only be verified by cycling the. weight loaded arm. Since the valve is located inside containment, it is not accessible dur.ing normal operation. Alternate Tcst: LFull stroked closed per OST 2.1.10.- I COLD SHUTDOWN JUSTIFICATION - 6 ; Valve No.: -2CHS*LCV1150 l 2CHS*LCV115E Category- B __ Class 2 , Function: Volume Control Tank [2CHS*TK22) outlet isolation valves l Test Requirament: Quarterly full stroke and tima Basis fo- CSJ: These valves are normally open during power operation. f Safety function is to isolate the VCT from the High Head -!' Safety Injection System. Closing this valve during normal operation would -isolate the suction of the charging pumps, causjng pump damage -and loss ofu pressurizer level centrol.- Alternate Test: Full stroked and timed per OST 2.1.10 4 109 ISSUE 1 REV 4
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' C01.D SHtTIDOWN JUSTIFICATION ' 7-
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Valve'No.:- -2CHS*84 2CHS*1?6-2CHS*141 3 Category C Class. 2;3-Function; Emergency and alternate Boration line check' valves s 'lest Requirement: Quarterly full stroke 4
) Basis for CSJ: These valves- are- normally. closed during power operation, t
-and are required to open for erergency : and alternate temergency boration. Exercising these valves durins .j normal operation would result in cncentrated, Boric Acid. ij
'being injected into the RCS, causing 'an undesired- 1 negative reactivity addition resulting in a reduction in plant power.
Alternate Test: Full stroked'open per OST 2.7.13 -l COLD SHUTDOWN JUSTIFICATION 8 ; 1 Valve No.: 2CHS*A0V204 l d Category- A Class 2 l q Function: Letdown isolation outside containment isolation valve 4 Test Requirement: Quarterly: full stroke and time
]
o Basis for CSJ: Valve is normally open. Safety function is to close for containment-isolation on a receipt- of a CIA signal. Stroking this valve at power will result in a thermal' shock to the Regenerative Heat Exchanger and associated-component piping resulting:in an. increased probability -j of system and component failure. In addition, failure j of -this valve in the closed position will cause loss of j pressurizer level control which will result in plant shutdown. Alternate Test: Full stroked and timed per OST 2.1.10 l I 110 ISSUE 1 REV 4
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BVPS-2 IST s i COLD SHUTDCVN JUSTIFICATION' 9 l
' Valve No.: 2CHS*MOV289 P
. Category A Class . 2 i
Function:- Normal charging system-makeup outside containment
> isolation valve
. Test Requirements Quarterly full stroke sad time .
Basis for CSJ:= Valve is normally open.- Safety function-is to close on 3 receipt of an SI signal. Stroking'this valve at power , will result in a thermal shock to the' Regenerative Heat-Exchanger-and associated component piping resulting in l an increased probability of system and component ] In addition, failure of this valve in the. ; failure.
' closed position will cause loss of pressurizer level control which will result in piant shutdown. '~'
Alternati Test: Full stroked and timed per OST 2.1.10 t
<- COLD SHUTDOWN JUSTIFICATION- 10 Valve No.: 2CHS'MOV308A !
2CHS*MOV308B- ~ 2CHS*MOV3080.
-l Category A Clas9 2 l
l: Function: ' Reactor- Coolant Pumps ' Seal water supply outside l containment isolation valves Test Requirement: Quarterly Ju11 stroke and time l l ., . Basis for'CSJ: Those valves are open during normal plant operation, but L are required to be closed for containment penetration isolation. Exercising these valves .at power' would secure RCP seal injection and cause seal damage. Failure in the closed position daring testing will result in plant shutdown. Alternate Test- Full stroked and timed par OST 2.1.10 l ll 1
'1 1
111 ISSUE i REV 4
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COLD SHUTDOWN JUSTIFICATION 11'
. Valve No.: .2CHS*MOV310
' Category. B Class 2~
Function: Regenerative Heat Exchangerioutlet isolation: valve Test Requiriment: Quarterly fu11' stroke and timv
~
Basis for'CSJ: Valve is normally open. Safety function is to close on' receipt offan SI signal. .$$roking-_this, valve! during T normal . operation will resu13 in a thermal shock to the Regenerative. Heat . Exchanger _ and associated- piping _{ resulting in- an- increased' probability of system and component failere. In addition, failure of this valve in the closec position will cause loss.of pressurizer level coatrol which will result in plant shutdown.
- Alternate. Test: Full stroked and-timed <per OST 2.1.10 i~
COLD.SHUTD'0WN JUSTIFICATION 12 Valve No.: 2CHS*MOV373 L Categer;r B Class- 2
, Function: Charging Pump recirculation isolation valve ,
l' Test Requirement: Quarterly full stroke and time- a y L' Basis for'CSJ: -Valve is normally open. Safety function is'to close on a safety injection signal. This valve cannot ,be full stroked during normal operation because fai:- re in the , closed position would isolate charging pump minimum flow ' L to the VCT, which could result in damege to the charging-pump. Alternate Test: Full stroked and timed per:0ST 2.1.10
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112 ISSUE 1 REV 4
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COLD SHLFDOWN JUS *rIFICAT1dN 13
' ' Valve No.': 2CHS*MOV378 2CHS*MOV381 Category. A ___ Class 2 3 Function:- Reactor l Coolant Pumps . Seal ' water return' inside and ,
outside contair.ient isolation valves
- EO . .
r Test Requirements. Quarterly _ full stroke and time Basis for CSJ . Valves are normally open. Safety function is to close
'for containment isolation on receipt of a CIA signal.
Exercising these valves at power would secure RCP seal-return which could cause secl-damage. Failure of these valves .i the closed position will result in plant shrtdown. Alternate Test: Full stroked and timed per OST 2.1.10 , t COLD SHUTDOWN JUSTIFICATION 14 i Valve No.: 2CHS*LCV460A s 2CHS*LCV450B Category B Class 1 Function: Letdown inside containment isolation valves Test Requirement: Quarterly full stroke and time Basis for CSJ: Valves t e norme.11y open. -Stroking these valves during
- normal operation will result in a thermal shock to the
! Regenerative Heat Exchat.ger and associated piping resulting in an increased probability of system and ; L compor ent f ailure. In addition,' failure of these valves I in thu closed position will ccuse loss of pressurizer level control which will result in plant shutdown. Alternate Test: Full stroked and timed per OST 2.1.10
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113 ISSUE 1 REV 4
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O-i . COLD SHUTDOWN JUST1FIClJION 15' Valve No.: 2CHS*473 Category A'/C ' Cir.s b 2' Function: Seal Watcr Return Containment penetration X-19 thermal relief check-valve (Bypasses'2CHS*MOV378) L1 Test Requirement:'. Quarterly full stroke Basis for CSJ . This valve. is closed during n.. mal plant; operation and is to remain closed for containo nt isolction. .However, it will momer.tarily open if; required to relieve pressure , dua to the mal 4xpansion. Full stroke testing'can only , be performed by manually cycling the weight.: loaded arm. 'l Since this valve is located inside containment, it is not acce .s ele during normal operation. t
, Alternate Test: Full stros.a in both directions per OST.2.1.10
. COLD SHUTDOWN JUSTI5ICATION 16 Valve No.: -2CHS*474.
2CHS*475 2CHS*476
"~ Category A/C Class. 2
- Function: Reactor Coolant Pumps Seal water supply .inside
-containment isolation check valves .
Test Requirement: Quarterly full stroke Basis for CSJ: These valves are open durine. normal plant operation, but .i' are required to be closed for containment isolation. Exercising these weight loaded arm check valves in the closed direction at power would secure hCP seal d injection which would result in seal damage. l Alternate Test: Full stroked closed per OST 2.1.10 l l L L l' 114 ISSUE 1 REV 4 1
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COLDSKUTDOWNJOSTIFICATION' 17 __ .s: f Valve No.:1 -2CHS*MOV8130A 2CHS*MOV8132B [ 2CHS*MOV8130B 2CHS*MOV8133A- .
?. , 2CHS*MOV8131A- 2CHS*MOV8133B
- 2CHS*MOV8131B-2CHS*MOV8132A.
- Category l B' Class 2' __
Function: Charging pumps suction- and dischargo cross connect, valves Test Requirement:~ Quarterly full stroke and time Basis for CSJ: The function of these- valves is for Safety Inje cion ' train; separation during cold -les recirculation. -One valve in' suction and discharge is required-to close for, l train-separation.1 Full stroking'of the discharge cross-connects. cannot be . performed ,during normal-operation because these valves are required to be open. and de-energized by technical specifications.- Failure in the I closed porltion. under certain pump operating - configurations would' render the HHSI syscem inoperable. In addition;_BV-2'has committed to de-energizing the power: supply to the charging pump suction cross connects ' to prevent loss of charging' pump suctfa.: in'certain; fire scenarios.. The potential-risk in damage to'a HHSI pump , j does not' justify the gain in'cycidng these valves during normal operation. Liternate Test: Full stroked and timed per OST 2.1.10 i i i 115 ISSUE 1 REV 4
m y- ..y N. +,, BVPS-2 IST COLD SHUTDOW CJUSTIFICATION 18 i= Valve No.: 2RH5*3' e 2RHS*4-p. Category C Class- 2
'Fanction: Residurl Heat kemoval Pomps check valves.
, Test Requirement!' Quarterly full stroke Basisifer CSJ: Valves ~open for Residual Heat Rcmoval system operation and close to prevens reverse flow through the standby c
-pump. During normal power operation RHS is isolated
. from;the RCS;and Retidual Heat ' Removal- pumps are not 3
requirea for operation. Verification of forward and - reverse Ptroking' requires. pump operation by non-rotation of the idle pump. Checking. reverse stroke requires local observation. Since' these valves. are .in containment' they are inaccessible during normal operation. i Alternate Test:~ Full stroked open per OST 2.10.1(2)
; Full stroked closed per OST 2.10.3(4) ,,
COLD SHUTDOWN JUSTIFICATION 19 , (? Valve No.: 2RHS*FCV605A 2RHS*FCV605B Category B Class 2 w Function: Residual Heat Removal Heat Exchangers bypass flow -
, control valves.
Test Requirement: Quarterly full stroke and time.and fail closed -l .( Basis for CSJ: The s e.f ety related function of these valves is to fail 1 closed on loss of power. Local observation is required / to determine valve stroking. Valves are located inside J.
" reactor containment and are inaccessible during power = g' operation. L Alternate Test: Full stroked, timed and fail closed per OST 2.10.3(4) l 116 ISSUL 1 REV 4
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i BVPS-2 IST k ) COLD SHUTDOWN JUSTIFICATION _ 20 Va4ve No.: 2RHS*MOV701A 2RHS*MOV720A 2RHS*MOV701B 2RHS*MOV720B 2RHS*MOV702A 2RHS*MOV702B Category A Class , 1
- Function: Re actor Coolant System to RHS isolation valves Test Requirement: Quarterly full stroke and time Basis for CSJ: These valves nre normally closed. The safety function is to open for initiation of RHS to attain cold shutdown and closed to isolate the RCS from the RHS system during normal operation. Full stroking these valves during normal operation cannot be performed because they are interlocked closed during normal operation to prevent overpressurization of RHF piping.
Alternate Test: Full stroked and timed per OST 2.10.3(4) COLD SHUTDOWN JUSTIFICATION 21 Valve No., 2RHS*HCV758A
.RHS*HCV758B Category B Class 2 Function: Residual Heat Rr , oval Heat Exchangers flow control valves.
Test Requirement: Quarterly full stroke and time and failed open Basis for CSJ: The safety related function of these valves is to fail open on 1 ss of power. Local observation is required to determine valve stroking. Valves are located inside reactor containment anc are inaccessible during power operation. Alternate Test: F-11 stroked, timed and failed open per OST 2.10.3(4) 117 ISSUE 1 REV 4
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- Valve'No.: 2 SIS *42'
' Category- -A/C -Class 2 5 i
Function: Safety! Injection Accumulator fill inside cot.tainment' isolation check valve ; Test Requirements. Quarterly full stroke
- Basis'for CSJ: Valve is normally closed during power operation. Safety function la to be closed for containment isolation.. .
Valve is; opened during accumulator fill operation, ' Full' , stroke testing is verified by observing weight 1caded crm movement- , .Since this valve is located ins ide-containment, it is .not accessible. during normal operation. Alternate Test: ' Full' stroked closed per OST 2.1.10 ' e i COLD SHUTDOWN JUSTIFICATION 23 Valys No.: 2 SIS *83 I 2 SIS *84 2 SIS *94 ! 2 SIS *95 Category A/C Class 2 Functiont HHSI to Hot and Cold. Legs inside containment isolation check valves Test Requirement: Quarterly full stroke Basis-for CSJ: Normal posi; ion for these valves is closed. These valves are to remain closed for containment isolation and'are opened for Hot Leg recirculation. Full stroking requires use of the weighted arm on the valves. Since these-valves are located inside the containment they are not acces,ible during normal operation. Alternate Test: Full stroked in both directions per OST 2.1.10 118 ISSUE 1 REV 4
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COLD SHUrDOWN JUSTIFICATION- 24-
- Valve No.:: 2 SIS *130' 2 SIS *132 2 SIS *133 :
- Category A/C . Class' 2 Function: .LH31 to Eot-and Cold Legs inside containment isolation .
V; -valves .!
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, Test Requirement: Quarterly full stroke ,
Basis for CSJ:. Normal position is closed. These valves are to remain closed for containment isolation' and ' reactor coolant pressure boundary isolation, and open for LHSI; Valves cannot be' cycled during rower operation because the LHSI p, pump .can not devehep . ensvgh head to overcome reactor , coolant system pres:;ure. In addition, cycling using the-weighted arms is not possible sir.ce these valves are .j located 11nside contcinment and are not accessible during 4 normal operation. Alternate Testi Full stroked an both directions per OST 2.1.10 i COLDlSHUTDOWN JUSTIFICATION 25 _ t
- Velve th). : 2 SIS *MOV836
- Category A Class 2'
,.o. Function: HHSI to cold-leg header isolation valve! , Test Requirement: Quarterly full stroke and time Basis for CSJ: Valve is normally closed and is opened by the operator - to achieve a redundant flowpath to the cold legs during the recirculation mode. .ull stroking during normal - operation would inject relatively cold water into the l RCS cold leg resulting in thermal shock to system piping l and components which can lead to their prematurs
- failure. !
Alternate Test: Full stroked and timed per OST 2.1.10 : e JV 1; i 119 ISSUE 1 l REV 4 w
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-Valve Nc : 2 SIS *MOV869A
- I,
!i , 2 SIS *MOV869B i ;
,. Category ~A Class 2 ,
Function: HHSI to hot leg header isolation valves. ! 4: , 1TestJRequirement Quarterly fulf stroke and time- q Basis.for CSJ:. Valves are normally closed and' are opened by the operator for hot leg recirculation.1-Full stroking these .i valves 'during normal operation would inject relatively cold water inco the RCS hot legs resulting in thermal shock to system piping and components which can lead to , 1 their premature failure. Alternate Test: .Ful1~ stroked and timed per OST 2.1.10 COLD SHUTDOVN JUSTIFICATION 27 Valvi No.: 2 SIS *MOV8889 1 Categocy A- Class 2 Function: LHSI to RCS hot leg outside' containment isolatinn valve- ;- Test Requirement: Quarterly full stoke and time ; Basis for CSJ:
-Valve is 'normally closed. Valve. is required to be opened during. hot' leg recirculation mode. This valve is ,
required: to be closed and deenergized during normal ~' operation in accordance with technical specifications. Full stroki.sg during normal operation could result in overpressurization of the low pressure portion of LHSI piping if simultaneous check valve failure occurred. Alternate Test: Full stroked and timed per OST 2.1.10 120 ISSUE 1 REV 4
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BVPS-2 IST COLD SHUTDOWN JUSTIFICATION' 28 J
Valve-No.: 2QSS*3' ( 2QSS*4 l t Category' A/C Class 2- , Function: Quench spray header inside containment'isolction check valves. ! Test xequirements Quarterly full-stroke' j Basis for CSJ: Valves are normally closed. Safety position is open for QSSL flow and- closedL for- centainment. isolation. Exercising can only be' performed by manually cycling the
- weight 1oaded arm on; the check valve. -Since' these.
~
t valves are located inside-reactor containment, they are a not accessible:during normal operation. Alternate Test: ' Full: stroked in both directions per OST 2.1.10. ] 1
' COLD SHUTDOWN JUSTIFICATION 29 Valve No.: '2QSS*S0V100A y 2QSS*S0V100B
! Category A Class 2 i Function: Chemical injection to containment sump outside
'E containment isolation valves.
Test Requirement: Quarterly' full stroke'and time j Besis - for CSJ: Failure of these valves in the open position would cause-loss of NaOH injection for the Quench Spray System. Also since' these valves are located at the containment penetration, failure'in the open position would require
. closing both chemical ~ injection pump discharge valves to comply with technical specifications rendering chemical l injection inoperable. This would require plant shutdown.
Alternate Test: Full stroked and' timed per OST 2.1.10 ; s 121 ISSUE 1 REV 4 c .ij , _ ..,.r- - . - - - ,
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., . Valve No.: 2QSS*267 Category- ~ A/C- Class 2 __
- Function: QSS chemical, injection -insidel containment isolation
,. check valve. Test Requirement: Quarterly, full stroke
.i Basis for CSJ: Valve -is normally closed. . Safety function < is open- j during chemical injection to containment sump and closed :l for containment. isolation. Exercising can only. be , j performed.by cycling weight loaded arm. Since the valve- !
is located inside the reactor containment, exercising. I cannot be performed during normal operation.- l Alternate Test: Full stroked in both directions.per OST 2.1.10 COLD SHUTDOWN JUSTIFICATION 31
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I Valve No.: 2RSS*29 2RSS*30
'2RSS*31-2RSS*32 Category C Class- 2 .
1
- Function: RSS discharge headers to' spray nozzle inside containment isolation valves i i
Test Requirement: Quarterly full stroke '; , Basis for CSJ: Valves are normally' closed. Safety function is open for s RSS operation. Because RSS is normally maintained dry I cycling can only be done using the weighted arm on the 3 valve. These valves are located in the containment and are inaccessible during normal operation.
. Alternate Test: Full stroked open per OST 2.1.10 >
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- COLD'SHttrDOWN JUSTIFICATION 32 _
' Valve- No. :
2CCP*A0V107A
-2CCP*A0V107B .
2CCP*A0V107C-(Category B Class 3' } r i; ' Functioni Rasetor Cec 1:nt Pu=p Thermal Barrier Heat Exchanger CCP fi outlet isolation valves. ; I
-Test Requirement: : Quarterly full stroke,' time,'and fail safe.
Basis for CSJ: Valves -are normally open, and are requiied to close in' l
-the' event.of a primary loop to CCP leak inL the reactor coolant pump seal thermal barrier. Closing the valves during normal operation would interrupt flow of cooling ,
water to the creactor coolant pump seals. This could. result in damage to the reactor coolant- pump. seals. (
. Failure in the closed position would result in plant shutdown, i
- Alternate Test: Full stroked, timod, and fail 1 closed per OST 2.1.10 l
s COLD SHUTDOWN JUSTIFICATION 33 ,
' Valve No.: 2CCP*MOV150-1 2CCP*MOV156-2 L 2CCPAMOV150-2 2CCP*MOV157-1 2CCP*MOV151-1 2CCP*MOV151-2 2CCr*MOV157-2 .]
- i. 2CCP*MOV156-1 Class 2 1 Category A-Function: CCP dupply and return headers go reactor containment outside and inside isolation valves L . Test Requirement: Quarterly' full stroke and time Basis for CsJ: ' Valves are normally open; safety position is closed for i o containment isolation. Closing the valves during normal operation would interrupt flow of cooling water to the reactor coolant pump seals. This could result in damage to the reactor coolant pump seals. -Failure in the
-closed position would result in plant shutdown.
Alternate Test: Full stroked and timed per OST 2.1.10 123 ISSUE 1 REV 4 1
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* . COID SHUTDOWN JUSTIFICATION-'
34 -- gl s tValve No.: i 2 MSS *18 '- :2 MSS *199- , " 2 MSS *19 -2 MSS *352~ , 2 MSS *20.
#s l2 MSS *196
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j
., j iFunction: ' Main Steam.to Auxiliary Feed Pump Check Valves l(
W - . _ .. . , : .t Test Requirement: Quarterlyifull stroke: l mj 7
-'- sBasis'for~CSJ:: Full;' stroking' these 3ah 2s- cannot be performed' during -
normal ~ operation because this 'would. require -injecting
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' ' lrelatively. cold- auxiliary ieedwater' to, the -steam h i--
9 generators at the/ design flowrate. This would result in J
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j - ia' thermal shock to the auxiliary feedwater; piping'which; could lead ro premature failure. ~,, t Alternate Te'st: Partial stroke open monthly and- .
-full stroke"open at' cold shutdown per OST 2.24.4 - .
i COLD SHUTDOWN'JUSTIIICATION
- 35 ' .l
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- Valve No.:- : 2 MSS *A0V101A ,
' 2 MSS *A0V101B 'l
'i 1 2 MSS *A0V101C' m
Category -B Class ___ 2-Function: Main Steam isolation valves-for Steam Generators ! Test Requirement: Quarterly full stroke and-time - D h Basis for CSJ: Valves are normally open; safety position-is closed for High Energy Line Break isolation. Closure of these valves during normal operation. would result in plant shutdown. > l j Alternate Test: Partial stroked.per OST 2.21.1(2)(3) quarterly. j
- - Full stroked and timed closed per OST 2.21.7 at shutdown with TAVG 2515F. l e
124 ISSUE 1 REV 4 a.
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1 COLD SHUTDOWN JUSTIFICATION. So a ^ Valve No.:. 2SYS*80-2SVS*81' , 2SVS*82- l i CategoryL C Class- 2-Function:- Steam Generators residual heat. release-check valves Test Requirement: Quarterly full stroke Basis fcr CSJ: Full stroking open these valves during normal operation _ l cannot be performed because a reduction in- plant power would be required in order to prevent exceeding full ;
. power limitations.
I Alternate.Teht: Full stroke open during unit shutdown per OH 2.51.4.C COLD. SHUTDOWN JUSTIFICATION 37 Valve No.: 2SVS*PCV101A 4 2SVS*PCV101B 2SVS*PCV101C Category B Class 2 ,
' Function: Steam Generators atmospheric dump valves Test Requirement: -Quarterly full stroke and time Basis for CSJ: These valves are normally closed. The safety function is to open to control S/G pressure after a reactor trip.
L Full stroking open these valves during normal operation-cannot be performed because a reduction in plant power would be required in order to prevent exceeding full power limitations. Closing the manual isolation valves J so that' these valves can be cycled presents an !' unacceptable risk to plant personnel due to their l- location in the plant. 1~ L- Alternate Test: Full stroked and timed per OST 2.1.10 125 ISSUE 1 REV 4 l
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- Valve No.:' 2SVS*HCV104 Category _B Class 2 Function: Combined' Main Steam atmospheric dump valve Test Requirement: . Quarterly full stroke and time
;= -
Basis'for'CSJ: Valve is normally closed. Opened as necessary_ by_ [ operator during cooldown from the control room or Emergency. Shutdown Panel. Full stroking open'this valve during normal operation cannot be performed because a reduction .in plant power would be required in order to prevent exceeding full power limitations. Closinf the _- manual isolation valve so that this valve can be cytted . . , t l-I presents an unacceptable risk to plant personnel due to its location in plant. Alternate Test: Full stroked and timed per OST 2.1.10 i COLD SFUTDOWN JUSTIFICATION 39 Valve No.: 2FWS*HYV157A. l 2FWS*HYV157B L 2iWC'HY"'57C Category B Class 2 l- Function: Mair Feedwater Headers Isolation Valves to Steam l: Generators l Test Requirement: Quarterly full stroke and time l Basis for CSJ: Valves are normally open. Safety position is closed for l Feedwater isolation in the event of a high energy line break or Safety Injection System actuation. Full stroking closed during normal operation cannot be-performed since this would stop feedwater flow to the steam generators resulting in plant shutdown. A). ternate Test: Full stroked and timed per OST 2.1.10 126 ISSUE 1 REV 4
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' Val've No.: ' 2WE*42A 2NE*44A
- 2WE*42B 2WE*44B 2WE*43A.
2WE*43B
. Category C Class -2 ^ ' Function: ' Auxiliary Feedwater headers check valves-r Test. Requirement: Quarterly full stroke Basis for CSJ: Valves are normally closed. Safety position is opened.
for Auxiliary Feed System . injection. and closed to provide' header separation in'the event of a-line break.= Full stroking these' valves during . normal.. operation cazmot be. performed because the test method requires design flow to the steam generator for both forward- and. reverse- stroking. . Injection of relatively cold auxi iary feedwater would result in a thermal. shock to , the auxiliary feedwater piping which could lead to premature failure. :l Alternate Test: Full stroked in-both directions per OST 2.24.6 . q COLD SHUTDOWN JUSTIFICATION 41 ! i
' Valve No.: 2WE*99 !
2WE*100 l 2WE*101 i Category C Class- 2 Function: Auxiliary Feedwater header check valves j i
' Test Requirement: Quarterly full stroke l t
Basis for CSJ: Full stroking these valves open during normal operation l cannot be performed because the test method requires j design flow to the steam generator. Injection of relatively cold auxiliary feedwater would result in a thermal shock to the auxiliary feedwater piping which could lead to premature failure. Alternate Test: Full stroke open per OST 2.24.6 f l 127 ISSUE 1 REV 4
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.g COLD SHUTDOWN JUSTIFICATION 42 Valve No.: 2FVE*FCV122 2FVE*FCV123A .;
2FVE*FCV123B
' Category -B/C' Class 3 Function: Auxiliary Feed Pumps discharge. flow control / check viives
- Test Requirement: Quarterly full stroke r Basis for'CSJ: These valves function as a pump discharge check valve (normally closed) and an Auxiliary feed pump -mini-flow control valve (normally open). Exercising of the check valves in the open position (and the mini-flow control
~
valve closed)- requires' design flow- to, the steam generators, that would result in a thermal shock to the auxiliary feedwater piping which coald lead to premature failure. Alternate Test: Full stroked per OST 2.24.4, 2.24.6 COLD SHUTDOWN JUSTIFICATION 43 Valve.bo.: 2SWS*57 2SWS*58 ; 2SWS*59 Category C Class 3 Function: Service water pumps discharge check valves Test Requirement: Quarterly full stroke l Basis for CSJ: Due to system design. flow requirements at power, l exercising of these valves requires use of the idle SWS l pump. Relief is requested in the event the idle SWS I pump is out of service for maintenance. Exercising can be ' accomplished upon return of the idle SWS pump to service, i Alternate Test: Full stroked open per OST 2.30.2(3)(6). l~ Full stroked closed per OST 2.30.6 quarterly or when the SW pump is returned to service or at least at CSD. 128 ISSUE 1 REV 4
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' COLD SHUTDOWN' JUSTIFICATION- 44 ,
Valve No.: -2SWS*MOV102A 2SWS*MOV102B 2SWS*MOV102C1 4 2SWS*MOV10202 , Category B~ __ Class 3 Lm Function:. Service water pumps discharge-valves ) h ~ Test Requirement:' Quarterly. full stroke and time. p -Basis for CSJ: Due to system design flow . requirements at- power,
- . exercising of these. valves requires use of the idle SWS L pump. Relief is c requested in the event the idle SWS~
l pump is out of service for maintenance.. . Exercising can be accomplished upon return of the idle SWS pump to-service. Alternate Test: Full stroked and timed per OST 2.30.6 quarterly or when the SW pnsp returned to service or at least at CSD. i
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i COLD SHUTDOWN JUSTIFICATION NO. 45 Valve No.: 2SWS*106 e 2SWS*107 Category- C Class 3
-Function: Service water header check valves =
- Test-Requirement: Quarterly full stroke
. Basis for CSJ: Full stroking these valves in the reverse direction is accomplished using a standby service water pump .and ',
cannot be performed during normal operation. Testing requires all SW pumps to be shutdown and the headers cross connected at the pumps in order to provide an upstream vent path of sufficient capacity to identify i valve deterioration. Alternate Test: Full stroked closed per OST 2.30.8 129 ISSUE 1 REV 4
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'i Category B , Class 3 -
Function: Servir.e Water headers isolation valves
, Test Requirement:.' Quar:erly full stroke and time Basis for CSJ: .There valves are normally open. The' safety function is to : lose to ensure sufficient SWS supply to the'RSS Heat exchangers.- Closing these valves during normal Loperation would reduce , service water supply to' Turbine Building.and CCP heat'exchangers below acceptable limits for full power operation. Failure of the valves to.
reopen after closure could lead to equipment damage and' plant shutdown. :( Alternate Test: Full stroked and' timed per OST 2.1.10 f
. COLD SHUTDOWN JUSTIFICATION 47 Valve No.: 2SWS*MOV107A 2SWS*MOV107B 2SWS*MOV107C 2SWS*MOV107D Category B Class 3' Function: CCS HX from service water headers isolation valves Test Requirement: Quarterly full stroke and time Basis for CSJ: These valves are normally open. The safety function is to close to isolate the NNS portion of the service water system. Full stroking during normal operation can.iot be performed because testing requires cross connection of the service water system in order to maintain the required SW flow for support of full power operation.
Failure of the valve to reopen would require operation of the SW system cross connected resulting in loss of SW train separation. Alternate Test: Full stroked and timed per OST 2.1.10 130 ISSUE 1 REV 4
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y-BVPS-2 IST-L: COLD SHUTDOWN JUSTIFICATION - 48 '
'/alve.No. , 2SWS*486 , 2SWS*487-l 2SWS*488 Category C Class' 3 Function: Service water pumps vacuum breaker check valves Test Requirement: Quarterly ful'. stroke- l I
Basis for CSJ: Due to syt t J design flow requirements. at power, exercising of these valves requires use of the idle SWS-pump., Relief isJ requested. in the event the idle'SWS~ pump is.out of service for. maintenance. Exercising- can be accomplished upon return of the idle SWS pump to-service. Alternate Test: Full stroked closed-per OST 2. 39.'2 ( 3) (6) .
-Full stroked open per OST 2.30.6 quarterly or when the SW pump is returned to service or at least at CSD.
COLD SHUTDOWN JUSTIFICATION 49 Valve No.: 2FPW*382 j 2FPW*388 2FPW*753 ! 2FPW*761 Category A/C Class 2 . l Function: Fire protection headers inside containment isolation check valves , Test Requirement: Quarterly full stroke Basis for CSJ: These valves are normally closed. They would be opened ; in the event of a fire in containment. The safety l l position is closed for containment isolation. Full stroke testing can only be performed by cycling the-weight loaded arm or leak testing. Since :hese valves are located inside containment, they are not accessible l during normal operation. 1 Alternate Test: Full stroked in both directions per OST 2.1.10 l 131 ISSUE 1 REV 4 i
in < < ' B,PS-2 IST~ [97 m COLD SHVFDOWN JUSTIFICATION 50- ; ,
~ Vtive No.: ~2IAC*22 Catsgory A/C Class 2
- Function: Instrument Air header inside containment isolation check .'
valve
" ~ Test Requirement: Quarterly fu11' stroke .
Basis for CSJ: This valve is normally closed and is opened as required to supply instrument air to the containment. The safety position is._ closed for containment isolation . Full-stroke testing can only be performed by cycling .the 4 weight loaded arm or leak testing. Since tnis valve is located inside containment, it -is not accessible during normal operation. Alternate. Test:' Full: stroked closed per OST 2.1.10 COLD SHUTDOWN' JUSTIFICATION 51 Valve No.: 2HVR* HOD 23A 2HVR* MOD 23D 2HVR* MOD 25A 2HVR* MOD 25B
. Category ~A .,_,
Class 2 Function: Containment purge discharge and supply outside and. inside isolation. dampers Test Requirement: Quarterly full stroke and time Basis for CSJ: These dampers are closed during power operation and opened for refueling operation. Safety functions are during power operation to remain closed for containment isolation and during refueling to close in the event of a refueling accident. These dampers cannot be cycled during normal operation because Technical Specifications require the dampers to be locked shut during normal operations. Alternate Test: Full stroked and timed per OST 2.1.10 132 ISSUE 1 REV 4
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' COLD SHUTDOWN JUSTIFICATION 52
- Valve'No.:. '2CVS*SOV102" 2CVS*SOV153A 2CVS*SOV153BJ
- Category A- Class ~ 2 1
Function: Containment ' Airborne' Activity: Radiation Monitor' [2RMR*RQ303)
' Containment Isolation Valves t Test Rcquirement: Quarterly full stroke and time b
Bcais for CSJ: During performance of _0ST 2.47.3A-(Quarterly Stroke Testing of.
-Containment Isolation and ASME XI Valves), Containment' Airborne-Activity Radiation Monitor (2RKR*RQ303] is shutdown to stroke. ,
associated containment isolation valves. When this occurs, both-the containment gaseous and particulate' airborne activity. monitors are. temporarily inoperable. ' This situation is less ' conservative-than the ~ action statement of Tech. Spec. 3.4.6.1, and places the-plant in a six hour action per Tech. Spec. 3.0.3, a Alternate Test: Full straked and timed per OST 2.1.10 l b COLD SHUTDOVN JUSTIFICATION 53 ,
~~ Valve No.: 2 SIS *46 2 SIS *47 Category C Class 2 Function: Recirculation Spray Pump discharge to LHSI Pump discharge weighted arm check valves
. Test Requirement: Quarterly full stroke ,
Basis for CSJ: These check valves are normally closed. Their safety function'is to open during the Recirculation Phase. Full stroke testing can only be done by cycling the weight loaded arm of each check valve. Exercising these weighted arm check valves-in the open direction during normal operation requires excessive forces due to the head of water from-the Refuelinc Water Ti rage Tank (RWST) against the check valve disk. Engineering .does not recommend applying the excessive forces required to cycle the check valves open. The pressurc created by the head of water from the RWST could be bled off by isolating one LHSI System train at a time and draining radioactive water from a drain valve into a sump. However, isolating oue train of en Emergency Core Cooling System during plant operation would place the plant in:o a Technical Specification Action Statement. If tested quarterly, the amount of radioactive water drained from the system to bleed off pressure would create additional liquid waste for disposal. Alternate Test: Full streked in both directions per OST 2.1.10 133 ISSUE 1 , REV 4
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o i SECTION VII. VALVE TESTING RELIEF REQUESTS
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. Function: Containment' Isolation '
~
' Test Requirement's: Leak tested per IWV-3420: >
Lat least ence every 2 years. Basis for Relief: These containment isolation valves.",re leak tested in accordance with 10CFR50, Appendix J '7ype C. - Since the acceptance criteria for Appendix J. Type C testing'is more limiting than: ASME -Section XI, additional leak' testing in accordance with ASHE- Section XI would be redundant.- Alternate Test: Leak test at refueling in accordance with 10CFR50, Appendix'J, IWV-3426, and IWV-3427(a) per-2BVT 1.47.5. -l. f e 135 ISSUE 1 REV 4
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, 2RCS*68 2CVS*151-1 2SSR*SOV129A-2 '2FPW*A0V205
- 2RCS*72 2CVS*S0V151A 2SSR*SOV130A-1 2FPW*A0V206
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2RCS*RV100 2CVS*SOV151B 2SSR*S0V130A-2 2FPW*A0V221 2RCS*A0V101 2CVS*SOV152A 2 PAS *SOV105A-1 2FPW*382 2RCS*A0VS19 2CVS*SOV152B 2 PAS *S0V105A-2 2FPW*3881 2CHS*HCV142- 2CVS*SOV153A 2CCP*RV102 2FPW*753 4
- 2CHS*A0V200A- 2CVS*SOV153B 2CCP*RV103 2FPW*761 2CES*A0V200B 2LMS*S1 2CCP*RV104 2SAS*14 i ; 2CHS*A0V200C 2LMS*52 2CCP*RV105 2SAS*15 ,
h 2CHS*RV203: 2QSS*3 -2CCP*MOV150-1 21AC*22 2CHS*A0V204 2QSS*4 . 2CCP*MOV150-2 2IAC*MOV130 2CHS*MOV378 ?QSS*SOV100A 2CCP*MOV151-1 2IAC*MOV133 2CHS*MOV381' 2QSS*SOV100B' 2CCP*MOV151-2 2IAC*MOV134 2CHS*473 2QSS*MOV101A 2CCP*MOV156-l' 2HVR* MOD 23A 2DAS*A0V100A 2QSS*MOV101B 2CCP*MOV156-2 2HVR* MOD 23B 2DAS*A0V100B 2QSS*RV101A 2CCP*MOV157-1 2HVR* MOD 25A 2DAS*RV110- 2QSS*RV101B 2CCP*MOV157-2 2HVR* MOD 25B 2DGS*A0V108A 2QSS*267 2FNC*9 '2HVR*DMP206 2DGS*A0V108B 2SSR*A0V100A-1 2FNC*38 2HCS*110 2DGS*RV115 2SSR*A0V100A-2 ^2FNC*121 2HCS*111 2VRS*A0V109Al 2SSR*A0V102A-1 2FNC*122 2HCS*SOV114A 2VRS*A0V109A2= 2SSR*A0V102A-2 2SWS*RV152 2HCS*S0V114B 2RHS*15 2SSR*A0V109A-1 2SWS*MOV152-1 2HCS*SOV115A 2RHS*RV100 2SSR*A0V109A-2 2SWS*MOV152-2 2HCS*SOV115B 2RHS*107 2SSR*A0V112A-1 2SWS*RV153 2HCS*MOV116 2 SIS *41 2SSR*SOV112A-2 2SWS*MOV153-1 2HCS*MOV117 2 SIS *42 2SSR*RV117 2SWS*MOV153-2 2HCS*S0V133A 2 SIS *RV130 2SSR*RV118 2SWS*RV154 2HCS*SOV133B 2 SIS *RV175 2SSR*RV119 2SWS*MOV154-1 2HCS*SOV134A-2 SIS *MOV842 2SSR*RV120 2SWS*MOV154-2 2HCS*SOV134B 2 SIS *A0V889' 2SSR*RV121 2SWS*RV155 2HCS*SOV135A 2GNS*A0V101-1 2SSR*RV122 2SWS*MOV155-1 2HCS*SOV135B L 2GNS*A0V101-2 2SSR*SOV128A-1 2SWS*MOV155-2 2HCS*SOV136A 2CVS*93 2SSR*SOV128A-2 2FPW*A0V204 2HCS*SOV136B 2CVS*SOV102 2SSR*S0V129A-1 l
.2CVS*151 l
I" 136 ISSUE 1 REV 4 w
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"' See below
. Valve No.:
- Category EA and A/C Class -2 ~
Function:- Containment Isolation Test Requirement: Corrective action following leak testing per IWV-3427(b) Basis for Relief: IWV-3427(b). spec 3~ 5 additional requirements . on increased test frequencies for valve sizes.of six inches and larger and repairs or replacement. over- the. requirements of IWV-3427(a). The. usefulness~ of-IWV-3427(b) does not- justify the burden cf complying with this requirement. Unnecessary repair or replacement of a valve or additional. leak testing, if attempted at cold shutdown, could delay plant startup Per 10CFR50.55a(a)(3)(ii), compliance with the specified requirements of IWV-3427(b) would result in hardship or i unusual -difficulties without a compensating increase in the level of quality and safety. . Alternate Test: For valves- (6 inch diameter or larger) in 2BVT 1.47.5, if the measured leak rate exceeds the rate determined, the valve shall be replaced or repaired. , CONTAINMENT ISOLATION VALVES , 2CCP*MOV151-1 2FNC*122 2SWS*MOV154 , 2CHS*A0V200A 2QSS*MOV101A 2CCP*MOV151-2 2SWS*RV152 2SWS*RV155 2CHS*A0V200B 2QSS*MOV101B 2CHS*A0V200C 2QSS*RV101A 2CC P*MOV156-1 2SWS*MOV152-1 2SWS*MOV155-1 2RHS*15 2QSS*RV101B 2CCP*MOV156-2 2SWS*MOV152-2 2SWS*MOV155-2 2CCP*RV102 2CCP*MOV157-1 2SWS*RV153 2HVR* MOD 23A g 2RHS*RV100 ' 2RHS*107 2CCP*RV103 2CCP*MOV157-2 2SWS*MOV153-1 .2HVR* MOD 23B p 2CVS*151 2CCP*RV104 2FNC*9 2SWS*MOV153-2 2HVR* MOD 25A ' 2CCP*RV105 2FNC*38 2SWS*RV154 2HVR* MOD 25B 2CVS*151-1 2QSS*3 2CCP*MOV150-1 2FNC*121 2SWS*MOV154-1 2HVR*DMP206' 2QSS*4 2CCP*MOV150-2 137 ISSUE 1 REV 4 l
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~ RELIEF REQUEST- 3
Valve No.: -2CHS*22
- 2CHS*23 l2CHS*24
. Category C Class 2
' i i; ' Function: Charging pumps discharge check valves Test Requirement: Quarterly full stroke ,
Basis for Relief: When the RCS is at normal operating pressure, full stroking the discharge check valves cannot be performed i because the charging pump will not develop the required flow. In addition, injection of relatively cold . water ', will cause a thermal cycle or shock resulting in an
- increased probability of system failure. At CSD full stroking cannot be performed because full flow testing could result in- low-temperature. overpressurization of the RCS.
Alternate Test: . Partial stroked quarterly per OST 2.7.4(5)(6).
- Full stroked open at refueling per OST 2.11.14 ;
RELIEF REQUEST 4 i Valva No.: 2 SIS *6 2 SIS *7 Category C Class 2 Function: LHSI pumps discharge check valves
-Test Requirement: Quarterly full stroke Basis for Relief: Normal position is closed. Safety function is to open for LHSI. When the RCS is at normal operating pressure, '
full stroking the discharge check valves cannot be performed because the LHSI pamp will not develop the ! required flow to open the valve. At CSD full stroking cannot be performed because testing would require full flow injection to the RCS where there is not sufficient volume to receive the additional inventory. Alternate Test: Full stroked open at refueling per OST 2.11.14 138 ISSUE 1 REV 4
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i I ! BVPS-2 IST i - . - RELIEF. REQUEST 5 , ValveNo. :" 2 SIS *27 Categor;< C Class- 2 4
-j Function: RWST to HHSI pump suction check valve Test' Requirement: Quarterly full stroke
- Basis for Relief: When the. RCS is at . normal operating pressure, full q stroking the suction eneck.. valve- cannot be performed: i because the' charging' pump will not develop the required
-flow. In addition, injection of relatively cold water will cause a thermal cycle or shock resulting in an-increased probability of system failure. At CSD full stroking cannot be performed because full flow testing .s could result in low-temperature - overpressurization of the RCS.
1 Alternate . Test : Full stroked open at refueling OST 2.11.14-RELIEF REQUEST- 6 Valve No.: 2 SIS *107 2 SIS *108 2 SIS *109 Category. A/C Class 1 Function: LHSI header check valves to RCS Cold Legs Test Requirement: Quarterly full stroke Basis for Relief: Normal position is closed. Safety function is to open for LHSI and closed to isolate the LHSI system piping from the RCS during normal operation. When the RCS is at normal operating pressure, full stroking the header check valves cannot be performed because the LHSI pump will not develop the _ required flow .tx> open the valve. At CSD full stroking cannot be performed because testing would require full flow injection to the RCS where there is not sufficient volume ~to receive the additional inventory. Alternate Test: Full stroked open at refueling per OST 2.11.14 139 ISSUE 1 REV 4
E . f BVPS-2 IST' 4 TRELIEF F2 QUEST 7 l} Valve No.:' 2 SIS *122- 2 SIS *126:
'2 SIS *123 -2 SIS *127- f 2 SIS *124 2 SIS *125 i
. Category C Class 1 Function: HHSI header check valves to RCS Hot Legs >
Test Requirement: Quarterly full stroke Basis for Relief: Normal- position is closed. Safety function'is to open: for HHSI. When the RCS is at normal operating pressure', n full stroking the header check valves 1 cannot be - de performed because the charging pump will not develop.the i required- flow.- In addition, injection of relatively cold water will cause a thermal cycle or shock resulting in an increased probability of system _ f ailure. At CSD full stroking cannot be performed because._ full flow testing could Lresult in low-temperature overpressurisation of the RCS. , s Alternate Test: Full stroke open at refueling per OST 2.11.14 ; i RELIEF REQUEST 8 Valve No.: 2 SIS *128
- 2 SIS *129 Category A/C Class 1 Function: LHSI header check valves to RCS Hot Legs Test Requirement: Quarterly full stroke Basis for Relief: Normal position is closed. Safety function is to open for LHSI and closed to isolate the LHSI system piping from the RCS during normal operation. When the RCS is at normal operating pressure, full stroking the header check valves cannot be performed because the LHSI pump will not develop the required flow to open the valve.
At CSD full stroking cannot be performed because testing would require full flow injection to the RCS where there is not sufficient volume to receive the additional inventory. Alternate Test: Full stroked open at refueling per OST 2.11.14 140 ISSUE 1 REV 4
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RELIEF REQUEST ~ 9 Valve No.1 2 SIS *134' 2 SIS *137 "" -2 SIS *135' 2 SIS *138 2 SIS *1361 -2 SIS *139 CategoryJ. C Class 1-Function: KHSI header check valves-to RCS Cold Legs _ l Test Requirement:. Quarterly full stroke s :i Basis for Relief: When 'the RCS is at _ normal operating pressure, full- 'j stroking the header check valves;jcannot be ' performed i because the charging pump will not develop the required flow. 'In addition-injection of relatively' cold water H will cause a thermal cycle or shock resulting in an increased probability of system failure. . At ,CSD full stroking -cannot be performed because full flow testing , could result in ' low-temperature overpressurization of the RCS. Alternate Test: Full stroked open at refueling per OST 2,11.14 RELIEF REQUEST 10 Valve No.: 2 SIS *141 2 SIS *147 2 SIS *142 2 SIS *148 ' 2 SIS *145 2 SIS *151
' Category' A/C Class 1 Function: Safety Injection Accumulators discharge check valves
- Test Requirement: Quarterly full stroke.
{ Basis for Relief: Normal position is closed. Safety function is to open j for passive low pressure injection to the RCS. When the ! RCS is at normal operating pressure, full stroking ' accumulator discharge check valves cannot be performed because the RCS is at a higher pressure than the I accumulators. Full stroking may not be performed during , h cold shutdown because the reduced pressure which is required to perform this test may not be obtainable. In ; addition, stroke testing if attempted at cold shutdown could extend the length of a plant shutdown due to i extensive prepatory work in establishing the proper . reactor coolant system conditions. Alternate Test: Full stroked open at refueling per 2BVT 1.11.3. l 141 ISSUE 1 REV 4
Er < , m. BVPS-2 IST. F RELIEF REQUEST . 11-Valve No.: 2 SIS *545: 2 SIS *546 2 SIS *547 Category C Class l'
' Function: HHSI/LHSI header to RCS Hot Legs check valves-
. -Test: Requirement:;-Quarterly full stroke-
! Basis'for Relief: When the RCS is at normal operating pressure, full .j stroking-the header check valves 1 cannot be performed.
because the charging pump will not develop the required-flow. In addition,. injection of relatively cold water will cause, a -thermal cycle- or shock resulting in an j increased probability of system failure. At CSD full i stroking cannot be performed for 2 SIS *547 because full. flow testing .could result in low-temperature overpressurization of the RCS, Additionally, full a stroking of 2 SIS *545 and 546 cannot be performed because 1 testing would require full; flow injection from LHSI to the RCS where there is not sufficient-volume to receive the additional inventory.. g I Alternate Test: Full. stroked open at refueling per OST 2.11.14 i I
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. RELIEF REQUEST 12 Valve No.: 2 SIS *548 g 2 SIS *550 i 2 SIS *552 Category C Class 1 Function: HHSI/LHSI header to RCS Cold Legs check valves Test Requirement: Quarterly full stroke .j Basis for Relief: Normal position is closed. Safety function is to open for HHSI/LHSI. When the RCS is at normal operating pressure, full stroking the header check valves cannot be performed because the LHSI pumps will not develop the required flow. At CSD full stroking cannot be performed because testing would require full flow injection to the RCS where there is not sufficient volume to receive the additional inventory, l
Alternate Test: Full stroked open at refueling per OST 2.11.14 l 142 ISSUE 1 REV 4
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, RELIEF REQUEST. 13 :
Valve No.: 2CVS*93 P
-Category A/C Class 2 *
~
Function: Containment Vacuum Radiation Monitor Pump discharge l
. header inside containment isolation check valve Test' Requirement: Quarterly full stroke
~
Basis for Relief: Valve is- normally:'open; safety function is closed for containment isolation. Full stroking closedE cannot' be performed during normal operation because this valve is ,. located inside~ containment and 's i inaccessible. In addition, leak testing is required'to verify closure of this valve, and if' attempted at cold shutdown ncould. T delay plant startup. Alternate Test: Full stroked closed by leak test at refueling per l-2BVT 1.47.5. RELIEF REQUEST 14 s
. Valve No.: 2CCP*289 2CCP*290 2CCP*291 4 Category C Clas: 3 Function: CCP to Reactor Coolant Pump . Thermal Barrier Heat o Exchanger supply check valves.
Test Requirement: Quarterly full stroke Basis for Relief: Valves are normally open. Safety function is to close to isolate CCP from reactor coolant if-a leak develops in the RCP thermal barrier ' heat exchanger. Valves cannot be full stroked during normal operation because 1 the valves are located inside the containment and leak " testing is required to verify closure. In addition, leak testing if attempted at CSD could result in a delayed plant startup. Alternate Test: Full stroke closed by leak test at refueling per l 2BVT 1.60.6 143 ISSUE 1 REV 4
3 7 y f, BVPS-2 IST f RELIEF. REQUEST 15 Valve No.: 2CCP*352 Category C ' Class 3 s Function: SC-3 to NNS boundary isolation valve Test Requirement: Quarterly full stroke ~ V Basis'for Relief: Valve. is .normally open. Safety _ function is closed.to g
' isolate NNS from SC-3 component cooling piping. -Testing _
during normal operation cannot be performed because leak testing is required to verity valve closure, which would-cause extended interruption of cooling ' water to the instrument air compressors. In addition, leak testing O' if; attempted at CSD could result in a delayed' plant startup, Alternate Test: Full stroked closed by leak test at refueling per l-2BVT 1.60.6 l
.c RELIEF REQUEST 16 Valve No.: 2 MSS *18 2 MSS *199 !
2 MSS *19' 2 MSS *352 2 MSS *20 2 MSS *196 Category C Class 3
. Function: 1 Main Steam to Auxiliary Feed Pumps Check Valves _4 l
Test-Requirement: Quarterly full stroka I l I Basis for Relief: .Normally. closed, safety function is to open for operation of the steam driven auxiliary feed pump and closed to prevent steam generator cross-connection ; during a high energy line break. Full stroking closed i for these valves cannot be performed during normal ! operation because leak testing is required to verify full closure. In addition, leak testing if attempted at cold shutdown could result in a delayed plant startup. Alternate Test: Full stroke closed by leak test at refueling per l 2BVT 1.60.6 l 144 ISSUE 1 REV 4
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Valve No.: 2SYS*80 2SVS*81' 2SVS*82 Category C Class 2 Function: ' Steam Generators residual ~ heat' release reverse flow-check valves s Test. Requirement: . Quarterly full. stroke Basis for Relief: Valves are normally, closed. Safety positioniis closed to_ prevent cross-connection of steam generators during a high ' energy line break. Full stroking closed for these valves cannot be performed during normal operation because leak testing is required-to verify' full closure. In addition, leak testing if. attempted at cold shutdown could result in a delayed plant startup. Alternate Test: Full stroke closed by leak test at refueling per l 2BVT-1.60.6
' RELIEF REQUEST -18 Valve No.: 2FWS*28 2FWS*29 ,
2FWS*30 Category _ C Class 2 Function: Main Feadwater header isolation check valves Test Requirement: Quarterly full stroke i Basis for Relief: Velves are normally open. Safety position is closed for l Feedwater isolation in the event of a high energy line break. Exercising during power operation is not possible since this would riquire stopping feedwater flow to the Steam Generators, resulting in a plant shutdown. Leak testing is required to verify the valves L are full closed because they have no position indication or weighted arms. In addition, the steam generators must be in wet layup with a nitrogen blanket established to perform this testing. Leak testing if attempted at cold shutdown could result in delayed plant startup. Alternate Test: Full stroked closed by leak test at refueling per l OST 2.24.8 145 ISSUE 1 REV 4
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. Function: Auxiliary Feedwater header to Steam Generators check valves Test Requirement: Quarterly full stroke Basis for Relief: Valves. are normally closed. Safety function is to open.
during Auxiliary Feed System operation. Verification of full stroke closed is. not poseible during' power operation because this involves a leak test. to. be performed with steam generator level 2 85%. Leak testing if attempted at cold shutdown could result in a 'J delayed plant startup.
. Full stroked closed by leak test at refueling per
. Alternate Test: l OST 2.24.8A RELIEF REQUEST 20 Valve No.: 2SWS*MOV103A
, -2SWS*MOV103B Category B Class 3 Function: RSS heat exchangers service water supply isolation valves.
Test Requirement: Quarterly full stroke and time Basis for Relief: Valve is normally closed; safety function is to open to supply cooling water to the RSS heat exchangers. Valve is not cycled during plant operation as failure of the valve in the open position would require plant shutdown. Failure of the valve in the open position at cold shutdown would delay plant startup. (The Service Water System car.not simultaneously support normal plant operation and the RSS heat exchangers)
. Alternate Test: Full stroked and timed at refueling per OST 2.30.13 i.
146 ISSUE 1 REV 4
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, BVPS-2'IST 1 RELIEFREQUE$iT 21-Valve No.: 2SWS*1103 i 2SWS*1104 l 4
Category C Class 3 Function: Service water to main steam valve house cooling headers check valves q Test Requirement: -Quarterly full stroke-
~ Basis for Relief: Valves are normally open; safety position is open to supply cooling water to main steam valve- house- cooling coils,-~and closed to prevent draining the' inlet lines to the MSVH cooling coils during a service water pump trip l on a loss of power. Full stroking in--the closed position cannot be performed during normal operation-because ' isolation of the service water supply. header in conjunction with a leak test is required to verify full.
closure. Isolation of the header is not acceptable because'both SW headers are normally in service. In addition,- leak testing if attempted at cold shutdown y could result in a delayed plant startup._ Alternate Test: Full stroked closed by leak test at refueling'per l 2BVT 1.60.6 RELIEF REQUEST 22 Valve No.: 2EGF*SOV202-1 2EGF*S0V203-1 2EGF*S0V202-2 2EGF*SOV203-2 Category B Class 3 Function: Emergency Diesel Generator Air Starting Solenoid Valves-Test Requirement: Quarterly stroke and time / verify remote pos.ition indication bi-annually , Basis for Relief: These valves are quick acting and do not have position < indication. Operation of these valves will be monitored by timing the starting time to rated speed for each EDG. Individual valves will be tested by isolating one bank of air prior to starting on an alternating frequency. This will insure each bank is capable of starting the EDG in the required time and that the air starting solenoids are not degrading. Alternate Test: Time emergency diesel generator starting time monthly per OST 2.36.1 and 2.36.2. Assign a limiting stroke time based on EDG starting requirements for ESF response time. EDG ready to accept loud 5 10 sec. 147 ISSUE 1 REV 4
l 1 BVPS-2 IST _' RELIEF: REQUEST 23 Valve No.: 2CHS*MOV378 2CHS*473 ,
' Category A and A/C Class 2 Function: - RCP Seal Water Return Line Inside Containment Isolation Valves .
i
. , ; Test Requirament:- IWV 3426 and. 3427(a) require Owner specified maximum l
_ permissable leakage rates fe" -specific _ valves as a ;
'fanction of valve size -and type and provide- the corrective action to be followed when these limits are exceeded.
Basis for Relieft- 'As shown on'the attached figure for Penetration #19, the
. configuration of'this containment penetration ~(i.e., two inside containment isolation-valves in-parallel) is such.
that individuc1 leakage rates for each specific valve egnnot -be ~ determined using the test method of 10CFR50, Appendix J. In this case,. assigning maximum permissable-
;1eakage rates for each valve would not be practical.
Alternate Test: Assign a maximum permissable leakage rate for the entire barrier to then be used as the criteria for initiating corrective action in accordance.with IWV-3427(a). l t f' l 148 ISSUE 1 REV 4 l l-l l
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; RELIEF, REQUESTx -24 LValve No.: 2CHS*A0V200A <
'2CHS*A0V200B H 2CHS*A0V2000 Category' 'A Class 2
' Function:' Reactor? Coolant Letdown Orifice LInside Containment ~*
Isolation Yalves 4 . Test Requirement: LIWV-3426 and 3427(a) require Owner specified maximum permissable leakage rates for specific valves as a
'I function -of valve size 'and type and provid- .the corrective action to be followed when these' limi6. - are exceeded.
Basis for Relief: As shown on the attached figure for Penetration #28, the configuration of- this containment penetration (i.e., three inside containment isolation valves- in - parallel) is such that individual leakage' rates for each specific valve cannot be determined using the test methea of-10CFR50, Appendix J. In this case,- assigning maximum permissable leakage rates for each valve would not be practical. Alternate' Test: Assign a maximum permissable leakage rate for the entire barrier to then be used as the criteria .for initiating corrective action in.accordance with IWV-3427(a). l 1 150 ISSUE 1 REV 4
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Valve No.: 2HVR* MOD 23A 2HVR* MOD 23B' Category- A Class 2 t Function: Containment' Purge Exhaust Fan Containment Isolation. ' Dampers' I ' Test Requirement: '.IWV-3426' and 3427(a) requiro Owner:specified maximum. 'l-permissable leakage rates for specific. valves as -a function of valve. size and type and. provide the 4
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corrective action to be followed when thase limits are exceeded. Basis for Relief: As shown on the attached figure for Penetration #90, the. configuration of_this containuent penetration (i.e., a. single test connection located between two containment isolation dampers in series) is such that -individual leakage _ rates for each specific damper cannot be. determined using the test method of 10CFR50, Appendix J.
- In this case, assigning maximum permissable leakage rates for each damper would not be practical.
Alternate Test:- Assign a maximum permissable leakage rate for the entire barrier to then be used as the criteria for initiating. corrective action in accordance with IWV-3427(a). .l l l l 1 l 1. l l 152 ISSUE 1 REV 4 l' _ _ , . _
is, i. 7 i. L. BVPS 2 IST RELIEF REQUEST 25 i O i W = Z o l N r = . V H w Z !
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BVPS 2 IST RELIEF REQUEST 26 Valve No.: 2HVR* MOD 25A I 2HVR* MOD 25B 2HVR*DMP206 Category A Clast 2 Function: ' Containment Purge Supply Fan Containment Isolation Dampers , Test Requirement: 1RV-3426 and 3427(a) require Owner specified maximum l permissable leakage rates for specific valves as a t function of valve size and type and provide the corrective action to be followed when these limits are exceeded. Basis for Relief: As shown on the attached figure for Penetration #91, the configuration of this containment penetration (i.e., a single test connection located between the three penetration isolation dampers) is such that individual - leakage rates for each specific damper cannot be 5 determined using the tect method of 10CFR50, Appendix J. In this case, assigning maximum permissable leakage rates for each damper would not be practical, Alternate Test: Assign a maximum permissable leakage rete for the entire barrier to then be used as the criteria for initiating corrective action in accordance with IVV-3427(a). l 1 1 ( l l 1 l 154 ISSUE 1 REV 4 l
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c t BVPS-2 IST RELIEF REQUEST 27 Valve No.: 2QSS*SOV100A 2QSS*SOV100B Category A Class 2 Function: Chemical Injaction Pump Discharge to Containment Sump Isolation Valves Test Requirement: 1WV-3426 and 3427(a) require Owner specified maximum l permissable leakage rates for specific valves as a function of valve size and type and provide the corrective action to be followed when these limits are exceeded. Basis for Relief: As shown on the attached figure for Penetration (1118.- the configuration of this containment penetration (i.e., two outside containment isolation valves in parallel) is such that individual leakage rates for each specific valve cannot be determined using the test method of 10CFR50, Appendix 1 In this case, assigning maximum permissable leakage r ;+: for each damper would not be practical. Alternate Test: Assign a maximum permissable leakage rate for the entire barrier to then be used as the criteria for initiating corrective sction in accordance with IWV-3427(a). l l l l. l l l^ 156 ISSUE 1
- REV 4 l
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f l BVPS 2 IST RELIEF REQUEST 28 Valve No.: See next page Category A and A/C Class 2 Function: Containment Isolation ? Test Requirement: IWV-3426 and 3427(a) require Owner specified maximum l permissable leakage rates for specific valves as a > function of valve . size and type and provide the corrective action to be followed when these limits are , exceeded. Basis for Relief: As shown on the attached figure for the penetrations listed on the next page, the configuration of these , containmant penetrations (i.e. two outside or two inside containment isolation valves in parallel, one valve being a relief valve) is such that individual leakage rates for cach specific valve cannot be determined using the test method of 10CTR50, Appendix J. In this case, assigning maximum permissable leakage rates for each valve would not be practical. Alternate Test: Assign a maximum permissable leakage rate for the entire barrier to then be used as the criteria for initiating corrective action in accordance with IWV-3427(a). l l l 158 ISSUE 1 REV 4
BVPS 2 IST RELIEF REQUEST 28 i& .
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Penetration No. 1 Valves 2CCP*MOV157-1 & 2CCP*RV105 Penetration No. 2 Valves 2CCP*MOV150-1 & 2CCP*RV102 Penetration No. 4 Valves 2CCP*MOV151-1 & 2CCP*RV103 - Penetration No. 5 Valves 2CCP*MOV156-1 & 2CCP*RV104 Penetration No. 14 Valves 2SWS*MOV153-1 & 2SWS*RV153 Penetration No. 20 Valves 2 SIS *41 & 2 SIS *RV130 Penetration No. 21 Valves 25WS*MOV155-1 & 2SWS*RV155 , Penetration No. 24 Valves 2RHS*15 & 2RHS*RV100' l Penetration No. 25 Valves 2SWS*MOV154-1 & 2SWS*RV154 ! Penetration No. 27 Valves 2SWS*MOV152-1 & 2SWS*RV152 I Penetration No. 29 Valves 2DGS*A0V108B & 2DGS*RV115 ! Penetration No. 38 Valves 2DAS*A0V100B & 2DAS*RV110 Penetration No. 45 Valves 2RCS*A0V519 & 2RCS*RV100' Penetration No. 55-1 Valves 2SSR*A0V109A2 & 2SSR*RV117 Penetration No. 56-1 Valves 2SSR*A0V102A2 & 2SSR*RV118 Penetration No. 56 2 Valves 2SSR*A0V128A2 & 2SSR*RV120 Penetration No. 56-3 Valves 2SSR*A0V100A2 & 2SSR*RV119 . Penetration No. 57-1 Valves 2SSR*A0V112A2 & 2SSR*RV121 Penetration No. 63 Valves 2QSS*MOV101A & 2QSS*RV101A Penetration No. 64 Valves 2QSS*MOV101B & 2QSS*RV101B Penetration No. 97-1 Valves 2SSR*SOV129A2 & 2SSR*RV122 : Penetration No. 106 Valves 2 SIS *A0V889 & 2 SIS *RV175 i . e l l l l l l 159 ISSUE 1 REV 4 l'
t BVPS 2 IST kELIEF REQUEST 29 . Valve No.: 25WS*106 2SWS*107 Category C Class _ 3 Function: Service water header check valves , Test Requirement: Quarterly full stroke Basis for Relief: These valves ate open during normal plant operation, but , full stroking of the . check valves in the forward direction cannot b2 performed because normal plant operation of the service water system will not develop the required flow. Full stroking of these valves is secomplished by aligning the service water system tirough the Recire spray heat exchangers. This can only ' be ione during refueling outages because the service wate.- system cannot simultaneously support normal plant : opera' ion and the Recirc spray heat exchangers. ; Alternate Test: Partial stroked open quarterly per OST 2.30.2(3)(6). Full stroke open at refueling per OST 2.30.13. , RELIEF REQUEST 30 Valve No.: See next page Category A,B Class 1,2.3 Function: Various Test Requirement: Stroke time trending, IWV-3417(a) Basis for Relief: Stroke times for rapid acting valves are affected by variations in the response time of personnel performing L the test. Therefore, trending stroke times for iapid I acting valves is not practical and relief from trending l these valves is requested. l Alternate Test: Assign a limiting stroke time of 2 seconds to these valves and delete trending requirements. 160 ISSUE 1 REV 4
i L: BVPS-2 IST .{ RELIEF REQUEST 30 RAPID ACTING VALVES- l 2RCS*SOV200A 2LMS*SOV950 2 MSS *SOV10$E , 2RCS*SOV200B 2LMS*SOV951 2 MSS *SOV10$F- l 2RCS*SOV201A 2LMS*SOV952 2HCS*SOV114A i 2RCS*SOV201B 2LMS*SOV953 2HCS*SOV114B 2RCS*PCV455C 2QSS*SOV100A 2HCS*SOV115A i 2HCS*SOV115B 1 2RCS*PCV455D 2QSS*SOV100B 2RCS*PCV456 2QSS*SOV101A 2HCS*SOV133A 2CHS*SOV206 2QSS*SOV101B 2HCS*SOV133B 2GNS*SOV853A 2QSS*SOV102A 2HCS*SOV134A 2GNS*SOV853B- 2QSS*SOV102B 2HCS*S0V134B 2GNS*SOV853C 2SSR*A0V172A-2 .2HCS*SOV135A ' 2GNS*SOV853D 2SSR*SOV128A-1 2HCS*SOV135B i 2GNS*SOVB53E 2SSR*SOV128A 2 2HCS*SOV136A 2GNS*SOV853F 2SSR*SOV129A-1 2HCS*SOV136B 2GNS*SOV854A 2SSR*SOV129A-2 2GNS*SOV854B 2SSR*SOV130A-1 2CVS*SOV102 2SSR*SOV130A 2 2CVS*SOV151A 2 PAS *SOV105A-1 2CVS*S0V151B 2 PAS *SOV105A-2 , 2CVS*SOV152A 2CVS*SOV152B 2CVS*SOV153A 2CVS*SOV153B I 1 l l l 161 ISSUE 1 REV 4
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I L. BVPS-2 IST ! RELIEF REQUEST 31 Valve No.: 2PHS*100 2PHS*111 2PHS*101 2PHS*112 - 2PHS*110 2PHS*113 Category A Class 2 Functions- Containment Isolation (Personnel Air Lock) Test Requirement: Leak tested per IWV-3420. In adds. tion, IWV-3426 and [ 3427(a) require Owner specified maximum permissable i leakage rates for specific valves as a function of valve size. and type and provide the corrective action to be followed when these limits are exceeded. Basis for Relief: These containment isolation valves are leak tested in accordance with 10CFR50, Appendix J, Type B. Since the acceptance criteria for Appendix J Type B testing is more limiting than ASME Section XI, additional leak tasting in accordance with ASME Section XI would be f redundant. In addition, as shown on the attached figure for the Personnel Air Lock, the configuration of this containment penetration (ie. , a single test connection located in the airlock between six airlock equalization valves) is such that individual leakage rates fer each specific valve cannot be determined using the test method of 10CFR50, Appendix J. In this case, assigning maximum permissable leakage rates for each valve would not be practical. Alternate Test: Leak test semi-annually in accordance with Technical Specification 4.6.1.3.b.1, 10CTR50, Appendix J and IWV-3426 per 2BVT 1.47.8. In addition, assign a maximum permissable leakage rate for the entire airlock to then be used as the criteria for initiating corrective action in accordance with IWV-3427(a). l I I , l l l l l l l l 162 SUE 1 REV 4 l
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e j; BVPS-2 IST RELIEF REQUEST 32 Valve No.: 2PHS*201 2PHS*202 Category A Class 2 Function: Cor.tainment Isolation (Emergency Air Lock) Test Requirement: Leak tested per IW-3420. In addition, TW-3426 and
- 3427(a) require Owner specified maximum- permissable leakage rates for specific valves as a function of valve size and type and provide the corrective action to be followed when these limits are exceeded.
Basis for Relief: These containment isolation valves are leak tested in accordance with 10CFR50, Appendix J, Type B. Since the acceptance criteria for Appendix J. Type B testing is more limiting than ASME Section XI, additional leak testing in accordance with ASME Section XI would be redundant. In addition, as shown on the attached figure for the Emergency Air Lock, the configuration of this containment penetration (ie., a single test connection located in the emergency airlock between two airlock equalization valves) is such that individesl leakage rates for each specific valve cannot be determined using the test method of 10CFR50, Appendix J. In this case, assigning maximum permissable leakage rates for each valve would not be practical. Alternate Test: Leak test semi-annually in accordance with Technical Specification 4.6.1.3.b.1, 10CFR50, Appendix J and IW-3426 per 2BVT 1.47,10. In addition, assign a maximum permissable leakage rate for the entire airlock to then be used as the criteria for initiating corrective action in accordance with IW-3427(a). 164 ISSUE 1 REV 4 1
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RELIEF REQUEST 32 ; . b t., Ig. !r ee. E o
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, RELIEF REQUEST 33 l-l' Valve No.: 2RCS*SOV200A 2RCS*HCV250A 2RCS*SOV200B 2RCS*HCV250B 2RCS*SOV201A 2RCS*SOV201B Category B Class 1,2 Function: Reactor Vessel Head Vent Valves Test Requirement:- Quarterly full stroke and time
. Basis for Relief: Valves are normally closed and are only required to be opened'during accident conditions. Westinghouse does not recommend these valves -be tested at temperatures above 200F or pressures exceeding 300 psia. (Reference PSE-SSA-4743, dated February 8, 1985 . " Reactor Head Vent / Cold Shutdown System Testing"). Degradation of the system can result from repeated strokes at greater than these temperatures / pressures.- Full stroking may not be '
performed during cold shutdown because the reduced-pressure which is required to perform this test may not be obtainable. In addition, stroke-testing if attempted at cold shutdown could extend the length of a plant shutdown due to extensive prepatory work in establishing the proper reactor coolant system conditions. Alternate. Test: Full stroked and timed at refueling per OST 2.6.9. l 1 ! l l 166 ISSUE 1 l REV 4 l _ l
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'[ BVPS Unit N;. 2 Enc 1! sura 2 r
i
. l ATTACHMENT 1 i i
LIST OF TECHNICAL CHANGES TO THE UNIT 2 IST PROGRAM (REV.4) e
- 1) The acceptable, alert, and required action ranges of Delta P for the ,
Chemical Inj ection Pumps (2QSS*P24A,B) were expanded using the criteria specified in OM 6 (Operations and Maintenance. Standard No. ' 6). OM 6 also recommends that measurement- of discharge pressure should be used as an indication of - pump degradation for positive displacement pumps instead of Delta P. Because expanded ranges are being used as permitted by IWP 3210, and pump discharge pressure is a better indication of pump degradation for positive displacement pumps, Pump Relief. Request No. 8 (page 45) was added to the IST Program to permit using pump discharge pressure and flow rate for evaluating pump , performance and trending degradation. The Pump Testing Outline Sheets : (pages 19 and 20) for beth the A and B Chemical Injection Pumps were also . revised to include this change in the column for Delta P, and Relief Request No. 8 was referenced.
- 2) The following System 47 (Containment) valves were added to the IST ,
Program as Category A/ Passive Valves (page 105). They will be Type B ; leak tested in accordance with 2BVT 1.47.8 and 2LVT 1.47.10 for the Personnel and Emergency Air Locks as explained in Relief Request No's. 31 and 32 (pages 162-165): ; [2PHS*100) Personnel Air Lock Escape Hatch Outer Door Equalizing Valve t [2PHS*101) Personnel Air Lock Escape Hatch Containment Door Equalizing Valve [2PHS*110] Personnel Air Lock Manual Equalization Valve Outer Door Atmosphere Side (2PHS*lll) Personnel Air Lock Manual Equalization Valve Outer Door Chamber Side , [2PHS*112] Personnel Air Lock Manual Equalization Valve Cont Door Chamber Side [2PHS*113) Personnel Air Lock Manual Equalization Valve Cont Door Containment Side [2PHS*201) Emergency Air Lock Equalization Valve - Outer Door [2PHS*202) Emergency Air Lock Equalization Valve - Cont Door
- The relief requests associated with these changes need NRC approval prior to implementation. All other changes do not require NRC approval.
PAGE 1 0F 4
BVPS Unit N;. 2
; Er,clisura 2 ;
[' Attcchment 1
- p.
' LIST OF TECHNICAL CHANCES TO THE UNIT 2'IST PROCRAM (REV.4)
- 3) The following Relief Valves were added to the IST Program following an !
extensive valve comparison review between the Unit 1 and Unit 2 IST Programs. They will be tested by 2BVT 1.60.5 at refuelings: i [2CIS*RV260A B.C) Reactor Coolant Pump Seal Water Penetration s Relief Valves (page 58) i l [2 SIS *RV858A B C) Accumulator Relief Valves (page 66) [2 SIS *RV8864A,B) LHSI Pump Discharge Relief Valves (page 68) [2 SIS *RV8865) LHSI Pumps Combined Hot Leg Injection Relief f i Valves (page 68) [2ECA*RV205,206, Diesel Cenerator Air Receiver Relief Valves. .
< 207,208) (page 99)
- 4) Added Relief Request No. 33 (page 166) and deleted CSJ No. 3 (page 108) to permit testing the Reactor Vessel Head Vent Valves
[2RCS*SOV200A,B), [2RCS*S0V201A,B), and [2RCS*HCV250A,B] .during refueling outages when proper RCS condi?, ions exist per Westinghouse recommendations ,(temperature less than 200F and pressure less than 300' psia). Full stroking may not be performed at cold shutdown because - the reduced pressure which is required to perform this test may not be obtainable. The Valve Testing Outline Sheet (page 56) was also : revised to reflect this -change by stroke timing each valve per OST r 2.6.9 at refuelings.
- 5) On' page 92, the Main Steam Valve Area Cooler Flow Control Valves
[2SWS*FCV120A,B) were changed from active to passive valves because their NSA position was changed from Automatic to Open. These valves fail open during an accident and are now already open. 6
- The relief requests associated with these changes need NRC approval prior to implementation. All other changes do not require NRC approval.
PACE 2 0F 4 l
s BVPS U2it N>. 2
- l Encl ~ sura 2 i Attachment 1 ,
, c.
LIST OF EDITORIAL CHANCES TO THE UNIT 2 IST PROGRAM (REV.4)
- 1) Under the Pump Testing Requirements Section:
a) Paragraph one on page 3 added as a basis for the IST Program, . Generic Letter No. 89 04, " Guidance on Developing Acceptable Inservice Testing Programs." ,
}
b) On page 4, the guidance for determining if corrective action , should be taken was broadened to include an evaluation of the ' pump's condition with respect to system operability and Technical , Specifications in a manner similar to that in the Valve Testing Requirements Section.
- 2) Paragraph one- on page 47 under the Valve Testing Requirements Section i added .as a basis for the IST Program, . Generic Letter No. 89 04,
" Guidance on Developing Acceptable Inservice Testing Programs."
- 3) The third paragraph on page 48 was reinserted back into the IST Program following deletion from the IST Program in Revision 3A because-it explains how . valves with fail safe actuators (ie., air operated !
valves) are tested.
- 4) For all Valve Testing Outline Sheets (pages 56-104) which reference OST 2.47,3A in the Comments column, OST 2.47.3B has also been referenced. OST 2.47.3B will be performed during refueling outages in place of OST 2.47.3A which is performed quarterly.
- 5) On page 62 for valves [2RHS*15] and [2RHS*107), the NSA position was changed from ADC-S (administrative 1y controlled shut) to LS (locked shut). , .
'6) on page 62, the Comments column for [2RHS*FCV605A,B) was revised to
" Stroke, Time, and Fall Closed" each of these valves. CSJ No. 19 on page 114 was also revised to reflect this change.
- 7) On page 63, the Comments column for [2RHS*HCV758A,B) was revised to
' Stroke, Time, and Fail Open" each of these valves. CSJ No. 21 on page 115 was also revised to reflect this change.
- 8) 2BVT 1.11.3, "SI Accumulator Discharge Check Valve Full Stroke Test" has been revised to include the testing previously performed by OST
- 2.11.15, ' Safety Injection Accumulator Check Valve Test." OST 2.11.15
- vas deleted from the Comments column for valves (2 SIS *141, 142, 145, 147, 148, and 151] on the Valve Testing Outline Sheets (pages 65 and 66). Relief Request No. 10 (page 141) was also revised to reflect l this change under Alternate Test.
I PAGE 3 0F 4 l
- l. ._- . _ _ . ,
'_BVPS Unit N3, 2 Encitsura 2 p Attcchment 1 J .
h e' m LIST OF EDITORIAL CRANGES TO THE UNIT 2 IST PROGRAM (REV.4)
- 9) The referenced Station Log was changed to Log 14 40 and a description of the forward flow test for Main Steam Valve Area Cooler Supply Line i
Check Valves [2 SUS *1103 and 1104) was revised to includo the location of the area where temperature-was being maintained (in the Main Steam l Valve Area) on the Valve Testing Outline Sheets (page 94).
- 10) The referenced Station Logs were changed to Logs L4 29 and L4-32 and a description of the forward flow test for Diesel Generator Air Start Compressor Discharge Check Valves [2EGA** . 00,101,130, and 131) was ,
revised to include more detail on how the check valves are verified i to be opened (D/G start air header pressure is maintained verifying the check valve is open (IWV 3414)) on the Valve Testing Outline
-Sheets (page 99). ,
11).1The Basis for' CSJ No. 18 was revised to say that a verification of forward and reverse stroking requires pump operation "by non rotation of tha idle pump." (page 116) 12)_ The Function for CSJ No. 44 was revised by deleting' the word " check" from the description of the valves on page 129. These are MOV's not check valves.
- 13) All Relief Requests associated with Type C testing _(RR No's. 1, 23, 4 24, 25, 26, 27, and 28) were revised in the Alternate Test and Test Requirements sections to specify "IWV 3427(a)" instead of IWV 3427 in its entirety. Relief Request No. 2 already encompasses IWV-3427'o).
(pages 135, 148, 150, 152. 154, 156,.158)
- 14) The Alternate Tesc sections of Relief Request No's.. 13, 14, 15, 16, 17, 18 19, and 21 were revised to say, " Full stroked closed by leak test at refueling per. . . . . " . (pages 143 147)
L
- 15) Relief Request No. 30 was revised to include a list of " Rapid Acting 1 Valves" (pages 160 and 161).
l l l L l l t l PAGE 4 OF 4 1
,. BVPS Unit N). 2.
J Enc 1: sura 2 p Attcchment'l t BVPS-2 IST RELIEF REQUEST' 7 Pump Mark No(s).: 2EGF*P21A l' 2EGr*P21B 2EGr*P21C ; 2EGP*P21D-Code Test Requirement: Measurement of pump suction pressure (before pump startup and during test) and delta P. Basis for Relief: There is no installed instrumentation provided to-measure auction pressure for these pumps. Suction pressure is dependent on the level in the diesel generator fuel oil storage t ank. Due to- the minimum technical specification level permitted in
'the tank (91,2%), suction . pressure will remain ,
almost constant (within 1/2 psig). The pump performance is dependent on flowrate and delta-P. Since Suction pressure will remain almost constant, any pump degradation due to changes in delta-P would solely be dependent on discharge pressure. Alternate Test: Discharge pressure will be recorded and trended as i an indication of pump performance in OST 2.36.1 and OST 2.36.2. RELIEF REQUEST 8 Pump Mark No(s).: 2QSS*P24A 2QSS*P24B j Code Test Requirement: Measure pump suction pressure AP and flow. Basis for Relief: The function of these pumps is to provide a NaOH ; water solution to the suction of the quench spray pumps during an accident. Since these pumps are rotary positive displacement pumps, flow rate and differential pressure are independent variables. Unlike centrifugal style pumps, it is not necessary to measure both parameters to assess the hydraulic performance of these pumps. i Alternate Test: Pump discharge pressure and flow rate will be utilized for evaluating pump performance in OST 2.13.10A and OST 2.13.10B. 45 ISSUE 1 REV 4 1
Page 9 of 18 PARAGRAPet 110. rnomrspegeluG ipt-6 PAnAEAArti NO. 1 mmm i facLE s:00-1 (cootsmeed) sevgangtlC PammETERS mancts of 7ts? Fatapeffeos Change: aggg* Alert values for hydramifC parameters were deleted. Bests: The general consensus was that test seqsters gestures thst resulted from "htgher than acctPTaste atret massct Acfrow manCE itst tamaMETre massce ge, ref e value* hydraulic meews were egget h* 81 3h cowsed by fastrument flectuations. F (Feettlee .9) to I.IOP .90 to *.9)t -
- 90F. DI.IOP Change:
# "**** r * =ggg= p,,,,gred Action velees were facreesed from 1.03 times reference te 1.18 time reference.
aF(verticot .95 to I.10er .9) to e.95&e _ e*93ay .g gggy j tsee sheft ' e r , Sesis- Altheep peamp bydreolic perfernance is
, rumpe) not espected to feprove, it was decfded to to ;
4 asintain a hip velve for megelred Actlen. 4
% (Feettise .93 to 3. log' .9) to e.93Qr - 4.9)g o g
- 3"r WS esseMs M test 3WMW h
- st eyteae e ressenable, thereby estatalning the quality of
! & vertteel the vibration testf ag. , time shof --
Fumpe) Change-
- tow
- Alert values for hydraulic parameters of centrifogel pumps were deleted.
ht(centrifoget .90 to 3.goey _ ~ Pompe) r '8 980F,*I IO8F' tests
- As stated fa tfie everview, these pesys are tested fa a window of differentiel I (centrifoget .90 to 3.gog Fumpe) r
*8.980,*l.109 pressere and flew. This window f asures that l - the vfbration nesserveents wf11 he repeetable. State the mein euphests of pump
- eperablif ty is besed en vfbretten meeserement, only that parameter has a alert range.
Wete: The sobecript r denotes reference vetoe. Change- " tow" Alert mange for flew rete l measurements of Vertical Llee Shef t Pumps and
- Positfwe 99spiacement Peeps was changed from (0.90 to 0.99) % to 10.9) to 0.951 g, respec tively.
p= Sests: store stringent hydraelle acceptance g gChange.. The acesurement of discharge pressere Change- yhe frement to acasure beerfag criteria f s necessary for these pumps. Thwe j was substituted for differential pressere for are inenerent deficiencies in eftration testing Positive Displacement Pumps. W #re l ared Ilote 2 regarding and degradetless will be Identiffed scener spect f fed I felgs for bearing temperature thmp changas in WaeHc parametm. 94515: Varfattens in talet pressere (sees not araswrements, were deleted. f af fect the discharge pressere for these pumps
- m gs.. Chooge: *Lew* peguired Actfen values for ,
therefore, df scharge pressesre is considered to Annwat seasurement of bearing um 5 not c ed fleurate aroserements of Vertical time shaf t y p, . , be a more appropriate test parameter. p'9e Pemys were changed from 0.90 % to 0.9) %. n :s
,,g
[ Change: IIett 1, regarding intet pressere fahanced utbration testing mes developed to g,g , . , ~ gym Ifelts, was deleted. menf ter this type of degradation. en ci Sesis: Of fferential pressesre fs considered to Canonge- 81ote 3, a reference to IWP-3230 (E o wttcal tf t S be a more meaningful hydrawife parameter for (Corrective Action), was deleted. fisps was hanged from (0.90 to 0.93) Pm to "ug deteroinfng hydraulic performente de M.93 to 0 5 y Pg . . o, i and 5200 now allows *determina t ten
- gradetion of this tests: This note dfd not provide any parameter; therefore, a requirement to measure meanincfwl help. g,,g, , ,
g i @ the inlet pressere and assure-that it fs i dh within established limits is not appropriate. , . i i
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i; BVPS Unit N;. 2 l' (" Encle:ura 2 l l' Attcchment.1' l BVPS-2 IST - RELIEF REQUEST 31 Valve No.: 2PHS*100 2PHS*111 , 2PHS*101 2PHS*112 l 2PHS*110 2PHS*113 l Category A Class 2 , Function: Containment Isolation (Personnel Air Lock) : Test Requirement: Leak tested per IWV-3420. In addition, IWV-3426 and 3427(a) require Owner specified maximum -permissable leakage rates for specific valves as a function of talve size and type and provide the corrective action to be followed when these limits are exceeded.
. Basis for Relief: These containment isolation valves are leak tested in accordance with 10CTR50, Appendix J. Type B. Since the ,
acceptance criteria for Appendix J Type B testing is -' more limiting than ASME Section XI, additional leak testing in accordance with ASME Section XI would be redundant. In addition, as shown on.the attached figure for the Personnel Air Lock, the configuration of this containment penetration (ie., a single test connection located in the airlock between six airlock equalization . valves) is such that individual leakage rates for each specific valve cannot be determined using the test method'of 10CFR00, Appendix J. In this case, , assigning maximum permissable leakage rates for each valve would not be practical. Alternate Test: Leak test semi-annually in accordance with Technical Specification 4.6.1.3.b.1, 10CFR50, Appendix J and IWV-3426 per 2BVT 1.47.8. In addition, assign a maximum permissable leakage rate for the entire airlock to then be used as the criteria for initiating corrective action in accordance with IVV-3427(a). 162 ISSUE 1 REV 4
, BVPS Unit N). 2 i Enc 10 sura 2 l Attcchment 1 ;
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~ RELIEF REQUEST 31 i
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BVPS-2 IST j RELIEF REQUEST 32 f Valve No.: 2PHS*201 j 2PHS*202 : I L Category A Class ,__ 2 ; Function: Containment Isolation (Emergency Air Lock) , Test Requirement: Leak tested per- IWV-3420. In addition, IWV 3426 and 3427(a) require Owner specified maximum permissable l 1eakage rates for specific valves as a function of salve . size and type and provide the corrective action to be followed when these limits are exceeded. Basis'for Relief: These containment isolation valves are leak tested in accordance with 10CTR50, Appendix J. Type B. Since the acceptance ariteria for Appendix J. Type B testing is more limiting than ASME Section XI, additional leak testing in accordance with ASME Section XI would be redundant. In addition, as shown on the attached figure for the Emergency Air Lock, the configuration of this containment penetration (ie., a single test connection located in the emergency airlock between two airlock equalization valves) is such that individual leakage rates for each specific valve cannot be determined using the test method of 10CFR50, Appendix J. In this case, assigning maximum permissable leakage rates for each valve would not bc practical. Alternate Test: Leak test semi-annually in accordance with Technical Specification 4.6.1.3.b.1, 10CFR50, Appendix J and IWV-3426 per 2BVT 1.47.10. In addition, assign a maximum permissable leakage rate for the entire airlock to _ then be used as the criteria for initiating corrective action in accordance with IWV 3427(a). 164 ISSUE 1 REV 4
y, BVPS Unit N). 2-(.
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4 p BVPS Unit No.~2. e E c10 sura 2. , s Attcchment.1 e BVPS-2 IST ) RELIEF REQUEST 33 sValve No.: 2RCS*SOV200A 2RCS*HCV250A 2RCS*SOV200B 2RCS*HCV250B 2RCS*SOV201A 2RCS*SOV201B Category B Class 1,2 Functian:' Reactor Vessel Head Vent Valves Test Requirement Quarterly full stroke and time i Basis for Relief: Valves are normally closed and are only required to be i opened during accident conditions. Westinghouse 'does. not recommend these valves be tested at temperatures above 200F or pressures exceeding 300 psia.. (Reference ! PSE-SSA-4743, dated February P. 1985, ' Reactor Head. Vent / Cold Shutdown System Testing"). Degradation of the + system can result from repeated strokes at greater than these temperatures / pressures. Full stroking may not be performed during cold shutdown because the reduced pressure which is required to perform this test may not be obtainable. In addition, stroke testing if attempted ' at cold shutdown could extend the length of a' plant ; shutdown due to extensive prepatory work in establishing '; the proper reactor coolant system conditions, & Alternate Test: Full stroked and timed at refueling per OST 2.6.9. ! 8 9 1 b 4 166 ISSUE 1 REV 4
BVPS Unit No. 2
.2 Enclosuro 2
- Attachmsnt 1- l l
.9 j
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9 AIL READ N0#04E WARDCOPY I 1 To 04WSHERTY.N.J (38:WTIl0451 Cc: MORRil.E.L (40:s45379) Cc: STEINati!.J.N (ulf64141 Froes ANTAKl.8.4 (WSf7959) Posted: Men 30 Mar-87 13:27 Elf nutject: RHV BYSTEM TElf!NG . E Mail to Daugherty. N.J. PT-SSAD-6013 , March 30. 1987 i Ref.:(1) PSE-55A-4743. 2/0/85 cca R. 9. Jones [ E. L. Morris J. N. Steinset: .
Subject:
RHV lystee Testing I in the referenced letter Westinghouse advised that any testing of the reactor head vent systes should not be perforced when the ACS is at full t
- l. operating pressure. This syntee to analysed to ASME !!! faulted condition b reeutrements, thus, use of the RHv5 at full pressure sould require l
nspection, evaluation, and possible testing and reanalysis. Additionally, L piping svntes def orestion could result free full pressure testing. l The above conditions do not prevent the RHVS free perforcing its intended ' safety' functions for safety grade cold shut 6oun or long tore cooling. The svette is designed f or a once-in-a-plant lif ettee event. shach as assuesd to ' occur in conjunction enth a taulted event (ASME Level 01. For desten (_ , purposes, head vent operation is conservativolv assueed to occur every hour for 6 hours at 2250 psia, and every subsequent hour for 20 beurs at i decreasing pressure free 2250 to 415 psia. A total of 26 cycles of valve I: operations are considered which are eithin the number defined by the various cooldoen scenarios. If anv additional inf ormatson as reautred, please advise. K. F. Accornero APPROVED: l Paping Analvs s 6 Engineering R. 8. Patel, Manager Piping Analysts & Engineering Dispositions
.r. -, . - . . . . . . _ - . ,e _ . . ~ . - - - , . . . ~ - , - . . - . . -. . . - . - , -. ,, -- -
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'U BVPs Unit W . 2 Enclos:re 2' Q '. Attechnent,l' g.
t fj:. ., jj PSE-SSA-443 ; u ,
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. . Plant E.ngineering Division- l
- Fiping Systems Engineering '
A. 262-6024
*n .Fetreary 8, 1985 i
'D
DMW Reactor Head Vent / Cold Shutdown System Testing p , i- .
- i. J. Pichter F W. IUrch c::JC.~J. Brennan t i= .,
='
j. Per our discussion on 2/8/85, it is agreed that the DMW reactor.
; head 'ient/ cold shutdcwn system can be tested to verify that the control- and isolation valves are fully functienal. .
This- can be achieved by coening and closing the valves under " low" .; te arature and pressure (200'F and 300 psia).. r We do r.ut suggest that the system be tested to design temperature , and pressure (620*F'and 2250 psia). This system will only be used : after a plant faulted condition. Please let me know if you need additional information.
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A. C. Chan E h.! APPROVED: N/ fk , Synems Structural Analysis C 'A. Antaki,lianager ' Syster.s Structural Analysis l< p- ; i l
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l EnclCCuro 2 Attachment 2 Overview Describina Unit No. 2 IST Proaram Generic Letter 89-04 has granted approval of all relief requests submitted to the NRC prior to April 3, 1989 which do not fall under ; the guidelines delineated in the Generic Letter. All relief requests added to the Unit 2 IST Program since Revision 0 and 1, and which fall outside of the areas defined in the Generic Letter are considered approved in Revisions 2, 3 and 3A (No new relief requests were added to Revisio7 3A). The following is an overview describing ; how the Unit No. 2 IST Program conforms to all of the items applicable to Unit 2 in Attachment 1 of Generic Letter 89-04 with some exceptions requiring NRC approval:
- 1) The NRC granted all of the Relief Requests in Revisions 0 and 1 of the Unit No. 2 IST Program with the exception of Relief Request No's. 1 and 10. We addressed each of the NRC's concerns which were identified in the SER dated March 18, 1988 in our submittal of Revision 3 to the Unit No. 2 IST Program on January 31, 1989. These concerns included meeting the requirements of ASME Section XI, paragraph IWV-3426, and 3427 in order to be granted Relief Request No. 1 (see Item 2 below).
Also, since Relief Request No. 10 was denied, we provided a new approach which is discussed in Item 3 below. Finally, the SER identified Unit No. 2 IST Program anomalies which were to be resolved in accordance with the staff positions. Each anomaly was addressed cither in accordance with the staff positions or as documented in our submittal dated January 31, 1989.
- 2) Relief Request No. 1 was amended in Revision 3 to the Unit No. 2 IST program to include the requirements of IWV-3426 and IWV-3427(a). This is in compliance with Generic Letter 89-04 and the SER. All Type-C valves in the Unit No. 2 IST Program -
were assigned a maximum permissible leakage rate as a function of valve size and type with a few exceptions. Relief Request No's 23 through 28 were added to the Unit 2 IST program in Revision 3 and are considered approved due to the April 3, 1989 cutoff date specified in Generic Letter 89-04. Relief Request No's. 31 and 32 will be added to the Unit 2 IST Program in Revision 4. These eight relief requests are required because, in a few cases, individual leakage rates fer each valve in a penetration cannot be determined due to the configuration of the penetration. Determination of leakage rates for an entire containment penetration as opposed to specifying leakage rates for specific valves was performed. Relief Pequest No's. 31 and 32 require NRC approval prior to implementation because they fall outside of the guidelines specified in Generic Letter 89-04. In addition, as stated in the Generic Letter on Attachment 1, Item No. 10, relief from meeting IWV-3427(b) is granted by the NRC if documented in the Unit No. 2 IST Program. Relief Request No. 2 documented this deviation from the Code in Revision 3 of the Unit 2 IST Program and is considered approved.
L m Y ;v h, Enclosure 2. Attachment 2 Page'2-r: L3)' The SER denied Relief Request.No. 10 which requested relief from full- stroke exercising the Accumulator Discharge Check Valves- j (2 SIS *141,- _142, 145, 147, 148, 151) . . The NRC recommended a sample- disassembly and inspection of these valves which is the method' specified in _the Generic Letter, Attachment 1, Item 2. c The agreed-upon approach with the NRC was to follow the same
. : course of ~ action as defined for Unit No. 1 which includes' full y stroke exercising these check valves each refueling, The Unit 1 9
' test- procedures for accomplishing this full stroke exercise were submitted for 'NRC review. The NRC requested more information about._the test method used stating. that it -did not appear '
adequate to verify a full-stroke exercise. _ We addressed the-NRC's -concerns in a conference call and fornally submitted supporting information on April 27, 1989. We reiterated our position that the method used eliminates the need to operate in a reduced RCS inventory condition which is necessary if valve-disassembly is considered. Loss of RHR events in the industry 1have. illustrated a need to reduce the duration-and fregaency of activities that require a reduced RCS condition. Considerable man-rem dose savings also exist through the use of our_ test method versus valve disassembly. Although this does not comply with the Generic Letter, Attachment 1, Item 2, we. feel that the method used is adequate to verify a full-stroke exercise of the check valves. It should be understood that if the SER for Unit No. 1 permits this test method then it will also be utilized'at ; Unit No-2.
- 4) Another concern raised by the NRC during their review of the Unit No. 1 IST Program dealt with verifying maximum design accident flow rate individually through check valves in parallel flow paths. The methods specified in the Generic Letter are not used at Unit No. 2 to test valves of this kind. The Unit No. 2 Low
' Head Safety Injection Hot and Cold Leg Check Valves [2 SIS *107, 108, 109, 128, 129, 545, 546, 548, 550] are similar to the valves of concern at Unit No. 1. We presented our methodology for full-stroke exercising these valves, which is similar for both >
. Units, in a conference call with the NRC and formally submitted supporting information on April 27, 1989. Although this does not comply with the Generic Letter, Attachment 1, Item 2, we feel that the method used provides acceptable valve stroking to satisfy code requirements. This methodology has already been proven at Unit No. 2 during our first refueling outage through the performance of Operational Surveillance Test (OST) 2.11.14, "SI Full Flow Test". The method useo at Unit No. 2 and the method to be used at Unit No. 1 during this seventh refueling outage, is still being reviewed by the NRC, and will be addressed in the SER for Unit No. 1.
'-- n,
i~ i cy ' i Enclosure 2. Attachment 2 g Page 3 L
- 5) ~
Generic- Letter 89-04, Attachment' 1,. Item .11 stated that the control room chilled water system pumps and valves are frequently Lerroneously .omitted from the IST Programs.. The Control Room' Refrigeration Pumps- and associated valves, and the Fuel Pool Cooling. Pumps were deleted from the Unit No. 2 IST Program in Revision 2. We were directed by the NRC to submit a letter describing the removal of these components from the Program. This- was accomplished in our submittal dated June 20, 1988. Both h pumps are still considered safety related, but not required to be tested in' the Unit No. 2 IST Program because of alternate means.. - They are- still tested in accordance with balance -of plant testing.
- 6) Several new or revised relief requests were submitted with the Unit No. 2 IST Program in Revision 3 on January 31, 1989. These reliof requests were not granted approval by the NRC in the SER '
dated March 18, 1988. Since then, Generic Letter 89-04-has granted approval of all ~ relief requests submitted to the NRC prior' to April 3, 1989 which do not fall under the guidelines , delineated in the Generic Letter. Those relief requests governed by the guidelines' established in the Generic Letter are satisfied
.and are. considered. approved for implementation. The following is-a discussion on each of these Unit 2 IST Program relief. requests which are considered approved by the NRC and which may be. ,
implemented: a) The Recirculation Spray Pumps (2RSS*P21A, B, C, D] and the p Standby Service Water Pumps (2SWE P21A, B] wers added to , t Pump Relief Request No. .1 in Revision 3 to the Unit No. 2 IST Program because they are currently using a pump curve to compare flowrate versus developed head in their OST's. The recirculation Spray Pumps (2RSS*P21A, B, C, DJ were also added to Pump Relief Request No. 5 to permit-calculation of
= pump suction pressure (Pi) using the level in the dam.
L These components were included in Revision'3 as a matter of completeness to identify to the NRC that the testing of these components had been conducted in this manner since the initial development of the Unit No. 2 IST Program. Previous submittals to the NRC failed to identify these components as being part of the referenced relief requests, [ b) Pump Relief Request No. 7 was added to the Unit No. 2 IST y Program in Revision 3 to permit the use of discharge pressure as an indication of pump performance of the Diesel [ Generator Fuel 011 Transfer Pumps [2EGF*P21A, B, C, D]. R Relief Request No. 6 for these same pumps was revised by 1 deleting the statement that a correction for the recirculation line will be included in the calculation. l l l: l l p
rvn s k > p
, Enclosure 2. Attachment 2
,Page 4 m
Service ; Water Header Check Valves c)- (2SWS*106 and-107] are presently full- stroked. open at refuelings and' partially stroked :open during the quarterly test of the Service Water Pumps. The Unit No. 2 IST Program was revised by Revision 3 to reflect this by incorporating' Relief- Request No. 29. These' check valves can only be full stroked open at a refueling- frequency' when service water flow can be. directed through the Recirculation Spray System' Heat Exchangers. J d) The section titled " Basis for Relief" in Relief Request No. 19 for the . Auxiliary Feedwater Check Valves (2FWE*99, 100, 101] was revised in Revision 3 to reflect an alternate. test- method for performing a leak test. The technical basis for this relief request has not been changed, and the guidelines in Generic Letter 89-04 are still. satisfied. 7). The following relief requests are being added to the Unit No. 2 IST Program in Revision 4 and do not fall under the guidelines of Generic Letter 89-04. NRC approval is required for these relief requests before they can be implemented: a) Pump Relief Request No. 8 is being added to the Unit No. 2 IST -Program in Revision 4 to permit using pump discharge pressure and' flow rate for evaluating pump performance and trending degradation. The Chemical Injection Pumps (2QSS*P24A, B] are positive displacement pumps. OM-6 recommends that measurement of discharge pressure be used as an indication of pump degradation ~for positive displacement pumps instead of Delta-P. Measurement of Delta-P will continue to be obtained and trended until this relief request is approved by the NRC. b). Valve Relief Request No's. 31 and 32 are being added to the Unit No. 2 IST ~ Program in Revision 4 and were previously discussed under Item 2) above. c) Valve Relief Request No. 33 is being added to the Unit No. 2 , IST Program in Revision 4 to permit full stroking and timing of the Reactor Vessel Head Vent Valves on a refueling i frequency instead of every cold shutdown per Cold Shutdown f Justification No. 3. These valves are supplied by l Westinghouse and are not recommended to be tested at temperatures above 200*F or pressures exceeding 300 psia. The reduced pressure which is required to perform this test may not be obtainable at cold shutdown or may require extensive preparatory work in establishing the proper reactor coolant system conditions. Full stroke and timing of these valves will continue to be performed at cold shutdown until this relief request is approved by the NRC. l-l
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q d Listing'of NRC_submittals included in' Enclosure 3 P J r -i L . - June 20,:1988; BV-2-Inservice Testing Program, Revision 2-1
*- - January-31, 1989; BV-2-Inservice. Testing Program, Revision'3-' -
l I
* : April 2 7 ,- 1989; Response to Questions on the Unit No..l':IST:
Program
*- September 19,~1989; BV-2 Inservice Testing Program, Revision 3A~
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B a er vaney Power $ tats Shen 9 port. PA 160774004 ' 1 4 s.OL.,w
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' June 20,-1988 U.;S'. Nuclear Regulatory. Commission.
Attn: Document' Control Desk washington, DC' 20555'
Reference:
Beaver Valley' Power Station,. Unit No. 2 Docket No. 50-412, License No. NPF-73 g BV-2 Inservice Testing (IST) Program, Revision 2 s
-Gentlemen: '
. During our investigations to resolve the concerns raised ~by the "
L.. . NRC in the Technical Evaluation Report (TER) to the-BV-2;IST Program- l
-(revisions 0 ;and 1), it was noted that-revision 2 was not submitted
? to the NRC for review. Revision 2 to Lthe BV-2 IST- Program ~ ! L incorporated several editorial changes and deleted the Control Room Refrigeration Pumps [2SWS*P25A,B] and- the Fuel Pool Cooling Pumps : (2FNC*P21A,B] from the. IST Program. effective January 28, 1988. A l statement: was made in the letter from the NRC (dated March 18, 1988) ' attached 'to .the Safety Evaluation Report- (SER) for the BV-2'IST Program stating that, " Program changes such as revisions to
- additional relief. requests or deletion of any components from the IST .
program should be submitted for our review, but should not be- ' implemented prior to-review and approval." In .a telephone conference call with the NRC (Peter Tam - et. al.) : ! on Friday, June 3, 1988, while discussing Anomaly No. 5 in Appendix C L to the TER on the BV-2 IST Program, the NRC was notified that these L pumps had been deleted in revision 2 to the BV-2 IST Program. We I, w
.ere directed to provide a letter of justification for deleting these pumps 'and a discussico on Anomaly No. 5 to document the changes which were .made. They also stated that revision 3 to the BV-2 IST Program, L 'which will include more editorial changes and any program changes L required as a result of our resolutions to the NRL's concerns in the 1 TER, should be submitted' for NRC review with sidebars in the page -
' margins . indicating any changes made since revision 1 to the BV-2 IST ,
Program. The BV-2 IST Program is currently operating under revision 2. The following discussion will provide the history leading to this l revision, and the justification for deleting these pumps.
. c,c m> c ; 2,,.
a;
-B30Vor Vc11cy Powar ction, Unit- Ro. 2 Dockst No. 50-412, Lic3n03 No. NPF-73 Page 2 Anomaly No . . 5 discussed two service Water Valves [2SWS*TCV101A) and (25WS*TCV101B] which were under-consideration for inclusion in
-the IST Program as Category B valves to be tested to the code requirements. Question / Reply 0 - 11 of the BV-2 Trip Report for the February 11 and 12, 1987 working meeting stated that these valves had been included in the IST Program as Category B valves. These valves were to be included in revision 1 to the BV-2 IST Program issued on April 15, 1987, but were not. A decision not to include these valves was made because. the Control Room Refrigeration Pumps (2SWS*P25A,B]
were going to be deleted in revision 2 to the IST Program. There was. insufficient time to delete them from revision 1 prior to submittal of the program to the NRC. Unit 1 was in the process of deleting similar pumps and valves from their IST Program. Both the pumps and valves were determined not to have a safety reisted function as , defined in ASME XI, Section IWP-1100. Unit I was also in the precess L of deleting their Fuel Pool Cooling Pumps (2FNC*P21A,B) from their i IST Program. BV-2 decided to do the same, and deleted these pumps in revision 2 to the BV-2 IST Program. The Control Room Refrigeration Pumps and Fuel Pool Cooling Pumps were determined not to be required to perform a specific function in , shutting down the reactor or in mitigating the consequences of an accident. A redundant means of cooling the Control Room to permit occupancy under accident conditions has been provided by two service water cooling coils located in the Control Room Air Conditioning . Units. There are no postulated accidents associated with failure of the Fuel Pool Cooling Pumps. Redundant means for hookup of temporary pumps and supplemental water supplies have been provided. Neither pump was required to meet the-ASME XI Code, so they were deleted from-the BV-2 IST Program in revision 2. The BV-2 IST' Program is also currently being reviewed to make the ! Unit 1 and Unit 2 IST Programs more consistent. Revision 3 to the BV-2 IST Program is expected to be approved and forwarded to the NRC in-the fall of 1988. l If you have any questions, contact me or members of my staff. L Very truly yours, l D. ANki - Siebsr ice President, Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Project Manager Director, Safety Evaluation & Control (VEPCO) l l l
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l i O F D<ND Pt6tn vce Presassat . Nucaser Group 4412) 64M255 January 31, 1989' U.'S, Nuclear Regulatory Commission i L Attn: Document Control Desk Washington,3 DC. 20555 L
Reference:
Beaver Valley Power Station, Unit No.'2
' Docket No. 50-412,' License No. NPF-73 4 g Inservice Test Program, Revision 3 Gentlemen:
- 0 Attached for your review as Enclosure 1 is the Beaver Valleyr
-Power, Station, : Unit No. 2 first interval- Inservice -Test (IST)-
~~ Program. . This submittal- represents Revision 3 to the program. As previously discussed, this submittal contains all revisions proposed' ,
(since the NRC's review of Revisions 0 and 1 for which your-review was
. documented in the NRC Safety Evaluation' Report dated: March 18, 1988.
L Changes- to the IST program since Revision 1 was issued are
- L summarized in Attachment- 1 to this submittal. The following.is an
- overview. of the changes contained .herein and the conversations '
influencing this program submittal..
- 1. During a telephone. conference call on June 3, 1988, we discussed four. aspects of the IST Program, some of which were addressed in
.a letter to the NRC dated' June 20,.1988.
' Revision 2 of the IST Program primarily contained editorial changes from Rev. O and 1, however, we did delete the Control' Room Refrigeration Pumps and the Fuel Pool Cooling Pumps. We were directed to submit a letter describing the -
removal of these components from the program; this-was 4 accomplished in our submittal dated June 20, 1988. Reference to these components is included in Attachment 1 (page 7 of 16). Preparation of additional relief requests (RR 23 thru 28) addressing determination of the leakage rate for an entire containment penetration as opposed to specifying leakage rates for specific valves. (Attachment 1; page 16 of 16) hu , ,s irr , , o a vca./ wst r dpp.
~
o 's l BeOvarLVallsy.Powar'Stu.lon, Unit-No. 2 !
, Docket No. 50-412, License No. NPF-73 (Inservice Test Program, Revision 3' ;
'Page 2 1
The NRC SER denied relief request 10 which' requested relief from full stroke exercising the-accumulator discharge check
-valves. The agreed-upon approach was to follow the same course of _ action as defined for Beaver Valley Unit No._1 which. includes full stroke exercising these -valves each refueling. . The test procedures for accomplishing this full-stroking were submitted for NRC review. Upon'a final NRC disposition of our proposed testing of these valves, Unit i No.' 2 will follow the-same approach agreed upon with the NRC for Unit No. 1. (Attachment 1,-page 15 of-16) "
Since--the NRC has reviewed Rev.- O and Rev. 1 of-the IST Program and we have issued a Rev. 2 and are now submitting a Rev. 3, _the NRC-requested we sidebar all revisions in this
- submittal.- Many revisions are editorial in' nature and some l are technical. Sidebars in the left margin are editorial L 'and those in the right margin are technical. Additionally, each sidebar has been identified as to whether it was a Rev.
2 "or a Rev. 3 change. As previously stated, changes to the-IS? Program are summarized in Attachment 1. This request .i was reiterated during a conference call on July 12, 1988.
- 2. During a telephone conference call on July 12 and again on July 26, 1988, the-following was discussed:
Sidebar the revisions as discussed above. In our letter of June 20, 1988, we stated the Fuel Pool Cooling' Pumps performed no sEfety related function as defined -by ASME XI, IWP-1100. We were advised by the NRC that if we should consider these pumps as non-safety related, then Standard Review Plan 9.1.3 identified- < additional criteria which would have to be addressed. 'We i consider these pumps safety related, but.not required to be L~ tested in the IST Program. They will be tested with balance l of plant testing. (Attachment 1, page 7 of 16) In- our Relief Request No. 19, we explained we had removed some information contained in the Basis for Relief in Rev. 2. We were requested by the NRC to reinsert that information or provide details justifying the change. This has been addressed in Rev. 3 (Attachment 1, page 15 of 16)
- 3. During a conference call on September 14, 1988, we discussed the parenthetical explanations of various abbreviations in the Pump Testing Requirements Section of the IST Program. These were removed to be consistent with the format of the Unit No. 1 program. (Attachment 1, page 1 of 16) ,
r
i l 4
-Be2V3r Volley Pow 3r Sth.lon, Unit No'.2 Docket No.- 50-412, License No. NPF-73 zInservice Test Program, Revision 3 Page 3 We have also addressed each of - the NRC's concerns which were identified _ in the Safety Evaluation Report (SER)/ Technical
-Evaluation Report (TER) dated March 18, 1988. These-; concerns included meeting the requirements of Section XI, paragraph IWV-3426 ,
and 3427 in. order to be granted Relief Request No. 1. Also, since-Relief Request 10 was- denied, we have-provided a new approach'as discussed above. Finally, the SER/TER identified IST Program anomalies which were to be resolved in'accordance with the staff positions. Each anomaly has been addressed either in accordance with the staff position or as documented above following discussions'with , the staff. As indicated in Attachment 1, some changes to the IST Program consist of revised or additional relief requests or the deletion of components from 'the Program. In your SER dated March 18, 1988, you indicated that program changes of this type should not be implemented without prior review and approval by the NRC. As such, we have individually listed those Revision 3 Program changes in Attachment 2, not previously discussed with the NRC, to expedite the NRC's identification and review of those changes requiring approval. The remaining changes identified in Attachment l' are-either implemented (as a result of. Revision 2 being effective prior to receiving the NRC's review and approval guidelines in the SER/TER) or will be implemented prior to the Unit No. 2 first refueling outage. ' Please be advised that we are ' preparing to make two other technical changes in the near future which should be incorporated into Revision 4. The first change is to delete the Standby Service Water Pumps [2SWE-P21A,B] from the program, and the second change is to revise the frequency for testing the Auxiliary Feedwater Pumps [2FWE*P22, 23A, 23B) from monthly to quarterly. Any affect that these two changes would have on any valves would also be' included in-Revision 4. Both of these changes are pending their associated Technical Specification changes (currently under development) and a will not be made until the Technical Specification changes are i approved. We consider receipt of the Technical Specification amendment as NRC approval to implement the changes in the IST Program. i i Several other changas are still being evaluated for consideration (i.e. addition or deletion of valves from the Program as a result of the continuing in-depth reviews and comparisons between Unit No. 1 and Unit No. 2 systems and components). Any Program changes will be 1 ovaluated against the guidance provided in your March 18, 1988 Unit i No. 2 SER/TER with respect to submitting specific items for NRC l cpproval prior to implementation. l l
f BeOvcr Vallsy>Powar-Stu. ion, Unit No. 2 '
. Docket No.:50-412', License No. NPF-73
, Inservice Test Program, Revision-3.
Page 41 In ' addition,- the- Unit No. 1 IST Program 11s currently being-reviewed to ensure consistency with the Unit- No. 2 Program. . a , revision to .the Unit No.. 1 Program will. be made to correct any ;
' inconsistencies where we consider it appropriate.
If you- have any questions regarding this submittal, please contact me or members of my staff. Very truly yours,
. i J.
kk D. Sieber Vice President Nuclear Group Attachments / enclosure
'cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator-
- Mr. P. Tam, Sr. Project Manager w/o attachments / enclosure Mr.-T. M. Gerusky, Director BRP/ DER Mr. R. Janati, BRP/ DER Director, Safety Evaluation & Control (VEPCO) l l
l l
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@ @ g.sg., no.., smion SNooingport. PA15077 0004 '
l Laodo sisena .
, vce Prescent , Peactee< Group id12' 643 5266 April 27,'1989 U. S. Nuclear Regulatory Commission Attn: ' Document Control Desk Washington,-DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 $ Docket No.1 50-334, License No. DPR-66
- Response.to-Questions on the Unit No. 1 IST Program-Gentlemen:
! The enclosed attachments have been prepared in response to -. i questions; telecopied to.my staff regarding the Beaver Valley Unit-
,No. 1 Inservice Test .(IST) Program. On ' January 19, 1989,~a !
conference . call between'ay staff and the NRC's staff addressed-six i 2 issues = regarding the; Unit No. 1.IST' Program. The attachments to 'i this; letter provide the NRC's questions.and'our responses. , As a result of. these' questions, several IST Program. changes' have been1 developed. Attachment 3 is' a copy of our program
. changes -for you to incorporate into your-copy of our IST Program- 7 Lfor Unit No. 1. We are presently following revision:3 of our-program, which is the same revision currently under review by the NRC. 'The above referenced questions, which are a result of this-review, identify the reviewer's concerns. Since we reached verbal <
, agreement during our conference call regarding~ the reviewer's ,
concerns, these subsequent-IST program-changes will be implemented prior to Unit No. 1 entering our seventh refueling outage, scheduled to begin September 1, 1989.
.If you have any questions regarding this submittal, please call me or members of my staff.
Very truly yours,
. . D. Sieber hvicePresident Nuclear Group
' Attachments (3)
- 1. Response to NRC Questions
- 2. LHSI Full Flow Acceptance Criteria Methodology
- 3. Revisions to Inservice Test Program for Unit No. 1 (Rev. 4) i-
,E nwaa>vt<~ w w L9 PP-
aj ggc , w fif :Be vOr Vallcy Pow 0r' Station,-. Unit-No.f1 Docket '. No.- 50-33 4, w License - No. : DPR-66
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, i cc : ' Mr.;J. Beall', Sr. Resident Inspector ' ~t
?
Mr.:;W.:T. Russell,.NRC Region I Admini.strator :( Mr..P.-Tam, Sr.--Project Manager i
- Director, Safety Evaluation & Control-(VEPCO)
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c ATTACHMENT 1 ~ Response.to NRC Questions Regardina the Unit No. 1 IST Procram
- 1. - . Valve relief- request -6 asks relief from quarterly exercising l
and. -timing of category A valve MOV-CH-142, residual heat i removal -letdown to the chemical and volume control system. . It - 4 appears that. this . valve has only a passive ~ safety function.<
.If so, - this . valve.is.not required to be exercised and timed.
-The- valve was categorized A passive in the previous program '
-submittal' and it appears that the licensee has incorrectly )
changed: the categorization. If indeed this valve is passive, then the licensee should delete this~ relief request.
Response
Valve MOV-CH-142 had been conservatively classified as active in- Revision 3 .of the IST Program since it can be used in a-flow path for bringing the plant to a cold shutdown. During the conference call, the NRC consultant, EG&G, questioned the. need for this classification. We agreed to classify the valve-
.as passive. We have. revised our program (Revision 4) to change. the valve classification to passive on the Valve Outline Sheet and delete relief request (RR) 6 which was based on the requirement for stroke testing an active valve.
i
- 2. Valve relief request 17 asks relief from quarterly exercising ;
of category -A/C valves S1-10, SI-11, SI-12, SI-15, SI-16, and SI-17, -low head safety injectica cold and hot leg check l valves. The. licensee has proposed to exercise these valves during refueling outages. How is the licensee verifying that these valves individually full stroke exercise? ResDonse: As- stated during the conference call, check valves SI-15,. SI-16 and SI-17 are located in the three parallel recirculation branch lines from the Low Head Safety Injection (LHSI) system to. the Reactor Coolant System hot legs. The , valves are located upstream of the connection of the High Head ' Safety Injection (HHSI) system branch lines to the LHSI system branch lines. The LHSI pumps are no longer used to deliver flow via these branch lines to the Reactor Coolant System hot legs during the post-LOCA hot leg recirculation mode on Beaver Valley Power Station Unit 1; only the HHSI system is used for this function. Consequently, when operating in the hot leg recirculation mode, LHSI check valves SI-15, SI-16 and SI-17 are not required to open. Agreement was reached to change the classification of these valves in the Unit No. 1 IST Program from Active to Passive. Our program has been revised to change the valve classification on the Valve Outline Sheet and we have deleted reference to these valves in RR 17 since stroke testing is not necessary.
._ _ _ . _ . _ _ _ _ _ . . _ _ _ _ _ _ _ ~ _ _ __
p g, E Att2ch00ntl1 . j L' Response-to NRC Questions Regarding j g the Unit No.11IST Program J .Page 2 \: L
, check valves SI-10, SI-11 and SI-12 are located in the three parallel injection branch lines from the- Low Head Safety-
]
l Injection (LHSI) system to the Reactor Coolant System cold legs.. To satisfy the stroking requirements, these valves will
'ba exercised during refueling outages as part of a full. flow H L test of the LHSI system. A description of the test J methodology: .and justification that the test is suitable for full-stroke exercising the subject check velves is provided-in. ,
the response to NRC Question 4. !
- 3. Valve relief request 18 asks relief from quarterly exercising of category C valves SI-20, SI-21, and SI-22, combined' low head and high head safety injection hot leg check valves. The licensee has_ proposed to exercise these valves during.
refueling outages. How is the licensee-verifying that these valves individually full-stroke exercise and is hath high head and low head combined flow .necessary for a full-stroke exercise (maximum design accident flow rate)? Note: Valve relief request 18 also includes valves.SI-100, SI-101, and SI-102. These valves are in flow rate i instrumented high head safety -injection lines and can be individually verified.to-full-stroke exercise.
Response
During the conference call, we explained that check valves SI-20,. SI-21 and SI-22 are located in the three parallel recirculation branch lines from'the Low Head Safety' Injection. (LHSI) system to the Reactor Coolant System hot legs. The
. valves are located downstream of the connection of the High Head Safety Injection (HHSI) system branch lines to the LHSI system branch lines. The LHSI pumps are no longer used to <
deliver flow via these branch lines to the Reactor Coolant System hot legs during the post-LOCA hot leg recirculation mode on Beaver Valley Power Station Unit 1; only the HHSI system is used for this function. Consequently, when operating in the hot leg recirculation mode, LHSI check valves SI-20, SI-21 and SI-22 will function similar to HMSI check valves SI-100, SI-101, and SI-102 and will experience only HHSI flow.
Attach:dnt 1E JResponse tcf NRC Questions Regarding !
;the-Unit No.1 IST Program ;
lPage , 5 As. a result of further review, we proposed that sincercheck valves SI-20,1 SI-21 and SI-22-will only experience NHSI flow, they -will be individually verified to full stroke exercise in a manner similar to NHSI check valves SI-100, SI-101 and ; SI-102 as part 1of the NHSI full flow test utilizing-tho' flow j instruments in the individual HHSI lines.- Sines the maximum-design accident flow rate for the subject valves is NHSI flow,. only HHSI -flow will be used to full-stroke-exercise these check. valves. We have provided a revised' Basis for Relief in RR 18 to a basis 'used for other HHSI branch line check valves (ie: SI-83, 84 in RR22). .
- 4. Valve relief request 19 asks relief from quarterly exercising of- category A/C . valves SI-23, SI-24, and SI-25, combined low head and high head safety injection cold leg check valves.
The licensee has proposed- to exercise these valves during refueling outages. How is the licensee verifying that-these - valves individually full-stroke exercise and is hath high' head. and low head combined flow necessary for a full-stroke exercise.(maximum design accident flow rate)? - i,
Response
We- presented our methodology for full-stroke exercising these valves during the conference call. We believe our testing provides acceptable valve stroking to satisfy code requirements. Due to thn complex discussion that took place, and 'since it represents a- new approach'for defining check , l valve operability 'in parallel flow paths, it was agreed that we would submit our methodology for NRC review. ~ Check valves SI-10, SI-11 and SI-12, SI-23, SI-24 and SI-25 are located in the three parallel injection branch lines of u l the Low Head Safety Injection (LHSI) system to the Reactor coolant System cold legs. The LHSI system is not designed with' flow instruments in the individual branch lines but does include flow instruments in the discharge header of each LHSI pump for use in determining total flow delivery from a-LHSI pump.. Total flow instruments are typically used during plant startup testing to provide system flow test data that is evaluated against acceptance criteria to verify that the LHSI system performance exceeds the design basis upon which the FSAR accident analyses are based. Since plant startup programs typically utilize LHSI full flow test data to verify compliance with system design bases, Duquesne Light Company initiated an evaluation to determine if a periodic LHSI full flow surveillance test could be used to verify continued acceptable performance of the LHSI system, including acceptable operation of the subject check valves.
i j Att0chmOnt'l' . I Response to NRC-Questions Regarding -
- the Unit No'.1'IST Program Page 4 ,
i l Based
' test on .this evaluation, of- the. LHSI system is an acceptable method.to determine it is concluded that a full flow j continued acceptable operation. of the LHSI. system,. including j acceptable operation of 'the subject check valves. The basis for- this conclusion is that a- quantitative full flow j acceptance criteria- can be established that, if satisfied, will confirm thac.the flow rates in the LHSI injection branch lines exceed the. minimum safeguards. flow rate requirements assumed in .FSAR accident analyses. Test results that satisfy -
]
the. F5AR accident analyses requirements:also verify acceptable operation of the subject check valves. n Duquesne Light company's evaluation has revealed additional insight into the use of a full flow test to verify acceptable branch line flows. The evaluation has shown that for a full flow test to be acceptable, the test must utilize quantitative flow acceptance criteria that- verifies acceptable flow distributionL in the three LHSI system injection branch. lines as well as total system flow. Furthermore,.the evaluation has shown that the requirement to verify acceptable flow . distribution in the LHSI injection branch lines is the most-limiting. with respect to the development of a full flow acceptance criteria. The resultant full flow- acceptance-criteria is very restrictive relative to the best estimate LHSI full flow. .Although very restrictive, an acceptance criteria can be developed that can function as a screening criteria for acceptable system performance, including check valve operation. Obtaining test- results that= satisfy the acceptance criteria will verify that actual LHSI system flow ' rates (i.e., both total flow and branch line flows) exceed the minimum LHSI flow rates taken credit for in the FSAR accident analyses. Since the flows in the branch lines exceed the FSAR accident analyses requirements, it can be concluded that the check valves in each branch. line are opening acceptably. Alternatively, failure to satisfy the acceptance criteria only indicates that actual LHSI flow rates may not satisfy design , basis requirements. In this situation, the test is inconclusive since the acceptance criteria has been developed as a screening criteria based on worst case assumptions with respect to adverse effects on flow distribution. LHSI flow rates and operation of the subject check valves may still be acceptable, however, additional testing and/or evaluation is [ needed to determine compliance with FSAR accident analyses L requirements. l l e-, avn e ,a -v,n -._-m* ....m,,,-,.,_,mm. --,-.__--,..,-._.,._-r-.._w-.m-_ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _
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. . . - .. ]
Attschm:nt 1 Response to NRC Questions-Regarding ithe Unit No.1>IST Program. j 4 Page 5 1 > Attachment- 2 provides a detailed description of. the
', , methodology developed to define full flow test acceptance criteria that will verify acceptable: operation of: the subject ,
1 check valves. Based 1on the information presented in the 4
' attachment, it is concluded ~that full flow test-results that ;
satisfy test- acceptance- criteria will serveLto verify that both total- LHSI system and branch line flow rates are greater than the minimum safeguards flow requirements assumed in the FSAR. accident analyses. Verification that branch line flows exceed -FSAR: . requirements confirms that the subject': check valves are individually opsning acceptably to satisfy design
-basis requirements.
The full ficy -test and associated acceptance criteria have been developed such that only LHSI flow is required to test for acceptable- opening of the subject check valves. The " methodology used to develop the acceptance criteria takescinto consideration the interaction of High Head Safety Injection (HHSI) flow and LHSI flow in the pip!ng sections that contain check valves SI-23, SI-24, and SI-25.: Although the test is performed. with only LHSI flow, the acceptance criteria is developed to ensure that both NHSI and LHSI minimum safeguards' e flow requirements will be satisfied when both pumps are operating. l i l Finally, Duquesne Light company is now performing a review program _for check valves installed in safety related systems of BVPS Units 1 'and 2. This review, which utilizes the guidelines of- EPRI Project RP-2233-20,. Application Guidelines E for Check Valves -in Nuclear Power Plants, includes a determination of: the . minimum flow velocity required for full disc lift. For the subject 6-inch check ' valves, the preliminary results of the check Valve Review Program for minimum flow velocity for full disc lift were compared against the individual LHSI branch line. flow rates that are required to satisfy the LHSI full flow acceptance criteria. The conclusion of this comparison is that the LHSI system branch p line flow rates that are required to satisfy the LHSI full flow acceptance criteria are greater than the flew rates required to satisfy the minimum flow velocity requirement for check valve full disc lift. Consequently, test results that satisfy the LHSI full flow test acceptance critoria will not u only verify acceptable check valve operation from an accident anlyses standpoint but should also be sufficient to individually full-stroke exercise the subject check valves. This preliminary conclusion will be confirmed following completion of the check Valve Review Program. l l
w - - ~ . - il , Attnchm:nt 1 Response to NRC Questions Regarding.
. the Unit No.1 IST-Program Page 6 ,
l (5. Valve relief request 21 asks relief from quarterly exercising of category A/C valves SI-48, SI-49, SI-50, SI-51, SI-52, and 7 SI-53, safety injection accumulator series discharge check J valves. The method that the. licensee is utilizing to y full-stroke exercise these valves does not appear to- be " adequate to verify a full-stroke exercise. The data obtained i from this. testing appears to contain'an excessive amount of data scatter. 1
Response
A discussion- about the. data scatter revealed one data point t which stood out from the rest. This was explained as'being a ' result of test conditions being different from previous tests l- since the reactor coolant system (RCS) was not verified to be j' solid in the loops. As a result, when the 'C" accumulator a flow test was performed, the pressurizer did not measure the l- total insurge to the RCS. Subsequent testing improved test l' conditions -which resulted in closely correlated test data. - This explained the apparent data scatter to the reviewer. Since the reviewer's concern was addressed, our method of full i ! stroke exercising these valves was to be further evaluated. l The reviewer did not request any further information pertaining to this question. ' l We would like to: reiterate our position stated in earlier l correspondence regarding the determination of valve L operability. This test method eliminates the need to operate in a reduced RCS inventory condition which is necessary if valve disassembly is considered. Loss of RHR events in the
, industry have illustrated a need to reduce the duration and frequency of activities that require a reduced RCS inventory L condition. Considerable man-rem dose savings also= exist i
through the use of our test method versus valve disassembly.
- 6. Valve relief request 36 for the emergency diesel generator air start solenoids does not have sufficient technical justification to be granted relief. Also, the proposed timing method on a refueling outage frequency is inadequate. Would it be possible for the licensee to utilize the same relief request for which Unit 2 was granted relief (Unit 2 SER dated January 25, 1988)?
- p p ceav -+vy-v - g -- v m- '--M v
. AttOcha:nt~1 -t RO;ponto;to NRC quo 3tien3 Regarding
- the Unit No.1-IST Program ,
i Page 7:
- i
' Resonnas:
During the conference call, the design differences lbetween the
;two units diesel generators was discussed. Unit No.1 cannot- '
perform testing. in a manner identical to Unit No. 2.- We proposed revising the monthly diesel generator test,to stroke and' . time. the solenoid . operated valves using the alarm circuitry of the diesel generators. The.NRC agreed with'this approach. Our program. has been revised to change the wording ofLthe relief request to use the diesel generator start failure alarm ' to time the valve strokes. l 5
'l l~
l l - L L L l l-a
6 ATTACHMENT 2 Pigo 1 of 10-4 DESCRIPTION OF LHSI FULL FIDW ACCEPTANCE CRITERIA METHODOLOGY ; This attachment describes the methodology for developing acceptance-criteria for the Low Head Safety Injection (LESI) system full flow test. Acceptance criteria developed to this methodology ensure that actual.LHSI system flow rates are greater than the minimum s safeguards design basis flow rates used in FSAR accident analyses. Satisfying-the acceptance criteria also. verifies acceptable ; operation of the LHSI system check valves, including check valves SI-10, SI-ll, SI-12,-SI-23, SI-24 and SI-25 on Beaver Valley Power Station Unit 1. Attached Figure A provides a simplified schematic of the Unit 1 LHSI system that identifies the subject check valves. Figures B-
- and C illustrate the application of this methodology to Beaver Valley Power Station Unit 1. Figures B and C are based on work currently being performed on Beaver Valley Power Station Unit 2 to '
l develop LHSI full flow acceptance criteria utilizing this methodology. Following completion of the Unit 2 acceptance criteria, the methodology will be applied to Unit 1. The activities and elements that comprise the LHSI Full Flow Acceptance criteria Methodology are itemized and described below: i l Item 1) Identify FSAR Accident Analyses Reauirements for LHSI Flow I l l-The first activity was to review the functional and performance design basis requirements for the LHSI system to identify the requirements for LHSI flow. These requirements consist of a number of cases which identify the minimum safeguards flow requirements which are used in the FSAR accident. analyses. Several of the cases take credit for total injection flow from all three LHSI branch lines. Other cases take credit'for injection flow from only two out of the three injection branch lines, assuming that the injection line with the largest flow rate spills to containment via the Reactor Coolant System pipe break. These two types of cases are referred to as the no spilling line cases and the spilling line cases, respectively. For a full flow test to verify acceptable operation of the LHSI l system, acceptance criteria must ensure that both the no l ' spilling line cases (i.e., total flow from all three injection branch lines) and the spilling line cases (i.e., flow from only two out of three injection branch lines) are satisfied. Spilling line flow requirements are also referred to as branch L line flow distribution requirements. l This review also identified the assumptions, analyses and l analytical model of the LHSI system used to calculate the LHSI minimum safeguards flow rates used in the FSAR accident analyses. l l t-, - - ...- ._. . - , . _ . _ . . , - . . - _ . _ . - , , . . . - . _ , , - . . - . _ . - . , . _ _ - - . _ _ . . _ - _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ _ _
U? l
' ATTACHMENT 2 Pago.2'of 10 Item 2)- Identify Actual LHSI= Flow Performance Plant; performance test data"was:then reviewed to identify the-actual performance _of the LHSI system. .This. review-included LHSI~ pump. performance.and system flow performance. Since flow performance is dependent on system test configuration, the alignment of the LHSI system as well-as system elevation heads 1 and static pressures during the performance of the tests were '
also reviewed. Item 31' Develon Analvtical Model for LHSI Flow Evaluation 1
\
An. analytical model for evaluation of LHSI flows was developed based'on the model identified in Itam_11 for the minimum- 1 safeguards design basis _ flew calculation. This model was' j benchmarked relative to the actual plant performance data of Item 2) inL order toL define the actual IJISI system resistance.
.The actual LHSI system resistance curve is'shown on Figure B along with'the actual'LHSI pump performance data obtained from Item 2).- Actual LHSI. flow for the test configuration is shown on Figure B as the intersection of the actual pump curve and the actual system resistance curve.
Item 4) Evaluate Sensitivity of IRMI Flow to Dearadation in Check Valve Performance i Sensitivity analyses were performed using the model developed in Item 3) to determine the sensitivity of total flow and branch line flow distribution to the location of a check valve that does not open properly. This was done by adding y additional piping resistance at each location where there_was a f check valve to simulate additional head loss due to a check o valve that was not1 opening properly. These_ analyses were performed with one LHSI and one High Head Safety Injection (HMSI) pump running to properly account for the interaction of HHSI and LHSI flow in that portion of the LHSI system in which check valves SI-23, SI-24 and SI-25 are located. This arrangement is, consistent with that used to develop the minimum safeguards flow cases used in FSAR accident analyses. The Sensitivity analyses served to locate the most critical LHSI check valve from the standpoint of adverse affect on LHSI flow distribution. This-evaluation resulted in the conclusion that the most critical check valve location was: i a) in the injection branch line that has the highest piping resistance. This location is critical due to the spilling line assumption. In developing the injection flows for the spilling line cases, the flows that are taken credit for are those from the tuo lines delivering the smallest p flows (i.e., the lines with the highest piping resistance). The line with the highest flow (i.e., the l~ line with the lowest piping resistance) is assumed to spill and is not taken credit for in the minimum L safeguards flow. By adding additional resistance to the path with the highest resistance, the flow in this branch l
g ATTACHMENT 2' Pago.3 of 10
- 7
'line is further reduced while the flows'in.the other two injection branch-lines are increased. This results in the minimum safeguards injection flow (i.e. , the sun ofsthe two lines delivering-the smallest flows) being reduced
.while the' spilling line flow is increased. Thus, the -
addition of resistance to~the branch line with the highest resistance has the largest adverse affect on LHSI flow ; distribution with respect'to compliance with minimum safeguards flow requirements. , b) = downstream-of the point where the HHSI injection lines connect to the LHSI injection branch lines. This location is critical since the check valves in this location receive a' higher flow (i.e., LHSI and HHSI combined' flow)- than do the check valves located upstream of the HHSI connection (s) to the LHSI injection branch line(s)._ Thus, for a given additional' resistance, the branch line:will-experience additional head _ loss'which will have the most a adverse effect on LHSI flow distribution and compliance with the minimum safeguards flow requirements. Item 5)- Determine Amount of Allowable Daaradation in Check Valve-Performance , sensitivity analyses were performed using the model developed in. Item 3) to determine the amount of additional resistance- i '- that could be-added to the worst case check valve location of Item-4) and not reduce either total flow or branch line flow distribution below the minimum safeguards flow requirements
-assumed in the FSAR accident analyses. Since the minimum safeguards flow requirements are developed with one LHSI.and one NHSI pump running to account for the interaction between '
s ' LHSI and HHSI flow in the SI system, the sensitivity analyses to define allowable additional resistance also utilized one , LHSI and one NHSI pump running. The sensitivity analyses utilized minimum safeguards pump performance curves consistent with the pump performance curves used to develop the minimum safeguards flow requirements assumed in the FSAR accident , analyses. The sensitivity analyses showed that additional resistance at the worst case check valve location resulted in a reduction in the associated LHSI branch line flow while the flow in the
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H other two branch lines increased. The not effect of this flow y redistribution was a relatively large reduction in associated l branch line flow but only a relatively small reduction in total LHSI flow. Due to this relationship between branch line flows L and total flow, the spilling line minimum safeguards cases were p determined to be the most limiting with respect to the amount g of additional resistance that could be added and still satisfy L the FSAR accident analyses requirements. Based on the sensitivity analyses, a limiting amount of acceptable L ' additional resistance was identified for the worst case check valve location. The new system resistance curve that includes this additional resistance is shown on Figure B. l
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t ATTACHMENT 2 Pago 4 of?10 This_new.rystem resistance curve is the maximum system resistance that can-be tolerated by the LHSI system and still satisfy the minimum safeguards flow requirements of-the-FSAR ' accident analyses. It is conservative-in that it assumes that- , all additional resistance is added at the worst case check valve location ~with respect to adverse effect on LHSI branch line flow distribution. Item 6) Dgline Accantance Criteria for Check Valve Operation , since LHSI system resistance cannot be directly measured and - compared against the-requirement defined in Item 5), it'is i necessary'to define an appropriate acceptance criteria that can-be used to verify LHSI system resistance. .This can be accomplished through defining a full flow acceptance criteria
' based on the system resistance curve of Item si in combination with pump' performance. Acceptable system resistance will.thus be determined by measuring system. flow rates and pressures and comparing them with the full flow acccptance criteria.g s
The LHSI full _ flow test configuration is one in which one LHSI i pump is running and the valves are in the cold leg injection alignment. The HHSI-pumps will not be operating during the LHSI full flow test. Consequently, acceptance criteria for the LHSI full flow test ils developed through performing analyses 1 using the maximum allowable system = resistance determined in i Item 5) .with one LHSI pump running. The full flow acceptance criteria is the intersection of the maximum system resistance curve and the pump performance curve. Since flow is a function of pump head as well as system resistance, the flow acceptance criteria can shift along the i maximum allowable resistance curve as a function of pump. performance. LHSI pump performance is acceptable if.it is ; greater than the minimum safeguards pump performance curve used to develop minimum safeguards flows for the FSAR accident
. analyses. Thus, analyses are performed to determined acceptance criteria for the 100% pump performance case and the minimum safeguards pump performance case. The results of the-analyses are shown on Figure B as the intersection of these pump performance curves with the maximum : system resistance curve. For the 100% pump performance curve, flow must be greater than the intersection of the pump head curve and the maximum system resistance curve. Should the pump performance degrade from the 100% performance curve, the intersection of the pump performance curve with the maximum system resistance curve will move down the resistance curve. If pump performance degrades to the minimum safeguards performance curve, the full flow acceptance criteria slides along the maximum system resistance curve to the intersection of the maximum system resistance curve and the minimum safeguards pump performance l' curve. Thus, the intersection of the pump performance curve and the maximum system resistance curve determines the full
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L flow acceptance criteria. The acceptance criteria decreases with decreasing pump performance. 1
4 ATTACHNENT 2 Pcgo 5 of 10 Item 7) Present lhill Flow Accentance 'Critarit ' for Test Configuration The acceptance-criteria developed in 113m_11 is' based'on a j 1 maximum system resistance curve and LHSI pump performance. ' between the 100% performance: curve.and the minimum safeguards-performance curve. .It.is also based on the assumption that.the differential head on the'LHSI system is eqNal to zero (i.e., the suction elevation head and static pressure is equal to the. " discharge elevation head'and static pressure). Since the full' flow test will be performed with different water levels in the Refueling Water Storage Tank and the Reactor Coolant System,
.the acceptance criteria can be adjusted to account for different suction and discharge conditions. This is accomplished analytically by running the LHSI model with different system differential heads (i.e., suction elevation '
head and static pressure minus discharge elevation head and c static pressure) and presenting the resulting full flow acceptance criteria as-curves that are a function of system u l differential head. Full flow acceptance criteria curves for l- the 100% and minimum safeguards LHSI pump performance curves are shown-in Figure C. Item 8) . Evaluation of LNEI Pull Flow Test Data L The LHSI system valve alignment used in the full flow c surveillance test is the same as the alignment used in the LHSI : i flow unalyses used to develop test acceptance criteria. One LHSI pump is run at-a time as the pumps are tested separately. As the test is performed, the LHSI flow is obtained as well am + the LHSI-pump developed head, LHSI system suction elevation head and static pressure and LHSI system discharge-elevation head and static pressure. The elevation heads and static ,: pressures are used to obtain a system differential head L corresponding.to the obtained LHSI flow. The values for total flow, pump developed head and system differential head are then used.to determine the acceptability of LHSI flow and check valve operation as follows: a) The point value for total flow / system differential head is plotted on Figure C. If this point is to the right of the acceptance criteria curve for the 100% pump performance curve, acceptance criteria are satisfied. All subject check valves are opening adequately for the LHSI system flow to satisfy the minimum safeguards flow requirements for FSAR' accident analyses. b) If the test point is to the left of the acceptance I criteria curve for the minimum safeguards performance curve, the subject full flow test cannot be used to verify acceptable LHSI flow and eneck valve performance. The check valves may or may not be operating properly; additional testing and/or evaluation are required to evaluate LHSI system flow distribution and check valve l L- . . . - . - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --
s ATTACHMENT 2 Pago 6 of 10 )
-performance.-
- No further conclusions.can be drawn from1the h +
full flow = surveillance' test'since the acceptance _ criteria: has-been developed as.a conservative screening criteria based'on'the assumption,that all additional system.
-resistance-is added to,the,systemmin the' check valve-location most critical to' system flow distribution.- If-the: failure to, satisfy the acceptance criteria is due to!
additional-resistance added elsewhere in;the system, the adverse affect 1on flow distribution will be less severe and the reduction in branch line flow with respect to :
- total' flow will be lens severe. Thus, minimum safeguards 1 flow requirements as assumed'in-the.FSAR accident analyses 1 may still be. satisfied.
c) If the. test point is between the full flow acceptance , criteria' curves for.the minimum safeguards pump s performance ~and 100% pump performance cases,'che LHSI flow-may be acceptable depending on actual pump performance. i The following process is used to determine the appropriate ' acceptance criteria: o The. Pump Performance Ratio.is first determined from Figure B based-on.the actual pump head test data and
' the corresponding 100% and minimum safeguards ~ pump heads at the same flow. The pump Performance Ratio g is equal to: i ,
Actual Pump Head - Minimum Safeguards Pump Head 100% Pump Head - Minimum Safeguards Pump Head ~ o .The Flow' Acceptance Criteria Range is then determined-from Figure C for the systew differential head. This range is determined by-subtracting the acceptance ; criteria value for.the m13imum safeguards pump ^ performance case:from th6 acceptance criteria value for the 100% pump performance case. o The actual full flow acceptance criteria is then ' determined by multiplying the Pump Performance' Ratio times the Flow Acceptance Criteria Range and adding the result to the acceptance criteria value for the minimum safeguards performance case. This actual-acceptance criteria is applicable to the actual pump performance head and can be used to evaluate the 4
- acceptability of the total flow / system differential '
L head test point. l i !
.--.---.-,.....~,-.--+,---..---_.---.,,n--------.-..-.,e -.--,--,_---~.--,,.-----m---.-~.--~... ,,v,,,,, . . . ...-,---nw,-. -
as l j: ! ATTACHMENT 2. .P go 7 of 10:
$;t-If the actuallflow is greater than the applicable i ' acceptance criteria; LHSI flow: satisfies FSAR accident i L analyses' assumptions and-the' subject check valves-are-1:
-cpening adequately. This,isithe same situation as in 113m_
Ag1 above. ;If the actual flow is less_than the acceptance criteria, the test results are. inconclusive: relative to
'the performance of the LRs1 system and subject check
( Additional testing-and/or evaluation are required
' valves. -
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to. evaluate LHSI systemLand-check valve performance.- This-is the same' situation as'in Item abi above.
.As an example of;this case, evaluate the acceptability of.
L La total' flow / system. differential head-test point of 4300 j T gpm/0 feet that is obtained:with a pump developed head of
-183-' feet. The pump developed headLof 183 feet at.4300'gpm. x E
" 'is greater than the minimum safeguards pump. performance ' curve on Figure B, thus, pump performance is acceptable. L The total . flow / system dif ferent Aal- head test _ point falls . L between the full flow acceptance criteria curves on~ Figure l C for the minimum safeguards pump performance case ad the-l 1004 pump performance case, thus Itam-sci applies. : Applicable full flow acceptance criteria bared on actual , LHSI pump performance is determined as follows:
'183-feet - 179 feet L o Pump Performance Ratio = --------------~~---
= 0.31 i, 192 feet - 179 feet o- Flow Acceptance Criteria Range = 4335 gpm - 4220 gpm ;
= 115 gpm :
o Acceptance criteria = 4220 gpm + ((0.31) * (115 gpm)) ,
= 4256 gpm At a system differential head of 0 feet, the example flow of 4300 gym is greater than the applicable full flow acceptance criteria of' 4256 gpm based on actual' LHSI pump performance. Thus, the LHSI full flow acceptance criteria are satisfied. The LHSI system flow rates are greater than assumed in the FSAR accident analyses'and the subject check valves are opening acceptably.
a, ; _ . , . _ _._.._ _ _ _ _ _ _ , . . . . _ . _ .. _ _ _ _ _ _
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' FIGURE A - SIMPLIE1ED LHS SYNTEM SCHEMATIC.
RCS LOOP 1 ;< j COLD LEG s'
'p FROM SI723- Sl-12 SH PUMPS RCS LOOP 2 .; < d : REFUELING -
COLD LEG I . WATER ; j STORAGE , SI-24 SI-11 TANK: 1 l- 3' J I RCS LOOP 3 COLD LEG
;c d 1 I
j lC SI-25 SI-10 L
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Y. , I a i l \ 5- . I I TO RCS - - "
-i HOT LEGS , S, '
V ' U-l l . LHSI . ' O PUMPS-3
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_ . . . , . , _ = . , ,_ . _ . . . . . , . . . . . . . . _ ._ _ . _ , , _ . .
Sy FIGURE B - LHSI SYSTEM PERFORMANCE 250 (100%) Pump . 4 Performance Curve himum @em i ; Resistance Curve I 200 .
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2 m v iMinimum Safeguards :
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- Actuai syseem .
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- 3000 3500 4000 4soo sooo Flow (GPM) :
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I l September 19, 1989
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U. S. Nuclear' Regulatory Commission Attnt Document Control Desk i Washinotor., DC . 20555 6 ReferW N Bcaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 i 7ST Program; Revision 3A ' i Gentlemen I L Attached as Enclosure 1 is Revisica 3A to the Beaver Valley Power Station Unit No. 2 Inservice Testing-(IST) Program. This revised program is being submitted with -the guidance provided into the NRC as information in accordance Generic letter 89-04, paragraphs B and D, and as discussed at the regional meetings on implementation of Generic Letter 89-04. ; [ I l This submittal contains specific revisad pager.which are intended to be a. page for page replacement. contained in revision 3 with those identifiedPlease replace those pages on the " Approval Sheet" < in Enclosure 1. i~
. The. Unit No. 2 IST Program is currently implemented as revision 3 i as modified by revision 3A (a partial issue of the Program).
The NRC issued their SER on the original version and revision 1 of the IST Program on March 18, 1988. Subsequently, we submitted information detailing rt/isions 2 and 3 on January 31, 1989. This subsequent submittal contained relief requests approval. requiring NRC submittal As a result of Generic Letter 89-04, we are reviewing that against the positions delineated Generic Letter. in' Attachment 1 of the response to the Generic Letter. The results of that review will be discussed in our However, with the issuance of Generic Letter 89-04 and discussions with the NRC, we have determined that revisions 3 and 3A may be implementcd without prior NRC approval. Enclosed as Attachment 1 is a summary Program incorporated with revision 3A. of changes i a f -- w w q' J w a s -- - QQ.
= . . - -- ._-_.___--
U ,, f. I' 1 Beav r Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 IST Program;-Revision 3A Page 2 L If' you have any questions, please contact me or members of my staff. Very truly yours, f J. MCD. Sieber Vice President Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector-Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Mr. R. Saunders (VEPCO) 1
a , j ATTACHMENT 1 1 LIET OF EDITonf Af. CRANCEE l i
- 1) Under the " Pump Testing Requirements" Section: :
a) The third paragraph on page 3 discusses performance of OST's, but was changed to "BVPS 2 Surveillance Tests" to encompass both OST's , and BVT's for testing pumps in the IST Program. : b) On page 5. "5VT Beaver Valley Test" was added to Ites No. 2. .
- 2) On pages 13 and 14 for RHR Pumps (2RHS*P21A,5), the nomenclature for Flow Indicators [2RHS FI605A,5) was corrected to " Return Line Flow Indicator to Cold Leg 22."
- 3) The Pump Testing Outline Sheets (pates 21 24) for the Recirculation !
Spray Pumps [2RSS*P2LA,8,C,D) were revised as follows: l a) The Surveillance Test used to test the RSS Pumps on a refueling ! frequency was changed from OST 2.13.7 to 2SVT 1.13.5. Pump Relief ; Request No. 4 (page 43) was also revised to reflect this change. ~ b) The motor outboard bearing for each RSS Pump does not have a computer point for indicating bearing temperature and was deleted from the bearing temperature (Tb) section.
- 4) On page 27 under the Comments column for the "C" Compor.ent Cooling ;
Water Pump ( 2CCP*P21C) , containment Cooling Water Supply Header Flow l Indicator [2CCP*FI117A2] was also added as part of the test flow path, j
- 5) On page 28 for the Steam Driven Auxiliary Feed Pump [2FWE*P22), the Comments section for speed (N) was revised to include "or portable ;
monitoring equipment." The installed tachometer is not always operable and sometists a stobotac is needed to obtain pump speed. '
- 6) On page 45 for Pump Relief Request No. 7 under Basis for Relief, the minimum technicel specification level permitted in the Diesel Cer.arator Fuel oil Storage Tank was changed to 91.24.
- 7) Under the " Valve Testing Requirements" Section:
4 a) The second paragraph under Stetion A on page 47 was revised to state that streke times would be measured "at least" to the , nearest second... Stroke time are typically measured to the ' nearest tenth or hundreth of a second. b) The first paragraph on page 48 was revised to say, " Exception is taken to part streke timing motor operated valves. . ." c) The third paragraph on page 48 was deleted since all valves with ' failsafe actuators are now tested by actually venting air off of the valve actuator instead of just positioning the control switch. PACE 1 0F 4 m.,--..,,,,_w, ,,,,,..,,,.m., .,..,-nng . . , , - - . , . ,n.v. . , , , . av.--,-,
e y l k l List 0F EDITORTAf cuA4 cts (Continuad)
- 7) d) ' ation 1 under Correct've Actions on page 48 was revised to i
specify a limiting valoa "of 2 seconds" for rapid teting valves. ; e) Section 2.c under Corrective Actions on page 49 deleted "for the ! valve's repair or replacement" because corrective actions may 1 involve a lot more than just the valve's repair or replaceanet. l f) On page 49, Item 6. "The design time listed in the UFSAR", was added as another basis for. determining ASME limiting valve stroke > tic;e s . g) Section C on page 51 was revised to read, "There are no ASME Class 1, 2, or 3 Category D valves..." There are Category D valves at Unit 2, but they are not safety related and not in the IST Frogram. h) Item 2 under the last paragraph on page 51 was revised to include ; as an example. " flow control valves." i) On page 53 under Item 3, "LC Locked closed" was deleted. The term "LS Locked Shut" is used in its place. j) On page 53, " CMP Corrective Maintenance Procedure" was added to i Item 7.
- 8) on page 57, deleted reference to IWV 3414 for Blender to VCT Check ,
Valve [2CHS*84) because the check valve is " full stroked" open only at cold shutdown per CSJ No. 7.
- 9) On page 59 under the Comments column, the forward direction (TD) stroke was deleted from RCP Seal Water Supply Check Valves [2CHS*474, 475, and 476) because these weighted arn check valves only require
- esting in the closed direction per CSJ No. 16.
- 10) on page 65, the frequency for OST 2.47.3A was corrected to (Q) instead of (CbD) for High Head to Cold Leg Injection Isolation Valve
[2 SIS *MOV840) on the Valve Testing Outline Sheet. ,
- 11) On page 69, the NSA positions for CNMT EJ Suction CNMT Isol Valves ,
[2CVS*151 and 151 1] were changed from LC to LS.
- 12) Quench Spray Header Check Valves [2QSS*3 and 4) are tested in both directions per CSJ No. 28. The Comments column on the Valve Testing outline Sheet (page 71) was revised to reflect this by adding "RD" l also. The description for Alternate Test on CSJ No. 28 (page 113) was also revised to say, " Full stroked in both d!rections per OST 2.1.10."
- 13) On page 81, the Valve Testing outline Sheet for Steam Cenerator Main Steam Isolation Valves [2 MSS *A0V101A,8,C) was revised to reflect that the valves are tested quarterly (Q), not monthly (M).
, PACE 2 0F 4 L -- . .__________-__-_A
3
. ==
LIST OF EDITORI AL CMNCEE (Continued)
- 14) On page 87, the NSA position for TD Aux Feedwater Pwtp Discharge Check and Recirculating Valve [2TVE*FCV122) was deleted because it does not have an NSA position.
- 15) On page 91, the internal inspections per CMP every 5 years for Diesel Generator Heat Exchanger Supply Header Check Valves [2SVS*110, 111, 112, 113) were noted "not required by ASME." IE Bulletin 83 03 requires an inspection of these check valvos to ensure valve integrity. Check valves [2SVS*110 and 113) are passive valves and do not* have any testing requirements so "QS" was changed to "NA" for these valves.
16) Instrument the closed Air Header
.lirection Inside per CSJCNMT No. 50.Check Valve [21AC*22] is stroked in The Valve Testing Outline Sheet (page 96) was revised to reflect this by adding "RD". The Alternate Test description for CSJ No. 50 (page 130) was revised to read, " Full stroked closed per 051' 2.1.10,"
- 17) On page 112, the Function for CSJ No.15 was revised to read, " Seal Water Return Containment penetration X 19 thermal relief check valve (Bypasses 2CHS*MOV378)."
- 18) On page 112, the Basis for CSJ No. 16 was revised to identify RCP Seal Vater Supply Check Valves [2CHS*474,475,476) as " weight loaded (
arm check valves" stroked "in the closed direction." L
- 19) on page 119, the Alternate Test description for CSJ No. 28 was revised to read. " Full stroked in both directions per OST 2.1.10."
- 20) On page 122, the Alternate Test description for CSJ No. 34 was revised to read, " Partial stroke open monthly and full stroke open at cold shutdown per OST 2.24.4."
. 21) On pake' 122, the Alternate Test description for CSJ No. 35 was revised to read, " Partial stroke per OST 2.21.1(2)(3) quarterly", and
" Full stroked and timed closnd per OST 2.21.7 at shutdwon with TAVC h 515F."
- 22) On page 131 under CSJ No. 52, the Basis for CSJ was revised to state that the plant would be placed in a "six" hour action instead of a one hour action per Tech Specs. 3.4.6.1 and 3.0.3.
PAGE 3 OT 4 i l
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-1 11ST OF TECHNICAL CHANCES l
- 1) Engineering has determined that Ri$ Pump Discharge Line to 1RSI Discharge Weighted Ara Check Valves [251S*46 and 47] should no longer be exercised in the open direction during normal operation because excessive forces. are needed to overcome the head of water created by the Refueling Water Storage Tank level against the check valve disks.
]
Cold Shutdwon Justification No. 53 (page 131) was added to the IST ] Program to permit full stroking these check valves at Cold Shutdown ; per OST 2.1.10. The Valve Testing Outline Sheet (page 63) was also ; revised to reflect this change.
)
1
- 2) On page 90, Recirc Spray Heat Exchanger Cooling Water Supply and' I Discharge Valves [2SWS*MOV104A.D and 105A.D) were changed from passive ;
back to active valves and will continue to be tested in OST 2.47.3A. UFSAR Section 9.2.1.1.3 states that the capability for isolating the inist and outlet sides of the RSS Heat Exchangers in the event of a h.' tube leak in the heat exchanger must exist. These valves are one of several . ways to isolate a tubo leak in the RSS Heat Exchangers and are being returned to active status in the IST Program as a preference and
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not as a requirement. c l L l PAGE 4 0F 4
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