Text

Rev 7 to IST Program Plan for Pumps & Valves
	ML20082C948
Person / Time
Site:	Braidwood
Issue date:	03/14/1995
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20082C946	List: ML20082C942; ML20082C948;
References
	PROC-950314, NUDOCS 9504070219
	Download: ML20082C948 (191)
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INSERVICE TESTING PROGRAM PLAN FOR PUMPS CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 SECTION 3.0 INSERVICE TESTING rnoannu rLaw rom runers ERAIDWOOD STATIcet UNITS 1 AND 2 9504070219 950330 PDR ADOCK 05000456 (03/14/95) P PDR o:\DEPTS\ZD79G\217.wpf/1

INSERVICE TESTING PROGRAM PLAN POR PUMPS KRAIDWOOD STATION UNITS 1 AND 2 ]

Revision 7

'thBLE OF CONTENTS 3.0 Inservice Testing Program Plan for Pumps 3.1 Program Description 3.2 Program References 3.3 Pump Tables 3.4 Pump Notes Note 1 -Deleted-Note 2 Pumps Lubricated by Pumped Fluid Note 3 . Pump Idle Suetion' Pressure .

Note 4 Deleted - Not Used at Braidwood - Byron ONLY Note 5 Not Used at Braidwc'd - Byron ONLY Note 6 Not Used at Braidwood - Byron ONLY Note 7 Not Used at Braidwood - Byron ONLY 3.5 Pump Technical Approaches and Positions PA-01 Performance Testing of the Boric Acid (AB) Transfer Pumps 3.6 Pump Relief Requests PR-01 Pump Vibration PR-02 Pump Bearing Temperatures PR-03 -Deleted- Not used at Braidwood - Byron ONLY PR-04 -Deleted- Not used at Braidwood - Byron ONLY FR-05 -Deleted- '

PR-06 Diesel Oil Transfer Pump Differential Pressure PR-07 Not used at Braidwood - Byron ONLY i

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IOSERVICE TESTING PROGRAM PIJul FOR PUMPS .

BRAIDWOOD STATION UNITS 1 AND 3

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INSERVICE TESTING PROGRAM PLAN FOR PUMPS <

ERAIDWOOD STATION UNITS 1 AND 2

Revision 7 4

FRoeRAM DESCRIPTIcN The Pump Inservice Testing (IST) - Program Plan for Braidwood Nuclear Power Station Units 1. and -2, is implemented in accordance with. the requirements of )

Subsection IWP of Section II of the ASME Boiler and Pressure Vessel Code, 1983

. Edition, through the Summer of 1983 Addenda. Where.these requirements are

, determined to be ispractical, specific relief is requested. Additional pump

, relief requests may be necessary and these will be. identified during i subsequent inservice tests. 'the pumps subject to IST testing are those pumps i

which are identified in accordance with the scope of ASME Section II,..

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subsection IWP-1100: "INP-1100 SCOPI... This Subsection provides the rules j and requirements for inservice testing of Class 1, 2, and 3 centrifugal and

displacement. type pumps that are installed in light-water cooled nuclear power

!. plants, that are required to bring,and maintain the plant in cold shutdown

] condition or mitigates the consequences of an accident, and that are provided with an emergency power source. The results of-these tests are to be used in .

j. assessing operational readiness of the pumps during their service life." )

The only exceptions 'are the diesel driven auxiliary feedwater pumps (1AF01PB

, and 2AF01PB), which are not supplied by an emergency power source. The diesel'

{ oil transfer pumps (1/2 DOO1PA, 1/2DOO1PB, 1/2DOO1PC and 1/2DOO1PD) are

classified non-ASME Class G.

i j Pump reference values shall be determined from the results of a pre-service a test, which may be run during pre-operational testing, or from the results of

the first inservice test run during power operation. Reference values shall

! be at points of operation readily duplicated during subsequent inservice j testing. Additional reference values may be necessary and these will be taken i in accordance with IWP-3111 and 3112:

1. After a pump has been replaced, l 2. When a reference value or set of values may have been,affected by repair

or routine servicing of a pump, or i

3. If it is necessary or desirable for some other reason than 1 or 2 above.

l Per NRC Generic Letter 89-04, Attachment 1, ' Position #8, ' whenever pump data is j determined to be within the Required Action Range, the pump is inoperable, and the Technical Specification LCO Action statement time starts.

! l l In the event a pump must be declared inoperable as a~ result of inservice l testing, limitations on plant operation will be as stated in the Technical

Specifications.

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i Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed ]

to supersede the requirements of any Technical Specification. !

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INSERVICE TESTING PROGRAM PLAN FOR PUMPS.

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 l

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INSERVICE TESTING PROGRAM PLAN FOR PUMPS ERAIDWOOD STATION UNITS 1 AND 2 l Revision 7 PROGRAM REFERENCES

1. Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of l Production and Utilisation Facilities, particularly Section 50.55a, Codes and

j. Standards.

l 2. ASME Boiler and Pressure Vessel Code,Section II, Rules for Inservice

[ Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 l

Addenda.

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3. ASME/ ANSI CH-1987,~ Operation and Maintenance of Nuclear Power Plants, including 1989 addanda, Part 6, Inservice Testing of Pumps in Light Water Reactor Power Plants.

4. U.S. Nuclear Regulatory Comunission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs.

5. Braidwood Station UFSAR, Section 3.9.6.1, Inservice Testing of Pusps.

6. Braidwood Station Technical Specification, 4.0.5, ASME II Program l Requirements. 1

7. Braidwood Station Technical Staff Procedure, BwvP 200-1, ISI Requirements for Pumps .

j 8. NRC Safety Evaluation Reports (SER's):

a. SER dated October 15, 1991 for Revision 4/4a.

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b. SER dated September 14, 1993 for Revision 5/Sa.

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-INSERVICE TESTING PROGRAM PLAN FOR PUMPS CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

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SECTION 3.3 i

Fladr TABLES i

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1 INSERVICE TESTING PROGRAM PIAN FOR PUMPS f ERAIDWOOD STATION UNITS 1 AND 2 l- Revision 7 ;

PtadP TABLE DESCRIPTION j The following information is included in the summary tables:

The first four columns include the unique Braidwood Station Eaul - nt Piece Number. the Pumo Name. the Code Class (1, 2, 3, N for non-Code, and T for tracking purposes only), and the system P & ID for the pump listed.

Somed: Speed will be measured by a tachometer for variable speed drives.

Tnlet Pressure: Inlet pressure will be measured via permanently installed gauges or other means, provided the equipment accuracy meets the requirements of IWP-4150. This is to be measured both before pump startup and during the test.

Differential Pressure: Differential pressures will be measured using calibrated differential pressure gauges or by recording the difference between calibrated inlet and outlet pressure gauges.

Elser Rate: Flow rates will be measured using perinanently installed instrumentati'on or other means, provided that equipment accuracy meets the requirements of IWP-4150.

Also, refer to relief request PR-05.

Vibration: vibration measurement shall be made using portable or hand held instruments at locations marked on the pumps, relief request PR-01.

Bearino Ta-aarature Bearing temperature 13 not measured per PR-02.

Test Interval: An inservice test shall be run on each pump nominally every 3 months during normal plant operation, in accordance with IWP-3400, except during periods when the pump is not required to be operable.

Lubrication Level: Lubrication level will be observed through sight glasses for the pumps listed in the program, when provided.

Remarks: Any applicable note (s) are referenced here.

Revision Nn=har: The current revision of the program is listed.

Table Pace: The table pages are numbered sequentially and show the total number of pages.

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i 900ElWE flNG PROGMM PLAN Ct. ASS 1,2. 3 Afe AUGWNTED PUtes BMDWOOD NUCLEAR POWE'9 STATION ,

UDNYS O,1,2 flovimien C- TEST PAMRETERS L

A S edLET DIFF PLOW OEANNG TEST LUBfBCATION PUhr NURS PUhr NARE S Pts tu'EE PUESS PlESS ETE VERATIO TEnr MTERVAL 1.EVEL fEMAfRS ,

OA903P Rede Acid 3/T E85 No No PA-1 PA-1 PA-1 PA-1 Oumrtedy Yes Tsunsfer Pissy 1A803P Bosto Acid 3/T E85 No & PA-1 PA 1 PA-1 PA. I Qumrtesty Yes Tsaiseur Piso, 2A803P 9ede Acid 3/T E85 No No PA 1 PA-1 PA-1 PA-1 Oumrtuser Yes Teensfer Ptsup 1AP01PA Aesummy Feedne 3 E37 See Yes Yes Yes PE1 PS2 Oumready Yom Ptsg inAstort 1AP01PB Aummary Feedne 3 E37 No Yes Yes Yes PE1 PN2 Omarcedr Yes Ptsey IDiment 2AP01PA Aasenry Foodwe 3 R4122 No Yes Yes Yes Ph1 PE2 Ouartestr Yes Ptsg lMotort 2AP01PB AummsyF W 3 E122 No Yes Yes Yes PS1 PM-2 Oumrfody Yes Ptsup N .

OCC01P ' Canyonent Coe5 3- 4498 No Yes Yes Yes PE1 PR-2 Oumrendr Yes Nute 3 Ptsup 1CC01PA Casequenent Cmag 3 EOS No Yes Yes Yes PS1 PS2 Ouartudy Yes piste 3 Pts 9 1CC01PS Congenent Cass 3 EOS No Yes Yes Yes PE1 PS2 Oumptesty Yes Note,3 Pts'y 2CC01PA Cnemyonent Cast 3 0488 Die Yes- Yes . Yes PS1 PN2 Genutestr Yes Note 3 Ptsuy 3.3 PUhr TABLES - Pass 1 et 4 eMspeeW9 \217/9 3

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l Of99ML IING PROGMM PLAN CLASS 1,2. 3 AM) AUGGENTED PUnes BMENWOOD NUCLEAR POWER STf. TION USSTS & 1,2 Rowblon C TEST PAMhETERS L

A S 98LET OIPF PLOW OEAf4NG TEST LU5f4 CATION PUnr NUng Pupp NAeg 8 Pee SPEE PDESS PDESS MTE VigRATIO TEhr Off9tVAL LEVEL IER44f5CS 2CC01P5 ComPenant Cost 3 4 88 No Yes Yes Yes Ph1 PS2 Questudy Yee feste 3 PWN IC901PA C_ _ -- .: SPr 2 E46 No Yes Yes Yes PR1 PR-2 Quartedy b Note 2 PWW IC901PS Centuhmmre SPr 2 E46 No Yes Yes Yes Pn1 PS2 Oneurtesty No Note 2 PW9 2C901PA Conombenant SP r 2 E129 No Yes Yes Yes PSI PR-2 Oumsteser No Note 2 PWN 2C901PB Cenaminment Spr 2 E129 No Vee Yes Yes PE1 FR-2 Ouurteser No . Deste 2 Peer ICV 01PA CentrNugal Charg 2 4 84 No Yes Yes Yes PE1 PN2 Ouartsdy Yes FWN ICV 01P9 CentrWugal Garg 2 4 84 eso yes yes yes Pn1 PS2 Quaresser yes PWN 2CV01PA Consedugal Chang 2 E138 No Yes Yes Yes PSI PR2 Oumreeser Yes PWN 2CV01PB Cenerfugmi chung 2 R4138 No Yes Yes Yes pn1 PS2 Oumrtedr Yes ,

Pew 10001PA OlsesI0E Tsunese 3 4 50 No Yee PES Yes PS1 PE2 Ousstadr See Note 2 Peer 3.3 PUhr TAN.ES - Pese 2 et 4 i

eMePeekd79gG17/10

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Of9ERYk TWeO PROGl%M PLAN CLASS 1,2,3 AND AUORENTED PUheS ORAIDWOOD NUCLEAR POWER STATION LMTS 0,1,2 Rev6 den C TEST PARA 8ETERS L

A S INLET DEF PLOW SEANNO TEST LUONCATION PUhr NUh5 PUhr NAhE S Pam WEE PfEss PfESS RATE VWRATIO TEtr INTERVAL LEVEL fEMMUCS 1DOO1PB Dimed OE Trunofe 3 ESO No Yes PIM Yes Pf41 PR-2 Ouarterly No Note 2 PWN 1D001PC Oleset OS Tserufe 3 4 50 No Yee PfM5 Yes Pf41 Pf42 Ouartertr % Nute 2 Purg 20001PA Olseul 0E Tsunsfe 3 4 130 No Yes PIM Yes PR-1 PR-2 Oumreesty feo Note 2 Fww 20001PB Diess108 Tsunsfa 3 4130 No Yes Pf46 Yes Pf41 PR 2 OumrtesIr % Note 2 Ptow 20001PC Olemet 0E Teensfo 3 E130 No Yes PfW Yes Pf41 Pf42 Oumreesty No Nees 2 Pium 10001PD OtmusI DE isensfa 3 4130 No You Pf46 Yes Pf41 Pf42 Quartesty Yes Plum Iftt01PA Moaldual Host 2 ES2 feo Yes Yes Yes Pf41 PY42 Oumsteser Yee Reuevel Plum Ift101P5 Rmehhaul Heat 2 4 62 No Yee Yes Yes Pf41 Pf42 Oumstesty Yes Removal Pteg 2ftt01PA Rusialuul Heat 2 04137 No Yes Yes Yes 8f41 PR-2 Oumrtesir Yes memoval Pwg 2fD401PB sq.ashpuml Host 2 4137 No Yes Yes Yes Pf41 f142 Oumesser No Note 2 Romewd Ptow 3.3 PUhr TAatfS- Pass 3 et 4 e:htspeebf793Q17/11

. _ . . _ . . . . . . . . . . . .....__o .._.._...m..m..m_..-.m,.. ,-.m _.m._ . _ _ - _ . . - . - .-._ m - ._ .m._ . . ~.. . _ . .-_. ._ .. ., ..=_. . _., m OdSEfML TING PROOMM PLAN QASS 1,2,3 AND AUOMENTED PURPS BMIDWOOD NUCLEAR POWER STATKIN UNITS 0,1,2 4 Rowielen C TEST PAMhETEftS L

A S WILET DIFF ftOW OEAlWIG TEST LUOf5 CAT 10N PUhr NURS PUhr NARE S PSD SPEE PfESS PfESS MTE VWIATIO TEhr pfTEstVAL LEVEL fER4 Mute 18001PA Safety tr(setten 2 2 01 No Yes Yes Yes PE1 PE2 Oumressly Yee -

Ptov 18101PB Safety tr(setien 2 4 61 % Yes Yes Yes PR-1 PS2 Oumrteser Yom Ptow 29001PA Safety in$setion 2 EOS No Yes Yes Yes PE1 PR 2 Oumrteser Yes Ptov 2910179 Safety Ir(estion 2 4 81 No Yee . Yes Yes PR 1 PS2 Oumrterly Yes Pis9 1SX01PA Essenatul Servius 3 0442 No Yes Yes Yes PR-1 PE2 Oumrtestr Yes Note 3 Water Pww ISXO1PS Essenudul Servios 3 4 42 No Yes Yes Yes PE1 PR-2 Omertmeer Yes Deste 3 wueer Pteg 2SX01PA EssentimI 5ervino 3 0442 tio Yes Yes Yes PE1 PR-2 Oumsteser Yes Neto 3 Water Pteg 2SM01P5 Emmesetal Servise 3 2 42 No Yes Yes Yes PE1 PE2 Ouurtsstr Yes Note 3 Water PWW ISXO4P 15 AFW SX 3 h442-3 Yes Yes Yes Yes PR-1 PR-2 Oumptaser Yes Sommeur Pussy 2SM04P 28 AFW SX 3 04126-Yes Yes Yao Yes PE1 PR-2 Oumsteser Yes geester Pteg OWD01PA Centrol Rearn 3 RS189 No Yes Yes Yes PS1 PE2 Oumrtesir Yee 90ste 3 Chand Water Pineq, OWOO1P5 Centrol Roam l 3 E119 Deo Yao Yes Yes PE1 PE2 Omurtsstr Yes Deste 3 Gesd Water Ptosy 3.3 PUtr TABLES - Page 4 et 4 o%pte\rd79g\217/12

1 i INSERVICE TESTING PROGRAM PLAN FOR PUMPS-CRAIDWOOD STATION UNITS 1 AND 2 Revision'7 I

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INSERVICE TESTING PROGRAM PLAN'POR PDMPS.

ERAIDWOOD STATION UNITS 1 AND 2 .j

j. -Revision 7 PUNF NOTRS .j

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The Diesel Oil Transfer (1DOO1PA-D and 2DOO1PA-D), Residual Heat Restoval- (1RH01PA/B and '

2RH01PA/B) and Contairmnent Spray (1C801PA/B and 2C801PA/B), pumps cannot be measured for lubrication level. These pumps are lubricated by the~ fluid pumped and hence have-no indication for lubrication level.

MQTE . 3 The Component cooling water pumps '(OCC01P, 1CC01PA/B and 2CC01PA/B), Essential Service

. Cat 0r Pumps (IS101PA/B and 2SIO1PA/B), and the Control Rocal Chilled-Water Pumps (OWOO1PA/B) are in systems which are in continuous operation. -The idle inlet pressure for-these pumps cannot be obtained without interrupting normal system operation and causing sy: tem transients. The idle inlet pressure will be recorded only if the pump to be tested

'13'not in operation at the start of the test. Proper pump operation is assured by continuous pump operation as well as quarterly monitoring of the remaining ISI pump l parameters.

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-Deleted-E2ZI 1 Not Used at Braidwood.- Byron ONLY' I

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-Deleted-IKyfE 7 Not Used at Braidwood - Byron ONLY i

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l INSERVICE TESTING PROGRAM PIAN FOR PUMPS-ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 l

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SECTION 3.5 PthdP TECEMICAL APPRQ4 CEES AND POSITIONS l

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l- INSERVICE TESTING PROGRAM PLAN FOR PUMPS ,

IRAIDWOOD STATION UNITS 1 AND 2 '

Revision 7 i

IST Technical Approach and Position i No. PA-01 l I

A. Commonent Identification: '

1.

Description:

Performance Testing of the Boric Acid (AB) Transfer Pumps l 2 Component Numbers: 0AB03P, 1/2AB03P

3.

References:

'(a)-Engineering Correspondence (CHRON #161733) dated ; January 17, 1991 l.

(' 4. Code Class: 3/T (Tracking purposes ONLY))

5. Raouirements: .

The ASME Section II Code requires safety related pumps performing a specific function in shutting down the reactor or in mitigating the consequences of an accident, and'that are provided with an-emergency power supply be included in the i

inservice testing program (IST) . However, the AB pumps do not have an " emergency" power supply, so consequently, they are not reauired to be included in the program.

Braidwood was licensed as a " hot shutdown" plant. This means it was only required to be capable of hot shutdown using non-safety related systems or repair to l postulated damaged equipment.. For this reason the electrical support for the emergency boration function is Safety Category II. Also, the RWST (Refueling Water Storage Tank) is a seismic Category I structure as described in the UFSAR Table 3.2-1 and is designed to withstand design basis accidents, including tornados. The RWST is required for ECCS (Emergency Core Cooling Systems) operation.

The AB pumps are tested per the Technical Specification requirement that requires an 18 month flow verification of 30 gym to the RCS. Also,'the AB pumps are monitored per the station's vibration monitoring program requirements.

I C. Position:

The AB pumps fall outside the scope of the ASME Section II and the IST program. l

, However, because of the operating significance of these pumps, and based on '

l correspondence and discussions with NRR and CECO Engineering, Braidwood Station has i

decided to list the AB pumps in the program for tracking purposes only. .They will l be tested in a like fashion to the ASME Section II program. The hydraulic limits used will be similar to those specified in ASME/ ANSI CMa-1988,.Part 6. Meaning that the differential pressure limits will be plus or minus 10 percent of its reference value (flow rate will be a set value) . There will be no alert limits placed on differential pressure. The AB pumps will be trended to monitor for degradation or abnormal / erratic operation. Also, the vibration readings and limits will be similar to those in ASME/ ANSI OMa-1988, Part 6.

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I2 SERVICE TESTING PROGRAM PLAN FOR PUMPS 2RAIDWOOD STATION UNITS'l AND 2 Revision 7 l

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SECTICII 3.6

.PtBer RELIEF REQUESTS 1

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' INSERVICE TESTING PROGRAM PIAN FOR PUMPS . ;

I- ERAIDWOOD STATION UNITS 1 AND 2 j Revision 7 RELIEF REODEST NO. PR-01 A. PDMP BDMBER:All pumps in the program plan.

l 2. NIEIRER OF ITEMS: - 44 pumps.

ll l 3. ASME CCE)E CIASS: 2&3

4. ASME CODE. SECTION II REOUIREMENTS:

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. In reference to Table IWP-3100-2, " Allowable Ranges.of Test Quantities", pump j' vibration is to be measured in and compared to' values given in mile displacement, i

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j he measurement of pump vibration is required'so that developing problems can be detected and repairs initiated prior to a pump becoming inoperable. Measurement'of-

! vibration only in displacement quantities does not take into account frequency which.

j is also an important factor in' determining the severity of the vibration.

i j 6. ALTERMkTE TESTING:

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] We ASME Code minimum standards require measuramant of the. vibration amplitude'in

mils (displacement) . Praidwood Station proposes an alternate program of measuring-j vibration velocity (inches per second) which is more comprehensive than that j, required by Section II. This technique is an-industry-accepted method which.is much *

more meaningful and sensitive to anall' changes that are indicative of developing.

. mechanical problems. These velocity measurements detect not only high amplitude i vibration, that indicate a major mechanical problem such as misalignment or j unbalance, but also the equally harmful low amplitude, high frequency vibration due to bearing wear that usually goes undetected by simple displacement measurements.

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l The allowable ranges of vibration and their associated action levels'will be-

[ patterned after the requir== ants established in ANSI /ASME OMa-1988, Part 6. These

ranges will be used in whole to assess equipment operational: readiness for all-ccaponents.

l The acceptable performance range for all components will be s 2'.5 times the .

1 reference value, not to exceed .325 inches per second. .The alert range,:at which I time the testing frequency would be doubled, will be > 2.5 to 6 times the reference 3

value, not to exceed .70 inches per second. Any vibrating velocity greater'than 6 l times the reference value or greater than .70 inches per second will require 3,

corrective actions to be performed on the affected component.

Vibration measurements for all pumps will be obtained and recorded in velocity, inches per second, and will be broadband unfiltered peak measuramants. The monitored locations for vibration analysis will be marked so as to permit subsequent duplication in both location and plane.

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INSERVICE TESTING PROGRAM PIAN FOR PUMPS RRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REODEST NO. PR-01 The frequency response range of the vibration transducers and their readout system j shall be capable of frequency responses from one-third minimum pump shaft rotational '

speed to at least one thousand herts.

The Vertical Line Shaft Pumps in the program will have vibration measurements taken j on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction.

7. JUSTIFICATION:

Measurements of vibration in mils displacement are not sensitive to small changes that are indicative of developing mechanical problems. 'Iherefore, the proposed -

alternate method of measuring vibration amplitude in inches /second provides added assurance of the continued operability of the pumps. Also, there are no positive displacement pumps or centrifugal pumps which rotate at less than 600 RPM in Braidwood's IST program.

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8. APPLICABLE TIME PERIOD:

This relief is requested once per quarter during the first inspection interval.

9. APPROVAL STA'IUS:

a. Relief granted per NRC Generic Letter 89-04.

b. Added the 1/2 SXO4P Booster Purps, Rev. Sa.

c. Approved per SER dated September 14, 1993.

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! INSERVICE TESTING PROGRAM PIAN FOR PUMPS .

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REODEST NO. PR-02

.. PIBIP NUMBER: All pumps in the program plan.

3 l 2. NUMBER OF ITEMS:44 pumps

3. ASME CODE CLASS:2 & 3 j 4 ASME CODE. SECTION ZI REQUIREMENTS: ,

Per IWP-3100, Inservice Test Procedure pump bearing temperatures are required to be i measured to detect any change in the mechanical characteristics of a bearing.

{ IWP-3500(b) requires three successive readings taken at ten minute inter;als~that do j not vary more than 36.

1 2 5. RA3IS FOR RELIEF:

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a. Se CC, CS, DO, RH, SX and WO pump bearings are not provided with permanent

j. temperature detectors or thermal wells. Therefore, gathering data on bearing : 'c i temperature is impractical. Se only temperature measurements possible are -

! from the bearing housing. Measurement of housing temperature on these pumps ,

j does not provide positive information on bearing condition or degradation.

j b. Even those cases where bearing temperature monitoring equipment is available, bearing temperature measurements will not provide significant additional 1

"i inforination regarding bearing condition other than that already obtained by measuring vibration. Measurement of vibration provides more concise and consistent information with respect to pump and bearing condition. The usage

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i of vibration measurements can provide.information as to a change in the

{ balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump integrity prior to the condition degrading to the point where the component is jeopardized. Bearing j temperature does not always predict such problems.

c. An increase in bearing temperature most often does not occur unti1 the bearing-

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has deteriorated to a point where additional pump damage may occur. Bearing temperatures are also affected by the temperature of the medium being pumped, l thus the hydraulic and vibration readings are more consistent. Also, the Code

] specifically exempts temperature measurement for pump bearings in the main j flow path (i.e., the diesel oil transfer pumps) .

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, INSERVICE TESTING PROGRAM PLAN FOR PUMPS.

CRAIDWOOD STATION UNITS 1 AND 2 i Revision 7- !

RELIEF REQUEST NO. PR-02

.. ALTERNATE TESTING:

Quarterly measurement of hydraulic parameters and vibration readings provide a more positive method of monitoring pump condition'and bearing degradation.

7. JUSTIFICATION:

- By measuring pump hydraulic parameters and vibration velocity, , (as described in . ;

PR-01), pump operability and the trending of mechanical degradation is assured.

Also, since these parameters (i.e., hydraulic parameters and vibration) are measured quarterly, the pump mechanical condition will be more: accurately determined than .

would be possible by measuring bearing temperature on a yearly basis.

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'S. APPLICARLE TIME PERIG): I

.This relief is requested once per year, during the first inspection interval.

9. APPROVAL STATUS: )

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a. . Approved per Rev. Sa SER dated September 14, 1993. l l

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INSERVICE TESTING PROGRAM PLAN FOR PUMPS CRAIDWOOD STATION UNITS 1 AND 2 ,

Revision 7 i RELIEF REODEST NO. PR-03

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ICSERVICE TESTING PROGRAM PIAN FOR PUMPS CRAIDWOOD STATION UNITS 1 NtD 3 Revision 7 RELIEF REQUEST NO. PR-04 l

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INSERVICE TESTING PROGRAM PIAN FOR PUMPS CRAIDWOOD STATION UNITS 1 AND 2 i Revision 7 l

I RELIEF REODEST NO. PR-05 1

Deleted per Rev. Sa SER response dated December 13, 1993. '

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I j INSERVICE TESTING PROGRAM PIAN FOR PUMPS ERAIDWOOD STATION UNITS 1 AND 2 j Revision 7 i RELIEF REQUEST NO. PR-06

.. PDMP MDMBER: 1DOO1PA, 1DOO1PB, 1DOO1PC, 1DOO1PD, 2

2DOO1PA, 2DOO1PB, 2DOO1PC, 2DOO1PD,

2. NUMBER OF ITEMS: 8 pumps

3. ASME CODE CLASS: 3 i

j 4. ASME CODE. SECTION II REQUIREMENTS:

1 j

Per IWP-3100, differential pressure shall be measured on all pumps that are tested.

1 1 5. BASIS FOR RELIEF:

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'ihese pumps are positive displacement Diesel Oil Transfer Pumps. The pump

differential pressure is not a factor affecting pump performance, but rather

dependent only m the inlet prowsure to the pump. As the pump discharge pressure is j constant, and t.he inlet pressure varies with tank level, the differential pressure j is not a valid r.@erational parameter. ;

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6. ALTERNATE TESTING

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Pung discharge pressure for positive displacement pumps 'is a valid operational l l parameter. This will be used to evaluate the Diesel Oil Transfer Pumps performance.

'1 JUSTIFICATION- I Using pump discharge pressure in lieu of pump differential pressure will provide meaningful pump performance data for evaluation of operational readiness of the Diesel Oil Transfer Pumps.

8. APPLICABLE TIME PERIOD:

This relief is r.squested once per quarter during the first inspection interval.

9. APPROVAL STATUS:

a. Relief granted per NRC M neric Letter 89-04.

b. Approved per SER dated October 15, 1991 as PR 4.

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1 I INSERVICE TESTING PROGRAM PLAN FC2.o WdS

' BRAIDWOOD STATION UNITS 1 AND 8 Revis, ion 7 l

RELIEF REODEST NO. PR-07 l

Not Used'at Braidwood - Byron ONLY' i

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INSERVICE TESTING PROGRAM PLAN FOR VALVES <

CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

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INSERVICE TESTING FROGRAM FIAN FOR VALVES BRAIDWocD STATION UNITS 1 AND 2 i

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! INSERVICE TESTING PROGRAM PIAN FOR VALVES

ERAIDWOOD STATION UNITS 1 AND 2 i Revision 7 TanLE OF CONTENTS 4.0' Inservice Testing Program Plan for Valves

4.1 Program Description i

i 4.2 Program References 4.3 Valve Tables ll 4.4 Valve Notes and Cold Shutdown Justifications i

! Note 1 Main Steam Isolation Valves l Note 2 CV Emergency Boration System Flowpath valves j Note 3 Main Feedwater Isolation Valves l Note 4 CV System Letdown and Make-up Isolation Valves

Note 5 RHR Pump Suction Isolation Valves 1 Note 6 Intersystem IDCA Valves

! Note 7 Reactor Vessel Head Vent Valves j Note 8 CV, RHR Pump Discharge Check Valves

Note 9 RHR Suction Check Valves Note 10 Main Feedwater Waterhasumer Prevention Valves Note 11 VQ Purge Supply and Exhaust Isolation Valves i Note 12 AF Suction and Steam Generator Check Valves j Note 13 CV High Head Injection Isolation Valves 1 Note 14 SVAG Valves i Note 15 -Deleted-Note 16 Main Feedwater Regulating Valves

, Note 17 Main Feedwater Regulating Bypass Valves j Note 18 -Deleted- (Incorporated into Note 21)

Note 19 -Deleted- (Incorporated into Note 14) ;

j Note 20 Position Indication Testing of Solenoid Valves i

No': e 21 Main Feedwater Tempering Flow Isolation Valves )

J Lote 22 Hydrogen Monitoring System Check Valves l l Note 23 Event V Check Valves j Note 24 Pressure Relief Check Valves i Note 25 SI Pump Suction Check Valve (1/2SI8926)

Note 26 CV Pump Suction Check Valve (1/2CV8546)

Note 27 RH Pump Suction Check Valves (1/2SI8958A/B) 1 Note 28 VCT Outlet Check Valve (1/2CV8440)

Note 29 Emergency Boration Check Valve (1/2CV8442)

Note 30 AF Check Valve Leak Checks (1/2AF014A-H) i Note 31 CV/SI Mini-Flow Recirculation Line Check Valve Full Flow Testing j (1/2CV8480A/B and 1/2SI8919A/B) i

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Note 32 - Deleted Note 33 Not Used at Braidwood - Byron'ONLY

, Note 34 SD Contairunent Isolation Valves (1/2SD002A-H, 1/2SD005A-D)

$ Note 35 RH Containment Isolation Valves (1/2RH8705A/B) l Note 36 PER PORVs 1(2)RY455A/456 Test Frequency (GL 90-06) j Note 37 RH Cross-tie valves (1/2RH8716A/B) 1 Note 38 Tempering Line Check Valves (1/2FWO36A-D)

} Note 39 Feedwater Header Check Valves (1/2FWO79A-D) i Note 40 CC Supply to Non-Essential Loads (1/2CC9415) i i

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e i INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

, ThBLE OF CoMTENTS i

i Cold Shutdown Justificatons

! VC-1 Safety Injection Accumnalator Dishcharge Motor Operated Valves j VC-2 RCP Seal Injection Inlet Motor Operated Valves and Check Valves VC-3 Blowdown Flow Control /High Energy Line Break Isolation Valves-i VC-4 CVCS Letdown Isolation and Letdown Orifice Isolation valves

); 4.5 Valve Technical Approaches and Positions j VA-01 Method of Stroke Timing Valves

! .. VA-02 Method of Fail Safe Testing Valves VA-03 Method of Exercising Check Valves l VA-04 Determining Limiting Values of Full-Stroke Times for Power Operated Valves

VA-05 Testing of the Boric Acid Transfer Pumps Discharge Check Valves' j VA-06 Stroke Timing Solenoid Valves without Position Indication using Non-intrusi,ve

Magnetic and Acoustical' Techniques VA-07 Refueling Outage Justification for Manual CC Valves j 4.6 Valve Relief Requests l VR-1 EgpanMx J Type C Tested Valves

] VR-2 Containment Spray NaOH Additive Check Valves

VR-3 Safety Injection ECCS Check Valves i VR-4 Containment Spray Discharge and Ring Header Check Valves

VR-5 Accumulator Discharge Check Valve Testing During Refueling j VR-6 SI Pump Suction Check Valve j VR-7 -Deleted-

VR-8 Component Cooling RC Pusp 'Ihermal Barrier Valves VR-9 RC Pump Seal Injection CV Check Valves VR-10 Instrument Air Containment Isolation Valves.

j VR-11 -Deleted-l VR-12 Valves Stroking Normally in 2 Seconds or Less l VR-13 Diesel Generator Starting Air Solenoid Valves i VR-14 -Deleted-l VR-15A Safety Injection ECCS Check Valve Testing During Refueling l _ VR-155 Safety Injection ECCS Check Valve Testing During Refueling i VR-15C Safety Injection ECCS Check Valve Testing During Refueling f VR-16 Containment Sump Outlet Isolation Valve Testing During Refueling VR Deleted - Rev. 6 VR Deleted - Rev. Sa'. .

l VR-19 Auxiliary Feedwater Pump Suction Check Va'.ve Closure Testing Using Acoustic j l Monitoring Techniques !

)-

VR-20 Fixed Alert Ranges for Power Operated Valves-VR-21 Not used at Braidwood Station - Epon ONLY - Deleted i VR-22 Not Used at Braidwood Station-- Byron ONLY - Deleted l VR Deleted - Rev Sa.

VR-24 PR Check Valve Back Flow (Bt) Testing During Refueling ;

9 VR-25 PS Check Valve Back Flow (Bt) Testing During Refueling '

4 VR-26 RY Check Valve Back Flow (Bt) Testing During Refueling-1 - VR-27 WO Check Valve Back Flow (Bt) Testing During Refueling

{ VR-28 Containment Spray Eductor Discharge Check Valves (1/2CS011A,5)

VR-29 Fire Protection Containment Isolation Check Valve i VR-30 Chemical and Volume Control Loop Fill Check Valve 1: VR-31 Main Feedwater Header Check Valves

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d l INSERVICE TESTING PROGRAM PLAN FOR VALVES-i CRAIDWOOD STATION UNITS 1 PND 2 i Revision 7 4

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SECTION 4.1 14

! F5toGRAM DESCRIPTICIE l

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INSERVICE TESTING PROGRAM PIAN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 PROGRAM DESCRIPTION Thi Inservice Testing (IST) Program for Class 1, 2, & 3 valves meets the requirements ~of Sub ection IW of the ASME Section XI Code,1983 Edition, through the Summer of 1983 Addenda. Where code requirements are determined to be impractical, specific requests for relief are written, referenced, and included with the tables. Additional valve relief requests may be necessary and these will be identified and submitted during subsequent program revisions. Per NRC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged. Any modifications to Braidwood's Station relief requests Cpproved in the SER which are covered by one of the eleven positions discussed in NRC j Gen 7ric Letter 89-04, Attachment 1, must be performed in accordance with the guidelines given in the Generic Letter. Pre-approval is granted for all relief requests submitted which are consistent with the eleven positions given. New relief requests dealing with a po0ition not covered by NRC Generic Letter 89-04, Attachment 1, must receive NRC approval J prior to implementation. The table lists all code Class 1, 2, & 3 valves which have been

! cecigned a specific code category as directed by Subsection IW of Section XI. The table is organized according to operating system and listed in valve number order using P&ID rsfarences to further categorize.

Th2 valves subject to ISI testing are those valves which are identified in accordance with tha scope of ASME Section XI, Subsection IW-1100:

"This Subsection provides the rules and requirements for inservice testing to assess operational readiness of certain Class 1, 2, and 3 valves (and their actuating and i position indicating systems) in light-water cooled nuclear power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident."

l

, Exc3ptions to this scope are those valves which are exempt, but added to the program based

n NRC mandates. These valves are identified in the program notes and relief requests.

1' After installation and prior to service, all valves identified in this program were tested es required by Subsection IW-3100 of Section XI of the ASME Code. These tests were conducted under conditions similar to those to be experienced during subsequent inservice

tssts. When a valve or its control system has been replaced or undergone maintenance that could affect its performance, it will be retested prior to its return to service, to d: monstrate that all performance parameters are within acceptable limits.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2

$ Revision 7 1

i j s required by NRC Generic Letter 89-04, Attachment 1, Position 5, the limiting value of j eull-stroke time will be based on the valve reference or average stroke time of the valve j wh:n it is known to be in good condition and operating properly. This limiting value is i bancd on a reasonable deviation from this reference stroke time based on valve size, valve i j type, actuator type, system design, dual unit / dual train design, etc. The deviation 4

chould not be so restrictive that it results in a valve being declared inoperable due to

, racconable stroke time variations. However, the deviation used to establish the limit

, thould be such that corrective action would be taken for a valve that may not perform its

inttaded function. New or additional reference values may be required it

1) A valve has been replaced, J 1 2) When a reference value or set of values may have been affected by repair or ;

i routine servicing of a valve, or i j 3) If it is necessary or desirable for some reason other than 1) or 2) above. '

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j NRC Generic Letter 89-04, Attachment 1, Positions 1-3 discuss full stroke, alternatives to

] full stroke, and backflow testing of check valves, respectively. A valid full stroke test l j io one in which verification of maximum required accident condition flow through the valve !

l in obtained. The minimum acceptable flow value for a specific valve is determined from ;

i Technical Specifications, UFSAR, manufacturers data, engineering calculations, etc. An '

! nitornative to full stroke testing includes, but is not limited to, a sample disassembly and inspection program of valves grouped by similarity of design (manufacturer, size, j model number, materials of construction, etc.) and service conditions (including valve orientation). This sample disassembly and inspection program will be performed during j rafualing outages. A backflow test verifies that the disc travels to the seat promptly on j cessction or reversal of flow, for-check valves which perform a safety function in the l clo cd direction. For category.A/C check valves (valves that have a specified leak rate j limit and are self-actuated in response to a system characteristic), the backflow test is 3 9tticfied by performing the leak-rate test, i

j .sr NRC Generic Letter 89-04, Attachment 1, Position #8, whenever valve data is determined

} to be within the Required Action Range, the valve is inoperable, and the Technical

Specification LCO Action Statement time starts. In the event a valve must be declared j inoperable as a result of inservice testing, limitations on plant operations will be as j statsd in the Technical Specifications.

i i S:ction XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede tha requirements of the Technical Specifications.

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! INSERVICE TESTING PROGRAM PLAN FOR VALVES.

i ERAIDWOOD STATION UNITS 1 AND 2 l Revision 7 i

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 PROGRAM REFERENCES

1. Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilisation Facilities, particularly Section 50.55a, Codes and Standards.

2. ASME Boiler and Pressure vessel Code,Section XI,~ Rules for Inservice Inspection of Nuclear Power Plant Cosponents, 1983 Edition, Suuuner 1983 Addenda. ]

1

3. ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants, including 1988 l Addenda, Part 10, Inservice Testing of Valves in Light Water Reaccor Power Plants.

4. U. S. Nuclear Regulatory Comunission, . Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs. 1

5. Braidwood Station UFSAR, Section 3.9.6.2, Inservice Testing of. Valves.

6. Braidwood Station Technical Specification 4.0.5, ASME XI Program Requirements.

7 Braidwood Station Technical Staff Procedures, BVP 200-2,' 200-3, & 200-4, IST Requirements for Valves.

8. NRC Safety Evaluation Reports (SER's)':

a. SER dated October 15, 1991 for Rev. 4/4a.

b. SIR dated Setpenber 14, 1993 for Revision 5/5a.

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i IISERVICE TESTING PROGRAM PLAN FOR VALVES 1 ERAIDWOOD STATION UNITS 1'AND 2 l Revision 7 l

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EECTION 4.3

. VALVE TABLES l-l l

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INSERVICE TESTING PROGRAM PLAN FOR VALVES.

l ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 TABLE DESCRIPTION 1

j- The following information -is included in the valve susunary tables:

A. REVISION:

The revision corresponds to the current revision of the program.

S. PAGE

i j' The pages are numbered sequentially and show the total number of tables.

j C. VALVE MtEdBER:

The valve number references the unique Braidwood Station equipsnent piece. number

(EPN). This specific valve number identifies the unit and system.

i

D. R&Ig

The P&ID column references the specific P&ID number which the valves are located on.

The Unit 2 P&ID number is given directly underneath the Unit 1 P&ID ntsaber. ,

E. Qa&SA:

1, This column refers to the ASME Code Class assigned to the specific valve (1, 2, 3, . N l for non-Code, and T for tracking purposes only) .

u j F. VALVE CATEGORY:

} The valve category identifies the valve category defined in subarticle IWV-2200 of 1 ASME Section XI.

1 i G. VALVE SIZE:

The valve size lists the nominal pipe size of each valve in inches.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES KRAIDWOOD STATION UNITS 1 AND 2 Revision 7 TABLE DESCRIPTION H. VALVE TYPE:

The valve type categorises the valve as to its valve design. The following abbreviations will be used to identify specific valve types:

Gate GA Globe GL Butterfly BTF Check CK Safety Valve SV Relief Tulve RV ,

Power Operated Relief Valve PORV .

l Diaphragm Seated D i Plug P Angle AN 1

I. ACT. TYPE: l The actuator type identifies the valve actuator. The following abbreviations will be used to designate specific types of valve actuators:

Motor Operated M . O .' I Air Operated A.O.

Hydraulic Operated H.O.

Self. Actuated S.A. I Manual M l

Solenoid Operated 8.0.

.. NORMAL POSITION: I Normal position identifies the normal operating position of a specific valve. Q for open and E for closed.

l K. STROKE DIRECTION:

The stroke direction identifies the direction the valve actuator moves a specific

! valve stem to place the valve disc in a position to perform its designed safety function. Q for open, and g for closed. -This identifies the direction the valve stem will move when tested. .

Note: Exercising of a power operated valve will involve stroking the valve to both its open and closed position. The valve will only be timed, however, in the direction (s) designated to perform its safety function. Therefore, the i program plan specifies only the direction (s) in which valves must be stroked j to be timed.

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I i INSERVICE TESTING PROGRAM PLAN FOR VALVES 2RAIDWOOD STATION UNITS 1 AND 2 Revision 7 TABLE DESCRIPTICM L. TEST METHOD:

The test method colusus identifies specific tests which will be performed on specific valves to fulfill the requirements of Subsection IW of ASME Section XI. The tests and abbreviations used are as follows:

1. (Bt) t%=ck Valve amek Flow Test The check valve disc will be exercised to the closed position required to fulfill its safety function by verifying that the disc travels to the seat prosptly on cessation or reversal of fT':s, except for those valves that can only be back flow tested by means of a seat leakage test.

2. (Ct) c' hack Valve Full Straka Test The check valve disc will be exercised to the open position required to fulfill its safety function by verifying the maximum required accident flow through the valve or alternatives to full flow testing, per NRC Generic Letter 89-04, Attachment 1, Positions 1 and 2.

3. (Ft) Fall Safe Test valves with fail safe actuators will be tested to verify the valve operator j moves the valve stem to the required fail safe position upon loss of actuating power, in accordance with IW-3415.

This will be accomplished during the normal stroking of the valve. Upon stroking a valve to its fail safe position, the solenoid operator is de-energized causing air to be vented which in turn allows the spring to move the valve to its fail safe position. This condition simulates loss of actuating power (Electric and/or Air) and hence satisfies the fail safe test requirements of IW-3415.

4. (It) Position Ynd4 cation f%=ck

' Valves which are identified to require a Position Indication Test will be inspected in accordance with IW-3300 of ASME Section XI.

5. (Lt) Beat hakaae Test The seat leakage tests will meet the requirements of IW-3420 for Category A valves. On these valves, seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function. l l

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! INSERVICE TESTING PROGRAM PIAN FOR VALVES.

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

3 TABLE DESCRIPTIcet i

6. (Rt) Rafety Valve Setnoint Nack i

Safety valve setpoints will be verified in accordance with IW-3510 of ASME Section II.

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7. (St) Full Strak= Test j . Valve exercising tests of Category A and B valves will be performed in j- accordance with IW-3400. The test will include full stroke testing to verify j operability in the direction required'to fulfill the required safety function.

8. (Xt) Partial-Stroke Test l If only limited operation is practical during plant operation, the valves j shall be part-stroke (Xt) exercised during plant operation and full-stroke j exercised during cold shutdowns, in accordance with IW-3412 or IW-3522.

} M. TEST RODE:

i i Denotes the frequency and plant condition necessary to perform a given test. The j- following abbreviations are used:

un=m1 Oneration (OP)

Tests designated "OP' will be performed.cnce every 3 months, except in those modes

in which the valve is not required to be operable, j Semiannual (S) 2

} Tests with this designation will be conducted once every 6 months,~except in those

i. modes in which the valve is not required to be operable.

l Cold Shutdown (CS) !

l Valves that cannot be operated during plant operation shall be full stroke exercised

during cold shutdowns. Valve testing will commer..::e within.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown, with completion of cold shutdown valve testing not being a prerequisite to plant j j startup. valve tests which are not ccepleted during a cold shutdown, shall be

completed during subsequent'

~

cold shutdowns to meet the Code.Specified Testing j Frequency.

1 For planned shutdowns, where ample time is available, and testing all.the valves

! identified for cold shutdown test frequency in the IST Program will be accceplished, i exceptions to the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months may be taken. In case of frequent cold shutdowns, valve

! testing need not be performed more often than once during any three-month period.

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Reactor Refuelino (RR)

Tests with this designation will be conducted during reactor refueling outages.only, i

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4 INSERVICE TESTING PROGRAM PLAN FOR VALVES-ERAIDWOOD STATION UNITS 1 AND 2 Revision 7

TABLE DESCRIPTIcet

] N. RELIEF REODEST:

1

, Relief requests reference a specific request for relief from code requirements. All 3

relief requests are included in Section 4.6.

j O. NOTES:

Notes provide a short explanation concerning a particular IST valve. All notes are

included in Section 4.4.

P. TECHNICAL APPROACHES AND POSITIONS:

i j Technical approaches and positions provide detailed discussions on a particular IST J

, topic. All technical approaches and positions are included in Section 4.5.

l Q. REMARKS: 1 1 !

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, Remarks reference other information useful in determining valve testing requirements i

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WetERVIL f900 PROGRAM Pt.AN GASS 1. 2,3 AfC AUGhENTEDVALVED BR4fDWOOD NUCLEAR POWER STATION Revision 7 i

VALVE VALVE VALVE VALVE ACT. leofMAL STROKE TEST TEST fEUEF TECH.

NUhSER PedD - Ct. ASS CATEGORY SIZE TYPE TYPE P00 MON DIRECT. hETHOD manr* IEOUEST 900TES POS. IEMAfuts flNJ twig (VAp 0488473 E85-5A 3/T C 2A CIL SA C O CT OP 5 1/2A00487 N 3/T C 23 CIC SA C O Ct OP 5 4 3 VALVE TABLES- Pues 1 et 46 -

e-MMPTS\2D79GEXMLW1273D7.XLS m . . _ _ . . _ _ _ . _ _ . _ _ . _ . _ _ _ _ _ . . _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _

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l. INSEftWit . (Wee Pft00MM PLAN '

( n ama 1,2. 3 AND AUGWNTED VALVES i SMWWOOD NUCLEAR POWER STATION Revision 7 ,

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I VALVE VALVE VALVE VALVE ACT. NOISML STROICE TEST TEST fEUEF TEOL

! NUhWER PSID n ama. CATEGORY SEZE TVFE TYPE POSITION DWECT. WTHOD MODE fEOUEST NOTES POS. IEMMECS l 188.3 IWft IVA8 l 1/2AP001A E37 3 C 9.0 m SA C O MWCt OPfCS 12 3 E122 C St 154 M18 3 ,

1/2AFOO18 E37 3 C 9.0 m SA C 0 MWCt OPfCS . 12 3 l

M 122 C St IWI MIS 3 1/2AF003A E37 3 C S.O CBC SA C .. O 2WCt GPfCS 12 3-E122 3 1/2AF00SS E37 3 C 9.0 m S.A. C O MWCt OPfCS 12 3 l

E122 3 1/2AF009A E37 3 3 S.O GA M O. C O St OP 1 .

E122 It fWL 'I 1/2AF00 W E37 3 8 S.0 GA M.O. 'C O - St - OP 1 i

E122 k- fut l 1/2AF013A E37 2 3 4.0 GL KO. O C St OP 1 ,

E122 k fWt i 1/2AF0135 E37 2 3 4.0 GL K O. O C St OP 1 l l E122 k'- IWI 1/2AF013C E37 2 3 4.0 E. KO. -- .O C St OP 1 E122 k IWI 1/2AF0130 E37 2 3 4.0 E KO. O- -C St OP 1 E122 It IWI

! 1/2AF013E M 37 2 3 4.0 GL KO. O C St - CP -- 1 ,

E122 h ' IWI

, 1/2AF013P E37 2 3 4.0 E M.O - O C- St - OP 1 E122 h- fut 1/2AF0136 E37 2 3 4.0 GL M.O. O.-. C -- St -. OP 1 E122 k IWI ~I

, 1/2AF013H E37 2 3 4.0 GL M.O. O .C h. OP 1 E122 h' IWI ,

1/2AF014A E37 - 2 C 4.0 m . SA C O Ct CS 12 3 E122 C St CS 12,30 3 m- SA '

1/2AF0148 E37 . 2 C. 4.0 C :O Ct CS' 12 3 E122 'C St ' CS 12,30 'S 4.3 VALVE TAR 28-PAM 2 of 40 t

?

t 4

e:WEPTSi2D790EXCELW127307 XLS I

1

INSERVIL IING PROGRAM PUW CLASS 1,2,3 AND AUGBENTED VALVES SRADN000 NUQ. EAR POWER CTf. TION RevWen 7 VALVE VALVE VALVE VALVE ACT. NOfMAL STROKE TEST TEST MLEF TEOt.

NURSER PSD CLASS CATE00RY SIZE TYPE TYPE POSITION DIMCT. DETH00 MODE MOUEST NOTES POS. MMMuCS ONJ (VI4 (VAB 1/2AFOI4C E37 2 C 4.0 - m SA C O Ct CS 12 3 4122 C St CS 12,30 3 1/2AF0140 8437 2 C 4.0 m SA C O Ct CS- 12 3 E122 C St CS 12,30 3 1/2AF014E E37 2 C 4.0 m SA C O . Ct CS 12 3 E122 C St CS 12,30 3 1/2AF014F E37 2 C 4.0 m SA C O Ct CS 12 3 GA122 C St CS 12,30 3 1/2AF014G E37 2 C 4.0 m SA C O Ct CS 12 3 GA122 C St CS 12,30 3 1/2AF014H e437 2 C 4.0 m SA C O Ct CS 12 3 E122 C St CS 12,30 3 1/2AF017A E37 3 8 6.0 GA M.O. C O St OP 1 04122 It fut 1/2AF017S E37 3 S 8.0 GA M.O. C O St OP 1 86122 It fut 1/2AF02SA 9437 3 C 8.0 m SA _C O Ct CS - 12 3 RA122 1/2AF02SS R437 3 C S.O M SA C O Ct CS 12 3 06132 4.3 VALE TASLES - PAGE 3 et 40 e@EPTS\ZD790EXCELW127307.XLS

MSEfWR T9eG PROGRAM PLAN CLASS 1. a. J AND AUGENTED VALVE 3 BRAIDWOOD NUCLEAR POWER ETATION ftswinten 7 VALVE VALVE VALVE VALVE ACT. NOFMAL STftOKE TEST TEST fEUEF TECH.

NUhWER PSID CLASS CATEGORY SIZE TWE TYPE POSITION DWECT. WTHOD MODE fEOUEST NOTES POS. fEMAfuts fBC) (VfW IVA) 1/2CCOSS EOSIA 2 A 4.0 GA K O. O C St CS VR-S 1 413St h fut La fut VS1 1/2CC9412A4 86-2 3 3 12.0 GA M.O. C O St OP 1 E13S2 k fut 1/2CC94129 48S2 3 S 12.0 GA 94 0. C O St OP 1 4 139'2 h ful 1/2CC9413A4461 A 2 A 8.0 GA K O. O C St CS VES 1

139 1 h fut Lt fut VE1 1/2CC9414 4661A 2 A 8.0 GA M.O. O C St CS VES 1 41391 k Nt Lt fut VS1 1/2CC9418 4 08-40 3 8 18.0 GA K O. O C/O St CS ~ 40 h 948 1/2CC9418 EOSIA 2 A S.O GA KO. O C St CS VE8 1 41341 h fut Lt fut VS1 1/2CC9437AEOS1A 2 3 3.0 GL A.O. C C/O StKt OP 1.2 E139-1 h fut 1/2CC94378400-1A 2 3 3.0 GL A.O. O C/O StMt OP 1,2 E13S1 k fut 1/2CC9430 EOSIA 2 A 4.0 GA M.O. O C Lt fut VE1 E13S1 h fut 1/2CC94SS EOS3B 3 3 18.0 GA M O OM: St CS 7 1/2CC94SSAEOSSA 3 3 18.0 GA M O O/C St CS 7 1/2CC94SSSEOS3A 3 3 18.0 GA M O/C Olc 9t CS 7 1/2CC9483AEOS38 3 C 12.0 CK SA. C. O Ct/Itt OP 32 3 C

4.3 VALVE TABLES - PAGE 4 et 46 i

e:MS\2D79GEXCEL94127307.XLS i

38SERVk IW80 PROGRAM PLAN CLASS 1. a. O AND AUOWNTED VALVE 3 BRAIDWOOD NUCLEAR POWER STQTION Rownsion 7 VALVE VALVE VALVE N0fteht STROKE TEST TEST fEUEF TECH.

NURSER PSC CLASS CATEGORY SEE VALVE TYPE l TYPE ACT. POerTION DilECT. N MODE fEOUEST 180TES POS. PBANWCS 488 9 (VUW (VA3 1/2CC94838 E88-38 3 C 12.0 m S.A. C O Ctigt OP 32 . 3 d :: 4 88-38 3 C 12.0 CK S.A. C O Ct.9t CP 32 3 C

1/2CC9467A4 66-40 3 3 10.0 GA M O OC St CS 7 1/2CC94679EOS-40 3 5 16.0 GA M OC OC St CS 7 1/2CC9487CE68-35 3 5 16.0 GA M O OfC St CS 7 1/2CC9473AM4E3B 3 8 18.0 GA K O. C O/C St CP 1

, It fut I

4.3 VALVE TABLES - PAGE 5 et 46 i

1 e:MS2D790 EXCEL 94127307.XLS 4

w

m . TING PROOMM PLAN Q. ASS 1. 2,3 APO AUGRENTED vat.VED BRADWOOD NUCLEAR POWER STATION Rowinion 7 VALVE VALVE VALVE VALVE ACT. NOM 4AL STROKE TEST TEST RELEF l TEOL NUteER Pee QASS CATEGORY WZE TYPE TYPE POSITION OWECT. N MODE fEOUEST NOTE l POS. 8En4MutS IIN.) (VR3 _

(yA) 1/2CCM73948638 3 8 18.0 GA M.O. C OfC St OP 1 It m II2CCMOS 488-1A 2 AC 8.0 CK S.A. O C Ltat M Vnt, e 3

138-9 0 Ct OP VR.e 3 1/2CC5618 E88-1A 2 AC 0.75 CK SA C C Last M Vnt, a 3 E139-1 O Ce m Vne M 3-1/2CC5534 448-1A 2 AC O.75 CK SA C C Ltst M Vnt, a 3 E139-1 0 Ct M Vns 24 3 4.3 VALVE TARRIS- PAGE 8 of 46 i

a:WEPTS\2D79GiEXCEL9A127307.XLS

De0EfML eM PROGRAM PLAN QASS 1,2,3 AND AUORENTED VALVES BRAONOOO NUCLEAR POWER STATION phevenien 7 VALVE VALVE VALVE VALVE ACT. NOINAL STROKE TEST TEST IELEP TEOL NUhWER PGO CLASS CATEGORY SIZE TYPE TYPE POSITION OfdCT. RETH00 MODE fEOUEST 9 DOTES POS. IG4UUCS 4381 (VfW (VA) 1/2C8001A 4 81-4 2 8 14.0 GA M.O. O C 9t OP 1 21364 h ful 1/2CS0019 4414 2 B 14.0 GA M.O. O C St OP 1 41364 k fut 1WA E4&tA 2 C 10.0 m SA C 0 Ct fWt VI44 3 E12SIA Xt OP 1/2C30038 E4&1A 2 C 10.0 m SA C O Ce fUt Vn4 3 M12SI A Xt OP 1/2C9007A E4S1C 2 A 10.0 GA E O. C OM: Lt fut VS1 E1291C St OP 1 h fut 1/2CS0075 E4&1C 2 A 10.0 GA M.O. C OWC Lt IWt Vn1 E12S1C St OP 1 h fut -

1/2C8000A E48-1C 2 AC 10.0 m SA C O Ct/9t ful VN4 3 E12 SIC C La fut Vit.1 3 1/2C30008 448-1C 2 AC 10.0 m SA C O Ct/St IWt vn4 3 E12S1C C Lt fUt VS1 3 1/2C9000A E81-4 2 8 18.0 GA M.O. C O St fut 1 E1364 It - OP 1/2C90005 E41-4 2 9 18.0 GA M.O. C O St OP 1 E13&4 It fut 1/2C9011A 44&1A 2 C. 8.0 CIC SA C O Xt OP 3 E12SIA Ce fut VE2t 3 1/2C30119 E4&tA 2' C 6.0 m S.A. C O Xt OP 3 E12STA Ce fut VS28 3 1/2C3019A E4&18 2 9 3.0 GA M.O. C OM: St OP 1 E12S13 It fut 1/2C90198 E46-18 2 8 3.0 GA M.O. C OWC St OP 1 M.12S18 lt IUt 1/2C5020A 44&lt 2 C 3.0 OC SA C O- Ct fWt VE2 3 E12SIA C 8t OP 3 1/2C3020s 44418 2 C 3.0 CIC SA C O Ct fut VE2 3 E12STA C Bt OP 3 4.3 VALVE TABLES - PAGE 7 af 46 e

e:WEPTS\ZD79GtXCELW1273D7.XLS

I

\ .

INSGMC .SIG PROGRAM PLAN QASS 1,2. 4 A8e AUGENTED VALVE 3

NtmlDWOOO NUCLEAR POWER STATION Revision 7 i

VALVE VALVE VALVE VALVE ACT. NOIB4E STROKE TEST TEST fELEF TECH.

NURSER PSS QASE CATEGORY SEE TYPE TYPE POEffl0N DWECT. 1ETHOD MODE IEOUEST NOTES ' POS. IEM4futs i WI.l IVfW IVAl

1/2CV1128 M844A 2 3 4.0 GA K O. O C St CS 4,28 1 E13848 It IWI 1/2CV112C E84-41 2 3 4.0 OA M.O. O C St CS . 4,28 1 i E13S48 k fWe 1/2CV1120 E84-48 2 3 3.0 GA M O. C -OC St CS 2 1 !

E1384A k fWe

, 1/2CV112E E84-48 2 3 ' O.0 GA M.O. C OC- St CS 2 1 E1384A It fut 1/2CV129 EO4-S 2 3 2.0 OL. A.O. C C St OP 1 EISW It ' IWt 2

! Pt OP 1/2CV4SS M 84-8 1 3 2.0 GL- A.O. O C St . CS VC-4 1:

E13W It ' fut >

Pt - CS 2 1/2CV4GO E84-S 1 5 3# 3 el. A.O. O~ C St CS VC-4 1 l

M.138 SS It - fut R W 2 j 1/2CVS100 E84-2 2 A 2.0 OL M.O. O C k IWI - Vf48 1 1 -'

(

E138 2 R ' f51

, Lt IWI VE1 1/2CVS104 M.e4-48 2 3 3.0 SL M.O. C O St CS 2 1 E1384A R IWI

] 1/2CVS105 M84 33 '2 3 3.0 GA . K O. O C. St CS .4 1 I E19845 k IWt !

1/2CVS100 M 84-38 2 3' 3.0 SA K O. O C k CS 4 1-E13S48 It fut l 1/2CVS110 u84 34 2 8 2.0 el. K O. O Cm M GP 1, 213H k IWI 3

1/2CVS111 M.04 3A 2. B 2.0 el M.O. O C#O - St OP. 1 E13834 k f51 l 1/2CVS112 Ee4-2 2 ,A- 2.1 GL K O. O C St fut vgl.e 1 E138 2 It fWt Lt 05 vfn a 1/2CVS113 W84-2 2 AC 0.78 m- _ SA. C C LtdSt fWt vnt. 8 3 E138 2 O C fWt Vft.e 3 1/2CVS194 Es4-3A 2 3 2.0 E S.C. O CJO k OP 1 E138-3 It IWI 38 1/2CVS110 M4444 -2 8. - 2.0 E S.O. O CJO St OP 1 E13EL3A = SWi 20 4.3 VALVE Taan ca . PAeE S at 48 - ,

q a:N78GEXML94127307.30.5

l BGBERVIL iSIG PROGRAM PLAN '

CLASS 1,2. 3 Afe AUGRENTED VALVEO BRASMNOOD NUCLEAR POWER STATION Revimien 7 i

VALVE VALVE VALVE VALVE ACT. N0fB44L STROKE TEST TEST. fELMF TEOL i Damasst Pee CLASS CATEGOfty SEE TYPE TYPE POeffl0N DsECT, RETHOD MODE fEQUEST NOTES POS. IEMMWts ONJ (VfD (VA) 1/2CVS149A2844 2 3 3.0 GL A.O. . C C SWPt CS VC-4 R&130-SS

{ et SWt 4

1/2CVe14SSthe44 2 3 3.0 GL A.O. O C SWPt CS VC4

, R&1as SS k IWt 5 1/2CV914SCR4044 2 3 3.0 GL A.O. C C SWPt ' CS VC4 he.138 OS It 954 1/2CVS152 06844 2 A 3.0 OL A.O. O CJO St CS 4 1 RS1364A It fWt Pt CS. 4 2 Lt IWt Vfb1

1/2CVS153AR&O4-2 1 3 1.0 GL A.O. ' O C SWR OP l 04133 2 It IWI

}

i 1/2CV915330644-2 1 8 1.0 GL A.O. C C SWPt OP 4 A8130 2 k 154 1/2CVS150 EG44 .2 A 3.0 (N. A.O. O C/O St CS - 4 1 RS13&SA It 75% '

R m. 4 2 1

Lt fut Vft1 1/2CV8340 444630 2 C. 2.0 m SA C C- St IUt Vf430 3 04138 38 tiK.

^

" ^ ^' t 2 3 2.0 E K O. O C St CS VC 2 acro sser RS 1381 It fut ausssse ,y tiK. "' 1 2 3 2.0 GL - R4 O. O C St . CS VC 2 Acre esor I

A6133-1 It fut mesmes tiK. O" "' 2 2 S 2.0 E R&O. O C St CS VC-2 nere esor R$13e 2 It 858 aussene tiK. -' 2 2' S 2.0 GL 81 0. O C St CS VC 2 acrossof RS130 2 k IWt ' maasse l 1/K. ^^^'1- 2 C 2.0 m S.A. O C. St CS VC 2 3 acro sser RS130-1 aussene tiK. "" 1 2 C 2.0 . M SA O C St CS VC 2 3 acre asof RS13E1 aussene te " *" 2 2 C 2.0 m SA O- C St CS VC-2 3 acreesor RS130-2 susesse tiKJ-- ^ 44-2 2 C 2.0 m SA O: C St CS VC 2 3 acreseer i 84136 2 aussano 1/2CV9s40 8404-48 2 C 4.0 m SA O C St CS 28.4 3 acreesor

04:3e 43 O Ce OP aus 4.3 VALVE TABLES - PAGE 9 et 48 e:iDEPTSQD79GiEXCELiM1273D7.XLS i

(.

._ . _ . - .- _ _ _ _ _ . . m_ _ . . . - _ _ . _ _ _ - _ . _ _ _ _ _ _ . _.._____.__.___m._. _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ , _ _ _ ,_ . . , _v _ _ _ _ _ _ _ _ _ _ . _ . .. __-.. .._____ _ _ ___

.~ . . , .~

l 980EmA f900 PROGRAM PLAN CLASS 1,2,3 AND CAf0hENTfD VALVES ORAENWOOD NUCLEAR PCVWER STATION Rowhien 7 VALVE VALVE VALVE VALVE ACT. N0pm44L STROKE TEST TEST fELEF TECH.

N Pte CLASS CATEGORY SEE TYPE TYPE PoelTION DfECT. RETHOD MODE fEOUEST NOTES l'US. IEM4futS 989 (Vf4 i_ .. (VA) 1/2CV9442 E94-48 2 C 2.0 m SA C O Ct CE 2.29 3 E130 4A 1/2CV94004E044A 2 C 2.0 m SA C O Ct OP 31 3 341304A C W- O' 3 r 1/2CV94808Ee64A 2 C 2.0 m SA .C O Cp OP 31 3 mA 13e-3A C D OP 3 1/2Cve481AM 944A 2 C 4.0 m SA C 0 Ca/xt f5 WOP VR.1SA 3 R&13ELSA C St 958 M1$& 3 1/2CV94818 R4844A 2 C 4.0 m SA C O Ct/Xt IWWOP M1SA 3 R41383A C St fWt M 1SA 3 1/2CveS46 0484-48 2 C S.0 m S A. C O Ct fWI M1SA 2.20 3 RE13644 ti2CJ:::^^ " " " " ' "

2 8- 8.0 GA M.O. C O St CS 2 1 0613841 h 154 4.3 VALVE TA F ES - PAGE 10 et 48 -

e:WEPTSm>790EXCELW1273D7.XLS

N TWeG MWGRAM PLAN CLASS 1,2,3 AM) AUGhENTED VALVE 3 BRADWOOD NUCLEAR POWER CTATION Revision 7 VALVE VALVE VALVE VALVE ACT. NOFWAAL STROKE TEST TEST MLEF TEOL NUhWER PSm MASS CATEGORY SEE TYPE TYPE POelTION DIMCT, METHOD MODE M OUEST NOTES POS. FEM 4futs 158 3 M (VA)

St20este2A E54 4 NONE B 3.0 GA S.O. C O St OP VTI-13 titoestese 4 152-20 NOfE B 3.0 GA S.O. C O St OP MIS tizoestesA 4 54-4 NOME 5 3.0 GA S.O. C O St OP M13 t/20esiess # 54-4 NOff 8 3.0 GA S.O. C O St OP M13 1/20estesa E152 *2 NOME C 3.0 M SA C O Ct OP M13 3 1/20es1% E152-20 NOfE C 3.0 m SA C O Ct OP MIS 3

[t20estesa E152-20 NONE C 3.0 m S A. C O Ct OP M 13 3 1/20eetees # 152-20 NOlE C 3.0 m SA C O Ct OP M13 3 4.3 VALVE TAGLES - PAGE 11 et to e:WEPTSW79GEXCELW1273D7.XLS

9 900EfWh f980 PTIOGRAM MAN CLASS 1, a. J ADO AUGRENTED VALVES BRAWWOOD NUQ. EAR POWER CTATION Movimien 7 VALVE VALVE VALVE VALVE ACT. NOIMAL STROKE TEST TEST IELIEF TEOt.

NUhWER PSID CLASS CATEGORY SIZE TYPE TYPE Poem 0N DOECT. RETN00 MODE fEOUEST NOTES Pot. . . _ ___.

IBIJ IVI4 fvAl II200003A K5019 3 C 1.5 CK S.A. C 0 Ct OP 3 E130-1A C Bt OP 3 112000038 K50-1A 3 C 1.5 m S.A. C O Ct OP 3 E130-15 C gt CP 3 1/200003C K50-18 3 C 1.5 CK SA C O Ct OP 3

130w1A C et OP 3 1/2000030 h450-1A 3 C 1.5 CK SA C O Ct OP 3 E13019 C St OP 3-4.3 VALVE TABLES- PAGE 12 of 40 i

a:WEPTS2D790tXCELW1273D7.XLS

WWEfML T980 PROOMM PLA4 CLASS 1,2,3 AfD AUOhENTED VALVES SMEWOOD NUCLEAR POWER STMION r Reviulun 7

.f 3

VALVE VALVE VALVE VALVE ACT. N0fuent Sin 0KE TEST TEST fELEF TECH.

pamasR PeID (1 ASS CATEGORY SIEE TYPE TVPE PoemON ONECT, hETHOD MODE fEOUEST NOTES POS. BERS4fRS Wil IVf4 IVA) 1/2FC000 kHS-1A 2 A 4.0 P M C C Le f54 mi PAtelWE 1/2FC010 RMS 1 A 2 A 4.0 P M C C Lt 154 M1 PASepVE 1/2FColl RMS-IS 2 A 3.0 P M C C Lt f54 M1 PAtelVE RMS-1C 1/2FC012 GHS-IS 2 A 3.0 P M C C Lt fut M1 PagelWE

RMS-1C 4.3 VALVE TAMES - PAM 13 at 4e e 1DEPTSED790EXCELW127307.XLS

_ _ _ - - . _ . _ _ _ _ _ _ _ _ _ - - . _ - - _ _ - - - - . _ _ _ . . - _ _ _ _ _ - -___ . - - . - . . . - - . . - . - - - . - . - - - . . . - , . . - - . . . - , - - - - . , - . . - . .- . _ - - , - . _ . - ~ . _ - - - - - _ _

N - iWO PROGRAM PLAN CLASS 1,2. 3 AND AUGGENTED VALVES BR4pM000 NUCLEAR POWER CTAT10N RevWen 7 VALVE VALVE VALVE VALVE ACT. N00M4L STROKE TEST TEST fElRF TECH.

NURSER PSAO QASS CATEGORY SEE TYPE TYPE POSm04 DEECT. hETH00 MODE IEQUEST NOTES POS. ISRAMES 138 9 (Vft (VA) 1/2PP010 us2-1 2 S 4.0 GL A.O. O C St OP 1 It fWt Pt OP 2 1/2 FPS 45 E52-1 2 C 8.0 m S.A. C C 9t 558 Vf429 3 4.3 VALVE TABLES PAGE 14 of 40 e@EPTSSD79GEXCELW1273D7.XLS

Ne9EftVM, flNG PROGRAM PLAN CLASS 1. 2. 3 AND AHOWNTED VALVES BRADNOOO NUCLEAR POWER STOTION fh4 mien 7 VALVE VALVE VALVE VALVE ACT, IN0fM AL STROKE TEST TEST fEUEF TECH.

NUMBER PSID CLASS CATE00RY St2E TYM TYPE POSITION DMECT. ETHOD MODE PEOUEST NOTES POS. feERKS WNJ (Vfg (VA) 1/2FW0004 E3 SIC 2 8 10.0 GA H.O. O C St/Xt CS/0P 3 1 4 121 18 h fut 1/2FWOO98 43&tA 2 8 18.0 GA H.O. O C St/Xt CS/OP 3 1 41210 h fW4 1/2FWOO9C E3SID 2 3 18.0 GA H.O. O C St/Xt CS/0P 3 1 4121-1 A k fut 1/2FWOO90 4 3 &19 2 8 16.0 GA H.O. O C St/Xt CS/0P 3 1 E121-1C k fWt 1/2FWO344 M4&lC NONE 8 2.0 GL A.O. O C Ft fft 21 2 4 121-10 1/2FWO348 438-1A NOPE P 2.0 01. A.O. O C R 944 21 2 2121-1D 1/2FWO34C 43&1D NONE 5 2.0 GL A.O. O C R fut 21 2 4121-1 A 1/2FWO340 E3&18 NONE S 2.0 OL A.O. O C Ft fut 21 2 E121-1C 1/2FWO.95A ESSIC 2 3 3.0 GL A.O. O C St OP 1 2 121-19 R PWt M OP 2 1/2FWO358 ES&tA 2 3 3.0 GL A.O. O C St OP 1 E121-10 k fut R OP 2 1,NC E3&1D 2 5 3.0 OL A.O. O C St OP 1 4121-1A k ful R W 2 ,

1/2FWO350 E3618 2 5 3.0 GL A.O. O C 9t OP 1 4121-1C k fut

~

R OP 2

'- kN>W E361C 2 C 3.0 m SA 0 C 9t CS 38 3 4 E121-te 1raWO3ee E361A 2 C 3.0 m SA 0 C 9t CS 38 3 E121-1 A 1/2FWO30C E361D 2 C 3.0 m SA O C 8t CS 38 3 E121-1C 1/2FWO30D ESS18 2 C 3.0 M SA 0 C 9t CS as 3 2121-1C 4.3 VALVE TAALES - PAGE 15 et 48 o@EPTSQDT9GTEXCELW127307.XLS

WSENVB .TWG FROGMM PLAN

1 ama 1,2,3 Afe AUORENTED VALVES ORASNWOOD NUCLEAR POWER STATION

}

Revhlen 9 5

')

VALVE VALVE VALVE Va&VE ACT. NOfth4L STCJIEE TEST. TEST fELEF TECH.l Nuh.ER Foo aASS C m .oRv SeE Tm Tm POm=W oW.CT. .TItoo mooE f.auEST .O m = fEuh=0 Wil fVfB fWAl 1/2FWOSSA RSSSIC 2 S 8.0 GA A.O. O C St CS TO 1 ;f R&121-19 k IWI R CS 10 2 1/2FWOSSS R43&1A 2 3 S.O GA A.O. 0- C St CS 10 1 RG121-1D k fWt >

Pt OS 10 2 1/IPWOSSC R43&10 2 S 5.0 GA A.O. O C St CS TO 1 RS121-1A It IWt Ft CS 10 2 1/2FWUSSD R&3&13 2 5 0.0 e4 A.O. 0 -C St CS 10 1

, R&t21-1C k fWt i

Pt CB 10 2 1/2FWO43A h438-1C 2 3 3.0 el A.0- C C St CP 1 R&121-10 k IWt ?

, Ft W t l 1/2FWO435 h6361A 2 3 3.0 GL A.O. .C C St OP 1

, R&t 21-10 It fWt

-R W 2 1/2FWO43C RSa&1D 2 5 3.0 GL A.O. C C St OP 1 '(

i h4121-1A k -IWt i

Pt OP 2

, 1/2FWO430 RS361-5 2 3 3.0 GL A.0- C. C St ' OP 1 R4121-1C k IWt '

Pt 'OP '2 1/2FWO794 RS381C 2 C. 15.0 m S.A- 0 C St CS Vf441 3 R&t21-19 -'

1/2FWO795 h63&1A 2 C 18.0 ;M SA 0 .C St CS VI431 3

, RS121-10 I 1/2FWO79C h438-10 2 C 18.0 M S A. 0- C St CS Vf431 3 i

RS121-1A

1/2PWO790 RSa&13 2 C ' 14.0 - M SA 0 C St CS VI431 3 RS 121-1C

! 1/2PWS10 h4341C 900RE 3 19.0 Abt A.O. -O C Pt . SWt IS 2 RS121-1 1/2FWS104 RSS&lC NONE 3 4.0 eA A.O. C C Pt f54 17 2 R4121-1

~ 4.3 VALVE TARES-PAM te of 48 l

. e: MIEPTSVD79GiEXCEL98127307.XLS

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h0EfML (h6 PROGRAM PLAN CLASS 1,2,3 AND AUONENTED VALVES BRAADWOOO prsCLEAR POWER STATION Revision 7 VALVE VALVE VALVE VALVE ACT. N0fMAL STROKE TEST TEST fEUEF TECH.

NUISER Pee CIAss CATEGORY SEE TYPE TYPE POSITION DNECT. IETH00 MODE fEOUEST NOTES POS. IEMAMS M.) (VRB IVAf 1/2tA005 E55-10 2 A 3.0 GL A.O. O C Lt fut M1 E55-15 9t f54 M10 1 Ft WWI M10 2 k f54 1/2tA006 4 55-10 2 A 3.0 GL A.O. O C/D Lt fut M1 +

M55-15 St f54 M10 1 Pt f54 VR 10 2 k f58 1/244001 2 55-10 2 AC 0.75 CK S.A. C C Lt/St 75% M 1,10 3 M55-15 O Ct OWI M10 3 4.3 VALVE TASLES - PAGE 18 et de e:WEPTSED79GtXCELW1273D7.XLS

__-.-- - -- - - - _ _ _ _ . - - - _ - _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ _ - . _ _ _ . - - . - - _ - . . _ ~-- .. . _ _ . - _ . - . _ _ - _ . _ . . - - - - _ _ _ _ _ _ _ _ _ -

SIOERVIL i500 PROOnmM PLAN

. (1ASE 1. 2, O Ape AUGAEfffEO VALVES ,

ORAWWOOD flut1 EAR POWER CTAT10N f Movtutun 7 l'

VAtvf ACr. Idoment Sinou mr HURSER PGID CLASS vAtve vuvrlVavE TEST IEuEP TECH.

CATEGORY SEE TYPE TYPE POSITION DEECT. AKTH00 SAODE SEOUEST DIOTES P05. IEhenfute 98.) (vf4 (val 1/20W001A AS35-2 2 8 30.25 SA H.O. O C Stott CS/UP 1 1 E120 34 k IWt

, 1/20W0018 E35-1 '2 8 30.75 GA H.O. O C Stott CBCP 1 1 4

IS1N1 k IWI 1/20 MOO 1C h435-2 2 S 30.75 GA M.O. O C - state CSPOP 1 1 RS1201 k IWI 1/28M001D R438-1 2 8 30.25 GA M.O. O C Stolt CSJ0P 1 1 RS1201 k IWt 112900013A R&35-2 2 C e.0 X SV SA C OPC m fWt -

RS120 2A 19.0 1/20000138 R&35-1 2 C 9.0 X SV SA C Om Mt _ IWt RS1201 10.0 StatA013C RS35-2 2 C 9.0 X SV SA C OPC ftt fWt R&t20IS 19.0 1/2843013D R638-1 2 C S.O X SV ' SA C Om Mt 958 RS1201 10 0 1128 5 0144 E35-2 2 C S.O X SV SA C OC- Ott IWt sta3A i 1/28 5 0148 8635 2 C S.O X SV SA C OC Nt - IWt RS120-1 10.0 1/20M014C RS35-2 2 C 5.0 X SV SA C OC' Mt IWt R&120 25 10.0 I 1/29A30140 RS35-1 2 C S.O X SV SA C OC Rt - fWI R&t20-1 10.0 ir20Ae01sA m as-2 2 C e.o X SV SA C- Om m fui m12e 2A to.e 1/20m0198 RS35-1 2 C- S.O X SV SA. C OC fut fut nS12o-1 to.o -

1/205019C RS35-2 2 C S.O X SV SA C. OC Rt ^ f51 h4120'28 10.9 1/285 0150 R635-1 2- C S.0 X SV SA .C OC . Mt fut

., .1 1.

4.3 VALVE TARES .Puhm te et 44 1

QWilPTSED7peEXCELDA127307.)tLS

_ _ _ _ _ _ _ _ _ _ _ _ __ . _ _ _ _ _ _ _ _ . _______.__ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ . . _ . . . . _ , . . . _ . _ . . . _ . ~ . . . . . . . . . . - . _ . ~ . . _ _

F NSERVK. NO PROGRAM MAN CLASS 1. 2,3 AND LUGWWTED VALVES ORAIDWOOO NUCLEAR POWER Lif. TION Revision 7 VALVE VALVE VALVE VALVE ACT. NOFMAL STROKE TEST TEST M UEF TECH.

NUhWER PedD CLASS CATEGORY SIZE TYPE TYPE PO0fT10N OrlECT. WTHOD MODE EOUEST NOTES POS. MMARKS few 3 (Vpe (VAp 1/2Me018A E352 2 C S.O X SV SA O Om m M E120-24 10.0 1/2M80188 ESS-1 2 C 8.0 X SV SA O Om m M M12S1 10.0 1/2M8018C E352 2 C 8.0 X SV SA O O/C m M E12428 10.0 1/2M5018D 4351 2 C 8.0 X SV SA O OtC Rt M M1241 10.0 1/2M0017A 4352 2 C 8.0 X SV SA O OIC m M E1242A 10.0 1/2M90179 4351 2 C 8.0 X SV SA O OC Rt M E1241 10.0 1/2M8017C ES352 2 C 8.0 X SV SA O OlC Rt M E12429 10.0 1/2M0017D ESSI 2 C 8.0 X SV SA O O/C m m 41241 10.0 1/2M8018A E352 2 8 8.0 X PORY H.O. C C/O St OP M12 1 E120 2A 8.0 h m R OP 2 1/2M80198 4351 2 5 8.0 X PORY H.O. C C/O St OP M12 1 E120-1 8.0 h m Pt OP 2 1/2MB018C 4352 2 5 8.0 K PORV H.O. C CIO St OP M12 1 4 120 29 8.0 h m Pt OP 2 1/2M801ED M351 2 8 8.0 X PORV H.O. C C/O - St OP M12 -1 E1241 8.0 h m R OP 2 4.3 VALVE TAOLES.PAGE 20 of 48 e:TEPTSVD79GTEXCELW1273D7.XLS

MSEFML IW8G PROGRAM PLAN CLASS 1,2. 3 AND AUGMENTED VALVES WRMOWOOD NUCLEAR POWER STOTION Revision 7 1

VALVE VALVE VALVE VALVE ACT. NOFSML STROKE TEST TEST IELEF TECH.

NUhWER PalO CLASS CATEGORY SEE TYPE TYPE POSITION DPECT. 1ETHOD MODE fEOUEST NOTES POS. fetWWCS ONJ (VRI (VA) 1/2M80194 E35-2 2 8 8.0 OA M O C 9t OP

120-2A 1/2M80198 E35-1 2 5 8.0 GA M O C 9t OP E1241 1/2M8019C E35 2 2 8 8.0 GA M O C St . OP M12429 1/2M8019D E35-1 2 5 8.0 GA M O C 9t OP E1241 1/2MS101A E 35-2 2 3 4.0 OL A.O. C C St OP 1

120-2A k M Ft OP 2 1/2MB1018 E35-1 2 8 4.0 OL A.O. C C 9t CP 1 E1201 k m Ft OP 2 1/2M5101C 4 35-1 2 5 40 GL A.O. C C 9t CP 1 412429 h M Ft OP 2 ;

1/2MB101D E35-1 2 8 4.0 GL A.O. C C. 9t OP 1 E120-1 h M Ft OP 2 4.3 VALVE TA8E8 PAGE 21 et 48 I

o-iDEPTS12D79GiEXCEL1M127307.XL5

INSERVM. MG PROGRAM PLAN CLASS 1,2. 3 AND AUGGENTED VALVED BRACWOOO NUCLEAR POWER CTATION Revision 7 VALVE VALVE VALVE VALVE ACT. NOfMAL STROKE TEST TEST M UEF TECH.

NUMIEft P&O CLASS CATEGORY SIZE TYPE TYPE POSITION DNECT. fETH00 MODE fEOUEST NOTES POS. IEMAfWts IIN.B fvf4 (VA) 1/2OG057A E47-2 2 A 3.0 BTF M.O. C Ct0 Lt fWt M1 9t OP E190 2 h fut 00G059 E47-2 2 8 2O STF M O. C O St OP 1 h fut 000061 4472 2 8 2.0 STF M.O. C O 9t OP 1 h IWt 000082 4 47-2 2 5 2.0 STF M O. C O St OP 1 h IUt 000083 E47-2 2 B 2.0 STF K O. C O 9t OP 1 h fWI 00G004 4472 2 8 2.0 STF M.O. C O St OP 1 h fut 000005 E160-2 2 8 2.0 OTF M.O. C O St OP 1 h fut 1/200079 E47-2 2 A 3.0 STF M.O. C C/O Lt fWt M1 2150w2 St OP 1 h FUt 1/200000 M-47-2 2 A 3.0 STF M O. C C/O Lt IUt VR-1 E190 2 St OP 1 h fut 1/200081 E47-2 2 A 3.0 STF M.O. C C/O Lt fut mt E150L2 St OP 1 h fut 1/200002 E47 2 2 A 3.0 BTF M.O. C C/O Lt f44 M1 41542 St OP 1 h fut 1/200083 M-47 2 2 A 3.0 BTF M.O. C ClO Lt fWt VM1 4 150'2 St OP 1 ft fUt 1/200064 E47-2 2 A 3.0 BTF M O. C CIO . Lt IWL M1 4 150-2 St OP 1 h fut 1/200005 E47-2 2 A 3.0 STF K O. C CIO Lt fut M1 M 150'2 St OP 1 h IUt 4.3 VALVE TABLES - PAGE 22 of 46 e:WEPTSUD79GTXCELW1273D7JCLS

BIERMt IDIO PROGftAM MAN CLASS 1,c.o AfS AUGAENTOVALVES

, WIANNYOOD NUCEAft POWER STOTION Rovanisse 7 -

i i

VALVE VALVE VALVE WALVE ACT, N0fRML STROKE TEST TEST fERMF TECH.

paanset PGID QASS CATEGORY SIEE TYPE TYPE Poem 0N DPECT, RETHOD MODE fEOUEST ff0TES POS. IBAMUES Wel (VIE fv4f 1/2PRD01A 147S10 2 -A 1.0 GL A.O.' O C Lt IWI VE1 j E151 1 Pt ' OP . 2 !

R W 1 ,

It fut ,

1/2PRD018 E7910 2 A 1.0 GL A.O. O C Lt fut ' -WE1 '

E191-1 Pt OP 2 St OP .1

.[

n mi i 1/2PRD02E E764 2 A 2.0 GL M C C Lt f54 VE1 PASSIVE 1/2PRDO2P E7&S 2 A 2.0 E M C C Lt fut VE1 PASSIVE i

It2PROO29 E7&S - 2 AC 2.0 Cpt .BA C C Lt fWt Vgl-1 PASWWE It2 PROS 2H E784 2 AC 2.0 M S.A. C C Lt fWt . Vft.1 PAggfWE i 1/2 PROS 2 R47410 2, AC 1.0 M SA C C l.tigt 15l WR-I,24 3 E181-1 1/2PR0334 E756 2 A 2.0 el. M C C Lt fut ' .VE1 PAgglWE 1/2PNBass R47Se 2 A - 2.0 SL M, C. C Lt 958 VE1 PAsWWE 1/2PROSSC E7&S 2 A 2.0 - el M C C Lt f54 VR1 PASSIVE 1/2 PROS 3D M.7Se .. 2- A 2.0 E M C C- Lt IWI WE1 PASWWE 1/2PRDOS h47&10 2 ,A 1.0 E A.O. O. C Lt .fWt- VE1 R4151-1 Pt OP 2' It . ' IWt '

et > OP 1 4.3 VALVE TAR 28 - PAW 23 et 48 .

e1EPTSED79GfXCELM27307.MLS

BIGERWit (W40 PROOMM PLAN CLASS 1,2,4 Ape AUGREftTED VALVES SMENWOOD NUCLEAR POWER STATION Revisten 7 i

VALVE VALVE VALVE VALVE ACT. NENWML STROKE TEST TEST fELEP TEOL NURGER PGO GASS CATEGORY SEE TVPE TVPE POel110N DOECT. GETHOD MODE IEOUEST 9001ES POS. IEMMutt M.I IVf4 (VA) 1/2PS22eA La fut VE1 R485-7 2 A 0.5 GA S.O. O C/O - St OP VII 12 1 041448 R OP 2 R OWt 20 1/2PS2288 Lt fWt M1 h400-7 2 A 0.5 GA S.O. O C/0 St W M12 1 R41448 R OP 2 h IWI 20 i 1/2PS2294 Lt . fWt Vft 1 4 E00-7 2 A 0.5 GA S.O. O C#O St OP M12 1 R4140-8 R OP 2 R IWt 20 1/2PS22GB Lt fWt Vft-1 h68E7 2 A 0.5 GA S.O. O ClO St OP M12 1 E1444 R OP . 2 h put 20 1/2PS2304 Lt ful M1 ;

1 R&eE7 2 A 0.5 GA S.O. C C/O St OP VR-12 1' I i

RS140'S - Pt OP 2 i k IWI 20 ,

1/2PS2 SOS Lt . fut VE1 8400-7 .2 A 0.5 GA S 0. C ClO St OP VEtt 1 R61404 R OP 2 R IWI 20 5 1/2PS231A R&GS7 2 AC 0.75 m S.A. C C LWBt. IWI vet,25 3 ;

, R61444 O Ct OP' 22 3 1/2PS2315 R68E7 2 AC 0.75 m S.A. C C LtJOt . 1W1 VE1,25 3 RS1468 O Ce ' OP 22 ' 3 i

4.3 VALVE TM - PAGE 24 af 48 l

4 l

1 i

e:iDEPTSGD790iEXCEL98127307.JELS r

'f

WIEUMC. .m8 PROGRAM MAN N m.1. 2. 3 AND AUGWNTED VALVES '

MAEMOOD NUCLEAR POWUt STQTION Revealen 7 ,

- i VALVE VALVE VALVE VALVE ACT. NOIBML STROIEE TEST TEST IELEP TECH. ,

. NURSER Pee CLASE CATE90ftY SEE TYPE TYPE. Poem 0N ONECT. WTHOD MODE 8EOUEST SIOTES POB. IEMMute

! WI.) (VID IVAl 1/arte354A St OP 1 E80-7 2 A 0.375 OL A.O. C C Lt - 55l M1 .

E140-1 ft fWt '

Pt (F 2 1/2POSS848 St OP 1 ESO-19 2 A 0.3M OL A.O. C C Lt fWt - M1 .

E1401 It 154 Pt CP 2 1/2POBROBA St OP 1 E8e-18 2 A 0.3M OL A.O. C C La fWt VE1 E1401 It IWI Pt OP 2 1/2P993505 St' OP 1 R4.Ge-18 2 A 0.3M E A.O. C C Lt 154 VR-1 }

E1401 ft IWI Pt OP 2 It2PeseteA St OP -1 EOSIA 2 A- 0.3M el A.O. C C Lt 954 VE1 R$1401 It IWt Pt CP 2 1/2P93056 St OP 1 R&ee-1A 2 A O.3M SL A.O. C C- Lt 558 VR.1 R$14061 11 IWt Pt OP '2 1/3POS357A St OP 1 2 40615 2 A S.3M E A.O. C C Lt fut VE1 E1441 It fWt Pt 'OP 2 3

1/2Pese5M St OP 1

't R$eE18 2 A 0.3M E A.O. C C Lt fWt M1 R$1461 It ful Pt CP 2 4.3 VALVE TARES PAM 25 of 40 a:iDEPTSQD70eiEXCELW127307.NLS

SISEfWh TWIG PROOMM PLAN r1 ama 1. 2. 3 AND AUGIENTED VALVES .

SMIDWOOO NUCLEAR POWER STQTION s Revishan 7 t

I s

i 4

VALVE VALVE VALVE VALVE ACT. 9000RML STROIE TEST TEST fELEF Teat.

NURSER PSID CLASS CATEGORY MEE TYPE TYPE POWTION OBECT. RETHOD MODE IEIRIEST IIOTES POS. fEmmISES WL) IVIE fv4) 1/2R0014A R40018 1 8 1.0 GL S.O. C OE . St CS - Vn12 7 1- -;

a 84135-18 Pt CS 7 2 8 IWI 20 If2R00148 8400-19 1 5 1.0 SL S.O. C OfC 55 CS vfl 12 7 _. 1 04135-19 Pt CS 7 2 8 IWI 20 1/2RC014C R400-18 :1 8 1.0 - GL 5 O. C OC St CS M12 7 1 'I R4135-15 Pt CS . .7 2 .l

'S IWL 20 1/2ftC014D ESO-15 1 5 1.0 W.. 5.0. C , OC St CS ' VR 12 7 1 04135-18 Pt CS 7 _- 2,

'k IWI 20

. 4.3 VALVE TAR 28'- FNIE 20 at 48 -

i i

e:WEPTSEDTSOEXCEL981273D7.MLS u_._____ m.__..m___._ . _ _ _ _ _ . . _ . ._._..__m_._- __. _.,m_ . . - _ _ _.m._...___m._-m ______.___m___.__- _-__.___m___m_ _ _ . _ _sm _ ____ _ - ____m.__.___mo_ _--__o___.--__- -

__.___m ____ _______ _ _ _ _ _ _ _ _ _ . _ _ _

t SIMIMC. .MG PRoeRAM MAN GASS 1,2,3 A80 AUGhENTED VALVEQ NthWWW000 NUQfAR POWER CTATION Mushism 7 ,

4

.I VALVE VALVE VALVE VALVE ACT, feOfSAAL STROICE TEST TEST IELEF TECH.

4 NURGER PSm as ama CATEGOftY 'SEE TVPE TYPE POSITICIe DUECT. RETHOD RAODE fEOUEST 100TES POS. fERAnfUt3 f WI.) (VUt (val 1/2fE1003 E70-1 2 A 3.0 0 - A.O. C C St OP 1 E141-1 Lt 5W4 Vft 1 ,

k fWt Pt CP 2 1/2fE9187 E791 2 -A 1.0 D . A.O. O C St- OP 1 E141-1 Lt IWt - mt R IWt Pt OP 2 1/2fE915SA EN1 2 A 0.75 D A.O. O C St OP 1.

E141-1 Lt fut mt

k' fWl R W t 1/2fE915ES EN1 2 A O.79 D A.O. C C . St OP M12 1 E141-1 Lt - fUt M1 h IWt PI W 2 1/29E91004 E701 2 -A 1.0 O . A.O. O C St OP 1 E141 1 Lt IWI M1 ,

-R IWI '

Pt OP 2

- 1/2fE91GOS EN1 2 A 1.0 - O A.O. O C, St OP. 1 E141-1 . Lt 95t M1 -

It IWI 4 M W 2 .

If2fE9170 EN1 - 2 A 3.0 0 A.O.. O C St OP 1 E141-1 Lt 958 31 R 954 N W 2 ,

'i 4.3 VALVE TASt28. PuhW 27 af 48 e@EPTSGD790EXCELVW127307JtLS

________..________m_.-,w-, ..~~..m..se.-,we- .3% . ..-r, .<we* .-~w%e .viw...* *..v-.e=- w.e. +-w.. +.w-.* ..w._ m .-km-- . - * - . - x_ m__mm t._._ __m._ . _ . _ _ .

DdSEfMC. IlNG PROGRAM PLAN CLASS 1,2,3 AND AUGRENTED VALVES ORADN000 NUCLEAR POWER STOTION Iktsien 7 VALVE VALVE VALVE VALVE ACT. NOpMhl STROKE TEST 1YST FEUEF TEOt NURSER 6 CLASS CATEGORY SEE TYPE TYPE POSITION DNECT. RETHOD MODE fEQUEST 9eOTES 998. FEMMES IBd.) (Vft (val 1/2fE026 M-4ELes 2 A 2.0 P A.O. O C Lt fWt Vfl!-1 St OP 1 R IWL Pt OP 2 1/2WO27 M 40-8A 2 A 2.0 P A.O. O C Lt fWt M1 St- OP 1 It FWt Pt OP 2 4.3 VALVE TAKES - PAGE 29 of 4e e:MSUD79GTXCELW127307.XLS

l l

WesEftVit. .D00 PROGfthM PLAN I Ct. ASS 1,2. 3 AND AUetENTED VALVES -!

SRERWOOD NUCLEAR POWEft STAT 1ON

Rowtulen 7 l

i 4

VALVE VALVE VALVE VALVE ACT. N0fteht STROICE TEST TEST IELEF TEOt.

pam pg5 CLASS CATEGORY SIZE TVPE TYPE PO9fflON DEECT. RETH00 MODE SEOUEST MW POS. IER4Muts IBI.) (VfD tvAl 1/2f90810 E82 . '2 3 3.0 GA M O. O Cm at OP R$137 k IWI 1/2190811 E42 2 8 3.0 GA M.O. O CJO St OP 06137 m 158 1/20 deb 701A RSe2 1 A 12.0 GA M O. C Om St . CS S- 1 RS137 'k IWI D M e !

1/219037019 RSS2 1 A 12.0 SA M.O. C Om St CS 5 1 2 96137 R fWt Lt IWI e i

1/2fDOS702AEtt 1 A 12.0 SA M O. C Om St CS S 1 f E137 'k IWI u foi e '!

1/20D057023 RSet 1 A 12.0 GA M O. C Om St CS S 1 R&137 ' R ' f54 Lt IWI e 1/2fDt5705AR642 2 AC O.75 m SA C C LWWt #Ut Vfbigt .e 3 RS187 O Ct IWI Vfbits 24, as 3 1/219457055 h682 2 AC 0.75 m SA C C LWWt fUt . Vfbl58 .e- 3 RS137 O Ct 151 Vfb1W 24, as 3 ,1 t i.- - . "5 2 C 3.0 X RV SA C O Rt fWI R$137 4.0 1/259007000 RSet 2 C 3.0 X ftV SA C O Rt IWt I B6137 40 1/2190571840642 2 3 0.0 - SA M O. O CJO - St CS 37 1, 4 +

06137 k IWI ,

1/25D45715 that .2 5 s.0 SA M.O. - O CJO St CS 37 1, 4 RS137 k IWI 1/21993730Ae682 2 C 5.0 CK SA C' O - (3/30t CSJOP e a RS187 C St CS~ 3 1/299037300 R682 2 C e.0 CK SA C 0 Cantt CSJOP e 3 R&t37 C Os CS 3 ,

i 4.3 VALVE TAM 25 - PAM 29 et de ,

.L e:N798 EXCEL *A4127307.31LS

9 C1 ASS 1,2,3 AND AUGNENTED VALVES ORAIDWOOD NUCLEAR POWER CTATION hovhien 7 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST fEUEF TECH.

NUMBER PelD M SS CATEGORY SIZE TYPE TYPE POttil0N DNECT. MTH00 MODE fEOUEST NOTES POS. fEMAfWCS WN1 (VRI IVAl 1/2RYO75 420046 2 A 0.5 GL M C C Lt M M1 PASSlYE 4 2135-0 1/2RY455A E045 1 8 3.0 PORV C Om St CS 38 1 E1354 A.O. k ful Ft CS 2 1/2RY458 4 00-5 1 5 3.0 PORV A.O. C OM St CS 36 1 4 135-5 k ful Fe CS 2 1/2RYS000A 2005 1 3 3.0 GA M O. O C 9t OP 1

1354 h fut 1/2RY90008 2845 1 B 3.0 GA M.O. O C 9t OP 1 E135-5 k fWI 1/2RY9010A E845 1 C 8.0 SV SA. C OC Rt fut 21364 It fWt 1/2RY90100 4845 1 C 8.0 SV S.A. C OC Rt FUt E138-5 h fut 1/2RYS010C 4845 1 C 8.0 SV S.A. C OIC Rt 14%

E135-5 h F54 1/29tV9025 4 00-8 St OP 1 4 135-8 2 A O.375 GL A.O. C C Lt fWt VR-1 h ful Ft OP 2 1/2RY9028 4 00-8 St OP 1 4 135-8 2 A O.375 OL A.O. O C Lt ful M1 h FWt Ft OP 2 1/2ftV9028 4 80-8 9t OP 1 i E135-8 2 A 3A D A.O. O C Lt #Ut VR.1 h fut Ft OP 2 1/2RYS033 4848 9t OP M12 1 4 135-8 2 A 0.75 D A.O. O C Lt fut M1 ft 754 Ft OP 2 4.3 VALVE TAGLES PAGE 30 et 48 e@EPT5'.* MIXCEL*41273D7.XLS

CLASS 1,2,3 APO AUGhENTED VALVES ORAUNOOD NUCLIAR POWER STOTION Rwheen 7 VALVE VALVE VALVE VALVE ACT. N0fMAL STROKE TEST TEST fELEF TEOL NUhWER PSC CLASS CATEGORY SEE TWE TYPE POSITION DWECT. AETHOD MODE fEOUEST NOTES POS. fEMutts ON.) (VIO (VA) 1/2RYWO46 4 80-8 2 AC 3.0 m SA C C Lt/St fut VE1,29 3 E1384 3 ft2RYSO47 EOSS 2 AC 015 m SA C C Lt/St fut Ynt. 2e 3 E 135-4 3 4.3 VALVE TASLES - PAGE 31 d de e@EPTS2D790tXCELWA1273D7.XLS

BdOETMC. .W80 PROOMM PLAN CLASS 1,2. 3 AND AUOWNTED VALVES EMWWOOD NUCLEAR POWER STATION Revluten 7 VALVE VALVE VALVE VALVE ACT. NOlWAL STROKE TEST TEST fEUEP TECH.

NUMBER PSID CLASS CATEGORY SEE TYPE TYPE POefflON OWECT. WTHOD MODE fEOUEST NOTES POS, IERWWtt IBI.) (VfB - (val 1/2SAOS2 M 54-2 2 A 1.5 OL A.O. O C Lt fut VR 1 St OP 1 h 954 Pt OP 2 1/2SAOSS M 84-2 2 A 1.5 GL A.O. O C Lt fWt VM-1 St OP 1 k fut Pt OP 2 4.3 VALVE TAR.ES - PAGE 32 of 48 e:WEPTS'2D79GEXCELW127307)tLS

__ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _______.______._._.____m__._____.~._______..________.______.__._____.____._m.

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A A 4 A A 4 4 A S S 4 9 S 3 S S e & & 6 4 & 6 & &

t 4 4 4 4 4 4 4 4 4 S 6 4 S 6 S S P R I 0 8 A B A R S

EN V0 A 8 C 0 E F 6 H S L1 2 2 2 2 2 2 2 2 L NA T t e O 0 O 0 0 0 O 0 E AV A E s O D

0 O D D 0 0 D

0 D

O D

0 D

J.

MDU Vn L S 0

9 S 5 S S S 9 7

0 MTU Et A e 2

/

2

/

2

/

2

/

2

/

2 t

2

/

2

/

3 7

hN Vp 1 1 1 1 1 I 1 1 2

W tEO f

GR 1

W OG P L I UR E M AA E C

X 8eM 0

t

5. A U E

0 8

3, M 7 D

L 2, DO O7 U C 1 S MS Wn a US0i G A4e v n

Me I LRe SCOR 4 4j .

MSERYtt (MG MtOGRAM Pt.AN C3. ASS 1,2,3 AND AUGWNTED VALVE 3 BRMOWOOO NUCLEAR POWER CTATION Revimien ?

VALVE VALVE VALVE VALVE ACT. NOFMAL STROKE TEST TEST FEUEF TECH.

NUhEER PWD CLASS CATEGORY SEE TYPE TYPE PO8fTION DWECT. MTH00 MODE fEQUEST NOTES POS. FEM 4futs IINJ (VRI (VA) 1/2SD005A 448-5Al 2 A 0.375 OL A.O. O C St OP 1 Lt M 34 k M Ft OP 2 1/2S00058 E4GLBAt 2 A 0.375 OL A.O. O C St OP 1 Lt fut 34 h fut Pt OP 2 1/290005C 24GLBAt 2 A 0.375 OL A.O. O C 9t OP - 1 Lt M 34 h M R OP 2 1/2300050 4 46-5At 2 A 0.375 GL A.O. O C St OP 1 LA fut 34 R RR R W 2 19D054A E48-54 2 8 2.0 GL A.O. O C Ft CS VC4 St CS 1/2300548 448-5A 2 8 2.0 OL A.O. O C Ft CS VC4 2 48-58 St CS 190054C E48-5A 2 8 2.0 GL A.O. O C Ft CS VC4 St CS 1/250054D MSA 2 B 2.0 GL A.O. O C Ft CS VC-3 2 48-58 St CS 19D054E E4eL5A 2 8 2.0 Ot. A.O. O C Ft CS VC 3 St CS 1/2SD054F 448-5A 2 8 2.0 GL A.O. O C Ft CS VC4 E48-58 9t CS 190054G 448-5A 2 3 2.0 OL A.O. O C Ft CS VC 3 9t CS 1/2SD054H E48-5A 2 8 2.0 OL A.O. O C Ft CS VC4 2 48-58 St CS 4.3 VALVE TABLIS - PAGE 34 af 48 e:OEPTSW79GT.XCELW1273D7.XLS

. .u u i . mum _....m_~.._.m.__.._...m.m_.~__.-m.-_ - . - ...-..-.....~m.-.-u-. _ . _ . . . . . ...-_--..,_.-_~.s.m. s J

Be m fBIS PROGithM PLAN '

O. ASS 1 c.6 A88 AUShetTED VALVE 3 ERAmWOOD nut 12AR POWER CTATION RouWan 7

~t I

I vALvt vALvt VALvt vatvt ACT. N0feant STRoss TEST TEST fuuEP TECH. '

NUhWR Pts CLASS CATEGORY SEE TYPE- TYPE POEf11000 DWWCT. RETHOD SdDDE IEOUEST NOTES POS. IWh44fWts WLI Evf4 (val 1/2slee01A R&#1-2 2 5 4.0 SA M.O. C OfC et CS 13 1 061362 k f51 1/2W30013 E41-2 2 3 4.0 SA R O. C OfC m CS 13 1 E1342 R IWI .

1/2SIGOO2A ASS 14 2 3 4.0 GA. M.O. C OfC St CS 14 1 R&1363 -k 951 1/20100025 R&G14 2 3 4.0 GA M O. C OfC m CS .14 1 R&13SS k IWI 1/29138048 I441-1A 2 3- 3.0 GA. R O. C O St OP 1 -

R&t3St it IWI :

' i 1/2913808 R&#1 1A -2 9 S.0 GA K O. O C St OP 14 1 861361 k fut 1/2810007A E641-1A 2 B 5.0 SA M.O. C O St OP 1 5 130-1 It IWI i

, 1/20105079 e461 1 A 2 5 8.0 SA K O. C O St OP 1 Rd 130-1 It SWt 1/20158084 # 81 4 1 3 - 10.0 . 8A htO. O OfC k. CS VC-1 Y I R&t3SS It fut 1/23IOSON 06814 1 5 19.0 GA 94.0. O OfC k CS VC 1 1 R$1384 k IWt

, 1/2- R&#14 1 B 10.0 . GA M.O. - 0 OfC k CS - VC 1 1 I

__ E1368 k IWt i

~

1/2-m the14 1 B 10.0 GA' R O. O OfC St - CS VC 1 1 B61384 m IWL '

1/2W000e4 h&GI-4 2- 3 3.0 SA RAO. O OfC St CS . 14 1 E1364 k IWI i 1

1/2- h641-4 2 3 S.0 GA - K O. O- OfC - St CS 14 1 b61364 t 151 1/2WIge11 A R441-4 -2 S .- 24.0 84- K O. OfC St IWt . vfl.19 C .- 1 h61364 It 'IWt '!

1/2sise11e n&st-4 2- e 24.0 eA aAO. -c OfC a fut . vfne 1~

06138-4 It 158 1/2013812A R401-4 2 8 12.0 SA M.O. .O C M. tr 1

? RS1864 m IWI 4.3 VALvt TAMES.PAM 35 af 4e i

9

'}

,4 e:tIEPTS'2D79EMEXML941273D7JELS i

1

'I t

. . _ . . . .____m _ _ _ _ . _____________m_.__ - - -- - r

INSEfWI. .TWG PROGmM PLAN '

Ct. ASS 1. 2,3 AND AUGIENTE@ VALVES '!

BRAERYOOD NUCE. EAR POWER STOTION ~f

Revimien 7 i

i VALVE VALVE VALVE VALVE ACT. 900f344 STROKE TEST TEST fERRF TEC94.

NUhWER PGdD CLASS CATEGORY SEE TYPE TYPE PoemON DgECT. GETHOD MODE SEGUEST SeOTES POS. fERAMute 1889 (Wit ~ (WAp 1/2918e129 M41-4 2 5 12.0 GA M.G. .O .c St CP 1 E138-4 It fut 1/2910813 E41 19 2 5 2.0 GL' K O. O C St CS - 14 1 E1361 a fut 1/2918914 RS41-1A 2 B 1.5 'IL K O. .O' C St OP - 1 E130-1 It fut I

4.3 VALVE TAKES - PAM 3e et 4e -

t i

4 6

e:WEPTS2D790iEXCEL941273D7.XLS s

1

- _ _ . _ _ . _ _ _. - m. _ - . _ _ _ _ - _ . _ _ _ _ _ . _ _ _ _ _ _ . _ . _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _ _ _

_ __.u _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ ____ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . - _ _ . _ _ _ _ _ _ _ - _ _ . _

~

SIGEIMC iStG PROGRAM PLAN ,

QASS 8,2,3 AfC AUGWNTED VALVES ;

WIMNWOOD NUCLEAR POWER STATION Revimien 7 i

VALVE VALVE VALVE VALVE ACT. foofMht STROKE TEST TEST IELEF TECH.

pammt peg mags CATEGORY SEE TYPE TYPE POSITION DUECT. IETHOD 1AODE SEQUEST NOTES POS. IEMMutS WO IVID IVAl i 1/2910815 E812 1 AC 3.0 m SA C O Ce fWt VIIISA 3 L E1362 C LtfBt IWI VI415A S 3 1/25100104 e6414 1 AC S.O m SA C O CtJ8t CS S 3 R&1364 C La IWI e, 23 3 1/2910810B R&e14 1 AC S.O M SA C O Coat CS S 3 R&1364 C Lt IWI S, 23 3 I 1/2910010C RSS14 1 AC - 8.0 m SA C O Ctat CS S 3 041364 C Lt fut 9, 23 3 1/251501ED to.414 1 AC G.0 m SA C O Ct/St CS- 3 3 RS1384 C Lt IWt e, 23 3 1/28108154 h&e14 1 AC 2.0 m SA C 0 LtdSt fWI VR 15C . S. 23 3 R&t363 C Ct IWI VI415C 3 1/28188195 RSS14 1 AC 2.0 .m SA C O Lt/St ful Vf41SC 8,23 3 R&t304 C Ct fut VI415C 3 1/251051SC E414 1 AC 2.0 m SA C O LtSt IWI Vft15C 8, 23 3 RS1363 C Ct IWI VU415C 3 1/2018819D 16814 1 AC 2.0 m SA C O Ltet fWt . Vf415C 9, 23 3 RS1304 C Ct IWt Vf415C 3 1/2SISO21A R&e14 2 3 4.0 GA M.O. .O. ClO - St OP 1 B61363 k fWt 1/20108218 R4414 2 3 4.0 GA M.O. O CfD St OP 1 '!

RS1304 k 954 1/255838 RSS?4 2 3 4.0 GA M.O. O CJO St CS 14 1 R&1963 h IWt 1/2918940 h&e14 2- 5 12.0 GA M.O. .C CJU St CS 14 1 ;

he.1363 h fut i 1/2Sege41A h4614 1 AC S.O M SA .C C- Lt 554 0 3 R&1363 O CtJBt 851 VII ISO 3 1/29100618 as.414 1 AC- 3.0 m SA C C Lt fut S 3 061363 O Ctet IWt VI41m 's l 4.3 VALVE TAM.SS - PAM 37 et 4e e:1DEPTSSD790EXCELiM127307.XLS i

_ - . _ . . _ .__ _ . _ _ _ _ _ _ . _ _ _ _ __________________ _ _ ____m _ _. . _ - . . . . ~ , .

u m . u~.. ..-,....#__ a--- ._mam--_-...m...----m.~,....m.._m - m.m...-__m_m.- -~m,___,_.___,m.

1 CLASS 1,2.3 AfD AUGWN1tD VALVES +

SftlleM000 NUCLEAR POWWER STATION Revlulen 7 e

i i

I

. VALVE VALVE VALVE VALVE 4CT. NOIRAAL STROKE TEST TEST fELEP TEOt. .!

pamasst Pee CLASS CATE00ftY - EEEE TYPE TYPE P0effl0N DWECT. RETHOD R400E fEOUEST NOTES POS. IERGMUt3

ON ) -(Vf4 qvAl 1/2else71 R4812 2 A 0.75 OL A.O. C C St OP 1 b61388 Lt 154 M1 k fWt +

Pt OP 2

, 112eISOOD h&St.S 2 A 1.0 GL A.O. C- C St OP 1 !

RS130'S ' Lt IWI M1

. R fut N W 2 ;

1/2elegge RSS14 2 A O.75 GL A.O. C C St OP - 1 !

h41384 Lt IWI M1

, k fut

i Pt -' OP 2 1/2- R441-2 1 AC 1.5 cit S.A. C f Ct - IWt M15A 3 E13ew2 .. , LeSt Ist VII 15A 6 3 1/20I00003 h681-2 1 AC 1.5 cit SA C 0 Ce _ fWL- M15A 3 .

RS130 2 C LaSt IWI VIt-19A 8 3 titelesseC R4812 1 AC 1.5 CK SA C 0 Ct IWI Vft19A 3 i RS18862 C LaSt IWt MitA 8 3 l Itteammann h441-2 1 AC 1.5 CK SA- C 0 Ce fWt M15A 3 (

B613052 C Lhmt IWI MISA 8 3 1/2eSeesA hsSt.3 SA 1 AC 2.o CK C 0 Ce fWt mieC 3 I' RS1884 C LtSt IWI M 19C S 3 IttelegeOS R4814 1 AC 2.0 CK - SA C O Ct IWt M15C 3 .

RS1384 C LASt ' IWI M15C S 3 !

1N h6414 1 AC 2E CK SA C O' Ct IWt VEISC 3 i R&1884 C Lhet WWI VE19C 8 3' 4 ittenmanen es414 1 AC 2.0 CK - SA C 0 Ct WWI VIb19C 3 R41384 C- Last IWt - VII 15C S- 3 I

titeleSith RS41-1A 2 C 1.5 CK SA . .C- O Ce. OP: 3 h6138-1 C St OP 31 3 Ittelsetes RSS1-1% 2 C 1.8 CK S.A. O O Ct OP 3- ?

R41381 C et OP 31 3

. 4.3 VALVE TARES.PAM as of 48 -

4 e: WEPT 9GD79GiEXCEL94127307.NLS l

. . _ - . .. __m . , _ - ........m.._ ..._m ...m_.m.. . ._ . .m.

,m.. _ _ _ - . . . .m . . . .- .m._ _ . _ _ . _ __ . ....m... .

i INSEfMCL .DeG PROOMM PLAN CLASS 1,2,3 AND AUORENTED VALVES l BfuiDWOOD NUCLEAR POWER STATION Rentalen 7 l

l l

[ VALVE VALVE WALVE VALVE ACT. N0fMAL STROKE TEST TEST fEREF TEOt.

l NURSER PSID CLASS CATEGORY 42E 1YPE TYPE POSITION DWECT. IETHOO MODE PEOUEST NOTES POS. fEnWUUCS i pNJ (Vf5 (VA) 1/2918920 Eel-1A 2 8 1.5 OL M.O. O C St OP 1 l

E 138-1 It fut l

1/518922A E01-1A 2 C 4.0 m SA C O Ct IWt VE3 3 fut VES 3 06138-1 C Be 1/29199228 Eel-1A 2 C 4.0 m SA C O Ct FUt VR4 3 84130-1 C Bt ful VES 3 1/2910024 tSel-1A 2 5 0.0 GA M.O. O C/O St OP ,

1 e41361 It IWt 1/2918926 R&gt.1A 2 C 3.0 m SA C O Xt OP VE6 25 3 e6138-1 Ct M 1/29189484 E614 1 AC 10.0 m SA C C Lt fWt VR4 e. 23 3 Xt/St - CS VE5 3 E1384 O Ce fut VE5 3 1/291384e8 84614 1 AC 10.0 CK SA C C Lt M VE5 8.23 3 Xt/St CS VE5 3 R&1365 O Ct fWt VR-5 3 1/291804ec R461-6 1 AC 10.0 m SA C C Lt fut VE6 e,23 3

' Xt/St CS VE5 3 i 06138-8 O Ct IWI VE5 3 1/29189480 4 61-0 1 AC 10.0 m SA C C Lt fWt VES 9. 23 , 3 Xt/8t CS VE6 3 R&t3Se O Ce fut VR4 3 1/20159494 34414 1 g AC 5.0 m SA C . C Lt fWt a 3 861363 I O CV3e fut Vit-1SO 3 1/2sloo4eo R&et4 1 AC e.0 m SA C C Ltat fut VE15C e 3 841384 O Ct 954 VE15C 3 1/2SIOD49C R&e14 1 AC e.0 - CK SA C C Lt fWI 8 3 R41363 O Cette 554 VR 150 3 1/29159480 R&#14 1 AC S.0 m SA C C Lt/Bt Mt VE15C S 3 E1384 0 ' Ce 994 VE15C 3 1/2m R&#14 1 AC 10.0 CK SA C C Lt/St fut VE5 8 3 841365 O Ce fut Vfts 3 1/25185555 04614 1 AC 10.0 CK SA C C Ltigt fWt VE5 0 3 861384 O Ct 954 VE5 3 1/2810880C 04014 1 AC 10.0 CK SA C C Lt/Bt - 75l Vft-5 3 3 e61368 O Ce fUt VUt4 3 4.3 VALVE TAM.ES - PAGE 39 et de e:WEPTSSD79GiEXCEL1M127307.XLS

_ _ . _ _ - - - _ _ - _ . _ - . - - _ . _ _ = _ _ _ _ _ - _ _ - - _ - _ . . _ _ _ _ _ _ _ - - - _ _ - - . - . . -. . . . . - . . - --

b l N (WIG PROGRAM M.AN

, CLASS 1. 2. 3 AND AUOMENTED VALVED

( ORASWOOD NUCLEAR POWER STATION Pow 4 mien 7 VALVE VALVE VALVE VALVE ACT. N0fMAL STROKE TEST TEST fELEF TECH.

NURSER PSD CtASS CATEGORY SIZE TWE TYPE Poem 0N DEECT. SETH00 MODE fEOUEST NOTES POS. FEMMULS SN.) (Vf8 (val 1/29sse50D E61-8 1 AC 10.0 m SA C C Ltet M MS 8 3 E136-8 O Ce fut VE5 3 1/28105584 Kel-4 2 C 12.0 m SA C O Ct CS S 3 E1364 C' St OP 27 3 1/28105588 E61-4 2 C 12.0 m SA C O Ct CS S 3 E1364 C St OP 27 3 1/2810004 E81-8 2 A 0.75 OL A.O. 'C C St OP -1 E13&S Lt M M1 It M Pt OP 2 1/2818888 4 01-8 ,2 . AC 1.0 M SA C C , Lt M VN1 PASONE E138 4 4.3 VALVE TAM.ES -PAGE 40 of 46 '

ENS \ZD79GEXCELW127307.XLS

s m . a . .-.m m . , .um _ .m _m_ . . m .m___m __ . m m . _ . __mu-,__---_.m.---.m . ~ m.m INSEmA f988 PR00ftARA MAN QASS 1. 2,3 Afe CUGRE9ff2D VALVES BRAON000 NUCLEAR POWER STQTION ItseWan 7 VALVE VALVE VALVE WALVE ACT. N0f3Ahl STROKE TEST TEST IEUEF NOTES TECH. fESShfuts M4 PSG QASS CATEOORY SEE TVPE TYPE Poeffloh OWECT. RETHOD RRODE IEOUEST POS.

Wij IVI4 IVAi OSM007 R&42 2A 3 3 30.0 STF R O. C O St' OP 1 i " E i OSX148 RS42 2A 3 8 30.0 STF M O. C O St OP 1 4 h IWI OSX147 R442 2A 3 9 20.0 STF R4.0. C O St OP- 1 h IWI 1/2SMOS2A AS4218 3' C 38.0 m SA C O- Ct OP 3 C St OP 3 i 1/2SM002S R4421 A 3 C 30.0 m SA C O Ct CP 3 C St OP 3 It2SMOOS RS421A 3 8 30.0 BTF RAO. C' O St OP 1 R IWt 1/28M0194 RS42 OS 2 3 10.0 BTF M O. O Om St OP 1 RS1204 k IWI 1/2SM015 R442-SA 2 0 10.0 BTF RA.O. O em. St OP 1 R$12S3 k 151 1/28MD27A B64245 2 8 18.0 STF Rd.O. O OfC ' St : OP 1 R$12S3 # SWI 1/2SM0275 R4424A 2 5 16.0 STF H O. O Om St W- 1.

R* 1293 h IWI i 1/2SK101A R4424 3 8 1.5 el S.O. C C St OP S R41261 0 Pt CP 2, S l 1/2SX112A B6424 3 5 12.0 STF A.O. O C St OP 1 R$12S1 R OWt M GP 2 1/2SR1123 B6424 3 3 12.0 STF A.O. O C St OP 1 RS1241 h IWt M W 2 1/2SK114A Rs424 .3 5 12.0 BTF A.O. O C ' St OP- 1 RS12S1 h fWt M- OP 2 1/2SK1948 R$424 3 9 . 12.0 STF A.O. O C St : OP 1 l RS12S1 R 554 M W 2 j 1/28K1194 R442-28 3 C 3.0 M SA O O Ct OP 3 R442-25 1128M115 R442-29 3 C- 3.0 m SA O- O Ct : OP - 3 R442-25 4.3 VALVE TAGLES . PAGE 41 of 40 e-13EPTSGD790EXCELO4127307.XLS

+

4

.- _ _ _ . . . _ _ . _ . . _ , _ _ _ _ _ _ _ . _ . . _ . _ . . - . . . . . _ . - _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . _ -____ _ __ __ _ _ _ _,w. _ _ _ _ _ _ _ . . _ _ _ _ _ __

1 i

r g

, ll[ . = - . . .. . -a h s

. I e i E- g l=it i

~

ll t a sea tst et e et ll r e s-e n-m ar a se gg . . . . . . .

ll 1 1 . . . . .

si s s s s s 3 s ji e e a e a s s lEi ! ! ! ! : : :

ll5 s

y e a n e n n a 25 25 25 25 25 25 25

. I Is is is is Is is is w <

gWg < 3 e

. E E E 4

h h

1<[ 3 d

!!.[ l lid !

NBERVICL .ING PROGl%M PLAN CLASS 1,2. 3 AND AUORENTED VALVES BRMDWOOD NUCLEAR POWEft LTATION Revimien 7 VALVE VALVE VALVE VALVE ACT. NOf9AAL STROKE TEST TEST fELEF NOTES TECH. IEMMstS NURSER PGO CLASS CATEGORY SIZE TYPE TYPE PoemON DUECT. RETHOD MODE IEOUEST POS.

SN.) (Vf4 (VA) 1/2V0001A E105-1 2 A 40.0 STF H.O. C C Lt S Vf41 11 M-106-1 St CS ' 11 1 It fut If2VOOO18 E105-1 2 A 48.0 STF H.O. C C Lt S M1 11 E1001 St CS 11 1 It IWL 1/2VOOO2A E105-1 2 A 48.0 BTF H.O. C C Lt S Vf41 11 1 410e 1 St CS 11 It M 1/2VOOO29 E105-1 2 A 48.0 BTF H.O. C C Lt S Mt 11 1 E108-1 St CS 11 It 9W4 1/2v0003 E105-1 2 A 8.0 BTF A.O. C C Lt f54 Vf41 11 E100-1 St OP 1 at IUt 1/2VQOO4A E1051 2 A S.O BTF A.O. C C La fWt Vft-1 11 E100-1 St OP 1 h put 1/2VOOO48 E105-1 2 A S.0 81F A.O. C C Lt ful Vf41 11 E100-1 St OP 1 It WWI 1/2VO005A E105-1 2 A S.O STF A 0. C C Lt fut V!41 11 E1001 9t OP 1 It fWI 1/2VOOO58 E1051 2 A S.O BTF A.O. C C Lt PWI Vf41 11 E100-1 at or 1 It fut 1/2VOOOSC E105-1 2 A S.O OTF A.O. C C Lt 954 Vft-1 11 E1081 St OP 1 It fut 4.3 VALVE TAaLES -PAGE 43 of 46 e:WEPTSUD790EXGLW1127307.XLS

WISEIML .386 PROGMM PLAN QASS 1. 2. 4 AfD AUGRENTED VALVE 3 .

BMWWOOD NUCLEAR POWWt ETATION 'f RevMen 7 l

I I

l i

l f

i VALVE VALVE VALVE VALVE ACT. 900lMht STRostE TEST TEST f4tMF NOTES TECH. IEMMELS BeuteER Pee class CATEGORY SEE. -TYPE TYPE PoeITION DEECT. RETHOD MODE. fEOUEST POS. ~

WJ (VfD fv4 '

1/2VOO19 E195-3 2 A 0.5 GL M C C . Lt fWt M1 PASONE 1/2VOO17 E105-3 2 A 0.5 el M C C Lt fWt WR 1 PASWWE 1/2VOO18 E1054 2 A 0.5 GL M C. C Lt - fWt M1 PAseIVE .- !

j 1/2VOO18 R&1054 2 A 05 GL M C C- Lt fUt M1 PeggNE 4.3 VALVE TABLES .PAM 44 et 46 i

1 e:MSSD790EXCELW1273D7.NLS

-_ m_.___.___ _ _ _ _ _.mm___. _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _. ____

seEfMC. ive0 PROGRAM PLAN CLASS 1,2,3 AND AUGhENTED VALVES ORAEM000 NUCLEAR POWER CTATION RowWen 7 i VALVE VALVE VALVE VALVE ACT. N0fMAL STROKE TEST TEST fELEF NOTES TEOt. FEMMets NURSER *SfD QASS CATEGORY SIZE TYPE TYPE P00lTION DNECT. RETH00 MODE IWOUEST POS.

TIN $ (V4 (VAp 1/2WM190 to-4StA 2 A 2.0 OL M C C La m M1 PAserVE M4418 t/2WM191 M491A 2 AC 2.0 cit SA. C C Lt fut M1 PASSIVE M4&tB 4.3 VALVE TAGLES -PAGE 45 of 40 i

e:N7931EXCELW127307.XLS

INSERV L .IW80 PROGRAM PLAN CLASS 1. 2. 3 AND AUGnENTED VALVES BRAIDWOOD NUCLIAR POWER STATION Revealen 7 VALVE VALVE VALVE VALVE ACT. NOfMAL STROKE TEST TEST fELEF NOTES TEOt. fEMMuts NURSER PSID CLASS CATEGORY SIZE TYPE TYPE PO9 TION DWECT. RETHOD MODE fEOUEST POS.

IIN.) (Vgg (VA)

OWOOO2A E118-1 3 C 9.0 m SA O Ct OP 3 OWOOO28 E118-1 3 C G.0 m S.A. O Ct OP 3 1/2WOOOSA 9t OP 1 4 119-5 2 A 10.0 GA M.O. O C Lt fut VR1 E118 7 k fr a

1/2WOOO68 St OP- 1 E118-5 2 A 10.0 GA M.O. O C Lt f54 VM1 E118 7 k fut 1/2WOOO7A E110-5 2 AC 10.0 m S.A. C C Lt!Bt fut VR 1.27 3 E118 7 1/2WOOO75 # 115-5 2 AC 10.0 m S.A. C C List f44 VR 1.27 3 E 110-7 1/2 WOO 20A St OP 1 41184 2 A 10.0 GA 94 0. O C Lt fUt . VE1~

118 7 k FUt 1/2 WOO 208 9t OP 1 4 118-5 2 A 10.0 GA M.O. O C Lt fut VE1' E118 7 k put 1/2WOOSGA St OP 1 E1184 2 A 10.0 OA M.O. O C Lt fut VIt-1 E 119-7 k fWt 1/2WOOSW St OP 1

118 5 2 A 10.0 GA M.O. O C Lt fWt VE1 M 118 7 k 754 4.3 VALVE TABLES Pues 4e of 49 e:WEPTS2D79GEXCELW127307.XLS

INSERVICE TESTING PROGRAM PLAN FOR VALVES.

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 I

I

'l 1

l l

l EBCTION 4.4 VALVE NOTES t

i l

i

)

l I

! I i

l l

(03/14/95) c:\DEPTS\ZD79G\217.wpf/37

INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 i Revision 7 '

VALVE NOTES NOTE 1 Clocure of the Main Steam isolation valves 1MS001A-D or 2MS001A-D during unit operation i would result in reactor trip and safety injection actuation. To avoid this transient, l the::o valves will be partially stroked every three months. Full stroke testing will be !

don 3 during Modes 4, 5, or 6 as plant conditions allow, per IWV-3412.

NorE 2 The testing of any emergency boration flowpath valves during unit operation is not practical. Stroke testing the Boric Acid injection isolation valve 1CV8104/2CV8104 and i check valve ICV 8442/2CV8442, the RH to CV pung suction isolation valve 1CV8804A/2CV8804A, cr the RWST to CV pump suction isolation valves 1CV112D,E/2CV112D,E, could result in borction of the RCS, resulting in a cooldown transient. Aligning the system in this configuration even for a short duration is, therefore, unacceptable. These valves will be ;

ctroke tested during cold shutdown, in accordance with IWV-3412. ;

NorE 3 j l

Th3Co valves are the Main Feedwater isolation valves: 1FWOO9A-D/2FWOO9A-D, and cannot be j fully stroked during operation as feedwater would be terminated causing a reactor trip. ,

They will, however, be partially stroke tested during operation as well as full stroke i tGcttd during cold shutdown, per the requirements of IWV-3412. !

NOTE 4 Clo;ure of these letdown and makeup valves 1CV1128,C/2CV112B,C, ICV 8105/

"V8105, ICV 8106/2CV8106, ICV 8152/2CV8152, and ICV 8160/2CV8160 during normal unit geration would cause a loss of charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactor trip. These valves will be full ,

ctroke/ fail safe exercised during cold shutdown as required by IWV-3412. I NorE 5 .

Th3 1RH8701A/B, 1RH8702A/B, 2RH8701A/B, and 2RH8702A/B valves are the isolation boundary l between the Residual Heat Removal Pumps and the Reactor Coolant System. Opening one of I

thsco valves during unit operation will leave only one valve isolating RHR from the high l RCS pressure. This would place the plant in an undesirable condition. Therefore, these l valves will be full stroke tested during cold shutdown, per IWV-3522.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 EZIX E The following valves have been identified as intersystem IDCA valves. They form a precoure M = h7 between the RCS and other essential components in order to protect these ,

components from damage. These valves will be leak tested in accordance with the Braidwood Technical Specifications. Performance of the leak test on these valves also satisfies the back-flow test required for check valves by NRC Generic Letter 89-04.

Intersystem IDCA Valves 1RH8701A/B 1RH8702A/B 2RH8701A/B 2RH8702A/B 1RH8705A/B* 18I8815 2RH8705A/B+ 2SI8815 ISIS 818A-D ISIS 905A-D 2SI8818A-D 2SIO905A-D 1 SIS 819A-D ISIS 94SA-D 2SISS19A-D .28I894SA-D 1SI4841A/B ISIS 949A-D 2SI8841A/B 2SI8949A-D ISI8900A-D ISIS 956A-D 2 SIS 900A-D 2SI8956A-D

Not true pressure isolation valves - not listed in Tech Specs.

NOTE 7 The Reactor Pressure Vessel Vent Valves 1RC014A-D and 2RC014A-D cannot be stroked during unit operation, as they provide a pressure M = h7 between the Reactor Coolant system and containment atmosphere. Failure of one of these valves in the open position would result in leaving only one valve as the high pre'<.*,'.e M_m h v. These valves will be full ctroke/ fail safe exercised when the RCS g tenura is at a minimum during cold shutdown, per IWV-3412.

bDL%

no Residual Heat Removal Pump discharge chccir a vos 1RH8730A/B and 2RH8730A/B cannot be full stroke exercised during unit operation s%7 G the high RCS pressure. These check valves will be partial stroke tested, however, to quarterly basis and full stroke ,

cxercised during cold shutdown. This is in ac~o, tace v'ch INV-3522. 6 NOTE 9 i

, Due to the RCS pressure, the check valves listed hilow cannot be ful'. stroke exercised l during unit operation:

ISI8958A/B 2SI8958A/B RWST to RHR Pump Suction These valves will be full stroke exercised during cold shutdown, in accordance with IWV-3522.

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J INSERVICE TESTING PROGRAM PIAN FOR VALVES j ERAIDWOOD STATION UNITS 1 AND 2 i Revision 7 s

i NOTE 10 j Th3 1FWO39A-D and 2FWO39A-D valves cannot be stroke tested during unit operation as cloI;ure of these valves would result in termination of the waterhasumer prevention j

fccdwater flow. This would result in undesirable affects on the Steam Generators. These j vslves will be full stroke / fail safe tested during cold shutdown, per INV-3412.

j NOTE 11 j Th3 Primary Containment Purge Supply and Exhaust Valves IVQ001A/B, IVQ002A/B, 2VQ001A/B,

. and 2VQ002A/B cannot be stroke timed during unit operation. These 48-inch valves are the i only isolation points between the containment atmosphere and the environment. Stroking 4

th re valves at any time other than mode 5 or 6 would be a violation of the Braidwood j Technical Specifications. These valves will be full stroke tested during cold shutdown,

in accordance with IWV-3412. These valves will be leak tested semiannually, in accordance trith Braidwood Station Technical Specifications.

j The Primary Containment Mini-Purge and Exhaust Valves 1VQ004A/B, 2")005A/B/C, 2VQ004A/B, and 2VQ005A//B/C, and the Post ICCA Purge Exhaust Valves IVQ003/ 2VQ003 will be leak tested every 3 months, in accordance with Braidwood Station Technical Specifications.

1 1 NOTE 12 j The Auxiliary Feedwater check valves 1AF001A/B, 1AF003A/B, 1AF014A-H, 1AF029A/B, j 2AF001A/B, 2AF003A/B, 2AF014A-H, and 2AF029A/B cannot be full stroke tested during unit j operation, as this would induce potentially damaging thermal stresses in the upper fordwater nossle piping. The 1AF001A/B, 1AF003A/B, 2AF001A/B, and 2AF003A/B valves will j be partially stroke tested during operation, and all valves full stroke tested during cold j ghutdown. This will be performed per Tech Spec 4.7.1.2.2 and is in accordance with

TV-3522.

1 j NOTE 13 l Th3 High Head Injection Isolation Valves 1SI8801A/B and 2SI8801A/B cannot be stroke tested i during unit operation. These valves isolate the CV system from the RCS. Opening them 3

during operation would enable charging flow to pass directly into the RCS, bypassing the

rag nerative heat exchanger. The temperature difference of the charging flow and the RCS 4 could result in damaging thermal stresses to the cold leg nossles as well as cause a l reactivity change which would, in turn, cause a plant transient. These valves will be

{ full stroke tested during cold shutdown in accordance with IWV-3412.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNIT 3 1 AND 2 Revision 7 NOTE 14 The safety injection system SVAG (Spurious Vkive Actuation Group) valves 1SI8802A/B, ISIS 806, ISI8809A/B, 1SI8813, 1SI8835, 1SI8840, 2SI8802A/B, 2SI8806, 2 SIS 809A/B, 2SI8813, 2SI8835, and 2SI8840 cannot be stroke tested during unit operation. nose valves are r: quired by the Technical Specifications to be de-energised in their proper positions during unit operation. Stroking them would be a violation of the Technical Specifications ,

co well as defeating the de-energised SVAG valve principle. These valves will be stroke tccted during cold shutdown when they are not required to be de-energized. This is in cccordi.nce with IW-3412.

NOTE 15

-DELETED-p 16 There feedwater valves are exaspt from all ASME Section XI testing requirements per IW-1100 and IW-1200. They are included in the program for operability tracking purposes only. The closure of the Main Feedwater Regulating Valves 1FW510, 1FW520, 1FW530, 1FW540, 2FW510, 2FW520, 2FW530, and 2FW540 during unit operation would cause a loss of feedwater to the steam generators, resulting in a plant transient with a possible reactor trip as a r3 cult. These valves will be fall safe (Pt) tested pursuant to the Braidwood Station Technical Specifications. '

NOTE 17 here feedwater valves are exempt from all ASME Section XI testing requirements per IW-1100 and IW-1200. They are included in the program for operability tracking purposes sly. The closure of the Main Feedwater Regulating Bypass Valves 1FW510A, 1FW520A,

/W530A, 1FW540A, 2FW510A, 2FW520A, 2FW530A, and 2FW540A during unit operation would rcquire the Main Feedwater Regulating Valves to correct for bypassed flow and could result in a plant transient with a possible reactor trip as a result. These valves will be fail cafe (Pt) tested pursuant to the Braidwood Station Technical Specifications.

NOTE 18 l

-DELETED-(Incorporated into NOTE 21)

NOTE 19

-DELETED-(Incorporated into NOTE 14) l I

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.l INSERVICE TESTING PROGRAM PLAN FOR VALVES.

! ERAIDWOOD STATION UNITS 1 AND 2 l Revision'7 j

! 1

NOTE 20 I i

he remote position indicator for these valves cannot be observed directly due to the i

encapsulated design of the solenoid valve body. During the indication test, indirect cvidence of the necessary valve disk movement shall be used, in accordance with IWV-3412 )

(b). The valves affacted are listed below

1CV8114 1PS230A/B 2PS228A/B. l

. 1CV8116 1RC014A-D. 2PS229A/B .

1 1PS228A/B .2CV8114 2PS230A/B l

1PS229A/B 2CV8126 2RC014A-D '

f EDTI 21 t

i The Main Feedwater. Tempering Flow Isolation Valves 1/2FNO34A-D are exempt from'all ASME j

! S ction XI testing requirements per IWV-1100.'and IWV-1200. Sey are included in'the :

l program for operability tracking purposes only, and will .be1 fail safe (Ft) .- tested pursuant 4 to the Braidwood Station Technical Specifications.

l MDTE 22 'l i

j -Per NRC request, the post-accident. hydrogen monitoring system check. valves 1/2PS231A and '

1/2PS231B will be stroke exercised open on a quarterly frequency to verify operability. j f EDTE 23 1

j 1/2SI8818A-D, 1/2 SIS 819A-D, and 1/2 SIS 948A/B are Event V check valves, which are defined

as'two check valves in series at a low pressurn/RCS-interface whose failure may result in

a LOCA that bypasses containment. Soy are individually leak-tested in accordance with j i "dC generic letter 89-04, position #4b.

} ~

j EDTI 24 1/2CC9518, 1/2CC9534, 1/2CV8113, and 1RM8705A/B are check valves designed to relieve l proccure between two containment isolation valves. The full flow limiting value is sero, i cince the safety function of these valves in the open direction is to relieve pressure l only.

1 EDTI 25 l

! Ch ck valve 1/2818926 prevents flow from the Safety Injection (SI) pump suction line to i the Refueling Water Storage Tank (RWST). The SI pumps are normally lined up in the

!. INJECTION MODE to take suction frcm the RWST. This check valve would stop reverse flow i when the SI pumps are transferred to NOT/COID LEG RECIRCULATION-MODE to prevent i contamination of the RWST. However, the 1/28I8806 M.O.V. is in series with this check j v:.lve and would be closed to prevent reverse flow as directed by the emergency procedures.

{ Therefore, no backflow test (Bt) is required for 1/28I0926.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES.

CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 NOTE 26 Check valve 1/2CV8546 prevents flow frosi the Cheatical and Voltane Control (CV) pump suction line to the Refueling Water Storage Tank (RWST) . The CV pumps are normally lined up in the INJECTION BODE to take suction frosi the RWST. This check valve would stop reverse flow when the CV pumps are transferred to NOT/ COLD LEG INJECTION MODE to prevent contamination of the RWST. However, the 1/2CV112D and 1/2CV112E M.O.V.'s-are in series with this check valve and would be closed to prevent reverse flow as' directed by the.

emergency procedures. Therefore, no back flow test (Bt) is required for 1/2CV8546.

MOTE 27 l Check valves 1/2 SIS 958A/B prevent flow from the Residual Heat (RH) Removal pump suction line to the Refueling Water Storage Tank (RWST) . The RH pumps are normally lined up in the INJECTION MODE to take suction from the RWST. These check valves would stop reverse flow when the RH pumps are transferred to NOT/ COLD-LEG RECIRCUIATION MODE to prevent contamination of the RWST. The 1/2SI8812A/B M.O.V.'s are in series with these check valves and would be closed to prevent reverse flow as directed by the emergency '

procedures. In addition, the RH suction valves 1/2SI8812A/B, 1/2RH8701A/B or 1/2RH8702A/B, and 1/2SISS11A/B are electrically interlocked to prevent the backflow to.the RWST when the RH system is in a RECIRCUIATION MODE. However, during the injection mode if-a pump fails to start, these valves are relied upon to prevent diversionary flow back to the RWST.

EDFE 28 The 1/2CV8440 check valves allow seal water return.to the suction-of the CV pumps. During the hot leg recirculation phase of an SI, the VCT outlet check valve prevents diversionary flow back to VCT via the seal water heat exchanger relief valve, which could potentially nd to an unfiltered release of radioactivity to the environment. These valves can only A tasted in cold shutdown, when all 4 RCPs and charging pump are off. Refer to CHRON

0117821 dated November 23, 1992.

NOTE 29 Check valve 1/2CV8442 prevents- flow from the Cheatical and Volume Control (CV) pump suction herder to the boric acid transfer pump. This line is normally isolated by the 1/2CV8104 l emergency boration valve. This valve would only be opened during an emergency with the boric acid transfer pump running. This check valve is unnecessary with the current system l oper: tion, and thus, no back flow testing of 1/2CV8442 is required.

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1 INSERVICE TESTING PROGRAM PLAN FOR VALVES 8

ZRAIDWOOD STATION UNITS 1 AND 2 i Revision 7 4

f NOTE 30 l Check valves 1/2AF014A-H are verified to be closed each shift by the Operating Department,

, by verifying that the temperature at 1/2AF005A-H is s 130' F. If the temperature is >

l 130' F at any 1/2AF005 valve, then an abnormal operating procedure is entered to isolate and cool down the affected lines. This shiftly monitoring of 1/2AF014A-H in the closed position adequately monitors the status of these valves during unit operation. However, et the NRC's request, the official IST backflow test will be performed following the full !

flow test during cold shutdowns. (NRC Inspection Report dated June 8, 1993, paragraph 2.c. (2))

NOTE 31 i Ch:ck valves 1/2CV8480A/B and 1/2SI8919A/B are the Centrifugal Charging Pump and Safety

, Injection Pump mini-flow recirculation line valves which open to allow recirculation flow

! during IST Surveillances. Acceptable full-stroke will be verified whenever the recorded q mini-recirculation flowrate is within the " acceptable" or " alert" ranges given in the IST Pump Surveillance.

NOTE 32 Deleted - Byron demonstrated quarterly testing did not adversely affect the low flow 81&rms and RCP seal flow.

NOTE 33

Used at Byron Station ONLY*

NOTE 34

.er Braidwood Technical Specifications Amendment, valves 1/2SD002A-H, 1/2SD005A-D have besn removed from the list of valves to be tested under 10CFR50 Appendix J and will now be tested per ASME Code Section XI, INV-3420.

NOTE 35 Tha 1/2RH8705A/B check valves will be operability tested by verifying that there is depressurization in line 1/2RH26AA-3/4 and 1/2RH26AB-3/4 when they are opened. This is a tost method which was approved by the NRC in Byron's SER dated 9/14/90.

NOTE 36 In response to GL 90-06, "PORV and Block Valve Reliability and Additional L10P for LWRs,"

ths 1(2)RY455A and 1(2)RY456 valves will be restricted from stroke testing in Mode 1.

T chnical Specifications will provide direction for any further operability testing rcquired.

(Raference NTS Item - 456-130-90-4.4-0100)

NOTE 37 Tha 1/2RH8716A/B "RHR Cross Tie" valves are out-of-service open per Technical Specifications and can only be exercised during cold shutdown or refuel.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES KRAIDWOOD STATION UNITS 1 AND 2 Revision 7 NOTE 38 There are the feedwater tempering flow check valves and are open during full /high power operation to ensure the S/G upper nozzle subcooled margin is maintained above the 75 *F ainimum. They also open to allow tempering flow during shutdown and startup. 'Ihe close to provide an immediate isolation function during a feedwater line break accident to mitigate a loss of secondary make-up and/or inventory.

Th:7 are 3 inch swing type check valves with no position indication. Flow through this lina at full /high power cannot be stopped for longer than one minute while in Mode 1.

Alco, flow / pressure is always toward the Steam Generators (S/Gs) during operation, making ,

it impractical to perform a back leakage or back pressure test to prove valve closure. l Thre check valves will be tested during cold shutdowns using non-intrusive techniques to prove valve closure.

NOTE 39 l

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- Deleted -

(Replaced by VR-31) l l

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I" SERVICE TESTING PROGRAM PIJdt FOR VALVES BRAIDWOOD STATION UNITS 1 AND.2 Revision 7 NOTE 40 1

l M e 1/2CC9415 are motor operated, 16 inch, gate valves in the supply line to the reactor coolant pues and other non-essential cesponent cooling loads. They close to isolate non- l

'ccsontial loads. Rose valves can caly be closed when all 4 RCPs are off, therefore,. l these valves will be tested in cold shutdowns when all 4 RCPs are off. Refer to VR-8 for '

additional information, i

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i j IN!ERVICE TESTING PROGRAM PLAN FOR VALVES

XRAIDWOOD STATION UNITS 1 AND 2 i Revision 7 f COLD SHUTDOWN JUSTIFICATION NUMBER (

2 l VC-1 1

l CCEEPONENT IDENTIFICATION: (Safety Injection Acctenulator Discharge Motor Operated Valves) 1 Motor Operated Valves

IWV-2200 CODE DRANING DRAWING >

) VALVE NIEEER CATEGORY QAEA M COQRDIERI'E 1 1(2)SIse0aA a 1 M 61(136)-5 C6 (C3) ;

j 1(2)SIssosa a 1 M 61 (136) - 5 C4 (C6) ,

i 1(2)SIsa0sC a 1 M 61(136)-6 C7 (D2) !

i 1(2) SI8808D a 1 M 61 (136) - 6 CS (D4) i 1 FDMCTION (S) : I I

l The SI8808 valves are Motor Operated Safety Injection Accumulator Discharge Isolation j valves. h se valves are OPEN with Power Reseved for Modes 1, 2, and 3 with Pressuriser i

Procsure above 1000 psig. These valves were included in the IST Program for their need to

) be closed after all of the water in the Accuan,tlator has been injected into the RCS. .

Clorure of these valves would prevent' injection of a Nitrogen bubble into the RCS. These j valves were included in the IST Program for testing in noth OPEN and CIOSED directions.

3 JUSTIFICATION:

T chnical Specification 3/4.5.1.a requires "The (Accusulator) isolation valve open and i

s swer reseved..." while in Modes 1, 2 or 3 (with pressuriser pressure above 1000 psig). i l Since the Technical Specifications require these valves to be OPEN with power to their motor operators removed during periods when pressuriser pressure is above'1000 psig, the i

valves cannot be exercised every three months. In lieu of stroke time testing the valves 1 cvery three months, these valves will be. tested during heatup or cooldown (the pressure transition between 800 and 1000 psig pressuriser pressure) or, they will be tested with

! ths RCS depressurized and the associated accumulator vented and drained. ;

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4 INSERVICE TESTING PROGRAM PIAN FOR VALVES

! ERAIDWOOD STATION UNITS 1 AND 3 i

Revision 7 i

COLD SHUTDOWN JUSTIFICATION NUMBER

VC-2 t

i

CCEEPOMENT IDENTIFICATION: (RCP Seal Injection Inlet Motor Operated Valves and Check l

$ Valves).

, ' Motor Operated valves i

i IWV-2200 CODE DRAWING DRAWING j VALVI MEREER i

CATEGORY M M COQRDIMkTI 1 (2) CV8355A B 2 - M 64 (138) -1 BS (BS) l

$ 1(2) CV83558 5 2 M 64 (138)-1 54 (54) l l 1(2) CV8355C B. 2 M 64 (138)-2 58 (BS) ]

] 1(2) CV8355D B 2 M 64 (138) -2 B5 ' (55) :

3-Check Valves I IWV-2200 CODE DRAWING DRAWING ;

VALVE MtEEER CATEGORY Q&gg , EtEEER COORDIMkTE I i 1(2) CV8368A BC 2 M 64 (138)-1 B7 (57) l 1

1 (2) CV83685 BC 2 M 64 (138)-1 C4 (C4)

.- 1(2) CV8368C BC 2 M 64 (138) .-2 38 (BS) i j 1(2) CV8368D BC- 2 M 64 (138)-2 B5 (B5). [

] l 1

l FUNCTION (S) :

4 l

l 'the CV8355 valves are Motor Operated Isolation valves in the seal injection :

i ine to the Reactor Coolant Pumps. Additionally, the CV8355s are designated l 1 .ontain= ant Isolation valves but are exempt frost Local. Leak Rate Testing of 10 t 4

CFR 50, Appendix J. The CV8355s are passive open valves and they have no autosiatic {

closure function as part of Containsient Isolation. Because they are required to be e

sianually closed for loss of all AC power or excesive seal injection leakage, they are included in the scope of IST.

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The CV8368 valves are Check Valves in the seal injection line to the Reactor i Coolant Pumps. Additionally, the CV8368s are designated Containment Isolation j v lves but are exempt from Local Leak Rate Testing of 10 CFR 50, Appendix J.

JUSTIFICATION:

J Ranctor Coolant Pumps (RCPs) are required to be in operation in Mode 1, Power Operation. Seal injection flow must be maintained when the RCPs are running.

Seal injection flow stoppage with the RCPs in operation, even for short j duration, is detrimental to the RCP seals. The above listed valves are Seal

! Injection Inlet valves and are designated Containment Isolation valves (CIVs).

1

j. 'these valves are exempt from Local Leakage Rate testing of 10 CFR 50, Wadix J, but due to their designation as CIVs, they will be tested per ASME Code in the closed direction.

I Due to the above, these valves will not be exercised during plant operation, but they will I i be exercised during Cold Shutdown WHEN THE RCPs ARE NOT RUNNING. Short duration forced j l out ges to Cold Shutdown seldom require shutdown of RCPs as they are part of the normal i helt removal loop. It is NOT the intent of this justification to require RCP shutdown

. only to perform the exercise tests for these valves. It is anticipated that these valves may not normally be. tested more often that once per refueling outage. However, these I v 1ves will be tested during cold shutdowns in which the RCPs are secured for sufficient j '.sie to perform the tests.

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IESERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 '

Revision 7 COLD SHUTDOWN JUSTIFICATION NUMBER ;

VC-3 i CCEEPONENT IDENTIFICATION (Blowdown Flow Control / High Energy Line Break !

[HEIA) Isolation Valves) j Air Operated Valves :

IWV-2200 CODE DRANING DRANING VALVE MtEEER CATEGORY g&gg M COORDIEATE ;

ISD054A B 2 M 48-5A DS 1(2) SD054B B- 2 M 48-5A(55) D7 (DS) ,

ISD054C. B 2 M 48-5A D6 1(2) SD054D B 2- M 48-5A(5B) D6 (D6) l 1SD054E B 2 M 48-5A D5 ;

1(2) SD054/ 3. 2 M 48-5A(55) De (D4) !

ISD054G .B 2 M 48-5A D3- ;

1 (2) Q054H B 2 M 48-5A(55) D2 . (D2)

FIBKTION(S) :

The SD054 valves are normal Steam Generator Blowdown throttle control valves. ;

An additional function of the Unit 1,- (A through H valves). and the Unit 2,. (B !

train valves [B, D, F, & H]) is to isolate Blowdown for High Energy Line !

Creek purposes.

JUSTIFICATICE: l l

t is impractical to exercise and stroke.. time the above listed valves on a l quarterly basis. The valves have no Open / Closed handswitch. They are ;

normally operated by means of a potentiometer which ultimately controls an cir signal to a positioner. Attainment of repeatable. stroke time results ,

i requires the valves to be stroked by causing (or simulating) HEIA relay i

.cetuation. This method of closure causes multiple valve actuations resulting '

in complete steam generator blowdown isolation. Furthermore, the remote .

position indicator, (a 0-100% indicator - not based on limit switch !

operation) may lag actual valve position. Therefore the only repeatable i method of stroke timing these valves involves stationing personnel locally at.

the valve (s) to witness actual valve movement. For this reason, the SD054 valves are exempt from position indication testing requirements.

Full stroke exercising the valves is a Unit operation concern in that closure cf these valves during normal operation presents a thermal transient to the downstream piping and components including the blowdown condenser. While the valves, piping, and components are designed to withstand this thezzal transient, each transient produces stress which may lead to premature failure cf the affected components. It is prudent to minimise the number of thermal transients that these high energy. lines are required to undergo.

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4 INSERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l

ir COLD SHUTDOWN JUSTIFICATION NUMBER '

j VC-3 !

(continued) ,

i 4 Pcrconnel safety concerns exist with this stroking exercise during normal !

j operation in that the valves are physically located in the Main Steam 1

IColation (MSIV) Valve House. This rocal contains the MSIVs, Feedwater ,

Icclation Valves (FWIVs), Main Steam Safety Valves, Main Steam PORVs, and '

cther miscellaneous piping and valves. The normal ambient tesperature in this l i roost with the Unit at power is greater than 110 *F. Almost all of the piping 1 (most of which is insulated) and instrument tubing in the room are normally at j temperatures of approximately 500 *F or more. The SD054 valves are located

above the floor some 16 to 20 feet and are not visible frasi the floor being .

obscured by Main Steam and Feedwater Piping. Since personnel must be i ctationed locally at the valve to witness actual valve movement, it is i j necessary to climb around very hot piping in a hot and very noisy ambient l

cteosphere. In some cases, it may be necessary to erect scaffolding to conduct

l l thin test with the Unit in normal operation. I Due to the above, these valves will be tested in Cold Shutdowns of sufficient l

j duration to allow safe access to the valves, including the erection of !

j ccaffolding if required. 1 l 1 i l 1 l 1

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES i l

CRAIDWOOD STATION UNITS 1 AND 2 !

j Revision 7 1

j COLD SHUTDOWN JUSTIFICATION NUMBER j VC-4 l 1

i i i CCEEPONENT IDENTIFICATION: (Charging and Volume Control system Letdown Isolation and !

l Letdown Orifice Isolation valves) l l j Air Operated Valves l

i 1 IWV-2200 CODE DRAWING DRAWING l j VALVE NIBIBER CATEGORY CL&SA NUMBER COORDIMkTI l l 1(2) CV459 B 1 M 64-5 (138-58) E7 (F5)

! 1 (2) CV460 B 1 M 64-5 (138-58) F8 (F7) l 1(2) CV8149A B- 2 M 64-5 (138-58) F6 . (E2) 4 1 (2) CV81495 B 2 M 64-5 (138-58) F6 (E3)

}

1 (2) CV8149C B 2 M 64-5 (138-58) F5 (F2)

FUNCTION (S) :

j CV459 & 460 valves are normally OPEN with the Unit at power, allowing letdown flow to occur. The valves auto close on low Pressuriser level and on letdown isolation due to an interlock with the orifice isolation valves.

CV8149 Orifice Isolation Valves are interlocked with CV459/460 to Close on Phase A j Containment Isolation signal. One or more of these valves are normally OPEN to maintain t 1stdown flow.

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j ,USTIFICATION:

1 It is impractical to exercise and stroke time the above listed valves on a quarterly

ba::is. Due to the interlocks between the 459, 460, & the 8149 valves, excercising these j valves during normal operation results in (multiple) total letdown flow isolation events.

The affect of a letdown isolation with the Unit at power is a thermal transient to the Ictdown lines, heat exchangers, and other components. A letdown isolation also results in j come amount of pressuriser level fluctuation until equilibrium letdown and makeup is re-j catablished. While the piping and components are designed for thermal transients, each j cycle presents some additional stress to all of the affected equipment. It is pnadent to

minimise the number of transients the equipment is required to undergo to prevent j premature failures.

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{ Due to the above, these valves will be tested in Cold shutdowns of sufficient duration.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES 2RAIDWOOD STATION UNITS 1 AND 2 Revision 7 l l

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l BBCTICH 4.5 VALVE TECENICAL APPROACEES AMD POSITIONS i

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1 INSERVICE TESTING PROGRAM PIAN FOR VALVES

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

1 IST Technical Approach and Position No. VA-01 A. Cr==v==nt Idantification:

1

1.

Description:

Method of Stroke Timing Valves - Timing using control board l position indication lights (St).

f 2. Cosponent Numbers: See IST Valve Tables.

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3.

References:

ASME Code,Section XI, Subsection IW, paragraph IW-3413 (a) .

l 4. Code Class: 1, 2, and 3.

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3. Reauirement

! Use of the control board open and closed lights to determine the stroke time of power-operated valves has recently become an issue for discussion in the industry.

I Paragraph IW-3413 of ASME XI defines " full-stroke time" as "that time interval from i initiation of the actuating signal to the end of the actuating cycle." It is common j industry practice to measure stroke time as the time interval between placing the j operator switch on the control board in the "close" or "open" position and

indication that the valve is open or closed on the control board (switch to light) .

C. Position:

l It is recognized that the way in which the limit switch that operates the remote j position indicator lights is set may result in " closed" or "open" indication before

the valve obturator has actually cospleted its travel. ' Itis is not considered to be a problem, as the purpose of the test is to determine if degradation of the valve operator system is occurring, which is determined by observing changes in stroke i

time relative to the reference stroke time. Stroke time measurements should be

. rounded to the nearest tenth (0.1) of a second, except that stroke times less than one half (0.5) second may be rounded to 0.5 second, if appropriate. ,

Standard rounding techniques are to be used when rounding stop watch readings during i

valve stroke time testing (e.g.,10.45 rounds to 10.5 and 10.44 rounds to 10.4) .

l Rounding to the nearest second for stroke times of 10 seconds or less, or 10% of the

} specified limiting stroke time for stroke times longer than 10 seconds, as allowed !

j by ASME Section XI subparagraph IW-3413 (b), will not be used. l l

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f i' INSERVICE TESTING PROGRAM PLAN FOR VALVES-2 ERAIDWOOD STATION UNITS 1 AND 2 j Revision 7 f

j IST Technical Approach and Position l No. VA-02

] A. Ccamanent Identification:

l l 1.

Description:

Method of Fail Safe Testing Valves.

2. Component Numbers: See IST Valve Tables (Ft) .

3.

References:

ASME Code,Section XI, subsection IW, paragraph IW-3415.

4 Code Class: 1, 2, and 3.

j B. Raauirement:

1 i Paragraph IW-3415 of ASME XI states that "When practical, valves with fail-safe j actuators shall be tested by observing the operation of the valves upon loss of i actuator power." Most valves with fail-safe positions have actuators that use the fail-safe mechanism to stroke the valve to the fail-safe position during normal operation. For example, an air-operated valve that fails closed may use air to open

- i i the valve against spring pressure. When the actuator is placed in the closed position, air is vented from the diaphragm and the spring moves the obturator to the 1 closed position.

C. Position:

In the cases where normal valve operator action moves the valve to the closed position by de-energising the operator electrically, by venting air or both (e.g.,

an electric solenoid in the air system of a valve operator moves to the vent position on loss of power), no additional fai2 -safe testing is required. Valves with fail-safe actuators that do not operate as part of normal actuator operation must be tested by other means. This may be accesplished for motor operated valves j by opening the circuit breaker supplying operator power and observing that the valve l moves to its fail-safe position. Lifting leads is not required unless it is the a

only method of de-energizing the actuator.

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Using a valve remote position indicator as verification of proper fail-safe l operation is acceptable, provided the indicator is periodically verified to be i operating properly as required by ASME Code,Section XI, subsection IW, paragraph l

IW- 33 00.

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES RRAIDWOOD STATION UNITS 1 AND 2 Revision 7 )

IST Technical Approach and' Position No. VA-03 )

A. Component Identification:

1.

Description:

Method of Full Stroke (Ct) and Back Flow (Bt) Exercising of I Check Valves.

2. Component Numbers: See IST Valve Tests (Ct and Bt) . j

3.

References:

(a) NRC Generic Letter 89-04, Guidance on Developing Acceptable i Inservice Testing Programs, Attachment 1, Positions 1, 2, and 3; (b) ASME i Code,Section XI, Subsection IW, paragraph IW-3522; (c) SMAD Report !

M 1078-91, *SI Accumulator Check Valve Acoustic Test." j

4. Code Class: 1, 2, and 3. j B. Reauirement.

Paragraph IW-3522 of Article XI states " check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical, during plant ,

operation the check valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns." For check valves with no external i l position indication devices, the determination of when they are in full open !

r position has proven difficult to determine. The verification of when a valve is the .

full open position affects the determination of which valves are only part-stroked 1 and thus require additional full-stroke testing during cold shutdown or refueling.

l .. Position: l Valid full-stroke exercising to the full-open or full closed position may be accomplished by observing an external position indicator which is considered to be a ,

positive means of determining obturator position. Where external position i indicators are not provided, manual stroking of the valve is acceptable. Where a mechanical exerciser is used, the torque required to move the obturator must be recorded and meet the acceptance standards of subparagraph IW-3522 (b) . Per the I requirements of NRC Generic Letter 89-04, Attachment 1, Position 1, the other acceptable method of full-stroke exercising a check valve to the open position is to verify that the valve passes the maximum required accident condition flow. Any flow less than this is considered as a part-stroke exercise. Flow through the valve must be determined by positive means such as permanently installed flow instruments, temporary flow instruments, or by measuring the pressure drop across the valve or l

other in-line component. Measuring total flow through multiple parallel lines does not provide verification of flow through individual valves.

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j INSERVICE TESTING PROGRAM PLAN FOR VALVES

! 3RAIDWOOD STATION UNITS 1 AND 2 4 Revision 7 l

l

IST Technical Approach and Position No. VA-03 i C. Position, continued I j One exception to the "=mvisum required accident flow" requirement is the methodology.-

j used to verify full-stroke exercising of the Safety Injection (SI) Accumulator

' Back-up Check Valves, 1/2 SIS 956A-D. Because of the high maw 4== design flow rate of l these valves, a maximum design accident flow rate test As physically impossible to i perform. For these valves, an Engineering calculation has been performed to j determine the minimum flow rate for full disc lift. An acceptable full-stroke j exercise of these valves will be performed each refueling outage by measuring the 1 pressuriser level increase over time, converting these parameters to a flow rate

through the valve, and verifying this value is greater than or equal to the engineering calculated minimum flow rate for full disc lift. Per reference c above, these valves were also verified to full-stroke open by using a " time of arrival" acoustic emission technique on the unit one valves that was performed in conjunction with the injection test dercribed in VR-05. ' This method is superior to sample ,

disassembly and inspection of one valve per outage which would require unusual- .,

system line-ups, freese seals, radiation exposure, and possible plant transients..

]

Other alternatives to measuring full design accident flow or disassembly and )

inspection of check valves to satisfy full stroke requirements is allowed as long as l the requirements of NRC Generic Letter 89-04, Attachment 1, Positions 1, 2, and 3 are utilized gg specific relief requests are approved by the NRC.

Stroking a valve to the full closed position for valves without a manual exerciser '

or position indicator must be verified using indirect means. These include, but are not limited to, (1) observing pressure indications on both sides of the valve to determine if the differential pressure expected with the valve shut is obtained, or (2) opening a drain connection on the upstream side of the valve to detect leakage rates in excess of that expected with the valve shut.

Valves that cannot be full-stroke tested or where full-stroking cannot be verified, shall be disassembled, inspected, and manually exercised. Valves that require disassembly for full-stroke testing during cold shutdowns or refueling still require quarterly part-stroke testing, where possible.

Testing of check valves by disassembly shall comply with the following:

a. During valve testing by disassembly, the valve internals shall be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised,

b. Due to the scope of this testing, the personnel hazards involved, and system operating restrictions, valve disassembly and inspection may be performed during reactor tefueling outages. Since this frequency differs from the Code required frequency, this deviation must be specifically noted in the IST program.

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b 1 INSERVICE TESTING PROGRAM PIAN FOR VALVES l GRAIDWOOD STATION UNITS 1 AND 2 l

j. Revision 7 )

!- l l IST Technical Approach and Position I No. VA-03 I l

-c. Where it is burdensome to disassemble and inspect all applicable valves each refueling outage, a sample disassembly and inspection plan for groups of g identical valves in similar applications may be esployed. The NRC Generic ,

Letter 89-04 guidelines for this plan are explained below: ;

l 'Ibe sample disassembly and inspection program involves grouping similar i valves and testing one valve in each group during each refuelirs outage. <

' The sampling technique requires that each valve in the group be the same ,

{ design (manufacturer, size, model number, and materials'of construction) !

l and have the same service conditions including valve orientation. !

j Additionally, at each disassembly the licensee must verify that the I

] disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound (no loose or corroded parts) . Also, if

the disassembly is to verify the. full-stroke capability of.the valve,

1 the disk should be manually exercised. '

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i A different valve of each group is required to be disassembled, ;

j inspected, and manually full-stroke exercised at each successive i

refueling outage, until the entire group has been. tested. 'If the )

i disassembled valve is not capable of being full-stroke exercised or j there is binding or failure of valve internals, the remaining valves in j that group must also be disassembled, inspected, and manually j full-stroke exercised during the same outage. Once this is completed, J

the sequence of disassembly must be repeated unless extension of the

interval can be justified.

I a Extending the valve sample disassembly and inspection interval from j disassembly of one valve in the group every refueling outage or a r M ng the j group size would increase the time between testing of any particular valve in

the group. With four valves in a group and an 18-month reactor cycle, each j valve would be disassembled and inspected every six years. If the fuel cycle 1 is increased to 24 months, each valve in a four-valve sample group would be i disassembled and inspected only once every eight years, i

3 Extension of the valve disassembly / inspection interval from that allowed by-j the Code (quarterly or cold shutdown frequency) to' longer than once every 6 j years is a substantial change which may not be justified by the . valve failure j rate data for all valve groupings. When disassembly / inspection data for a !

! valve group show a greater than 25% failure rate, the station should determine whether the group size should be decreased or whether more valves from the group should be disassembled during every refueling outage.

f Extensions of the group size will be done on a case by case basis, i

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INSERVICE TESTING PROGRAM PIAN FOR VALVES .

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 IST Technical Approach and Position No. VA-04 j A. Commonant Idantification:

1.

Description:

Determining Limiting Values of Full-Stroke Times for Power Operated Valves. l l

2. Component Numbers: See IST Valve Tables (St) .

3.

References:

a. ASME Code,Section II, subsection IWV, Sub Article IWV-3413. ]

b. NRC Generic Letter 89-04, Attachment A, Position 5. l

c. ANSI /ASME Cat-1987 through 03b-1989 Addenda, Part 10, Section 4.2 ]

4. Code Class: 1, 2, and 3.

B. Raauiramant:

h e IST program originally assigned a limiting value of full-stroke time based on ,

the most conservative value from plant Technical Specifications (TS) or Updated 1 Final Safety Analysis Report (UFSAR) . For valves not having a specified value of ;

full-stroke, a limiting value was assigned based on manufacturers design input, I engineering input, or initial valve pre-operational testing. . his methodology is ;

contrary to NRC Generic Letter 89-04. I 1

According to NRC Generic Letter 89-04 the limiting value of full-stroke should be l based on an average reference stroke time of a valve when it is known to be )

operating properly. The limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results in a valve being declared-inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended functien. When the calculated limiting value for a full-stroke is greater than a TS or safety analysis limit, the TS or safety analysis limit should be used as the limiting value of-full-stroke time.

Based on this, a review of each valve operating history was performed and an average / reference value of full-stroke determined. In addition, valves were grouped l

together by system, train, unit, valve type, and actuator type to provide for a more l

thorough review in determining what would be a ' reasonable" deviation from the

! average / reference full-stroke value.

The 1983 Edition through Summer 1983 Addenda of ASME Section II does not provide guidance for determining values of full-stroke.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES .

! ERAIDWOOD STATION UNITS 1 AND'2 Revision 7 f

l IST Technical Approach and Position

No. VA-04 I l

C. Position

The following criteria will be used as general guidance to establish REQUIRED ACTION ranges for power-operated valves

sovs/Hova/Aava famm th=a or e==1 to 10 seconds

i REQUIRED ACTION VALUE: Greater than (2.0) (T,.r)

SOVs/HOVs/ADVs - Greater than 10 seconds:

, REQUIRED ACTION VALUE: Greater than (1.75) (T,,,) or ' (T,.r+20 sec)

ICVs - Imss than or maual to 10 seconds:

REQUIRED ACTION VALUE: Greater than (1.5) (T,.r)

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I IDVs - Greater than 10 seconds:

J j REQUIRED ACTION VALUE: Greater than (1.25) (T,.r) or (T,,,+2 0 sec) i Additional Notes:

1. T,.c is the reference or average stroke value in seconds of an individual valve e

or valve grouping established when the valve is known to be operating acceptably.

2. Standard rounding techniques are to be used when roemd4ng off stopwatch readings during valve stroke timing (e.g.10.45 rounds to 10.5, and 10.44 is rounded to 10.4 seconds). Round off all measured stroke time to the nearest

, tenth of a second.

. 3. When reference stroke valves or average stroke valves are affected by ot"or parameters or conditions, then these parameters or conditions must be analyzed and the above factors adjusted.

4. If the above calculated values exceed a Technical Specification or FSAR value, then the TS or FSAR value must be used for the limiting value of full-stroke.

5. Lir.scing values of full stroke will be rounded to the nearest second.

6. REFER to relief request VR-20 for fixed ALERT Ranges.

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i l ICSIRVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 ,

i Revision 7 i

l l IST Technical Approach and Position l No. VA-04 l 4

j. Additional Notes: (continued) '

i

7. Fast acting valves (valves which normally stroke in less than 2 seconds consistently) are included in Relief Request VR-12. These valves are. E

! assigned ALERT RANGES and are E trended. [

, i l 8. 'Ihe above criteria is a guide and cannot cover all valves. The REQUIRE ACTION :

{

VALUES are selected based on comparison between the REFERENCE VALUE, LIMITING j j VALUE given in Technical Specifications /UFSAR, operating history, and i

calculated values using the above criteria. i

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9. Valves which serve the same function on dual trains (i . e . , ICC9473A and '

{ 1CC94738) and dual units (i.e. ICC9473A and 2CC9473A) are assigned the same l REQUIRED ACTION VALUE based on human factors considerations, unless valve or 1 l system design differences exist between the trains / units. 4 f

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 IST Technical Approach and Position No. VA-05 A. Coniponent Identificaticm:

1.

Description:

Testing of the Boric Acid Transfer Pumps Discharge Check Valves

2. Component Numbers: 0AB8473, 1/2AB8487

3.

References:

(a) Engineering Correspondence (CHRON # 161733). dated January 17, 1991

4. Code Class: 3/T (Tracking purposes ONLY)

3. Reauirement:

These check valves are tested per the Technical Specification requirement that ;

requires an 18 month flow verification of 30 gym to the RCS. Because the AB punps were added to the program, the discharge check valves will also be added for-tracking purposes only.

C. Position:

The boric acid transfer pumps were added to the IST program per pump technical position PA-01. Since this was done, it was decided to put the discharge check valves in the program as well for tracking purposes only. These valves are required to pass a minianum of 30 gym in order to meet the Technical Specification requirement. The quarterly pump test will verify greater than 30 gym, which is significantly more frequent than the currenc Technical Specification frequency.

Back flow is prevented from the r ha=4 cal and volume control system (CV) by check valve 1(2)CV8442 and motor operated valve 1(2)CV8104 in the emergency boration flow path. Also, the system uses only a single pump in series which precludes short circuiting of flow through the parallel pusp's discharge check valve, so no back flow test will be performed.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 IST Technical Approach and Position No. VA-06 A. Cosmonent Identification:

1.

Description:

Stroke Timing Solenoid Valves without Position Indicatico using Non-intrusive Magnetic and Acoustical. Techniques !

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2. Component 3hesbers: 1SIl01A,- 2SIl01A

3.

References:

ASME Code,Section XI, Article IW-3000 3

a. Full stroke time power operated valves per IW-3413 (a) and IW- !

3413 (b) . '

b. Fail-safe test actuators per IW-3415.

c. Take corrective action per IW-3417 (a) and IW-3417 (b) .

4. Code Class: 3

3. Reauirement f The 1/2SX101A valves are the essential service water (SI) cooling outlet valves for the motor driven auxiliary feedwater (AF) pump lube oil coolers. Both of these '

valves are completely encapsulated per design (valve stem not visible) and do not

-have any type of limit / reed switches for remote position indication. These valves are energized and de-energized in conjunction with the pump control-start switch. l l

The 1/2SIl01A valves are pilot operated globe type solenoid valves - energized to i close. Upon de-energising (pump start), the valve opens by both spring force !

against the plunger, which holds the pilot off its seat, and differential pressure :

across the main disk, caused by the pilot orifice opening allowing pressure to be j reduced, assisting in opening the valve. Upon'energising, tho' valve closes by the ;

magnetic force of the coil pulling the plunjer down, closing the pilot disk which l closes the pilot orifice, permitting pressure to build up above the main disk, j assisting in closing the valve. In the absence of any pressure differential across i the main disk, the spring or magnetic force is sufficient to open or close the i valve, respectively.

Per the Code requirements, these valves can not be tested by the traditional means l of stopwatch and. indicating lights. The Code also requires that fail-safe actuators be tested by observing the operation of the valve upon loss of actuator power (in this case electrical power). Additionally, stroke times are to be compared to the previous value. Relief request VR-20 has been approved to use fixed reference values to establish acceptance criteria.

C. Position:

In situ testing has shown that the differential pressure, which is not able to be controlled, affects the opening stroke characteristics more so than the closing stroke characteristics, in regards to stroke time measurement. Therefore, the stroke time will be measured in the close direction (instead of the open direction) on a quarterly basis. The closing stroke time'will be used to provide the key parameter for determining degradation (based on the repeatability in stroke time results, in the closed direction, obtained to date). The fail-safe test will be l accomplished by observing that the cooling water outlet temperature changes when the pump starts, along with a minismen stroke time value on valve closing.

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I INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 IST Technical Approach and Position No. VA-06 C. Position: (continued)

The process developed for measuring the actuation time of the 1/2SIl01A solenoid operated valves uses both an acoustic (accelerometer) transducer and magnetic field (inductive coil) sensor mounted external to the valve's housing. The use of an magnetic field sensor provides the (within a few milliseconds) time the solenoid's coil is either energized or de-energized. The accelerometer detects the acoustical l

" click" within the valve to indicate the end of the stroke cycle. The same certified test equipment and computer software (not safety related) that is used for check valve testing is used for this test. Signal processing and analysis of the collected data is performed to accurately determine valve stroke time. This timing method is on the order of two magnitudes more accurate than the conventional Code stroke time method and is clearly an acceptable test method to meet the Code requirement.

The acceptance criteria to be used for these valves has bene established at two times the reference value (these valves stroke normally around 80 maec), with a minimum stroke time of 40 maec. The minimum stroke tims is based on the acoustic

" click" which is representative of the pilot valve and main disk impacting the seat.

Any stroke time value less than 40 maec is indicative of the valve not full stroking to the open position. There is also a monthly test which uses changes in the cooling water outlet temperature, in conjunction with acceptable lube oil temperatures, to monitor valve opening.

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i 1 INSERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 3 '

Revision 7 9

i VA-07 l IST Technical Approach and Position A. Component Identification:

t

1.

Description:

Justification for exercising the Cosponent Cooling heat

! exchanger and pump manual isolation valves on a U-2 Cold Shutdown frequency.

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} 2. Component Numbers / Functions:

1 l a. 1/2CC9458: CC pump Discharge Header Manual Isolation valves which may j provide for train separation in a post accident situation.

J l b. 1/2CC9459A: CC Pump Suction Header Croestie Manual Isolatic$n valves

} which may provide for separation / isolation of the CC system into two ,

t redundant trains during recirculation phase'of RHR operation during a

IOCA and other applicable accident modes. i

] c. 1/2CC94598: CC Pump Suction Header Crosstie Manual Isolation valves j which may provide for separation / isolation of Unit-1 and Unit 2'CC

systems during normal cooldown and recirculation phase of RHR operation, t j d. 1/2CC9467A: CC heat exchanger Outlet Header Crosstie Manual Isolation i Valves which provide for possible manual isolation of flow to the unit

{ normal plant loads if the respective CC9415 valve fails open.

i e. 1/2CC94675: CC Heat Exchangsr Header Crosstie Manual-Isolation Valves i j which may provide for train separation while the subject unit undergoes ;

j~ Post LOCA cooldown. Provides separation / isolation of Unit-1 and Unit 2 ;

CC systems during normal cooldown and recirculation phase of RHR '

operation. ,

]

l f. 1/2CC9467C: CC Supply Header Crosstie Manual Isolation Valve which may 1

need to be called upon due to a single failure within the CC system

) configuration.

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3.

References:

j a. ASME Code,Section II, Subsection IWV, paragraphs

IWV-3411, 3412

! b. Draft NUREG-14B2, Section 3.1.1 b

r c. OM-10, paragraphs 4.2.1.1, 4.2.1.2

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1 4 INSERVICE TESTING PROGRAM PIAN FOR VALVES I ERAIDWOOD STATION UNITS 1 AND 2 2

Revision 7 1

h -1

j. '4. Code Class: 3 )

i l 5. Category: B h 5. Requirement:

l Per IWV-3412, " Valves shall be exercised to the position required to fulfill their i function unless such operatico is not practical during plant operation". In related !

l regulatory documents, section 4.2.1.2.c of OM-10 states that, " if emercising is not- 3 j practicable during plant operation, it may be limited to full-stroke exercising l

during cold shutdowns". Draft NUREG-1482, section 3.1.1, states that " Exercising j valves at each cold shutdunn outage is not a deviation from the Code and does not- l j ; require a relief request". ;

1 j C. Position: 1 i

i PART A:

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1 Manual Valves 1/2CC94595 and 1/2CC9467B are used to provide train separation and/or- ,

i isolation of the ccaponent Cooling Water System. More specifically, they are l l aligned to place the U-0 Heat a ehanger and Pump on the U-1 or U-2 side of CCW to 1 i ensure adequate cooling during shutdowns and/or Post-Accident.

I j Stroking these valves quarterly or during U-1 cold shutdowns would be a considerable burden and potential. safety concern. The CC system is a delicately balanced system l

i that has the potential' for becosting upset upon swapping the Unit 0 Heat Exchanger l

} and Pump frcm one unit to the other. History has shown that stroking these valves i i will cause oscillation in-the lines, disrupt flow balancing due to D/P differences :

i throughout'the system, and would place the normal' loads at risk for adequate l j cooling. For instance, the CC685 valve, which is the Reactor Coolant Pump thermal l t barrier Component Cooling Water return valve, autocloses on high flow, which would

] result in a loss of flow to the RCP thermal barriers. ~ 'Ittis valve could potentially ;

. close during the CC stroke testa due to the upset flow conditions. In addition, the {

j CC surge tanks will be at risk of draining, resulting in possible pump trips on low- )

low level. The potential problems would only be compounded by stroking these valves '

during a U-1 cold shutdown since the U-0 heat exchanger and pump will be.in use on the U-1 train. Hence, Braidwood considers it impractical to perform this testing

quarterly or during a U-1 cold shutdown.

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! INSERVICE TESTING PROGRAM PIAN FOR VALVES l ERAIDWOOD STATION UNITS 1 AND 2 j Revision 7 ;

A review of maintenance history dating back to 1989, showw there has been no 4

evidence of valve exercising malfunctions frost that time to the present, further i justifying that exercising these valves on a quarterly basis would result in no value added. The 1/2CC9459B and 1/2CC94678 valves will be exercised at the same ;

j frequency as each U-2 Cold Shutdown, or a minimuni of once every 18 months due to s i each U-2 Refueling Outage. This is when the U-0 heat exchanger and pung are l normally swapped to U-2, necessitating the stroking of these valves. This ,

j frequency, rather than quarterly, will reduce the likelihood of a CC system

, malfunction caused by stroking these manual valves.

PART B

The 1/2CC9467A valves should not be stroked on a quarterly basis for reasons similar to that empressed in part A. One function of these valves is to isolate flow to the normal plant loads in a post-accident situation if the respective CC9415

, valve were to fail open. This would be an undesirable exercise during normal

operations. When the plant is in its normal lineup, isolation of the 2CC9467A valve 3 would indeed isolate flow to the normal plant loads. For U-1, if the ICC9467A valve j were isolated, CC flow would need to be diverted through the U-0 heat exchanger, l which may cause disruptions within the CC system. If the U-0 heat exchanger was .

aligned to the U-2 side, the opposite affects would be felt. For these reasons, j these valves will also be exercised during U-2 Cold Shutdowns with the valves from !

j part A.

j Part C: !

. Exercising the remaining valves (1/2CC9458, 1/2CC9459A, and 1/2CC9467C) on a >

l quarterly basis would not result in as much of a burden as the previously mentioned j valves. However, the exercising of these valves on a quarterly basis would clearly be impractical for the following reasons. As with all of the CC valves mentioned, i j maintenance history since 1989 indicates that there have not been any problems '

} associated with these valves concerning the actual manual exercising of them. There j are no indications of binding or other trouble exercising the valves. The work on 4

them has consisted nearly entirely of preventive maintenance re-packs and a repair j of a gearbox oil leak. One of the main reasons for incorporating IST testing is to j monitor for degradation, and there would be no value added to exercising these ;

valves on a quarterly basis. These valves will be exercised at the same time as the j

other valves in this position, on a U-2 Cold Shutdown basis. '

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7

Conclusions:

Besides the previous justifications mentioned, for each set' of valves, the UFSAR

" active valve" table 3.9-16 does not list any of thece valves as " active" and section 9.2.2.4 gives justification that these valves are not required in the short term following an accident. Also, the UFSAR states that if there was a single failure of a valve in the long term, making it undesirable to use a particular pump and heat exchanger, sufficient cooling would be provided with a different subsystem.

Testing these valves is conservative on Byron's part, and quarterly testing is less significant that in other cases due to the design of the system. All the valves listed in this position experience minimal wear and a minimum eighteen month manual exercise frequency (U-2 Cold Shutdown) should be sufficient to detect a problem.

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ICSERVICE TESTING PROGRAM PIAN FOR VAff1ES CRAIDWOOD STATION UNITS 1 AND 8 Revision 7 l 1

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EECTION 4.6 vaLv5 mzLIsr mEguBsTs k

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELTEF REOUEST VR-1 l

1. Valve Number:

All Type C tested primary containment isolation valves in this program are listed as Category A:

VALVE # VALVE # VALVE #

1) 1CC685 41) 1PR033B 81) ISIB888

2) ICC9413A 42) IPR 033C 82) ISI8964

3) ICC9414 43) IPR 033D 83) ISI8968

4) 1CC9416 44) 1PR066 84) 1VQOOLA

5) 1CC9438 45) IPS22&A 85) IVQ0015 j

6) ICC9486 46) IPS228B 86) 1VQOO2A i

7) 1CC9518 47) IPS229A 87) 1VQ002B

8) ICC9534 48) 1PS229B 88) 1VQ003

9) 1CS007A 49) 1PS230A 89) 1VQOO4A

10) 1CS007B 50) 1PS230B 90) 1VQ004B

11) ICSOOLA 51) 1PS231A 91) 1VQ005A

12) 1CS008B 52) 1PS231B 92) 1VQ005B

13) 1CV8100 53) 1PS9354A 93) 1VQ005C

14) 1CV8112 54) 1PS9354B 94) 1VQOl6

15) 1CV8113 55) 1PS9355A 95) 1VQO17

16) ICV 8152 56) 1PS9355B 96) 1VQO18

17) ICV 8160 57) 1PS9356A 97) 1VQ019

18) 1FC009 58) 1PS9356B 98) 1NM190

19) 1FC010 59) 1PS9357A 99) 1NM191

, 20) 1FC011 60) 1PS9357B 100) 1WOOOGA l 1) 1FC012 61) 1RE1003 101) 1W00065

.2) 11A065 62) 1RE9157 102) IN0007A

23) 11A066 63) 1RE9159A 103) IWOOO73

24) IIA 091 64) 1RE91595 104) 1NOO20A

25) 10G057A 65) 1RE9160A 105) IWOO20B

26) 10G079 66) 1RE9160B 106) 1NOO56A

27) 10G080 67) 1RE9170 107) 1 WOOS 6B

28) 10G081 68) 1RF026 l 29) 10G082 69) 1RF027

30) 10G083

70) 1RYO75 i 31) 10G084 71) 1RY8025 l 32) 10G085 72) 1RY8026

33) 1PR001A 73) 1RY8028

34) 1PR001B 74) 1RY8033

35) 1PR002E 75) 1RY8046 1 36) 1PR002F 76) 1RY8047 i

37) 1PR002G 77) 1SA032

38) 1PR002H 78) ISA033 l 39) IPR 032 79) ISI8871

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i j INSERVICE TESTING PROGRAM PIAN FOR VALVES l ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 l

i RELIEF REOURST VR-1 l

Valve Ehmmber: (continued) ;

i YAINE_i VALVE # EEfLi ,

108) 2CC685 148) 2PR0338 .188) 2818888 i f 109) 2CC9413A 149) 2PR033C. 189) 2 SIS 964 )

! 110) 2CC9414 150) 2PR033D 190) 2 SIS 968 !

l' 111) 2CC9416 151) 2PR066 191) 2VQ001A ]

112) . 2CC9438 152) 2PS228A- 192) 2VQ0015 113) 2CC9486 153) 2PS228B 193) 2VQ001A 114) 2CC9518 154) 2PS229A 194) '2VQ0028 l 115) 2CC9534 155) '2PS2295 195) 2VQ003 1 116) 2C8007A 156) 2PS23nA 196) 2VQ004A j- 117) 2CS007B 157) 2PS2308 197) 2VQ004B i 118)- 2C8008A 158) 2PS231A 198) 2VQ005A ;

j 119) 2CS0088 .159) 2PS231B 199) 2VQ0055 3

120) 2CV8100 160) 2PS9354A 200). 2VQ005C ;

i 121) 2CV8112 161) 2PS9354B 201) 2VQ016

122) 2CVS113 162) 2PS9355A 202) 2VQO17 l 123) 2CV8152 163) 2PS93558 203) 2VQ018 j 124) 2CV8160 164) 2PS935&A- 204) 2VQ019

, 125) 2FC009 165) 2PS9356B 205) 2Wkn90 1

126) . 2PC010 166) 2PS9357A 206) 2WM191 I i

127) 2FC011 167) 2PS93575 207) 2WO006A l i 128) 2FC012 168) 2RE1003 208) 2WOOO68 ;

129) 2IA065 169) 2RE9157 209) 2WOOO7A l

, 130) 2IA066 170) 2RE9159A 210) 2WOOO75 I

] 131) 2IA091 171) 2RE9159B 211) 2 WOO 20A j 132) 2OG057A 172) 2RE9160A 212) 2 WOO 20B I 133) 20G079 173) 2RE91605. 213) 2 WOO 56A i 134) 20G080 174) 2RE9170 214) 2 WOO 56B i 135) 2OG081 175) 2RF026 i

136) 20G082 176) 2RF027 i l 137) 20G083 177) 2RYO75 '

138) 20G084 178) 2RYS025 !

139) 20G085 179) 2RY8026 i

140) 2PR001A 180) 2RY8028 141) 2PR001B 181) 2RY8033 J 142) 2PR002E 182) 2RY8046

} 143) 2PR002F 183) 2RY8047

144) 2PR002G 184) 2RA032 1 145) 2PR002H 185) 2SA033' 146) 2PR032 186) 2SI8871

147) 2PR033A 187) 2SI8880 i

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INSERVICE TESTING PROGRAM PLAN FOR VALYSS

! CRAIDWOOD STATION UNITS 1 AND 2

Revision 7 j

RELIEF REOURST VR-1 i

j- 2. Number of Items: 214

~3. ASME Code Cateaory: A or AC l 4 3- 4. ASME Code.Section II Reauirements:

i I j Seat Leakage Measurement per IW-3420 and Corrective Action per IW-3427 (b) .

4-

$- 5. Basis for Ralief: '

l Primary containment isolation valves will be seat: leak tested in accordance with 4 10CFR50, AppanM w J. .For these valves,Section XI testing requirements are '

j essentially equivalent to those of Appendix J.

1 j 6. M ernate Testino:

..- .I

.l Primary containment isolation valves shall be seat leak rate tested in accordance with the requirements of 10 CFR 50, W adix J.. 'the results of such leak rate l

}

a measurements shall be analysed and corrected, as necessary, in accordance with the' ;

! . guidance set forth'in ASME Code Section II, Subsection IW, paragraphs IW-3426 and '

l-i IW-3427 (a) . The trending requirements of IW-3427(b). will agt be utilised. ;

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{ 7. Justification:

i .

i j No additional information concerning valve leakage would be gained by performing j i separate tests to both Section XI and Appendix J. Therefore, overall plant safety is -

not affected. As'specified per NRC Generic Letter 89-04, Attachment 1, position 10, j the usefulness of IW-3427(b) does not justify the burden of cceplying with this . ,

j requirement.

} '8. Acolicable Time Period:

! I f This relief is requested once per two years during the.first inspection interval. l J

9. Anoroval Status: '

i

a. Relief granted per NRC Generic Letter 89-04, Position 10.

b. Deleted SD valves per Technical Specification h nt #26.

c. Added 1/2RYO75 due to Appendix J, Type r Testing per Rev. 5a.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES.

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-02

1. Valve Bumber: ICS020A 2CS020A 1CS0205 2CS0205

2. Number of Itests: 4

'3. ASME Code Cateaorv C

4. ASME Code.Section II Smauirements:

Exercise check valves to the position required to fulfill their function (open=Ct;

-closed =Bt) quarterly, unless such operation is not practical during plant operation, per INV-3522, or exercise during cold shutdown per.IWV-3522.

5. Baala for Ralief:

These check valves in the spray additive systest (CS) cannot be stroked without introducing Ma0H into the CS system, unless the piping between-the NaOH storage. tank-and the injection isolation valves, 1/2CS021A/B, is drained into containers, which amounts to almost two 55 gallon drums of potentially (radioactive / toxic) mixed waste .

that requires either recycling or disposal. Men, primary water is connected to the CS systesi and is used to flow test the line to ensure that the proper Technical Specification eductor flow rate can be passed, via special test connections.

~

Se problem with disposal stems frost the caustic being slightly contaminated,- as well as having a high ph. Recycling (pouring the contents of the drums bank into the NaOH tank) is not always a viable option either, considering.the caustic has been contained in a stagnate line (up to five years) and may not meet chemistry requirements. S us storage of hasardous mixed waste can become very costly. This is due to the non-existence of commerical disposal facilities for mixed waste, which means that any mixed waste generated would have to be -stored rm-site. Also, the

, draining and handling of this highly caustic material poses m'significar.2. hasard to l personnel, and can result in loss of eye sight and/or chemical burns, if splashed or i spilled.

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l 6. Alternate Testina:

I he A and B train valves are of the same design (manufacturer, sise, model nusber, l and materials of construction) and have the same service conditions, including !

orientation. This forms an acceptable sample disasombly group per Generic Letter 89-04, Position 2c.

[ Each group will be disassembled and visually inspected at the same frequency as the-l Technical Specification eductor flow test, conducted at least once every five years. .

The visal inspection of internals will precede the eductor flow test. j GROUP 1 GROUP 2 ;

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l INSERVICE TESTING PROGRAM PLAN POR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7

.. Justification:

If the disassembled valve is not capable of being manually full-stroked exercised or there is binding or failure of internals, the remaining valve on the affected unit will be evaluated for further action as well.

Full flow testing of these valves cannot be accomplished without posing a serious.

threat to the safety of equipment and personnel. It is impractical to either full l or partial stroke exercise these valves since flow through them requires draining i and flushing the piping to prevent the introduction of caustic effluent into the CS system. The problem of mixed waste disposal or recycling created by_ system draining i of approximately two 55 gallon drums is considered an undue hardship, if the Code requirements are imposed.

The alternate test frequency (same frequency as the Technical Specification eductor-flow test of at least once every five years) is justifiable in that maintenance? ;

history and previous inspections of these valves at both Byron and Braidwood '

stations has shown no evidence of degradation or physical impairment (i.e. ,

corrosion, chemical buildup, wear). This is to be expected since these' valves see '

limited operation (flow in line during eductor- flow test only) .

Industry experience, as documented in NPRDS, show no history of problems with these valves. A company-wide check valve evaluation addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type-failures.

The alternate test method, visual inspection of internals followed by the Technical Specification eductor flow test, at least once every five years, is sufficient to ensure operability of these valves and is consistent with Generic letter 89-04 guidelines. The hardship involved with the hazardous mixed waste disposal and handling caustic material with regards.to personnel safety does not provide a compensated increase in safety of the CS system equipment.

In addition, the following information is provided to support the proposed five-year frequency for the 1/2CS020A and B check valves:

a. The Technical Specification eductor flow test is. required to ensure adequate NaOH

~

concentration of the containment spray system during an accident. This test has to be performed at least once every five years. Due to the hardships involved with this flow test as described in the proposed relief request, it is not practical to perform this test every refueling outage in lieu of disassembly and inspection. This is due to: 1) The potential to generate mixed waste that has to be stored on site. There are no commercial disposal sites available. 2) The risk associated with reducing the safe shutdown margin for the fuel below acceptable levels by the relatively large amounts of pure water necessary to accomplish eductor flow testing,-which is directly recirculated back to the RNST.

This reduces the boron concentration in the RNST, which is used as the make-up supply for the fuel pool and reactor refueling cavity. 3) Inconsistent with the ALARA concepts of the newly revised 10 CFR 20 regulation, due to the nigher exposure levels involved for the eductor flow test versus inspection. 4) Impedes the optimization of the preventive maintenance program, as implied by 10 CFR 50.65 (a) (2), by not utilizing.the information and data through monitoring and l trending as gained through visual inspection for these valves.

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INSERVICE TESTING PROGRAM PLAN POR VALVES

.BRAIDWOOD STATION IBtITS 1 AND 2 Revision 7 b.~The' design of these valves consists of a wafer style body and dual' disk plates,. ;

comanonly referred to as a duo check. They are simple check. valves,' requiring no disassembly of their internals in order to perform a thorough visual examination

-when removed.from the piping system.

c. The application of these valves,with regards to size,. proximity to turbulent sources in the piping system, and orientation has been reviewed and.foand i acceptable by recent industry guidelines. They are not subject to high !

concentrations of NaOH due to the upstream isolation valve being closed and the

internals of the valve being on the downstream side of the disk plates. They ar subject to stagnant borated water from the Refueling Water Storage Tank (RNST), l which is not as severe an environment as the NaOH stagnant line. This should eliminate the accelerated corrosion rate concern discussed in the TER.' ,

d. The failure history for these valves at both Byron and Braidwood is non-existent. l Their.are a total of 12 inspections documented-for;these valves, with no j degradation mechanisms identified (e.g., erosion, corrosion, fouling, wear,-

. binding, loose parts, and fatigue failure). This represents ten outages worth of inspection data or 15 valve-years without.any problems associated with valve j

condition. The failure data for the industry is insufficient to determine any-type of preventive maintenance frequencies which could factor into the proposed i five year test: frequency. Additionally, these valves have been reviewed in- ;

detail, using.the check valve inspection program optimization methodology, which !

evaluated each valve as having a preventive maintenance (PM) inspection frequency .;

of 7.5 years. This detailed evaluation process reviewed inspection data, .

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surveillance test data, maintenance history, vendor / industry information, NRC t I

information, safety significance, system service media, operating conditions, and- '

system application / design information.

e. Diagnostic non-intrusive techniques for these valves would require flow through :

the line in order to detect valve opening. However, design flow would be i obtained before disc full-stroke, based on the critical. flow calculation for these valves. Acoustic testing, which Commonwealth Edison employs at it's- :

nuclear units for non-intrusive testing, on similar duo type check valves has not !

been successful in proving full-stroke of both disk plates.' The smaller the i valve the more difficult it is to detect and evaluate full-stroke. . Based on !

this, the design flow through the valve would be.used in lieu of acoustics for.

' meeting the Section XI full-stroke open test requirement,.if the-eductor flow test is imposed to prove valve operational readiness. :

1

f. The water in the RNST is processed reactor coolant,Dand therefore potentially !

contaminated (it contains low level activity) . During-refueling outages the RWST l is used as a source of water for filling the reactor refueling cavity. When the ;

reactor refueling cavity is drained it is sont back to the RNST as well. If there is any leakage back to~the NaOH tank, then it has the potential to contain low levels of radioactivity, making it mixed hazardous waste. -

g. GL 89-04, Position 2 allows for a maximum of six years between inspections for an individual valve out of a sample group of four valves. Braidwood's proposal to inspect any single valve at a frequency of no greater than five. years-(three refuel outages) is bounded by the-six year acceptable interval established in the GL. Also, the full flow versus the partial flow testing after disassembly will meet the GL requirement to partial flow the valve after reassembly. The expansion criteria requirement will also be followed if the valve has a problem related to full-stroke operability, per Position 2.

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES l

CRAIDWOOD STATION UNITS 1 AND 2 l- Revision 7 l

s. Applicable Time Period:

This relief is requested for the first inspection interval..

9. Approval Status:

a. Relief granted per Generic Letter 89-04, Rev. 4/4a.

b. This relief request is being resubmitted based on further experience grained' during nservice testing and inspections, Rev. 5. ,

I

c. Resubmitted for mixed wast r:onsiderations, Rev. 5 Supplement. '

d. Incorporated into Rev. Sa; previously reviewed per OSR 92-017.

e. Pending SER (dated September 14, 1993) Response dated December 13, 1993. Refer to attachment B of response for interim relief requirements.

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IDSERVICE TESTING PROGRAM PLAN.FOR VALVES-CRAIDNOOD STATION IntITS 1 AND 2

-Revision 7

' RELIEF REQUEST VR-3

-l.

Valve Number: ISIB922A/B ,2SI8922A/B

2. Number of Items: 4

3. ASME Code Category: C

~4. ASME Code,Section XI Requirements:

Exercise for operability'(Ct/Bt) of check valves every 3 months, per Iwv-3521.

S. . Basis for Relief:

j These check valves cannot be full flow tested during operation as the shut-off head i of the Safety Injection pumps is lower than the reactor coolant system pressure. l

l. Parformance of this test with the RCS depressurized,, but intact, could lead to i-ir. advertent ~'over-pressurization of the system. The alternate method of protecting' against over-pressurization by partially draining the RCS to provide a surge volume

, is 'not considered a safe practice due to concerns. of maintaining adequate water level above the reactor core.

6. Alternative Testing:

These valves.will be full-stroke tested during refueling. outages as a minimum, but no more frequently than once per quarter.

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7. Justification:

j This alternative will adequately maintain the system l'n a state of operational readiness, while not sacrificing the safety of the plant, by testing the-valves as often as safely possible.

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8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status:

a. Relief granted per NRC Generic Letter 89-04 and SE dated 10/15/91.

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I INSERVICE TESTING PROGRAM PIAN FOR VALVES l LRAIDWOOD STATION UNITS 1 AND 2 Revision 7 ,

)

l RELIEF REQUEST VR-4

1. Valve Number. 1CS003A/B 2CS003A/B ICS008A/B 2CS008A/B

2. Number of Items: 8

3. ASME Code Category: AC and C

4. ASME Code,Section XI Requirements:

, a. Exercise check valves to the position required to fulfill their function j l

(Open/Ct; Closed /Bt), unless such operation is not practical during plant '

operation, per IWV-3522.

l b. When a valve has been repaired, replaced, or has undergone maintenance that could t

affect its performance and prior to the time it is returned to service, it shall be tested to demonstrate that the performance parameters, which could have been affected by the replacement, repair, or maintenance, are within acceptable limits, per IWV-3200. ,

The 1/2CS003A/B check valves are on discharge of the CS pumps and function in the !

j open direction to allow flow from the refueling water storage tank (RWST) to the

spray rings inside containment. They function in the closed direction to prevent t water column separation and reverse rotation of the CS pumps. The 1/2CS008A/B check l valves are the inboard containment isolation valve for the spray header piping and function in the open direction to allow flow. They function in the closed direction .

l to provide for containment isolation, which is a redundant function to the outboard i

! CIV. These valves cannot be full flow tested as a matter of course during unit operation or cold shutdown as water from the CS pumps would be discharged through the CS ring headers causing undesirable effects on many critical components inside l

containment. ,

Additionally, the full flow testing of these check valves during periods of cold :

shutdown, using the CS pumps, would fill the reactor refueling cavity with borated l water from the refueling water storage tank. This would adversely affect the i reactor head components (e.g. Control Rod Drives). Tne filling of the cavity, via !

temporarily installed large bore piping, would require the removal of the reactor vessel head so as to preclude equipment damage from borated water. The erection of temporary piping from the CS line to the reactor cavity would take an estimated nine to twelve shifts, compared to one to two shifts for valve inspection. This estimate does not take into account the time required to drain and remove the piping from containment. Testing in this manner would also require overriding protective electrical interlocks in the pump start circuitry.

l Full flow recirculation flow paths do not exist from the discharge of the CS pumps through these check valves to the refueling water storage tank. The addition of such flow paths would require extensive modifications to existing plant designs: 1 including additional penetrations of the containment boundary, and electrical system l changes to allow for pump start without the need of jumpering out protective

! interlocks.

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I INSERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 l l

RELIEF REQUEST VR-4 I

5. Basis for Relief: (continued)

Partial stroking of the 1/2CS008A/B valves with air using existing LLRT connections does not provide adequate flow to obtain any meaningful acoustic monitoring data, relative to valve condition or its performance parameters. This acoustic testing was attempted at Byron Station per special process procedure, SPP 91-054. l

6. Alternate Testing:

UNIT 1 Group 1 Group 2 ,

1CS003A 1CS008A 1CS003B 1CS008B UNIT 2 Group 1 Group 2 l

2CS003A 2CS008A l 2CS003B 2CS008B Tha A and B train valves are of the same design (manufacturer, size, model number, and l matsrials of construction) and have the same service conditions, including orientation, !

23rofore they form a sample disassembly group.

On2 valve from each group, on a per unit basis, will be examined each refueling outage. If ths disassembled valve is not capable of being manually full stroked exercised or if there i is binding or failure of internals, the remaining valve on the affected unit will be inrpected.

In addition to the above, the 1/2C5003A/B valves will be partial stroke tested during the qu rterly pump surveillance and after maintenance in order to verify that it was installed corrcctly. The 1/2CS008A/B are required to be leak tested before and after visual intp:ction per Appendix J requirements. The leakage test following reassembly of the valve into the system will serve as post-maintenance verification that the valve was installed corrcetly. Partial flow testing the 1/2CS00BA/B following maintenance in not practical for ths game reasons given in the " Basis for Relief" section.

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7. Justification:

Tha 1/2CS003A, B and 1/2CS008A, B valves are removed from the system and visually examined par the strict detailed inspection requirements of the Station Check Valve Program. This l insp2ction adequately verifies that the valves are maintained in a state of operational recdiness and that their performance parameters are adequately assessed. The valves are varified to be functional by perforndng a thorough visual inspection of the internals and by parforming a manual full-stroke exercise of each disc. Previous inspections of these particular valves at both Byron and Braidwood Stations have repeatedly shown them to be in good condition.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES

-ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-4 '!

7. Justification: (continued) i The wafer type design of the valve body for these valves makes their removal.a !

simple process, with little chance of damage to their internals. Also, there is no._ ,

disassembly of internal parts required; all wear surfaces are accessible to visual ;

examination. After inspection and stroke testing, the valve is reinstalled into the i line and post maintenance testing is performed.-The 1/2CS00BA, B valves receive a local leak' rate test per the requirements of 10CFR50 Appendix J, and the 1/2CS003A, B valves are partial flow tested. These tests verify proper installation of the ;

check valves, and the valve inspection procedure-requires post-inspection visual- ;

examination of the check valve to ensure that the pin is oriented properly and that i the flow direction is correct.

The alternate test frequency is justifiable in that main *====a= history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. In addition, industry emperience, as documented in NPRDS, show no history of problems with these valves.

l A company wide check valve evaluation addressing the "EPILI Application Guidelines l for check valves in Nuclear Power Plants" revealed that the location, orientation '

I and application of these valves are not conducive to-the type of wear or degradation ;

! correlated with SOER 86-03 type problems. However, they still require some level of '

monitoring to detect hidden problems.

The alternate test method is sufficient to ensure operability of these valves and is consistent with Generic Letter 89-04. The hardship involved with full stroke ;

exercising these check valves, if the Code requirements were imposed, does not !

l provide a compensated increase in safety of these CS system valves. i

8. Applicable Time Period:

This relief is requested once per. quarter during the first inspection interval.

9. Approval Status:

a. Relief granted per NRC Generic Letter 89-04, Rev. 5.

b. Changed to incorporate acoustic test results, Rev. Sa.

c. Approved per SE dated 9/10/92 with provision.

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i l INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-5

1. Valve Number:

1SI8948A-D 2SI8948A-D (SI Accumulator Check Valves)

ISI8956A-D 2SI8956A-D (SI Accumulator Check Valves)

2. Number of Items: 16

3. ASME Code Category: AC

4. ASME Code,Section XI Requirements:

The purpose of this relief request is to request relief from the 3 month test frequency for the full stroke (CT) and backflow (BT) test as stated in ASME Section XI, IWV-3521: " Check Valves shall be exercised at least once every 3 months, except as provided by IWV-3522."= IWV-3522 states that valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be ,

full-stroke exercised during cold shutdowns.

5. Basis for Relief:

Safety Function The 1/2SI8948A-D and 1/2SI8956A-D check valves are located inside the containment building missile barrier on the lines from the accumulator tanks to the Reactor coolant System (RCS) cold legs. These 16 check valves have safety functions in both the open and closed directions:

1/2SI8956A-D Closed The 1/2SI8956A-D check valves' safety function in the closed direction is to

, maintain the Reactor Coolant Pressure Boundary (k'03). ,

Open ,

The 1/2 SIB 956A-D check valves' safety function in the open direction is to j perndt the injection of borated water into the reactor vessel cold legs during i the passive injection phase of a safety injection.

Basis Check valves 1/2SI8956A-D cannot be tested during unit operation due to the pressure ,

differential between the accumulators (650 psig) and the reactor coolant system I (2235 psig). Full stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system. Exercising ti:ese valves at times other than refueling poses an undesirable situation as discussed in NRC Information Notice 89-67: " Loss of Residual Heat Removal Caused by Accumulator Nitrogen Injection."

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L U l- I INSERVICE TESTING PROGRAM P/AN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 2 Revision'7-

-RELIEF REQUEST VR-5 cont.

=1/2SI8948A-D' 1 Closed . l The 1/2SI8948A-D check valves' safety function in the closed direction is to I provide a redundant (backup to the 1/2SI8956A-D, 1/2SI8818A-D, and 1/2SI8819A-D Reactor Coolant Pressure Boundary (RCPB).

'Open _

The 1/2SI8948A-D check valves'-safety function in the open direction'is to permit the injection of borated water into the RCS cold legs during the_ ,

injection phase of a safety injection.

Basis ,

check _ valves 1/25I8948 cannot be' tested without depressurizing the-RCS to_1600'psig, j (to stroke using Safety, Injection pumps).or to'200 psig (to use the-Residual Heat.

Removal pumps). ,

6. Alternate Testing:

These valves will be backflow tested (BT) ~ on the same schedule as _ the Braidwood station Technical Specifications leakage test as follows.

a. At least once per 18 months,

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 .

hours or more if leakage testing has not been performed in the previous 9 months,

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve,. and

d. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve' actuation due to manual action or flow through the valve.

I Braidwood Station will full stroke exercise-(CT) these check valves each refueling 1 outage and partially stroke the 1/2SI8948. valves during cold shutdowns. ~ The full stroke test will-be accomplished using the pressurizer as afsurge volume and l ~

" burping" the accumulator discharge check valves.- Positive verification of valve operability will be by noting a change in pressurizer or accumulator _ level and by.

the use of acoustic monitoring to confirm full disk-lift by the time-of-arrival a technique. !

.The time of arrival. technique utilizes two sensors, one mounhed at the backstop !

location and the other at the seat location. When the valve full strokes open, the <

disk arm impacts on the backstop (valve body) creating an acoustic event.. This !

acoustic event propagates through the body at a specific velocity based on.the-l material of construction. The sensor at the backstop detects the event first, with 4 the sensor at the seat detecting the event at a'later point in time. This lag or

! time delay between the backstop sensor and the seat sensor represents the time of i L arrival method and is used to demonstrate that the valve full strokes. '

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INSERVICE TESTING FROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-5' cont.

7. Justification:

These sixteen valves are part of the Passive Injection subsystem portion of the j safety injection system. This subsystem is designed to inject borated water into i the-reactor cold legs only after Reactor Coolant System (RCS) pressure has decreased I

below the accumulator nitrogen gas pressure. Under normal plant conditions the RCS system pressure is 2235 psig and the accumulator pressure is 650 psig making passive injection impossible. Therefore, it is not possible to full stroke these valves unless there is rapid depressurization of the Reactor Coolant System.- Full stroke testing (CT) of these valves during operation or at cold shutdown requires depressurization of the RCS. The SI8948 check valves can be partial stroked using

.the RHR pumps during shutdown cooling operations.

Additionally, full stroking these valves during cold shutdowns, routine or forced would impose considerable hardship with no compensating increase in plant safety.

To perform this test, the reactor coolant system (RCS) must be at'approximately 40 psi with all 4 reactor pumps (RCPs) off and accumulator pressure at 100 psi over RCS pressure. Also, at or near end-of-core-life, the boron concentration is low compared to the 1900-2100 ppm concentration of the accumulators. -This injection r test requires that approximately.8 thousand gallons of this boron concentrated water be injected into the RCS. This would result in a' considerable increase in the boron concentration of the RCS. The feed and bleed process required to restore desired RCS boron concentration would result in considerable increasss in testing time and in amounts of radioactive water rejected from the site. The cost of the nitrogen.

required to test these valves is at least $2500, and'although not' quantified, the cost of processing the reactor coolant to restore the optimum boron concentration ,

are not inconsequential.

Successful completion of the seat leakage test will provide positive verification of closure (BT). Therefore, backflow testing these valves on the same schedule as their required Technical Specification leak rate testing will adequately maintain

!. the system in a state of operational readiness.

8. Applicable Status: l This relief is requested once per quarter during the first inspection interval.

9. Approval Status:

l a. Relief granted per NRC Generic Letter 89-04 for Rev.4.

I b. Requesting refueling frequency for the CT exercise test; incorporated the necessary information and justification, Rev. 5.

c. Incorporated additional technical information and justification and acoustic

! time-of-arrival, per Rev. Sa.

d. Approved per SE dated 9/14/93.

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._ _ - . ~ . _ . . _ ._ _ . - _. . . _ . . _ . . ~ _.- . . . ._ ._.__ _ , . .

INSERVICE' TESTING PROGRAM PLAN'FOR VALVES-

.ERAIDWOOD STATION UNITS =1 AND 2 Revision 7.

I 1

' RELIEF REQUEST VR-6

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1. Valve Number: ISIB926 2SI8926 '

2. Number of Items: 2 3.'

ASME Code Category: 'C' i

.)

4. ASME Code,'Section XI Requirements:

! )

Exercise for operability (Ct) of check valves every 3 months, per. INV-3521.

'5. . Basis for Relief:

! fFull stroke exercising of the Safety Injection pump suction check valves,.lSI8926 '

and 2SI8926 cannot be demonstrated during unit operetion as: the reactor coolant system pressure prevents the pumps from reaching. full flow injection conditions.

Performance of this test with the reactor coolant system intact could lead to an

' inadvertent over-pressurization of the system. The-alternate method of. protecting 1

{

against over-pressurization by partial draining of the reactor coolant system to ~

provide a surge volume is not considered a safe practice due to concerns of maintaining ' adequate- water level above the reactor core. ;

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6. Alternate Testing: !

1 The ISI8926 and 25I8926 valves will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode. . Full ^ stroke exercising.. l I

for the valves will be done during refueling outages as a minimum, but no more frequently.than once per quarter.

' Justification:

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This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the. safety of the plant, by testing the valves as often as safely possible.

l 8. Applicable Time Period:

i l

This relief is requested once per quarter during-the first inspection interval.=

l 9. Approval Status:

I a. Relief granted per NRC Generic Letter 89-04.

b. Approved per SE dated 10/15/91.

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES

, CRAIDWOOD STATI E UNITS 1 AND 2 ,

Revision 7

.I RELIEF REQUEST VR-7 i

-DELETED- '

f Deleted relief request VR-7. Incorporated valves formerly covered by VR-7 into l VR-12'and VR-17. ;

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INSERVICE TESTING PROGRAM PIAN FOR VALVES i CRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l l

RELIEF REQUEST VR-8

1. Vai

~ ~ ~ '

Number: ICC685 2CC685 Thermal Barrier Return i 1CC9438 2CC9438 Thermal Barrier Return '

ICC9518 2CC9518 Pressure Relief Check 1CC9413A 2CC9413A Motor / Thermal Barrier Supply ICC9486 2CC9486 Motor / Thermal Barrier Supply j 1CC9414 2CC9414 Motor Bearing Return i 1CC9416 2CC9416 Motor Bearing Return !

ICC9534 2CC9534 Pressure Relief Check j

2. Number of Items: 16

3. ASME Code Category: A, B, and C .

4. ASME Code,Section XI Requirements: l Exercise for operability: full stroke timing and exercising (St) of: Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valves every 3 months per IWV-3411 and IWV-3421, respectively. Per IWV-3412 for power operated i valves, and INV-3522 for check valves, valves that cannot be exercised during plant operation shall be specifically identified-by the owner and exercised during _ cold shutdowns.

l 5. Basis for Relief:

All of the above listed valves function in the closed position to provide a limited r leakage barrier between the containment atmosphere and the environment during '

accident conditions (containment isolation). The isolation valves function in the 1 open position to allow component cooling water flow (monitored by flow sensing i instruments) to the upper and lower RCP motor bearings and to the thermal barrier between the RCS and the RCP mechanical seals. The 1/2CC9518 and 1/2CC9534 check- i valves function in the open direction only when both of the associated containment )

isolation valves (CIVs) are closed during an accident condition involving adverse i containment conditions. Each valve opens in a manner that will bypass the upstream '

isolation valve to relieve excess pressure. This is to prevent hydraulic locking of the associated isolation valves in the closed position; which can be accomplished manually by using the manual vent between the two isolation valves. They are also !

needed for pressure integrity purposes.

Component cooling (CC) water flow to the Reactor Coolant Pumps (RCPs) is required at all times while the pumps are in operation. The failure of one of these valves in a closed position during an exercise test would result in a loss of cooling flow to i the RCPs and possible pump damage and/or trip, which can further lead to disruptions l in RCS pressure control. In addition, the RCPs provide the necessary driving head to the pressurizer spray valves for pressure control in the RCS while a steam bubble exists in the pressurizer during power operation and cold shutdown.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-8

5. Basis for Relief: (continued)

A reactor coolant pump start involves two operations personnel in attendance to monitor and report pump shaft rotation information to the control room. This involves a containment entry, inside the inner missile barrier, which is a high radiation area. The exposure to personnel is dependent on the number of " bumps" !

needed (normally 2-3 bumps at an estimated 9-12 hours) to rid the system of air. j The Code requires that the 1/2CC9518, 1/2CC9534 and the 1/2CC9486 check valves be l tested in the closed direction to verify their seating capability. However, these check valves can only be verified closed by performing the Appendix J, Type C local leakage rate test (LLRT). Performing the LLRT requires placing the system in an inoperable status (removed from service) for an extended period of time due to the need to isolate and drain portions of the system, and connecting a leak rate monitor (LRM). This will prevent starting the RCPs and could delay reactor startup. These d

tests will require a minimum of three shifts each to perform.

This would cause undue hardship with no compensating increase in plant or component safety, if the Code requirements were imposed. ,

1

6. Alternate Testing:

i The isolation valves will be stroked on a refueling frequency or at planned cold {

shutdowns when all four RCPs are no longer required to support plant conditions and !

can be removed form service. The RCPs will not be shutdown for the sole purpose of stoke tindng the isolation valves.

Check valves 1/2CC9486 (total) CC supply flow to the RCPs will be back flow tested (Bt) closed on the same frequency as their Appendix J seat leakage test. The 1/2CC9518 and 1/2CC9534 pressure check valves will be exercised and back flow tested (Ct/Bt) each refueling outage in conjunction with their associated Appendix J seat leakage test. This frequency is at least once per two years, to be performed during reactor refueling outages.

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7. Justification: 1 This alternate testing will adequately maintain these portions of the CC system in a state of operational readiness, while not impacting the safety of the plant. It also eliminates unnecessary personnel radiation exposure, possible damage to the RCP seals, and minimizes the potential RCS pressure transient involved with restarting j RCPs at low temperatures.

Back flow testing f i a check vaaves on the same schedule as their Appendix J 1eakage test will te.quately so.ntain this portion of the CC system in a state of operational readiness without causing unnecessary personnel radiation exposure, possible damage to the RCPs or delays in reactor startup. In addition, the Code only requires a five year frequency for pressure relief testing.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES l CRAIDWOOD STATION UNITS 1 AND 3 Revision 7 RELIEF REQUEST VR-8 !

7. Justification: (continued) i Performance of leakage testing on a two year (refueling) frequency is adequate to !

demonstrate structural integrity and valve seating capability per both Appendix J '

and ASME Section XI requirements.

There is no reason to perfonn the Appendix J, Type C (low pressure air at I approximately 45 psig) seat leakage test more often than that already required by 10CFR50. This low pressure air test is adequate to monitor the valve's ability to seat; the smallest amounts of dirt, general corrosion, and foreign material can be l detected between the seating surfaces by this test.

l

! Perforndng an LLRT to prove valve closure would only draw manpower away from the j task at hand, and could hamper attempts to restart the unit. An LLRT requires l personnel involvement from operations (valve manipulations and out of services),

i radiation protection (radiation surveys and monitoring), instrument maintenance (installation of test equipment), and technical staff (LLRT test equipment operation and test supervision) that results in increased exposure. This excess exposure conflicts with station ALARA goals and radiation work practices. For these reasons,

! performing an LLRT to verify valve closure is considered to be impractical during l cold shutdown.

Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and radiation practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set. The performance of this test would require a minimum of three (3) shifts with personnel working in a high radiation area. In addition, l

performing the LLRT test on a more freque at basis has an adverse impact on the required test equipment (LRMs).

The leak rate monitors (LRM) used for Ty C LLRTs are required to be shipped off-site for calibration. During operat on and cold shutdown when containment integrity is set, the LRM(s) would need so be taken inside the containment. If the J LRM is contaminated and then unable to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of ,

monitors available for use is limited. During refueling outages, a staging area is j set up outside containment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. This is possible due to the relaxed containment integrity requirements. These precautions are taken to prevent the LRMs from becoming contaminated.

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i I' 4SERVICE TESTING PROGRAM PLAN FOR VALVES l

CRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 1

i

( RELIEF REQUEST VR-8

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status.

a. Relief granted per NRC Generic Letter 89-04.

b. Requesting additional relief for valves 1/2CC9518 & 1/2CC9534, Rev. 5.

c. Added additional technical information and justification, Rev. Sa.

d. Approved by SE dated 9/14/93.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ;

BRAIDWOOD STATION UNITS 1 AND 2 ;

Revision 7 i

RELIEF REQUEST VR-9 )

1. Valve Number: 1CV8100 2CV8100 RCP Seal Water Return 1CV8112 2CV8112 RCP Seal Water Return ICV 8113 2CV8113 Pressure Relief Check l

l 2. Number of Items: 6 1

3. ASME Code Category: A and AC l

4. ASME Code,Section XI Requirements: '

l Exercise for operability: full stroke timing and exercising (St) of Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valves every 3 months per IWV-3411 and IWV-3421, respectively. Per IWV-3412 for power operated valves, and IWV-3522 for check valves, valves that cannot be exercised during plant operation shall be specifically identified by the owner and exercised during cold shutdowns.

! 5. Basis for Relief:

l l

All of the above valves function to provide for a limited leakage barrier between the containment atmosphere and the environment during accident conditions (containment isolation). Their open function is to allow a return path for filtered seal water flow for cooling and flushing to the RCP mechanical seals during plant 1 operation. During startup and shutdown, the pressure in the RCS is too low to maintain the gap across the number 1 seal. Under such conditions, the number 1 seal bypass flow is established which assures adequate cooling of the pump's lower radial l bearing and limits the temperature rise of water cooling the number 1 seal. The l 1/2CV8113 pressure relief check valves function in the open position only when both of the associated containment isolation valves (CIVs) are closed during an accident condition involving adverse containment conditions. Each valve opens in a manner that will bypass the upstream isolation valve to relieve excess pressure. This is to prevent hydraulic locking of the associated isolation valves in the closed position; which can be accomplished manually by using the manual vent between the two isolation valves. They are also needed for pressure integrity purposes.

These valves cannot be tested during unit or pump operation as seal water flow from the CV system is required continuously while the reactor coolant pumps are in operation. Loss of flow could result in damage to the seals from overheating and contamination by foreign material. Also, failure of one of these valves in the closed position during an exercise test would result in seal water return flow being diverted to the PRT by lifting a relief valve upstream of the isolation valves, generating significant quantities of liquid radwaste. The RCPs are also needed to provide the driving head to the pressurizer spray valves for pressure control in the RCS while a steam bubble exists in the pressurizer during power operation and cold shutdown.

A reactor coolant pump start involves two operations personnel in attendance to monitor and report pump shaf t rotation information to the control room. This involves a containment entry, inside the inner missile barrier, which is a high radiation area.

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l INSERVICE TESTING Pamann PLAN POR VALVES -

CRAIDWOOD STATION UNITS 1'AND 2~

Revision 7 i

RELIEF REQUEST VR-9 !

't

5. Basis for Relief: (continued)

The exposure 'to personne1' is dependent on the number of = "busps" needed (normally 2-3 !

bumps estimated at an 8-12 hours) to rid the system of air. ;

The closure test for the 1/2CV8113 (seal return pressure relief check valves)_can.

only be verified by performing a local leakage rate test (TLRT). Performing this test requires placing the system in an inoperable status,tisolating the seal return line portion of piping, and connecting an external pressure supply. This test will '

require a minimum of two shifts to perform. 'The opening test requires isolating l l both the inboard motor and manual isolation valves and running =a. centrifugal. q l charging pump on mini-flow recirculation to supply pressure 'for oper.ing the valve. !

L The inboard manual vent is opened to verify that the check valve is capable of ,

relieving pressure.. This would require.a minimum'of I shift to perform.

6. Alternate Testing:

)

[ The 1/2CV8113 and 1/2CV8112 isolation valves will be stroked on a refueling. .

frequency or at planned cold shutdowns when all. four RCPs tare no longer required to - -

!. support plant operations and can be taken out of service. .The RCPs will'not be :)

shutdown for the sole purpose of stroke-timing the isolation valves' l

The 1/2CV8113 pressure check valves.will be exercised.and back flow (Ct/Bt)' tested each. refueling outage in conjunction with their associated Appendix J 1eakage rate test. 'This frequency is at least once per two years,'to be performed during each' ,

reactor refueling outage. '

! . Justification:

This alternate testing will adequately maintain this portion of the CV system in a state of operational readiness, while not. impacting the safety of the plant. It t l

also eliminates unnecessary personnel radiation exposure, possible damage to the RCP l seals, and minimizes the potential RCS pressure transient; involved with restarting !

RCPs at low temperatures.

'Back flow testing these check valves on the same schedule as their Appendix J' leak i rate test will adequately maintain this portion of the CV system in a state'of !

operational readiness without causing unnecessary personnel radiation exposure, delays in reactor startup or possible damage-to the RCPs. In addition, the Code-l

j. only requires a five year frequency for pressure relief. testing. l Performance of. leakage testing on a two year-(refueling) frequency is adequate to-demonstrate structural integrity and valve seating capability per both Appendix J-and ASME Section XI requirements. There is no reason to perform the Appendix J, '

Type C (low pressure air at approximately 45 psig)' seat leakage test more often than

..that already required by 10CFR50. This low pressure air test is adequate to monitor the valve's ability to seat; the smallest amounts of dirt, general corrosion,.and' foreign material can be detected between the seating surfaces by this test.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES 1 ERAIDWOOD STATION UNITS 1 AND 2 i Revision 7 l

RELIEF REQUEST VR-9 l

1

7. Justification: (continued)

During forced outages, limited manpower and resources are available to perform the i j necessary prerequisites involved with an LLRT. Performing an LLRT to prove valve :

closure would only draw manpower away from the task at hand, and could hamper !

attempts to restart the unit. An LLRT requires personnel involvement from operations (valve manipulations and out of services), radiation protection l,

~

(radiation surveys and monitoring), instrument maintenance (installation of test equipment), and technical staff (LLRT test equipment operation and test supervision) i that results in increased exposure. This excess exposure conflicts with station JdJJUL goals and practices.

For these reasons, performing an LLRT to verify valve !

j closure is considered to be impractical during cold shutdown.

1 1 Quarterly and cold shutdown testing requires a containment entry which would ,

, conflict with station ALARA goals and radiation practices in reducing nan-rom, and '

] it is not prudent from a personnel safety standpoint. For personnel safety

considerations, two individuals must always enter containment together, whenever i containment integrity is set. The performance of this test would require a minimum

of three (3) shifts with personnel working in a high radiation area. In addition, t performing the LLRT test on a more frequent basis has an adverse impact on the

j. required test equipment (LRMs).

4 i The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped

, off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the a

LRM is contaminated and then unable to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of

monitors available for use'is limited. During refueling outages, a staging area is ;

i set up outside containment in a low dose, non-contaminated area and hoses are run '

] inside to the various containment isolation valves. This is possible due to the j relaxed containment integrity requirements. These precautions are taken to prevent j the LRMs from becoming contaminated.

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8. Applicable Time Period

1

'This relief is requested once per quarter during the first inspection interval.

] 9. Approval Status:

1 i a. Relief granted per NRC Generic Letter 89-04.

i b. Requesting additional relief for the 1/2CV8113 check valves, Rev. 5.

4 i c. Added additional technical information and justification, Rev. Sa.

J l d. Approved by SER dated 9/14/93.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-10

1. Valve Number: IIA 065 2IA065 Outbd Instrument Isolation IIA 066 2IA066 Inbd Instrument Isolation IIA 091 2IA091 Inbd Isolation Supply Check l

2. Number of Items: 6

3. ASME Code Category: A and AC

4. ASME Code,Section XI Requirements:

Exercise for operability: full stroke timing and exercising (St) of Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valves.every 3 l months per IWV-3411 and IWV-3421, respectively. Per INV-3412 for power operated l valves, and IWV-3522 for check valves, valves that cannot be exercised during plant l operation shall be specifically identified by the owner and exercised during cold shutdowns.

Fall-safe test actuators per IWV-3415.

5. Basis for Relief:

1 The 1/2IA065 and 1/2IA066 valves are air-operated containment isolation valves for i the instrument air line to containment; they fail closed on loss of air l supply / power. The 1/2IA091 check valves are in the supply air line to the 1/2IA066 1 valves, which taps off the line between the two isolation valves. These check valves also perform a containment isolation function in the closed position.

Stroke testing of these valves during plant operation or cold shutdown would, by design, isolate the air operated instruments and valves inside the containment j building. The loss of instrument air to containment creates a very serious i situation and should be avoided for testing purposes. This situation involves loss of pressure control via the sprays, letdown isolation, and loss of charging flow.

l Additionally, loss of air would leave the pressurizer PORVs with only their accumulators as an air supply, limiting the number of operations available.

l

6. Alternate Testing:

, These valves will be exercised during refueling outages. The back flow (Bt) test for the 1/2IA091 check valves will be done in conjunction the Appendix J seat leakage test.

l This testing period will be each refueling outage as a minimum, but no more i frequently than once per quarter.

7. Justification:

l The full stroke exercising of the instrument air containment isolation valves during

! unit power operations or cold shutdowns introduces the possibility of causing major '

l operating perturbations and/or personnel safety concerns during the test.

I Additionally, should these valves fail to re-open during testing activities, the transient would be exacerbated.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-10

7. Justification: (continued)

The failure of these valves in the closed position, as a result of testing l activities during plant operation or cold shutdown,;would subsequently isolate the j mir operated instruments and valves inside the containment building thus resulting )

in one or more of the following scenarios:

A. Loss of Pressuriser Pressure control The pressurizer spray valves 1/2RY455B & C and the pressurizer auxilisry spray valve 1/2CV8145 would fail closed and not be available for pressurizer pressure cuntrol.

B. Loss of chemical volume control system Letdown riow (both mozual and emoess) and charging riov The loss of instrument air would cause a disruption in the unit letdown flow i

paths resulting in pressurizer level increases. Such valves as the letdown l

orifice containment outlet header isolation valve 1/2CV8160, the letdown line isolation valves 1/2CV459 and 1/2CV460, the letdown orifice outlet isolation:

valves 1/2CV8149 A, B & C, the excess letdown heat exchanger inlet isolation valves 1/2CV8153A & B, and the regen heat exchanger letdown inlet isolation valves 1/2CV8389A & B would go to their fail closed positions. Additionally, the ability to normally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal boration/ dilution) would also be lost as the regenerative heat exchanger inlet isolation valves 1/2CV8324A & B would fail to their respective closed positions.

An additional detrimental effect would be the thermal cycle imposed on the i reactor vessel nozzle upon restoration of system operation.

C. Loss of component cooling to containment penetrations The loss of instrument air supply would cause the penetration cooling supply flow control valve 1/2CC053 to go to its fail closed position. . The loss of penetration cooling would result in elevated temperatures being imposed on the penetrations being supported by the component' cooling system.

D. Loss of personnel areathing Air l

The loss of instrument air supply to the service air downstream isolation valve 1/2SA033 would cause this valve to go to its fail closed position. This loss of service air in the containment building would eliminate the normal. source of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated radiological environment.

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES . ,

BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-10

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval. *

9. Approval Status:

a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321).

b. Added check valves 1/2IA091, regarding back flow testing. Rev. 5.

l

c. Added additional technical information and justification, Rev. Sa.

d. Approved per SE dated 9/14/93. ,

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INSERVICE TESTING PROGRAM PLAN FOR VALVES-BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 i

RELIEF REQUEST VR-11 l

-DELETED- i J

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Deleted relief request VR-11 per EG&G Idaho (Technical Reviewers) reconunendation to l Byron. This was a request for extension of position indication tests from every two j years to every three years. '

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-12

1. Valve Number: Valves that normally stroke in 2 seconds or less as identified in '

Braidwood Station Test Procedures.

2. Number of Items: As applied in Test Procedures.

3. ASME Code Category: A&B

4. ASME Code,Section XI Requirements:

Verification, by trending of power operated valve times, that an increase in stroke time of 50% or more, fram the previous test,' does not occur, per IWV-3417 (a) .

5. Basis for Relief:

' Minor timing inaccuracies, with small stroke times can lead to substantial increases (percent wise) in stroke times. For example, a valve with a stroke time of 1 second in an initial test, and 1.6 seconds in the subsequent test, has experienced an apparent 60% increase in stroke time. If the accuracy requirements of IWV-3413(b) are utilized, it could be argued that stroke times between 1.and 2 seconds could constitute as much as a 100% increase in stroke time when, in fact, only a 0.2.

second increase occurred. For instance, if the initial time was 1.4 seconds, (measured to the nearest second is 1.0 second) and if the next time is then 1.6 seconds, (measured to the nearest second is 2.0 seconds) the percent-increase is 100%.

l l 6. Alternate Testing:

Fast acting valves can be. defined as those valves that normally stroke in 2 seconds or less. No trending of stroke time will be required, and upon exceeding 2 seconds, corrective action shall be taken immediately in accordance with IWV-3417 (b) . Valves classified as rapid-acting shall be chosen at the station's discrestion and should be identified in the IST Program Plan Valve Tables or in Station Test Procedures.

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REOUEST VR-12

7. Justification:

For short stroke times, the trending requirements are too stringent for the -

accuracies specified in the Code. The alternative specified will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.

l GL 89-04, position 6 will be followed for any valve which has the 2 second maximum stroke criteria applied.

8. Applicable Time Period:

j This relief is requested once per quarter, during the first inspection interval.

9. Approval Status:

a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321).

b. Relief granted per NRC Generic Letter 89-04.

c. Approved per SE dated 10/15/91.

d. Revised to allow implementation for any valve selected at the station's discretion, as granted per GL 89-04.

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES j CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 l

l RELIEF REQUEST VR-13 i

1. Valve Numbers: 1DG5182A,B 2DG5182A,B 1DG5183A,B 2DG5183A,B 1DG5184A,B 2DG5184A,B 1DG5185A,B 2DG5185A,B

2. Number of Items: 16 l

3. ASME Code Category: B&C

4. ASME Code Section XI Requirements:

j These valves are not within the scope of ASME Code,Section XI, Subsection IWV !

requirements. However, the requirements for stroke timing and trending of the i valves associated with the Diesel Air Start System are being mandated by the NRC as l an augmented testing requirement pursuant to'10CFR50.55 (a) (g). l l Therefore, valves associated with the Diesel Air Start System shall be exercised to the position required to fulfill their function during plant operation per IWV-3412 i and IWV-3522. Additionally, the stroke testing of power operated valves shall be measured to the nearest second and such stroke times trended to document continued valve operational readiness per IWV-3413 (b) and INV-3417. l 1

5. Basis for Relief:

The monthly Diesel Generator testing program, outlined in Braidwood Station's l Technical Specifications and implemented by station operating procedures, exceeds <

the intent of the quarterly valve testing program which would be required by ASME l Code,Section XI. Additionally, the stroke timing of-solenoid operated valves l associated with the Diesel Air Start System is impractical due to the fast actuation i of these valves.

I

! 6. Alternate Testing:

The performance of Braidwood Station's Diesel Generator operability monthly surveillance will verify the operational readiness of_the valves associated with the Diesel Air Start System.

i This surveillance testing will require the recording of the air pressures contained in both trains A & B of the Diesel Generator Air Start Receiver Tanks both before and immediately after Diesel Generator start.

By the comparison of these valves between trains, the satisfactory operation of the <

power operated and self-actuated check valves associated with the Diesel Air Start l System can be adequately demonstrated. l l

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1.

INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 ,

Revision 7 RELIEF REQUEST VR-13

7. Justification:

Proper valve operation will be demonstrated on a monthly basis by the verification of Diesel Generator air start capability. Such verification will compare the air pressures contained in the receiver tanks both before and after the Diesel Generator j start, thus verifying the operability of the air start control valves. The proposed. !

testing amthodology at the increased frequency satisfies the intent of the section XI requirements without posing undue hardships or difficulties.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval. i

9. Approval Status:

a. Relief granted NRC Generic Letter 89-04. *

b. Approved per SE dated 10/15/91.

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r INSERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-14

-DELETED-Deleted relief request VR-14. This was a request for exemption for position indicating tests for solenoid operated valves. Alternate testing allowed by the ASME Code will be used instead.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-15A

1. Valve Numbers: ICV 8481A,B 2CV8481A,B CV Pmp Dsch ICV 8546 2CV8546 CV Pmp Comb Suction ISI8815 2SI8815 CV Inject comb Hdr ISI8900A-D 2 SIB 900A-D CV Cold Leg Inject

2. Number of Valves: 16

3. ASME Code Category: AC

4. ASME Code,Section XI Requirements:

Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full stroke (Ct) and backflow (Bt) tests for the above check valves as required by paragraphs IWV-3521 and IWV-3522.

5. Basis for Relief:

Safety Punction 1/2SI8815 Open l This valve is in the line from the chemical and Volume Control (CV) l Centrifugal Charging pump. Its safety function in the open direction is to permit flow of coolant from the centrifugal charging pump to the four lines which branch off and provide flow to the reactor cold legs during the high pressure injection phase of a safety injection.

Closed The safety function of this valve in the closed direction is to provide a redundant (back up to the 1/2SI8900A-D check valves) reactor coolant system pressure boundary (PIV).

1/2SI8900A-D Open These valves are in the four lines which branch off from the lines containing the 1/2SI8815 valves mentioned above. Their safety function in the open direction is to permit flow of coolant from the chemical and volume control centrifugal charging pumps to the reactor cold legs during the high pressure injection phase of a safety injection.

Closed The safety function of these valves in the closed direction is to provide a reactor coolant pressure boundary.

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ICSERVICE TESTING P m m PLAN FOR VALVES :f' BRAIDWOOD STATION UNITS 1 AND,2.

Revision 7 RELIEF REQUEST VR-15A'(continued) y 1/2CV8481A,B Open . .

These check valvesLare located at the discharge of the chemical and Volume-Control charging pump. Their function-is'to prevent reverse flow from the charging header when the~ pump is not in operation. The safety function in the ,

open position is to permit flow of coolant during a' safety injection. !

1/2CV8546 Apen, . .

l This check valve is the cambined suction of the charging pumps from the Refueling Water Storage. Tank (RNST).- .Their function is to prevent flow from the suction header. The safety function in the open position is to permit flow of coolant when the charging pumps,take suction from the PNST during a safety injection. !

~ Basis . . ,

The full stroke exercising of check valves 1/25I8815 and 1/2SI8900A-D associated with the Emergency Core Cooling System during operation would induce: thermal stresses on their respective reactor vessel nozzles ~as the Reactor Coolant System (maintained at greater than 500 'F) is injected with water fram the Refueling. Water.

Storage Tank (maintained at approximately 65'F) . _ The 1/2CV8481A,8 and.1/2CV8546 check valves are in series and cannot be full stroke. exercised without causing stroking of 1/2SI8815 and 1/2 SIB 900A-D.

These valves cannot be exercised during cold shutdowns without' increasing the ,

, possibility of low temperature' over-pressurization (LTOP) L of the Reactor. coolant System. The Braidwood Station. Technical Specifications requires.that all. Safety

~

Injection Pumps and all but one Charging Pump be inoperable during Modes 4, 5 and 6,

- except when the reactor vessel head is removed to prevent this over-pressurization occurring while at low temperatures. In addition, injecting large quantities of highly borated water from the RNST would likely delay reactor start up and the cost of processing the reactor coolant to restore the optimum boron concentration are not inconsequential.

The 1/2SI8900A-D and 1/2SI8815 check valves can only'be verified closed by performance of an individual leakage test on each valve. These valves are simple lift check valves and are not equipped with an external: operator or disk position indication. .It is impractical to verify them closed during power operation or during cold shutdowns. System reconfiguration and connecting and disconnecting leak testing equipment during cold shutdowns would likely delay the return to power.

This would be costly and burdensome to the station. System redesign and modification would be necessary~to allow testing these valves closed. quarterly, which would also be costly and burdensome. Both of these alternatives would provide no compensating increase in plant safety.

6. Alternate Testing:

Braidwood Station will full stroke exercise (open--Ct; close--Bt) the 1/2SI8815 and I 1/2SI8900A-D on a' refueling frequency test schedule. These. valves are verified closed in conjunction with the Technical Specification pressure isolation-valve ,

leakage test. J Check valves 1/2CVB481A, B; 1/2CV8546'cannot'be full stroke exercised without l causing stroking of 1/2SI8815 and 1/2SI8900A-D, therefore they will be full stroke- l exercised on the same schedule (refueling frequency) as the 1/2SI8815 and 1/2SI8900A-D valves.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-15A (continued)

7. Justification Based on the guidance provided in question 24 of the "Public Meeting notes on Generic Letter 89-04": check valves possessing safety functions in both the open and closed direction should be stroked to the open position and then tested in the closed position. For the 1/2SI8815 and 1/2SI8900A-D valves, it is best to perform the backflow (Bt) test, which in this case is accomplished in conjunction with the leakage test (Lt), on the same frequency as the full flow (Ct) test, thus testing them to their open position and then to their closed position.

Check valves 1/2CV8481A, B and 1/2CV8546 cannot be full stroke exercised without causing stroking of 1/2SI8815 and 1/2SI8900A-D because of the system configuration.

l Therefore, 1/2CV8481A/B will be full flow (Ct) and backflow (Bt) tested in conjunction with the 1/2SI8815 and 1/2SI8900A-D full flow test (B. train backflow tested during A train full flow and vice versa) . The 1/2CV8546 will also be full flow (Ct) tested in conjunction with the full flow test of the 1/2SI8815 and 1/2SI8900s.

In addition, the high pressure (from CV pumps) safety injection check valves will have their seat tightness demonstrated during the Braidwood Station Technical Specification testing required to verify the pressure isolation capability of these i

valves under the following conditions:

a. At least once per 18 months.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not haen performed in the previous 9 months.

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and

d. Within the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to manual action or flow through the valve.

The alternate test frequency will adequately maintain this portion of the safety injection system in a state of operational readiness, while not sacrificing the safety of the plant, by testing these check valves at each refueling outage, when the safety risks are minimal.

8. Applicable Status:

i l This relief is requested for the first inspection interval.

9. Approval Status:

a. Approved per SE dated 10/15/91.

b. Approved per SE dated 9/14/93.

c. Rev. 6 - Reorganized to indicate:

1) Safety function of all valves

2) Full-stroke and backflow tests.

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l IN ERVICE TESTING PROGRAM PLAN FOR VALVES aRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l

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RELIEF REQUEST VR-15B l i

1. Valve Number: 1RH8705A,B 2RH8705A, B RH Suction Isolation Thermal / Pressure Relief l i

2. Number of Valves: 4

)

3. ASME Code Category: AC

4. ASME Code,Section XI Requirements:

Relief is requested from both the quarterly and cold shutdown exercise frequencies i for the full stroke (Ct) and backlow (Bt) tests for the above check valves as l required by paragraphs Iwv-3521 and IWV-3522.

5. Basis for Relief:

1 l Safety Punction l 1/RH8705A, B .

! Open .

l These valves are located on the 3/4" branch line between the' 1/2RH8701A, B and 1/2RH8702A, B RH suction isolation valves. Their safety function in the open direction is to relieve excess pressure due to thermal expansion back to the RCS when both suction isolation valves are closed in order to prevent over pressurization of the piping.

Closed The safety function of these valves in the closed direction is to maintain the integrity of the reactor coolant pressure boundary, hence, pressure isolation ,

valve (PIV). '

The 1/2RH8705A, and 1/2RH8705A, B thermal / pressure relief check valves can only be verified closed by performance of an individual leakage test on each valve.

These valves are simple spring loaded lift check valves and are not equipped with l an external operator or disk position indication. It is impractical to verify them closed during power operation or during cold shutdowns. System reconfiguration and connecting and disconnecting leak testing equipment in conjunction with depressurizing the RCS during cold shutdowns would delay the return to power. . This would be costly and burdensome to the station. System redesign and modification would be necessary to allow testing these valves closed l quarterly, which would also be costly and burdensome.

6. Alternate Testing:

The 1/2RH8705A/B check valves will be operability tested in the open direction by verifying that the piping between the suction isolation valves is able to be depressurized through the applicable valve. The PIV leakage test will be used to j verify valve closure and seat tightness. Both of these (Ct-open, Bt-closed) tests ;

will be performed at each reactor refueling outage. l 4.6 - Page 36 of 70 (03/14/95) o:\DEPTS\ZD79G\217.wpf/104

INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 ,

Revision 7 l RELIEF REQUEST VR-15B

7. Justification Performing the exercise test requires placing the standby train of residual heat removal (RHR) in an inoperable condition and that the RCS be depressurized (requires ,

all four reactor coolant pumps to be stopped). This will delay reactor start up and j l return to power. In addition, taking away the back/ redundant train of RHR reduces l both the plant decay removal capability and the available safety margin regarding l shutdown risk assessment. Furthermore, these valves are also given specific )

! exemption from being leakage tested (no closure test required) following flow '

through the suction isolations per Technical Specifications (regarding PIV testing.)

This alternate test frequency is adequate to a maintain this portion of RHR in a state of operational readiness, while not sacrificing the safety of the plant, or causing undue hardship in returning to power with no compensated increase in safety.

l

8. Applicable Status:

1 This relief is requested for the first inspection interval.

9. Approval Status:

a. Approved per SE dated 9/14/93.

b. Rev. 6 - Reorganized to indicate:

1

1. Safety function of all valves. l

2. Full stroke and backflow tests. !

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4 INSERVICE TESTING PROGRAM PLAN FOR VALVES i BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-15C

1. Valve Number: 1SI8819A-D 2SI8819A-D SI Cold Leg Inj ISI9805A-D 2SI8905A-D SI Hot Leg Inj 1 SIB 949B,D 2 SIB 949B,D SI/RH H(t Leg Inj '

2. Number of valves: 20 n 1

3. ASME Code Category: AC j 4. ASME Code,Section XI Requirements:

Relief is requested from both the quarterly and cold shutdown exercise frequencies for the full stroke (CT) test and backflow (BT) test as stated in ASME Section XI' j INV-3521: " Check Valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

5. Basis for Relief

Safety' Function 1/2SI8819A-D Open ,

These valves are located in the lines going from the safety Injection pumps to the reactor vessel cold legs. Their safety function in the open direction is i to permit flow of coolant to the reactor cold legs during a safety injection.

Clesed The safety function of these valves in da M osed direction is to maintain the

, reactor coolant system pressure boundary (PIV). !

i 1/2SI8905A-D '

Open The safety function of this valve in the open direction is to permit flow of J

coolant from the Safety Injection pump to the reactor vessel hot legs during ,

l the Hot Leg Recirculation portion of a safety injection, j i

Closed l

The closed safety function of this valve.is to maintain the reactor coolant '

pressure boundary. l

1/2SI8949B,D !

l Open The safety function of this valve in the open direction is to permit flow of coolant from the' Safety Injection pumps to the reactor vessel hot legs during I the Hot Leg Recirculation portion of a safety injection.

Closed The closed safety function of these valves is to maintain the reactor coolant pressure boundary.

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I IISERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 ;

Revision 7 RELIEF REQUEST VR-15C (continued)

5. Basis for Relief: (continued)

These valves cannot be full stroke exercised during operation or during routine Mode 5 cold shutdowns due to Braidwood Station Technical Specifications requirement that all Safety Injection Pumps and all but one Charging Pump be inoperable during modes 4, 5, and 6 (temperature less then 350' F), except when the reactor vessel head is removed (the reactor head is only removed during refueling outages). This requirement minimizes the possibility of low temperature over-pressurization (LTOP) of the Reactor Coolant System (RCS).

6. Alternate Testing:

Full stroke exercising of these valves can only be safety performed in Mode 6 with the Reactor vessel head removed. Therefore, full stroke exercising and backflow testing of these valves will be performed at each refueling outage.

! 7. Justification:

These check valves cannot be stroked during cold shutdown without exceeding Technical / specification limiting condition for operation (LCO 3/4.5.3). Since stroking these valves requires starting an SI pump. Stroke exercising check valves 1/2SI8819A-D, 1/2SI8905A-D, and 1/2SI8949B,D during each reactor refueling outage, will insure compliance with Braidwood Station Technical Specification and will l reduce the risk of low temperature over-pressurization of the Reactor Coolant System.

. Applicable Status:

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This relief is requested for the first inspection interval. i

9. Approval Status:

a. 01/15/91 - Relief for full stroke granted per SER

]

b. Approved per SE dated 9/14/93. I

c. 01/01/93 - Reorganized to indicate:

l 1) Safety Punction of all valves.

2) Backflow test for valves 1/2SI8819A-D, 1/2SI8905A-D, and 1/2SI8949B,D.

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. INSERVICE TESTING PROGRAM PIAN FOR VALVES BRAIDWOOD STATION UNITS 1-AND 2 Revision 7 l

RELIEF REQUEST VR-16 1.. Valve Numbers: '1SI8811A, B 2SI8811A, B-2.1 Number of Valves: 4 l l

l '3. -ASME Code Category: B i

.'4. ASME Code,Section XI Requirements:

Valves that cannot be exercised during plant operation shall be:specifically-identified by the owner and shall-be full stroke exercised.during cold shutdowns per. ,

-IWV-3412. -1

! 5. ~ Basis for ' Relief: ;

l L =The full stroke exercising of valves not stroked quarterly is required.to be .

i j performed during ccid shutdowns. However, the stroking of the Containment.-Sump.- i

' Outlet Isolation-Valves,.1/2SI8811A,B requires the. suction of the Residual: Heat. '

Removal Pumps to.be drained, thus rendering one train of the system inoperable.

For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of~

1 Residual' Heat' Removal declared inoperable,:Braidwood Station's Technical:

Specifications require two steam generators with a secondary' side. narrow range water- ;

level greater than 41% L (Unit 1) and greater than.18% (Unit 2) . However,,if the cold i shutdown was necessitated by a problem requiring draining of the secondary side of !

[ the Steam Generators.(i.C. tube leaks), Braidwood Station's Technical Specification' ,

i- 3.4.1.4.1 would preclude the testing of the . containment sump. outlet isolation valves : '

i until such time as the affected steam generators had been refilled.

! ' For Cold shutdown operations with the Reactor Coolant Loops not" filled- (i.e; drained - !

down to support Reactor Vessel Incore Seal Table, Loop Stop Valve, Reactor Coolant -

Pump and Seal. Maintenance or primary leakage), Braidwood Station's Technical .

l Specification 3.4.1.4.2 would preclude the testing of the containment Susp Outlet ,

Isolation Valves as it mandates that "two residual heat. removal-'(RHR) Loops shall be operable and at least one RHR Loop'shall be in operation.

6. Alternate Testing:

! Braidwood Station will full stroke exercise the Containment Sump Outlet Isolation '

i. Valves, 1/2 SIB 811A, B during refueling outages vice cold shutdown.

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$ INSERVICE TESTING PROGRAM PLAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 l RELIEF REQUEST VR-16 4 7. Justification:

The full stroke testing of the 1/2SI8811A, B valves; in conjunction with system draining, filling and venting of each train, accounts for an additional six days (3 days per train) of scheduling requirements and increased radiation dose to operators

and radiological control personnel. Processing of thousands of gallons of contaminated water, and subsequent required liquid effluent discharges would also result from the draining, refilling and venting of the RHR system. This time

! duration required to perform the surveillance testing of the Containment Sump Outlet Isolation Valves during Cold Shutdown activities, could, as a result, cause a violation of the action requirements for Braidwood Station's Technical 4 Specifications 3.4.1.4.1 and 3.4.1.4.2. The violations would occur since these action statements require (as noted in their respective foot note sections) the return of the inoperable residual heat removal loop to service within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , if such loop was removed for surveillance testing provided the other RHR Loop is operable and in operation.

In addition, NRC Generic Letter 88-17, Loss of Decay Heat Removal, highlights the consequences of a loss of RH during reduced Reactor Coolant System inventory (below three feet below the reactor vessel flange). If the operating RH pump is lost due to air entrainment, and the other train is inoperable for the stroke test, then the

" operable" train must be vented to restore decay heat removal. Under worst conditions, boiling in the core would occur in approximately 10 minutes, the core

, would be uncovered in approximately 30 minutes, and fuel damage would occur in approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Given the apparent disparity between the Technical Specification time requirements for an inoperable RHR Loop return to service (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and the time required to perform surveillance stroke testing of the containment Sump Outlet Isolation valves (3 days) during Cold Shutdown, the proposed alternate testing frequency of refueling outage periodicity will adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.

j 8. Applicable Time Period:

1 2

This relief is requested once per quarter, during the first inspection interval.

9. Approval Status:

4

a. Revised (to address NRC concerns) in Byron's response to SER 12/16/90.

b. Approved per SER dated 10/15/91.

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~ ICSERVICE TESTING PROGRAM PLAN FOR VATNES l BRAIDWOOD' STATION UNITS 1 AND 2 Revision 7

, RELIEF REQUEST VR-17 l 1 I

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l INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-18 DelGted per Revision Sa. Valves are passive and only require leak testing per IWV-3700.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES.

ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-19 l

1. Valve Numbeers: 1AF001A 2AF001A 1AF001B 2AF001B

2. Number of Valves: 4

3. ASME Code Category: C

4. ASME Code,Section XI Requirement:

Exercise check valves to the position required to fulfill their function (Bt/ Closed, Ct/Open), unless such operation is not practical during plant operation, per IWV-3522.

5. Basis for Relief:

The 1/2AF001A/B valves are the suction check valves to the 10W pumps from the condensate storage tanks, and function to prevent backflow of essential service water if that auction source is required. It is undesirable to full stroke open these valves quarterly due to the transients placed on the feedwater system and the thermal stresses imposed on the steam generator (S/G) nozzles (refer to program note 12). .

With respect to acoustically testing these valves to prove closure, versus ,

disassembly, the operating surveillance procedure used for the auxiliary feedwater '

(AFW) check valve cold shutdown full stroke test.is written to test a single train of AFW at a time. With an AFW pump running on mini-flow recirculation, flow is 3 initiated to each S/G on a gradual basis, while simultaneously reducing feedwater flow. As scon as the required flow data is obtained, AFW ' flow is gradually reduced, while simultaneously increasing feedwater flow, to minimire feodwater flow perturbations to the S/Gs. Due to this gradual change in flow, the open and close acoustical impacts cannot be observed from that of the flow noise.

However, the acoustic data taken during the 16 month dual pump injection test, has l provided sufficient data to determine valve disk closure'(refer to SMAD Report !'

M-6479-91, dated 10-28-91). This test is scheduled during the shutdown process, preceding reactor refueling, due to the large transient placed on feedwater flow and the thermal stresses imposed on the S/Gs.

l The application of RQH (Reliability Centered Maintenance) to the AF system has both j concluded and recommended that performing acoustic monitoring on a 3 year frequency l is sufficient to detect if the check valves fail to close. The failure analysis process required that the functional failures identified be evaluated using the failure modes and ef fects analysis (MHEA) . The FMEA provides a format for identifying the dominant failure modes of component failures leading to a functional failure and the impact of each component failure locally at the component, on the system, and on the plant.

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES l ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-19 1

l S. Basis for Relief: (continued)

Additionally, the closure capability of these valves cannot be verified adequately l by performing a back pressure test due to the multiple boundary isolation points. '

The system configuration makes it impossible to assign any observed leakage to any individual valve or component using standard mass make-up or pressure decay l techniques, j j 6. Alternate Testing:

The 1/2AF001A and 1/2AF001B suction check valves will be acoustically tested for closure (Bt) at each refuel outage in conjunction with the AEW full flow test and equipment response time of the AFW pumps. The open stroke (Ct) test will be tested during cold shutdowns, or at least once during each refueling cycle (approximately j 18 months).

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7. Justification: I i

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' Performing a pressure test to verify closure is impractical due to the system configuration. To perform this test it would be necessary to attach a pump or some other type of pressure source to a test connection and pressurize the line i containing the valve. However, this line also contains many potential leakage paths l (valves, pump seals, and instruments). It is not possible to assign a leakage value '

to any specific path using available methods of seat leakage testing.

]

Maintenance history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. !

Industry experience, as documented in NPRDS, has shown no history of problems with l these valves. A company wide check valve . %=d on addressing the "EPRI ;

Application Guidelines for Check Valves in ".<uclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems, l

Accustic testing provides ample information relative to valve condition, without i physically taking the valve apart for visual inspection to prove valve closure. '

These valves are of the same design (manufacturer, size, model, and materials of construction) and have the same service conditions, including orientation. Upon abnormal or questionable acoustic test results, the valve will be scheduled for disassembly and internal visual inspection. The results of this inspection will be used to further evaluate the standby train valve as well, for possible action. This type of alternate testing provides more than adequate assurance of both valve functional and operational requirements.

The alternate test method is sufficient to ensure both functional and operational requirements are met based on RCH failure mode and effect analysis for these valves. '

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INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-19

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status: ,

a. Relief granted per NRC Generic Letter 89-04, for Rev. 5.

b. Changed to incorporate RCM recommendations using acoustic monitoring techniques, Rev Sa. [

c. Changed to reflect approval of refueling frequency per SER dated September 14,. I

, 1993. ;

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l INSERVICE TESTING PROGRAL PLAN FOR VALVES- I CRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 '

RELIEF REQUEST VR-20 l 1. Valve Numbers: All Power Operated Valves, except those identified in VR-12 l (rapid-acting valves)

I

2. Number of Valves: Various

3. ASME Code Category: A and B

4. ASME Code,Section XI Requirement:

Subarticle IWV-3417(a), " Corrective Action"

5. Basis for Relief:

The Code requirement for increased frequency testing is based on a comparison between the current stroke time and the previous stroke time. Depending on the stroke duration and the percentage increase, monthly testing may be required. This approach, if not checked by trending, allows for the threshold for more frequent testing to slowly creep up over time. For example, an increase of 10% at each quarterly test could take place over a period of one year without any action being required. This variable limit is also difficult to administer because the limit is not a permanent entry in the test procedure. <

l A more appropriate method to be used should be based on an empirically derived fixed '

limit using valve operating history, valve condition and comparison with other valves of similar design (valve size, valve type, and actuator type). This allous for a more thorough review in determining what the " reasonable deviation" from the average / reference stroke value should be for an individual or group of valves.

For those valves that are identified for stroke testing in cold shutdown or refueling only, these valves cannot be placed on monthly testing for the reasons already presented in the valve test program. The Code does not provide any direction for these frequencies of test, as to if these valves are even to be included in the context of IWV-3417 (a) .

6. Alternate Testing:

, For all power operated valves which normally stroke in greater than two seconds, an

" Alert" range will be established based on reaching a given percent increase from l l the reference / average value. The maximwn limiting value of full stroke is !

established per Technical Approact .,nd Position, VA-04.

The reference value used to det-tvune the alert range will be reconfirmed following maintenance activities that cours atreet valve stroke time, or a new lindt will be established based on the new stroke time.

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES I

! ERAIDWOOD STATION UNITS 1 AND 2 i I Revision 7 l

l RELIEF REQUEST VR-20 l l

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6. Alternate Testing: (continued) i l

For valves that can only be stroke timed in cold shutdown or refueling, once the valve (s ) enter the alert range, they will be retested. If the retest is acceptable then an evaluation will be performed to determine the cause. If the retest is unacceptable then the valve will be declared inoperable until corrective actions are taken or an evaluation is completed justifying continued operability.

For valves that are stroke timed quarterly, when the alert range is exceeded the valve will be Ommediately retested. If the retest is acceptable, then an evaluation i will document this deviation. If the retest is unacceptable the valve will be

placed on monthly testing until corrective action is taken or an evaluation is i j completed, justifying continued operability providing the limiting valve or full t stroke is not exceeded.

The following criteria will be used as a starting point in evaluation of this fixed ALERT RANGE for power operated valves:

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l SOVs/HOVs/AOVs - Less than or equal to 10 seconds:

l ALERT RANGE VALUES: (1. 50) (T,,,)

l SOVs/HOVs/ADVs - Greater than 10 seconds: l

! I l ALERT RANGE VALUES: (1. 25) (T,,,) , or (T,,,+10 see) l l

! MOVs - Less than or equal to 10 seconds:

ALERT RANGE VALUES: (1.25) (T,,,) l l

MOVs - Greater than 10 seconds:

ALERT RANGE VALUES: (1.15) (T,,,) , or (T,,,+10 sec) i NOTE REFER to TECHNICAL POSITION AND APPROACH VA-04 for additional related information REGARDING LIMITING VALUES OF FULL STROKE.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES l CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-20 l

7. Justification: i l Using fixed ALERT ranges based on the reference value established when a valve is known to be operating acceptably will ensure that gradual valve performance degradation is monitored and evaluated, by placing the valve on increased testing frequency when the stroke time exceeds a fixed multiple of the reference value. This method is superior to that required by the Code in that the point of reference used to evaluate the performance trend on a valve remains fixed. This alternate test method uses the same percentage increase as the Code, except that its applied to the reference value.

Performing an engineering evaluation / investigation when a cold shutdown / refueling valve enters the Alert range providing the retest is acceptable, is adequate to l monitor the valve for degradation.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status:

a. This relief request is being submitted for initial approval per Rev. Sa.

b. Relief revised to incorporate SER comments re: OM-10 corrective actions for cold shutdown and refueling valves. Alternative authorized per SER dated September 14, 1993.

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I P INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-21 Withdrawn from Byron's program per SER dated 09/1.l/90 -

Not used at Braidwood - Byron ONLY*

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INSERVICE TESTING PROGRAM PLAN FOR VALVES.

BRAIDWOOD STATION UNITS 1 AND 2 Revision 7 i l

RELIEF REQUEST VR-22 i i

Not used at Braidwood - Byron ONLY* r i

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INSERVICE TESTING PROGRAM PIAN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 2 Revision 7' !

l.

RELIEF REQUEST VR-23 ,

Deleted by Revision'Sa. Valves are passive and only require leak testing per IWV-3700.

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ITERVICE TESTING' PROGRAM PLAN FOR. VALVES -

CRAIDWOOD-STATION UNITS 1 AND 2 j Revision 7 i 1

RELIEF REQUEST VR-24 1

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,1. Valve Wombers: -1/2PR032

2. Number of Valves: 2 ~

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3. ASME Code Category: AC l 4.' ASME Code, Seetion'XI Requirament:

Exercise check valves to the positiion required to fulfill' their function (Bt/ Closed), unless such operation is not practical during plant operation, per.

INV-3522. a t

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5. Basis for Relief: !

I The 1/2PR032 check valves are located inside containment in the return line of the.

processiradiation' monitor (PRM) (1/2PRllJ. panel).and are normally open.. The only safety function these valves provide'in the closed position is containment ;

l isolation,'which is a' redundant function to the outboard containment isolation- ,

valve. These valves open to allow return air flow back into containment.- The. 1

-1/2PRllJ PRM panel also provides the continuous means to monitor containment '

atmosphere during plant operation and cold shutdown.

The Code requires that these check valves be tested in the closed direction to l- ; verify their seating capability on a quarterly or cold shutdown basis. However, these valves can only be verified closed by performing the Appendix J, Type C local leakage rate test (LLRT). Performing the LLRT; requires placing the' system in an.

inoperable status;(removed from service) for an extended period of time due-to the need to isolate portions of,the system, and connecting a leak rate monitor (LRM). . ~!

This would make the process: radiation monitor'(PRM) inoperable requiring entry.into ;

a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Technical Specification time clock'(LCO).- j This would'cause undue hardship with no compensating increase in plant or. component !

safety, if the Code requirements were isposed.. ~

6. Alternate Testing: j These check valves will be back flow tested each refueling outage by.the performance of their Appendix J, Type C seat leakage test.

l 7. Justifi cation.

1.

Performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity and valve seating capability per both Appendix J and ASME Section XI requirements. There is no reason to perform the Appendix J, Type C (low pressure air at approximately 45 psig) seat leakage test more often than that already required by 10CFR50.' This low pressure air test is adequate to monitor the valve's ability to seat; the smallest amounts of dirt, general corrosion, and

=

foreign material'can be detected between'the seating surfaces by this test.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 3 1 Revision 7 i

RELIEF IT?UEST VR-24

7. Justification: (continued)

When a valve fails to meet its leakage criteria and repairs are required which make i the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of ;

being full stroked and is checked for binding or failure of valve internals.

Trained check valve inspectors are utilized for this examination and the results are reviewed and evaluated by the station's check Valve Coordinator. This is in addition to the root cause analysis performed per station requirements.

Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and radiation work practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety considerations, two individuals must always enter containment together, whenever containment integrity is set. The performance of this test would require a ndnimum of three (3) shifts with personnel working in a high radiation area. ,

The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unable to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside containment in a low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs from becoming contaminated.

, This alternate test method is sufficient to insure the safety function of these i

valves is maintained at an acceptable level.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status:

a. Relief is requested per Rev. 5.

b. Added additional technical information and justification, Rev. Sa.

l c. Approved per SE dated 9/14/93 with provision to investigate non-intrusives.

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l i I SERVICE TESTING PROGRAN PLAN POR-VALVES ~

I' ERAIDWOOD STATION UNITS 1 AND 2 l- Revision 7 i

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l- RELIEF REQUEST VR-25 l

1.; Valve Numbers:- 1/2PS231A, 1/2PS231B j i

2. Number of Valves: 4 .I

3. ASME Code Category: AC t

4. ASME Code,Section XI Requirement:

.[

t Exercise check valves to the position; required to fulfill their function I (Bt/ Closed), unless such operation is not. practical during plant operation, per .j INV-3522.

5. Basis for Relief:

The.1/2PS231A,B check valves are located inside containment in the return line of

, the post-LOCA hydrogen monitors and are normally closed. These check valves have a j l

safety function in the closed position 'to provide containment isolation, which is a i redundant function to the outboard containment isolation valves. They function in. I the open direction to allow the sampled containment air to be returned to -l containment. '

The Code requires that these check valves be tested in the closed direction to j verify their seating . capability on a quarterly or cold shutdown basis. - However, J

. these valves can only be verified closed by performing the Appendix.J, Type C' local ;

leakage rate test (LLRT). Performing the LLRT. requires placing the system.in an !

inoperable status (removed from service) for an extended period'of. time due to the .;

need to isolate portions.of.the system, and connecting a leak rate. monitor (LRN). .l This would make the hydrogen monitor-inoperable while the system is isolated. ;

This would cause undue hardship with no compensating increase in plant.or component safety, if the code requirements were. imposed. {

6. Alternate Testing: l These check valves will be'back flow tested each' refueling outage by the performance. l of their Appendix J, Type C seat leakage test. !

7. Justification:

f 1

Performance of leakage testing on a two year (refueling) . frequency is adequate to !

demonstrate structural integrity and valve; seating capability per both-Appendix J ,

and ASME Section XI' requirements. There is no-reason to perform the Appendix J, i Type C (Iow pressure air at approximately 45 psig) seat-leakage test more often than j that already required by 10CFR50. This low pressure air test is adequate,to monitor j the valve's ability to seat; the smallest amounts of dirt, general corrosion, and l foreign material can be detected between the seating surfaces by this test. !

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i INSERVICE TESTING PROGRAM PLAN FOR VALVES- 6 CRAIDWOOD STATION UNITS 1 AND 2 Revision 7-RELIEF REQUEST VR-25

7. !

Justification: (continued) l l When a valve fails to' meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection is performed :

per station procedures. The disassembled' valve disc is verified to be capable of- !

being full stroked and is - checked for bindin'g or failure of valve internals. !

Trained check valve inspectors are utilized for this examination and the results are l reviewed and evaluated by the station's Check Valve Coordinator. This is'in I addition to the root cause analysis performed per station requirements.

! Quarterly and cold shutdown testing requires.a containment entry and climbing inlthe I l penetration areas which would conflict with station ALARA goals and radiation work ~

practices in reducing exposure, and it is not prudent from a personnel safety ,

standpoint. For personnel safety considerations, two individuals must always enter

! containment together, whenever containment integrity is set. The performance of ;

this test would require a minimum of.three (3) shifts with personnel working in a high radiation area. Also, quarterly testing would conflict with Technical- !

Specification 3/4.6.3.2, which requires the hydrogen monitors to be in the standby mode in order to meet the requirements set forth in NUREG 0737, Item.II F.1.6 in- ;

Modes 1 and 2.-

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The leak rate monitors (LNW) used for Type'C'LLRTs'are required to be shipped.

Loff-site for calibration. During operation and cold shutdown when containment integrity is set, .the LRM(s) would need to be L taken inside the containment. If the LRM is contaminated and then unable to be decontaminated,' this would prevent its - ;

l calibration and render it unusable. This equipment is expensive and the number of l monitors available for use is limited. During refueling outages, a staging area is j set up outside containment in a low dose, non-contaminated area and hoses-are run inside to the various containment isolation valves. These precautions are taken- to !

prevent'the LRMs from becoming contaminated. ?

1 l This alternate test method is sufficient'to insure the safety function of these l valves is maintained at an acceptable level.

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8. Applicable Time Period:

l l This relief is requested once per quarter during the first inspection interval.

l 9. Approval Status:

a. Relief is requested per Rev.~ 5.

b. Added additional technical.information and justification, Bev. Sa.

c. Approved per SE dated 9/14/93 with provision to investigate non-intrusives.

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INSERVICE TESTING PROGRAM PLAN POR VALVES

. ERAIDWOOD STATION UNITS.1 AND 2 i

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Revision 7 RELIEF REQUEST VR-26 V

I. l. . Valve Numbers: 1/2RY8046, 1/2RY8047 i

j 2. Number of Valves: 4 7

'3. -ASME Code Category: AC i

j 4. :ASME Code,Section XI Requirement:

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J Exercise check valves to the position required to. fulfill their' function i 1-I i

(Bt/ Closed), unless such operation is not practical during plant operation, per I

INV-3522. !

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j 5. Basis for Relief:

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The.RY8046 check. valve is located inside containment in'the primary water (PW) '

i supply line to'the Pressure Relief Tank (PRT) and Reactor Coolant Pumps (RCPs) :

{- number three seal head tanks / standpipes.1 The only safety. function for this check l j valve is to close for containment isolation purposes; this'is redundant to the j i

outboard air operated isolation valve. The open function is to provide makeup water. 1 l to the PRT and to each of the #3 seal head tanks. The water in the PRT serves as a

~

1 quench volume for steam discharged from the 'PORVs and/or PER safety relief valves, I l

it also is used to cooldown the PRT after a. steam discharge. 1The primary water to- 1 j the RCPs #3 seal is'for cooling and flushing. ,

J d -

} The RY8047 check valve is also located inside containment in the nitrogen supply' i l line to the PRT. The only safety function for this check valve is to close for. !

containment isolation purposes; this is redundant to the outboard air operated. j

)

i isolation valve. The open function is to provide nitrogen gas to the PRT in. order.

~

to maintain an inert atmosphere to prevent 0, and H,' gas from combining into an ;

} explosive mixture. PRT pressure is maintained at 3 psig and is monitored by,

- installed instrumentation. 3 t _

! The Code requires that these check valves be tested in the' closed' direction to-i- verify their seating capability on a quarterly or cold shutdown basis. However, j

j these valves can only be verified closed bv performing the Appendix J, Type C local j j leakage rate test (LLRT). Performing the LLRT requires placing the system in an- ;

4 inoperable status (removed from service) - for an extended period of time due 'to the l need to isolate portions of the system, and connecting a leak' rate monitor (LRM) .

1 1

This would cause undue hardship with no compensating increase in' plant or component

] safety, if the Code requirements were imposed.

t 4 '6. Alternate Testing:

3, j These check valves will be back flow tested each refueling outage by the performance l- of their Appendix J, Type C seat leakage test.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-26

7. Justification:

Performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity and valve seating capability per both Appendix J and ASME Section XI requirements. There is no reason to perform the Appendix J,.

Type C (low pressure air at approximately 45 psig) seat leakage test more often than that already required by 10CFR50. This low pressure air test'is adequate to monitor the valve's ability to seat; the smallest amounts of dirt, general corrosion, and foreign material can be detected between the seating surfaces by this test.

When a valve fails to meet its leakage criteria and repairs are required which make the internals accessible for. inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve internals. !

Trained check valve inspectors are utilized for this e 7.wination and the results'are reviewed and evaluated by the station's check Valve Ccordinator. This is ih addition to the root cause analysis performed per station requirements.

To perform a Type C leakage test on a quarterly ' basis would require that both the nitrogen and PW systems be removed from service and placed in an inoperable condition, directly impacting the operability of the PRT and the RCPs. These components are not required to be operable during refueling, hence, allowing for the LLRT to be performed without affecting~ systems or components.

Quarterly and cold shutdown testing requires a containment entry which would conflict with station ALARA goals and radiation work practices in reducing exposure, and it is not prudent from a personnel safety standpoint. For personnel safety-considerations, two individuals must always enter containment together,.whenever containment integrity is set. The performance of each of_these tests would require-a minimum of three (3) shifts with personnel working in a high radiation area..

Also, it is not. practical to remove these valves from service, during quarterly or cold shutdowns, as these systems are required to support plant conditions-(RCS pressure protection and' control) and safe equipment (PRT and the RCP #3 seal) operation.

The leak rate monitors (LRM) used for Type C LLRTs are. required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unable to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside containment in a' low dose, non-contaminated area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs from becoming contaminated.

This alternate test method is sufficient to insure the safety function of these valves is maintained at an acceptable level.

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i INSERVICE TESTING PROGRAM PLAN FOR VALVES r ERAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l RELIEF REQUEST VR-26

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

9. Approval Status:

a. Relief is requested per revision 5 submittal.

b. Added additional technical information and justification, Rev. Sa.

c. Approved per SE dated 9/14/93 with provision to investigate non-intrusives.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES

-ERAIDWOOD STATION UNITS l'AND 2'

+

Revision 9 1

RELIEF REQUEST VR-27

'l. : Valve' Numbers: 'l/2WOOO7A,.1/2WOOO7B

)

2. Number of Valves:~4 '

3. ASME Code Category: . ' AC <

.4. ?ASME Code,Section XI Requirement:

Exercise check valves to the position required to fulfill their' function !

.(Bt/ Closed), unless such operation is not practical during plant operation, per- '

IWV-3522.

S. Basis ' for Relief:

The'l/2WOOO7A, B check valves are located inside: containment in the supply lines tio i the Reactor Containment Fan Coolers (RCFC) chilled water coils. These valves are_ ;

normally open valves requiring'a closure test quarterly or during cold shutdown per- ;

the Code. These-valves are not required for safe shutdown, their;only safety >

function is to close for containment isolation. purposes. This is also a: redundant

. function to the outboard motor operated valve's. containment isolation-function .i (1/2WOOO6A/B). .i The Code requires that these check valves be tested in the closed direction to . '

verify their seating capability : However, these valves can only be' verified closed ,

by performing the Appendix J, Type C localileakage rate test (LLRT)., Performing the- l LLRT requires placing the system in an inoperable status (removed from service) for -l an extended period of time due to the need to' isolate and drain portions of the- J system,' and connecting a' leak rate monitor (LRM).

This would cause undue hardship with no compensating increase in plant or' component 'I safety, if the Code requirements were imposed.

6. Alternate Testing:

=These check valves will be back flow tested each refueling outage by the performance of their Appendix J, Type C seat leakage test.

7. Justification:

Performance of leakage testing on a two year (refueling) frequency is adequate to l demonstrate structural integrity and valve seating capability per both Appendix J l .and ASME Section XI requirements. There is no reason to perform the Appendix J,

Type C (low pressure air at approximately 45 psig) seat leakage test more often than that already required by 10CFR50. This low pressure air test is. adequate'to monitor the valve's ability to seat; the smallest amounts of. dirt, general corrosion, and !

foreign material can be detected between the seating surfaces by this test. l l-l 4.6 - Page 60 of 70 1

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INSERVICE TESTING PROGRAM PLAN FOR VALVES ERAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-27

7. Justification: (continued) i When a valve fails to meet its leakage criteria and repairs are required which make l the internals accessible for inspection, a detailed visual inspection is performed per station procedures. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve internals. l Trained check valve inspectors are utilized for this examination and the results are !

reviewed and evaluated by the station's Check Valve Coordinator. This is in i addition to the root cause analysis performed per station requirements.

To perform an LLRT on a quarterly or cold shutdown basis would require that the l containment chilled water (WO) system be removed from service and placed in an inoperable condition for an extended period of time. It is impractical to perform this test during power operation because the WO system is needed to keep containment temperatures below 120*F. This is based on the environmental qualification of components inside containment and accident analysis assumptions.

Quarterly and cold shutdown testing requires a containment entry which would j conflict with station ALARA goals and radiation practices in reducing exposure, and ,

it is not prudent from a personnel safety standpoint. For personnel safety !

considerations, two individuals must always enter containment together, whenever )

containment integrity is set. The performance of this test would require a minimum j of ten (10) shifts (six shifts to drain the piping, 1 shift to test, and one day to fill and vent) with personnel working in a high radiation area.

The leak rate monitors (LRM) used for Type C LLRTs are required to be shipped off-site for calibration. During operation and cold shutdown when containment integrity is set, the LRM(s) would need to be taken inside the containment. If the LRM is contaminated and then unable to be decontaminated, this would prevent its calibration and render it unusable. This equipment is expensive and the number of monitors available for use is limited. During refueling outages, a staging area is set up outside containment in a low dese, non-contaminated area and hoses are run inside to the various containment isolation valves. These precautions are taken to prevent the LRMs from becoming contaminated.

This alternate test method is sufficient to insure the safety function of these valves is maintained at an acceptable level.

8. Applicable Time Period:

i This relief is requested once per quarter during the first inspection interval. i

9. Approval Status:

a. Relief is requested per revision 5 submittal.

b. Added additional technical information and justification, Rev. Sa.

c. Approved per SE dated 9/14/93 with provision to investigate non-intrusives.

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. INSERVICE TESTING ' PROGRAM' PIAN POR VALVES .- .

ERAIDWOOD STATION tEtITS 1 AND 2- l

Revision 7 -l i

RELIEF REQUEST VR-28' !

1

1. ; Valve Number: ICS011A/B 2CS011A/B ,

i

2. Number of Items: 4

-[

.i

3. ASME Code Category: C ,

4.- ASME Code,Section XI Requirements:

Exercise check valves to the position required to fulfill their function.(open/Ct;'

closed /Bt), unless such operation is not practical during plant operation, per IWV : ;

3522. '

i

5. - Basis for Relief: !

The 1/2CS011A/B check valves are on the discharge of the eductor and the safety f function in the open direction is to allow flow from the' discharge of the CS puaqp

and the spray additive tank back to the suction of.the CS pump. They function in'~ -l the closed direction to prevent backflow into the eductor front the CS pumpi suction i side. These valves cannot be full or design flow (185 gym is the design flow rate: '

130 gym eductor flow plus 55 gym NaOH flow)= tested as a matter of course during: unit ~ j

-operation or cold shutdown as NaOH from the spray additive tank would-be discharged i throughout the CS system causing undesirable chemical effects.on the reactor make-up supply (RNST) and associated systems.; However, ; they are partial flow tested , (> 130 i gpm) on a quarterly basis.

Non-intrusive techniques (NIT) using acoustics and magnetics have not been i successful in proving full stroke of the disk plates. The reason is'that the- -

critical flow rate is 10 feet per second.(the amount of flow which is required to .

full-stroke the disks) and cannot be obtained based on current system design.

It is considered to be impractical and burdensome to attempt to ' disassemble valves ~ !

in both trains every outage. Large amounts of reactor grade water needs to be - '

reprocessed due to the need to drain the entire. system before removing the valve

.from the system.

6. . Alternate Testing:

The A and B train valve are of the same design (manufacturer, size, model' number, j and materials of construction) and have the same service conditions, including ;

orientation, therefore they form a sample disassembly group.

One valve from each group, on a per unit basis, will be examine'd each refueling outage. If the disassembled valve is not capable of being manually full stroked exercised or if there is binding or failure of internals, the remaining valve on the .

affected unit will be inspected.

In addition to the above, the 1/2CS011A,B valves will partial stroke tested during the quarterly pumps surveillance and after maintenance in order to verify that it was installed correctly.

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INSERVICE TESTING PROGRAM PLAN FOR VALVgS

%RAIDWOOD STATION UNITS 1 AND 2

, Revision 7 l

l l RELIEF REQUEST VR-28 (continued) l ,

7. Justification: ;

l i

The 1/2CS0llA,B valves are removed from the system and visually examined per the i strict detailed inspection requirements of the Station Check Valve Program. This inspection adequately verifies that the valves are maintained in a state of operational readiness and that their performance parameters are adequately assessed.

The valves are verified to be functional by performing a thorough visual inspection of the internals and by perforndng manual full-stroke exercise of each disc.

The wafer type design of the valve body for these valves makes their removal a simple process, with little chance of damage to their internals. Also, there is no disassembly of internal parts required; all wear surfaces are accessible to visual examination. After inspection and manual stoke testing, the valve is reinstalled into the line and post maintenance testing is performed by partial flow testing the valve.

The alternate test frequency is justifiable in that maintenance history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. In addition, industry experience, as documented in NPRDS, show no history of problems with these types of valves in this service. This data indicates that there is no significant decrease in plant safety by perfo. ming sample disassembly.

The alternate test method is sufficient to ensure operability of these valves and is consistent with Generic Letter 89-04, Position 2. The hardship involved with full stroke exercising these check valves, if the Code requirements were imposed, does not provide a compensated increase in safety of these CS system check valves.

. Applicable Time Period:

l This relief is requested once per quarter during the first inspection interval.

9. Approval Status

a. Relief is granted based on NRC Generic Letter 89-04, Position 2.

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INSERVICE TESTING PROGRAM PIAN POR VALVES CRAIDWOOD STATION UNITS'l AND 2 Revision ~7 i

c- RELIEF REQUEST VR-29 i

~i

1. Valve Nurber: (Fire Protection - Inside Containment Isolation Valve)

Check'/alves .:

! .lFP345< P&ID M-52-l' I .2FP345 P&ID M-52-1 l ,

2. Number of Items: 2' !

3. ASME Code Category (IWV-2200) : C !

4. ASME Code Section XI Requirements: l Check Valves shall be exercised to the position required to fulfill their function. -l unless such operation -is not practical during. plant operation. Valves that cannot ;

be exercised during plant operation shall be specifically identified by the owner !

and shall be partial stroke exercised during power operations or full-stroke j exercised during. cold shut downs. (INV-3522) j i

5. Basis for Relief:

~ The above listed valves are Fire Protection 1(Water) to Containment Check valves and< )

are designated containment Isolation valves (CIVs).- These valves are exempt from j Local Leakage Rate testing of 10 CFR 50, Appendix J, but due to their designation as i CIVs, they shall be tested in the Closed direction. ~The valves are physically l located inside containment. Even though personnel access to the containment. ;

.(outside the biological shield) while the reactor is operating is allowed, it is not 'i a routine practice. There is no flow through these valves during any mode of i operation except for triennial flow blockage testing. This valve is passive in the ;

closed position and would only open in the event of a fire. i verifying the closed position of these valves during' cold shutdowns is m'significant' l burden for the following reasons: )

L i

1) The valves are inconveniently located for testing purposes. At a minimum, a ladder is required for one person.to climb, but ladders are not routinely taken into containment during cold shutdowns. Also, climbing is a personnel safety concern.

2) Scaffolding is the safest way to access these valves, but for elevations.of 14 to 20 feet above the floor construction'of scaffolds takes approx.'32 person-hrs at a cost of $900 to $1,000. Scaffolding removal has the same costs. -The time associated with this job could delay plant startup.

3) Cold shutdown testing would violate ALARA radiation exposure goals since it is ,

estimated that total dose to scaffold installers, insulation removers, and -I testing personnel would be at least 120-150 mrom on either unit.

4) Ultrasonic testing requires special expertise. Since a non-intrusive technique has been selected for verifying valve position, certified UT inspectors must be involved. Since inspectors are not necessarily on' site during cold shutdown activities but are routinely hired to support refuel outage activities, cold shutdown frequency testing would require additional cost.

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INSERVICE TESTING PROGRAM PIAN FOR VALVES I CRAIDWOOD STATION UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-29 (continued)

Testing these valves more frequently than each associated refueling outage adds no additional confidence in the valve's closure capability but it does add to the occupational radiation exposure of those personnel required to perfona the test.

6. Alternate Testing:

The above listed valves will be tested on a refueling outage frequency to verify closure.

7. Justification:

Testing these valves on a frequency of every three months during normal operation adds undue hardship without a compensating increase in the level of safety. Testing the valves every three months or on a cold shutdown basis adds to the occupational radiation exposure of the personnel required to perform the test. There is normally no flow through this valve to result in the valve disc leaving the seat, therefore the valve remains passively closed during periods of normal operation. No l additional confidence in the ability of the valve to close is gained by subjecting )

this valve to quarterly or cold .=hutdown testing versus testing on a refueling outage frequency.

! 8. Applicable Time Period: I l

This relief request is requested once per quarter during the first inspection interval.

9. Approval Status: I l

I

a. Relief is requested per revision 7 submittal.

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i IZSERVICE TESTING PROGRAM PIAN FOR VALVES ;

BRAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l 1

l 1

RELIEF REQUEST VR-30 ]

1. Valve Number: (Chemical and Volume Control - Loop Fill Check Valve) 1 Check Valves

)

j ICV 8348 P&ID M-64-3B 2CV8348 P&ID M-138-3B l I

2. Number of Items: 2 l

3. ASME Code Category (IWV-2200) : C

4. ASME Code Section XI Requirements:

l Check Valves shall be exercised to the position required to fulfill their function l unless such operation is not practical during plant operation. Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be partial stroke exercised during power operations or full-stroke l exercised during cold shut downs. (IWV-3522)

5. Basis for Relief:

The above listed valves are Reactor Coolant Loop Fill check valves in the Chemical and Volume Control System (CV) and are designated Containment Isolation Valves (CIVs). these valves are exempt from Local Leakage Rate testing of 10 CFR 50, ;

Appendix J, but due to their designation as CIVs, they shall be tested in the closed -

direction. The valves are physically located inside containment approximately 14 l feet above the floor, requiring scaffolding for access. Even though personnel i

access to the containment (outside the biological shield) while the reactor is operating is allowed, it is not a routine practice. There is no flow through these valves during periods when the associated reactor is at power, and there is very i seldom any flow through these valves during any mode of operation. This valve is passiva in the closed position and only opens during initial loop fill following a refueling outage. I l

verifying the closed position of these valves during cold shutdowns is a significant burden for the following reasons:

1) The valves are inconveniently located for testing purposes. At a minimum, a ladder is required for one person to climb, but ladders are not routinely taken

! into containment during cold shutdowns. Also, climbing is a personnel safety concern.

2) Scaffolding is the safest way to access these valves, but for elevations of 14 to 20 feet above the floor construction of scaffolds takes approx. 32 person-hrs at a cost of $900 to $1,000. Scaffolding removal has the same costs. The time l associated with this job could delay plant startup.

l 3) Cold shutdown testing would violate ALARA radiation exposure goals since it is estimated that total dose to scaffold installers, insulation removers, and testing personnel would be at least 120-150 mrem on either unit.

4) Ultrasonic testing requires special expertise. Since a non-intrusive technique has been selected for verifying valve position, certified UT inspectors must be involved. Since inspectors are not necessarily on site during cold shutdown activities but are routinely hired to support refuel outage activities, cold shutdown frequency testing would require additional cost.

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l INSERVICE TESTING PROGRAM PLMt FOR VALVES BRAIDWOOD STATICII UNITS 1 AND 2 Revision 7 RELIEF REQUEST VR-30-(continued)

I

~ Testing these valves more frequently than each associated refueling. outage adds no cdditional confidence in the valve's closure capability but it does add to-the occupational radiation exposure of.those personnel required to perform the-test. . .)

6. Alternate Testing: j The above listed valves will be tested on a refueling outage. frequency to verify' closure. )

o

7. Justification:

Testing these valves on a frequency of every three months during normal' operation adds to the occupational radiation exposure of the personnel required to perform the j test. Erection of scaffolding inside containment while at power presents unique.~ ;

hazards and requires extensive analysis and evaluation. There is normally no flow j through this valve to result in the valve disc leaving the seat, therefore the valve !

remains passively closed during periods of normal operation. No additional ;

confidence in.the ability of the valve to close is gained by subjecting this valve i to quarterly or cold shutdown testing versus testing on a refueling outage j frequency. ;

8. Applicable Time Period: ,

This relief request is requested once per quarter during the first inspection i interval. !

l

9. Approval Status:

)

t

a. Relief is requested per revision 7. submittal'. j l \

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES .

BRAIDWOOD STATION UNITS 1 AND 2 !

Revision 7 l

RELIEF REQUEST VR-31

1. Valve Number (Main Feedwater Header Check Valves) l IFWO79A-D 2WO79A-D ]

1

2. Number of Items: 8

3. ASME Code Category (IWV-2200) : C

4. ASME Code Section XI Requirements:

l

! Check Valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. Valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be partial stroke exercised during power operations or full-stroke exercised I l during cold shutdowns. Normally open valves... shall be tested in a manner that !

l proves the disk travels to the seat promptly on cessation or reversal of flow (IWV- j l 3522).

I

5. Basis for Relief:

The main feedwater header flow check valves are 16-inch tilting disk check valves l built with a vertical piston and rod assembly that serves as an anti-slam mechanism; the valves do not have external position indicators. The valves are designed to have a delayed closure time of 2 to 3 seconds to isolate flow during a feedwater line

! break accident without inducing significant water hammer transients. Their closed safety functions are to 1) mitigate a loss of secondary inventory and/or make-up, and 2) provide pressure integrity between the safety and non-safety related portions of piping.

These valves cannot be exercised to their closed position during power operations l because feed flow to a steam generator would be isolated, causing loss of Steam i I

Generator water inventory and a subsequent low S/G level Reactor Trip. '

Full-stroke exercising these valves by performing complete disassembly and inspection of each valve during cold shutdown conditions is undesirable and impractical because:

1) The main feedwater system would have to be drained. This would both delay I

reactor start-up and eliminate a method of reactor decay heat removal. The latter, in particular, could adversely affect shutdown safety.

2) Complete disassembly often requires machining activities that remove metal from the valve walls which may jeopardize minimum wall thickness. If minimum wall thickness is approached, then costly and difficult weld overlay techniques and associated machining would be required.

3) Scaffolding must be built and removed to allow i

examination of these valves.

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INSERVICE TESTING PROGRAM PLAN FOR VALVES i ERAIDWOOD STATION UNITS 1 AND 2 l Revision 7 l

! RELIEF REQUEST VR-31 (continued) l l Pull-stroke exercising these valves by performing partial disassembly (i.e. removing only the actuator bonnets) of all four valves on a refueling or cold shutdown frequency is burdensome because of the system draining necessary and the potential wall material loss associated with disassembly and inspection work.

Non-intrusive testing during cold shutdowns has been attempted at Braidwood and Byron Stations with still unproven results. Specifically, ultrasonic examination of the piston rod position has not conclusively demonstrated valve closure: The anti-slam mechanism prevents the disk frem travelling completely to its seat after cessation of forward flow. In fact, during normal feedwater system shutdown evolutions, the valves routinely come to rest at a partial open position --

substantial reverse flow or reverse differential pressure would be required to bring the disk into contact with the seat.

l Traditional backflow testing methods were considered, but it has been determined l that reverse flow and/or differential pressure sufficient to close the valve cannot

be obtained without major modification to the existing plant configuration.

Clearly, acoustic testing techniques which require contact noise between disk and I seat cannot be used for this application, either. l 1

6. Alternate Testing: .

1 The four valves on each unit are of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions, ;

including orientation; therefore, they form a sample disassembly group. ~

! One valve from each group, on a per unit basis, will be fully disassembled and examined each refueling outage. If the initial disassembled valve is not capable of l being full stroke exercised or if there is binding or failure of internals, '

subsequent disassembly and inspection of the remaining three group members will be commensurate with the initial valve's failure mode.

This means that the remaining three valves may be " partially" disassembled, which refers to the removal of the actuator [ upper) bonnet for inspection of the piston, piston seal ring, mating surfaces, and also for manual full stroke closing. A

" fully" disassembled valve (minimum of one per outage) would additionally include removal of the valve body [ lower) bonnet, giving access to the disk and seating surfaces. The subsequent disassembly requirements would be satisfied through either

" partial" or " full" disassemblies depending on what is found with the initial disassembled valve. This will both satisfy the testing requirements to demonstrate all four valves' ability to perform their safety function and minimize the potential concerns regarding minimum wall thickness discussed earlier. This approach is consistent with the intent of Generic Letter 89-04, position 2.

A partial stroke test following complete installation will not be required for these check valves since an "as left" stroke is performed prior to the installation of the actuator bonnet; installation of the actuator bonnet does not affect the stroke of the valve. In addition, the plant operates with these valves in the open position and open stroke problems would be readily identified during plant startup.

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l INSERVICE TESTING PROGRAM PLAN FOR VALVES BRAIDWOOD STATION UNITS 1 AND 2~

. Revision 7 RELIEF REOUEST VR-31'(continued) H l

7. Justification:

Because major plant modifications would be required to establish enough reverse , I flow / pressure to fully close the valves, in-service testing in accordance with NRC !

Generic Letter 89-04 is justified. The Generic Letter allows valves of similar design, service conditions,~ etcetera to be classified in sample disassembly and inspection groups of up to four members with testing of-one valve.in the group j during each refueling outage. .

In-service testing of the valves that close-on a feedwater isolation signal,- .

-i including the safety-related feedwater containment isolation valves (FNOO9A-D), the : j non-safety-related feedwater regulating valves (FW510, 520, 530, 540), and the .

feedwater regulating bypass valves (FW510A,' 520A,...) helps ensure that the power operated valves and.the system are capable of safely responding to-an initiating feedwater line break accident regardless of FWO79 check valve position. '

i The alternate test method is sufficient to ensure operability of these valves and is; I consistent with Generic Letter 89-04 sample disassembly and-inspection program. The i

alternate test method in. conjunction with other existing in-service testing of -

feedwater valves is more than. sufficient to ensure the system's ability to safely; respond to a feedwater line break accident.-

8. Applicable Time Period:

This relief is requested once per quarter during.the'first inspection interval'and l I

will be implemented prior to NRR review..

9. Approval Status:

t l Relief granted per Generic Letter 89-04.

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ATTACHMENT TO RELIEF REQUEST VR-31 Figure 1 37 Q 4g u & n% l1' A 19 m

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ATTACHMENT To

RELIEF REQUEST VR-31 j Figure 2 l 49 56

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l l ATTACHMENT TO RELIEF REQUEST VR-31 4

l Figure 3 1

i i

ITDI ITEM MAME ITEN ITEM NAME ITEM ITEN NAME j MO. No. MO.

j 1 Stop 19 Piston Ring 43 5/8 Lockwasher ,

t 2 1/2-13 Mut 20 Drive Screw 44 Bushing Retainer l

) 3 1/2-13 Stud 21 Drive Screw 46 Retainer i 4 1/2" Lockwasher 25 Seat 47 Spacer j Canopy Seal 5 26 Body 48 O-ring j 6 Pia 27 Piston 49 Retaining Ring j 7 Retainer 28 Piston Nut 50 Retainer

8 Clovis 29 Cylinder $1 Housing j 9 Bonnet 30 0-rlag 52 Poppet 10 Bushing 31 Protective Cap 53 Washer 11 Bushing 33 0-rlag 54 Shim 12 Bonnet Seal 34 Nossle 55- Spring 13 Retainer Spacer 35 Bonnet Seal 56 Retaining Ring I

14 Pivot 36 Bonnet 58 Lockwire 15 Piston Rod 37 Retainer 59 Spring-

16 Disc 38 Retainer Spacer 60 Bushing 1 17 O-ring 41 5/8-11 Stud 61 Pia la Bushina l 42 E/a-11 Mut 62 Estaerew i

s i

m i

1 i

A-3 i

i

ML20082C948

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ML20082C948

Text

Description:

References:

Description:

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Description:

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Description:

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Description:

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Description:

References:

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Conclusions:

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