ML20091N340

Temporary Change Notice to Rev 9 to S023-V-35, IST of Valves Program

ML20091N340
Person / Time
Site:	San Onofre
Issue date:	08/24/1995
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20091N329	List: ML20091N326 ML20091N340
References
S023-V-35, S23-V-35, NUDOCS 9508310128
Download: ML20091N340 (177)

Text

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L l PuiPERENCE: 8012341.0.1 - Subminal No. (Fapp#oeble) 95080&G39 TEMPORARY CHANGE NOTICE Page 1 of 4'

]; ' NOTES: 1) . N the Doeusnent le QA Program a Technisel SpeelAseden Vieleden ale eesur if CFDid snel approval

% megen 14 days trese et leessapee.

3) M Coneedeneare then tonn PF(1SB) 111 should be used trefer to SO133 VI 1.0.1).

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{ 1. DocumentNo. 6D230*3D Revision No. Single use TCN: YesO

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2. I required, TCN Deviation el: NY: II (%

cPOW tw esmeesse sunnwrai y er unpri puma Arma no staTu part/Tum

a. Cneck opproprime boa: Enere oooumere Ammh.4 O An.oied Page(s) AmaEMIVED700 l 87 ^ Tieorporated TCN(eVEC(e)

,.ue CYI (Not appocable for Single Use 7CNe)

.p - e-l 4. Tid. change eenn una m n.a ,.ieion m u oocumeni and ie requi,ed: AUG.251995 i a. O To knplanent feesty design ohenge (oce, ines, wu, me.) .

j Feellhy design ohenge idenuner RITF FilF MPY /

esosania cxy, nasp, puc, wu, sTu ouhmen shage he.

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b. q,s Other (e.g., CNI, NMC CommNrnende) Spootno Reason. t ')Jh WTMs5 AA.y to MnY alit Omhtials ses Eirm A4HewsF,

oeeerip6en of Change (e) (Uee Flenroe Side RRequired) f $1TW20$

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!' 5. Could implernentadon of this change pose adverse environmental eNeces of pe direocy or inallroouy? Yes O No

. p yet een a n:N ie noe adhomed we a podem een amuswenedei Presumen b osenhed new no 1 13) _j

) 1

,1 Review requested from other orgentregone/desciptnes? yv.sF(1a411eA, ereesussentesewnenessen, may be seashed.) YeeO No W Part C s l l 7. le the docurnent being TCN'd QA Program ANeeting or Level 1 QA Program Aneceng? YesEr No O I Anemer peo aner e esmanent e emessed as met on pensern mesens. run a wesessed en me rame et canesen mese er me answeent l

a ven, seme== ese sessen; men pressed m Past & F No, seer poseed a Port a fBee

• tese ser kded appmeL e one pernes, emedn heel and enel h) j l r* le the document to be obenged an Emergency Opweene instruoson? Yee O No !_E'j i

! b. le the intent of the original document eneroM YeeO NoIW

(If the answer to e or b is Yes, then a TCN le not aershoriand. A revision is required; ese 80123 Vl 0.9 and 80123Ni-1.)

10 CFR 50.80 Consideration:

l o. kee the proposed change airwedy been evalueesd for 80.50 considereelon or a 7 quee6cn Safesy Evaluation prepared using an approved Procese? pas erespseved peessess are: M AMP /rPMtPecFVTechnhal eposegdn smense, menschend pennewe emessy E%enmoon [r seassensk era l Yee O Enter idonener and eseoclased no. No IN Asoch PF(123) 1001 or 50.50 Safmy Evolustion (7 quessons).

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note sine.enesc we. v. neo-se

_ - eene must nee4een.s esedypas, (Refw to 8012341.3.)

! NOTE:

os - .e.a. - _ m. - ,, Both,YE,S , and N,O may be checked, if applioable.

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Part I- M Ihe entile dooumett weg reviewed in annueyb6ennial rwiew dieposalon of Witt tes TCN ed tonmd to be are=renhie as wrteen. This conettums an l l

As Wrneen-Extend (9012241.0.2).

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, Port tJ- For Are IAes anfy: ,

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. e e se mer sem en me Genew Amusense nonserAeemsel == m Put e.

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.Referencet 30123.VI-1.3 Page Gf IMREVIEMED SAFETY CUESTION (10 CFR 50.591 SMCBWLCRIIERIA

(

oocumT m. '

so23-V-34 -

REv. no. 3 TCn. no. 9 -W

- (if applicable)-

, 'PART1) 10 CFR 50.59 REVIEW (Refer to 50123-VI-l'.3)-

~

N 1. Does this new procekre/procekn ehenge alter systen/ component perforanace

or the design configuratton of a systen inportant to safety? Yes___. No d '.

i t.' ' Does this new procedun/procekrw change alter the calibration of a systaa important to safety? ' Yes.___ No f '

• 3. Does this new procedure /procedvn change alter the required actions as a - ..

result meeting the acceptance criteria or alter Technical Specification

., numeric 0 of a systen important to safety? ' Yes ,No _(_.

l 4. Does this'new procedure /proce k re change reduce the level of approval required for a plant activity? - Yes.,,_,,,No y :

. .$. ?Does this new procedure /pncekre c e atter pro esses for hendting pmcess , nonitoring, or releasing l consed tvdioactive noterial ag.,t c conta in plant systems! .

Yes ,_ No f t

8

6. Does this new procedurv/procekte change violate the provisions of the Yes__No.,_f

} Technical Specifications?- _,

t Remarks: ~

h ;6 (If required, use reverse side or ettech additional sheets.)

PREPAREDBYsid . b b/A. DATE f**7 8 APPROVED BY: - DATE I

, Cogni ont Lugervisor L 1.f. "Yes" is the answer to any question in Part I), gg STOP document processing. Coordinate

! Part II) completion with nizant Supervisor, or contact Nuclear Procedures Group ( PG) to i , coordinate Part II complet on with Supervisor, Technical Support, or contact Superv sor,

Technical Support irectly; during off-hours contact the on-duty Station Technical Advisor 4- '

(STA).

PART II) 50.59 SAFETY EVALUATION DETERMINATION (Required when YE3 checked in PART !)

Area / individual Assigned: DATE

j. (PleasePrint)- '

l -Is a 50.59 Safety Evaluation required based on the new procedure /

t. procedure change? (Refer to S0123-VI-1.3 Attachment 1) Yes*,,No**___.

l If Yt$. complete 50.59 Safety Evaluation per established procedures and attach. stor document processing if 1 TIS entwer indicated on 50.59 $afety Evaluation, j - .lf NO. provide justification (Indicate resources consulted, as applicable):

1 (if required, use reverse side or attach additional sheets.)

PREPARED BY: DATE

Cognizant Individual /STA

' APPROVED BY: DATE

CFDM or Designee

~ NPGr 1) .jf YES in part II), ,thgn notify NPG supervision; forward a copy of this form and associated 50.59 Safety

,( . twelvetion(7questicas)toNuclearLicensing.

4

2) li TES enswer is indicated on 50.59 Safety tvaluation (? questions). 3hgg STOP document processing and notify NPG supervisions fomerd a copy of this form, 50.59 Safety Evaluation, and document to Nuclear Licensing and j .Neclear, Sefety Grout.

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- _ -_______ _ _ __ _ __ _ . . ~ _ _ ___ _ _.

3093-N.6 TCN N Pese.b of$

, N 0I DeecrQdion of Changee(Contermed) 1 e

.1. Throughout he pmoedure, eninor rephical enore have been corrected where found, including

elle changes, valve code cines as wel as other minor, similar correceons throughout the i~ pmcedure, l l

Romeon: Editorialimprovenmt. '

2. ' l Reference 2.1.1, chan0e to delete "Rev. 0*.

Reason: Editorial. This paragraph already late " latest version".

3. Delete reference 2.1.14.

I Fleason: Old reference le no longer in use. 90055 (refwence 2.1.1) was subsetuted to roolace this -

! Item. .

j j 4. Add a note following paragraph 6.6.5.2.1 to read:  !

c .

)

NOTE: ' Seat le 6 mite met appear in the requirements records of the ISTM computer appication 1 for J toets, test type AJ, are maintenance threshold Imite only and do not  !

necesserny reflect the test pass /lall Imite determined using the colouis9on in the above i paragraph.

j Reason: Clarilles the desnodon between he Appendx J acoeptance Emite iden#6ed in the ISTM requiremente recorde.

5. Attachment 2, add new General Note 6 as follows: )

4 '. .

GENERAL NOTE NO. 6 - For test type AJ, a 25% test interval extenolon le not allowed. Accordnely. l I

a maximum teet interval of 730 dava is used for these toets when the 1

nominalInterval specified in his attachment le "RR", and, a maximum test interval of 92 days le used for these tests when the nominalinterval

, spedSed in thle attachment is "OP". (See Appendx J and the Technical i

Spoollloadons.)

, Reason: Clattnee the desnodon between the OM-10 Interval guidelines and those of Appendx J.

4

6. Nachment 2, note 1, e the last Ine to read,"See References 2.1.1 (Document M.90055) ano 2.5.3 (NUREG 1482), 3.4."

l.

Reason: Old reference is no longer in use. 90055 (reference 2,1,1) was substituted to replace this i item.

i 7. Attachment 2, note 7, change to read, "The closed stroke test was added at the recommendsson of INPO to mitigate an inter eystem LOCA in the RCP heat exchanger even though this test le not ,

, identfled as required in reference 2.1.1."

Reason: Old referonoe is no longer in use 90055 (reference 2.1.1) was substituted to replace this

Item.

, 8. Attachment 2. notes 14 and 22 change " References 2.1.14" to med " References 2.1.1".

3 Reason: Old reference is no lon0*r in use. 90055 (reference 2.1.1) was substituted to replace this Item.

9. Attachment 2, note 12, change the last une to road, "See Refer'enoes 2.1.1 (Document M-90055) and 2.5.3 (NUREG 1482), Sooton 3.4."

Reason

Old reference is no longer in use. 90055 (reference 2.1.1) was substituted to replace this

[ ltem.

10. Attachment 2, nots 21, change the last une to road,"See Technicai 3pecificatone, Paragraph 4.7.5 5

and References 2.1.1 (Document M-90055).

' Reason: Old reference le no longer in use. 90055 (reference 2.1.1) was subsetuted to replace this F ltem.

i l

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.- . - ..~. - - - .- . - - - - . . . - . - .

i sot 3 V3.6. TCN O

• Y Page$ot$

esniT ms,n orcungseicanee,uem

= 11. Attachment 2, note 23, ohenge to read, -

~ 23. Reference 2.1.1 calle for a Poelton Indoetion Test (PIT) on 2(3)HCV9918 and 2(3)HCV9946 and on 82(3)1312MUO37 and 82( 1312MUO38. These valves are locked in their safety poeltion ad all

' times when they are made to perform heir eefety funcuon. As a consequence, no sotual PIT testle 8023-017, "Locidng of Safety-Related Cdiloel Valves and

Breakere.' Note thatif loddng requirement le removed, a Pif test will be required.

i .

Reason

Old references are no longer in use. 90066 (reference 2.1.1) wee substituted to replace thle -

item.

12. Attachment 2, Under Fuel Storage Pool and Refueling, delete S2(3)1204MUO28 from the table.

Reason: Testing no longer required. See DCN # 11 to 5023-IST-1204,

13. ' Attachment 3, paragraphs 10.2.5 and 16.4.4, " References 2.1.14* to read "Referencee 2.1.1*.

Reason: Old reference le no lon0er in use. 90066 (reference 2.1.1) was substituted to repleos thle

, item.

peo:TCN36R w61

August 22,1996 1

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i NUCLEAR ORGANIZATION- iENGINEERINGPROCEDURE-S023-V-3.5

' UNITS 2 AND~3 PAGE 10F 173 i EFFECTIVE DATE' JUNE 30 1995 , REVISION LTCN/EC 9@y l I

JNSERVICE TESTING OF VALVES PROGRAN 1

IMLE OF CONTENTS i l

, l 4

SEC110M PAGE 1.0- OBJECTIVES AND GENERAL INFORMATION 2

2.0 REFERENCES

- 4

-3.0 . PREREQUISITES 6

.- 4. 0 PRECAUTIONS 6  ;

l '5.0 CHECKLIST (S) 6

'.' 6.0 PROCEDURE 7 6.1 Determination of Program Scope -7 l 6.2 Terminology 7 1 6.3 Categories of Valves 8 2

. 6.4 .0wners Responsibilities 9 6.5 Testing Requirements 12 6.6 Testing Nethods 15 6.7 Acceptance Criteria and Corrective Action 28 6.8 Instrumentation 29 7.0 RECORDS AND REPORTS 30 l

, 7.1 Valve Records 30 l 7.2- Test Plans 30 i: 7.3 Records of Tests 31 7.4 Record of Corrective Action 31

• ATTACHNENTS 1 Listing - Check Valve and Relief Valve Groups I (Valves Grouped for Testing) 32 i 2 List of Valves Within the Inservice Testing Program- 35 3 Alternate Testing Justification and Basis For Other Than l i

Quarterly Test Interval 106 4 Stroke Time Acceptance Criteria For Valves Required to Stroke at Other Than Their Safety Analysis Limits 168  ;

5 Acceptance Limit Change Record 173 l i

' 23V35T92.W51- QA PROGRAM AFFECTING

, ., - - - --r r

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 . REVISION 9 PAGE 2 0F 173-

,TCN/EC Sy

. INSERVICE TESTING OF VALVES PROGRAM I

1.0 DBJECTIVES AND GENERAL-JNFORMATION

! 1.1 To establish the requirements for preservice and inservice testing to assess the operational readiness of valves and pressure relief devices

{and their actuating and position indicating systems) in accordance-with Reference 2.1.5. See discussion in Section 3 of Reference 2.5.1.

1 l NOTE: Test results are usod in assessing operational readiness of valves during their service life to perform a specific function in shutting down the reactor, bringing it to cold

shutdown or in mitigating the consequences of an accident.

f 8 1.2 To establish test intervals, parameters to be measured and evaluated, acceptance criteria and requirements for corrective action, and j records. [ Reference 2.1.3, Para. 1.1]

1.3 'To meet the requirements of References 2.1.1, 2.5.1, 2.1.3 and 2.1.4.

. NOTE: Organizational responsibilities for meeting References 2.1.1, 2.5.1, 2.1.3 and 2.1.4 are described in Reference 2.2.1.

i 1.4 Scope 1.4.1 Tnis program is applicable to safety related components including, but not limited to ASME Class 1, 2 and 3.

Certain non-ASME components are included in this program

as recommended and discussed in Rcference 2.1.9, Position 11, IST Program Scope. ,

NOTE

For ;ome non-ASME Section III valves, testing is 4

not .1 full conformance with OH-10. Where testing departs from the OM 10 rules the testing is censistent with the safety significance of the non-code valve and consistent with Reference 2.5.2, Question 53, and

! Reference 2.5.3, Section 2.2. See the valve-by-valve discussion of these cases in

Attachment 3.

1.4.2 The active or passive valves covered in this progrant p procedure are those which are required to perform a i

specific function in shutting down a reactor to the cold

. shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident.

y )- -

i

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 PAGE 3 0F 173  !

. REVISION 9@gr TCN/EC 1.4.3 The pressure relief devices covered are those identified i in accordance with the M-90055 document, Reference 2.1.1.

1.4.4 This Procedure may include the testing of components in addition to those listed in References 2.1.1, 2.5.1 and 2.1.4 (Paragraph IWA-1200), but shall, as a minimum, require testing of at least all of the components (meeting the above scope description) in those references.

1.4.5- The Check Valve Program, and its interrelationship with the IST Program are defined in the Station Order addressing the Check Valve. Program, Reference 2.2.2.

1.5 Exclusions 1.5.1 The following are excluded from the scope of this program provided that the valves are not required to perform a specific function as specified above (Reference 2.1.3, Para. 1.2]:

.1 Valves used only for operating convenience such as vent, drain, instrument, and test valves;

.2 Valves used only for system control, such as pressure regulating valves;

.3 Valves used only for system or component maintenance.

1.5.2 External control and protection systems responsible for sensing plant conditions and )roviding signals for valve operation are excluded from tie requirements of this program.

I

, 1.6 General Information 1.6.1 The Inservice Testing of Valves Program delineated herein covers a ten (10) year interval commencing on August 18,

~

1993 and terminating on August 17, 2003. The date for implementing the second 10 year interval was extended until April 1, 1994.

1.6.2 In accordance with Reference 2.2.1, the Manager, Technical Division, is responsible for this program and its implementation at the San Onofre Site.

1.6.3 Administrative requirements are identified in this program procedure where appropriate. These recuirements are necessary for the orderly execution anc docur.entation of program operations. Administrative requirements also provide for documenting program changes and for management of the implementing procedures. I 1.6.4 The collection and review of data trends to detect component degradation is governed by Reference 2.3.1.

l l

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NUCLEAR ORGANIZATION ENGlNEERING PROCEDURE S023-V-3.5

! UNITS 2 AND 3 PAGE 4 0F 173 l REVISION 9 @ p

, . TCN/EC -

2.0 REFERENCES

'2.1 NRC Commitmentis)-

2. I '. i M-90055, Selection of Valves and Determination of Valve Inservice Testing, latest version  % .

2.1.2 OM-1, ASME/ ANSI 0M-1987, Operation and Maintenance'of Nuclear Power Plants, Part 1, Requirements for Inservice

. Performance Testing of Nuclear Power Plant Pressure Relief Devices-2.1.3 OM-10, ASME/ ANSI OM-1987, Operation and Maintenance of.

Nuclear Power Plants, Part 10, Inservice Testing of Valves in Light-Water Reactor Power Plants (including ASME/ ANSI OMA-1988 ADDENDUM) '

2.1.4 ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition.with no addenda (July 1, 1989), Rules for Inservice Inspection of Nuclear Power Plant Components

,'- 2.1.5 Units 2 and 3 Technical Specification 4.0.5, Surveillance ' l Requirements for inservice inspection and testing of ASME l Code Class 1, 2 and 3 components. i 2.1.6 Technical Specifications, Units 2 and 3, Section 1.0, Definitions 2.1.7 Topical Quality Assurarce Manual (TQAM), Chapter 7, ASME Code Program Scope, Responsibilities and Program Controls, latest revision 2.1.8 Updated Final Safety Analysis Report (UFSAR) 2.1.9 NRC Generic Letter 89-04, Guidance on Developing , 1 Acceptable Inservice Testing programs, April 3,1989 1 2.1.10 10CFR50, 9 50.55a, Codes and Standards 2.1.11 10CFR50, 9 50.55a(f), Inservice Testing Requirements 2.1.12 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors 2.1.13 Ceneric Letter 91-18, Information~to Licensees Regarding '

Two NRC Inspection Manual Sections on Resolution of

, Degraded and Nonconforming Conditions and on Operability, November 7, 1991 ,

4

- NUCLEAR. ORGANIZATION L ENGINEERING PROCEDURE S023-V-3;5 UNITS 2 AND 3 PAGE 5 0F 173 2

REVISION 9b N TCN/EC ]

4 2.2- Orders ,

~

2.2.1 S0123-IN-1,-Inservice Inspection Program-  !

l '2.2.2 S0123-CV-1, Check Valve Program 2[3 Procedures

! )

[ 2.3.1 S0123-V-5.15, Inservice Testing (IST) Coordination and  :

Trending j

j 2.3.2 S0123-XV-5, Nonconforming Material, Parts or Components

! 2.3.3 -50123-XXI-1.11.11, Engineering Training and ' Qualification

Program Description s .

2.3.4 -S0123-XXIV-10.9, Design Process Flow and Controls,

- SONGS 1, 2.& 3-I 2.3.5 S0123-XXIV-10.16, Development, Review, Approval and Release of Conceptual Engineering Packages (CEPs) and

.'J Design Change Packages (DCPs), SONGS 1, 2 & 3 2.3.6 S023-V-3.13, Containment Penetration Leak Rate Testing-i 2.3.7 S023-XV-6, Technical Specification Response Time -

Surveillance Implementing Procedure Master List ~

2.3.8 S0123-V-5.22, Supplemental Check Valve Program j 2.4 Operatina Instructions l 2.4.1 S0123-0-20, Use of Procedures 2.4.2 S0123-0-23, Control of System Alignments 2.5 Other

2.5.1 - Inservice Testing Topical Report, Design Bases Document, DBO-S023-TR-IS2, latest revision 1

i. '

2.5.2 Letter, J. G. Partlow, NRC, to All Licensees,- etc, Minutes of the Public meetings on Generic Letter 89-04,

. October 25, 1989 -

2.5.3 NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants, April 1995 2.5.4 Letter, T. R. Quay [NRC), to H. B. Ray [SCE), Second i 10-Year Interval for Inservice Testing of Pumps and Valves l

[ Safety Evaluation Report (SER)], August 31, 1994 l

j

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' NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-305 LUNITS 2 AND'3- .PAGE 6 0F 173

' REVISIONW TCN/EC 9n b 3.0 PREREQUISITES

' NOTE: Reference to SDMS, ON-LINE, with a PC is the preferred

method to verify which version of the Procedure and TCNs

, are current.

,@J1QH CDM-SONGS Controlled copies are updated as soon as their.

resources permit, however, this might sometimes mean that controlled copies in the Technical Library, for example, are updcted several days after the new TCN or revision is s

issued. This is not the case with the on-line SDMS system.

1 3.1 Before using this document, verify the revision and any issued TCNs.

and/or ECs (Editorial Corrections) are current by using one of the following methods:

3.1.1 Access the San Onofre Document Management System (SDMS)

[ San Onofre local area network (SLAN) or online system]

(preferred methods).

3.1.2 Check it against a Corporate Documentation Management-SONGS (CDM-SONGS) controlled copy and any 4

issued TCNs/ECs.

3.1.3 Contact CDM-SONGS by telephone or through counter inquiry.

3.1.4 Obtain a user-controlled copy of this procedure from I

. CDM-SONGS or SDMS SLAN. l

{ 4.0 PRECAUTIONS >

! 4.1 Testing required in this program p acedure shall not be conducted in l Modes or under conditions that place the Plant in an unsafe condition. ,

Likewise, care shall be exercised that no test will be conducted so a  !

4- failure of the test would put the plant la an unsafe condition. '

4.2 Special care must be exercised to ensure that the allowed test i interval is not exceeded. With the exception of Appendix J tests, a test interval extension is allowed. This extension shall not exceed twenty-five percent of the test interval. See Technical -

l

-Specification 4.0.5(Reference 2.1.5). The twenty-five percent (25%) '

interval extension is allowed to accommodate plant conditions that may not be suitable for conducting a surveillance (such as transient  :

conditionsorothersurveillanceinprogress). It also provides  !

flexibility.for refueling interval surveillance.

5.0 CHECKLIST (S1 5.1 None 4

% , - - , -+

o NUCl. EAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 t'

UNITS 2 AND 3 PAGE 7 0F 173 REVISION 9@ M TCN/EC 4

6.0 PBQCIDURE 1

6.1 Determination of Procram Scone

! -6.1.1 The Nuclear Engineering Design Organization (NEDO) is-

+

responsible for determining the scope of the Inservice Testing Program. This responsibility is accomplished using documented methods for design engineers such as Reference 2.1.1, and the documents identifying the results of the analysis ' required thereby.

~

6.1.2 Additional guidance for establishment of Program Scope 1s included in References 2.5.1, 2.1.3, 2.1.8, 2.1.9, 2.5.2 l and 2.1.6.

6.2 Terminoloav

[;

NOTE: Hany_ of the definitions in this section are derived from Reference 2.1.3.. Consistency with this Reference provides

, a common basis for understanding among (a) ourselves, as

, the owner,-(b) the ASNE documents with which we must l' -comply and (c) the individuals.who audit our program, such as the NRC, ANII, etc.

4 active valves - valvas which are required to change obturator position toaccomplishtherequiredfunction(s)asspecifiedinthisprogram

procedure, above.

l I

cold shutdown - The Code uses Cold Shutdown "CS" for all modes other

, than Operating and Refueling and therefore ("CS" as used in the IST Program) includes Technical Specification Modes 3, 4 or 5. All valves identified for Cold Shutdown testing are not testable in all modes. ,

y Accordingly, appitcable implementing procedures (Operating l Instructions) will specify which valves can be tested in a given Mode. '

1

[ (Foradditionalinformation,seetheNOTEfollowingstep6.6.2.4.)

f exercising - the demonstration based on direct visual or indirect

positive indications that the moving parts of a valve function.

full-stroke time - the time interval from initiation of the actuating

signal to the indication of the end of the operating stroke. .

Inservice Testing Coordinator - an individual appointed by the Manager, Technical Division to coordinate the procedures, program and

, testing associated with the inservice testing program in accordance 4- with Reference 2.3.1.

I nonintrusive. test methods - testing methods or technologies (such as acoustic emission, magnetic flux measurement, ultrasonic examination,

or radiography) used in place of disassembly to satisfy exercise j requirements.

4

plant operation - the conditions of startu), o>eration at >ower, hot standby, and reactor cooldom, as defined )y tie plant Tec1nical t ' Specifications.

4 1

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' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023-V-3.5 l UNITS 2 AND 3 REVISION 9 PAGE 8 0F 173 TCN/EC N  :

obturator - valve closure member (disk, gate, plug, ball, etc.)

i operational: readiness - the ability of a valve to perform its intended

['

function.

passive valves - valves which maintain obturator position and are not

, required to change obturator position.to accomplish and required

~ function (s), as specified under 1.4, above.

i preservice test period - the period of. time following completion of j construction activities related to the valve and prior to first t electrical generation by nuclear. heat in which component and system testing takes place.

reactor coolant system pressure isolation - that function which prevents inter-system over-pressurization between the reactor coolant system and connected low-pressure systems.

reference

values - one or more values of test parameters measured or determined when the equipment is known to be operating acceptably.

SRO Operations Supervisor - Any Operations individual holding an SR0' license (active or inactive) who has qualified to the position of

Shift Superintendent or Control Room Supervisor [See Reference 2.4.1, Attachment 1, Definitions).

L Test Interval - This program uses the same test interval definitions 1 l as those used in the Technical Specifications, namely, one month is  !

defined as 31 days and one quarter is defined as 92 days

[ Reference 2.1.6].  !

l g 6.3 Cateaories of Valves j 6.3.1 Valves within the scope of this program shall be placed in one or more of the following categories, l i NOTE: When more than one distinguishing category i characteristic is applicable, all requirements

of each of the individual categories are applicable, although duplication or repetition of common testing requirements is not necessary.

L [ Reference 2.1.3, Para.1.4]

II I i= l Category A - valves for which seat leakage is limited to a - l specific maximum amount in the closed position for i fulfillment of their required function (s), as specified in ,

j. 1.4, above. - 1 i l

v i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE .S023-V-3.5 1 H

UNITS 2 AND 3 REVISION 9 'PAGE 9 0F 173-e 'TCN/EC ' N

, Category 8 valves for which seat leakage in the closed' l position ~ is inconsequential for fulfillment of the '

required function (s), as specified in 1.4,- above.

Category C - valves which are self actuating in response -

to some system characteristic, such as pressure ~(relief '

valves) or flow direction (check valves) for fulfillment.

of the required function (s), as specified in 1.4,' above.

I NOTES: 1. Category D is' defined in the Code, however there i- are no Category D valves at San Onofre and  !

. therefore this program procedure omits all i discussion thereof. 4 1

2. The listing of valves in this program and the Section XI category applicable to each valve is-provided in Attachment 2.

4

.; Category AC - All check valves are Category "C"; however, i

.,' some require that their seat leakage be limited to a j specific amount. In these cases they cre categorized as  !

Category "AC".. )

l 1 i 4 NOTE: The categorization'of a check valve is not dependent l solely on the function performed by the valve, such as - I whether it is a containment isolation valve. If any of the considerations from Reference 2.1.1 indicate that Category "C" testing may not be. adequate, the check valve may be assigned Category "AC" and receive a seat leak test' l as required by this program (See Reference 2.5.2, Question 107].

, j

^

6.4 Resoonsibilities 6.4.1 This program procedure lists testing required to be performed under various implementing procedures. When.

this program procedure is changed, implementing procedures should be updated to reflect these changes prior to the.

next due date for the affected testing = in the plant, or within one month, whichever is later.

.1 The Technical Division shall be responsible for the update and issuance of changes to this program procedure.

L .2 The Operations, Technical and Maintenance Divisions!shall

- be responsible for update and issuance of implementing procedures applicable to the testing for which they are responsible, including such documents as Operating Instructions and Repetitive Maintenance Orders (Reference 2.2.1].

d

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NUCLEAR ORGANIZATION ' ENGINEERING PROCEDURE S023-V-3.5-

LUNITS 2 AND 3 . REVISION 9 PAGE 10 0F 173 b TCN/EC Of 'y- -

a 6.4.2 - Following the' issuance of each significant change.to the  !

inservice testing program, the IST Coordinator shall alert ~.  ;

Nuclear Licensing with a request that they transmit the

{

- change to the NRC. (See Reference 2.5.2, page 1 ,

l

! NOTE:. The Inservice Testing Program is updated at 120 4 .

month intervals. The current interval ends August 17, 2003.  ;

6.4.3 ' When the edition and addendum of the Code are adopted by i SONGS such as at the beginning of a new ten year ~ interval, j the following. individuals and agencies shall be notified and provided a copy of_ the new program: NRC, State of California (See Reference 2.1.7) and.the ANII. . In

addition, the following documents may need updating and shall be reviewed and updated as necessary

UFSAR L Reference 2.1.8 , Valves Relief Requests, TQAN Reference 2.1.7 , and the Technical Specifications j

Reference 2.1.5 . ,

6.4.4 Other Owner's' Responsibilities:

r

.1 The Technical Division or NED0 shall specify acceptance

! criteria and required test conditions. [ Reference 2.1.3, j Para. 2.']

^

.1.1 For each valve to be tested under the IST Program, Attachment 2 identifies the Code Class,Section XI Category and testing requirements. Attachment 2 reflects the detailed implementation of the IST Program (see IST

Topical Report 080, Reference 2.5.1) as discussed in paragraph 1.0, above.

! .1.2 Acceptance Criteria and test conditions are specified in

.- the implementing procedures and the ISTN computer application.

.2 The Technical and Nuclear Engineering Design Divisions 3, shall assure that the design and arrangement of system l

components includes allowances for adequate access-and )

i clearances for conduct of the examination and tests

. [ Reference 2.1.4, Para. IWA

1400(b)].

.2.1 Procedures used by the design organizations reflect the

, detailed implementation of requirements imposed by the IST Program. See References 2.3.4 and 2.3.5.

, 1

.3 Reference 2.2.1 identifies the responsibility of each )

station organization for perfomance of inservice testing l under this program. For their scope of work, each i

. division shall .be responsible for planning and scheduling )

their own tests, including quart 6.rly testing, cold

shutdown testing and reactor refue. ling testing, j [ Reference 2.1.4, Para.IWA-1400(b)].

c

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

NUCLEAR' ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

' UNITS 2 AND 3 REVISION 9 PAGE 11 0F 173-TCN/EC ky 6.4.4.4 Implementing procedures identifying the methods of testing and the components to be tested shall be prepared, issued and controlled by the responsible Divisions for their testing [ Reference 2.1.4, Para.- IWA-1400(d)].

.5 Qualification of personnel who perform the Inservice Testing shall be verified by the responsible Divisions.for their testing [ Reference 2.1.4, Para. IWA-1400(e) and .

Reference 2.3.3].

.6 Each Division shall perform the required Inservice Testing for which their Division is responsible [ Reference 2.1.4, Para. IWA-1400(g) and Reference 2.2.1].

.7 Each Division shall record their Inservice Testing results

.such that the results provide a basis for evaluation and facilitate comparison with the results of subsequent-Inservice Testing [ Reference 2.1.4, Para. IWA-1400(e)].

. .8 Each Division shall provide evaluation of the Inservice Testing results for which they are responsible (Reference 2.1.4, Para.IWA-1400(1)].

4

. NOTE: The Technical Division Cognizant Engineers, l Supervisors and.the IST Coordinator may be i called upon to assist in the evaluation of valve 4 operability when test results indicate a -

potential problem. See step 6.6.4 below.

.9 Maintenance of adequate Inservice Testing records, such as i test data and description of procedures used and evidence

! of personnel qualifications, shall be the responsibility

! of each Division for the testing under its responsibility

!- (Reference 2.1.4, Para. IWA-1400(k)].

• l .10 Ea'ch Division responsible for the creation of the records 1

required by this program procedure shall be responsible i

for formally transmitting these records to CDM on a timely basis for CDM retention.

.11 Cort

• rate Document Management Center (CDN) shall retain

> Inservice Testing records for the service lifetime of the L components (Reference 2.1.4, Para.IWA-1400(1)].

l

[ .

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE. S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 12 0F 173  !

, TCN/EC N 6.5 Testino Reauirements i:

6.5.1- Preservice Testing NOTES

1. This program procedure applies to the second 120 4

month interval for San Onofre Units 2 and 3.

i. .The initial preservice test period is past for the valves in this program. Accordingly, many 4'

of the valves will not have a reference.value for stroke time from a preservice examination  ;

stroke test. In these cases, a reference stroke o time.is identified from past test data when the valves were.known to be operating properly.

This reference value will be noted in the records.

l 2. Preservice' Examination for our plant is

, conducted on newly. installed components as a result of plant design modifications.

1 .

4 i a'  !

.1' Each valve shall' be tested during the preservice test j 4

period as required by Reference 2.1.3. These tests shall  !

4 be conducted under conditions as near as practical to '

those expected during subsequent inservice testing. Only one preservice test of each valve is required except in the following cases [ Reference 2.1.3, Para. 3.1]:

1 t

.1.1 Any valve that has undergone maintenance that could affect its performance after the >reservice test shall be tested

, in accordance'with 6.5.4, )elow; l

l. .1.2 Safety and relief valves shall meet the preservice test requirements of IST Topical Report DBD, Reference 2.5.1.

6.5.2 Inservice Testing i

! .1 Inservice testing in accordance with this program  ;

! procedure shall commence when the valves are required to P be operable to fulfill their required function (s), as

specified in 1.4, above. (Reference 2.1.3., Para. 3.2)

! 6.5.3 Reference Values

.1 Reference values shall be determined from the results of

! preservice testing or from the results of. inservice testing. These tests shall be performed under conditions as near as practicable to those expected during subsequent

inservice testing.

I i

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j i

kb

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

t NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AMD 3 PAGE 13 0F 173

- REVISION 9 @ p 3 , TCN/EC j '6.5.3.2 When reference values are changed,-the reason shall be

documented, a statement of the adequacy of the new value shall be provided, as well as appropriate level of review and approval of the new value before it is used for valve stroke time evaluation.

i .3 When Reference values are initially established or .

I changed, they shall be documented in a controlled manner.

NOTE: The new reference value may be used as soon as i the record discussed in paragraphs 6.5.3.2 and n 6.5.3.3 (which includes an explanation of the reasons for the new value) is approved.

s .

.4 Reference values shall only be established when the valve-is known to be operating acceptably. If the particular-parameter being measured can be significantly influenced

by other related conditions, then these conditions shall be analyzed. ,

6.5.4 Effect of Valve or Actuator Replacement, Repair, and Maintenance on Reference Values NOTE: Adjustments, removal or replacement of stem packing, limit switches, control system valves, bonnet, stem assembly, actuator, obturator, or

! other control system components are examples of

maintenance that could affect valve performance

" parameters such as stroke time.

i-

.1 When a valve or its control system has been replaced, repaired, or has undergone maintenance that could affect

, the valve's performance, then a new reference value shall be determined or the previous value reconfirmed by an

, inservice test run prior to the time it is returned to service or immediately if not removed from service, to demonstrate that performance parameters which could be

. affected by the replacement, repair, or maintenance are within acceptable limits.

.2 Deviations between the previous and new reference values shall be identified and analyzed.

.3 Verification that the new values represent acceptable operation shall be documented in the record of testt,.

.4 . Safety and Relief valves shall be tested as required by the replacement, repair, and maintenance requirements of IST Topical Report DBD, Reference 2.5.1.

-[ Reference 2.1.3, Para.3.4]

1

i l NUCLEAR ORGANIZATION ENGINEERING' PROCEDURE S023-V-3.5 UNITS 2 AND 3 ^ REVISION 9 TCN/EC 9'p PAGE 14 0F 173 i l

j 6.5.5 Establishing an Additional Set of Reference Values

.1. If it is necessary or desirable for some reason, other

than-stated 'in paragraph 6.5.4,. to establish additional - )

references values, an inservice test shall first be run-at- .

. the conditions of an existing set of. reference values, or, l 4 if impractical, at the conditions for which the new-  ;

]

reference values are required, and the results analyzed. I 1

.2 If operation is acceptable in accordance with 6.6.2.6 and i 6.6.3, a second test shall be performed under the new t conditions as soon as practical. The results of.the second test shall establish the additional reference

~

1 values.

' Whenever additiona1' reference values are established, the

.3 reasons for doing so shall be justified and documented.in the record of tests. . [ Reference 2.1.3., Para. 3.5]

6.5.6 Inservice Test Requirements

^

', .1 Active and passive valves in the categories defined under Section 6.3,-shall be tested in accordance with the sections specified in the following Table

[ Reference 2.1.3, Para. 3.6]:

' TABLE 1 INSERVICE TEST REQUIREMENTS NOTE: When more than one distinguishing category characteristic l 1s applicable, all requirements of each of the individual categories are applicable, although duplication or repetition of common testing requirements is not necessary.

l Valve Leakage Test Exercise Test Position Indication

, Category Function Procedure Procedure Verification

+ 'A Active see 6.6.5, see 6.6.5, below. see 6.6.1, below.

A Passive D'I*"* None .

8 Active None see 6.6.2, below.

8 Passive None C(Sofety Active see 6.6.6.1, see 6.6.6.1, below.

andRelief) below.

c(Check Active ~ See 6.6.6, below.

valves)

I

[

r  ! NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5

UNITS 2 AND 3 REVISION 9 PAGE 15 0F 173 TCN/EC--- N

- 6.5.7 Establishing or Revising Valve Strok'e Time Limits:

j .

NOTE: The " Acceptance Limit Change Record",

1 Attachment 5, is used for both modifications.and new additions to acceptance criteria on the

valve list.

.1- New stroke time limits are established and documented' using Attachment 5, " Acceptance Limit Change Record".

They are recorded and controlled in.the ISTN in accordance i with the requirements of that system.- An independent

' verification by a second engineer is required to assure' 4

correctness of the change and the basis used.

.2 Periodically, limits are reassessed and modified as i necessary following review by engineering of the .

historical trends for stroke. time. This is accomplished i approximately biennially and the objective of the i

', Engineering review is to establish reasonable stroke time '

, limits based on historical performance where this is -

appropriate. Guidance in Reference 2.1.9 is used as the basis of this review.

j .3- Affected valves and their safety analysis or Technical

Specification limits for stroke time-are listed in-Attachment 4 to this procedure. These " protected" limits

may not be exceeded. See Reference 2.1.8 and 2.3.7.

l 6.6 Testina Methods 1 6.6.1 Valve Position Verification i

.1 Valves with remote position indicators shall be observed I

,. locally. at least once every 2 years to verify that valve-

[

4 operation is accurately indicated.

.2 Where practicable, this local observation should be supplemented by other indications such as use of flow s meters or other suitable instrumentation to verify e obturator position. These observations need not be concurrent. ,

.3 Where local observation is not possible, other indications )

shall be used for verification of valve operation.

e i

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t t

,--s *- , - - e

, . - . . . - - - . . .-. - . - . - . - - . . . - .- -. . - . . . - - - . . =

.. NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

. UNITS 2 AND JREVISION 9 PAGE 16 0F 173

,TCN/EC- 4M j ' 6.6.2 ' Inservice Tests for Category A and B Valves-

.1 . Exercising Test' Frequency.- Active Category A 'and B valves

shall be tested nominally every 3 months, except as

= discussed in Attachments 2.and 3 [ Reference 2.1.3, Para.4.2.1.1].- ,

NOTE: '"Every 3 months" is the same as quarterly, or

every 92 days, see Reference 2.1.6.

]

l .2 Exercising Requirements. Valves shall be tested as follows _ (Reference 2.1.3, Para. 4.2.1.2, and

' Reference 2.5.3,Section3.1.1]: -

4 l .2.1- Full Stroke during plant operation to the position (s)

- .. required to fulfill its function (s);

} .2.2 If full stroke exercising during plant operations is not i: ..,.

. practicable, it may be limited to part stroke during plant

, operation and full strcke during cold shutdowns; I .2.3 If exercising is not practicable during plant operation, it may be limited to full stroke exercising during cold shutdowns;

.2.4 If exercising is not practicable during plant operation j and full stroke during cold shutdowns is also not i practicable, it may be limited to part stroke during cold g shutdowns, and full stroke during refueling outages;

.2.5 If exercising is not practicable during plant operation or i cold shutdowns, it may be limited to full stroke during refueling outages;

[- ,

.2.6 Valves full stroked at cold shutdowns shall be exercised

- during each cold shutdown, except as specified in the following paragraph. Such exercise is not required if the i time period since the previous full stroke exercise is

less than 3 months.

l NOTE: Three months means 1 quarter or 92 days, see i Paragraph 6.2, above. l 1 .3 Cold Shutdown Testing: Valve exercising during cold -

shutdowns shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48_ hours providad all valves required to be tested during cold l shutdown will be tested prior to plant startup. However, j it is not the intent of this requirement to keep the plant in cold shutdown in order to complete cold shutdown i -- testing.

L ,

)

i

_NUCl. EAR ORGANIZAT!0N ENGINEERING PROCEDURE S023-V-3.5 ,

UNITS 2 AND 3 (REVISION 9 PAGE 17 0F 173 i

! ,TCN/EC N 1-

! 6.6.2.4 Refueling Interval Testing: All valve testi required to I be performed during a refueling outage shall completed prior to returning the plant to operation.

)

NOTE: Before beginning power ascension,' Responsible ' -l

! Divisions normally complete the tests.of those l 1 valves tested at each refueling outage. )

i However, to test any valves that can.only.be c  !

!. tested during power ascension, we raise >ower level and change modes in accordance witi our j Technical S>ecification requirements and test the applica)1e valves when the plant conditions allow testing. If maintenance has been i performed on a valve during the outage, we are

! required t6 consider the valve inoperable until j completing. post-maintenance testing in s

accordance with the operability requirements' .

our Technical Specifications. .See Reference 2.5.3, Para. 3.1.1.2.

e F .5 Valve obturator Novement:_ The necessary valve obturator

_- movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating

lights which signal the required change of obturator

- position, or by observing other evidence, such as changes in system pressure, flow rate, level, temperature, or nonintrusive examination techniques which reflect change

of obturator position. [ Reference 2.1.3, Para. 4.2.1.3]

V

, .6 Power-0perated Valve Stroke Testing

.6.1 Where applicable, requirements records of the ISTN

computer application identify the limiting value(s) of '

full-stroke time of each power-operated valve. Criteria-are estabitshed in accordance with paragraph 6.5.7,.above.

! .6.2 The stroke time of all power-operated valves shall be measured to at least the nearest second.

l .6.3 The valve stroke time is measured with a stopwatch or

' appropriate timing device. The timing device is started

[~ when the valve is actuated and stop>ed when the back light for the desired valve position is tie only ono

, illuminated. '

l .6.4_ Thetestingorganization(ty>icallytheOperations-Olvision) shall record any a > normality or erratic action and evaluate the valve stroke regarding the need for corrective action. The Technical Division may be called upon to assist in this evaluation. (Reference 2.1.3, Para. 4.2.1.4]

C e

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, . ~ ,+r.- 4 .- - . - - ~ . , . . - -

NUCLEAR ORGANIZATION- ENGINEERING' PROCEDURE S023-V-3.5 UNITS 2 AND.3 REVISION 9 PAGE 18 0F 173 4M TCN/EC

~

l 6.6.2.7 Valves in Regular Use: Valves which operate in the course

of plant operation at a frequency which would satisfy the

exercising requirements of this Program Procedure need not

'be additionally exercised,-provided that the observations-

- otherwise required for testing are made and analyzed

during such operation and are recorded in the plant '

records at intervals no greater than specified under

. 6.6.2.1, above.:[ Reference 2.1.3, Para. 4.2.1.5]

.8 Fall-Safe Valves. Valves.with fall-safe actuators shall be tested by observing the operation of the actuator upon

loss of valve actuating power in accordance with the exercising frequency specified under 6.6.2.1, above.

[ Reference 2.1.3, Para. 4.2.1.6]

l i .8.1 Fail-safe testing is' required on1'y for those valves which

stroketested,and,(b) for which

- are required feature the fail-safe to be (a)is a required _ safe function of the ,

valve.

.9 Valves in Systems Out of Service. For a valve in a system declared inoperable or not~ required to be operable, the i

i exercising test schedule need not be followed. Within 3 months prior to placing the system in an operable status, the valves shall be exercised and the schedule followed thereafter in accordance with this program procedure.

1 [ Reference 2.1.3. Para. 4.2.1.7]

^

6.6.3 Stroke Time Acceptance Criteria. Stroke test results shall be compared to the initial reference values or reference values established in accordance with 6.6.2.2 or 6.5.7, above. [ Reference 2.1.3, Para. 4.2.1.8]

.1 Electric-motor-operated valves with reference stroke times greater than 10 seconds shall exhibit no more than

• 15 %

change in stroke time when compared to the reference

, value.

.2 Other power-operai.ed valves with reference stroke times greater than 10 seconds shall exhibit no more than_i 25 %

change in stroke time when compared to the reference value.

. .3 Electric-motor-operated valves with reference stroke times

, less than or equal to 10 seconds shall exhibit no more than i 25 % or i 1 second change in stroke time, whichever 4

.is greater, when compared to the reference value.

.4 Other power-operated valves with reference stroke times less than or equal to 10 seconds shall exhibit no more than i 50 % change in stroke time when compared to the reference value.

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND S . REVISION 9 PAGE 19 0F 173

.TCN/EC N

.6.6.3.5 Valves that stroke in less than 2 seconds are exempted from 6.6.3.3 and 6.6.3.4 above. In such cases the maximum

_ limiting stroke time shall be 2 seconds. This is summarized in the following table:

TABLE 2 ,

SupWARY OF REFERENCE RANGE LIMITS FOR VALVE STRIKE TIME TESTING Valve Actuator Type _ Reference Stroke Limits of Time [T] Range . Reference Range Electric-Motor Operated T > 10 sec

• 15 % of T Other Power Operated T > 10 sec

• 25 % of T

^

Electric-Motor Operated 2 5 T s 10 see i 25 % of T Other Power Operated 2 s T 510 sec

• S0 % of T Any Operator Type- T < 2 sec~ 2 sec '

', 6.6.4 Corrective Action * *

NOTE: The requirements to initiate a Nonconformance Report (NCR) apply to the IST Program. See

,- Reference 2.3.2 for NCR initiation criteria.

.1 Strcke Time Exceeding the Limiting Value: If a valve

. fails to exhibit the required change of obturator position or exceeds the limiting values of full-stroke time, see 6.6.2.6, above, the valve shall be inmediately declared

. inoperable and a Nonconformance Report shall be initiated i by the Division discovering the inoperability.

l [ Reference 2.1.3, Para.4.2.1.9(a)] '

b .1.1 The NCR shall be validated, the operability assessment completed and Operations notified as required by L '

Reference 2.3.2.

i '. 2 Stroke Time Outside the Reference Range: Valves with measured stroke times which do not meet the acceptance i criteria discussed under 6.6.3, above, but are less than the maximum stroke time limit, shall be immediately retested or declared inoperable. An NCR shall be initiated by the Division discovering the inoperability.

F . NUCLEAR.0RGANIZATION~ ENGINEERING PROCEDURE: S023-V-3.5L 1

. UNITS 2 AND 3 REVISION 9 PAGE 20 0F.172L i.

,TCN/EC i

6.6.4.2.1 If the valve is retested and the second set of data 'also.

j' does;not meet the acceptance criteria, the data shall be-

, analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that'the new stroke-time represents acceptable valve operation, or the valve

' shall be declared inoperable. Although 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> is 1

~ allowed, our policy is to complete the analysis as soon as

• is' practical. See discussion in Section 6.7

.2.2- If the second set of data meets the acceptance criteria,

the cause of the initial deviation shall be analyzed and 3

the results documented in the record of tests by .. i i referencing the NCR containing the evaluation and data.  ;

. [ Reference 2.1.3,= Para.' 4.2.1.9(b)] ' i l

.3 Valves declared inoperable may be repaired, replaced,,or the data may be analyzed to determine the cause of the deviation and to show the v' alve to be operating.

1. . acceptably.[ Reference 2.1.3, Para.4.2.1.9(c)]-

o ,

! ..3.1 If valve operability is based upon analysis, the results- -

1  ; .of the analysis shall be in the record of tests by - '

l .

referencing the NCR number containing the evaluation and )

!: data.'[ Reference 2.1.3, Para.~ 4.2.1 9(d)] .

! .3.2 When corrective action.is required as a result of tests

made during cold shutdown, the condition shall be p corrected before startup.

.4 Post-Maintenance Testing: Prior to returning a repaired i or replacement valve to service, a test demonstrating satisfactory operation shall be performed.

!. [ Reference 2.1.3,-Para.4.2.1.9(e)]

[ 6.6.5 Valve Seat Leakage Rate Test

! .1 Scope. Category A valves shall be leakage tested, except valves which function in the course of plant operation in i- r a manner that demonstrates functionally adequate seat

!. leak-tightness need not be additionally leakage tested.

, In such cases, the valve record shall provide the basis l for the conclusion that operational observations  !

constitute satisfactory demonstration [ Reference 2.1.3, i

! Para.4.2.2.1]. ,

l

-12 Containment Isolation Valves. Cat 4

are containment isolation valves, hory all beAtested valves,inwhich '

accordance with Federal Regulation 10CFR50, Appendix J

-(Reference 2.1.12). Containment isolation valves which also provide a reactor. coolant system pressure isoldtion 0 '

function shall' additionally be tested in tecordance with' 6.6.5.3, below. [ Reference 2.1.3, Para. 4.2.2.2].

i 1

2 J

. - - - - - - - - . - . - - vr~ - ~ *., . - - - - - - - , - - . - - , . _a -"- - - a . -

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 c UNITS 2 AND 3 . REVISION 9 PAGE 21 0F 173' l

TCN/EC 9 M' .

l l

!- 6.6.5.2.1: Leakage rate measurements will be compared with previous i measurements and with the permissible leakage rates

, specified using Reference 2.3.6. The acceptance criterion (permissible Leak Rate) for each valve can be determined i by taking the "0.6La"'and subtracting.the leak rates of

all penetrations in the Appendix J Program except the-valve under test. These are available from the records created in accordance with Reference 2.1.12. The result is the seat leakage acceptance criterion of the valve-under test in standard cubic centimeters per minute or other' appropriate units.

NOTE: Seat 1eakage limits that appear in the requirements .

records of the ISTM computer application for Appendix J tests, test type "AJ", are maintenance threshold limits only and do not necessarily reflect the test pass / fail y

g' limits determined using the calculation in the above paragraph.

.2.2 The test medium used for Appendix J, Containment Penetration leak rate tests, will be specified in Reference 2.3.6.

.2.3 [ Reference 2.1.10, Paragraph (b)(2)(vii), Inservice Testing of Containment Isolation Valves] "Mben using subsection IWV in the 1988 Addenda or the 1989 Edition of section XI, Division 1, of the ASME Boiler and Pressure Vessel Code, leakage rates for Category A containment isolation valves that do not provide a reactor coolant system pressure isolation function must be analyzed in accordance with paragraph 4.2.2.3(e) of part 10" [see.

paragraph 6.6.5.3.5, below), "and corrective actions for these valves must be made in accordance with paragraph 4.2.2.3(f) of part 10 of ASME/ ANSI OMA-1988 Addenda to ASME/ANSIOM-1987". [See paragraph 6.6.5.4, below.]

.3 Leakage Rate for other Than Containment Isolation Yalves.

Category A valves, which perform a function other than containment isolation, shall be seat leakage tested to verify their leak-tight integrity. Valve closure prior to seat leakage testing shall be by using the valve operator with no additional closing force applied.

[ Reference 2.1.3, Para. 4.2.2.3]

.3.1 frequency. . Valve Seat Leakage tests shall be conducted at i least once every 2 years [ Reference 2.1.3, l Para.>4.2.2.3(a)].-

.3.2 Differential Test Pressure. Valve seat leakage tests j shall be made with the pressure differential in the same direction as when the valve is with the following exceptions Reference[ performing its function, 2.1.3,'

Para.4.2.2.3(b)].  ;

1 1

(

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE-.S023-V-3.5 UNITS 2 AND.3 . REVISION 9 PAGE 22 0F 173 c

J TCN/EC QM b 6.6.5.3.2.1 Globe-type valves may.be tested with pressure under the ,

seat. l

. 3.2.2 Butterfly valves may be tested in either direction, t

provided their. seat construction is designed for sealing.

against pressure on either side. ,

i I

.. 3.2.3 Double-di n gate valves may be tested by pressurizing. '

between the disks. I

' 3.2.4 Lt.akage tests involving pressure differentials lower than i function pressure differentials are permitted in those types of valves in which service pressure will tend to diminish the overall leakage channel opening, as by-pressing the disk into or onto the seat with greater j force. When leakage' tests ~are made in such cases using pressures lower than function. maximum pressure differential, the observed-leakage shall be adjusted to

. the function maximum pressure differential value. This-

s. adjustment shall be made by calculation appropriate to the

, test media and the ratio between test and function.

/ pressure differential, assuming leakage to be directly 4

proportional to the pressure differential to the _one-half power. Gate valves, check valves, and globe-type valves, i

having function pressure differential applied over the

, seat, are examples of valve applications satisfying this

! requirement. ,

j-j *

. 3.2.5 Valves not qualifying for reduced pressure testing as defined above shall be tested at full maximum functional prossure differential.

1

. 3.3 Seat Leakage #easurement. Valve seat leakage shall be determined by one of the following methods (Reference 2.1.3, Para.4.2.2.3(c)]: ,

3.3.1 measuring leakage through a downstream telltale connection j

while maintaining test pressure on one side of the valve; or

. 3.3.2 measuring the feed rate required to maintain test pressure in the test volume or between two seats of a gate valve,

. provided the total apparent leakage rate is charged to the

. valve or valve combination dr gate valve seat being L tested, and that the conditions required by 6.6.5.3.2, f

above, are satisfied; or j- . 3.3.3 determining leakage by measuring pressure decay in the test volume, provided the total apparent leakage rafe is

charged to the valve or valve combination or gate valve

, seat being tested,.and that the conditions required by e 6.6.5.3.2, above, are satisfied.

i

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- NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3: REVISION 9 PAGE 23 0F 173 TCN/EC N .

4 6.6.5.3.4 Test Mediust. - The test medium shall be specified by the Test Implementing Procedure, in those cases where it is

, not obvious, such as in system piping where either gas and l water may be present during normal system operation

, [ Reference 2.1.3, Para. 4.2.2.3(d)].

1

^

3.5 AnalysisofleakageRates. Leakage rate measurements shall be compared with the permissible leakage rates specified by the implementirxj procedure for a specific valve or valve combination. If leakage rates are not otherwise determined, for implementing procedures, the following rates shall be used [ Reference 2.1.3, Para.4.2.2.3(e)]:

a) for water 0.5D gpm or 5 gpm, whichever is less at function pressure differential; b) for air, at function pressure differential, 7.50 standard cu ft/ day

-, WHERE: 0 - nominal valve size, in. ,

3 ,

.4 Corrective Action. Valves or valve combinations with leakage rates exceeding the values specified by the above criteria (or the_ implementing procedure for the leakage o test) shall be declared inoperable and either repaired or replaced.

[

4 .5 A retest demonstrating acceptable operation shall be performed following any required corrective action before the valve is returned to service [ Reference 2.1.3, Para.4.2.2.3(f)].

.6 Establish or Revising Valve Leakage Rate Limits. New 1eak rate limits are established and dccumented using Attachment 5, " Acceptance Limit Change Record". They are recorded and controlled in the ISTM in accordance with the requirements of that system. An independent verification ,

by a second engineer is required to assure correctness of '

the change and the basis used.

1 6.6.6 Inservice Tests for Category C Valves

.1 Safety Valve and Relief Valve Tests. Safety and Relief Valves listed in Attachment 2 to this program procedure shall be tested in accordance with the inservice testing l requirements of the IST DBD Topical Report, Reference 2.5.1.

.2 Exercising Test Frequency. Check Valves listed'in Attachment 2 shall be exercised nominally every 3 months, except as discussed in Attachments 2 and 3 i

[ Reference 2.1.3, para. 4.3.2.1]. "Three months" means l one quarter or 92 days, see paragraph 6.2, earlier in this program procedure.

I

NUCLEAR ORGANIZATION- ENGINEERING' PROCEDURE S023-V-3.5 UNITS 2 AND 3 PAGE 24 0F 173 REVISION 9 @ p' TCN/EC

! 6.6.6.3 , Exercising Requirements. During plant operation, each l check valve shall be exercised or examined in a manner .

3-which verifies obturator travel to the closed, full-open i or partially open position required to fulfill its i function (Reference 2.1.3, Para.4.3.2.2(a)]. l

[ .3.1 If_ full-stroke exercising during plant operation is not practicable, exercising may be limited to part-stroke i during plant operation and full-stroke during cold i

shutdowns [ Reference 2.1.3, Para. 4.3.2.2(b)].  !

l .3.2 If exercising is not practicable during plant operation,

, it may be limited to full-stroke exercising during cold shutdowns (Reference 2.1.3, Para. 4.3.2.2(c)].

.3.3 If exercising is not' practicable during plant operation and full-stroke during cold shutdowns is also not practicable, exercising may be limited to part-stroke during cold shutdowns, and full-stroke during refueling outages [ Reference 2.1.3, Para. 4.3.2.2(d)].

.3.4 If exercising is not practicable during plant operation or

cold shutdowns, it may be limited to full-stroke during refueling outages [ Reference 2.1.3, Para. 4.3.2.2(e)]. i 1

.3.5 Valves full-stroke exercised at cold shutdowns shall be exercised during each cold shutdown, except as specified below. Such exercise is not required if the time period since the previous full-stroke exercise is less than 3 months (Reference 2.1.3, Para. 4.3.2.2(f)].

.3.6 The rules of paragraph 6.6.2.3 shall' apply to check valve testing at cold shutdown intervals [ Reference 2.1.3, Para.4.3.2.2(g)].

.3.7 All valve testing required to be performed during a refueling outage shall be completed prior to returnin plant to operation [ Reference 2.1.3, Para. 4.3.2.2(h)g ;. the 4

i- .4~ Valves in Regular Use. The rules of Paragraph 6.6.2.7 i shall apply to check valve testing for check valve in L regular use. [ Reference 2.1.3, Para. 4.3.2.3].

.5 Valve obturator Novement

.5.1 The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to.the seat on cessation or reversal of flow, or opens to the position required'to fulfill its function -[ Reference 2.1.3, Para. 4.3.2.4(a)].

t 4

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

UNITS 2 AND 3 . REVISION 9 PAGE 25 0F 173

, , TCN/EC Ol & -

6.6.6.5.1.I' Observation may be by a direct indicator such as -a position indicating device, or by other indicator (s) such as changes in system )ressure, flow rate, level, temperature,. seat. lea (age testing, nonintrusive examination techniques, or other positive means..

NOTE: Currently there are no check valves in this program that use a mechanical exerciser.

i . 5.2 - Disassembly Testing: As-an alternative to the testing in the above paragraph,' disassembly every refueling outage to verify operability of check valves may be used 2

(Reference 2.1.3, Para.4.3.2.4(c)]. A sampling program is also available, see paragraph 6.6.6.6, below, d

4- .. 5.2.1 For. valves identified in Attachments 2 and 3 that are to i be tested by disassedly, the internals shall be visually 1 inspected for worn or corroded parts, and the valve disks j ,'

shall be manually exercised. It shall be verified that 4

. the valve is capable of full-stroking and that the internals of the valve are structurally sound. This i testing shall be conducted at each refueling outage (or at 4 refueling outages on a rotating basis, see paragraph 6.6.6.6,below).

. 5.2.2 One valve of each disassembly group (a group is identified '

as all the valves of the same manufacturer, size, model and service) will be tested each successive refueling outage, until the entire group has been tested.

NOTE: Refer to Attachment 1 for the population of each of the identified valve groups in the IST '

Program.

. 5.2.3 If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of the valve internals, the remaining valves in the disassembly group shall also be disassembled, inspected,

and manually full-stroke exercised during the same outage.

If possible, a partial flow test shall be performed on the disassembled valve followins reassembly, but before it is returned to service.

c . 6 SAMPLING DISASSEMBLY PROGRAM FOR CHECK VALVES: When the IST Coordinator determines it is burdensome to disassemble and inspect all applicable valves each refueling outage, a 1- sample disassembly and-inspection plan for groups of identical valves in similar applications may be employed

, in accordance with References 2.1.3 and 2.1.9, Position 2,

" Alternative to Full Flow Testing of Check valves".

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

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 t UNITS 2 AND 3 REVISION 9 PAGE 26 0F 173 TCN/EC 4'p 6.6.6.6.1 The sample disassembly and inspection program involves grouping similar valves and testing one valve in each  !

group durir , each refueling outage, i

. 6.2 The sampling technique requires that each valve in.the group be the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation.

Additionally, at each disassembly it shall be verified that the disassembled valve is capable of full-stroking- l 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 the disk should be manually exercised.

. 6.3 A different valve of *each group is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the.

entire group has been tested.

, . 6.4 If the disassembled valve is not capable of being

. full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspacted and manually full-stroke

. exercised during the same outage. Once this is completed, the sequence of disassembly must be repeated unless extension of the interval can be justified.

. 6.5 Extension of the valve disassembly / inspection interval to one valve every other refueling outage or expansion of the group size above four valves should only be considered in cases of extreme hardship where the extension is supported by actual in-plant data from previous testing.

Considerations and methodology for justifying this testing is addressed in Generic Letter 89-04 Position 2. '

, (Reference 2.1.9).

. 6.6 Disassembly Group Size Reassessment: When disassembly /

inspection data for a valve group show a greater than 25%

failure rate, a determination will be made and documented (for example, in a memo) by the Cog. Supervisor, assisted by the Cog. Engineer and IST Coordinator, whether the group size should be decreased or whether more valves from the group should be disassembled during every refueling outage (Reference 2.1.9, Position 2).

. 7 Valves in Systems Out of Service. Paragraph 6.6.2.9,

-above applies to check valves in system out of service.

[ Reference 2.1.3, Para.4.3.2.5).

. 8 Open Stroke Testing of Check Valves Using Flow. Full Stroketesting(open)ofcheckvalvesisnormallydone using flow.

5

NOCLEAR ORGANIZATION ' ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 27 0F 173 TCN/EC 4M 6.6.6.8.1 The flow test shall be designed such that degradation of ~

check valve perfomance can be detected. This means that )

rather than specifying only the minimum flow for the test j

- (example: " greater than 2000 gpm"),~ a range of acceptable i

. flow shall be used '(examples: "2000~+_150 gpa", or, "1850 to2150gpa").

.9 . Non-Intrusive (NI) Testing

.9.1 NI Testing is considered as an acceptable (and preferred):

alternative to disassembly for determining the capability to open, close, and fully stroke. (Reference 2.5.3, Section4.1.2).

.9.2 When using non-intrusive testing techniques in a sampling i plan, similar valves'may be grouped for testing purposes, i not to exceed four valves in a single roup, as described .

I inNUREG1482(draft)(Reference 2.5.3 Section 4.1.2 and

~

Generic Letter 89-04 (Reference 2.1.9) Position 2.

, .9.3 Additional guidance on NI testing techniques is provided in S0123-V-5.22 (Reference 2.3.8). l

.10 Corrective Action: If a check valve fails to exhibit the required change of obturator position, it shall be i declared inoperable. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service 1

[ Reference 2.1.3, Para. 4.3.2.6]. I l

.11 When corrective action is required as a result of testing '

during cold shutdown, the condition shall be corrected before startup. 1 l

NOTE: The requirements to initiate an NCR apply to the

• I

IST Program. See Reference 2.3.2 for NCR  !

initiation criteria.

i i

6.6.7 Inservice Tests for Category 0 Valves j

.1 Not applicable. There are no safety-related or important-to-safety Categorf D valves at SONGS.

I j

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i 1

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

. UNITS 2 AND 3 . REVISION 9 PAGE 28.0F 173 i

. TCN/EC h4 l 6.7 Accentance Criteria and Corrective Action I

6.7.1 Acceptance criteria and corrective actions for Category A, B and C valve testing are contained in the implementing

procedures, and as described in this program procedure, in i .the above sections 6.6.3, 6.6.4, 6.6.5.3.5, 6.6.5.4, 6.6.6.10 and 6.6.6.11. [ Reference 2.1.3, Para. 5].

1 6.7.2 During a test, anomalous data with no clear indication of j .the cause must be attributed to the valve under test.

1 When data is recognized as anomalous, a prompt determination of operability is appropriate with follow-on corrective action as necessary. Recalibrating test f

i instruments and then repeating volve tests 'is an L acceptablealternativetothecorrectiveactionofrepair or replacement, but is not an action that can be taken

~

before declaring the valve inoperable. However, if during

, a test it is obvious a test instrument is malfunctioning,

. the test may be halted and the instruments promptly

recalibrhted or replaced. [SeeNRCGenericLetter91-18, l , "Information to Licensees Regarding ... Operability.'] ,

6.7.3 It is appropriace.to validate the data prior to declaring a valve inoperable. Validation (verifying the test was conducted using the required system lineup, instruments were not obviously out-of-calibration, a second check of calculations, etc.) must be coupleted as soon as practical following completion of data gathering phase of the test F when it is probable that the test results do not meet the limiting values for operability. The validation period is provided to obtain management concurrence that the-

Inservice Test results are valid and entry into an L applicable action statement is required. A retest using ,

. recalibrated instrumentation is not allowed as a i validation step.

l

! 6.7.4 If supervision and the assigned tester conclude that the i j test is invalid, the test may be invalidated and the test '

i records not used. IN THIS CASE. A VALID TEST SHOULD BE

COMPLETED ON THE VALVE IN QUESTION A$ $00N AS POS$1BLE l0 l l CONFIRN VALVE OPERABILITY. Performing an invalid test in  !

no way absolves those responsible from compliance with the 4

surveillance requirements and schedules of the Technical-S)ecifications (e.g., IST requirements) as they apply to tle components under test. ,

I c

7 t . . s l NUCLEAR ORGANIZATION- lENGINEERINC PROCEDURE. 5023-V-3.5

~. UNITS 2 AND 3- . PAGE 29 0F 173

. TCN/EC REVISION 4 9. I e

NOTE: -NRC POSITION: The NRC guidance on Technical Specification Clock Policy states that when a 4

test result fails to meet the acceptance-i criterion, regardless of whether the limit is

equal to or more conservative than the Technical

j. Specification limit, .the valve must be J immediately declared inoperable and the . .

4 Technical Specification Action Statement for'the essociated system must.be entered. In: cases j where the required action range limit is more i conservative than its corresponding Technical.

~ Specification limit, the corrective action may.

not be. limited to replacement or repair, but i rather it may consist of an. analysis to demo:istrate that the. specific performance i i. degradation does not impair operability and that the valve will still . fulfill its function, such as delivering the required flow. A new HEFERENCE RANGE and OPERABILITY LIMIT [as l

necessary]hich analysis w would then allow a newmay be established after 7

l determination of operability.

Y "The durations specified by the Code for

analyzing test results have not been accepted by-

! the NRC for postponing entering a Technical l Specification Action Statement. As soon as the 1 data are recognized exceeding the OPERABILITY 3 LlHiI of full-stroke time for valves, the associated component must be declared inoperable L. and, if subject to the Technical Specification, L theAllowedOutageTime(A0T)specifiedinthe.

F action stateme t must be started at the tima the component was declared inoperable." (See Reference 2.1.13.) ,

[' 6.7.5 If supervision determines that the test was valid and the data are outside of the REFERENCE. RANGE or exceed the I OPERABILITY LIMIT, then supervision shall immediately

{ assure an NCR is initiated and validated (including an

[ operability assessment) and notify the SRO Operations

Supervisor.

2

[i- 6.8 Instrumentation'

• 6.8.1 Instrumentation used during valve inservice testing shall -

4 be selected with range and accuracy suitable to the

i. . measurements to be made and shall be in the calibration i

program here at. SONGS, with an appropriate recall date for recalibration, i.

- 6.8.2 - Instrumentation shall not be used for Inservice testing if the recall date has expired.-

F 6.8.3 Instrumentation requirements for safety and relief valve testing are provided in the IST Topical (Reference 2.5.1),

p

..x._

_ _ _,_n._.'_.~l_. ._._,,._.,e , , , , . . , , , , . ,' , , . _ , , , , _ . .,,_,n .,., e . ,, , ,,.,,g.,.,e .

y , , , , ,

I NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 -

l 1 UNITS 2 AND 3- REVISION 9 y .PAGE 30 0F 173-

. TCN/EC 9 '

7.0 RECORDS AND REPORTS

[

~

7.1 Valve ' Records 7.1.1 It is the responsibility of the record originator to

.i provide the record to CDM for retention'. For vendor.

- supplied records and similar non-SCE generated records,.

the Division in receipt of the record is responsible for providing the record to CDM for retention.

7.1.2 The Corporate Document Management Division (CDM) shall

maintain a record which shr.11 include the following for

each valve tested under this program procedure

[ Reference 2.I.3, Para. 6.1]:

l

.1 The manufacturer and* manufacturer's model and serial or other unique ,dentification number.

j. .2 A copy or summary of the manufacturer's acceptance test j--

report if available.

}- 'f '3'

. Preservice test results.

! NOTE: Limiting value of full stroke time is identified in the ISTM computer application. See i Section 6.5.7 for more information.  !

1 7.2 Test Plans (Proaram and Innlementation Procedures) 7.2.1 CDM shall maintain a record of test plans (Program and Implementation Procedures). I NOTE: Implementing Procedures for the Inservice Testing Program should be consistent with the '

requirements of References 2.4.1 and 2.4.2.

7.2.2 The test plans shall include this )rogram procedure and .

implementing procedures from each )ivision for the valve (s) under its responsibility.

7.2.3 Attachment 2 identifies all valves subject to test, the 1 Section XI category of each valve, the tests to be l performed. Attachment 3 provides justifications for 1 testing at other than quarterly intervals.

[ Reference 2.1.3, Para. 6.2] '

7.2.4 Documentation of changes in acceptance criteria shall be made using Attachmert 5, " Acceptance Limit Change Record." 1

' When this record is completed and implemented, it snall be '

transmitted to CDM for permanent retention.

,,._. f,- a a J SJ a%-,p-- +,ia-d., a y W,.me b e e aemT-- -iw *,.es- , " -m-- p .m*

m-I .

'NUCl. EAR ORGANIZATION: ENGINEERING PROCEDURE' S023-V-3.5 F  : UNITS 2 AND 3 - PAGE 31 0F 173

' . REVISION 9 @ p ' ,

lTCN/EC

! 7.0 RECORDS AND REPORTS (Continued) 7.3 Records of Tests 7.3.1 - CON shall maintain a record of each test. ,

a i- 7.3.2 Each Division shall (for the valves under its .

- responsibility) include the following in its records of .

tests sent to CON valve identification (including unit 2,-

common or 3), date of test, reason for test (e.g., post p maintenance, routine inservice' test establishing ~ reference values, etc.), values of measured parameters, identification of instruments 'used, comparisons with ,

allowable ranges-of test values and ~ analysis of deviations, requirement for corrective action, signature

[ of the person or persons responsible for conducting and j y ' analyzing the test. [ Reference 2.1.3, Para. 6.3) i 7.4 Record of Corrective Action i.

', NOTES: 1. The Nonconformance Report (NCR) is the normal vehicle for documenting the record of corrective ,

- action.  !

2. The requirements to initiate an Nonconformance j i Report (NCR) apply to the IST Program. See .

j Reference 2.3.2 for NCR initiation criteria.  !

7.4.1 CDN shall maintain records of corrective action for cases whereitisnotonsecureelectronicmedia(suchasthe

NCRs, see Reference 2.3.2).

7.4.2 - Each Division shall provide a record of corrective action '

that includes a summary of the corrections made and the subsequent inservice tests and confirmation of operation adequacy and the signature of the individual responsible l for corrective action and verification of results 4

[ Reference 2.1.3, Para. 6.4].

i i

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p PCroy:23V35T92.W51

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 I UNITS 2 AND 3- REVISION 9 PAGE 32 0F 173 ATTACHMENT 1 TCN/EC d LISTING - CHECK VALVE AND RELIEF VALVE GROUPS (VALVES GROUPED FOR TESTING)

NOTES: 1. Check valves are grouped on the basis of make/model, size, system, service, orientation and other factors as appropriate to individual systems. Pressure relief / safety valves are grouped similarly. These groupings are used to determine and justify testing and/or disassembly intervals.

2. Each group consists of one group of Unit 2 valves and one group of Unit 3 valves unless otherwise noted.

GROUP 1: SAFETY INJECTION SYSTEN CHECK VALVES S21204NU001, RW Tank T005 to Spray Pump P012 Suction Header, ,

S21204HU002, RW Tank T006 to Spray Pump P013 Suction Header, S31204MU001, RW Tank T005 to Spray Pump P012 Suction Header, and 531204MU002, RW Tank T006 to Spray Pump P013 Suction Header, NOTE: This is a single group consisting of valves from both Unit 2 and Unit 3. The grouping is based on criteria provided in Reference 2.1.9' and Reference 2.5.3, Section 4.1. That is, the four valves ia this group are essentially identical with respect to age, size, model, service, etc.

GROUP 2: SAFETY INJECTION SYSTEN CHECK VALVES ,

S21204MU003, Outlet Check Valve - Containment Emergency Sump S21204MU004, Outlet Check Valve - Containment Emergency Sump

, S31204MU003, Outlet Check Valve - Containment Emergency Sump l S31204MU004, Outlet Check Valve - Containment Emergency Sump NOTE: This is a single group consisting of valves from both Unit 2 and Unit 3. The grouping is based on criteria provided in Reference 2.1.9 and Reference 2.5.3, Section 4.1. That is, the four valves in this '

group are essentially identical with respect to age, size, model, service, etc.

l l GROUP 3: SAFETY INJECTION SYSTEN CHECK VALVES S2(3 1204MUO40, Safety Injection Ttnk T008 Outlet Check Valve, S2(31204MUO41, Safety Injection Tank T007 Outlet Check Valve, ,

S2(31204 MOO 42, Safety lejection Tank T009 Outlet Check Valve, and S2(31204MUO43,SafetyInjectionTankT010OutletCheckValve.

GROUP 4: SAFETY INJECTION SYSTEN CHECK VALVES S2 1204MUO77, LPSI Pump P016 Suction Header Check Valve,

• S2 1204MUO84, LPSI Pump P015 Suction check Valve, '

S2 1204MU199, LPSI Pump P016 Suction Header Check Valve, and S2(3 1204MU201. LPSI Pump P015 Suction Header Check Valve.

ATTACHMENT 1 PAGE 1 0F 3

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

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

. ' UNITS 2 AND 3. REVISION 9 PAGE 33 0F 173 e ATTACHNENT 1 4M 2

-TCN/EC ,

4. i j ' LISTING - CHECK VALVE AND RELIEF VALVE GROUPS (VALVES GROUPED FOR TESTING) 4 GROUP 5: CONTAllelENT SPRAY SYSTEN CHECK VALVES L S2(3)12f l004, Containment 1 solation Stop Check Valve '- Spray Header #1, and  ;

.S2(3)1f J006, Containment Isolation Stop Check Valve - Spray Header #2.  !

j GROUP 6: NAIN STEAN SYSTEN CHECK VALVES L ~ S2(3)130lNU003, Steam Supply - S/G EOS8 to AFP Turbine K007 Check Valve, and,

! S2(3)130lNU005, Steam Supply - S/G E089 to AFP Turbine K007 Check Valve.

1

. \

i NOTEt WedisassembleandinspectbothS2(3)130lNU003 ands 2(3)l30lNU005

every refueling. This change in interval was made as the result of l ' poor valve performance trends, i .

i

. GROUP 7: CONDENSATE Alm FEEDWATER SYSTEN CHECK VALVES.

i' .

i.

S2(3 1305NUO36, Main Feed Check at Steam Generator E089, and, I S2(3 1305NU129, Main Feed Check at Steam Generator E088. l i- GROUP 8: REACTOR COOLANT SYSTEN VALVES

2(3)PSV0200,PressurizerSafetyValve,and, 2(3)PSV0201, Pressurizer Safety Valve GROUP 9: NAIN STEAN RELIEF VALVES F 2 PSV8401, 2(3 PSV8402, 2(3 PSV8403, 2(3 PSV8404, 2(3 PSV8405, 2(3)PSV8406,

.2 PSV8407,- 2(3 PSV8408, 2(3 PSV8409, 2(3 PSV8410, 2(3 PSV8411, 2(3)PSV8412, ,

j -2 PSV8413, 2(3 PSV8414, 2(3 PSV8415, 2(3 PSV8416, 2(3 PSV8417, 2(3)PSV8418 GROUP 10: $AFETY INJECTION SYSTEN RELIEF VALVE

2(3)PSV9349, Shutdown Cooling System Relief Valve From RCS Loop No. 2 e

NOTE: Although this group consists of a single valve, it is considered

a group for purposes of the Code rules for testing of f

safety / relief valves.

i l

[.

ATTACMENT 1 PAGE 2 0F 3

___ _ . _ __ _ i. _ _ _ _ _ _ _ _ _ _ _ . _

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. NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023-V-3.5

. UNITS 2 AND 3: REVISION 9 PAGE 34 0F 173 ATTACHMENT

] .TCN/EC .;

1

' LISTING - CHECK VALVE AND RELIEF VALVE GROUPS (VALVES GROUPED FOR TESTING 1 i

GROUP 11:' NITROSEN GAS RELIEF VALVES

$ 2(3)PSV5403, Nitrogen Gas Relief Valve, Train "A" CCW Surge Tank 2(3)T003l

. 2(3)PSV5404, Nitrogen Gas Relief Valve, Train "B" CCW Surge Tank 2(3)T004

NOTES

1. Although these are non-ASNE Section III Valves, they will be tested-in accordance with OM-1 requirements for Class 2 and 3 Pressure Relief Devices.

2. The Unit 2 valves and the Unit 3 valves are treated as two separate-groups.

• GROUP 12: NITR0 GEN GAS RELIEF. VALVES 1 -

2(3)PSV6414, Train "A" Backup Nitrogen Header Relief Valve, CCW Surge Tank l'

2(3)PSV6420, Train"B"BackupNitrogenHeaderReliefValve,CCWSurgeTank )

NOTES: 1. Although these are non-ASME Section III Valves, they will be tested in 1 accordance with OM-1 requirements for Class 2 and 3 Pressure Relief i Devices.

l 2. The Unit 2 valves and the Unit 3 valves are treated as two separate

groups.

GROUP 13: CONTAINNENT SPRAY SYSTEN VALVES S31206MU012, Spray Pump 3P012 Discharge Stop Check Valve, and,

[ S31206NU014, Spray Pump 3P013 Discharge Stop Check Valve.

l GROUP 14: CONTAINNENT SPRAY SYSTEM VALVES l S31206MUO29, Spray Pump 3P012 Discharge Check Valve to SDCS, and, l

S31206MU030, Spray Pump 3P013 Discharge Check Valve to SDCS.

! GROUP 15: CHILL WATER SYSTEM RELIEF VALVES 2/3PSV9887A, (ME336) Emergency Chilled Water Loop "A" Makeup Water Relief

j. 2/3PSV9887B, (ME335) Emergency Chilled Water Loop "B" Makeup Water Relief i NOTE: This group consists of two valves total in the common section of the Chill Water System.

o GROW 16: CCW SYSTEM RELIEF VALVES 2(3)PSV6356, CCW SURGE TANK T003 RELIEF 2(3)PSV6359,'CCW SURGE TANK T004 RELIEF r

23V35T92.W51 ATTACHMENT 1 PAGE 3 0F 3 l

~ NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2'AND 3: REVISION 9 .. PAGE-35 0F 173 ATTACHMENTf 4-N-TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

.lHQfl

-GENERAL NOTES -37 NOTES- 38 AIR CONDITIONING 42-AUXILIARY BOILER -42

~ AUXILIARY FEEDWATER 42 BORIC ACID MAKEUP -- 4 5 CHEMICAL AND VOLUME CONTROL .47

.' CHILLED WATER 49 '

COMPONENT COOLING WATER 50 CONDENSATE AND FEEDWATER 59 CONTAINMENT HVAC (NORMAL) 61' CONTAIMENT SPRAY 62 DIESEL AIR START 63 DIESEL FUEL OIL 65 DIESEL GENERATOR 66 ESFAS 70 i- FIRE PROTECTION 71 FUEL STOR. POOL & REFUELING 71 GAS RADWASTE 72 r LIQUID RADWASTE 72 NITROGEN GAS ,

73 l NUCLEAR SAMPLING 76 NUCLEAR SERVICE WATER 80 i

ATTACMENT 2 PAGE 1 0F 71 t

1 l

< i

NUCLEAR ORGANIZATION- ' ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 36 0F 173 ATTACHMENT 1 TCN/EC HM LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

INDEX (Continued)

REACTOR C00l'1T 80 4

RESP. & SERVICE AIR 83 3-SAFETY INJECTION 83-l SALT WATER COOLING 97 i

STEAN 100 SUMPS AND DRAINS 105 l f

l 1

1 1

, I 4

9 ATTACMENT 2 PAGE 2 0F 71

. NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE S023-V-3.5

' UNITS 2 AND 3 REVISION 9 'PAGE 37 0F 173 ATTACMENTJ TCN/EC 'fO LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

GENERAL NOTES

' GENERAL NOTE NO. 1 - Values of the acceptance criteria, such as stroke time '

limits and seat leakage criteria, are recorded and controlled in the ISTM application. This application is operated under the jurisdiction of the Quality Assurance Program. Additionally, Attachment 4 provides a list of

. valves with protected stroke time limits.

GENERAL NOTE NO. 2 - Certain valves are grouped for testing in accordance with this program and the' Code (Reference 2.1.3). Attachment I to.this Program Procedure, Listing - Check Valve.and ReliefValve'eroups(ValvesGroupedforTesting),

identifies the valves in each group. Uses of these r groupings are discussed in the provisions of Secticn 6 of

,f this Program Procedure.

GENERAL NOTE NO. 3 Definition of Test Types used in the Valve IST Listing:

~ Abbreviation Definition AJ Appendix J Seat Leakage Test AT Seat Leakage Test BM0 Manual Stroke Open

'BMC- Manual Stroke Closed

~ BMPO .- Partial Manual Stroke Open BMPC Partial Nanual Stroke Closed ,

BTO Stroke Test Open BTC Stroke Test Closed BTP0 Partial Stroke Test Open BTPC- Partial Stroke Test Closed CVTO Check. Valve Stroke Test Open CVTC Check Valve Stroke Test Closed CVP0 . Partial Check Valve Stroke Test Open FSTO. Fail Safe Test Open ,

FSTC ' Fail Safe Test Closed PIT. Position Indication Test RVT Relief Valve Test )

ATTACHMENT 2 PAGE 3 0F 71

. NUCLEAR ORGANIZATION' ' ENGINEERING PROCEDURE- S023-V-3.5 i UNITS 2.AND 3 REVISION 9. PAGE 38 0F 173 l ATTACHNENT L i

'TCN/EC (4 0 1 1

LI'ST OF VALVES WITHIN THE INSERVICE' TESTING PROGRAN-(Continued)

l t

i

. GENERAL NOTES (continued) l l

GENERAL NOTE NO.. 4 - Definition of Test Intervals used in the Valve IST .l Listing

L Abbreviation- Definition L OP Quarterly'(Atleastevery92 days)

CS Cold Shutdown-

- 'RR Reactor Refueling

• See Section 6.6.2.3 for a discussion of Cold Shutdown intervels and testing rules applicable to the cold shutdown interval.

l. ,

• The nominal interval for Reactor Refueling is every two years.

Specific tests are governed by the Technical Specifications, Appendix J, or 0N-10. Exceptions (and the bases therefore) to the two year interval are identified in this attachment and accompanying notes.

4 GENERAL NOTE NO. 5 Nany of the valves in'the listing of this attachment I

! - indicate that the Code Class is "NA". These valves are  !

non-Code valves that have a safety function and therefore I require periodic surveillance. They are listed here in l the IST Program for convenience, however, a missed or l

failed surveillance will not constitute a violation of 1 Technical Specificatior. 4.0.5. See Reference 2.5.2,

, Response to Question #53, and Reference 2.5.3, .

i~ Section 2.2.

! GENERAL NOTE NO. 6 - For test type "AJ", a 25% test interval extension is not l l allowed. Accordingly, a maximum test interval of 730 days i is used for these tests when the nominal interval specified in this attechment is "RR", and a maximum test interval of 92 days is used for these tests when the g 1 j g  !

nominal interval specified in this attachment is "0P". 1

(See Appendix J and the Technical Specifications.) )

l

SPECIFIC NOTES USED IN THE VALVE IST TABLE l

1. This is a control valve. Operability is verified during the IST of .

pump P140. Turbine speed is measured during the test which indicates that

_ this valve is controlling turbine speed. NoCode(OM-10)testsare 4

required. See References 2.1.1 (Document M-90055) and 2.5.3 (NUREG 1482), 8 Section 3.4. F 4

1 l

ATTACHMENT 2 PAGE 4 0F 71

.. .__ _ _ .___ _ ____ _ ___ _ _ _ __ _ _ _U

L ,

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NUCLEAR'0RGANIZATION' ENGINEERING PROCEDURE S023-V-3.5.

UNITS 2 AND 3 REVISION 9: PAGE 39 0F 173-

-ATTACHMENT f L

TCN/EC-- 4M LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM 1- (Continued) ,

2.- These pressure relief devices are tested at the frequency stated in OM-1 (Reference 2.1.2.) Pressure. Relief valve groups are identified in .

2 1 Attachment 1.

3. Themaximum-stroketimes'associatedwiththesevalvesareprotectedvilues and may only be changed under certain circumstances. - See Attachment-4 for -

i a summary of the safety analysis and technical specification stroke time i limits for valves in this program. If a valve stroke time exceeds the

safety' analysis or technical specification limit,-it shall be considered ,

- . inoperable and the Technical Specification _ action statements implemented l

immediately. On the other hand, if a valve exceeds a required action stroke time limit even ifzit is less than the Technical Specification

limit, an NCR shall be generated and the valve evaluated for operability in

• accordance with the NCR program, see Reference 2.3.2. For valves that do not appear in Attachment 4, the limit shown in ISTM.is the only limit and ,

if a valve exceeds this limit, it shall be considered inoperable. l I ~

4. HV4705,2(3)HV4706, F

The maximum allowable stroke times for valves'2(3)d values and may not be 2(3)HV4715,2(3)HV4716and2(3)HV4730areprotecte relaxcd without revision to the disposition of Non-conformance. Report-(NCR) l

[" G-992.  !

I

5. This valve cannot be partially stroke exercised during Plant operation.

6 *. See General Note No. 5. "Autovent" valves S2(3)1413NW458, 459, 460 and

'461 are tested by verifying that no continuous water flow issues form the-

!- 6" open ended SWCS Pump Vent Pipe, when the associated pump is in operation.

L 7. The closed stroke test was added at the recommendation of INP0 to mitigate q

[ an inter-system LOCA in the RCP heat exchanger even though this test is not identified as required in Reference 2.1.1.

u F

8. Reactor Coolant Pumps need not be stopped for cold shutdown valve testing.

!' That is, affected valves may be tested during plant outages when reactor

coolant pumps are stopped for a sufficient period of time and on a

refueling outage schedule, but not more often than once every 92 days. See

. Reference (NUREG 1482), Paragraph 3.1.1.4.

9. NOT USED.

l 10. A " Verify ~ Closed" test is called out for these valves in Reference 2.1.1 in addition to toe Seat Leakage Test.' Stroke testing (exercise testing) is not required.' The leak test is itself verification of " valve closed" and no additional' testing need be specified. Verifying closure in conjunction with the Appendix."J" Seat Leakage Test at refueling intervals is consistent with Reference 2.5.3,-Section 4.1.4.

ATTACMENT 2 PAGE 5 0F 71 f-p l

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__._m - _ _ _ , _ ___ __ _____ _ n _ _____ _ _ _ _ _

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.5 ..

' UNITS 2'AND 3 ' REVISION 9 PAGE-40 0FJ173 1

~ ATTACHMENTJ -

,TCW/EC N.

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

.(Continued) 1 l: v 11. In addition to the tests called out in the following table, additional ,

~

testing of the atmospheric dump valves shall comply with Technical

Specification 4.7.1.6.

~

t

12. 1 Stroke timing not' required. The successful exercise testing of the associated isolation valve (HV4714 or HV4731) confirms the operability of

[ these solenoid valves. See References 2.1.1 (Document M-90055) and 2.5.3 g (NUREG1482),Section3.4. p ,

4

13. -The seat. leakage testing for-these valves.is controlled and conducted in' accordance with Technical Specification Surveillance requirement 4.4.5.2.2.

F 14. The.IST Program requires only specific tests of these valves in accordance ,

with the analysis provided in Reference 2.1.1. -[ Note: @10,#eference 2.1.3, if"used alone, would exempt these valves from testing as passive,'

category B." Accordingly, all Code testing is not necessarily required foreachofthesevalves.)

15. . Test pressure relief valve 2(3)PSV9349 at the frequency stated in the  ;

Technical Specifications.

F 16. Valves $31208MUO94, S31206MU012 (NCR 92010186), S31206MU014 (NCR 92010188),

4 S31206MU029 (NCR 92010189), and S31206MU030 (NCR 92010190) require nonintrusive examination at reactor refueling intervals to satisfy the closed exercise test as they do not have vent valves like the same valvos t at Unit 2. Technical Division is responsible for the completion of the Unit 3 tests. Operations uses conventional methods to test the j corresponding Unit 2 valves.

1-d

17. See General Note 5. These valves are non-code skid mounted valves located

in the lube oil, fuel oil, starting air, or other diesel generator systems.

• Proper operation is verified during regularly scheduled " loaded run" surveillance. This is in agreement with Reference 2.5.3, Section 3.4.

18. This check valv6 is required to undergo a partial stroke test (as a minimum) using flow following disassembly, inspection and reassembly. See '

CL 89-04, Reference 2.1.9.

19. The manual stroke test specified for these valves is only required to be a  ;

partial-stroke to the extent necessary to demonstrate the operation of the valve manually, including the ability to engage the clutch.

20. NOT USED. ,

J 1

. ATTACHMENT 2 PAGE 6 0F 71

' NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE 'S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 41 0F 173

ATTAC MENT 2 TCN/EC 9O LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM.

(Continued)

21. . Stroke. time is not required for Chilled Water system valves 2/3HYJ888A, Emerg. Chiller Water. Loop A - Chiller E336, 2/3TV9720, Control Room Complex 4 Emerg A/C E-419 Coil Temp Cont Valve and 2/3TV9749, Control Room Complex ~

Emerg A/C E-418 Coll . Temp Cont Valve. Operability of these valves is confirmed in conjunction with the Technical Specification testing of the ,

chiller; See Technical Specifications, Paragraph 4.7.5,: and Reference 3 2.1.1 (Document M-90055). k

22. This requires close verification only per Reference 2.1.1. Stroke testing (orexercisetesting)isnotrequired.

. 23. Reference 2.1.1 calls for a Position Indication Test (PIT) on 2(3)HCV9918, 2(3)HCV9945 and S2(3)1312MUO37 and S2(3)1312MU038. These valves are locked in their safety position at all times when they are required by plant mode to perform their safety function. As a consequence, no actual PIT test is [

required. See 5023-0-17, " Locking of Safety-Related Critical Valves and , F.

. -Breakers." Note that if the locking requirement is removed,. a PIT test will be required.

24. In formulating a response to Reference 2.5.4, it was determined that' the test interval for these valves should be revised from Cold Shutdown /

Refueling to Quarterly. The transition to Quarterly is scheduled for full

implementation within 92 days following the Unit'3 Cycle 8 refueling outage (Close of Breakers).

L i

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f i i

i d

4 l

l l

4 ATTACHMENT 2 PAGE 7 0F 71

-f y-- -,---s-

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 l

, ' UNITS 2 AND 3- . REVISION 9 PAGE 42 0F 173 L ' -ATTACHMENTj!. b

.TCN/EC Of "

[]ST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued).

INSERVICE TESTING PROGRAM SYSTEM VALVE LIST: UNITS 2 AND 3

AIR COMITIONING SYSTEM l ~2(3)HCV9918. Hydrogen Purge Exhaust Control Valve-(Code / Category 2/A)-

(6" Butterfly / Manual) Dwg 401728 l AJ/RR-(Note: 23)-

2(3)HCV9945;HydrogenPurgeUnit'A-080DischargeValve(Code / Category 2/A)

(6" Butterfly / Manual) Dwg 401728 4

AJ/RR(Note: 23)

- 2(3)HV9917, Containment Hydrogen Purge Outlet Valve (Code / Category 2/A) i: (6" Butterfly / Motor) Dwg 40172B

, AJ/RR'

.' PIT /RR I 2(3)HV3946, Containment Hydrogen Purge Inlet (Code / Category 2/A) 1 (6" Butterfly / Motor) Dwg 401728 AJ/RR ,

, PIT /RR l i 1500MU038 (3/4-038-C-396), ILRT Pressurization Connection  !

[

S2(3)/

(Code Category 2/A) (3/4" Globe / Manual) Dwg 40171B I AJ/RR-c S2(3)l500MUO39.(3/4-039-C-396), ILRT Pressurization Connection j 4

(Code / Category 2/A) (3/4". Globe / Manual) Dwg 40171B  ;

AJ/RR , {

^

l AUXILIARY 80!LER SYSTEN j S2(3)l312MUO37 (2-037-C-387), Auxiliary Steam Inside Containment Isolation 4

Valve-(Code / Category 2/A) (2" Gate / Manual) Dwg 40169C '

AJ/RR(Note

23) i S2(3)l312MU038 (2-038-C-387), Auxiliary Steam Outside Containment Isolation i Valve (Code / Category 2/A) (2" Gate / Manual) Divg 40169C

'AJ/RR(Note: 23)

AUXILIARY FEEDNATER

!; 2(3)HV4705, AFW Control Valve - Steam Generator E088 (Code / Category 3/8)

(4" Globe / Motor) Dwg 40160A AT/RR~

BTC/0P.(Notes: 3&4) i l -BT0/0P (Notes: 3&4) I PIT /RR ATTACHMENT 2 PAGE 8 0F-71 j

j L i l

i L ' NUCLEAR ORGANIZATION ENGINEERIN' rAOCEDURE S023-V-3.5 UNITS 2 AND 3 -REVISION 9- PAGE 43 0F 173 ATTACHMENT TCN/EC- ci 1@-

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

-2(3)HV4706,: AFW Control Valve - Steam Generator E089 (Code / Category 3/B) ,

. (4" Globe / Motor) Dwg 40160A' I

AT/RR l BTC/0P(Notes: 3&4)

BT0/0P (Notes: 3&4).

j PIT /RR

. 2(3)HV4712, AFW Pump 2P504 Discharge to Steam Generators (Code / Category

3/B) (4" Globe / Motor Dwg 40160A L

BTC/0P (Nrte: 3 '

BT0/0P(Note:'3 PIT /RR i

2(3)HV4713, AFW Pump 2P141 Discharge to Steam Generators (Code / Category-i ~3/B) (4" Globe / Motor Dwg 40160A

, BTC/0P (Note: 3 BT0/0P (Note: 3 l PIT /RR 2(3)HV4714, AFW Isolation Valve-to Steam Generator E088 (Code / Category 2/B)

(6" Globe / Electro Hydraulic) Dwg 40160A i BTC/0P (Note

3)

!. 'BT0/0P(Note: 3) 1 '

FSTC/0P

} PIT /RR 2(3)HV4715,AFWIsolationValvetoSteamGeneratorE089(Code / Category 2/B) i (6" Globe / Motor) Dwg 40160A i BTC/0P(Notes:.314)

BT0/0P(Notes: 3&4) '

l PIT /RR l '2(3)HV4716, AFW Pump Turbine Trip and Throttle Valve (Code / Category NA/B)

. (4" Globe /Notor)Dwg40160B i BTC/0P (Note: 3)

BT0/0P (Notes: 3&4) j- PIT /RR 1

2(3)HV4730, AFW Isolation Valve to Steam Gensrator E088 (Code / Category 2/B)

}- (6" Globe / Motor) Dwg 40160A BTC/0P-(Notes: 3&4).

BT0/0P(Notes:3&4)

PIT /RR ,

2(3)HV4731,' AFW Isolation Valve to Steam Generator E089 (Code /Chtegory 2/B)

(6" Globe / Electro Hydraulic) Dwg 40160A BTC/0P(Note: 3)

BT0/0P (Note: 3) l FSTC/0P PIT /RR j ATTACHNENT.2 PAGE 9 0F 71 i

4 l

2

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. . NUCLEAR ORGANIZATION' ~ ENGINEERING PROCEDURE S023-V-3.5

. UNITS 2 AND 3 REVISION 9 PAGE 44 0F 173

-ATTACHMENT TCN/EC

- 'M l LIST OF' VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

L' 2(3)HV4762, E/H Bypass Valve for AFW Valve HV4712 (Code / Category :f/4)

(4" Globe / Electro Hydraulic) Dwg 40160A BTC/0P (Note: 3).

j PIT /RR.

, 2(3)HV4763,E/HBypassValveforAFWValveHV4713(Code / Category 3/8).

j (4" Globe / Electro Hydraulic) Dwg.40160A BTC/0P(Note: 3) 4 PIT /RR 2(3)HY47142, AFW HV4714 Energize to Open Solenoid. Valve (Code / Category NA/B)-(1/4"3-Way/ Solenoid)Dwg40160C BTC/0P(Note: 12) j BT0/0P f

FSTC/0P l c . 2(3)HY47311, AFW HV4731 Energize to Open Solenoid Valve (Code / Category NA/B) (1/4" 3-Way/ Solenoid) Dwg 40160C

i. BTC/0P(Note: 12)

BT0/0P FSTC/0P i

2(3)SV4700, AFW Pump K007 Speed Controller (Code / Category NA/B) I (4" Globe / Electro Hydraulic) Dwg 40160B BT0/0P (Note: 1)

FST0/0P S2(3)1305NUO88 (8-088-D-212), Drain Valve From Condensate Storage Tank T121

. to T120 Sump (Code / Category 3/B) (8" Gate / Manual) Dwg 401500 l BM0/CS ,

S2(3)1305MU121 (6-121-D-598), AFW Pump P140 Supply to Steam Generator E089 l

! (Code / Category 3/C) (6" Check /Self Actuated) Dwg 40160A l CVTC/CS l CVT0/CS(Note: 5) l S2(3)l305Mul26 (6-126-D-598), AFW Pump P141 Discharge Check Valve ,

l

, (Code / Category 3/C) (6" Check /Self Actuated),Dwg 40160A CVTC/CS

CVT0/CS (Note: 5)

S2(3)1305MU468 (8-468-D-212), AFP P140 Suction Isolation Valve

_(Code / Category 3/B) (8" Gate /Nanual) Dwg 40160A

• BMC/0P (Note: 24) i S2(3)l305MU469-(8-469-D-212), AFP P141 Suction Isolation Valve (Code / Category 3/B)'(8" Gate / Manual) Dwg 40160A BMC/0P(Note: 24) l ATTACHMENT 2 PAGE 10 0F 71

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

NUCLEAR ORGANIZATION- ENGINEERING PROCEDCdE S023-V-3.5

. UNITS 2 ANO 3

~

REVISION 9 PAGE 45 0F 173 ATTACHMENT K N

4 TCN/EC I

' LIST OF VALVES WITHIN'THE INSERVICE TESTING PROGRAM - l

.(Continued) )

i S2(3)1305MU496 (1/2-496-D-617)k/Self ' Actuated) Dwg 40160A-, Ammonia Discha j (Code / Category 3/C)(1/2"Chec 1 CVTC/0P

! .S2(3)l305MU497-(1/2-497-D-617), Hydrazine Pump P037 Discharge Check to AFP-P140 (Code / Category 3/C) (1/2" Check /Self Actuated) Dwg 40160A CVTC/0P

^

S2(3)1305MU498(1/2-498-D-617),AmmoniaDischargeChecktoAFPP141 Suction '

(Code / Category 3/C) (1/2" Check /Self Actuated) Dwg 40160A  !

CVTC/0P-4

! S2(3)1305MU499'(1/2-499-D-617),HydrazinePumpP037DischargeChecktoAFP-

! P141-(Code / Category 3/C) .(1/2" Check /Self Actuated) Dwg 40160A l

CVTC/0P S2(3)l305MU532 (6-532-D-598), AFW Pump P504 Discharge Check Valve (Code / Category 3/C) (6" Check /Self Actuated)_ Dwg 40160A

CVTC/CS

CVT0/CS(Note:.5)

S2(3)l305MU538 (8-538-D-212), AFW Pump P504 Suction Isolation Valve (Code / Category 3/8) (8" Gate / Manual) DWg 40160A BMC/0P (Note: 24) l

. . \

l' , Ammonia Discharge Check to AFP P504 Suction l S2(3)l305MU539 (Code / Category 3/C)(1/2-539-D-617)k/Self (1/2" Chec Actuated) Dwg 40160A

. CVTC/0P. ,

~S2(3)1305MU541 (1/2-541-D-617), Hydrazine Pump P037 Discharge Check to AFP P504 (Code / Category 3/C) (1/2" Check /Self Actuated) Dwg 40160A CVTC/0P

S2(3)l305MU547 (6-547-D-598), AFW Pump P140 Discharge Check Valve F (Code / Category 3/C) (6" Check /Self Actuated) Dwg 40160A

, CVTC/CS j CVT0/CS (Note: 5) 4 BORIC ACID MAKEUP-4 2(3)FV9253, Makeup Water to Volume Control Tank (Code / Category 3/B)

, (3" Globe / Air) Dwg 40125B BTC/0P.

FSTC/0P PIT /RR ATTACHMENT 2 PAGE 11 0F 71 t

b NUCLEAR ORGANIZATION ENGINEERING-PROCEDURE 'S023-V-3.5 l iUNITS'2 AND 3 REVISION 9. . PAGE 46 0F 173

' ATTACHMENT 2 TCN/EC W,

I LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM .

i- (Continued) .

H Y

' 2(3)HV9231, Boric Acid Makeup Pump P175 Recirculation to. Tank T072 ,

(Code / Category 3/B)(2" Globe / Air)Dwg.40125A l

BTC/0P ,

FSTC/0P  !

PIT /RR l

-l 2(3)HV9235, BAMU Tank T072 to Gravity Feed to Charging Pump Suction.

. (Code / Category 3/B) (3" Gate / Motor) Dwg 40125A BMP0/CS-(Note: 19)

. 'BT0/CS (Note: 5) {

PIT /RR I i P P174 Recirculation to Tank T071 j 2(3)HV9236,BoricAcidMakeup/

(Code / Category 3/B)(2" Globe Air 40125A Dwg BTC/0P 1 jl - - , FSTC/0P l 4 .

PIT /RR

~

i 2(3)HV9240, BAMU Tank T071 to Charging Pump Suction Header Control Valve (Code / Category 3/B) (3" Gate / Motor) Dwg 40125A 4 BMP0/CS (Note: 19)

BT0/CS'(Note:'5)

PIT /RR 1

2(3)HV9247, BAMU Pump to Charging Pump Suction Control Valve _(Code / Category '

- 3/B) (3" Gate / Motor) Dwg 40125B BMP0/CS (Note: 19)

BT0/CS (Note: .5)

, PIT /RR l

S2(3)/

(Code Category 3/C) (3" Check /Self Actuated) Dwg 40125B1218MUO33 (3-033-D-l

CVTC/0P l

CVT0/CS S2(3)1218MUO35(3-035-D-676),BAMUPumpP174DischargeCheckValve (Code / Category 3/C) (3" Check /Self Actuated) Dwg 40125B CVTC/0P '

CVT0/CS 4

, S2(3)1218MUO46 (3-046-Y-675), Demineralized Water to Boric Acid Mixing Tee (Code / Category 2/C) (3" Check /Self Actuated) Dwg 40125B CVIC/0P ,

i i

ATTACHMENT 2 PAGE 12 0F 71

_s _..____.______________m__

.- . - . . .. - - . - - . . .. . . - . . - - . . - ~ .

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3- REVISION 9- .PAGE 47 0F 173

- ATTACMENT 4

.TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

,  :(Continued)

CHEMICAL AfG V0LUME C0 E R0L. ,

;2(3)HV9200, Charging Pumps to Regenerative Heat Exchanger E063

, (Code / Category 2/A) (2" Globe / Air) Dwg 40123A

AJ/RR BTC/CS(Note: 15)

BT0/CS-p .FST0/CS

PIT /RR s

b 2(3)HV9205, Regenerative Heat Exchang'er to Letdown Heat Exchanger (Code / Category 2/A) (2" Globe / Air) Dwg 40123A 1

AJ/RR

BTC/CS (Notes

.3&5)

FSTC/CS l PIT /RR. ,

2(3)LV02278, VCT Outlet Valve (Code / Category 2/A) (4" Gate / Motor) Dwg '

40124A-AT/RR BTC/CS(Note: 5).

f.

PIT /RR

' 2(3)TV9267, Letdown Containment Isolation Valve (Code / Category 2/A)

. (3" Gate / Motor) Dwg 40123A

-AJ/RR

BTC/CS (Notes

3&5)

E PIT /RR S2(3)1201MUO31 (3-031-C-170), Purification Valve - Letdown Return to '

, Shutdown Cooling (Code / Category P/A) (3" Gate / Manual) Dwg 401128 AT/RR i .

S2(3)1208MU005(2-005-C-036),CVCStoNo.2HPSIHeaderIsolationValve (Code / Category 2/B) (2" Gate / Manual) Dwg 40112C BM0/0P L S2(3)1208MU015 (4-015-C-675), VCT to Charging Pump Suction Check Valve 1

(Code / Category 2/AC) (4" Check /Self Actuated) Dwg 40124A AT/RR '

CVTC/CS S2(3)1208MU017 (2-017-C-554), Charging Pump P192 Discharge Check Valve

' (Code / Category 2/C) (2" Check /Self Actuated) Dwg 401248 CVT0/0P i

ATTACHMENT 2 PAGE 13 0F 71 i

1'

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

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3c5 I UNITS 2 AND 3, REVISION 91 PAGE 48 0F 173:

ATTACMENT 2 '

a

.TCN/EC GM LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM I .

(Continued)- ,

t S2(3)1208MUO45(1/2-045-C-611), Chemical'AdditionTank-T001.toCharging ,

- Pump Suction Header (Code / Category 2/C) (1/2" Check /Self Actuated) .Dwg -

n 401248.

I CVTC/CS (Note: 22)

S2(3)1208MUO65 2-065-C-036),ChargingPumpCombinationDischargeValveto

. HPSI Header (Co e/ Category 2/B).(2 Gate / Manual) Dwg 401240 m BM0/0P I S2(3)1208MUO66 (2-066-C-554), Charging. Pump Combined Discharge Valve to HPSI Header-(Code / Category 2/C) (2" Check /Self Actuated) Dwg 401248

. , CVT0/CS E S2(3)1208MU067(2-067-C-554),ChargingPumpP190DischargeCheckValve

-(Code / Category 2/C) (2" Check /Self Actuated) Dwg 40124B

j. -, CVT0/0P ,

S2(3)1208MUO69 (2-069-C-554), Cheroing Pump P191 Discharge Check Valve -

-(Code / Category 2/C) (2" Check /Self' Actuated) Dwg 401248

, CVT0/0P S2(3)1208MU082 P190 Suction (Co (de/ Category 2/C)-(3" Check /Self Actuated) 401248 Dwg3-082-C-675)l  ;

j

• CVTC/CS CVT0/CS(Note: 5) t 52(3)1208MUO83 (3-083-C-675)k/Self (Code / Category 2/C) (3" Chec Actuated) Dwg 40124B, BAMU Pumps toi 7: CVT0/CS (Note: 5) i S2(3)1208MUO84 (2-084-C-334), Charging Pump Discharge to Regen Heat l

. Exchanger (Code / Category 2/B) (2" Globe / Manual) Dwg 40123A l

! BMC/CS i S2(3)1208MUO94 (1 1/2-094-C-611), Coolant Polishing Domineralizer to i Charging Pump Suct Header (Code / Category 2/C) (1-1/2" Check /Self Actuated)

Dwg 40124A t

CVTC/CS (Notes: 16&22) ,

S2(3)1208MU122 (2-122-C-554), Charging Pumps Check Valve to Regen Heat '

Exchanger E063 (Code / Category 2/AC) (2" Check /Self Actuated) Dwg 40173A

, AJ/RR

CVTC/RR

• i CVT0/0P 1

l

. ATTACHMENT 2 PAGE 14 0F 71

. NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-305-UNITS 2 AND 3- REVISION 9' - PAGE 49 0F 173

^

/

1 1

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM-(Continued). i

~

L S2(3)1208MU130 (2-130-C-334), Contet Iso 1~'- Chg. Pump Disch to Aux Spray , )

L Regen HX Bypass (Code / Category 2/A)-(2" Globe / Manual) Dwg 40123A AJ/RR BMC/CS ,

BM0/CS 1 PIT /RR CHILLED WATER 2(3)HV9900,'

(Code / CategoryContainment 2/A)-(8" ButterflyCooling Supply

/ Motor Dwg ) Isolation Valve Penetration 45 40170A ')

4 AJ/RR

-BTC/0P (Note: 3)

-PIT /RR

,- 2(3)HV9920, Containment Isolation Valve - Cooling Supply (Code / Category 2/A) (8" Butterfly / Air) Dwg 40170A AJ/RR BTC/0P(Note: 3)

FSTC/0P l PIT /RR 2(3)HV9921, Containment Isolation Valve - Cooling Return (Code / Category l ,

2/A) (8" Butterfly / Air) Dwg 40170A AJ/RR BTC/0P (Note: 3) 3 FSTC/0P i PIT /RR i l 2(3)HV9971, Containment Isolation Valve - Cooling Return, Pen 46 ' l (Code / Category 2/A) (8" Butterfly / Motor) Dwg 40170A l AJ/RR BTC/0P(Note: 3)

PIT /RR 2/3HYJ888A,EmergencyChillerWaterLoopA-ChillerE336(Code / Category 4

NA/B) (1" Gate /Solenold) Dwg 40179A l BT0/0P(Note: 21) ,

2/3PSV9887A, (ME336) Emergency Chilled Water Loop "A" Makeup Water Relief (Code / Category 3/C) (1-1/2" Safety /Self Actuated) Dwg 40179A

RVT/RR (Note

2) 2/3PSV98878, (ME335) Emergency Chilled Water Loop "B" Makeup Water Rslief (Code / Category 3/C) (1-1/2" Safety /Self Actuated) Dwg 40180A RVT/RR (Note: 2)

ATTACHMENT 2 PAGE 15 0F 71

NUCLEAR ORGANIZATIONl ENGINEERING PROCEDURE S023-V-3.5 .

UNITS 2 AND 3 REVISION 9 PAGE 50 0F 173

- ATTACHMENT TCN/EC -

O ,

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM l

. (Continued) --

2/3TV9720, Control Room Complex Emerg A/C E-419 Coil Temp Cont Valve (Code / Category 3/8) (4" 3-Way/ Electro Hydraulic) Dwg'401808 BTC/0P (Note: 21) ,

1 BT0/0P 2/3TV9749, Control Room Complex Emerg A/C E-418 Coil Temp Cont Valve

-(Code / Category 3/B)- (4" 3-Way/ Electro Hydraulic) Dwg 401798 BTC/0P(Note:'21)~

BT0/0P SA1417MU136 (1-136-D-639), (ME 335) Check Valve to Prevent Leakage and Backflow on NSW-(Code / Category 3/AC) (1" Check /Self Actuated) Dwg 40180A AT/RR CVTC/RR t

.- SA1417MU138 (1-138-D-639), (ME 336) Check Valve to Prevent Leakage and -j

. Backflow on NSW (Code / Category 3/AC) (1" Check /Self Actuated) Dwg 43179A 1 I

AT/RR CVTC/RR SA1513MU830 (1 1/8-830-D *), Aux Bldg Emerg Chiller E336 011 Cooler Gatlet Check Valve (Code / Category 3/C)- (1-1/8" Check /Self Actuated) Dwg 40179E CVT0/0P SA1513MU835 ,, 1/8-835-D *), Aux Bldg Emerg Chiller E335 011 Cooler Outlet )

Check Valve (Code / Category 3/C) (1-1/8" Check /Self Actuated) Dwg 401800-CVT0/0P COMPONENT C0OLING WATER 2(3)HV6211, Containment Isolation Valve - CCW Non-Critical Loop (Code / Category 2/A) (10" Butterfly / Motor) Dwg 40127F AJ/RR BMP0/CS (Notes: 5&l9) i BTC/CS (Note: 3)

BT0/CS l PIT /RR l i 2(3)HV6212, CCW from Heat Exchanger E001A to'Non-Critical Loop l (Code / Category 3/A) (28" Butterfly / Air) Dwg 40127D '

AT/RR l BMP0/CS (Note: 19)

BTC/CS (Note: 3) '

1 BT0/CS FSTC/CS PIT /RR L

4 ATTACHMENT 2 PAGE 16 0F 71 n.

6 1

' NUCLEAR ORGANIZATION ,

ENGINEERING PROCEDURE SO23-V-3.5

. UNITS 2-AND_3 ' REVISION 9. .

PAGE 51 0F 173 ATTACHMENT u g, M p TCN/EC l

LIST OF VALVES WITHIN THE' INSERVICE TESTING PROGRAM

~

(Continued)_

t 2(3)HV6213f Component Cooling Discharge to Non-Critical Loop'(Code / Category . ..

[

s 3/A)- (28" Butterfly / Air) Dwg 401270 AT/RR BMP0/CS (Note: 19)

-BTC/CS.(Note: 3)'

BT0/CS-

{ FSTC/CS-

. PIT /RR.

2(3)HV6216, containment Isolation - CCW Non-Critical Loop Return l l(Code / Category 2/A) (10" Butterfly / Motor) Dwg 40127F AJ/RR BMP0/CS (Notes: 5&l9)'

= BTC/CS.(Note: 3)

'BT0/CS i PIT /RR' 2(3)HV6218, Component Cooling Water Pump Suction From Non-Critical Loop (Code / Category 3/A) (28" Butterfly / Air) Dwg 40127A AT/RR BMP0/CS (Notes: 5&l9)

BTC/CS-(Note: 3)

BT0/CS

, FSTC/CS PIT /RR 2(3)HV6219, Component Cooling Water Pump Suction From Non-Critical Loop (Code / Category 3/A) (28" Butterfly / Air) Dwg 40127A AT/RR BMP0/CS (Notes: 5&l9) ,

BTC/CS(Note: 3)

BT0/CS FSTC/CS PIT /RR 2(3)HV6220, CCW Pump P025 Miniflow Block Valve to Critical Loop "A" Hdr (Code / Category 3/A) (10" Butterfly / Motor) Dwg 40127A AT/RR .

2(3)HV6221, CCW Pump P025 Miniflow Block Valve to Critical Loop "B" Hdr (Code / Category 3/A) (10" Butterfly / Motor) Dwg 40127A AT/RR 2(3)HV6222A, CCW Pump P025 Suction from Critical Loop "A" Return Header (Code / Category 3/A) (28" Butterfly / Motor) Dwg 40127A AT/RR 2(3)HV6222B, CCW Pump P025 Suction from Critical Loop "A" Return Header

(Code / Category 3/A) (28" Butterfly / Motor) Dwg 40127A '

'AT/RR ATTACHMENT 2 PAGE 17 0F 71

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

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5  !

UNITS 2'AND 3 REVISION 9 : . PAGE 52 0F 173 ATTACIMENT 2j-A r TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)-

2(3)HV6223, Containment Isolation - CCW Non-Critical Loop Supply- ' ,

.(Code / Category 2/A). (10". Butterfly / Motor) Dwg 40127F

AJ/RR

. .BMP0/CS (Notes: 5&l9) 4-BTC/CS(Note:'3) ,

e BT0/CS

, PIT /RR 2(3)HV6224A, CCW Pump P025 Suction'from Critical Loop "B" Return Header (Code / Category.3/A)-(28". Butterfly / Motor) Dwg 40127A

. AT/RR.

4 2(3)HV62248, CCW Pump P025 Suction from Critical Loop "B" Return Header

~

(Code / Category 3/A) (28" Butterfly / Motor) Dwg.40127A AT/RR

' 2(3)HV6226A, CCW Pump P025 Train "A" Discharge Valve (Code / Category 3/A) j' (28" Butterfly / Motor) Dwg 40127A AT/RR i-2(3lHV62268, CCW Pump' P025 Train "A" Discharge Valve (Code / Category 3/A)

!. (28 Butterfly /Notor) Dwg 40127A ,

AT/RR. l 2(3)HV6227, CCW Critical Loop "A" Supply to CCW Pump P025 Motor i (Code / Category 3/A) (3" Gate / Motor) Dwg 40127A

~

AT/RR.

2(3}HV6228A, CCW Pump P025 Train "B" Discharge Valve (Code / Category 3/A)

(28 Butterfly / Motor) Dwg 40127A

)

i AT/RR 2(3)HV62288, CCW Pump P025 Train "B" Discharge Valve (Code / Category 3/A)

(28" Butterfly / Motor) Dwg 40127A AT/RR

2(3)HV6229, CCW Critical Loop "B" Supply to CCW Pump P025 Motor

, (Code / Category 3/A) (3" Gate /Notor) Dwg 40127A j AT/RR i

j

.2(3)HV6236, Containment Isolation - CCW Non-Critical Loop Return '

(Code / Category 2/A) (10" Butterfly / Motor) Dwg 40127F

. AJ/RR *

, BMP0/CS (Notes: 5&l9)

BTC/CS (Note: 3)

BT0/CS

. PIT /RR i

i

ATTACIMENT 2 PAGE 18 0F 71

NUCLEAR ORGANIZATION ENGINEERING' PROCEDURE 'S023-V-3.5-

. UNITS-2 AND'3  : REVISION 9,. PAGE.53 0F 173 i l

' ATTACHMENTg'y1 TCN/EC LIST OF VALVES WITHIN-THE INSERVICE TESTING PROGRAM l (Continued). j er E062 CCW Return to Critical ~ Loop _"A" L2(3)HV6293A,LetdownHeatExchang/

(Code / Category 3/A) (8" Butterfly Air)Dwg'40127E' '

.AT/RR FSTC/0P 2(3)HV6293B, Letdown Heat Exchanger E062 CCW Supply Fm Critical: Loop "A" (Code / Category 3/A) (8" Butterfly / Air) Dwg 401270

~

AT/RR-FSTC/0P.

2(3)HV6366, Component Cooling Water to Emergency Cooling Unit E-401.

'(Code / Category 2/A) (8" Gate / Motor) Dwg 40172B' AJ/RR BTC/0P BT0/0P(Note: 3)

, PIT /RR 2(3)HV6367,ComponentCoolingWatertoEmergencyCoolingUnitE-401 (Code / Category 2/A) (8" Gate / Motor) Dwg 401728 AJ/RR BTC/0P.

BT0/0P(Note:3)~

PIT /RR 2(3)HV6368, Component Cooling Water to Emergency Cooling Unit E-400 (Code / Category 2/A) (8" Gate / Motor) Dwg 401728 AJ/RR BTC/0P BT0/0P(Note: 3)

PIT /RR ,

2(3)HV6369, Component Cooling Water to Emergency Cooling Unit E-400 (Code / Category 2/A) (8" Gate / Motor) Dwg 40172B

' AJ/RR

' BTC/0P BT0/0P(Note: 3)

PIT /RR

.2(3)HV6370, Component Cooling Water to Emergency Cooling Unit E-399 (Code / Category 2/A)(8" Gate / Motor)Dwg 401728 1

AJ/RR

,. BTC/0P BT0/0P(Note: 3)

• PIT /RR ATTACHMENT 2 PAGE 19 0F 71

. . a e s --ve--,- a s. .. ,- > ~ * -- m - . = . - - = - x <~s

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 . PAGE 54 0F 173 ATTACHMENT 2 1TCN/EC HN LIST OF VALVES WITHIN THE INSERVICE TESTING PROGPAM (Continued) 2(3)HV6371,ComponentCoolingWaterRet.fromEmergCoolingUnitE-399 ,

(Code / Category 2/A).(8" Gate / Motor)Dwg40172B AJ/RR BTC/0P .

BT0/0P(Note: 3)

- PIT /RR 2(3)HV6372,ComponentCoolingWatertoEmergencyCoolingUnitE-402 (Code / Category 2/A):(8" Gate / Motor) Dwg 40172B AJ/RR '

BTC/0P BT0/0P(Note:-3)

PIT /RR 2(3)HV6373, Component Cooling Water to Emergency Cooling Unit E-402

, (Code / Category 2/A) (8" Gate / Motor) Dwg 40172B AJ/RR-BTC/0P .

BT0/0P (Note: 3)

PIT /RR 2(3)HV6500, Component Cooling Water from SDCS Heat Exchanger E003 (Code / Category 3/B) (18" Butterfly / Air) Dwg 40127E BT0/CS (Notes: 3&5)

L FST0/CS PIT /RR 2(3)HV6501,ComponentCoolingWaterfromSDCSHeatExchangerE004  ;

. (Code / Category 3/B) (18" Butterfly / Air) Dwg 40127E  !

t BT0/CS(Notes: 315) '

1

+

FST0/CS  ;

PIT /RR 2(3)HV6522A, Letdown Heat Exchanger E062 CCW Return to Critical Loop "B" (Code / Category 3/A) (8" Butterfly / Air) Dwg 40127E AT/RR l j FSTC/0P i 2(3)HV65228, Letdown Heat Exchanger E062 CCW' Supply Fm Critical Loop "B" 1

(Code /Cctegory 3/A) (8" Butterfly / Air) Dwg 40127C AT/RR

FSTC/0P p 2(3)HV6551, CCW Pump P025 Miniflow Block Valve to Critical Loop "A" Rdr

(Code / Category 3/A) (10" Butterfly / Motor) Dwg 40127A

, - AT/RR ATTACHMENT 2 PAGE 20 0F 71

NUCLEAR ORGANIZATION. ENGINEERING PROCEDURE S023-V-3.5 .

I

'. UNITS 2'AND 3 .c'

- REVISION 9' PAGE 55 0F 173 l

ATTACHNENT 1 W4 TCN/EC

' LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3)HV6552, CCW Pump P025 Miniflow Block Valve to Critical Loop "B"-Hdr (Code / Category 3/A) (10iButterfly/Notor) Dwg 40127A AT/RR 2(3)HV6569,PPMU'toCCWLoop"B"MakeupDischargeValve(Code / Category 2/B)

(1" Ball /Alr) Dwg 40127J BTC/0P ',

'BT0/0P (Note: 3)

FST0/0P PIT /RR 2(3)HV6570, PPMU to CCW Loop "A" Nakeup Discharge Valve.(Code / Category 2/B)

(1" Ball / Air) O g 40127J BTC/0P.

BT0/0P(Note: 3)

, . FST0/0P J . PIT /RR 2(3)PCV6358, CCW Surge Tank T003A Nitrogen Back-Pressure Regulator (Code / Category 3/A) (1" Globe / Air) Dwg 40127B AT/RR BTC/RR 2(3)PCV6361, CCW Surge' Tank T0048 Nitrogen Back-Pressure Regulator

'(Code / Category 3/A) (1" Globe / Air) Dwg 401278 1 AT/RR BTC/RR 2(3)PSV6356, CCW Sur e Tank T003 Relief (Code / Category 3/C) (1x2" )

Safety /Self Actuated Dwg 401278 , )

RVT/RR(Note: 2  !

d 2(3)PSV6359, CCW Surge Tank T004 Relief (Code / Category 3/C) (1x2" Safety /Self Actuated) Dwg 40127B i RVT/RR (Note: 2) )

i 2(3)TV9144, CCW From RCP P001 Seal Heat Exchanger (Code / Category 3/B) (1 1/2" Globe / Motor)Dwg40130A ,

BMP0/CS(Notes: 8&l9)

BTC/CS(Note: 7)

BT0/CS

! 2(3)TV9154,CCWFrom.RCPP003SealHeatExchanger(Code / Category 3/B)-(1 1/2" Globe / Motor) Dwg 401308 l BMP0/CS (Notes: 8&l9)

BTC/CS(Note: 7)-

BT0/CS~

ATTACHNENT 2 PAGE 21 0F 71 1

1 i

l

_----_:_ -__-_. ____=_____ __ ._- - , . . . - - . , , , , .. , , . .

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

+

s  ! NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 h '

~ UNITS 2 A E 3- -REVISION 9- PAGE 56 0F 173 ATTACHMENT 1 p TCN/EC N:

~ LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

(Continued) I Y l 1 l I

I 2(3)TV9164, CCW From RCP P004 Seal Heat' Exchanger (Code / Category 3/B) -(1 ,

( 1/2" Globe / Motor)Dwg 401300

.BMP0/CS (Notes: 8&l9)~ .,

BTC/CS (Note: 7) )

BT0/CS l 5 2(3)TV9174, CCW From RCP P002 Seal Heat' Exchanger (Code / Category 3/8) (l' 1/2".-Globe / Motor)Dwg 401300

, BMP0/CS (Notes: 8&l9)

BTC/CS(Note: 7) '

i

BT0/CS S2(3)1203MU001. (8-001-D-801), CCW Supply to Control Room Emergency Chiller

E336 (Code / Category 3/A) (8" Ball / Manual) Dwg.40179A  !

j AT/RR ]

l S2(3)1203MU003 (8-003-D-801), CCW Return from Control Room Emergency 1

Chiller E336 (Code / Category 3/A) (8" Ball / Manual) Dwg 40179A

, AT/RR

'S2(3)1203MU007 (8-007-D-801), CCW Return from Control Room Emergency Chiller E335 (Code / Category 3/A) (8" Ball / Manual) Dwg 40180A AT/RR

S2(3)1203MU101 (28-101-D-725), CCW Pump P024 Discharge Check Valve

(Code / Category 3/C) (28" Split Disc Check /Self Actuated) Dwg 40127A 4

CVP0/0P CVTC/0P

CVT0/CS i '

S2(3)1203MU102 (28-102-D-725), CCW . Pump P026 Discharge Check Valve

(Code / Category 3/C) (28" Split Disc Check /Self Actuated) Dwg 40127A CVP0/ 0P

! CVTC/0P i' CVT0/CS S2(3)1203MU103 (28-103-D-725), CCW Pump P025 Discharge Check Valve i (Code / Category 3/C) (28" Split Disc Check /Self Actuated) Dwg 40127A

CVP0/0P

. CVTC/0P '

1 CVT0/CS i

S2(3)1203MU104 (1 1/2-104-D-387), CCW Pump P024 to Chemical Feeder W009

Isolation Valve (Code / Category 3/A) (1-1/2" Globe / Manual) Dwg 40127A' i- AT/RR S2(3)1203MU105 (1 1/2-105-D-387), CCW Pump P026 to Chemical Feeder W009 Isolation Valve (Code / Category 3/A) (1-1/2" Globe / Manual) Dwg 40127A

AT/RR a ATTACHMENT 2 PAGE 22 0F 71 l

i l

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 )

UNITS 2 AND 3 REVISION 9 PAGE 57 0F 173 1 ATTACHMENTg'p TCN/EC

, LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

S2(3)1203MU106 (11/2-106-D 387), CCW Pump P025 to Chemical Feeder WOO 9 Isolation Valve-(Code / Category 3/A) (1-1/2". Globe / Manual) Dwg 40127A

.AT/RR S2(3)1203MU108 (2-108-D-387), CCW Critical Loop "B" From Chem Feeder WOO 9 Isolation Valve (code / Category 3/A) (2" Globe / Manual) Dwg 401278 AT/RR S2(3)1203Mul09 (2-109-D-387), CCW Critical Loop "A" From Chem Feeder WG09

. Isolation Valve (Code / Category 3/A) (,2" Globe / Manual) Dwg 401278 AT/RR S2(3)1203MU124 (3-124-D-221), CCW Surge Tank MT-003 Drain (Code / Category 3/8) (3" Gate / Manual) Dwg 401278 BM0/0P i S2(3)1203MU125 (3-125-D-221), CCW Surge Tank MT-004 Drain (Code / Category

3/8) (3" Gate / Manual) Dwg 401278

BM0/0P S2(3)1203MU180 (8-180 D 801), CCW Supply to Control Room Emergency Chiller l E335 (Code / Category 3/A) (8" Ball / Manual) Dwg 40180A AT/RR l 4

l S2(3)1203MU181 (8-181-D-801), CCW Return from Control Room Emergency l Chiller E335 (Code / Category 3/A) (8" Ball / Manual) Dwg 40180A l AT/RR l S2(3)1203MU185 (8-185-D-801), CCW Supply to Control Room Emergency Chiller E336 (Code / Category 3/A) (8" Ball / Manual) Dwg 40179A ,

AT/RR l

S2(3)1203MU186 (8-186-D-801), CCW Return from Control Room Emergency Chiller E336 (Code / Category 3/A) (8" Ball / Manual) Dwg 40179A

AT/RR S2(3)1203MU231 (2-231-D-387), Isolation Valve - CCW Ret From HPSI P018 to ,

Loop "B" Header (Code / Category 3/A) (2" Globe / Manual) Dwg 40127E I AT/RR l S2(3)1203MU232(2-232-0-387), Isolation Valve - CCW Rat From HPSI P018 to Loop "A" Header (Code / Category 3/A) (2" Globe / Manual) Dwg 40127E AT/RR ,

S2(3)1203MU243 (8-243-D-801), CCW Supply to Control Room Emergency Chiller ,

E335(Code / Category 3/A)(8" Ball / Manual)Dwg40180A AT/RR ATTACHMENT 2 PAGE 23 0F 71

.HUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 i UNITS 2 AND 3 REVISION 9 PAGE 58 0F 173.

jf &

4 LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM l (Continued)

S2(3)1203MU258 (2-258-D-387),-Isolation Valve - CCW Supply to HPSI P018 (Code / Category 3/A) (2" Globe / Manual) Dwg 401270 AT/RR -  ;

1 S2(3)1203MU259'(2-259-D-387), Isolation Valve - CCW Supply to HPSI P018 i

-(Code / Category 3/A)-(2" Globe / Manual) Dwg 40127D.

. AT/RR

S2(3)1203MU268 (1-268-D-627), Nuclear Plant Service Water Supply to CCW i Loop A'(Code / Category 3/AC) (3" Check /Self Actuated) Dwg 401278 AT/RR CVTC/CS.

S2(3)1203HU269 (1-269-D-627), Nuclear Plant Service Water Supply to CCW

, Loop B (Code / Category 3/AC) (3" Check /Self Actuated) Dwg 40127B c AT/RR ,

CVTC/CS i 3)1203MU280 (1 1/2-280-D-554), Check Valve - CCW to RCP P001 Seals S2(de/

(Co Category 3/C) (1-1/2". Check /Self Actuated) Dwg 40130A 4- CVTC/CS (Notes: 7&8)

CVT0/0P

S2(3)1203MU281 (1 1/2-281-D-554), Check Valve - CCW to RCP P002 Seals (Code / Category 3/C) (1-1/2" Check /Self Actuated) Dwg 40130B 4

CVTC/CS (Notes: 7&8) l- CVT0/0P S2(3)1203MU282 (1 1/2-282-D-554), Check Valve - CCW to RCP P003 Seals (Code / Category 3/C) (1-1/2" Check /Self Actuated) Dwg 401300 '

CVTC/CS (Notes: 7&8)

CVT0/0P S2(3)1203MU283(11/2-283-D-554),CheckValve-CCWtoRCPP004 Seals (Code / Category 3/C) (1-1/2" Check /Self Actuated) Dwg 401300 CVTC/CS (Notes: 7&8)

CVT0/0P S2(3)1203MU305(3-305-D-681),~CCWEmergencyRakeupCheckValve (Code / Category 3/AC) (3" Check /Self Actuated) Dwg 401278 '

AT/RR.

-CVTC/0P CVT0/0P ,

S2(3)1203MU307 (3-307-D-681), CCW Emergency Mkeup Check Valve - Tank MT004

.(Code / Category 3/AC) (3" Check /Self Actuated) Dwg 401278 AT/RR-CVTC/0P

.CVT0/0P ATTACHMENT 2 PAGE 24 0F 71 1

d

"_.__.______ir'__.___________________

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

NUCLEARORGANIZATION! ENGINEERING PROCEDURE. S023-V-3.5-UNITS 2 AND 3 ~ REVISION 9' PAGE 59 0F 173 ATTACHMENT TCN/EC p ,

' LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAN i (Continued) 3 S2(de/ Category 3/AC) (1 1/2", Check /Self Actuated) Dwg 40127J -3)1203MU736'

(Co -

AT/RR CVTC/0P l CVT0/0P S2(3)1203MU737 (1 1/2-737-D-617), PPMU to CCW Train "B" Makeup Discharge-(Code / Category 3/AC) (1 1/2" Check /Self Actuated) Dwg 40127J

, AT/RR CVTC/0P '

i 'CVT0/0P ,

[

S2(3)1203MU740 (1-740-0-108), CCW Makeup Pump P1018 Test Loop Inlet Isolation Valve (Code / Category 3/A) (1" Gate / Manual) Dwg 40127J

. AT/RR-

.' S2(3)1203MU741(1-741-D-108),CCWMakeupPumpP1019TestLoopInlet Isolation Valve (Code / Category 3/A) (l" Gate / Manual) Dwg 40127J AT/RR COM ENSATE AM FEEDWATER

'2(3)HV1105, Feedwater Bypass Valve for Steam Generator E089 (Code / Category HA/B) (6" Gate / Air) Dwg 401568 BTC/CS (Note: 3)

FSTC/CS f -

PIT /RR 4

2(3)HV1106, Feedwater Bypass Valve for Steam Generator E088 (Code / Category NA/B) (6" Gate / Air) Dwg 401568 ,

[ BTC/CS (Note: 3)

FSTC/CS PIT /RR 2(3)HV4047, Feedwater Block Valve - Steam Generator E088 (Code / Category g NA/B) (16" Gate / Electro Hydraulic) Dwg 40156B BTC/CS (Notes: 3&5) j' FSTC/CS '

i PIT /RR L

L 2(3)HV4048, Feedwater Isolation Valve - Steam Generator E088 (Code / Category 2/B) (16" Gate / Electro Hydraulic) Dwg 401568 BTC/CS-(Notes: 3&5) *

. FSTC/CS p PIT /RR I'

ATTACHMENT 2 PAGE 25 0F 71 1

> NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 1 REVISION 9 PAGE 60 0F.173

' TCN/EC ATTACHMENT m' f@

i LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM 1 t

-(Continued).

]

2(3)HV4051,' Feedwater Block Valve - Steam Generator E089 (Code / Category ,

l NA/B) (16" Gate / Electro Hydraulic) Dwg 401568 l 1

BTC/CS(Notes:S&5)

FSTC/CS

. PIT /RR.

2(3)HV4052, Feedwater Isolation Valve '- Steam Generator E089 (Code / Category

' ~'

2/B)-(16"' Gate / Electro Hydraulic) Dwg 40156B BTC/CS-(Notes: 3&5)

FSTC/CS ,

PIT /RR -1 i 2(3)HV5715, Condensate Tank T120 Isolation Valve (Code / Category NA/B)-

(6" Butterfly / Manual) Owg 401500 BMC/0P i- S2(3)1305MUO36(20-036-C-609)',MainFeedCheckatSteamGeneratorE089 l (Code / Category 2/C) (20" Check /Self Actuated) Dwg 40141A

- CVTC/RR(Note: 18) t S2(3)1305MU124 (4-124-C-599), AFW Check Valve at Steam Generator E089 1

'(Code / Category 2/C) (4" Check /Self Actuated) Dwg 40141A.

I

. CVTC/CS e

CVT0/CS (Note: 5)

S2(3)1305MU129 (20-129-C-609), Main Feed Check at Steam Generator E088 l (Code / Category 2/C) (20" Check /Self Actuated) Dwg 40141A j CVTC/RR(Note: 18)

? S2(3)1305MU448 (4-448-C-599), AFW Check Valve at Stear. Generator E088 ,

(Code / Category 2/C) (4" Check /Self Actuated) Dwg 40141A

CVTC/CS CVT0/CS(Note: 5) c S2(3)1305MU476 (8-476-D-212), Header Supply to and from Condensate Storage Tank T121 (Code / Category 3/B)-(8" Gate / Manual) Dwg 40150D

, BM0/0P S2(3)1414MU092 (8-092-W-212), Makeup Block Valve to Cond Storage Tanks T120 l 4 and T121 (Code / Category NA/8) (8" Gate / Manual) Dwg 401500

BMC/0P

ATTACMENT 2 PAGE 26 0F 71

. ] +;

, , , - a . - - . a , -- , < , , , , . , . - , , , ..,,,w

NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 61 0F 173

~

ATTACHMENT TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM l (Continued) 'l L

CONTAINMENT HVAC (NORMAL) ,

i 2(3)HV9821, Containment Isolation Valve - Minipurge Supply (Code / Category i 2/A) (8" Butterfly / Air)'Dwg 40171A j AJ/0P  !

BTC/0P(Note: 3) l FSTC/0P ,

PIT /RR j 2(3)HV9823, Containment Isolation Valve.- Minipurge Supply (Code / Category

~

2/A) (8" Butterfly / Air) Dwg 40171A AJ/0P BTC/0P(Note: 3)

FSTC/0P PIT /RR 2(3)HV9824, Containment Isolation Valve - Minipurge Exhaust (Code / Category 2/A) (8" Butterfly / Air) Dwg 40171A AJ/0P BTC/0P(Note: 3)

FSTC/0P

PIT /RR 2(3)HV9825, Containment Isolation Valve - Minipurge Exhaust (Code / Category 2/A) (8" Butterfly /Af r) Dwg 40171A AJ/0P BTC/0P (Note

3)

FSTC/0P l

PIT /RR

. 2(3}HV9948,ContainmentPurgeSupply(Code / Category 2/A) i (42 Butterfly / Air) Dwg 40171A l AJ/0P  !

BTC/CS(Note: 3)

FSTC/CS  ;

PIT /RR 2(3)HV9949, Containment Purge Supply (Code / Category 2/A)

(42' Butterfly / Motor) Owg 40171A AJ/0P BTC/CS(Note: 3)

PIT /RR 2(3}HV9950,ContainmentPurgeExhaust(Code / Category 2/A) ,

(42 Butterfly / Motor) Dwg 40171A  ;

AJ/0P '

BTC/CS (Note: 3) )

PIT /RR j ATTACHMENT 2 PAGE 27 0F 71 I

I I

1

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 62 0F 173  !

ATTACHMENT L 9M l

l TCN/EC 4

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3)HV9951, Containment Purge Exhaust:(Code / Category 2/A) .

. .(42" Butterfly / Air) Dwg 40171A AJ/0P

.BTC/CS(Note:3)

FSTC/CS I

' PIT /RR CONTAINMENT SPRAY.

I 2(3)HV8150, Isolation Valve - SDCS HX,E004 to LPSI Header (Code / Category i 2/B) (10" Globe / Motor) Dwg 401148 BTC/CS BT0/CS PIT /RR

. 2(3)HV8151, Isolation Yalve - SDCS HX E003 to LPSI Header (Code / Category 2/B) (10" Globe / Motor) Dwg 40114Bl BTC/CS BT0/CS

PIT /RR

~

2(3)HV9367, Containment Isolation Valve - Spray Header #1 (Code / Category 2/A).(8" Gate / Motor) Dwg 40114B AJ/RR BTC/0P.

BT0/0P(Note: 3)

PIT /RR 2(3)HV9368, Containment Isolation Valve - Spray Header #2 (Code / Category 2/A) (8" Gate / Motor) Dwg 40114B ,

i AJ/RR BTC/0P BT0/0P (Note: 3)

PIT /RR S2(3)1206MU004 (8-004-C-406), Containment Isolation Stop Check Valve -

Spray Header #1 (Code / Category 2/AC) (8" Stop Check /Self Actuated) Dwg 40114B- .

AJ/RR CVP0/RR (Notes: 5&l8)

CVTC/RR l CYT0/RR

- i

)

ATTACHMENT 2 PAGE 28 0F 71 l

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5~ l UNITS 2 AND 3 REVISION 9 PAGE'63 0F 173 4-ATTACM ENT i

TCN/EC Y.

l LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

[ (Continued) 4 S2(3)1206MU006l(8-006-C-406), Containment Isolation Stop Check Valve - '

Spray Header #2 (Code / Category 2/AC) (8" Stop Check /Self Actuated) Dwg

40114B-1AJ/RR -

CVP0/RR(Notes: 5&l8)

CVTC/RR jj CVT0/RR-L S2(3)1206MUO10 (2-010-C-329), Pum) P012 Miniflow Stop Check Valve

'(Code / Category 2/C) (2" Stop Chec(/Self Actuated) Dwg 40114A

CVTC/CS CVT0/0P .

i i ' S2(3)1206MU011 (2-Oll-C-329), Pump P013 Miniflow Stop Check Valve

! (Code / Category 2/C) (2" Stop Check /Self Actuated). Dwg 40114A

.,. CVTC/CS CVT0/0P 4

. S2(3)1206MU0'12(8-012-C-406),SprayPumpP012DischargeStopCheck' Valve i -(Code / Category 2/C) (8" Stop Check /Self Actuated) Dwg 40114A i

. .CVTC/CS (Note: 16 l 4

CVT0/CS(Note: 5)) l 1

S2(de/

(Co Category 2/C) (8" Stop Check /Self Actuated) Dwg 40114A3)1206MU014(

n CVTC/CS (Note: 16)

'CVT0/CS (Note: 5)

S2(3)1206MUO29 (8-029-C-645), Spray Pump P012 Discharge Check Valve to SDCS

.  ; HX E004 (Code / Category 2/C) (8" Check /Self Actuated) Dwg 40114A '

CVIC/CS (Note: 16)

CVT0/CS (Note: 5) i S2(3)1206MUO30 (8-030-C-645), Spray Pump P013 Discharge Check Valve to SOCS

HX E003 (Code / Category 2/C) (8" Check /Self Actuated) Dwg 40114A i

CVTC/CS(Note: 16)

[ CVT0/CS (Note: 5) l DIESEL AIR START '

2(3)HV5931A, Diesel Generator G002, 20 Cyl.,- Air Start Relay Valve i --

. (Code / Category NA/B) (1-1/2" Globe / Air) Dwg 40110A l BTC/0P (Note: 17)

• BT0/0P i

l' ATTACHNENT 2 PAGE 29 0F 71 f);

}

i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 d.- UNITS 2 AND 3 REVISION 9 PAGE 64 0F 173 ATTACMENT 4 TCWEC 9"N LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) l 1

2(3)HV59318, Diesel Generator G002,16 Cyl., Air Start Relay Valve l (Code / Category NA/8) (1-1/2" Globe / Air) Dwg 401108

'BTC/0P (Note: 17) ,

t BT0/0P 2(3)HV59310, Diesel Generator G002, 20 Cyl., Air Start Relay Valve  !

(Code / Category NA/B) (1-1/2" Globe / Air) Dwg'40110A.

~

l BTC/0P (Note: 17)

' BT0/0P i'- 2(3)HV59310, Diesel Generator G002,16 Cyl., Air Start Relay Valve (Code / Category NA/B) (1-1/2" Globe / Air) Dwg 401108 BTC/0P (Note

17)

BT0/0P ,

1

.. 2(3)HV5931E, Diesel Generator G003, 20 Cyl., Air Start Relay Valve l

-(Code / Category NA/B)-(1-1/2" Globe / Air' Dwg 40110C l BTC/0P (Note: 17)- .

E  !

BT0/0P 2(3)HV5931F, Diesel Generator G003,16 Cyl., Air Start Relay Valve 4

(Code / Category NA/B) (1-1/2" Globe / Air) Dwg 40110D BTC/0P (Note: 17)

, BT0/0P

'2(3)HV5931G, Diesel Generator G003, 20 Cyl., Air Start Relay Valve

.. (Code / Category NA/B) (1-1/2" Globe / Air) Dwg 401100 BTC/0P (Note: 17)

BT0/0P 2(3)HV5931H, Diesel Generator G003,16 Cyl., Air Start Relay Valve (Code / Category NA/B) (1-1/2" Globe / Air) Dwg 40110D

BTC/0P(Note: 17) p BT0/0P 2(3)HY5955A1,' Air Start Sol. - Diesel Generator G002, 20 Cyl., Right Bank (Code /CategoryNA/B)(3/8"3-Way/Solenold)Dwg40110A BTC/0P (Note: 17) .

BT0/0P 2(3)HY5955B1, Air Start Sol. - Diesel Generator G002, 16 Cyl., Left Bank n '(Code / Category NA/B) (3/8" 3-Way/ Solenoid) Dwg 401108 h

BTC/0P(Note: 17) ,

BT0/0P.- I

, l

. ATTACHMENT 2 PAGE 30 0F 71

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 65 0F 173 N

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3)HYS955C1, ~ Air Start Sol. - Diesel Generator G002, 20 Cyl., left Bank (Code /CategoryNA/B)(3/8"3-Way/ Solenoid)Dwg40110A  ;

BTC/0P-(Note: 17). )

BT0/0P j 1

2(3)HY595501, Air Start Sol. - Diesel Generator G002,16 Cyl., Right Bank' (Code / Category NA/B) (3/8" 3-Way/ Solenoid) Dwg 401108 BTC/0P(Note: 17) .l BT0/0P i 2(3)HY5955E2, Air Start Sol. - Diesel' Generator G003, 20 Cyl., Right Bank -  !

(Code / Category NA/B) (3/8" 3-Way/ Solenoid) Dwg 40110C BTC/0P (Note: 17)

BT0/0P

,- 2(3)HY5955F2, Air Start 501. - Diesel Generator G003,16 Cyl., Left Bank (Code / Category NA/B) (3/8" 3-Way/ Solenoid) Dwg 401100 BTC/0P. (Note: 17) l BT0/0P ~

2(3)HY5955G2, Air Start Sol. - Diesel Generator G003, 20 Cyl., Left Bank j (Code /CategoryNA/B)(3/8".3-Way/ Solenoid)Dwg40110C i BTC/0P (Note: 17)

BT0/0P 2(3)HY5955H2, Air Start Sol. - Diesel Generator G003,16 Cyl.~, Right Bank (Code / Category NA/B) (3/8" 3-Way/ Solenoid) Dwg 401100 BTC/0P(Note: 17)

BT0/0P D1ESEL FUEL OIL S2(3)2421MUO39 (2-039-D-627;, Diesel Fuel Oil Transfer Pump P096 Discharge Check Valve (Code / Category 3/C) (2" Check /Self Actuated) Dwg 40116A CVTC/0P .

CVT0/0P

-S2(3)2421MUO48 (2-048-D-627), Diesel Fuel Oil Transfer Pump P093 Discharge Check Valve (Code / Category 3/C) (2" Check /SeTf Actuated) Dwg 40116A CVTC/0P-l CVT0/0P S2(3)2421MUO54 (2-054-D-627), Diesel Fuel Oil Transfer Pump P095 Discharge Check Valve (Code / Category 3/C) (2" Check /Self Actuated) Dwg 40116A

• CVTC/0P CVT0/0P ATTACHMENT 2 PAGE 31 0F 71

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

]

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE-S023-V-3.5 l UNITS'2 AND 3 REVISION 9 PAGE 66 0F'173 ATTACHMENT 2 TCN/EC 'd-i LIST OF '!ALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

S2(3)2421MU063 (2-063-D-627), Diesel Fuel Oil Transfer Pump P094 Disch'arge ,

j Check Valve (Code / Category 3/C) (2" Check /Self Actuated) Dwg 40116A '

CVTC/0P

, CVT0/0P DIESEL GENERATOR I

~

i S2(3)2420MU120 (*-120-P *), Engine Sump Turbo Supply Check Valve-l (Code / Category NA/C) (3/4" Check /Self Actuated) Dwg 401108 CVTC/0P (Note: 17) *

CVT0/0P Engine' Sump Turbo Supply Check Valve S2(de/ Category NA/C) (3/4" Check /Self Actuated) Dwg3)2'420MU121 (*-12

. (Co 401108

CVTC/0P (Note

17)

CVT0/0P-

[

S2(3)2420MU126 (Code /CategoryNA/C)(3/8 (*-126-D *g, Check /Self Actuated) Dwg 40110 Bright Bank Air Su CVTC/0P (Note: 17)

CVT0/0P l

! S2(3)2420MU127 (*-127-D *), Air Supply 3-Way Valve (Code / Category NA/8)

(3/8" 3-Way/ Air) Owg 40110C 4' BTC/0P (Note:- 17)

BT0/0P i S2(3)2420MU128 (*-128-D *), left Bank Air Supply Check Valve (Code / Category NA/C)CVTC/0P(Note:(3/8" 17) Check /Self Actuated) Dwg 40110C CVT0/0P

! S2(3)2420MU130 (*-130 D *) Fuel Priming Pump Supply Header Check Valve

. (Code / Category NA/AC) (5/8" Check /Self Actuated) Dwg 40110B

AT/RR l' CVIC/0P - (Note

17) s CVT0/0P S2(3)2420MU132 (*-132-D *), Engine Driven Pudp Discharge Header Check Valve (Code / Category NA/C) (5/8" Check /Self Actuated) Dwg .40110B

, CVTC/0P (Note: 17)

CVT0/0P

- S2(3)2420MU134 (*-134-0 *),L Right Bank Air Supply Check Valve

(Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 401100 d

.CVTC/0P (Note: 17)

! CVT0/0P -

ATTACHMENT 2 PAGE 32 0F 71

(

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

- UNITS 2 ANO.3- REVISION 9 . PAGE 67 0F 173 ATTACHMENT 2 I '

TCN/EC Q'Y

~

4- LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

(Continued) i

S2(3)2420MU135 (1-1/2-135-Z *), Diesel Air Receiver T-338 Air Inlet Check Valve (Code / Category NA/C) (1.1/2" Check /Self Actuated) Dwg 40110F j .

CVTC/0P 1

S2(3)2420MU136(*-136-P* Engine Sump Turbo Supply Check Valve

-(Code / Category NA/C) (3/4), Check /Self Actuated) Dwg 401100

-CVIC/0P(Note: 17) 1 CVT0/0P S2(3}2420MU137 (*-137-D *), Air Supply 3-Way Valve (Code / Category NA/B) i (3/8 3-Way/ Air) Dwg 40110B BTC/0P (Note: 17)

BT0/0P

~S2(3)2420MU138 (*-138-0 *), Left Bank Air Supply Check Valve (Code / Category-

,. .NA/C) (3/8" Check /Self Actuated) Dwg 401108 CVTC/0P-(Note: 17)

CVT0/0P i S2(3)2420MU139 (*-139-D *), Air Sup. ply 3-Way Valve (Code / Category NA/B) l

. (3/8" 3-Way/ Air) Dwg 401100

, BTC/0P (Note: 17) '

j. BT0/0P S2(3)2420MU140 (*-140-P *), Engine Sump Turbo Supply Check Valve (Code / Category NA/C) (3/4" Check /Self Actuated) .Dwg 40110A CVTC/0P(Note: 17)

CVT0/0P S2(3)2420MU141 (*-141-P *), Engine Sump Turbo Supply Check Valve ,

t (Code / Category NA/C) (3/4" Check /Self Actuated) Dwg 40110A CVTC/0P (Note: 17)

CVT0/0P 2

S2(3)2420MU145(*-145-P*l,EngineSumpTurboSupplyCheckValve (Code / Category NA/C) (3/4 Check /Self Actuated) Dwg 401100

CVIC/0P (Note

17) l CVT0/0P ,

!- S2(3)2420MU146-(1 1/2-146-Z *), Diesel. Air Receiver T-335 Air Inlet Check Valve (Code / Category NA/C) (1 1/2" Check /Self Actuated) Dwg 40110E .

, .CVTC/0P

! _ S2(3)2420MU150'(*-150-D *), Fuel Priming Pump Supply Header Check Val've l (Code / Category NA/AC) (5/8" Check /Self Actuated) Dwg 40110A AT/RR CVTC/0P(Note: 17) l CVT0/0P

, ATTACHMENT 2 PAGE 33 0F 71 E

r.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 68 0F 173

. ATTACHMENT L 9 TCN/EC W LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAN j

)

(Continued).

4

.S2(3)2420MU152 (*-152-D *), Engine' Driven Pump Discharge Header Check Valve '

(Code / Category NA/C) (5/8" Check /Self Actuated) Dwg 40110A l i -CVTC/0P (Note: 17)  !

CVT0/0P S2(3)2420MU155 (*-155-0 *)', Right Bank Air Supply Check Valve (Code / Category NA/C)-(3/8" Check /Self Actuated) Dwg 401100-CVTC/0P.(Note: 17)

CVT0/0P ,

1 i

, S2(3}2420MU157 (*-157-D *), Air Supply 3-Way Valve (Code / Category NA/B)

(3/8 3-Way/ Air) Dwg 40110A BTC/0P (Note: 17)

BT0/0P

, S2(3)2420MU158(*-158-0*), Left Bank Air Supply Check Valve (Code / Category i . NA/C) (3/8" Check /Self Actuated) Dwg 40110A  ;

l

, CVTC/0P(Note: 17) 1 a- CVT0/0P S2(3)2420MU159 (*-159-D *), Right Bank Air Supply Check Valve

+

(Code / Category NA/2) (3/8" Check /Self Actuated) Dwg 40110A CVTC/0P (Note: 17)

CVT0/0P A

S2(3)2420MU160 (1 1/2-160-Z *), Diesel Air Receiver T-336 Air Inlet Check

. Valve (Code / Category NA/C) (1 1/2" Check /Self Actuated) Dwg 40110E CVTC/0P S2(3)2420MU161 (*-161-0 *), left Bank Air Supply Check Valve (Code / Category NA/C) (3/8" Check /Self Actuated) .Dwg 401100 CVTC/0P (Note: 17)

CVT0/0P S2(3)2420MU162(*-162-P*),EngineSumpTurboSupplyCheckValve (Code / Category NA/C) (3/4" Check /Self Actuated) Dwg 40110C CVTC/0P (Note: 17)

CVT0/0P ,

S2(3)2420MU163 (*-163-P *), Engine Sump Turbo Supply Check Valve (Code / Category NA/C) (3/4" Check /Self Actuated) Dwg 40110C CVTC/0P (Note: 17)

CVT0/0P ,

i:

ATTACHNENT 2 PAGE 34 0F 71

NdCLEAR' ORGANIZATION ENGINEERING PROCEDURE' S023-V-3.5 .

UNITS 2 AND 3 REVISION 9 PAGE 69 0F 173 ATTACHMENT 2 TCN/EC-LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAN J (Continued)-

l Fuel Priming Pump Supply Header Check Valve  ;

S2(de/

(Co Category NA/AC) (5/8" Check /Self Actuated) 401100 Dwg3)2420MU167 (*-167-D AT/RR CVTC/0P'(Note: 17)

CVT0/0P i

'S2(3)2420MU168 (1 1/2-168-2 *),-Diesel Air Receiver-T-337-Air Inlet Checki

- Valve (Code / Category 3/C) (1 1/2" Check /Self. Actuated) Dwg 40110F-

.'CVTC/0P -

! 3)2420MU170 (*-170-D *), Engine Driven Pump Discharge Header Check Valve S2(de/

(Co Category NA/C) (5/8" Check /Self Actuated) 401100 Owg s CVTC/0P(Note: 17)

CVT0/0P i S2(3)2420MU172 (*-172-0 *), Fuel Priming Pump Supply Header Check Valve

! (Code / Category NA/AC) (5/8" Check /Self Actuated) Dwg 401100 f AT/RR CVTC/0P (Note: 17)

CVT0/0P

]

S2(3)2420MU174 (*-174-D *), Engine Driven Pump Discharge Header Check Valve (Code / Category NA/C). (5/8" Check /Self Actuated) Dwg 40110C

, CVTC/0P (Note: 17) i' CVT0/0P S2(3)2420MU289 (*-289-D *), Downstream Check Valve, DC Auxiliary Turbo Pump

, P495 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 40110B

~

CVTC/0P(Note: 17)

CVT0/0P ,

S2(3)2420MU290.(*-290-D*),DownstreamCheckValve,Y-StrainerMF1334 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401108 CVTC/0P (Note: 17)

CVT0/0P S2(3)2420MU291(*-291-D*),DownstreamCheckValve,ACLub011TurboPump

, P1015 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 40110B CVTC/0P(Note: _17)

CVT0/0P ,

S2(3)2420MU292 (*-292-D *), Downstream Check Valve,'DC Auxiliary Turbo Pump P494-(Code / Category NA/C) . (1" Check /Self Actuated) Dwg 40110A ,

, CVTC/0P(Note:-17)

CYT0/0P -

ATTACletENT 2 PAGE 35 0F 71 1

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

NUCLEAR ORGANIZATION ENGINEERING' PROCEDURE' S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 70 0F 173

~

ATTACMENT TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM i (Continued)

S2(3)2420MU293 (*-293-D *), Downstream Check Valve, Y-Strainer MF1333 4 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401108 CVTC/0P(Note: 17) e CYT0/0P  ;

S2(3)2420MU294' (*-294-D *), Downstream Check Valve, AC Lube.011 Turbo Pump . _

P1014 (Code / Category NA/C) ~(1" Check /Self Actuated) Dwg 40110A CVTC/0P(Note: 17)

CVT0/0P

S2(3)2420MU295'(*-295-D *), Downstream Check Valve, DC Auxiliary Turbo Pump l P497 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401100 CVTC/0P(Note

17),

CVT0/0P i S2(3)2420MU296 (*-296-D *), Downstream Check Valve, Y-Strainer MF1336 i (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401100 <

CVIC/0P(Note: 17)

CVT0/0P i

[ S2(3)2420MU297 (*-297-D *), Downstream' Check Valve, AC Lube Oil Turbo Pump P1017 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401100 I CVTC/0P (Note: 17) l CVT0/0P g S2(3)2420MU298 (*-298 D *), Downstream Check Valve, DC Auxiliary Turbo Pump P496 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 40110C CVTC/0P(Note:17)

CVT0/0P i S2(3)2420MU299 (*-299-D *), Downstream Check Valve, Y-Strainer NF1335 (Code / Category NA/C) (1" Check /Self Actuated) Dwg 401100 CVTC/0P (Note: 17)

}' CVT0/0P

S2(3)2420MU300 (*-300-0 *), Downstream Check Valve, AC Lube 011 Turbo Pump P1016.(Code / Category NA/C) (1" Check /Self Actuated) Dwg 401100 l CVTC/0P(Note: 17) '

CVT0/0P ESFAS

. , 2(3)HV0352A, Containment Pressure Sensing Line Isolation Valve *

. (CoJe/ Category 2/B) (3/4" Globe / Solenoid) Dwg 40172A 4

BTC/0P PIT /RR ATTACHMENT 2 PAGE 36 0F 71 1

q

• .]

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023-V-3.5

- UNITS 2.AND 3 REVISION.9 PAGE 71 0F 173-ATTACHMENT 1 TCN/EC QM LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3)HV03528, Containment Pressure Sensing Line Isolation Valve .

.(Code / Cat ory 2/B) (3/4" Globe / Solenoid) Dwg 40172A BTC/0 PIT /RR 2(3)HV03520,. Containment Pressure ~ Sensing-Line' Isolation Valve .

(Code / Category 2/B) (3/4" Globe / Solenoid) Dwg 40172A BTC/0P

PIT /RR 2(3)HV0352D,1 Containment Pressure Sensing Line Isolation Valve (Code / Category 2/B) (3/4" Globe / Solenoid) Dwg 40172A '

BTC/0P

. PIT /RR FIRE PROTECTION 2(3)HV5686, Contet Isolation Valve, Outside - Fire Prot. System Water (Code / Category 2/A) (3" Gate / Motor) Dwg 401848

-AJ/RR BTC/0P(Notes: 3 and 24) -

PIT /RR.

SA2301MU061 (4-061-C-681), Unit 2 Fire Protection Isolation Valve - Inside Containment'(Code / Category 2/AC) (4" Check /Self Actuated) Dwg 40184B AJ/RR(Note: 10)

SA2301MUO95 (4-095-C-681), Unit 3 Fire Protection Isolation Valve - Inside l Containment (Code / Category 2/AC) (4" Check /Self Actuated) Dwg 401898S03

-AJ/RR(Note

10)' ,

}

FUEL STORAGE P00L AM REFUELING  !

1 I

2(3)LV0227C, RWST To Charging Pump Suction (Code / Category 2/8)

(3" Gate / Motor) Dwg 40124B BMP0/CS (Note: 19)

L BT0/CS(Note: 5)

• PIT /RR s

l

. ATTACHMENT 2 PAGE 37 0F 71 h

4

______1.___1 _ _ _ _ _ _ _ . .-

e . - - . - . - . . - . - . -. . - . . . - . . - - .. . - -.

t

. NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023-V-3.5 4  : UNITS 2 AND 3~ REVISION 9 PAGE 72 0F 173

, , ATTACHMENT

- TCN/EC 4

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM 4

(Continued).

S2(3)1219MUO52(6-052-C-675),RWSTT006toCharging'PumpSuctionHeader_. .

. (Code / Category. 2/C) (6" check /Self Actuated)'Dwg _401248 -

CVTC/CS -

! CVT0/CS (Note: 5)

S2(3)1219MU070, Outlet Valve from T006 Refueling Tank to Poll Spent Fuel Pool Makeup Pump (Code / Category 2/C)-(4" Gate / Manual) Dwg 401228

'BMC/0P

[ S2(3)1219MU100 (10-100-C-212), Refueling Pool Outlet Inside Containment i (Code / Category 2/A) (10"-Gate / Manual) Dwg 40122A

AJ/RR j- PIT /RR S2(3)1219MU101 (10-101-C-212), Refueling Pool Outlet Outside Containment to 4

i Pump P014 (Code / Category 2/A) (10" Gate / Manual) Dwg 40122A AJ/RR PIT /RR

j. GAS RADWASTE i 2(3)HV7258,ContainmentIsolation-WasteGastoSurgeTank(Code / Category

: 2/A)-(3" Gate /Notor) Dwg 40131A

, AJ/RR

.!- BTC/0P-(Note: 3)

, PIT /RR l 2(3)HV7259, Containment Isolation - Safety Injection Tank Vent Header (Code / Category 2/A) (3" Gate / Air) Dwg 40131A

AJ/RR ,

i BTC/0P (Note: 3)

FSTC/0P 1

PIT /RR LIQUID RADWASTE

2(3)HV7512',.RCDT Pump Discharge from Containment to Radwaste (Code / Category I 2/A)(3" Globe / Motor)Dwg40131A .

I AJ/RR 4

BTC/0P(Note: 3)

PIT /RR ,

i 2(3)HV7513,ContainmentIsolation'-RCSDraintoRadwaste(Code / Category 2/A) (3"-Globe /Alr) Dwg 40131A AJ/RR BTC/0P-(Note: 3)

FSTC/0P PIT /RR

ATTACiflENT 2 PAGE 38 0F 71 L _ __ _ _ _ _ - - .- - -. - .

l i

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5i , l UNITS 2 AND 3 ' REVISION 9 PAGE 73 0F 173 i j 4

l ATTACHMENT @2

'TCN/EC  !

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM f

(Continued)

' S2(3)1901MU321- (2-321-C-376), Isolation' Valve - Coolant Polishing Demin to i Quench Tank (Cede / Category 2/A)-(2"' Globe / Manual) Dwg 40111C  !

AJ/RR. l

PIT /'tR -

1901MU573 (2-573-C-611),1 Check. Valve'- Coolant Polishing Demin to.. --

'S2(3)h Quenc Tank-(Code / Category 2/A).(2" Check /Self Actuated) Dwg 40111C j; -AJ/RR_(Note: 10)

NITR0 GEN, GAS-2(3)HV5434, Nitrogen to' Safety Injection Tanks (Code / Category 2/A)

(2" Globe / Air) Dwg 40192C

!~ AJ/RR  :

BTC/0P(Note: 3)  !

. .i. FSTC/0P-

PIT /RR -

._ 2(3)HV5437, Nitrogen Supply to Containment (Code / Category 2/A). -

i (3/4" Globe / Air) Dwg 40192C AJ/RR l BTC/0P(Note: 3) l FSTC/0P PIT /RR 2(3)PSV5403, Nitrogen Gas Relief Valve, Train "A" CCW Surge Tank T003 l (Code / Category NA/C) (3x1-1/2" Safety /Self Actuated) Dwg 401278  ;

I RVT/RR (Note: 2)-

2(3)PSV5404, Nitrogen Gas Relief Valve, Train "B" CCW Surge Tank T004 , .

(Code / Category NA/C) (3x1-1/2" Safety /Self Actuated) Dwg - 401278

RVT/RR (Note

2) 2(3)PSV6414, Train "A" Backup Nitrogen Header Relief, CCW Surge Tank (Code / Category NA/C) (3x1-1/2" Safety /Self Actuated) Dwg 40127H

, RVT/RR (Note: 2) 2(3)PSV6420, Train' "B" Backup Nitrogen Header Relief, CCW Surge Tank _

(Code / Category NA/C) (3x1-1/2"' Safety /Self Actuated) Dwg 40127H RVT/RR (Note: 2) 2418MU002 (3/4-002-C-611), Nitrogen Supply to Containment

'S2(3)/

(Code Category 2/AC) (3/4" Check /Self Actuated) Dwg 40192C . ,

1 AJ/RR l CVTC/RR l ATTACMENT 2 PAGE 39 0F 71 L

. . - . - - --- . - - . - - . ~ . - -

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

UNITS

2 AND 3- REVISION 9 PAGE 74'0F 173

[ '

ATTACIMENT g 'p '

l' TCN/EC' LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

S2(3)2418MU108(2-108-C-627)', Nitrogen.SupplytoSafetyInjectionTanks

.(Code / Category 2/AC) (2" Check /Self Actuated) Dwg 40192C

AJ/RR

, 'CVTC/RR.

S2(3)2418MU356 (3/8-356-P-913),' Backup Nitrogen Cylinder MV-057 Check Valve-i (Code / Category NA/C) (3/8" Check /Self Actuated). Dwg 40127H CVT0/CS:

'j S2(3)2418MU358 (3/8-358-P-913),. Backup Nitrogen cylinder MV-058 Check Valve (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS 1

j S2(de/

(Co Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H3)2418MU360(3/8

> CVT0/CS

52(3)2418MU362 (3/8-362-P-913), Backup Nitrogen Cylinder MV-060 Check Valve (Code /CategoryNA/C)'(3/8" Check /SelfActuated)Dwg40127H CVT0/CS

! 2418MU364(3/8-364-P-913) Backup Nitrogen Cylinder MV-061 Check Valve S2(3)/

(Code Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H

i. .CVT0/CS.

- S2(3)2418MU366(3/8-366-P-913),BackupNitrogenCylinderMV-062CheckValve

, (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS t '

S2(3)/

(Code Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H2418MU368 (3/8-3 CVT0/CS S2(3)2418MU371 (3/8-371-P-913), Backup Nitrogen Cylinder MV-064 Check Valve *

(Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H j CVT0/CS

, S2(3)2418MU373 (3/8-373-P-913), Backup Nitrogen Cylinder MV-065 Check Valve

.(Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS-

^

S2(3)2418MU375 (3/8-375-P-913), Backup Nitrogen Cylinder MV-066 Check Valve (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H ,

CVT0/CS-S2(3)2418MU377 (3/8-377-P-913), Backup Nitrogen Cylinder MV-067 Check Valve

-(Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS ATTACMENT 2 PAGE 40 0F 71

v NUCLEAR ORGANIZATION ENGINEERING PROCEDURE. S023-V-3.5 3- UNITS 2 AND 3- REVISION.9 PAGE-75 0F 173  ;

8 ATTACHMENTg'y TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) p S2(3)2418MU379(3/8-379-P-913),BackupNitrogenCylinderMV-068CheckValve

(Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H  !

CVT0/CS S2(3)2418MU387 (3/8-387-P-913), Backup Nitrogen Cylinder MV-069 Check Valve

+ (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H  ;

j CVT0/CS

- S2(3)2418MU389 (3/8-389-P-913), Backup Nitrogen cylinder MV-070 Check Valve -

(Code / Category NA/C) (3/8" Check /Self, Actuated) Dwg 40127H  !

CVT0/CS  ;

S2(3)2418MU398 (1-398-D-627), Nitrogen Supply to Component Cooling Water Surge Tank T0048 (Code / Category NA/AC) (1" Check /Self Actuated) Dwg 401278

.AT/RR

. CVTC/RR i' S2(3)2418MU402(1-402-D-627),NitrogenSupplytoComponentCoolingWater Surge Tank T003A (Code / Category NA/AC) (1" Check /Self Actuated) Dwg 40127B AT/M

CVTC/RR S2(3)2418MU406(3/8-406-P-913),BackupNitrogenCylinderNV-102CheckValve (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS

S2(3)/

(Code Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H2418MU408 (3/8-40 CVT0/CS ,

S2(3)2418MU410 (3/8-410-P-913), Backup Nitrogen Cylinder MV-104 Check Valve (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H

CVT0/CS S2(3)/

(Code Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H2418MU412 (3/8-CVT0/CS l

S2(3)/

(Code Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H2418MU414(3/8-4 CVT0/CS S2(3)2418MU416(3/8-416-P-913),BackupNitrogenCylinderMV-107CheckValve (Code / Category NA/C) (3/8" Check /Self Actuated) Dwg 40127H CVT0/CS i ATTACHMENT 2 PAGE'41 0F 71 4

1 5

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5-

. UNITS 2 AND 3 REVISION 9 PAGE 76 0F.173 ATTACHMENT g y TCN/EC _

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

. (Continued) 1RICLEAR SAMPLING

~

2(3)HV0500, Post LOCA Hydrogen Monitor (Code / Category 2/A) j (1" Gate / Solenoid) Dwg 40172A

) .AJ/RR' BTC/0P BT0/0P FSTC/0P PIT /RR 2(3)HV0501,'PostLOCAHydrogenNonitoi.(Code / Category 2/A)

(1" Gate /Solenold)Dwg40172A

~

AJ/RR

" BTC/0P BT0/0P ~

-, FSTC/0P PIT /RR' 2(3)HV0502, Post LOCA Hydrogen Monitor (Code / Category 2/A) 4 (l" Gate / Solenoid) Dwg 40172A AJ/RR BTC/0P BT0/0P FSTC/0P ';

PIT /RR l 2(3)HV0503, Post LOCA Hydrogen Monitor (Code / Category 2/A)  !

, (1" Gate / Solenoid) Dwg 40172A i l'

AJ/RR l BTC/0P ' l BT0/0P FSIC/0P i PIT /RR 2(3)HV0508, Containment Isolation - RCS Hot Leg (Code / Category 2/A)  !

(3/4" Globe / Motor)Dwg40134A AJ/RR BTC/0P (Note: 3) , i PIT /RR 2(3)HV0509, Containment Isolation - RCS Hot ' Leg-(Code / Category 2/A)-

(1" Globe / Air) Dwg 40134A AJ/RR '

i

~

BTC/0P (Note: 3)

FSTC/0P PIT /RR -

ATTACfMENT 2 PAGE 42 0F 71

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3,5 .

UNITS 2 AND 3 REVISION 9 PAGE 77 0F 173

' ATTACHMENT 2

?

TCN/EC Ol M 4

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAN (Continued)

2(3)HV0510,' containment. Isolation . Pressurizer Vapor Sample Line (Code / Category 2/A)(3/4" Globe /Notor)Dwg40134A AJ/RR '

-BTC/0P(Note:3)

PIT /RR-2(3)HV0511, Containment Isolation - Pressurizer Vapor Sample Line (Code / Category 2/A)-(3/4" Globe / Air)Dwg40134A AJ/RR BTC/0P(Note'

.3) ,

FSTC/0P L PIT /RR-

- 2(3)HV0512, Containment ' Isolation ' Pressurizer Surge' Line Sample i V (Code / Category 2/A)(3/4" Globe / Motor)Dwg40134A

~

! -i AJ/RR i BTC/0P(Note: 3) i PIT /RR t-

~ 2(3)HV0513, Containment Isolation - Pressurizer Surge Line Sample (Code / Category 2/A)(3/4"-Globe / Air)Dwg40134A AJ/RR 4

BTC/0P(Note: 3)

, FSTC/0P PIT /RR

2(3)HV0514, Isolation Valve - Quench Tank to Waste Gas System 4

(Code / Category 2/A)(3/4" Globe / Motor)Dwg'40111C AJ/RR BTC/0P (Note: 3) ,

PIT /RR i

2(3)HV0515, Isol. Valve - Quench Tank /RCDT to Waste Gas Sampling System (Code / Category 2/A)(3/4" Globe / Air)Dwg40111C i AJ/RR BTC/0P-(Note: 3)

FSTC/0P j._ PIT /RR ,

~ 2(3)HV0516, Isolation Valve - RCDT to Waste Gas Sampling System (Code / Category 2/A) (3/4" Globe /Notor) Dwg 40111C 1

'AJ/RR- l 4

BTC/0P(Note: 3)- , I

~ PIT /RR l 4

i ATTACiflENT 2 PAGE 43 0F 71 i

4

w  !

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS.2 AND 3 REVISION 9.. PAGE 78 0F 173.

'ATTACMENT-2'N TCN/EC- Q' LIST OF VALVES'WITHIN THE-INSERVICE-TESTING PROGRAM

-(Continued)-

~

2(3)HV0517, RCS Hot Leg' #2 Sample Isolation Valve (Code / Category 2/A) .

'(3/4" Globe / Motor) Dwg 40134Ai

-AJ/RR .

.BTC/0P(Note: 3)

PIT /RR:

2(3)HV05888, Safety--Injection Pump Recirc Line Emergency- Sample Valve

L(Code / Category 2/A) (1" Globe / Solenoid)-Dwg 401340

~' '

AT/RR ,

BTC/0P ,

FSTC/0P' S

2(3)HV7800, Containment' Airborne Rad Monitor Train "A" Isol (Pen 308)

F

'(Code / Category 2/A)-(3/4" Globe /Solenold) Dwg '40170A i- AJ/RR. .

i 4- BTC/0P-(Note: 3)

'FSTC/0P j' PIT /RR v 2(3)HV7801, Containment Airborne. Rad Monitor Train "A" Isol-(Pen 308) l' (Code / Category 2/A) (3/4" Globe /Solenold) Owg 40170A

, 'AJ/RR

, BTC/0P (Note: 3)

FSTC/0P L PIT /RR-t iL 2(3)HV7802, Containment Airborne Rad Monitor Train "A" Isol (Pen 30A)

!- (Code / Category 2/A) (3/4" Globe /Solenold) Dwg 40170A AJ/RR BTC/0P(Note: 3) .

.FSTC/0P i . PIT /RR 4 i .2(3)HV7803, Containment Airborne Rad Monitor Train "B" Isol (Pen 3A)

(Code / Category 2/A) (3/4" Globe / Solenoid) Dwg 40170A AJ/RR 4

BTC/0P (Note: 3)

FSTC/0P .

l PIT /RR t 2(3)HV7805, Containment Isolation - Airborne Rad Nonitor Train "B"

(Code / Category 2/A) (3/4" Globe / Solenoid) Dwg 40170A {

AJ/RR ,

BTC/0P-(Note: 3)-

L FSTC/0P

' PIT /RR i ATTACMENT 2 PAGE 44 0F 71 g

! - l

' l l

l l'

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023-V-3.5 UNITS 2 AND 3 REVISION.9- PAGE~79 0F 173

' . ATTACHMENT 2 y TCN/EC d' ,

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2'(3)HV7806, Containment' Isolation - Airborne Rad Monitor Train "B" (Code / Category 2/A) (3/4" Globe / Solenoid).Dwg 40170A )

AJ/RR i BTC/09 (Note: 3) 1 FSTC/0P PIT /RR 2(3)HV7810, Containment Airborne Rad Monitor Train "B" Isol (Pen 16C) ~

(Code / Category 2/A) (3/4" Globe /Solenold) Dwg 40170A AJ/RR BTC/0P(Note:'3)

FSTC/0P PIT /RR 2(3)HV7811, Containment ~ Airborne Rad Monitor Train "B" Isol (Pen 270)

, (Code / Category 2/A) (3/4" Globe / Solenoid) Dwg 40170A-AJ/RR-BTC/0P(Note: 3)~

FSTC/0P PIT /RR j l

2(3)HV7816, Contet Isolation - Airborne Rad Monitor Emergency Sample 1 (Code / Category 2/A) (3/4" Globe / Solenoid) Dwg 40170A AJ/RR BTC/0P (Note: 3)

FSTC/09 PIT /RR l

S2(3)1212MUO10 (1/2-010-C-335), Isolation Valve - SI System to Central Liquid Sample System (Code / Category 2/A) (1/2" Globe / Manual) Dwg 40134D ,

AT/RR BMC/0P

- S2(3)1212MU261 (1-261-C-556), SI System Loop B to Central Liquid Sample i System Check Valve (Code / Category 2/AC) (l" Check /Self Actuated) Dwg 401140 1 AT/RR CYTC/RR S2(3)1212MU262 (1-262-C-556), SI System Loo '

. System Check Valve -(Code / Category- 2/AC) (1"pActuated)

Check /Self A to Central Liquid Sample Dwg 401140 AT/RR CVTC/RR S2(3)'1212MU580 (1-580-C-556), Nuclear Service Water to Liquid Sample ' System Check Valve (Code / Category 2/AC)-(1" Check /Self Actuated) Dwg 40134D AT/RR '

CVTC/RR ATTACHMENT 2 PAGE 45 0F 71 3-- I

. - - . -. . ~ . . . . - - . .- - ...---- . ..

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE: -S023-V-3.5' l

-UNITS 2 AND 3 ~ REVISION 9 . PAGE 80 0F 173. , l

, ATTAC M ENT 2 n' j TCN/EC Wr -

LIST 0F VALVES WITHIN THE INSERVICE. TESTING PROGRAM 4

(Continued)

NUCLEAR SERVICE WATER '

.2('3)HV7911, Containment Isolation - Nuclear Service Water (Code / Category 2/A)'(3" Globe / Air)Dwg 401408.

AJ/RR.

.BTC/0P (Note: 3)

. FSTC/0P X PIT /RR S2(3)1415NU236 '('3-236-C-675), Containment Isolation Check Valve - Nuclear Service Water (Code / Category 2/AC) (3" Check /Self Actuated) Dwg 401408

.AJ/RR

[ CVTC/RR. ,

REACTOR C0OLANT 1 .

. J 2(3)HV0296A, Reactor Head Vent (Code / Category 2/B) (1" Globe / Solenoid) Dwg.

40111C

. BTC/CS BT0/CS j.' .FSTC/CS PIT /RR

2(3)HV02968, Reactor Head Vent (Code / Category 2/B) (1"_ Globe / Solenoid) Owg

40111C BTC/CS

BT0/CS c FSTC/CS PIT /RR

.2(3)HV0297A, Pressurizer Vent Valve (Code / Category 2/B) (1" Globe /Solenold)

, Dwg 40111C

.BTC/CS

.BT0/CS FSTC/CS

-PIT /RR

, 2(3)HV02978, Pressurizer Vent Valve (Code / Category 2/B) (1" Globe / Solenoid)-

. Dwg 40111C-t-

' BTC/CS BT0/CS FSTC/CS PIT /RR- ,

i.-

ATTACMENT 2 PAGE 46 0F 71 o

i

-.A_..

1 NUCLEAR'0RGANIZATION ENGINEERING-PROCEDURE S023-V-3.5  !

UNITS 2 AND 3 REVISION 9 PAGE 81 0F 173  ;

., ATTACHMENT .l TCN/EC LIST OF VALVES WITHIN-THE INSERVICE TESTING PROGRAM (Continued)

. 2(3)HV0298, Vent to Contat from Reactor Head / Pressurizer (Code / Category . l 2/B) (1" Globe / Solenoid) Dwg 40111C l

BTC/CS j BT0/CS FSTC/CS- l

PIT /RR <

2(3)HV0299, Quench: Tank Inlet from Reactor Head / Pressurizer Vent -

.(Code / Category 2/B) (l" Globe / Solenoid) Dwg 40111C

~

BTC/CS BT0/CS FSTC/CS PIT /RR 2(3)HV9201,' Regenerative Heat Exchanger E063 to ' Auxiliary Spray i (Code / Category 1/B) (2" Globe / Motor) Dwg 40123A BTC/CS(Note: 5) 4 BT0/CS-

?

PIT /RR 2(3)HV9202, Regenerative Heat Exchanger E063 to RCS Loop 2A (Code / Category 1/B) (2" Globe / Motor) Dwg 40123A BTC/CS-BT0/CS 2(3)HV9203,RegenerativeHeatExchangerE063toRCSLoop1A(Code / Category 1/B)~ (2" Globe /Notor) Dwg 40123A BTC/CS BT0/CS t 2(3)HV9204, RCS Loop 2B Letdown to Regenerative Heat Exchanger (Code / Category 1/B)(2" Globe / Air)Owg40123A BTC/CS(Note: 5)

FSTC/CS PIT /RR 2(3)HV9217, Reactor Coolant System Bleed Off to Volume Control Tank (Code / Category 2/A)(3/4" Globe / Motor)Dwg40124A AJ/RR BTC/CS(Notes: 3&S)

BT0/CS PIT /RR ATTACMENT 2 PAGE 47 0F 71 I

H l

1 l

MUCLEAR ORGANIZATION ~ ENGINEERING PROCEDURE S023-V-305- l

-UNITS'2 AND 3- REVISION 9 PAGE 82 0F 173

, ATTACHMENT TCN/EC g

IIST OF VALVES WITHIN THE' INSERVICE TESTING PROGRAM

.(Continued) I

')

1

-2(3)HV9218 RCS Bleed Off to VCT Isolation' Valve Inside Containment ,

(Code / Category 2/A) (l" Globe / Air) Dwg 40124A AJ/RR BTC/CS (Notes: 3&5)

BT0/CS l FSTC/CS PIT /RR .-

~

2(3)PSV0200, Pressurizer' Safety Valve (Code / Category 1/C)-(6" Safety /Self Actuated) Dwg 401118 .

-RVT/RR (Note: 2)-

2(3)PSV0201, Pressurizer Safety Valve (Code / Category 1/C) (6" Safety /Self Actuated) Dwg 40111B RVT/RR (Note: 2) 2(3)TV0221, Letdown Isolation Valve (Code / Category 1/B) (2" Globe / Air) Dwg 40123A-BTC/CS(Note:5)

FSTC/CS PIT /RR 2(3)XCV9219, Thermal Relief of Regenerative Heat Exchanger (Code / Category 1 1/C) (2" Check /Self Actuated) Dwg 40123A CVT0/CS ,

l S2(3)120lMU019(2-019-A-554),AuxiliarySprayCheckvalve(Code / Category  !

p 1/C) (2" Check /Self Actuated) Dwg 40123A I

'CVTC/CS CVT0/CS(Note: 5) .

S2(3)1201MUO20 (2-020-A-554), Charging Line check Valve to RCS Loop 2A

. . (Code / Category 1/C) (2" Check /Self Actuated) Dwg 40123A CVTC/CS CVT0/CS l S2(3)120lMUO21 (2-021-A-554), Charging Line Check Valve to RCS Loop 1A (Code / Category 1/C) (2" Check /Self Actuated).Dwg 40123A CVTC/CS

CVT0/CS S2(3)120lMU129 (2-129-A-554), Auxiliary Spray to RCS from Charging Pumps  !

, -(Code / Category 1/AC) (2" Check /Self Actuated) Dwg 40123A . .

AJ/RR ' )

.CVIC/CS ,

CVT0/CS l I

ATTACMENT 2 PAGE 48 0F 71 l

i 1

-[

b NUCLEAR ORGANIZATION ENGINEERING' PROCEDURE S023-V-3.5 UNITS 2 AND 3 ' REVISION 9 PAGE 83 0F 173

'. ATTACMENT 2 TCN/EC qh' LIST OF VALVES 'WITHIN THE INSERVICE TESTING PROGRAM (Continued) i S2(3)120lNU200 (14-200 C-645), Pump'P016 Suction Check Valve (Code / Category 2/C) (14" Check /Self Actuated) Dwg 401128

'CVTC/CS j' .

.CVT0/CS

$2(3)1201MU202 (l'4-202-C-645)r Pump P015 Suction Check Valve'(Code / Category-2/C) . (14" Check /Self Actuated)-Dwg 401128

-CVTC/CS:

CVT0/CS.

S2(3)120lMU976 (4-976-A *), Check Valve - Pressurizer Spray. Line from RCS .

Loop "lA" (Code / Category 1/C) (4" Check /Self Actuated) Dwg 40111D CVTC/CS S2(3)1201MU977 (4-977.-A *), check Valve - Pressurizer Spray Line from RCS Loop "1B" (Code / Category 1/C) (4" Check /Self Actuated) Dwg 401110

-a -

, CVTC/CS-RESPIRATOR AW SERVICE AIR SYSTEM

2(3)HV5388, Containment. Isolation Valve - Instrument Air (Code / Category 2/A)(1-1/2" Globe / Air)Dwg40191G AJ/RR ,

, BTC/CS(Note: 3) l

.FSTC/CS PIT /RR-

$2(3)2417MU016 (1-1/2-016-C-617),' Instrument Air Contmt Isol Check - Inside Containment (Code / Category 2/AC) (1-1/2" Check /Self Actuated) Dwg 40191G AJ/RR- ,

CVTC/RR 1

i S2(3)2423MU017 (2-017-C-627), Containment Isolation Valve - Service Air

j. (Code / Category 2/AC) (2" Check /Self Actuated) Dwg 40191E AJ/RR (Note: 10)

S2(de/ Category 2/A) (2" Globe / Manual) Dwg 40191E3)2423MU055 (2 055-C-387 (Co l

, -AJ/RR

)- SAFETY INJECTION

. 2(3)HV0396, Flow Control. Valve - LPSI Pumps to Shutdown Cooling Systeln

-(Code / Category 2/B) (10" Globe / Motor) Dwg 40112B

'BMPC/CS(Note: 19)

R BT0/CS PIT /RR ATTACHMENT 2 PAGE 49 0F 71 4

NUCLEAR'0RGANIZATION- ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3' REVISION 9 PAGE 84 0F 173

, ATTACMENT 1 :

TCN/EC 9'I LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3)HV8152, Isolation Valve - SDCS' Heat Exchanger E004' Inlet (Code / Category -

2/B) (12" Gate / Motor) Dwg 401128 BMP0/CS(Note: 19)

'BTC/CS BT0/CS PIT /RR 2(3)HV8153, LIsolation Valve - SDCS Heat Exchanger E003 Inlet (Code / Category 2/B) (12" Gate / Motor) Dwg 40112B BNP0/CS (Note: 19) .

BTC/CS

BT0/CS PIT /RR

~2(3)HV8160,' Flow Control Valve --SDCS Heat Exchanger Bypass (Code / Category i 401128' 2/B) BMPC/CS (Note:(10" 19 Globe / Motor))Dwg BTC/CS PIT /RR 2(3)HV8161, Block Valve - SOCS Heat Exchanger Bypass to LPSI (Code / Category

2/8) (14" Gate / Motor) Owg 401128 BMP0/CS (Note: 19)

BTC/CS-PIT /RR 2(3)h78162, LPSI Pump P015 Miniflow Block Valve (Code / Category 2/A)

! (3": Gate / Motor)Dwg 401128 AT/RR

-BMPC/0P (Notes: 19and24) .

BTC/0P (Note: 24)

[

PIT /RR I 2(3)HV8163,LPSIPumpP016MiniflowBlockValve(Code / Category 2/A)

_(3" Gate / Motor) Dwg 401128 AT/ftR OMFC/0P (Notes

19 and 24)

.BTC/0P(Note: 24) .

PIT /RR

[ 2(3}HV9300,' East Refueling Water Tank Outlet Valve (Code / Category 2/B) z(24 Gate / Motor) Owg 40ll2A BTC/0P (Note: 24)' .

j. PIT /RR i

ATTACHMENT 2 PAGE 50 0F 71

.- r, . ..,,.. w.. . ,,,m,--#.re, -- - i e--.- - .,n - - - - .-

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNIT 3 2 AND 3 REVISION 9 PAGE 85 0F 173 ATTACMENT TCN/EC d 'M

^

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) 2(3}HV9301,WestRefuelingWaterTankOutletValve(Code / Category 2/B)

. (24 Gate / Motor) Dwg 40ll2A BTC/0P (Note: 24)

PIT /RR 2(3)HV9302, Control Valve - Contat Emergency Sump to Spray Pump P013 i

(Code / Category 2/B) (24" Butterfly / Motor) Dwg 40ll2A BTC/0P BT0/0P (Note: 3)

PIT /RR 2(3)HV9303,' Control Valve - Contat Emergency Sump to Spray Pump P012 (Code / Category 2/B) (24" Butterfly / Motor) Dwg 40ll2A 1-BTC/0P

• ~

BT0/0P (Note: 3)

PIT /RR 2(3)HV9304, Control Valve - Containment Emergency Sump Outlet

, ~

(Code / Category 2/B) (24" Butterfly / Motor) Dwg 40112A BT0/0P (Note: 3)

PIT /RR 2(3)HV9305, Control Valve - Containment Emergency Sump Outlet (Code / Category 2/B) (24" Butterfly / Motor) Dwg 40ll2A BT0/0P (Note: 3)

HT/RR 2(3)HV9306, Isolation Valve - SI Recirculation to RWST T005 (Code / Category 2/A) (3" Gate / Motor) Dwg 401140 AT/RR i BTC/0P (Note: 3)

PIT /RR 2(3)HV9307, Isolation Valve - SI Recirculation to RWST T005 (Code / Category 2/A) (3" Gate / Motor) Dwg 401140 AT/RR BTC/0P (Note: 3)

PIT /RR -

2(3)HV9322, Control Valve - LPSI Header to RCS Loop 1A (Code / Category 2/B)

-(8". Globe / Motor) Dwg 401120 BTC/0P BT0/0P (Note: 3) -

PIT /RR ATTACHMENT 2 PAGE 51 0F 71

. _ _ _ . _ ~ _ ,

L NUCLEAR ORGANIZATION- ENGINEERING ~ PROCEDURE-S023-Vo3.5 UNITS 2 AND 3- REVISION 9 PAGE 86 0F 173- -

' ATTACHMENT j O -

l TCN/EC M 1

LIST OF VALVES WITHIN THE-INSERVICE TESTING PROGRAM (Continued) l2(3)HV9323, Control' Valve,- HPSI Header #2 to RCS Loop 1A (Code / Category.

2/B):(2"G1obe/ Motor)Dwg'40112C BTC/0P BT0/0P(Note:3)-

PIT /RR 2(3)HV9324, Control Valve - HPSI-Header #1 to-RCS Loop 1A (Code / Category 2/B)-(2" Globe /Notor) Dwg 40112C

.BTC/0P-BT0/0P(Note: 3) '

PIT /RR 2(3)HV9325, Control Valve - LPSI Header to RCS Loop IB (Code / Category 2/B)

(8" Globe / Motor) Dwg 40112D BTC/0P

, BT0/0P(Note: 3)

PIT /RR 2(3)HV9326, Control Valve - HPSI. Header #2 to RCS Loop IB (Code / Category 2/S) (2" Globe / Motor) Dwg 40112C BTC/0P BT0/0P-(Note:3)

PIT /RR-2(3)HV9327, Control Valve - HPSI Header #1 to RCS Loop 1B (Code / Category i 2/B) (2" G1obe/ Motor) Dwg 40112C' '

BTC/0P BT0/0P(Note: 3)

PIT /RR 2(3)HV9328, Control Valve - LPSI Header to RCS Loop 2A (Code / Category 2/B)  ;

(8 Globe / Motor)Dwg40112D BTC/0P BT0/0P(Note: 3)

PIT /RR i l

2(3)HV9329, Control Valve - HPSI Head 9r #2 to RCS Loop 2A (Code / Category -

2/B)(2" Globe / Motor)Dwg40112C  !

BTC/0P BT0/0P (Note: 3)

PIT /RR I

2(3)HV9330, Control Valve - HPSI Header #1 to RCS Loop 2A (Code / Category

?/B) (2" Globe / Motor) Dwg 43112C BTC/0P BT0/0P(Note: 3)

PIT /RR ATTACHMENT 2 PAGE 52 0F~71 1

I

NUCLEAR ORGANIZATION ~ ENGINEERING PROCEDURE -5023-V-3.5~

l.

UNITS 2 AND 3 REVISION 9 , PAGE 87 0F 173.

>ATTACMENT Z g ~

'TCN/EC- M

, LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM 1

'(Continued) 2(3)HV9331, Control Valve -LPSI Header to RCS Loop 2B (Code / Category 2/B) ]

~

(8" G1obe/ Motor) Dwg.401120 '

BTC/0P BT0/0P (Note: 3)- 1 i- l PIT /RR i V2(3)HV9332,' Control Valve HPSI Header J2 to-RCS Loop-28 (Code / Category.. -

2/8)-(2" Globe / Motor) Dwg 40112C i BTC/0P i BT0/0P (Note: 3) .

l' PIT /RR 2(3)HV9333,~ Control Valve - HPSI Header #1 to RCS Loop 2B (Code / Category 2/B) (2" Globe / Motor) Dwg 40112C-BTC/0P'.  !

i BT0/0P (Note: 3) l

. PIT /RR 3

' 2(3)HV9334, Containment Isolation - SI Tank Drain Header to RWST T005 (Code / Category 2/A) (2" Globe / Motor) Dwg 401140 AJ/RR-BTC/0P(Note: 3)

PIT /RR -

4-2(3)HV9336. Isolation Valve - SDCS to LPSI Pump buction (Code / Category 2/B) s.- (16" Gate /Notor) Dwg 40112D t

BMP0/CS (Note: 19)

BTC/0P BT0/0P

, PIT /RR ,

i 2(3)HV9337, Isolation Valve - SDCS to LPSI Pump Suction (Code / Category 1/A)

L (16" Gate / Motor)Dwg 401120 AT/RR (Note: 13)

BTC/CS (Note: 5)

BT0/CS

.' PIT /RR 2(3lHV9339, Isolation Valve - SDCS from RCS [.oop 2 (Code / Category 1/A) t (16 Gate / Motor) Dwg 401120 ,

i AT/RR(Note:.13)'

BTC/CS-(Note: 5)

BT0/CS .

7 PIT /RR -

E I

i-ATTACMENT 2 PAGE 53 0F-71 o

t ..

l sNUCLEAR ORGANIZATION ENGINEERING PROCEDURE. S023-V-3.5 -

UNITS 2 AND 3. REVISION 9 PAGE 88 0F 173 ATTACHNENTJ TCN/EC (A M

' LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

-(Continued) 2(3)HV9340, Safety Injection Tank T008 Outlet Valve to RCS Loop 1A ,

.(Code / Category 1/B)'(8" Gate /Notor) Dwg 40113A BTC/CS BT0/CS (Note: 5)

. PIT /RR

2(3)HV9341, Safety Injection Tank T008 Drain Isolation Valve = (Code / Category--

~

1/A).(1" Globe / Air)Dwg40113A >

AT/RR BTC/CS (Note: 3) '

FSTC/CS PIT /RRL

- 2(3)HV9345, Safety Injection Tank T008 Vent Valve (Code / Category 2/A)

(1" Globe / Solenoid)Dwg40113A i AT/RR

. BT0/CS (Note: 5)

FSTC/CS PIT /RR 2(3)HV9347, Safety Injection Recirc Return to RWST T005 Isolation Valve (Code / Category 2/A) (3" Gate /Notor) Dwg 40114D '

i AT/RR i BTC/0P(Note: 3)

PIT /RR 2(3)HV9348, Safety Injection Recirc Return to RWST T005 Isolation Valve (Code / Category 2/A) (3" Gate /Notor) Dwg 401140 i

, AT/RR- ,

BTC/0P (Note

3) '

PIT /RR i

2(3)HV9350, Safety Injection Tank T009 Outlet Valve to RCS Loop 1B (Code / Category 1/B) (8" Gate /Notor) Dwg 40113A BTC/CS i

BT0/CS(Note: 5)

PIT /RR 2(3)HV9351, Safety Injection Tank T007 Drain' Isolation Valve (Code / Category

. 1/A) (1" Globe / Air) Dwg 40113A

! AT/RR '

I E

BTC/CS (Note: 3)

FSTC/CS *

PIT /RR l

ATTACHNENT 2 PAGE 54 0F 71 i

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

.. ~ _ . . ..

I NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 89 0F 173 i

' , ATTACHMENT a y .

TCN/EC M LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

~2 (3)HV9353, Isolation Valve Shutdown System Recirculation (Code / Category 2/B).(6" Gate / Motor) Dwg 401120 BT0/CS PIT /RR s 2(3)HV9355, Safety Injection Tank T007 Vent- Valve (Code / Category 2/A)-

(1" Globe / Solenoid) Dwg 40113A AT/RR -

BT0/CS(Note:.5)

FSTC/CS

• PIT /RR 2(3)HV9359, Shutdown Cooling Warm-Up Valve (Code / Category 2/B) ,

(6' Gate / Motor)Dwg40112D .

BT0/CS.

i PIT /RR 2(3)HV9360,-Safety Injection Tank T009 Outlet Valve to RCS Loop 2A (Code / Category 1/B) (8" Gate / Motor) Dwg 40113B BTC/CS BT0/CS(Note: 5)

-PIT /RR-2(3)HV9361 Safety Injection Tank T009 Drain Isolation Valve (Code / Category 1/A) (1" Globe / Air) Dwg 40113B AT/RR BTC/CS(Note: 3)

FSTC/CS PIT /RR 2(3)HV9365, Safety Injection Tank T009 Vent Valve (Code / Category 2/A)

(1" Globe / Solenoid) Dwg 40113B AT/RR BT0/CS(Note: 5) .

FSTC/CS PIT /RR 2(3)HV9370, Safety Injection Tank T010 Outlet Valve to RCS Loop 2B (Code / Category 1/B) (8" Gate / Motor) Owg 40113B BTC/CS BT0/CS(Note: 5)

PIT /RR 6

i ATTACHNENT 2 PAGE 55 0F 71

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE- S023-V-3.5  ;

. UNITS'2 AND 3 REVISION 9 PAGE-90 0F 173. l ATTACHNENT 2 l

[ ,

TCN/EC QW l LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM l (Continued) 2(3)HV9371, Safety Injection Tank:T010' Drain' Isolation' Valve'(Code / Category -j 1/A)(l" Globe / Air)Dwg40113B  !

.AT/RR.

BTC/CS (Note: 3) )

FSTC/CS.

PIT /RR 2(3)HV9375, Safety injection Tank T009 Vent Valve-(Code / Category 2/A)-

(l" Globe /Solenold)Dwg40113B AT/RR '

BT0/CS (Note: 5) '

'FSTC/CS

PIT /RR I

2(3)HV9377, SDCS Bypass to LPSI Suction Isolation Valve (Code / Category 1/A) n -(8" Gate / Motor) Dwg 401120 ,

AT/RR'(Note: 13) '

BTC/CS(Note: 5)

BT0/CS

PIT /RR 2(3)HV9378, SDCS Bypass to LPSI' Suction Isolation Valve (Code / Category 1/A)

(8" Gate /Notor) Dwg 401120

,~

AT/RR(Note: 13). j BTC/CS (Note: 5)

BT0/CS PIT /RR -l 2(3)HV9379, SDCS Bypass to LPSI Suction Isolation Valve - Seal l (Code / Category 2/B) (8" Gate / Motor) Dwg 40112D ,

BMP0/CS(Note: 19) o

. BTC/0P

,- BT0/0P

PIT /RR

! 2(3)HV9420, Control Valve - HPSI Header #1 to RCS Loop 2 Hot Leg (Code / Category 2/A)(3".Giobe/ Motor)Dwg40112C AJ/RR '

BT0/CS q- PIT /RR i 2(3)HV9433, Reactor Coolant Loop IB Hot leg injection Drain Valve

(Code / Category 1/A) (l" Globe / Air) Dwg 40112C- ,

AT/RR 4

BTC/0P(Note:3)

FSTC/0P PIT /RR ATTACHMENT 2 PAGE 56 0F 71

NUCLEAR ORGANIZATION- ENGINEERING' PROCEDURE S023-V-3.5

. UNITS 2 AND 3 REVISION 9' PAGE 91 0F 173 ATTACHMENT TCN/EC LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) i

~

i- 2(3)HV94'34, Control Valve - HPSI Header f2 to'RCS Loop 1 Hot Leg ,

l(Code / Category 2/A) (3" Globe / Motor) Dwg 40112C AJ/RR BT0/CS~

PIT /RR

2(3)HV9437, Reactor Coolant -Loop -1A' Hot- Leg ' Injection Drain Valve i~

(Code / Category'1/A)(1" Globe / Air)Dwg40112C AT/RR BTC/0P (Note: 3) i FSTC/0P

' PIT /RR.

, 2(3)PSV9349, Shutdown Cooling System Relief Valve From RCS Loop No. 2 1 (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 401120 l , RVT/RR (Note: 15)

S2(3)1201MUO15 (14-015-C-173),' Shutdown Cooling Line to LPSI P015 (Code / Category 2/8)(14" Gate / Manual)Dwg40112B PIT /RR(Note: 14).

i' S2(3)/

(Code Category 2/B) (14" Gate / Manual) Dwg1201MU018 (14-018-C-173), Shutd 401128

PIT /RR(Note: 14)

S2(3)1204MR433(V-433),LPSI016CasingVent(Code / Category 2/B)

(1/2" Globe / Manual) Dwg 401128 BM0/0P (Note: 14)

S2(3)1204MU001 (24-001-C-724), RWST T005 to Spray Pump P012 Suction Header ,

11 (Code / Category 2/C) (24" Split Disc Check /Self Actuated) Dwg 40112A t

CVP0/0P.

CVTC/RR CVT0/RR (Note: 18)

I S2(3)1204MU002(24-002-C-724),RWSTT006toSprayPumpP013SuctionHeader

' (Code / Category 2/C) (24" Split Disc Check /Self Actuated) Dwg 40112A CVP0/0P '

} CVTC/RR l CVT0/RR (Note: 18) ,

S2(3)1204MU003 (24-003-C-724), Out'et Check Valve - Containment Emergency Sump (Code / Category 2/C) (24" Split Disc Check /Self Actuated) Dwg 401,12A CVP0/RR (Note: 5)

CVT0/RR (Note: 18) 4 ATTACHMENT 2 PAGE 57 0F 71 i.

NUCLEAR ORGANIZATION ~ ENGINEERING PROCEDURE S023-V-3.5~

UNITS 2 AND 3- REVISION 9 PAGE 92 0F 173.

- ATTACMENT L y TCN/EC- 01 "

LIST OF VALVES WITHIN THE INSERVICE TESTING-PROGRAM (Continued).

S2(3)1204MU004 (24-004-C-724), Outlet Check Valve Containment' Emergency .

Sump (Code / Category 2/C) (24" Split Disc Check /Self Actuated)'Dwg 40112A.

i CVP0/RR (Note: 5)

CVT0/RR(Note:18)

~

'S2(3)1204MU006 (10-006-C-675), HPSI Pumps P017 and P018 Suction Check Valve

~(Code / Category 2/C) (10" Check /Self Actuated) Dwg 40112A e .m-CVP0/0P

CVT0/RR S2(3)1204MU008-(10-008-C-675), HPSI Pumps P018 and P019 Suction Check Valve (Code / Category 2/C) (10" Check /Self Actuated) Dwg 40112A j CVP0/0P 4

CVT0/RR i S2(3)1204MU012.(4-012-C-358), HPSI Pump P017 Discharge Check Valve (Code / Category 2/C) (4" Stop Check /Self Actuated) Dwg 40112A

CVTC/CS (Note

5)-

CVT0/CS ,

'S2(3)1204MUO15 (4-015-C-358), HPSI Pump P019 Discharge Check Valve (Code / Category 2/C) (4" Stop Check /Self Actuated)~ Dwg 40112A CVTC/CS (Note: 5)

CVT0/CS S2(3)/

(Code Category 2/C) (4" Stop Check /Self Actuated) Dwg 40112A1204MUOl6 (4-016 CVTC/CS (Note: 5)

CVT0/CS

. S2(3)1204MU017 (4-017-C-553), HPSI Pumps P018 and P019 to #2 High Pressure Header (Code / Category 2/C) (4" Check /Self Actuated) Dwg 40112A CVTC/CS (Note: 5)

CVT0/CS S2(3)1204M0018 (3-018-A-551), HPSI Combined Header to RCS Loop 1A Check l

, Valve (Code / Category 1/AC) (3" Check /Self Actuated) Dwg 40112C '

?

AT/RR (Note: 13) .

CVTC/CS (Note

5) i

CVT0/CS ,

l l S2(3)1204MU019 (3-019-A-551), HPSI Combined Header to RCS Loop IB Check Valve (Code / Category 1/AC) (3" Check /Self Actuated) Dwg 40112C ,

AT/RR (Note: 13)

CVTC/CS-(Note: 5)

CVT0/CS ATTACHMENT 2 PAGE 58 0F 71 3

. NUCLEAR ORGANIZATION ' ENGINEERING PROCEDURE S023-V-3.5

' UNITS 2 AND 3 REVISION 9 PAGE 93 0F 173 a

-h kN.

'L'IST OF VALVES WITHIN'THE INSERVICE TESTING PROGRAM-(Continued)

S2(3)1204NU020 (3-020-A-551)', HPSI Combined Header to RCS Loop 2A Check ,

Valve (Code / Category 1/AC) (3". Check /Self Actuated) Dwg 40112C AT/RR (Note: 13)

CVIC/CS (Note: 5)

CVT0/CS:

'S2(3)1204MU021(3-021-A-551),HPSI-CombinedHeadertoRCSLoop2BCheck. -

Valve (Code /(Note:

AT/RR 13) Category 1/AC) (3" Check /Self Actuated) Dwg~ 40112C CVIC/CS (Note: 5) *

• CVT0/CS S2(3)1204MU024 (10-024-C-406)', LPSI Pump P015 Discharge Stop Check Valve

'(Code / Category 2/C)-(10" Stop Check /Self Actuated) Dwg' 401128 .

CVTC/CS (Note: 5)

, CVT0/CS S2(3)1204MUO25 (10-025-C-406), LPSI Pump P016 Discharge Stop Check Valve

. (Code / Category 2/C) (10" Stop Check /Self Actuated) Dwg.401128 CVTC/CS CVT0/CS S2(3)1204MU027 (12-027-A-551), Safety Injection Headers to RCS Loop 1A (Code / Category 1/AC) (12" Check /Self Actuated) Dwg.40113A L AT/RR (Note: 13)

L CVTC/CS (Note: 5)

CVT0/CS S2(3)1204MUO29 (12-029-A-551), Safety Injection Headers to RCS Loop 1B (Code / Category 1/AC) (12" Check /Self Actuated) Dwg 40113A '

AT/RR (Note: 13)

CVTC/CS (Note: 5) l CVT0/CS S2(de/

(Co Category 1/AC) (12" Check /Self Actuated) Dwg 40113B3)1204MUO31 (12-0 AT/RR (Note: 13)

CVTC/CS(Note: 5)

• CVT0/CS e

, ATTACMENT 2 PAGE 59 0F 71 e

L

-NUCLEAR ORGANIZATION ENGINEERING PROCEDlGE S023-V-3.5- . ,

UNITS 2 AND 3: REVISION 9 PAGE 94 0F 173.

L l

, ATTACHMENT 2 i Q I.

.TCN/EC

~

! ' LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) v 1 S2(3)1204MU033-(12-033-A-551), Safety Injection Headers to RCS Loop 2B , 1

(Code / Category 1/AC) (12" Check /Self. Actuated) Dwg 40113B '!

i AT/RR-(Note: 13)  !

, -CVTC/CS (Note: 5)- , j p CVT0/CS-S2(3)1204MUO34 (2-034-C-329), HPSI P017 Miniflow (Code / Category 2/C) '

(2" Stop Check /Self Actuated) Dwg 40112A CVTC/RR

CVT0/0P- ,

S2j3)1204MUO35 (2-035-C-329), HPSI P019 Miniflow (Code / Category 2/C)

(2 Stop Check /Self Actuated) Dwg 40112A

, CVTC/RR. .

CVT0/0P S2(3)1204MUO36 (2-036-C-329), HPSI P018 Train "A" Miniflow (Code / Category 2/C) (2" Stop Check /Self Actuated) Dwg 40112A CVTC/RR' CVT0/0P

.S2(3)1204MU037 (2-037-C-329), LPSI Pump P015 Miniflow Stop Check Valve

- (Code / Category 2/C) (2" Stop Check /Self Actuated) Dwg 401128-CVTC/RR CVT0/0P

, S2(3)1204MU040 (12-040-A-551), Safety Injection Tank T008 Outlet Check F ValveAT(/RR(Note:13) Code / Category 1/AC) (12" Check /Self Actuated) Dwg 40113A CVP0/CS(Note: 5) ,

'. CVTC/CS'

[ CVT0/RR i

S2(3)1204MUO41 (12-041-A-551), Safety Injection Tank T007 Outlet Check j Valve (Code / Category 1/AC) (12" Check /Self Actuated) Dwg 40113A L- AT/RR (Note: 13) l CVP0/CS(Note: 5)

CVIC/CS .

' CVT0/RR

'S2(3)1204MUO42 (12-042-A-551), Safety Injection Tank T009 Outlet Check

- Valve (Code / Category 1/AC) (12" Check /Self Actuated) Dwg 40113B AT/RR(Note: 13) ,

i i CVP0/CS (Note: 5)

CVTC/CS CVT0/RR ATTACMENT 2 PAGE 60 0F 71

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-305-

. UNITS'2 AND 3 REVISION 9 PAGE 95 0F 173 ATTACHMENT 2.

TCN/EC Of I LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM-

-(Continued)

~S2(3)1204MUO43'(12-043-A-551), Safety Injection Tank T010 Outlet Check ,

.Velve (Code / Category 1/AC) (12' Check /Self Actuated) Dwg 40113B '

.AT/RR (Note: 13)

CVP0/CS (Note: 5)- ,

CVTC/CS CVT0/RR -

' S2(3)1204MU063 (2-063-C-329), LPSI Pump P016 Miniflow Stop Check Valve

-(Code / Category 2/C) (2" Stop Check /Self Actuated) Dwg 401128 CVTC/RR CVT0/0P S2(3)1204MUO72-(8-072-A-552), LPSI Check Valve to RCS Loop 1A (Code / Category 1/AC) (8" Check /Self Actuated) Dwg 401120 AT/RR (Note: 13)

, CVTC/CS CVT0/CS(Note: 5)

-S2(3)1204MUO73 (8-073-A-552), LPSI Check Valve to RCS-Loop 1B (Code / Category 1/AC) (8" Check /Self Actuated) Dwg 401120 AT/RR (Note: 13)

CVTC/CS CVT0/CS(Note: 5)

S2(3)1204MUO74 (8-074-A-552), LPSI Check Valve to RCS Loop 2A (Code / Category 1/AC) (8" Check /Self Actuated) Dwg 401120 L

AT/RR (Note: 13)

CVTC/CS CVT0/CS (Note: 5)

S2(3)1204MUO75 (8-075-A-552), LPSI Check Valve to RCS Loop 2B (Code / Category 1/AC) (8" Check /Self Actuated) Dwg 401120 AT/RR (Note: 13)

CVTC/CS CVT0/CS(Note: 5)

S2(3)1204MUO77 (16-077-C-645), LPSI Pump P016 Suction Header Check Valve (Code / Category 2/C) (16" Check /Self Actuated), Dwg 40112A CVP0/0P CVTC/RR(Note: 16) '

CVT0/RR S2(3)1204MUO84. (16-084-C-645) LPSI Pump P015 Suction Check Valve ,

(Code / Category 2/C) (16" Check /Self Actuated) Dwg.40112A CVP0/0P CVTC/RR.(Note: 16)

!' CVT0/RR ATTACHMENT 2 PAGE 61 0F 71

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

- NUCLEARORGAh!ZATION l ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3- REVISION 9- PAGE 96 0F 173 4 -

ATTACHMENT 2

TCN/EC

CF M LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued)

! S2(3)1204MU087 (16-087-C-675), Spray Pump P013 Suction Check Valve (Code / Category 2/C) (16" Check /Self Actuated) Dwg 40114A CVP0/0P CVT0/CS'

Spray Pump P012 Suction Check Valve. --

'S2(3)1204MUO88-(16-088-C-675)k/SelfActuated)Dwg40114A (Code / Category 2/C) (16"'Chec lJ CVP0/0P CVT0/CS S2(3)1204MU099 (2-099-C-334), Containment Isolation, SI Tank to Drain Header to RWST T005 (Code / Category 2/A) (2" Globe / Manual) Dwg 401140 AJ/RR S2(3)1204MU104 (2-104-C-329), HPSI P018 Train "B" Miniflow (Code / Category

, 2/C) (2" Stop Check /Self Actuated) Dwg 40112A CVTC/RR CVT0/0P t S2(3

'(1/2l1204MU132(1/2-132-D-279),LPSIP015CasingVent'(Code Gate / Manual) Dwg 40112B / Category 2/B)

BM0/0P (Note: 14) '

S2(3)1204MU152 (3-152-A-551), To #2 HPSI Header (Code / Category 1/AC)

(3" Check /Self Actuated) Dwg 40111A AT/RR(Note: 13)

CVIC/CS CVT0/CS S2(de/

(Co Category 2/B) (2" Gate / Manual)-Dwg 40112C3)1204MU154 (2-154-C-036), ,.

BM0/0P i S2(3)1204MU155 (3-155-C-551), HPSI Header #1 to RCS Loop 2 Hot leg

(Code / Category 2/C) (3" Check /Self Actuated) Dwg 40112C

, CVT0/CS (Note: 5)

S2(3)1204MU156 (3-156-A-551), HPSI Header #1.to RCS Loop 2 Hot Leg Inlet Check Valve -(Code / Category 1/AC) (3" Check /Self Actuated) Dwg 401120 AT/RR (Note: 13)

CVIC/CS j CVT0/CS (Note: 5)

ATTACHMENT 2 PAGE 62 0F 71 l

t

l NUCLEAR ORGANIZATION ENGINEERIN'G PROCEDURE S023-V-3.5

- UNITS 2 AND 3 REVISIM 9 PAGE 97 0F 173 '

ATTA.CHMENT 2 -

TCN/EC 40, LIST 0F VALVES WITHIN THE INSERVICE TESTING PROGRAM (Con',1nued)

I 1

S2(de/

(Co Category 1/AC) (3" Check /Self Actuated)'Dwg 40112C3)1204MU157 (3-1  ;

AJ/RR AT/RR-. l CVTC/CS-- ,  !

CVT0/CS (Note: 5) l S2(3)1204MU138 (3-158-A-550), HPSI Header #1 to RCS Loop 2 Hot Leg l j (Code / Category 1/AC) (3" Check /Self Actuated) Dwg 40112C l AJ/RR l i AT/RR' CVTC/CS CVT0/CS (Note: 5)

.S2(3)1204MU199(16-199-C-645),LPSIPumpP016SuctionHeaderCheckValve c . (Code / Category 2/C) (16" Check /Self Actuated) Dwg 40112A l CVP0/0P CVTC/RR (Note: 16)

CVT0/RR

'1

, S2(3)1204NU201 (16-201-C-645), LPSI Pump P015 Suction Header Check Valve

~

(Code / Category 2/C) (16" Check /Solf Actuated) Dwg 40112A ~ '

CVP0/0P CVTC/RR (Note: 16) ,

CVT0/RR SALT WATER C0OLING 2(3)HV6200, Salt Water Cooling System Pump P112 Discharge Valve

-(Code / Category 3/B) (30" Butterfly / Air) Dwg 40126A , ,

BT0/0P (Note: 3) I FST0/0P PIT /RR 2(3)HV6201, Salt Water Cooling System Pump P113 Discharge Valve 1 (Code / Category 3/8) (30" Butterfly / Air) Dwg 40126A BT0/0P (Note: 3)

FST0/0P ,

. PIT /RR 2(3)HV6202, Salt Water Cooling System Pump P307 Discharge Valve i (Code / Category 3/B) (30" Butterfly / Air) Dwg 401268 BT0/0P (Note: 3)' ,

FST0/0P PIT /RR 4

ATTACHMENT 2 PAGE 63 0F 71 I

-l NUCLEARLORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 4 . UNITS 2 AND 3 ' REVISION 9 PAGE 98 0F 173-

< ' ATTACHMENT 2 i TCN/EC Qh: I l

l LIST OF' VALVES WITHIN THE~ INSERVICE TESTING PROGRAM

.. (Continued) 2(3)HV6203, Salt Water Cooling System Pump P114 Discharge Valve ,

(Code / Category 3/B)-(30" Butterfly / Air) Dwg 401268 , ,

BT0/0P (Note: 3)

FST0/0P PIT /RR

~

^2(3)HV6376, Service Water to SWC Pump P112A Control Valve -(Code / Category.: ..

3/B) (2" Globe / Solenoid) Dwg 40126A BT0/0P -

FST0/0P '

PIT /RR 2(3)HV6377, Service Water to SWC Pump P1138 Control Valve (Code / Category 3/B) (2" Globe / Solenoid) Dwg 40126A BT0/0P

.- FST0/0P-PIT /RR

^

2(3)HV6378, Service Water to SWC Pump P307A Control Valve (Code / Category 3/B) (2" Globe / Solenoid) Dwg 40126B i BT0/0P FST0/0P

PIT /RR j 2(3)HV6379, Service Water to SWC Pump P1148 Control Valve (Code / Category l 3/B) (2" G1obe/ Solenoid) Dwg-40126B  !

' . BT0/0P l FST0/0P .

PIT /RR l

. 2(3)HV6495, Salt Water from CCW Heat Exchanger E002B (Code / Category 3/B)

(30" Butterfly / Motor) Dwg 40127C BT0/0P PIT /RR s

4 2(3}HV6497, Salt Water from CCW Heat Exchanger E001A (Code / Category 3/B)

(30 Butterfly / Motor) Dwg 40127C BT0/0P '

PIT /RR S2(3)1413MU009 (30-009-0-722), SWCS Pump P112 Discharge Check Valve I (Code / Category 3/C) (30" Split Disc Check /Self Actuated) Dwg 40126A i 2

CVIC/0P

• 1 CVT0/0P l 1

l l

ATTACHMENT 2 PAGE 64 0F 71

NUCl. EAR ORGANIZATION ENGINEE' LING PROCEDURE S023-V-3.5 UNITS'2 AND 3 REVISION 9 .. PAGE 99 0F 173 ATTACMENT 2 Cl O TCN/EC

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) l S2(3)1413MUO10-(30-010-D-722), SWCS Pump P113 Discharge Check Valve _- ,

-(Code / Category 3/C) (30" Split Disc Check /Self Actuated) Dwg 40126A

'CVTC/0P CVT0/0P i - S2(3)1413MUO11 (30-011-D-722), SWCS Pump P307 Discharge Check-Valve (Code / Category 3/C) (30" Split Disc Check /Self Actuated) Dwg 401268~

CVTC/0P CVT0/0P S2(3)1413MU012 (30-012-D-722), SWCS Pump P114 Discharge Check Valve (Code / Category 3/C) (30" Split Disc Check /Self Actuated) Dwg 40126B -

1 CVTC/0P

CVT0/0P l . S2(3)1413MU013 (1-013-D-691), SWCS Pum) P112 Recirculation to Cyclone

. Separator (Code / Category 3/C) (1" Chec(/Self. Actuated) Dwg 40126A CVT0/0P S2(3)1413MU016(1-016-D-691),SWCSPum) P113 Recirculation:to Cyclone Separator (Code / Category 3/C) (1" Chec c/Self Actuated) Dwg 40126A l CVT0/0P

! S2(3)1413MUO21 (1-021-D-691), SWCS Pump P307 Recirculation to Cyclone Separator (Code / Category 3/C) (1" Check /Self Actuated) Dwg 401268 CVT0/0P l S2(3)1413MUO24(1-024-D-691),SWCSPum) P114 Recirculation to Cyclone Separator (Code / Category 3/C) (1" Chec c/Self Actuated) Dwg 401268 CVT0/0P ,

i S2(3)1413 MOO 47 (1-047-D-691), Check Valve Service Water Supply to Salt Water Pump P112 (Code / Category 3/C) (1" Check /Self Actuated) Dwg 40126A q CVTC/0P S2(3)1413MUO48 (1-048-D-691), Check Valve Service Water Supply to Salt Water Pump P113 (Code / Category 3/C) (1" Check /Self Actuated) Dwg 40126A CVIC/0P S2(3)1413MUO49 (1-049-D-691), Check Valve Service Water Supply to Salt ,

Water Pump P307 (Code / Category 3/C) (1" Check /Self Actuated) Dwg 40126B ,

1 CVTC/0P S2(3)1413MUO50 (1-050-D-691), Ch'eck Valve Service Water Supply to Sal't Water Pump P114 (Code / Category 3/C) (1" Check /Self Actuated) Dwg 40126B CVTC/0P l i

ATTACHMENT 2 PAGE 65 0F 71 4

1

, . ~. .- .. . . . - - -. - -

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3,5 UNITS 2 AND 3 REVISION 9 PAGE 100 0F 173

, ,ATTACMENT 2

1 .

TCN/EC Of & -l

! LIST'0F VALVES WITHIN THE INSERVICE TESTING PROGRAM-(Continued) i S2(3)1413MW458 (1-458-D-691), Vent Float Valve to Atmosphere for. P112 Salt ,

Water Pump.(Code / Category NA/C) (6" Check /Self Actuated). Dwg 40126A CVTC/0P(Note: 6). )

S2(3)1413MW459 (1-459-D-691), Vent' Float Valve to Atmosphere for P113' Salt I

, Water Pump (Code / Category NA/C) (6" Check /Self Actuated) Dwg 40126A -

CVTC/0P.(Note: 6)

S2(3)1413W460 (1-460-D-691), Vent Float Valve to Atmosphere for P307. Salt

! Water Pump (Code / Category NA/C) (6' Check /Self Actuated) Dwg 401268

-CVTC/0P(Note: 6)

! S2(3)1413NW461 (1-461-D-691), Vent Float Valve to Atmosphere for P114 Salt Water Pump (Code / Category NA/C) (6" Check /Self Actuated) Dwg 401268 '

CVTC/0P (Note: 6)

'- STEAM i 2(3)HV4053, Blowdown Isolation' Valve - Steam Generator E089 (Code / Category 2/8) (6"' Globe / Air) Dwg 40141A BTC/0P (Note: 3) i FSTC/0P l PIT /RR-

} 2(3)HV4054, Blowdown Isolation Valve - Steam Generator E088 (Code / Category l 2/8) (6" Globe / Air) Dwg 40141A l BTC/0P(Note: 3)

FSTC/0P PIT /RR 2(3)HV4057, Sample Isolation Valve - Steam Generator E089 (Code / Category 2/8) (1" Globe / Air) Dwg.40141A i BTC/0P(Note: 3)

FSTC/0P

j. PIT /RR i

2(3)HV4058, Sample Isolation Valve - Steam Generator E088 (Code / Category 2/B) (1" Globe / Air) Dwg'40141A .

2 BTC/0P (Note: 3)

FSTC/0P PIT /RR ATTACMENT 2 PAGE 66 0F 71

1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9- PAGE'101 0F 173

~ ATTACHMENT 2 TCN/EC 4& 1 LIST OF VALVES WITHIN THE' INSERVICE TESTING PROGRAM (Continued) 3- 2(3)HV8200, Steam from Steam Generator E089 to AFW Pump-P140 (Code / Category ,

2/B) (4"-Globe / Air) Dwg 40141C 8MPC/CS (Note: 19)

BTC/0P BT0/0P (Note:~ 3)

FST0/0P-PIT /RR 2(3)HV8201;LSteam from Steam Generator E088 to AFW Pump P140 (Code / Category 2/B) (4" Globe / Air) Dwg 40141D ,

BNPC/CS(Note: 19) l

BTC/0P BT0/0P (Note: 3)

FST0/0P j PIT /RR

. 2(3)HV8202, Steam Generator E089 Main Steam Isolation Valve Bypass

(Code / Category 2/B) (4" Globe /Alr) Dwg 40141E BTC/0P (Note: 3)

FSTC/0P PIT /RR

! 2(3)HV8203, Steam Generator E088 Main Steam Isolat'on Valve Bypass  ;

i (Code / Category 2/8) (4" Globe / Air) Dwg 40141D ,

BTC/0P(Note: 3)

FSTC/0P PIT /RR j 2(3)HV8204, Steam Generator E089 Main Steam Isolation Valve (Code / Category j 2/B) (30" Gate / Hydraulic) Dwg 40141C ,  ;

BTC/CS(Note: 3)

FSTC/CS i'

PIT /RR I

2(3)HV8205, Steam Generator E088 Main Steam Isolation Valve (Code / Category 2/B)' (30" Gate / Hydraulic) Dwg 40141D

~

BTC/CS'(Note: 3)

FSTC/CS ~

PIT /RR 4

i j ATTACHMENT 2 PAGE 67 0F 71

f 3'  ; NUCLEAR ORGANIZATION-ENGINEERING PROCEDURE S023-V-3.5-J UNITS 2 AND 3' , REVISION 9 'PAGE 102 0F 173 ATTACMENT 2:

LTCN/EC Ol E .

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM- '

(Continued) .

12(3)HV8419,'MainSteam'DumptoAtmosphere~(Code / Category 2/B) ,

l (8" Angle / Air) Dwg'40141D D~ -BMC/RR (Note: 11)

L IBM 0/RR BTC/CS (Note: 3):

p BT0/CS

BTP0/0P FSTC/CS

PIT /RR.

2(3)HV8421, Main Steam' Dump to Atmosphere.(Code / Category 2/B)'

- (8" Angle / Air) Dwg 40141C

BMC/RR(Note: 11)

BM0/RR .. ;

BTC/CS(Note

3)

D ..s BT0/CS BTP0/0P i- FSTC/CS

. ' PIT /RR-4 2(3)HY84198, Main Steam Dump to Atmosphere Solenoid Valve (Code / Category.

2/A)'(3/4" 3-Way/ Solenoid) Dwg 40141D j 'AT/RR l 2(3)HY84190, Main Steam Dump to Atmosphere Solenoid Valve (Code / Category 2/A)-(3/4" 3-Way/Solenold) Dwg 40141D

.AT/RR

'.i 2(3)HY84190, Main' Steam Dump to Atmosphere Solenoid Valve (Code / Category NA/A):(3/4"3-Way/ Solenoid)Dwg40141D ,.

AT/RR-2(3)HY8421B, Main Steam Dump to Atmosphere Solenoid Valve (code / Category 2/A) (3/4" 3-Way/Solenold)~Dwg 40141C AT/RR 2(3)HY8421C,MainSteamDumptoAtmosphereSolenoidValve(Code / Category i

l 2/A).AT/RR(3/4" 3-Way/ Solenoid) Dwg 40141C

.2(3)HY8421D, Main Steam Dump to Atmosphere Solenoid Valve (Code / Category

{- 2/A)(3/4"3-Way/Solenold)Dwg40141C

AT/RR ,

i I 2(3)PCV8463, Nitrogen Supply to Main Steam Dump Valve HV8419 (Code / Category

, NA/B)'(1/4" Globe / Air) Dwg 40141D BT0/CS 7

ATTACHMENT 2 PAGE 68 0F 71

[ NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3' REVISION 9 PAGE 103 0F 173

. TCN/EC-ATTACHMENT Cl 2&

LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM (Continued) o

! 2(3)PCV8465, Nitrogen Supply to Main Steam Dump Valve HV8421 (Code / Category  ;

.NA/8)'(1/4" Globe / Air) Dwg 40141C 8T0/CS I

. 2(3)PSV8401, Main Steam Relief Valve (Code / Category 2/C)-(6" Safety /Self - ,

Actuated) Dwg 401410 l 1

RVT/RR (Note: 2)

-2(3)PSV8402, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self

-Actuated) Dwg'40141D '

j RVT/RR(Note: 2) 2(3)PSV8403, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141D RYT/RR(Note: 2) 2(3)PSV8404, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self 4 Actuated) Dwg 40141D i RVT/RR (Note: 2) 2(3)PSV8405, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 401410

.RVT/RR(Note: 2)

' 2(3)PSV8406, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141D RVT/RR(Note: 2)

' 2(3)PSV8407, Main Steam Relief Yalve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141D '

, RVT/RR(Note:.2)  :

2(3)PSV8408, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141D RYT/RR (Note: 2) 2(3)PSV8409, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141D '

RVT/RR(Note: 2) 2(3)PSV8410, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self

Actuated) Dwg 40141C HVT/RR(Note

2) ,

2(3)PSV8411, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141C RVT/RR(Note:.2)

ATTACHMENT 2 PAGE 69 0F 71

4

. NUCLEAR ORGANIZATION ENGINEERING PROCEDURE- S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 104 0F 173 1.7TACHMENT 2 CN/EC AN LISTOF'VALVESWITHINTHEINSERVICETESTINGPROGRAM (Continued)'.

I 2(3)PSV8412, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self

Actuated) Dwg 40141C i RVT/RR(Note:2) 2(3)PSV8413,' Main Steam Relief _ Valve (Code / Category 2/C) (6" Safety /Self Actuated)'Dwg40141C RYT/RR (Note: 2) l 2(3)PSV8414, Main Steam Relief Valve-(Code / Category 2/C) (6" Safety /Self

' Actuated) Dwg 40141C' ,

- RVT/RR (Note: 2)

I 2(3)PSV8415, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141C RYT/RR(Note: 2) 4 2(3)PSV8416, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self j' Actuated) Dwg 40141C' l RVT/RR'(Note: 2) 2(3)PSV8417,1 Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141C

RVT/RR (Note

2)

'2(3)PSV8418, Main Steam Relief Valve (Code / Category 2/C) (6" Safety /Self Actuated) Dwg 40141C RVT/RR (Note: 2) 4 o S2(3)1301MU003 (4-003-D-620), Steam Supply - S/G E088 to AFP Turbine K007 Check Valve (Code / Category 3/C) (4" Check /Self Actuated) Dwg 40141C

CVP0/0P (Note: 18) 1 CVTC/RR l CVT0/CS i S2(3)1301MU005 (4-005-D-620), Steam Supply - S/G E089 to AFP Turbine K007

i. Check Valve (Code / Category 3/C) (4" Check /Self Actuated) Dwg 401410 l CVP0/0P (Note: 18)

CVTC/RR '

[ CVT0/CS S2(3)1301MUO21 (3/4-021-P-145), Nitrogen Supply Isolation Valve to HV8421 (Code / Category NA/B) (3/4" Globe / Manual) Dwg 40141C-j BMC/CS ,

! S2(3)1301MUO27 (3/4-027-P-636), Instrument Air Supply Check Valve for HV8419 (Code / Category NA/AC) (3/4" Check /Self Actuated) Dwg 40141D AT/RR CVTC/0P ATTACHMENT 2 PAGE 70 0F 71 L ,

l

e

.. NUCLEAR 0RGANIZATION ENGINEERING PROCEDURE S023-V-305

,  ; UNITS 2 AN9 3 REVISION 9 PAGE 105 0F 173

'. ATTACMENT 2 TCN/EC M-LIST OF VALVES WITHIN THE INSERVICE TESTING PROGRAM

, (Continued)

S2(3)130lMUO34 (3/4-034-P-636), Instrument Air Supply Check Valve for

HV8421 (Code / Category NA/AC) (3/4" Check /Self Actuated) Owg 40141C AT/RR CVTC/0P 3)1301MU1264~ (3/8-1264-P *), Valve HV8419 Equalizing Valve d- -S2(de/

(Co Category NA/B)-(3/8" Ball / Manual) Dwg 401410 BM0/CS.

S2(3)l30lMU1265 (3/8-1265-P *), Valve.HV8421 Equalizing Valve (Code / Category NA/B) (3/8" Ball / Manual) Dwg 40141C-

-BM0/CS 4-4 S2(3)l30lMU1328 (3/4-1328-P-145), Nitrogen Supply Isolation Gate Valve to

.L HV8419(Code /CategoryNA/B)(3/4" Gate / Manual)Dwg 401410 i

BMC/CS SUNPS AND DRAINS 1

2(3)HV5803, Containment Sump to Radwaste Sump (Code / Category 2/A)

(3" Gate / Motor) Dwg 40117A AJ/RR

' BTC/0P(Notes: 3&5)

PIT /RR 1 2(3)HV5804, Containment Sump to Radwaste Sump Isolation Valve (Code / Category 2/A) (3" Gate / Air) Dwg 40117A AJ/RR BTC/0P (Notes: 3&5)

FSTC/0P ,

i l PIT /RR

\

l 23V35T92.W51 ATTACHMENT 2 PAGE 71 0F 71

- NUCLEAR ORGANIZATION ' ENGINEERING PROCEDURE S023-V-3.5-l UNITS 2 AND 3 REVISION 9 PAGE 106 0F 173 '

ATTACHMENT L g TCN/EC W I ALTERNAIE TESTING' JUSTIFICATION AlO BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL ,

-l TABLE OF CONTENTS SECTION PAE I l

1.0 AUXILIARY FEEDWATER 107. I

{

1 2.0 BORICACIDMAKEUP(BAMU)' 108 i 3.0.; CHEMICAL'AND VOLUME CONTROL 109' 4.0 CHILLED WATER ,

115 5.0 COMPONENT COOLING WATER 116 l

! 6.0 CONDENSATE AND FEEDWATER 119

,'7.0 CONTAINMENT HVAC (NORMAL) 122

! 8.0 CONTAINMENT SPRAY 122

-; . 9.0 FUEL ~ STORAGE P0OL AND REFUELING 127 i l

10.0 NITROGEN GAS 127 l 11.0 NUCLEAR SAMPLING 129 1.2.0 NUCLEAR SERVICE WATER 130 i

13.0 REACTOR COOLANT 130 14.0 RESP. & SERVICE AIR SYSTEM 136 ,

15.0 SAFETY INJECTION 137 16.0 STEAN 160 1

i l

ATTACEMENT 3 PAGE 1 0F 62 1

i

g NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 107 0F 173 ATTAC} MENTW 1~ V TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued) 1.0 AUXILIARY FEEDWATER 1.1 $2(3)1306NdO88, Drain Valve from Condensate Storage Tank T121 to T120 Sump 1.1.1 Test Requirement: ON-10, Para. 4.2.1.1, test' nominally every three months.

1.1.2 Alternate Test this valve at cold shutdown intervals. <

1.1.3 This valve is closed'at all times except when crosstie l between T121 and T120 enclosure is required. Valve  !

provides access to the assured water inventory in T120 as part of the design basis of the condensate storage and ,

transfer system and is deemed necessary for safe operation

.- of the plant. NRC Branch Technical Position (BTP) Reactor. ,

System Branch (RSB) 5-1, states this must be a seismic Category I source of supply and available with either loss of offsite or onsite power. Access to the condensate in  !

T120 is based on gravity feeding through NU476, gravity  ;

feed valve from T120 Demineralizer Header to T121, as documented in Emergency Operating Instructions (E01)

S023-12-9. Access to that portion of the assured contents L of T120 which would spill into the T120 enclosure, should T120 rupture following a DBE is assured by gravity feeding through NUO88.

1.1.4 Technical . Specification 3.7.1.3, Condensate Storage Tanks, i invokes an action statement of four hours if either condensate tank is inoperable. The NUO88 exercise test ,

involves installing a alug on tank T121 outlet rendering the tank inoperable. 30th tanks T120 and T121 provide the i water for Auxiliary Feedwater Pump suction. Isolating ,

I these tanks from each other renders the makeup water supply and therefore the AFW system inoperable for the duration of the test. Hence, the exercise test for this i valve is deemed to be not practical during plant ,

! operation. .

[ 1.2 52 1305NU121, AFP P140 Supply to S/G E089,  !

$2 1305NU126, AFW Pump P141 Discharge Check Valve,-

$2 1305NU532, AFW Pump P504 Discharge Check Valve and

$2 1305NU547,.AFW Pump P140 Discharge Check Valve ,

1.2.1 Test Requirement: ON-10, Para. 4.3.2, test nominally every three months. )

l ATTACHMENT 3 PAGE 2 0F 62 b

i'

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 LUNITS 2 AND 3 REVISION 9 PAGE 108 0F 173 ATTACHMENT 3 TCN/EC 4M' ALTERNATE TESTING JUSTIFICATIC4f AND' BASIS FOR OTHER THAN DUARTERLY TEST INTERVAL (Continued) 1.2.2 Alternate ~ Testing:' Test the valves at cold shutdown.

This avoids injecting cold water into hot feedwater piping and consequent thermal stresses'.

1.2.3 These check valves prevent backflow of feedwater from Steam Generators to' the discharge of Auxiliary Feedwaterr4 Pumps. They'also )revent by)assing the flow from a running Auxiliary :eedwater ) ump' backwards through an idle Auxiliary Feedwater Pump.

1.2.4 Exercising these valves while the plant is at power requires injection of Auxiliary Feedwater into the Steam.

Generators. This flow places unnecessary and deleterious thermal stresses on the feedwater piping and could result in premature failure of this piping. The connection between the Auxiliary Feedwater Pump discharge piping and

', the main feed piping usually has a steady-state temperature of a 350*F, however, the Auxiliary Feedwater Pumps' inject condensate directly from the condensate - y storage tanks. Consequently, during' the test of these 4 valves at power, the piping ex)eriences a rapid cooldown I to approximately 70*F. Over tie life of the plant, if_ the testing were conducted quarterly, the resulting fatigue i from thermal cycling would exceed the original design i assumptions from such a source. Accordingly, testing at 4 this damagi_ng frequency is considered, impractical.

f 2.0 SQMC ACID MAKEUP (BAMU)

I 2.1 2(3)HV9236, BAMU Tank T072 to Gravity Feed to Charging Pump suction, i

2(3)HV9240, BAMU Tank T071 to Charging Pump Suction Header Control i Valve, and, 2(3)HV9247, BAM Pump to Charging Pump Suetion Control Valve.

2.1.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally

every three months.

i

2.1.2 Alternate Testing: Test the valves at cold shutdown.

This avoids uncontrolled boration and consequent reactor shutdown,

).

i 2.1.3 These valves are normally closed to block concentrated

boric acid to the charging pump suction. When open, the contents of the boric acid system is directed to the t Regenerative Heat Exchanger via the charging pumps and

! directly into the Reactor Coolant System- .

b 2.1.4 Opening these valves during plant operation would result in injecting concentrated boric acid into the reactor coolant system, causing plant shutdown.-

ATTACM ENT 3 PAGE 3 0F 62

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

E NUCLEAR' ORGANIZATION. . ENGINEERING PROCEDURE. S023-V-3.5 UNITS.2 AND 3- REVISION 9 PAGE 109 0F'173 i

' ATTACHMENT 3. A _ '

TCN/EC WV ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST-INTERVAL (Continued) j' 4

2.2.52(3)1218881033, BANU Pump 2(3)P175 Discharge Check Valve, and,

$2(3)1218NU035 BANUPump2(3)P174DischargeCheckValve p

2.2.1 Test Requirement: 0M-10, Para. 4.3.2,- Exercise check

~

i valves open quarterly.

i 2.2.2 Alternate Testing: Test the valves at cold' shutdown.

4 This avoids uncontrolled boration and consequent reactor

shutdown.

2.2.3 These valves close to prevent backflow through an idle .

- Boric Acid Transfer Pumps.thus preventing bypass of the

! discharge of the running pump and open to allow flow from.

the associated BAMU pump to the Charging pump suction.

. 2.2.4 The only flow path through these valves which will allow test flow is into the Volume Control Tank (VCT or to the-i suction of the Charging Pumps (See P&ID 40125B . The only source of water to open these valves is from t e BAMU

- Pumps and is concentrated boric' acid. As a result, l 4

exercising of these valves during power operation would 1 result in uncontrolled boration of 'the reactor coolant I system and the effect would be reactor plant shutdown.

{-- 3.0 CHEMICAL AND VOLUME CONTROL 3.1 2(3)HV9200 Charging Pumps to Regenerative Heat Exchanger E063 l 3.1.1 Test Requirement: 0M-10, Para. 4.2.1.1, Active Category A and B valves shall be tested nominally every 3 months. ,

l 3.1.2 Alternate Testing: Test the valve at cold shutdown. This shifts the testing to a period during which is allowed by the Technical Specifications and avoids Reactor Coolant

. System pressure and boration control problems or complications.

4 3.1.3 This valve is the Containeerit Isolation for the Charging

. Pump Discharge into the Containment, where it goes to the

Regenerative Heat Exchanger. It must open to allow normal charging flow and close if there is a need to isolate this ' i

line from the regenerative hear exchanger. -It is in 1 series with a check valve inside the containment (MU,122)

which also closes to isolate backflow from the-

Regenerative Heat Exchanger.

ATTACHMENT 3 PAGE 4 0F 62 l

L_-________. ... . __ -

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3- REVISION 9 PAGE 110 0F 173 ATTACHMENT 3

~TCN/EC' CI M 6LIERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OVARTERLY TEST INTERVAL (Continued) 3.1.4 Exercising HV9200 while the plant is at power would isolate normal charging to the Reactor Coolant System.

This would result in a non-compliance with Technical ,

Specification 3.1.2.2, which requires two flow paths for i

boration during power operation. In addition, exercising -

this air operated valve during plant power operation would;

! require securing letdown and charging entirely. This is a-1engthy plant evolution as is the restoration of letdown fol'owing the exercise test. Further, stopping charging and letdown flow imppses a large thermal transient on the components in the charging / letdown path which would

! eventually damage components such as the letdown heat

exchanger and the regenerative heat exchanger.

3.2 2(3)HVg205,RegenerativeHeatExchangertoLetdownHeatExchanger, .

. and, l

2(3)TVg267, Letdown Containment Isolation Valve '

3.2.1 Test Requirement: OH-10, Para. 4.2.1.1, Active Category A and B valves shall be tested nominally every 3 months.

3.2.2 Alternate Testing: Test these valves at cold shutdown.

L 3.2.3 These valves block letdown flow from the Regenerative Heat Exchanger to the Letdown Heat Exchanger. Exercising these ,

valves during power operation would result in interruption /

. of' flow and allow the associated heat exchanger temperatures to equalize for a short period. Later, upon restoration of flow as the valves are opened, the hot  !

reactor coolant flow through the Regenerative Heat Exchanger would result in return to the former

" equilibrium" temperatures. This would result in damaging thermal stress transients on the regenerative heat exchanger and reactor coolant system charging nozzles. j Exercising these valves at cold shutdown shifts the testing to a period during which tem)eratures are much j closer to ambient on both sides of tie heat exchanger. As  !

a result, the' thermal transients from momentary ,

interruption of flow are almost completely avoided. l

. l l

j 1

i ATTACHMENT 3 PAGE 5 0F 62 l i

i

s. . NUCLEAR ORGANIZATION-'

ENGINEERING PROCEDURE S023-V-3.5 l UNITS 2 AND 3 REVISION 9 PAGE 111 0F 173 ATTACHMENT @1 TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) 3.3 2(3)LV02278 VCT Outlet Valve, andi S2(3)1208MUO15 VCT to Charging Pump Suction Check Valve

~3.3.1 Test Requirement: 0M-10, Para. 4.2.1.1, Active Category A and B valves shall be tested nominally every 3 months, and Para. 4.3.2.1- ~ check valves shall be exercised nominally J

every 3 months.

.3.3.2 Alternate Testing: Test these valves at cold shutdown.

3.3.3 LV0227B regulates th's Volume Control Tank (VCT) Level by

, . throttling the outlet to the Charging Pumps. Check valve 4 MOO 15 prevents backflow into the VCT from the Charging pump suction piping.

Exercising these valves closed requires shifting charging

. 3.3.4 pump suction and injecting highly concentrated boric acid into the Reactor Coolant System, causing plant shutdown.

! Exercising these valves at cold shutdown avoids the -

uncontrolled and unwanted boration during the period these valves and the associated VCT are out of service for their i i closed stroke test.

3.4 S2(3)1208MUO45 Chemical Addition Tank T001 to Charging Pump Suction Header 3.4.1 Test Requirement: OM-10, Para. 4.3.2, test nominally every three months.

3.4.2 Alternate Testing: Verify closure at cold shutdown ,

intervals.

3.4.3 This valve provides the pressure boundary between safety related and non-safety related piping. Valve is normally closed and required to remain closed during accident mitigation when pressure boundary integrity is required to be maintained.

3.4.4 This test requires a backpressure from the charging pump suction header that can only be achieved when the charging pumps are secured for a period of time, thus requiring Modes 5 and 6. Additionally, an exercise test would result in unnecessary / undesirable dilution of the Reactor Coolant System if performed during power operation.

ATTACHMENT 3 PAGE 6 0F 62

4 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

' UNITS 2 AND 3 REVISION 9 PAGE 112 0F 173 ATTACHMENT 3 TCN/EC Of M

. -ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL, (Continued)

3.5 $2(3)1208NUO66 Charging Pumps Combined Discharge Valve to HPSI

' ~

Header

.3.5.1 Test Requirement: 0M-10, Para. 4.3.2, test ncminally

. every three months.

3.5.? Alternate Testing: Open' stroke test at cold shutdown intervals.

! 3.5.3 This valve is normally closed and is isolated by one normally closed valve upstream, 1208MUO65 and two normally closed valves downstream,1204MU154 and 1208MU005. This 4 valve prevents backflow from the HPSI header to the charging pump discharge header. Valve is located in the auxiliary charging path used for mitigating a high energy line~ break (HELB) of the charging line inside containment and re-establishing charging flow.

j 3.5.4 When valve is stroked open using the auxiliary charging

path, cold borated water will be injected into the reactor

' coolant system via the HPSI header because the regenerative heat exchanger is bypassed. This results in extreme thermal shock, and consequent damage to the associated system connection /nczzles.

3.6 S2(3)1208MUO82, Gravity Feed - BAMU Tanks to Charging Pump P190 Suction, and,

$2(3)1208MUO83, BAMU Pumps to Charging Pumps Suction Header

. 3.6.1 Test. Requirement: OM-10, Para. 4.3.2, test nominally j every three months. .

3.6.2 Alternate Testing: Test the valves at cold shutdown.

This avoids uncontrolled boration and consequent reactor shutdown.

4 3.6.3 These valves block backflow from the charging pump suction to the boric acid system. When open, the contents of the boric acid system is directed to the charging pump suction and via to the Regenerative Heat Exchanger directly into e the Reactor Coolant System. Both valves are normally i closed. They open to provide flow from the BAMU tanks through the gravity feed valves during safety injection upon failure of BAMU pumps or if the BAMU pumps are .

operating during safety injection, MUO82 remains closed to prevent flow diversion back to the BAMU tanks.

3.6.4 Testing these valves in the open direction would result in

injecting concentrated boric acid into the reactor coolant system, causing plant shutdown.

ATTACHMENT 3 PAGE 7 0F 62

L .

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023-V-3.5 UNITS 2 AND~3 -RFVISION 9 'PAGE 113 0F 173

, ATTACHMENT TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) 3.7. 52(3)12081R1084, Charging Pisap Discharge to Regenerative Heat Exchanger e 3.7.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

3.7.2 Alternate Testing: Test the valve during cold shutdown.. = )

, 3.7.3 Nanual' isolation valve upstream of HV9200 (Charging Pumps  !

to Regenerattve Heat HV9200 and this 1 valve are locked open. Exchanger during E063). This valve normal operation.

i is unlocked and throttled during shutdown operation from l outside the Control Room. See Abnormal Operating Instruction (AOI) Nos. S023-13-2 and S023-13-21.

,- 3.7.4 Exercising MUO84 while' the plant is at power would isolate normal charging to the Reactor Coolant System. This would~

! result in a non-compliance with Technical Specification 3.1.2.2, which requires two flow paths for boration during power operation. In addition, exercising this manually l operated valve during plant power operation would require securing letdown and charging entirely. This is a lengthy plant evolution as is the restoration of letdown following the exercise test. Further, stopping charging and letdown flow imposes a'large thermal transient on the components 4 in the charging / letdown path which would eventually damage L components such as the letdown heat exchanger and the regenerative heat exchanger.

3.8'52(3)1208NU094, Check valve - Coolant Polishing Domineralizer to '

Charging Pump suction Header 3.8.1 Test Requirement: ON-10, Para. 4.3.2, Active Category A and a valves shall be tested nominally every 3 months.

3.8.2 Alternate Testing: Test this valve at cold shutdown intervals. This will avoid unplanned dilutions and potential power excursions.,

3.8.3 This valve provides the pressure boundary between Safety Related and Non-Safety Related piping. Valve is normally closed and required to remain closed during accident mitigation when pressure boundary integrity is requi, red to be maintained. Additionally, this valve will cause an unplanned dilution of the Reactor Coolant System if a exercise test is performed during power operation.

ATTACHNENT 3 PAGE 8 0F 62

NUCLEAR ORGANIZATICN ENGINEERING PROCEDURE S023-V-3.5-

, UNITS 2 AND 3 REVISION 9 PAGE 114 0F 173 ATTACHNENT 3 AM TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) 3.8.4 The Unit 2 valve and the Unit 3 valve are tested ,

- differently. The Unit P. valve has a test tee located l upstream, and valve closure is verified t,y measuring i leakage past the valve. Performing these tests at Cold

' Shutdown intervals while measuring leakage is consistent

with NUREG-1482 (Reference 2.5.3) Section 4.1.4.

3.8.5 .A test tee does not exist in Unit 3, and the valve is

verifled CLOSE using radiography. Performing radiography j at Cold Shutdown intprvals is consistent with NUREG-1482 (Reference 2.5.3) Section 4.1.2.

! 3.9 52(3)1208NU122 Charging Pumps check Valve to Regenerative Heat Exchanger E063

. 3.9.1 Test Requ kement: 0M-10, Paragraph 4.3.2, exercise this valve every three months.

! 3.9.2 Alternate Testing: This valve will be verified closed i

during refueling outages while performing Appendix "J" t testing. The check. valve open (CVTO) test is quarterly l during routine inservice testing of the charging pumps.

i 3.9.3 This containment isolation valve opens to allow normal charging flow to the reactor coolant system. It is located inside containment and is in constant use.

. Closing this valve during power operation (or any time

reactor charging flow is required) results in cessation of f flow through the regenerative heat exchanger and results

in an extreme thermal transienc. Additionally, the system ,

arrangement provides no source of backflow or pressure to

! provide for a CVTC other than the containment penetration

! leak rate testing connections. Accordingly, to. complete l theCLOSEstroketest(CVTC),thereactorrefueling

interval seat leakage test is used as the verification of '

valve closure. This is consistent with the requirements of ON-10, Section 4.3.2.2.

ATTACHMENT 3 PAGE 9 0F 62 1

- w.

\

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE -5023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 115 0F 173 ATTACl#iENT lL TCN/EC- Lik 8LTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued) l 3.10 $2(3)1208MU130,' Containment' Isolation - Charging Pump Discharge to .

Aux Spray Regenerative Heat Exchanger Bypass t

3.10.1 Test Requirement:. OM 10, Para. 4.2.1.1, Active Category A and B valves shall be tested nominally every 3 months.

3.10.2 Alternate Testing

Stroke test this valve open and closed

at cold shutdown intervals. During cold shutdown the.-

extreme temperature difference between the normal spray -

flow and the charging pump discharge is avoided.

l 3.10.3 This valve provides the containment ' isolation (outside i' containment) for the charging pump discharge to the 1 pressurizer auxiliary spray.

i o 3.10.4 Exercising this' valve during power operation results in admission of cold charging pump discharge to the

pressurizer spray and an unnecessary thermal transient and 4

stress on the pressurizer spray nozzle.

j. 4.0 CHILLED WATER 4.1 SA1417NU136, check Valve to Prevent Leakage and Backflow on NSW SA1417NU138, Check Valve to Prevent Leakage and Backflow on NSW i 4.1.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally i- every three months.

2 4.1.2 Alternative Testing: These valves will be verified closed i

at Refueling intervals. The only way to verify closure of these valvos is by disassembling an upstream valve and ,

i measuring leakage past MU136 (MU138). This creates an

, = unnecessary burden on Maintenance and introduces the e possibility of human error during disassembly and

, reassembly of the upstream valve. Performing the CLOSE tests in conjunction with the LEAKAGE tests at refueling intervals is consistent with NUREG-1482 (Reference 2.5.3)

Section 4.1.4.

r ATTACHNENT 3 PAGE 10 0F 62 l

. l 4

j- NUCLEAR ORGANIZATION . ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3

. REVISION 9 PAGE 116 0F 173

~ ATTACHMENT q TCN/EC

) ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL

. (Continued) 5.0 COMPONENT COOLING. WATER 5.1 2 HV6211, Containment Isolation Valve - CCW Non-Critical Loop, 1 2 HV6212 CCW from Heat Exchanger E001A to Non-Critical Loop, 2 HV6213. Component Cooling Discharge to Non-Critical Loop,

2 HV6216, Containment Isolation - CCW Non-Critical teop Return, j "2 HV6218, Component Cooling Water Pump Suction From Non-Critical

Loop, .

2(3)HV621g, component cooling Water Pump Suction From Non-Critical -

Loop, .

2 HV6223, containment IsolationL- CCW Non-Critical Loop Supply, 1 1 2 HV6236 Containment Isolation - CCW Non-Critical Loop Return,-

2 HV6500 Component Cooling Water from Shutdown Cooling System Heat Exchanger E003, and. . .

2(3)HV6501, Coaxment Cooling Water from Shutdown Cooling System Heat

i Excianger E004 i 5.1.1 -Test Requirement

0M-10, Para. 4.2.1.1, test nominally .

] every three months.

5.1.2 Alternate Testing: Stroke these valves at cold shutdown intervals to avoid damage to plant equipment which can result from interruption of CCW flow.

' HV6211 and HV6216 are the CCW non-critical loop supply and 5.1.3 return containment isolation valves (outside). HV6223 and

, HV6236 are the CCW non-critical loop supply.and return containment isolation valves (inside). They provide o isolation of the containment CCW header. They are closed upon receipt of a containment isolation actuation signal ,

[CIAS].

I 5.1.4 HV6212 and HV6213 isolate the non-critical loop supply l

from the discharge of CCW heat exchanger IA and 28.

5.1.5 HV6218 and HV6219 isolate the non-critical loop return

, flow from CCW critical loops respectively "A" and "B" return piping. .

l 5.1.6 HV6500 and HV6501 isolate the shutdown cooling heat exchanger outlets from the CCW pump sections.

5.1.7 Exercising HV6211, HV6216, HV6223, and HV6236 during

operation would secure or direct cooling water flow from i RCP seals, which could result in seal damage and plant l shutdown. Similarly, exercising HV6212 and HV6213 would L isolate the non-critical loop supply from the discharge of CCW heat exchanger IA and 2B and secure CCW flow to the

RCP seals with the same result.

i. ATTACHMENT 3 PAGE 11 0F 62

[

~ i

- NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 117 0F 173 4- '

ATTACHMENT A o .

TCN/EC M'V 4

! ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL' (Continued) 1

5.1.8 Exercising HV6218 and HV6219 would isolate the ,

' non-critical loop return flow from CCW critical loops 1 return piping and have the same effect. I 5.1.9 ' Exercising HV6500 and HV6501 would initiate flow in the i shutdown cooling heat exchanger and therefore bypass flow intended for the normal CCW heat loads momentarily.

5.2 2(3)PCV6358 CCW-Surge Tank T-003 Nitrogen Backpressure Regulator, and .._

- 2(3)PCV6361,CCWSurgeTankT-004NitrogenBackpressureRegulator 5.2.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nominally every three months.

5.2.2 Alternate Testing:' Test at Refueling Intervals.

5.2.3 These valves maintain CCW surge tank maximum pressure at 41 psig and valve closes when tank pressure drops below 41 psig. They remain closed and leak tight to prevent loss of Nitrogen inventory and/or consequent loss of adequate CCW pump suction pressure.

5.2.4 During plant refueling, each CCW train is taken out of service for maintenance and these valves can be tested at that time.

5.2.5 Closure of these valves is verified by measuring leakage past the valves. The test involves installation of a test rig similar to that used for LLRTs and measuring leakage flow past the valves. Performing the CLOSE test of these * '

valves in conjunction with the LEAKAGE test at refueling intervals is consistent with NUREG-1482 (Reference 2.5.3)

Section 4.1.4.

5.3 2(3 TV9144, CCW from RCP P001 Seal Heat Exchanger 2 TV9154, CCW from RCP P003 Seal Heat Exchanger 2 TV9164, CCW from RCP P004 Seal Heat Exchanger 2 TV9174, CCW from RCP P002 Seal Heat, Exchanger 5.3.1 Test Requirement: 0M-10, Para. 4.2.1.1, exercise open and closed nominally every three months.

5.3.2 Alternate Testing: Remote manually test valves at cold shutdown intervals and manually stroke valves when plant conditions allow containment entry at cold shutdowns of a long enough duration.

ATTACHMENT 3 PAGE 12 0F 62

M NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.~5 UNITS 2 AND 3 REVISION 9 PAGE 118 0F-173

, ATTACHMENT TCN/EC i ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL 4

(Continued) 5.3.3 .In order to stroke open the valve remotely from the Control Room, valves will first have to be closed and then stroked open interrupting flow to the reactor coolant pump .

, (RCP) seal. The closure would result in seal damage.

Accordingly, these valves can only be exercised when the RCPs are secured (at cold' shutdown).

5.3.4 Containment entry is required to manually open stroke 4

these valves.

i 5.4 S2 1203NU101, CCW Pump P024 D'ischarge check Valve

$2 1203NU102, CCW Pump P026 Discharge Check Valve

- $2 1203NU103, CCW Pump P025 Discharge Check Valve 5.4.1 Test Requirement: ON-10, Para. 4.3.2, test nominally

. every three months. l

}

5.4.2 Alternate Testing

Test partially open quarterly and full-

open at cold hutdown intervals.

p )

5.4.3 These check valves are in the discharge of each CCW pump l

, and prevent backflow through an idle pump when the associated parallel pump is operating.

[

5.4.4 Stroke at cold shutdown intervals when plant conditions allow adjustment of CCW flow without the complexity represented by the Node 1 configuration. To achieve full flow to stroke these check valves open (restoration of normal CCW flowadjustment and complicated is equally of complicated) the flow balance betweenrequires a tediou 4

numerous CCW loads. This usus.liy results in high temperature alarms in the control room and results in a thermal cycle on the components serviced by CCW.

5.5 S2(3)1203N0268, Nuclear Plant Service Water Supply to CCW Loop A, 52(3)1203MU269 Nuclear Plant Service Water Supply to CCW Loop B

, 5.5.1 Test Requirement: . ON-10, Para. 4.3.2, test nominally every three months.

5.5.2 Alternate Testing: Stroke at cold shutdown intervals when i plant conditions allow CCW loops to be inoperable without i rendering several Technical Specification required j components inoperable.

ATTACHMENT 3 PAGE 13 0F 62 4

m , _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ . . _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ . _ _ . _ . . _ _ _ _ _

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE ~ S023-V-3.5 UNITS 2 AND 3' REVISION 9 PAGE 119 0F 173 ATTACHMENT TCN/EC W 1b ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued)

'5.5.3 These check valves provide water makeup to the CCW surge tanks. To achieve a close stroke of these check. valves, the upstream volume of the associated piping must be isolated and depressurized. The CLOSE test-is performed I by measuring leakage past the valve. This renders the I associated CCW surge tank and therefore the associated CCWs i loop to be inoperable. The result is entry into multiple l Technical Specification LCO Action Statements if done I during plant operation. Performing the CLOSE tests via 1 LEAKAGE tests at cold shutdown intervals is consister' l with NUREG-1482 (Ref' e rence 2.5.3) Section 4.1.4.

^

5.6 52 1203NU280, Check Valve CCW to RCP P001 Seals 52 1203NU281, Check Valve CCW to RCP P002 Seals 52 1203NU282, Check Valve CCW to RCP P003 Seals

, $2 1203NU283, Check Valve CCW to RCP P004 Seals 5.6.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

5.6.2 Alternate Testing: Stroke at cold shutdown intervals when plant conditions allow Containment entry for valve testing and CCPs are secured.-

i 5.6.3 These valves close to prevent backflow in the non-critical loop supply line providing cooling water to RCP Seal Heat Exchangers. MU280 through MU283 were originally put in the system to provide a barrier between the Reactor Coolant System and CCW in the event the RCP seal heat exchanger catastrophically failed. ,

5.6.4 In order to exercise these check valves both OPEN and CLOSED, interrupting flow to the reactor coolant pump ,

l' (RCP) seal. The closure would result in seal damage. I Accordingly, these valves can only be exercised when the 1

RCPs are secured (at cold shutdown). Additionally, I testing these valves requires a containment entry. I 6.0 CONDENSATE AND FEEDWATER ,

n 6.1 2(3)HV1105, Feedwater Bypass Valve for' Steam Generator E089, and, i 2(3)HV1106, Feedwater Bypass Valve for Steam Generator E088 6.1.1. Test Requirement: OM-10, Para. 4.2.1.1, test nominally .

every three months. l

)

6.1.2 Alternate Testing: Test these valves at cold shutdown

intervals.

ATTACHMENT 3 PAGE 14 0F 62 l

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

-ENGINEERING PROCEDURE S023-V-3.5 NUCLEAR ORGANIZATION UNITS 2 AND 3 REVISION 9 PAGE 120 0F 173 j

ATTACHMENT TCN/EC W A E

. ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) i 6.1.3 These valves serve to isolate the bypass line around the ,  !

main feedwater. regulation valves. .

'6.1.4 These valves-cannot be full stroke exercisod during power F operation as this would disturb steam generator level-

' control, which could result in plant shutdown.

6.22'3 HV4047, Feedwater Block Valve - Steam Generator E088, ,

L 2(3HV4048,FeedwaterIsolationValve-SteamGeneratorE088, l 2(3 HV4051, Feedwater Block Valve - Steam Generator E089, and, ,

2(3 HV4062 Feedwater Isolation Valve - Steam Generator E089 ,

6.2.1~ Test Requirement: OM-10, Para. 4.2.1.1, test nominally 1 every three months.

,. 6.2.2. Alternate Testing: Test these valves at cold shutdown intervals.

I 6.2.3 These valves block feed flow in the main feed lines

. entering containment. They are all outside the containment. Valves 2(3)HV4048 and 2(3)HV4052 are

containment Isolation valves.

6.2.4 Full stroke exercising these valves during )ower operation

would result in loss of feedwater flow to tie steam

' generator, which could result in a plant shutdown.

6.3 S2(3)1306MUO36, Main Feed Check at Steam Generator E089 j' -S2(3)1306Mul29, Main Feed Check at Steam Generator E088

6.3.1 Test Requirement: OM-10, Paragraph 4.3.2, exercise these  !

valves every three months. ]

l

, 6.3.2 Alternate Testing: At each refueling outage, test the valves by partial disassembly, inspection and manual stroking.

l 6.3.3 These valves are in the main feedwater supply to the steam 4

generators, and are norma 11i full open while main feedwater is supplied to the steam generators. To exercise these valves CLOSE would require securing main'

< feedwater to the steam generators. During a loss of feedwater accident, these check valves close isolatin main feedwater piping from auxiliary feedwater flow.' g the f

4 ATTACHMENT 3 PAGE 15 0F 62

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 l UNITS 2 AND 3 REVISION 9 PAGE 121 0F 173 t I J

ATTACl#

TCN/EC LENT Ol 3M l ALTERNATE TESTING JUSTIFICATION AE BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL- l i

(Continued) 1 6.3.4 Closure of these valves is verified by disassembly.and . ,

)

hand-stroking the valves. The use of non-intrusive test techniques to verify closure have been considered, and ,

determined to be impractical at this point. The valves are located in containment, and performance of magnetic.

and/or' acoustics would require working in containment at-

j. power, which would increase radiation exposure.

Ultrasonics have been attempted in the past, but were t unsuccessful because ultrasonics depend upon water as a 4

medium, and the water drains from these valves 'upon shutdown. Radiography may be feasible, but would require securing access to the refueling deck during the outage, thus impacting the critical. path of the outage. Also, valve degradation has been observed in these valves, and i as a result all valves are disassembled each outage to

,- inspect for continued degradation. Thus, no additional .

impact (e.g., human error) is introduced in performing the.

hand-stroke to credit the IST.

. ~6.3.5 A full open stroke of the valves is performed upon return

to power.

6.3.6 ON-10, Section 4.3.2.2, Exercising Requirements, Paragraph (e) stipulates if exercising is not practicable during plant operations or cold shutdowns, it may be limited to full stroke during refueling outages.

6.3.7 hetion 4.3.2.4(c), Valve Obturator Novement, further states, "As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to verify ,

operability of check valves may be used."

I 6.3.8 Disassembly and inspection is performed in accordance 1 with, and does not deviate from, ON-10, Para 4.3.2.4, and GL 89-04, Position 2.

6.4 52(3)1305MU124, AFW Check Valve at Steam Generator E089, and. I

$2(3)1305NU448 AFW Check Valve at Steam Generator E088 6.4.1 Test Requirement: ON-10, Para. 4.3.2, test nominally every three months.

6.4.2 Alternate Testing: Test these valves at cold shutdown i intervals.

1 ATTACHNENT 3 PAGE 16 0F 62 l l

i

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

, NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 122 0F 173 ATTACMENT J 61h TCN/EC i ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL l (Continued)

. 6.4.3 These valves prevent backflow out of the steam generators in the event of an auxiliary feed line rupture. This l 1 provides )rotection from pipe whip and jet-impingement and i loss of tie steam generator in the loss of f.uxiliary. feed. 1

! line accident.

6.4.4 Exercising these. valves while the plant .is'at power would -- -

result in placing unnecessary thermal stresses on the- 1 feedwater piping, which could result in premature failure m j of this piping. ,

7.0 CONTAINMENT HVAC (NORMAL) i 7.1 2 HV9948,. Containment Purge Supply, HV9949, Containment Purfa Susply, 2 ,

2 HV9950 Containment Purge Ex1aust, and, l 2 HV9951, Containment Purge Exhaust i

7.1.1 Test Requires.ent: OH-10, Para. 4.2.1.1, test nominally every three months.

1

[ 7.1.2 Alternate Testing: Test these valves at cold shutdown  !

, intervals.

7.1.3 Containment isolation for the main ventilation piping into I and out of containment.

7.1.4 These valves are passive except in Modes 5 and 6, at which time they are tested. In addition, exercising these valves during plant power operation would result in '

i non-compliance with the Technical Specifications. j

{ 8.0 CONTAINMENT SPRAY 8.1 2(3)HV8150,IsolationValve-ShutdownCoolingSystemHeatExchanger  ;

E004 to LPSI Header, and, i 2(3)HV8151. Isolation Valve - Shutdown Cooling System Heat Exchanger

4 E003 to LPSI Header- ,

8.1.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nominally f-every three months. ,

I 8.1.2 Alternate Testing

Test these valves at cold shutdown i

~ intervals.

, 8.1.3 These valves provide isolation between the outlet of the Shutdown Cooling System (SDCS) heat exchanger and the LPSI discharge header to the Reactor Coolant System. They are opened for Shutdown Cooling System operation and must )

remain closed during power operation.

ATTACHMENT 3 PAGE 17 0F 62 i

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 123 0F 173

' ATTACHMENT L TCN/EC N ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL

j. (Continued) l l

8.1.4 For ECCS system operability (in plant Modes 1, 2 and 3) , ,

the Technical Specifications (Surveillance 4.5.2.a) i require verification at least once per twelve hours that i HV8150 and HV8151 are closed and power to the valve operators is removed.

8.1.5 Testing these' valves at a cold shutdown interval is consistent with NUREG-1482, Para. 3.1.1. Removing these

. valves-from power lockout, restoring power and opening them in Modes 1, 2 or 3 involves a hardship; i.e.,

repositioning of a breaker from "off" to "on", and closing t the manual isolation valves for HV8150 and HV8151. Manual action would be required to restore the ECCS if an

, accident occurred while the test was in progress. ,

4

. 8.1.6 This risk outweighs the benefits achieved with a quarterly.

test in light of the facts that (1) these valves are in 4 the idle shutdown cooling loops that are not used except when the plant is placed in cold shutdown, (2) being in power lockout, these valves have a minimal probability of failure. They are idle (>otential sources of failure are  ;

very limited), and, (3) tie realignment of the system for l the exercise tests in question invalidates the assumptions I in the Safety Analysis (see the Technical Specification Bases, Section B 3/4.5.2). -

8.2 S2(3)1206MU004, Containment Isolation Stop Check Valve - Spray Header

1. 1(Code & Category: 2/AC)

S2(3)1206MU006 Containment Iso?ation Stop Check Valve - Spray Header

1. 2 (Code & Category: 2/AC) ,

8.2.1 Test Requirement: OH-10, Paragraph 4.3.2, exercise these

. valves every three months.

l

, 6.2.2 Alternate Testing: At each refueling outage, (1) test the valves by partial disassembly, inspection and manual strokingonarotatingbasis(onevalveperrefueling),

i and, (2) perform a partial stroke test (OPEN) of each

valve using system flow.

8.2.3 During partial disassembly the valve internals shall be visually inspected for worn or corroded parts, and the valve disks will be manually exercised. If it is found that the full stroke capability of the disassembled , valve is in question, the other valve will be similarly disassembled and inspected and manually full stroked during the same outage.

ATTACHMENT 3 PAGE 18 0F 62

. . . = - - --- - - . - . - -

NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3 REVISION 9 PAGE 124 0F 173 ATTACHMENT 3 TCN/EC GO ALTERNATE TESTING JUSTIFICATION AND BASIS FOR'0THER THAN OUARTERLY TEST INTERVAL (Continued) 8.2.4 Following reassembly and prior to return to service, these valves will be tested by partial stroking using system flow.

8.2.5 FULL FLOW TESTING

.I These valves open to allow a flow of water from the containment spray pump discharge into the containment spray ring headers. They are inside the containment building in the line leading from the Containment penetration to the riser supplying the ring headers and.

s) ray nozzles. As a consequence full-stroke exercising _

t1ese valves through this flow path using the containment spray pumps would result in a containment spray-down and consequent potential equipment damage as well as create i additional liquid radwaste to be removed from the Containment Building sump.

8.2.6 PARTIAL FLOW TESTING

.I The riser inside the containment building is drained each refueling and refilled prior to returning the plant to service. When the riser is being filled with water, the water can be put in the system upstream of each stop check valve. Therefore, this flow through the Spray Header Containment Isolation Stop Check Valves during the filling of the riser would result in a partial stroke of these valves. Other methods to achieve a partial open stroke are also available.

8.2.7 NON-INTRUSIVE TESTING

.1 The use of non-intrusive te'st techniques to verify full

open capability has been considered, and determined to be impractical at this point. Acoustics were attempted to determine whether the valves went full open at a reduced flow, but no opening impact could be detected.

t i

i ATTACHMENT 3 PAGE 19 0F 62

i NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 l l UNITS 2 AND 3 -REVISION 9 PAGE 125 0F 173 ATTACHNENT 1 N

t j TCN/EC f- ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL

,' (Continued)

[ '8.

2.8 CONCLUSION

. 1 NRC Generic Letter 89-04, Attachment 1, Position 2, j identifies partial' disassembly and inspection as an j acceptable alternative for stroking a valve when it is i t impractical to use flow. In this case, there is no way to <

L stroke these valves with the existing system design using flow. The Code required full-stroke testing using flow

, could'only be performed after considerable modification of the system design, such as installation of an instrumented i test loop. The high' costs of the necessary design changes l involved would not be justified by the improve;nent of the valve testing. Further, the additional valves, piping, supports and penetrations could result in reduced plant reliability.

p )

i ", 8.2.9 TEST SCHEDULE I

! . 1 Each valve is disassembled and inspected each refueling L outage which requires additional draining of the

- associated system piping over and above draining the riser j as previously discussed. This generates a significant amount of radioactive liquid waste. In addition, considerable radiation exposure can be received by personnel performing the partial disassembly, hand stroking and inspection. As a consequence, there is a

clear advantage in reducing the number of these tests required in each refueling.

l

. 2 GL 89-04 allows development of staggered testing of like '

E components by establishing an inspection plan for similar groups of valves. This is stated in position 2 of the

, Generic Letter. Disassembly and inspection is performed

) in accordance with, and does not deviate from, OH-10, Para 4.3.2.4, and GL 89-04, Position 2.

8.3 $2(3)1206NU010 Pump 2(3)P012 Miniflow Stop Check Valve,

$2(3)1206NU011 Pump 2(3)P013 Miniflow Stop Check Valve j- -

8.3.1 Test Requirement: ON-10, Para. 4.3.2, test nominally every three months.

l ~8.3.2 Alternate Testing: Test these valves at cold shutdo,wn intervals.

8.3.3 These stop-check valves direct miniflow recirculation from

- the Containment Spray pumps back to the Refueling Water

. Storage Tanks.

I ATTACHMENT 3 PAGE 20 0F 62 l

i

, - r o. - . - - - - -

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3 REVISION 9 PAGE 126 0F 173 ATTACHMENT A

. ~,

TCN/EC O ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OVARTERLY TEST INTERVAL 1

(Continued) 8.3.4 Providing flow or pressure to verify completion of the .

closed stroke requires placing the miniflow line out of.

service for the HPSI,.LPSI and Containment Spray Systems.

This renders those systems inoperable and is therefore only practical in modes during which these systems are not

-required to be operable under the Technical

~

Specifications.

8.4 $2 1206MU012 Spray Pump 2 P012 Discharge Stop Check Valve.

52 1206MUO14 Spray Pump 2 P013 Discharge Stop Check Valve.

S2 1206MUO29, Spray Pump 2 P012 Discharge Check Valve to Shutdown Cooling System Heat Exchanger E004,

! 52(3)1206NUO30, Spray Nap 2(3)P013 Discharge Check Valve to Shutdown 4 Cooling System Heat Exchanger E003 l , 8. 4 .'1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

8.4.2 Alternate Testing: Test these valves at cold shutdown or reactor refueling intervals as explained below, i 8.4.3 Provido check valves to prevent back-flow through idle spray pumps and associated loss of flow and pressure from the outlet of the operating spray pump. ,

l 8.4.4 The OPEN EXERCISE test for these valves requires a flow rate of 2300-2750 gpm. The flow path for this test involves establishing flow through S2(3)1204MU162 to the RWST. The line-up uses a portion of the common LPSI header for the flow path. Aligning the Containment Spray ,

(CSS) and LPSI systems in this manner renders one train of containment spray and both trains of LPSI inoperable.

With the LPSI and CSS aligned to support this testing, ,

LPSI flow from both trains is diverted to the RWST. This 4 constitutes a loss of LPSI system function and places the plant in a condition which is outside the licensing basis.

, Because of this loss of system function, MU012, 014, 029 and 030 are excluded from gyarterly testing consistent withtheguidanceinNUREG-1482, Para.3.1.1(1).

8.4.5 The EXERCISE CLOSED test is also done at cold shutdown

intervals. There is a difference between the CLOSE tests

for Unit 2 and for Unit 3. Unit 2 has a vent betwegn valve pairs that allow the CLOSE tests to be performed by measuring leakage using a test rig. Performing these tests at refueling intervals while measuring leakage is consistent with NUREG-1482 (Reference 2.5.3)

Section 4.1.4.

ATTACHMENT 3 PAGE 21 0F 62 f

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5

- UNITS 2 AND 3 REVISION 9 PAGE 127 0F 173

ATTACHMENT 3 J

TCN/EC Cl'Y

) '

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL l (Continued) )

_8.4.6 This vent does not exist in Unit 3, and the_ valves are verified CLOSE using radiography. The radiogra 2y is i '

performed at refuellag intervals on a rotating ) asis  ;

consistent with NUREG-1482 (Reference 2.5.3)

. Section 4.1.2. ,

i  :

4 8.4.7 _ As an additional argument to CLOSE test the valves at  !

refueling intervals, OM-10, paragraph 1.3 defines exercising as "the demonstration based on direct visual or  ;

indirect positive indications that the moving parts of a valve function." Since it is not possible to OPEN EXERCISE test these valves at a quarterly interval, verifying the valves CLOSED at a quarterly interval would

, not satisfy the code requirement to exercise the valves.

Therefore, the interval for the CLOSED EXERCISE test is

, set at the same interval as the OPEN EXERCISE test.

9.0 FUEL STORAGE POOL AND REFUELING  !

9.1 2(3)LV0227C, RWST To Charging Pump Suction, and,

$2(3)1219MU052. RWST T006 to Charging Pump suction Header J 9.1.1 Test Requirement

0H-10, Paras. 4.2.1.1 and 4.3.2, test l

. nominally every three months.

9.1.2 Alternate Testing: Test these valves at cold shutdown intervals.

. 9.1.3 These valves provide flow of boric acid from the RWST into the suction of the charging pumps. ,

9.1.4 Opening these valves would result in injecting highly l concentrated boric acid into the reactor coolant system, causing plant shutdown.

10.0 NITROGEN GAS 10.152(3)2418MU002, Nitrogen Supply to Containment, and, S2(3)2418MU108 Nitrogen Supply to Safat'y injection Tanks 10.1.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

10.1.2- Alternate Testing: Test these valves at refueling Intervals.

'10.1.3 Containment isolation inside containment for nitrogen supply to various components.

ATTACHMENT 3 PAGE 22 0F 62

.---_..-------_-----_-__-s .-- r

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE' S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 128 0F 173 ATTACMENT

TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL i

(Continued) I t

i

! 10.1.4 The CVTC is performed in conjunction with the 10 CFR 50, l Appendix J seat leakage test. Testing of these valves

. requires utilization of LLRT test equipment and j containment entry. NUREG-1482 (Reference 2.5.3) i Section 4.1.4 allows performance of such tests at

- refueling intervals.

! 10.2 52 2418MU356, Backup Nitrogen cylinder MV-057 Check Valve Testing, ,

52 2418MU358, Sr.ckup Nitrogen cylinder MV-058 Check Valve, .l' 2

52 2418MU360, Backup Nitrogen, Cylinder MV-05g Check Valve, i 52(3)2418MU362, Backup Nitrogen cylinder M-060 Check Valve, Backup Nitrogen Cylinder MV-061 Check Valve, 52(3)12418MU364, 52(3 2418MU366, Backup Nitrogen cylinder W-062 Check Valve, l

, 52 2418NU368, Backup Nitrogen Cylinder MV-062 Check Valve, i 1

52 2418NU371, Backup Nitrogen cylinder MV-064 Check Valve,

52 2418MU373, Backup Nitrogen cylinder M -065 Check Valve, i l

$2(3 2418MU375, Backup' Nitrogen cylinder W-066 Check Valve,

}-

f' 52(3 2418NU377, Backup Nitrogen cylinder MV-067 Check Valve, 52(3 2418MU379, Backup Nitrogen cylinder W-068 Check Valve, i-52 2418MU387, Backup Nitrogen cylinder MV-069 Check Valve, f 52 2418MU389, Backup Nitrogen cylinder MV-070 Check Valve, 52 2418NU406, Backup Nitrogen cylinder M -102 Check Valve,

$2 2418NU408, Backup Nitrogen cylinder MV-103 Check Valve, 52 2418NU410 Backup Nitrogen cylinder MV-104 Check Valve.

[ $2 2418MU412, Backup Nitrogen Cylinder NV-105 Check Valve, ,

$2(3)2418MU414, Backup Nitrogen Cylinder MV-106 Check Valve, and

, 52(3)2418MU416, Backup Nitrogen cylinder MV-107 Check Valve i

! 10.2.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally

every three months.

10.2.2 Alternate Testing: Test at cold shutdown intervals in a plant mode that permits the ' associated CCW train to be inoperable.

10.2.3 These valves open to admit backup nitrogen to the CCW surge tanks from the individual nitrogen storage bot,tles.

F They close to prevent depressurization in the event a

. bottle is removed for replacement.

ATTACHMENT 3 PAGE 23 0F 62

NUCLEAR ORGANIZATION. ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3 REVISION 9 PAGE 129 0F 173 ATTACHMENT A p l TCN/EC P J ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL I (Continued) 10.2.4 These valves _ require placing the associated Component Cooling Water Loop 00S. This can only be done.in a mode in which the Technical Specifications permit one CCW Loop to be inoperable.

10.2.5 These are non-code valves. See General Note #5 in Attachment 2. The analyses provided in Reference 2.1.1 h specifies the type (s) of tests which must be performed. A Cold Shutdown interval has been determined to be sufficient to provide assurance of operability for these valves, and is consistent with Reference 2.5.2, Response to Questions 53 and 110, and Reference 2.5.3 Section 3.4.

10.3 S2(3)2418MU398, Nitrogen Supply to component Cooling Water Surge Tank T0048, and,

, $2(3)2418MU402, Nitrogen Supply to component Cooling Water 10.3.1 Test Requirement: 0M-10, Para.'4.3.2, test nominally every three months.

10.3.2 Alternate Testing: Stroke at refueling intervals.

10.3.3 These check valves provide nitrogen makeup to the CCW surge tanks. To achieve a CLOSE stroke of these check valves, the upstream volume of the associated siping must be isolated and depressurized. This renders tte associated CCW surge tank and therefore the associated CCW

, loo) to te inoperable. The result is entry into multiple Tecinical ';pecification LCO Action Statements if done during plant operation. ,

10.3.4 The test involves installation of a flowmeter on a test tee and measuring leakage flow past the valves.

Performing the CLOSE test of these valves in conjunction with the LEAKAGE test at refueling intervals is consistent with NUREG-1482 (Reference 2.5.3) Section 4.1.4.

11.0 W CLEAR SAMPLING ,

11.1$2(3)1212MU261, $1 System Loop 8 to Central Liquid Sample System Check Valve

$2(3)1212MU262, $1 System Loop A to Central Liquid Sample System Check Valve ,

S2(3)1212MU580 Nuclear Service Water to Liquid Sample System Check

. Valve 11.1.1 Test Requirement

0M-10, Para. 4.3.2, test nominally l every three months.

I ATTACft1ENT 3 PAGE 24 0F 62 t

l t

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023-V-3.5 UNITS 2 AND 3 PAGE 130 0F 173

. REVISION 9 2

ATTACHMENT 1 TCN/EC 4M ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued)

$ 11.1.2 Alternative Testing: These valves will be verified closed- ,

at Refueling intervals. The only way to verify closure of l these valves is to measure leakage into a test volume

, upstream of the check valves using 'a hydro pump. The l closed tests are performed in conjunction with the leakage j tests'on MU261, MU262, MU580, MU010, and HV05888. The

! elaborate valve line-up, test equipment required, and high man-hours required to perform this test make it impractical to perform on a more frequent basis.

Performing the CLOSE tests in conjunction with the LEAKAGE

tests at refueling intervals is consistent with NUREG-1482

(Reference 2.5.3) Section 4.1.4.

12.0 NUCLEAR SERVICE WATER

, 12.152(3)l415NU236 Containeent Isolation Check Valve - Nuclear Service

Water

12.1.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

12.1.2 Alternate Testing: Test this valve at cold shutdown intervals.

12.1.3 This valve provides containment isolation for the penetration conveying Nuclear Service Water into the containment for use during maintenance, system fill, refueling, etc.

. 12.1.4 The CLOSE stroke verification requires containment access. ' l This is only practical during plant shutdown.

13.0 REACTOR COOLANT 13.1 2 HV0296A, Reactor Head Vent, 2 HV02968, Reactor Head Vent, 2 HV0297A Pressurizer Vent Valve, 2 HV02978 Pressurizer Vent Valve, 2 HV0298, Vent to Containment from Reictor Head / Pressurizer, and, t 2 HV0299, Quench Tank Inlet from Reactor Head / Pressurizer Vent 13.1.1 -Test Requirement: 0M-10, Para. 4.2.1.1, test nominally.

p every three months. ,

i 13.1.2 Alternate Testing: Stroke these valves open and closed at i- cold shutdown intervals.

. '13.1.3 The function of these valves is to vent various components in the Reactor Coolant System (RCS).

4 ATTACHMENT 3 PAGE 25 0F 62

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 131 0F 173 ATTACHMENT J o 4 #

TCN/EC ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OVARTERLY TEST INTERVAL

, (Continued) 13.1.4 Power is normally removed from these solenoid valves because they are part of the RCS boundary and opening them ,

while the RCS is pressurized would release RCS to the vent l system. Both the very restrictive Action Statement in the Technical Specification (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and the risk of a potential accident, dictate against the quarterly IST interval in Modes 1 through.4. ,

a' 1 Technical Specification 3.4.10, Reactor Coolant Gas Vent

.1 System, requires the. valves listed all remain closed in .

Modes 1 through 4. If any of these valves are inoperable  ;

or open, the Action Statement must be completed within 4  !

hours. '

.2 The design redundancy of the RCS Gas Vent System serves to 1 i . minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent

, valve, or control system does not prevent isolation of the

. vent path (from Technical Specification basis, Paragraph

! 3/4.4.10). If, in Modes 1 through 4, a valve were to remain open during an exercise IST, the potential for a i Loss of Coolant Accident (LOCA) would exist.

13.2 2(3)HV9201, Regenerative Heat Exchanger E063 to Auxiliary Spray.

52(3)1201MU019 Auxiliary Spray Check Valve, and,

$2(3)1201MU129 Auxiliary Spray to Reactor Coolant System from Charging Pumps 13.2.1 Test Requirement: OM-10, Paras, 4.2.1.1 and 4.3.2, test nominally every three months. ,

13.2.2 Alternate Testing: Stroke the valves at cold shutdown intervals, i

13.2.3 These valves provide flow to the auxiliary spray into the pressurizer, either through the regenerative heat exchanger, or bypassing the regenerative heat exchanger.

13.2.4 Exercising wou k result in unnecessary severe thermal transients and stress on the pressurizer spray nozzle.

13.3 2(3)HV9202 Regenerative Heat Exchanger E063 to Reactor Coolant System Loop 2A, and, ,

4 2(3)HV9203 Regenerative Heat Exchanger E063 to Reactor Coolant System Loop 1A 13.3.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally every three months.

ATTACHMENT 3 PAGE 26 0F 62

I.

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 J UNITS 2 AND 3 REVISION 9- PAGE 132 0F 173

! ATTACHMENT-TCN/EC 'b-

[  ; ALTERNATE-TESTING JUSTIFICATION'AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL

, .(Continued) 13.3.2- Alternate Testing: Stroke the valves open and closed at cold shutdown intervals.

I '

13.3.3 These valves block the charging line from the Regenerative i Heat Exchanger to the Reactor Coolant System when they

. -close. They are located in the line between these two - -

. components. .

13.3.4- These valves must remain open during power operation in cr u to ensure consistency with assumptions made regarding system flow to the RCS cold legs in the accident analysis and to comply with the intent of LCO 3.5.2. In addition to Technical Specification action statement 4

entry, exercising either air operated valve during plant

- power operation would require securing letdown and

, charging entirely. This is a lengthy plant evolution as l 1s the restoration of letdown following the exercise test.

Further, stopping charging and letdown flow imposes a i large thermal transient on the components in the charging /

letdown path which would eventually damage these  !

! components such as the letdown heat exchanger and the l

- regenerative heat exchanger.

13.4 2(3)HV9204. Reactor Coolant System Loop 28 Letdown to Regenerative ,

Heat Exchanger, and,  !

!~ 2(3)TV0221 Letdown. Isolation Valve j l 13.4.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nominally every three months.

13.4.2 Alternate Testing: Stroke the valves closed at cold shutdown intervals.

13.4.3 These valves are in the letdown line from the Reactor Coolant System to the Regenerative Heat Exchanger and e close to block flow through these lines.

13.4.4 Exercising these valves duri.ng power operation would

. result in unnecessary thermal stress transients on the regenerative heat exchanger and reactor coolant system-charging nozzles.

13.5 2(3)HV9217. Reactor Coolant System Bleed Off to Volume ,

1. Control Tank, and,

.2(3)HV9218,ReactorCoolantSystemBleedOfftoVCTIsolationValve c Inside Containment 13.5.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally every three months.

. ATTACHMENT 3 PAGE 27 0F 62 i

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

i

' NUCLEAR ORGANIZATIONl ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 133 0F 173

ATTACHMENT A o ,  :

'TCN/EC WV-4

ALTERNATE TESTING' JUSTIFICATION AM BASIS FOR OTHER THAN GUARTERLY TEST INTERVAL

.(Continued).

I 1 . . . .

.13.5.2 Alternate Testing:~ Stroke the valves closed at cold shutdown intervals,

]

i 13.5.3 These valves are the containment isolation valves for the

,. reactor coolant pump' seal leakoff line to the Volume j Control Tank (VCT). _

'13.5.4 Exercising these valves could result in Reactor Coolant i- Pump (RCP) seal failure and subsequent reactor shutdown.

! Operation of the RCP. mechanical seals depends on steady

bleed off flow to maintain proper staging and seal

cooling. Without continuous bleed-off the seals very . .

. .quickly overheat and are destroyed. Because of historical

performance problems with our RCP seals, great care is exercised to avoid even momentary fluctuation or

. interruption of seal bleed-off flow. Exercising these valves while the RCPs are in operation interrupts the. seal i; bleed-off flow and consequently, HV9217 and HV9218 cannot

be shut while the RCPs are-in operation without the risk of destruction of the RCP seals.  !

1 13.6 2(3)XCV9219. Thermal Relief of Regenerative Heat Exchanger

. 13.6.1 Test Requirement: 0M-10, Para. 4.3.2.1, test nominally every three months.

l 13.6.2 Alternate Testing: Test at Cold Shutdown Intervals.

l- 13.6.3 This is a spring loaded check valve used as a thermal

relief valve in the event charging is isolated (Closure of ,

L 2(3)HV9202 and 2(3)HV9203 without isolating letdown. This bypass line can be credited as the boration flow path required by Technical Specifications 3.1.2.1 and 3.1.2.2.

As such, normally this normally closed valve is required

. to open.

13.6.4 .This valve is tested OPEN by closing 2(3)HV9202 and 1 i

i 2(3)HV9203 and ensuring that flow still exists. The justificationfornotclosing2(3)HV9202and2(3)HV9203

quarterly (i.e., testing at Cold Shutdown intervals) is

provided in Section 13.3. 2(3)XCV9219istestedin i'

conjunction with the closure of these valves.

' Additionally, 2(3)XCV9219 is only required as a flow path when the Unit is in a shutdown condition, and is tested prior to placing it into service for this purpose.

t ATTACMENT 3 PAGE 28 0F 62 i

2

. , ~ - - ., v , a

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 134 0F 173 TCN/EC N ATTACl#IENT A ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) 13.7 52(3)1201MUO20. Charging Line Check Valve to Reactor Coolant System Loop 2A 13.7.1 Test Requirement: OM-10, Para. 4.3.2, test nominally every three months.

-13.7.2 Alternate Testing: Test valve at cold shutdown frequency.

13.7.3 This valve prevents backflow from the Reactor Coolant .

System to the Regenerative Heat Exchanger when it closes upon reversal of pressure / flow in the charging line to the Reactor Coolant System. The valve is located in the line between these two components.

13.7.4 This valve cannot be tested without closing HV9203

, (discussed elsewhere in this Attachment).

13.852(3)1201MUO21, Charging Line Check Valve to Reactor Coolant System Loop 1A 13.8.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

13.8.2 Alternate Testing: Test valve at cold shutdown frequency. j l

13.8.3 This valve prevents backflow from the Reactor Coolant

System to the Regenerative Heat Exchanger when it closes upon reversal of pressure / flow in the charging line to the

! Reactor Coolant System. The valve is located in the line between these two components. ,

13.8.4 This valve cannot be tested without closing HV9202 i (discussedelsewhereinthistable).

13.9 ht(3 1201MU200, Pump 2(3)P016SuctionCheckValve,and, SE(3 1201MU202, Pump 2(3)P015SuctionCheckValve

13.9.1 Test Requirement

0M-10, Para. 4.3.2, test nominally l- every three months. '

13.9.2 Alternate Testing: Test these valves at cold shutdown intervals. ,

13.9.3 These check valves provide flow into the suction of 'the respective LPSI pumps and prevent backflow from the pump into the lines from the RWST, etc.

8 ATTACHMENT 3 PAGE 29 0F 62

...._t ,..~,.x .

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

~

-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5' UNITS 2 AND 3 REVISION 9 PAGE 135 0F 173

' ATTACHMENTJ TCN/EC W-1 ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) e i

13.9.4 These are check valves on the shutdown cooling (SDC) line -

to the LPSI pump suctions. The suction from this line E '

comes from the RCS, on the hot leg injection line inside the first pressure isolation valve. The only' flow path l that would open these valves during plant operation would j require taking suction from the RCS and pumping it into the RWST on miniflow, which is not practical. The only -

practical method of opening these valves is on shutdown cooling, and so the valves must be tested at cold shutdown intervals. ,

13.9.5 Closura of these valves is verified by measuring leakage past the valves. OM-10, Paragraph 1.3 defines exercising as "the demonstration based on direct visual or indirect positive indications that the moving parts of a valve.

I- . function." Since it is not possible to OPEN exercise test

these valves at a quarterly interval, verifying the valve -

closed at a quarterly interval would not satisfy the code 4 requirement to exercise the valve. Once the valve has

been verified closed, there is no mechanism to open the valve once SDC is secured, and hence no benefit on re-verifying closure on a quarterly basis. Therefore, the interval for the CLOSE exercise test is set at the same interval as the OPEN exercise test. This position is 4 further supported by NUREG-1482 (Reference 2.5.3)

Section 4.1.4, which recognizes the difficulty in 4 performing a seat leakage test to satisfy a CLOSE test, and provides the extension of the test interval for testing of this nature is appropriate.

, 13.10 $2(3)1201NU976, Check Valve Pressurizer Spray Line from Reactor Coolant Loop 1A

S2(3)1201NU977, Check Valve Pressurizer Spray Line from Reactor

Coolant Loop IB

) 13.10.'1 Test Requirement: 0M-10,' Para. 4.3.2, test nominally i- every three months.

13.10.2 Alternate Testing: Test val've at cold shutdown frequency.

4 ATTACHMENT 3 PAGE 30 0F 62 l:

c r i

NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE S023-V-3.5 r UNITS'2 AND 3 REVISION 9 PAGE 136 0F 173 ATTACHMENT J 61M l TCN/EC

~

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued) ,

1 L

^

13.10.3 Valves open to allow pressurizer spray flow. Valves are ,

a held partially open during normal operation by flow. To. l

! minimize thermal shock of the nozzles, the pressurizer . 1 4

spray control valves PV0100A & 8 provide about 2 gpm of l

continuous flow to maintain the pressurizer spray nozzles  !

at approximately Reactor Coolant System cold leg l

temperature. Valves MU976 and MU977 must close to prevent ,

flow diversion back to the Reactor Coolant System from the  !

Chemical & Volume Control System should PV0100A fail to i close. AOI (Abnormal Operating Instruction) S023-13-2  ;

j . directs charging pump discharge to the Chemical and Volume Control System auxiliary pressurizer spray line instead of f the normal pressurizer spray path through PV0100A and

PV01008. If these valves were to stick open, it would bypass this auxiliary spray flow to the Reactor Coolant

i . System and disable the spray function in the pressurizer.

13.10.4 During normal plant operation, Reactor Coolant System l pressure is maintained via pressurizer spray with flow i- through these valves. To CLOSE stroke MU976 and NU977 4 would require closing the upstream pressurizer spray control valve and isolating the pressurizer spray line.

i This would place the plant in an unsafe condition due to loss of spray flow and consequent pressurizer level and 4

pressure control. Also the CLOSE stroke test can only be performed at cold shutdown intervals because the valves

are inside the Containment and require a Containment entry

' to the perform test. Nuclear service water is used to

stroke these valves closed.

14.0 RESP. & SERVICE AIR SYSTEM 14.1 2(3)NV5388. Containment Isolation Valve - Instrument Air 14.1.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally every three months.

i 14.1.2 Alternate Testing: Test this valve at cold shutdown intervals.

14.1.3 .This valve provides isolation for the penetration that

, conveys instrument air into the containment building.

14.1.4 Exercising this valve during plant power operation '

isolates instrument air to the Containment and could result in a plant shutdown.

ATTACHMENT 3 PAGE 31 0F 62-4 2

e

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 )

UNITS 2 AND 3 REVISION 9 _ PAGE 137 0F 173 ATTACHMENT l TCN/EC ALTERNATE TESTING JUSTIFICATION ~AND BASIS FOR OTHER THAN'0UARTERLY TEST INTERVAL (Continued) l 14.2 52(3)2417MU016 Instrument Air Containment Isolation Check - Inside. ,

Containment 14.2.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally -

every three months.  !

14.2.2 Alternate Testing: ' Test this valve at refueling intervals.

14.2.3 This valve provides . isolation for the penetration-that l conveys instrument air into the containment building.

14.2.4 Thereisnowaytoplaceabackpressureonthisvalve without losing control of the Safety Injection Tank Drain Valves, hence this valve can only be tested when SIT Tanks

, are not required (i.e., Modes 5 and 6).

-15.0 SAFETY INJECTION j l

-15.12(3)HV8152.IsolationValve-ShutdownCoolingSystemHeatExchanger I

E004 Inlet. l

= 2(3)HV8153, Isolation Valve - Shutdown Cooling System Heat Exchanger l E003 Inlet.

15.1.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nominally every three months.

15.1.2 Alternate Testing: Test these valves at cold shutdown

, intervals.

I 15.1.3 2(3)HV8152 and 2(3)HV8153 are in the Shutdown Cooling l System (SDCS). They are employed in directing SDCS flow into the SOCS heat exchanger.

15.1.4 For ECCS system operability, the Technical Specifications  ;

(Surveillance 4.5.2.a) require verification at least once per twelve hours that these valves are closed and power to

the valve operators is remoyed.

, 15.1.5 Testing these valves at a cold shutdown interval is consistent with NUREG-1482, Para. 3.1.1. Removing these valves from power lockout, restoring power and repositioning them in Modes 1, 2 or 3 involves a hardship;

'i.e., repositioning of a breaker from "off" to 'on" (and closing the manual isolation valves for HV8152 and

. HV8153). Manual action would be required to restore the ECCS if an accident occurred while the test was in progress.

4 ATTACHMENT 3 PAGE 32 0F 62 i

_________._.______m.__.____E.. ~ w,- - ,,r7

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

l NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE S023-V-3.5 .

i UNITS 2'AND 3 REVISION 9 PAGE 138 0F 173 l L ATTACMENT1 TCN/EC N:

ALTERNATE TESTING JUSTIFICATION AND BASIS'FOR OTHER THAN QUARTERLY TEST INTERVAL j _(Continued) 15.1.6 This risk outweighs the benefits achieved with a quarterly

, test in light of the facts that (1) these valves are in the idle shutdown cooling loops that are not used except when the being in power loccout, >1 ant is placed these valves in have colda minimal shutdown, pro (2)bability of failure. They are idle (potentialisources of failure are verylimited), and,(3) the realignment of the system .

for the exercise tests in question invalidates the

_ assumptions in the Safety Analysis (see the Technical Specification Bases,,Section B 3/4.5.2).

'15.2 2(3)HV9420, Control Valve - HPSI Header #1.to Reactor Coolant System Loop 2 Hot Leg, and,

2(3)HV9434, Control Valve - HP51 Header #2 to Reactor Coolant System Loop 1 Hot Leg i 15.2.1 Test Requirement

OH-10, Para. 4.2.1.1, test nominally

! every three months, f

15.2.2 Alternate Testing: Test these valves at cold shutdown intervals.

15.2.3 For ECCS system operability, the Technical Specifications  !

(Surveillance 4.5.2.a)requireverificationatleastonce per twelve hours that these valves are closed and power to the valve operators is removed.

15.2.4_ Testing these valves at' a cold shutdown interval is l consistent with NUREG-1482, Para. 3.1.1. Removing these i valves from power lockout, restoring power and ,

repositioning them in Modes 1, 2 or 3 involves a hardship; i.e., repositioning of a breaker from "off" to "on".

Manual action would be required to restore the ECCS if an accident occurred while the test was in progress.

15.2.5 This risk outweighs the benefits achieved with a quarterly l test in light of the facts that; (1) being in power lockout, these valves have 4 minimal probability of failure. They are idle (>otential sources of failure are very limited); and, (2) tie realignment of the system for the exercise tests in question invalidates the assumptions-in the Safety Analysis (see the. Technical Specification Bases,-Section B 3/4.5.2). .

15.3 2(3)HV0396, Flow Control Valve - LPSI Pumps to Shutdown Cooling System 2(3)HV8160. Flow Control Valve - Shutdown Cooling System Heat Exchanger Bypass,  !

2(3)HV8161,BlockValve-ShutdownCoolingSystemHeatExchanger Bypass to LPSI, ATTACHMENT 3 PAGE 33 0F 62 l

i d - _ . _ _ _ _ _ - - . .___- _ .. .- . _ _ __-._ ________..__.___

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

. , - . _ . . ~ _

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 139 0F 173 ATTACHMENT ) y TCN/EC W ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OVARTERLY TEST INTERVAL (Continued) 15.3.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nominally ,

every three months.

15.3.2 Alternate Testing: Test these valves at cold shutdown intervals.

15.3.3 These valves are used in establishing and controlling the flow 3ath when the Shutdown Cooling System is in operation and tie plant is shutdown.

15.3.4 For ECCS system operability, the Technical Specifications (Surveillance 4.5.2.a) require' verification at least once per twelve hours that these valves are closed and power to the valve operators is removed.

. 15.3.5- Testing these valves at a cold shutdown interval is consistent with NUREG-1482, Para. 3.1.1. Removing these.

valves from power lockout, restoring power and repositioning them in Modes 1, 2 or 3 involves a hardship; i.e., repositioning of a breaker from "off" to 'on".

Manual action would be required to restore the ECCS if an accident occurred while the test was in progress.

15.3.6 This risk outweighs the benefits achieved with a quarterly test in light of the facts that; (1) being in power lockout, these valves have a minimal probability of failure. They are idle (potential sources of failure are verylimited); and,(2) the realignment of the system for the exercise tests in question invalidates the assumptions in the Safety Analysis (see the Technical ,

Specification Bases, Section B 3/4.5.2).

15.3.7 Also, with regard to 2(3)HV8160 and 2(3)HV8161, being in the common LPSI hekder, repositioning either of these valves also renders both trains of LPSI inoperable since 4

they are in the connon discharge line for the LPSI system.

Because of this loss of system function, 2(3)HV8160 and 2(3)HV8161 are excludod from quarterly testing consistent with the guidance in NUREG-1482, Para. 3.1.l(1).

15.4 2(3)HV9336 Isolation Valve - SDCS to LPSI Pump Suction, 2(3)HV9379, SDCS Bypass to LPSI Suction Isolation Valve - Seal 15.4.1 Test Requirement: Manually stroke in addition to exercising with the power operator in accordance with .

0M-10, Para. 4.2.1.1, test nominally every three months. j 15.4.2 Alternate Testing: Manually exercise at cold shutdown j intervals. '

l ATTACHNENT 3 PAGE 34 0F 62 i

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 l UNITS 2 AND 3 REVISION 9 PAGE 140 0F 173 ,

j ATTACHMENT 3 l AM l

i TCN/EC.

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL I

(Continued) i

! 15.4.3 The manual stroke test is a non-Code required test. These l valves are used in establishing the Shutdown Cooling I System flow path when the plant is shutdown. The manual i stroke test specified for these valves is only required to

! be a partial stroke to the extent necessary to demonstrate i j the operation of the valve manually, including the ability i l

to engage the clutch.

i 15.5 2(3)HV9337. Isolation Valve - Shutdown Cooling System to LPSI Pump

. ' Suction, and, . 1

! 2(3)HV9339. Isolation Valve - Shutdown Cooling System from Reactor l Coolant System Loop 2 +

2(3)HV9377, Shutdown Cooling System Bypass to LPSI Suction Isolation Valve, and,

2(3)HV9378,ShutdownCoolingSystemBypasstoLPSISuctionIsolation

. Valve ,

1 15.5.1 Test Requirement: OH-10, Para. 4.2.1.1, test nominally j every three months. 1 Alternate Testing: Test these valves at cold shutdown 15.5.2 intervals.

4 15.5.3 These valves are used in establishing the Shutdown Cooling System flow path when the plant is shutdown.

15.5.4 These valves are required by Technical Specification 3/4.5.2 to be interlocked to prevent opening whenever reactor coolant system pressure exceeds 376 psia.

i 15.6 2(3)HV9340, Safety Injection Tank T004 Outlet Valve to Reactor Coolant l

. System Loop 1A, .

i 2(3)HV9350, Safety Injection Tank T009 Outlet Valve to Reactor Coolant System Loop 18, ,

2(3)HV9360,safetyInjectionTankT009OutletValvetoReactorCoolant l System Loop 2A, and,  ;

. 2(3)HV9370,SafetyInjectionTankT010OutletValvetoReactorCoolant

System Loop 28 .

l 15.6.1 Test Req':lrement: OH-10, Para. 4.2.1.1, test nominally every three months.

15.6.2 Alternate Testing: Test these valves at cold shutdo.wn I intervals.

15.6.3 These valves block the discharge path cf the Safety l Injection Tanks into the Reactor Coolant System when closed.

ATTACHMENT 3 PAGE 35 0F 62 I

- -- . . - . =. - - -

NUCLEAR ORGANIZATION ENGINEERING PRNEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 141 0F 173 l ATTACFMENT 3 -

l TCN/EC & ,/

i ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OVARTERLY TEST INTERVAL (Continued)

'15.6.4 Restoring power to these valves or closing these valves while the plant is at power would result in non-compliance with the Technical Specifications. Closing the SIT outlet valve isolates and renders the SIT inoperable. Technical Specification 3.5.1 is very restrictive, requiring action within one hour if.the SIT is rendered inoperable.

NUREG-1482, (April 1995) Para. 3.1.1, recognizes entry into very restrictive LCOs as a valid basis for deferral of the stroke test to cold shutdown.

15.7 2(3)HV9341, Safety Injection Tanii T008 Fill and Drain Line Isolation Valve

-2(3)HV9351, Safety Injection Tank T007 Fill and Drain Line Isolation Valve 2(3)HV9361, Safety Injection Tank T009 Fill and Drain Line Isolation r Valve 2(3)HV9371, Safety Injection Tank T010 Fill and Drain Line Isolation Valve 15.7.1 Test Requirement: OH-10, Para. 4.2.1.1, test nominally every three months, 15.7.2 Alternate Testing: Close stroke test these valves at cold shutdown intervals.

15.7.3 These valves are normally closed during plant operations i and are opened to fill the Safety Injection tanks. These valves are closed upon receipt of a SIAS. They are Reactor Coolant System boundary valves.

15.7.4 During plant operations, the lines downstream of these valves are depressurized and the valves are closed. In order to close stroke each valve, it must be opened and then stroked closed. Opening these valves causes the associated Safety Injection Tank to depressurize, contrary ,

to the requirements of Technical Specification 3/4.5.1. l This results in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action Statement.

15.8 2 HV9345, Safety Injection Tank 7008 ilent Valve. l 2 HV9355, Safety Injection Tank T007 Vent Valve. l 2 HV9365, Safety Injection Tank T009 Vent Valve, and, i 2 HV9375, Safety Injection Tank T009 Vent Valve j 15.8.1 Test Requirement: 0M-10, Para. 4.2.1.1, test nomina'lly every three months.

15.8.2 Alternate Testing: Test these valves at cold shutdown intervals.

ATTACHMENT 3 PAGE 36 0F 62 l

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-VIS-

_ UNITS 2 AND 3' REVISION 9 PAGE 142 0F 173 ATTACMENT 3 TCN/EC CFM ,

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN QUARTERLY TEST INTF,8y&L (Continued) 15.8.3 :These ulves provide a means of depressurizing'th'e Safety Injection Tanks.

4 15.8.4 During power operation, Technical Specifications require i power to be locked out for these valves. This prevents inadvertent depressurization of the Safety Injection Tanks.

15.9 2(3)HV9353, shutdown Cooling warm-up valve 2(3)HV9359, Shutdown Cooling warm-up valve j

l 15.9.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally every three months.

] -15.9.2 Alternate Testing:' Test these valves at cold shutdown -

4: i ttaquency when shutdown cooling is placed in service.

! 15.9.3 Lse valves are normally closed during plant operation and are used to regulate the amount of water that bypasses the core to limit cooldown. These valves are credited as active components in the FSAR but are not required to open

. in order to bring the plant to a safe shutdown according totheFailureModesandEffectsAnalysis(FMEA)inthe '

l

- FSAR.

1 15.9.4 These valves are closed during plant operation and are

! placed in service when shutdown cooling is required. To stroke these valves open during normal plant operation-would required entry into a one hour Action Statement

.under the Technical Specifications. This is because both ,

i trains of LPSI are put out of service for this stroke.

. Opening these valves will cause Safety Injection flow diversion from Reactor Coolant System toop 2A back to LPSI

pump suction.

l 15.10$2(3)1204MU001,RWST2(3)T005toSprayPump2(3)P012SuctionHeader

S2(3)1204MU002 RWST 2(3)T005 to Spray Pump 2(3)P013 Suction Header 15.10.1 Test Requirement

OH-10, Par'agraph 4.3.2, exercise these j; valves open and closed every three months.

l 15.10.2 Alternate Testing: Quarterly, perform a partial stroke test  ;

(OPEN) of each valve using system flow. At each refueling 1 outage, test the valves by partial disassembly, inspection

and manual stroking on a rotating basis (one valve per refueling).

ATTACHNENT 3 PAGE 37 0F 62

]

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 143 0F 173 1

'~

ATTACHMENT 1 l TCN/EC M i - ALTERNATE TESTING JUSTIFICATION'AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued)-

l t

15.10.3 During partial disassembly, the valves' internals will be j 1 visually inspected for worn or corroded parts, and the-  ?

l 4 valves' disk will be manually exercised. If it is found the full stroke capability of the disassembled valve is in question, the remaining valves in tho' group will be

similarly disassembled and inspected and manually full ,

' stroked during the same outage in the case of the valve in,  !

the unit undercoing refueling and at the very next refueling )

outage for tho' valves in the opposite unit. Following "

, reassembly, the valve will be tested by partial stroking

using system flow. l r .

15.10.4 These valves prevent back-flow from the High Pressure Safety

Injection Suction Header, Low Pressure Safety Injection Suction Header and Spray Pump Suction header to the

,. Refueling Water Storage Tanks (RWSTs).  ;

15.

10.5 INTRODUCTION

.1 The source of flow to these valves is borated water

from the RWSTs. Pumps that produce flow through these valves are the High pressure Safety Injection (HPSI), Low Pressure Safety Injection (LPSI) and Containment Spray pumps. They discharge into the Reactor Coolant System (Reactor Coolant System) or i containment building spray headers.

]

.2 These safety injection system check valves prevent

. post accident recirculation flow from escaping the normal flow path into the RWST. Plant conditions can '

be grouped into three test situations with respect the these valves: (1) Reactor Coolant System i Pressurized and at normal operating temperature, (2) Reactor Coolant System depressurized and cooled 4 down, and, (3) Reactor Coolant System open during refueling. These conditions are discussed below:

(1) REACTOR COOLANT SYSTEM PRESSURIZED AND AT NORMAL OPERATING TEMPERATURE l

These valves cannot be full-stroked using flow -

during power operation, for the following reasons: ,

l ATTACHMENT 3 PAGE 38 0F 62 l l

l I

- 1

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e NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5-UNITS 2 AND 3- REVISION 9 - PAGE 144 0F 173 ATTAC}9 TENT 3 p ~-

TCN/EC Q ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL-(Continued) 2 15.10.5.2(1) a.- The HPSI (shutoff head 1500 psi) and LPSI

l. (shutoff head 200 psi) pumps are unable to l

overcome Reactor Coolant System pressure (nominal operating pressure = 2000 psi). There is no full flow recirculation to the RWST from either pump.

i As a retnit, only pump recirculation through the

miniflow line is. produced using these pumps i while the Reactor Coolant System is pressurized.

Although this is sufficient for a partial stroke

. test, flow for a full-stroke test is not available. ,

b. A quarterly test at power, using the only i , available flow path, would either inject borated

water into the Reactor Coolant System or spray i down the containment building, or both. If injection were )ossible during operation, the test would not )e performed because the result i would be an immediate, uncontrolled and complete reactor shutdown (as a result of the borated water) and/or flooding and resultant degradation of the components and systems located in the <

3 containment building (as a result of the '

containment building spray down).

c. The containment spray pumps cannot be utilized

, to full-stroke these valves using flow, as the i only full flow path during plant operation is '

through the containment spray header and

, nozzles.

(2) REACTOR COOLANT SYSTEM DEPRESSURIZED AND COOLED DOWN These valves cannot be full-stroked using flow during

! cold shutdown for the following reasons:

i

. a. TESTING WITH ALL PUMPS IN A LOOP: Sufficient 4

flow to full-stroke the RWST outlet check valves

, is not achievable in this condition. Return

flow from the HPSI and LPSI pump discharge lines is very limited, consisting of mini-flow recirculation lines and Reactor Coolant Sistem vent lines.

ATTACHMENT 3 PAGE 39 0F 62

- - . - _ _ _ _ - - - - - - - - _ - - _ _ _ - - _ _ g

1 NUCLEAR ORGANIZATION  : ENGINEERING PROCEDURE S023-V-3.5

UNITS 2 AND 3 REVISION 9 PAGE 145 0F 173

, ATTACHNENT A y TCN/EC M ALTERNATETESTINGJUSTIFICATIUNANDBASISFOROTHERTHANOUARTERLYTESTINTERVAL (Continued) 15.10.5.2(2)' b. TESTING ~WITH THE CONTAINNENT SPRAY PUNP: The ,

containment Spray (CS) pumps have a 6" recirculation line to the RWSTs, but these pumps.

! by themselves cannot develop full-stroke flow for the RWST outlet check valves.

c. TESTING WITH THE LPSI PUNPS: Stroking the RWST ,

outlet check valves with flow from the LPSI. I pumps is prohibited by the Technical Specifications in Cold Shutdown because the LPSI pumps must be aligned to take suction from the  ;

Reactor Coolant System to provide shutdown

cooling during this mode of operation. The LPSI pumps cannot, therefore, take a suction through

the RWST outlet check valves.

d. TESTING WITH THE HPSI PUNPS: The equivalent of the combined Containment Spray, LPSI, and HPSI flow rate cannot be developed with the HPSI pump l i

alone. The HPSI pumps cannot be used to exercise these valves during cold shutdown because of the risk of exceeding cooldown rate limits. The borated water in the RWST is normally at an ambient temperature of = 65'F and the cooled down Reactor Coolant System is nominally c. -- 135'F.

e. CONCLUSION: The Code required testing of the I RWST outlet check valves while the plant is in  !

[ Cold Shutdown could only be performed after ,

t significant redesign of the system, such as the addition of an instrumented full flow test line.

f i

if l

f l

ATTACHNENT 3 PAGE 40 0F 62 i

i  ;

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE ;5023-V-3.5 UNITS 2'AND 3 REVISION 9 PAGE'146 0F 173 ATTACHMENT 3 C

TCN/EC QM ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL-

- (Continued) 15.IO.5.2(3) REACTOR COOLANT SYSTEM OPEN DURING REFUELING

, a.. FLOW PATH:

1

. The RWST outlet check valves are in the 24"-

. supply line to the suction headers of the HPSI,- .

i LPSI and Containment. Spray Pumps. To a full-stroke the RWST outlet check valves using L flow during' refueling with the Reactor Vessel head remov v would require that the system 2

achieve a 1 '

flow of approximately 6500 gpm 4 (full accident flow). There is one check valve- <

for each of the two trains of pumps. Full flow ,

J- from the RWST through the check valves of -

l interest-is only achieved with all of the pumps 1 , in one train running at the same time (one HPSI

pump, one LPSI pump and one Spray pump).-

.A large flow could be achieved in the refueling

mode during refueling cavity fill. The HPSI, ,

- LPSI and containment Spray pum>s-could take a h suction from the RWST and disciarge to the Reactor Coolant System. With the Reactor

Pressure Vessel head removed, flow would first

l. fill and then overflow the Reactor Pressure Vessel into the Refueling Cavity.

b. C00LDOWN LIMITS:

l

. The only discharge path that exists for this ' j L flow is into the core through the safety- '

injection headers to the cold legs and/or the 6"

! recirculation line from the Containment Spray j- ) ump discharge to the RWST (this 6" line alone 1as insufficient capacity for the full-stroke of

the RWST outlet check valves using flow). The ,

, borated water in the RWST is normally at an  !

ambient temperature of = 65'F and the Cooled i down Reactor Coolint System is nominally at 1

= 136'F.

Injection of the borated RWST water could result i in a cool-down rate in violation of the i i

Technical Specifications (see Figure 3.4-5, Reactor Coolant' System Maximum Allowable Cool-Down Rates) for the reactor vessel.

i i

ATTACHMENT 3 PAGE 41 0F 62 i-i

( .

g

- NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-30 5 UNITS'2 AND 3 REVISION 9~ PAGE 147 0F 173 i

~ATTACMENTj '

TrWEC M' ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN QUARTERLY TEST INTERVAL' l (Continued).

5

.15.

10.6 CONCLUSION

.1 From the above discussion, it-can be seen that no allowable flow path exists in any plant mode for a 4 full-stroke of the RWST outlet check valves using flow. Testing of these valves could only be accomplished after significant redesign of the system, such as installation of a fully instrumented full flow test loop. NRC Generic Letter 89-04, Attachment 1, Position 2, identifies partial

' disassembly and' inspection as an acceptable alternative for stroking a valve when it is

, impractical to use flow. In this case, there 1:s no.

! way to stroke these valves with the existing system 2

design using flow.

.2 Non-intrusive techniques have been considered.

However, because a flow path cannot be constructed

which will fully stroke the valves, there is no non-4 intrusive tet.hnique such as magnetics or acoustics that can be utilized to verify the valves achieve full stroke capability. Although it is conceivable radiography could be utilized to verify closure, the valve must be disassembled anyway to verify the open .

capability, and so there is no additional value in

- verifying closure through non-intrusive techniques.

15.'10.7 TEST SCHEDULE 4 .1 .To disassemble and inspect all four of these valves '

1 each refueling outage requires the associated piping i to be drained. This generates a significant o. mount a of liquid radioactive waste. In addition,

, considerable radiation exposure can be received by

personnel perfonning the partial disassembly, hand stroking and inspection. As a consequence, there is

a clear advantage in reducing the number of partial

disassembly and hand st,roking tests required in e

u.h refueling.

ATTACHMENT 3 PAGE 42 0F 62

4 4 ,

NUCLEAR ORGANIZATION. ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 148 0F 173 ATTACHMENT g y

.TCN/EC ,

ALTERNATE TESTING JUSTIFICATION AND' BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL l (Continued)  ;

j 15.10.7.2 This is an a > proved code exception in accordance with :

1 NRC Generic .etter 89-04,(GL 89-04), Attachment 1,.

]- Position 2, Alternative to full flow testing of check l valves. This section specifies for valves which 1

cannot be full flow tested, the NRC staff position is '

valve disassembly and inspection can be used as a

, positive means of determining whether a valve's disk l~ will full-stroke exercise open or of verifying i closure capability. If possible, partial valve stroking quarterly or during cold shutdowns, or after-re-assembly must be performed.

i

.3 OM-10, Paragraph 4.3.2 allows that a valve may be

disassembled as an alternative to full flow testing, s

, .4 GL 89-04, Position 2, allows development of staggered testing of like components by establishing an ,

inspection plan for similar groups of_ valves. '

i Disassembly and inspection is performed in accordance

with, and does not deviate from, OM-10, Para 4.3.2.4, and GL 89-04, Position 2.

15.13 $2(3)1204NU003, Outlet Check Valve - Containment Emergency Sump S2(3)1204NU004, Outlet Check Valve - Containment Emergency Sump 15.11.1 Test Requirement: . OM-10, Paragraph 4.3.2, exercise these valves every three months.

15.11.2 Alternate Testing: The valves will be partially disassembled, inspected and manually full stroked at each ,

refueling outage on a rotating basis (one valve per refueling). During partial disassembly, the valves' internals will be visually inspected for worn or corroded

l. parts, and the valves' disk will be manually exercised. If it is found that the full stroke capability of the disassembled valve is in question, the remaining valves in the group will be similarly disassembled and inspected and manually full stroked during the same outage in the case of i the valve in the unit undergoing refueling and at the very next refueling outage for the valves in the opposite unit. ,

1 15.11.3- A method of partial flow testing will be developed and used i following the partial disassembly and prior to returni,ng the l valve (s) to service.-

15.11.4 These valves open to 3rovide recirculation flow from the -

i containment sump to tte suction piping of the HPSI, LPSI and Containment Spray pumps.

ATTACHMENT 3 PAGE 43 0F 62 i

1

l '

! NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 149 0F 173 I

ATTACIMENT TCN/EC CI 3M i ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL

(Continued).

i 15.11.5~ Test Methodology-

.1 NORMAL PLANT OPERATION The only source of water to the inlet of the 1 cnntainment sump outlet check valves is the  !

containment building sump. During normal plant i o)eration this sump is required to be kept dry and.

3 tie isolation valves shut. This system lineup

precludes either full-stroke or partial stroke of

these check valves using flow in this mode.

.2 COLD SHUTDOWN AND REFUELING MODES t

.2.1 In cold shutdown or reactor refueling modes, part stroke exercising of these valves is possible with

. flow from the containment sump, however, the sump is

. not maintained at a cleanliness level consistent with i the internals of the Safety Injection or Reactor a Coolant system piping. The cleanup of the i' containment sump to a cleanliness level consistent

with the internals of the Safety Injection or Reactor Coolant system would be labor intensive.

.2.2 If part stroke exercising were conducted by filling the sump with water and flow testing these valves, this would potentially contaminate the safety injection systems, the refueling water storage tank, and/or the reactor coolant system with low quality

. water. This contamination of the systems would cause '

{ accelerated corrosion and degradation. Extensive flushing and cleanup following such testing would t therefore be required.

.3 CONCLUSION

.3.1 The Code required testing could only be performed after significant system modifications involving considerable costs. Tfiese system modifications would involve additional containment penetrations and long runs of large diameter piping with associated supports and isolation valves. NRC Generic-Letter 89-04. Attachment 1, Position 2, identifies par,tial disassembly and inspection as an acceptable alternative for stroking a valve when it is

impractical to use flow. In this case, there is no practical way to. full-stroke these check valves using flow with the existing system design.

ATTACHMENT 3 PAGE 44 0F 62 l

L i

iNUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS'2-AND 3- REVISION 9 PAGE 150 0F-173 .

,. ATTACHMENT 3 1 TCN/EC OIM

ALTERNATE TESTING JUSTIFICATION AND BASIS ~FOR OTHER THAN OUARTERLY TEST INTERVAL-(Continued)

I 15.11.5.3.2 Non-intrusive techniques have been considered.

However, because a flow path cannot be constructed which will fully stroke the valves, there is no non-

intrusive technique such as magnetics or acoustics l 1 that can be utilized to verify the valves achieve full stroke capability. Although it is conceivable radiography could be utilized to verify closure, the valve must be disassembled anyway to verify the open

. capability, and so there is no additional value in verifying closure through non-intrusive techniques.

.4 TEST SCHEDULE

.4.1 To disassemble and inspect all four of these valves each refueling outage requires the associated system.

.- piping to be drained. This~ generates a significant amount of liquid radioactive waste. In addition, considerable radiation exposure can be received by personnel performing the partial disassembly, hand i stroking and inspection. As a consequence, there is

. a clear advantage in reducing the number of these tests required in each refueling.

.4.2 This Alternate Testing is an approved Code exception in accordance with NRC Generic Letter 89-04 (GL

. 04), Attachment 1, Position 2,Alternativeto. full flow testing of check valves. This section specifies

. that valves which cannot be full flow tested the NRC

staff's position is

valve disassembly and inspection can be used as a positive means of determining a ,

valve's disk will full-stroke exercise open or of

verifying closure capability. If possible, partial 4 valve stroking quarterly or during cold shutdowns, or after re-assembly must be performed.

.4.3 OM-10, Paragraph 4.3.2 allows that a valve may be j disassembled as an alternative to full flow testing.

( .4.4 GL 89-04, Position 2, allows development of staggered

' testing of like components by establishing an inspection plan for similar groups of valves.

Disassembly and inspection is performed in accordance with, and does not reviate from, OM-10, Para 4.3.2.4, j and GL 89-04, Position 2.-

i 15.12.S2(3)1204MU006, HPSI Pumps 2 3 P017 and 2 3)P018 Suction Check Valve

$2(3)1204MU008.HPSIPumps23P018and23)P019SuctionCheckValve 15.12.1 Test Requirement: OH-10, Paragraph 4.3.2, exercise these

valves every three months.

ATTACEMENT 3 PAGE 45 0F 62

___.-_---.-l___-._-----_-_--__----_---.--.-------._-_.__-.-_ ----a- , ,.

A NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023-V-3.5 l UNITS 2 AND 3: REVISION 9 PAGE 151 0F 173- l ATTACHNENT @3 p

, TCN/EC.

l ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL ~ I

-(Continued) i F 15.12.2 Alternate Testing

These valves will be full stroke exercised at each refueling, while using the high pressure i safety injection pumps to fill the refueling pool canal, and part stroke exercised quarterly during routine inservice j testing of the HPSI pumps.-

15.12.3 These valves own to allow a flow of water into the ' suction

piping of the ligh pressure safety injection pumps.

15.12.4 These check valves cannot be full stroke exercised during power operations because the high pressure safety injection 4

pumps cannot overcome reactor coolant system )ressure.

During cold shutdown full stroke exercising tiese valves could result in a low temperature over-pressurization of the i reactor coolant system.

15.12.5 OM-10 Section 4.3.2.2, Exercising Requirements, paragraph (e) stipulates if exercising is not )racticable during plant operation or cold shutdowns, it may )e limited to full stroke during refueling outages.

. 15.13 52 1204NUO12, HPSI Pump 2 P017 Discharge check Valve,

$2 1204NUO15. HPSI Pump 2 P019 Discharge Check Valve, L $2 1204NU016. HPSI Pump 2 P018 Discharge Check Valve, and,

, $2 1204NU017. HPSI Pumps 2(3)P018 & 2(3)P019 to #2 High Pressure Header, 15.13.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months.

15.13.2 Alternate Testing: Test these valves at cold shutdown intervals.

15.13.3 These valves are in the flow path from HPSI directly to the RCS. The CVT0 cannot be performed during o)eration because

, shutoff head of the HPSI sump is less than (CS pressure.

Exercising the valves witi full accident flow requires

-875 gpm, which is not possible during plant operation.

~

There is no alternate flow path that will support the requisite flow rate during operation. l i'

l ATTACHMENT 3 PAGE 46 0F 62

k iNUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V'-3.5 UNITS 2 AND 3 REVISION 9 'PAGE 152 0F 173:

L ,

'ATTACHMENTg i TCN/EC i < ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL (Continued)

~

15.13.4 The EXERCISE CLOSED test is also done at cold ' shutdown -

3 intervals. Closure of these valves.is verified by measuring d leakage past the valves. OM-10, >aragraph 1.3 defines i exercising as "the demonstration )ased on direct visual or indirect positive indications that the moving parts of a valve function." -Since it is not possible to OPEN EXERCISE i

i test these valves at-a-quarterly interval, verifying the

! valves closed at a quarterly interval would not satisfy the

! code requirement to exercise the valves. Therefore, the interval for the CLOSEQ EXERCISE test is ' set at the same interval as the OPEN EXERCISE test. Performing the CLOSED tests at Cold Shutdown intervals by measuring leakage is consistent with NUREG-1482 (Reference 2.5.3) Section 4.1.4.

i

15.1452(3)1204NUO18.HPSICombinedHeadertoReactorCoolantSystemLoop i . IA Check Valve,

, $2(3)1204NU019.HPSICombinedHeadertoReactorCoolantSystemLoop 4

IB Check Valve, i $2(3)1204MUO20. HPSI Combined Header to Reactor Coolant System Loop i 2A Check Valve, and, i $2(3)1204NU021.HPSICombinedHeadertoReactorCoolantSystemLoop i; 2B Check Valve ,

15.14.1 Test Requirement

0H-10, Para. 4.3.2, test nominally every n three months.

15.14.2 Alternate Testing:- Test these valves at cold shutdown j intervals. i

15.14.3 These valves direct flow into the Reactor Coolant System , i

from the HPSI pumps.

! 15.14.4 Exercising these valves while the plant is at power would i result in non-compliance with Technical Specification i

. 3/4.5.2. In any event, during power operation there is no i t full flow path available to stroke test these valves. LPSI  !

or HPSI pumps cannot overcome the Reactor Coolant System l

pressure. .

J 15.14.5 Since the OPEN streke test can only be accomplished at cold shutdown intervals, the CLOSE stroke exercise test is the same interval. Without being able to open the valves, '

exercising, that is moving the obturator, cannot be , )

accomplished. )

l 1

l I

ATTACHMENT 3 PAGE 47 0F 62 i

NUCLEAR ORGANIZATION- ' ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 153 0F 173 ATTACHMENT 3 TCN/EC N ALTERNATE TESTING JUSTIFICATION'AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued) l I

f .

15.1552(3)1204MU024.LPSIPump2(3)P015DischargeStopCheckValve,and,-

, '52(3)1204NUO25. LPSI Pump 2(3)P016 Discharge Stop Check Valve 15.15.1 Test-Requirement: 0M-10, Para. 4.3.2, test nominally every three months. l 15.15.2 Alternate Testing: Test these-valves at cold shutdown.

intervals..

. 15.15.3 These valves are on the discharge of the LPSI pumps and a prevent backflow through an idle LPSI pump in the event the other pump is operating.

j 15.15.4 These valves are in the flow path from LPSI directly to the RCS. The CVT0 cannot be performed during operation because

.- shutoff head of the HPSI pump is less than RCS pressure.

Exercising the valves to the full open position requires 5000 - 5300 gpm, which is not available. There is no alternate flow path that will support the requisite flow  !

rate during operation.. l 15.15.5 The EXERCISE CLOSED test is also done at cold shutdown intervals. OM .10, paragraph 1.3 defines exercising as "the demonstration based on direct visual or indirect positive indications that the moving parts of a valve function."

Since it is not possible to OPEN EXERCISE test these valves j at a quarterly interval, verifying the valves closed at a j quarterly interval would not satisfy the code requirement to '

l exercise the valves. Therefore, the interval for the CLOSED EXERCISE test is set at the same interval as the OPEN '

j EXERCISE test. Performing the CLOSED tests at Cold Shutdown

. intervals by measuring leakage is consistent with NUREG-1482 (Reference 2.5.3)Section4.1.4.

l j

i 4

4 ATTACHMENT 3 PAGF. 48 0F 62

- - - . ~ - .- ,n

I NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE = S023-V-3.5 UNITS 2 AND 3 REVISION 9. PAGE 154 0F 173 ATTACHMENT 1 TCN/EC- N 4 l

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL

_(Continued) i 15.16 52(3)1204MU027 Safety Injection Headers to Reactor Coolant System s

Loop 1A, and, 52(3)12044RJ029,SafetyInjectionHeaderstoReactorCoolantSystem ,

s Loop 18, l

$2(3)1204NUO31,SafetyInjectionHeaderstoReactorCoolantSystem i Loop 2A, and.

l 52(3)1204MUO33,SafetyInjectionHeaderstoReactorCoolantSystem Loop 28 15.16.1 Test Requirement: OM-10, Para. 4.3.2, test nominally every-three months.

15.16.2 Alternate Testing

Test these valves at cold shutdown intervals.

]

i , 15.16.3 These valves direct flow into the Reactor Coolant System i from the LPSI and HPSI pumps.

j 15.16.4 During )ower operation there is no full flow path available

to stroce test these valves. LPSI or HPSI pumps cannot overcome the Reactor Coolant System pressure. Requires 2000 GPM for full Stroke.

. 15.17 $2 1204MUO34. HPSI 2 3)P017 Miniflow

S2 1204MUO35, HPSI 2 3)P019 Miniflow, i

S2 1204NUO36. HPSI 2 3)P018 Train "A" Miniflow,

, $2 1204NUO37, LPSI-Pump 2(3)P015 Miniflow Stop Check Valve, S2 1204NUO63, LPSI Pump 2(3)P016 Miniflow Stop Check Valve.

S2 1204MU104, HPSI 2(3)P018 Train'"B" Miniflow 15.17.1 Test Requirement: OH-10, Para. 4.3.2, test nominally overy i

three months.

15.17.2 Alternate Testing: Test these valves at refueling intervals, i 16.17.3 These stop-check valves direct miniflow recirculation from i

the HPSI, LPSI pumps back to the Refueling Water Storage

• Tanks.

15.17.4 Providing flow or pressure to verify completion of the closed stroke requires placing the miniflow line out of

, service for the HPSI, LPSI and Containment Spray Systems.

i These ) umps may run for a )rolonged time during a small break ;.0CA and rely upon tie miniflow for pump cooling. The pumps may be damaged if this cooling is not available.

, Thus, placing the miniflow line out of service renders those systems inoperable and is only practical in modes during which these systems are not required to be operable under the Technical Specifications.

ATTACHMENT 3 PAGE 49 0F 62 4

NUCLEAR ORGAN!ZATION' ENGINEERING PROCEDURE S023-V-3.5

. UNITS 2 AND 3 REVISION 9 PAGE 155 0F 173 ATTACHNENT-3  !

L TCN/EC Q/V i ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL g (Continued)

\

s . . .

l f 15.17.5 The only way to verify closure of the'se valves is to measure i leakage into a-test volume u> stream of the check valves

" using a hydro pump. The ela> orate valve line-up, test equipment required, and.high man-hours required to perform

. this test make it impractical to perform on a more frequent'

'. basis. Performing the CLOSE test of these valves in

!' conjunction with the LEAKAGE test at refueling intervals is consistent with NUREG-1482 (Reference'2.5.3) Section 4.1.4.

15.18 S2 1204W040 Safety injection Tank T008 Outlet Check Valve 52 1204NU041, Safety. Injection Tank T007 Outlet Check Valve 52 1204NUO42, Safety Injection Tank T009 Outlet Check Valve i 52 1204NUO43 Safety Injection Tank T010 Outlet Check Valve 15.18.1 Test Requirement: ON-10, Paragraph 4.3.2, exercise these p .- .; -valves every three months, i

j 15.18.2 Alternate Testing: These valves will have stroke capability verified using non-intrusive (NI) testing at each refueling

outage on a rotating basis in accordance with NUREG-1482 (Reference'2.5.3, Section 4.1.2). This test utilizes a dump of the SITS to achieve the flow necessary to full stroke the

, valves, and magnetic and acoustic sensors to verify full l' open stroke of the obturator. This testing is done during

j. filling'of the refueling cavity. If the NI testing does not  ;

provide adequate results, alternative techniques, including l

! a determination of the "K-value" of the system, and/or a t calculation of flow velocity through the valves calculated ,

using changing tank levels, will be utilized to determine a l successful stroke. The justification required for these , )

j- alternative techniques (if necessary) is provided in  !

! Nemorandum for File by P. Schofield, dated 3/31/95, subject: l

! Justification of Alternate Testing of SIT Discharge Check Valves. If the alternative techniques are also unsuccessful, disassembly and hand-stroking will be l performed in accordance with Generic Letter 89-04 (Reference 2.1.9).

15.18.3 Full closure of the valves is' ensured by leak testing the valves to the limits specified in Technical i Specification 4.4.5.2.2 after they have been exercised but

prior,to Mode 2.

i ATTACHNENT 3 PAGE 50 0F 62 4

k.

I

. _ _ _ _ _ _ _ . _ _ _ _ _ _ - . _ _ _ _ _ . _ . _ _ _ _ . _ _ . _ - , . __ - =-, , . - w w

' NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 i UNITS 2 AND 3 REVISION 9 PAGE 156 0F 173 l ATTACHMENT 3 L

TCN/EC ON i

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL

.(Continued) l 15.18.4 These valves open to ' allow a flow of water from the Safety Injection Tanks into the Safety Injection Header. of each Primary loop. Opening these valves during ' power. operation is not possible against normal Reactor. Coolant System operating pressure.. OM-10 Section 4.3.2.2(d) stipulates,

. "If exercising is not practicable during plant operation and full-stroke during cold shutdowns is also not )racticable, it may be limited to part stroke during cold slutdowns, and

full-stroke during refueling outages."

L -15.19 $2 1204NU072, LPSI Check Valve to Reactor Coolant System Loop 1A,

! - 52 1204NUD73, LPSI Check Valve to Reactor Coolant System Loop 18, L $2 1204NU074,'LPSI Check Valve to Reactor Coolant System Loop 2A, and, i 52(3)1204NU075, LPSI Check Valve to Reactor Coolant System Loop 28 15.19.1 Test Requirement: OM-10, Para. 4.3.2, test nominally every j three months.

l 15.19.2 Alternate Testing: Test these valves at cold shutdown intervals.

15.19.3 These check valves direct LPSI flow into the Reactor Coolant 4 System whenever the Reactor Coolant System pressure drops l~' below LPSI pump discharge pressure. There is no flow path to exercise these valves during power operation. LPSI ) umps cannot overcome Reactor Coolant System Pressure while t1e plant is at power.

i 15.20 $2 1204NUO77, LPSI Pump 2 P016 Suction Header Check Valve ,

S2 1204NUO84, LPSI Pump 2 P015 Suction Check Valve ,

S2 1204NU199, LPSI Pump 2 P016 Suction Header Check Valve l S2 1204NU201, LPSI Pump 2 P015 Suction Header Check Valve  ;

]

15.20.1 Test Requirement: OH-10, Paragraph 4.3.2, exercise these i j valves every three months, i 15.20.2 Alternate Testing: Quarterly, part-stroke exercise these t

valves. Full stroke exercise using flow at reactor refueling intervals.

15.20.3 A flow path exists during the filling of the refueling canal ,

1

.with the LPSI pumps in plant Mode 6 (refueling). The I suction of the LPSI pumps can be aligned to the RWST a,nd the discharge to the LPSI header or shutdown cooling header.

j Flow could then be directed through~the LPSI Suction Header j- Check Valves at full flow (LPSI Pump Design Flow is 4150 gpm at 400 psid) for a short period of time sufficient to

, full-stroke those valves with flow.

l- ATTACHMENT 3 PAGE 51 0F 62

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NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 157 0F 173 ATTACHMENT-1 p

[ TCN/EC W

< ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL-(Continued)

, 15.20.4 These valves open to allow a flow of water from the i refueling water storage tank (RWST) into the suction piping of the Low Pressure Safety Injection (LPSI) pumps.

15.20.5 The refueling interval for the Check Valve Stroke Test closed is required due the impracticability of erecting scaffolding and handling the heavy radiography apparatus in

the vicinity of the Safety Injection equipment.. The radiography is performed at refueling intervals on a rotatingbasisconsistentwithNUREG-1482(Reference 2.5.3) 4 Section 4.1.2.

i 15.20.6 0URING POWER OPERATION i .1 Full-stroke exercising of the LPSI pump suction check

. , valves with flow requires the passage of the maximum

required accident flow rate through the valves. The LPSI suction checks are in the suction lines of the associated LPSI pumps and deliver borated water to these pumps from the RWSTs. The pumps in turn discharge to the Reactor Coolant System, Shutdown Cooling heat exchanger ~ and the mini-flow i recirculation lines (returning the flow to the

. RWSTs).

! .2 These valves cannot be full-stroke exercised using

flow during power operation, for the following

! reasons:

a. The mini-flow recirculation lines cannot provide ,

! enough flow through the LPSI pump suction check e valves, as the maximum flow achievable through this path is less than required accident flow.

i Although this is sufficient for a partial stroke

} test, flow for a full-stroke is not available.

b. During power operation, the Shutdown Cooling System is isolated and cannot be used as a flow path because it mtist remain isolated due to

! interlocks controlled by Technical Specification 3.4.5.2.d.

4 ATTACHMENT 3 PAGE 52 0F 62

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5-F -UNITS 2 AND 3i - REVISION 9- PAGE 158.0F 173 ATTACMENT 3 TCN/EC- 4'I ALTERNATE TESTING JUSTIFICATION AM) BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL

{ _

.(Continued) p' ' 15.20.6.2.. c. Injecting water into the Reactor Coolant System during power operation is not possible. - The Low .

Pressure Safety Injection (LPSI) pumps (shutoff

[;

head = 200 psi) are unable to overcome Reactor Coolant System pressure (nominal operating

- pressure = 2000 psi) and therefore there can be a no flow into the Reactor Coolant System in this

plant mode.- If a test at power could be ' <

conducted, it would result in injection of borated water into the Reactor Coolant System.

1' The result'would~be an imediate, uncontrolled and complete reactor shutdown (as a result of

. the borated water).

15.20.7 COLD SHUTDOWN 4 .1 The Technical Specifications require the LPSI pumps remain aligned to provide shutdown cooling at all j times while the plant is in Cold Shutdown. The LPSI suction check valves are, accordingly, bypassed and cannot~ be full-stroke tested using flow. - Compliance with the Code requirement to perform quarterly

testing could only be accomplished after a major modification of the system design. The improvement of the testing in cold shutdown would not justify the high costs involved.

.2 ON-10 Section 4.3.2.2(d) stipulates, "If exercising is not practicable during plant operation and

. full-stroke during cold shutdowns is also not '

i practicable, it may be limited to part stroke during l- cold shutdowns, and full-stroke during refueling l outages."

! .3 We meet this requirement by performing a partial

stroke quarterly during operation and a full stroke during refueling outages.

! NOTE: There is not a clear fit in the code for

this condition. Section 4.3.2.2(d) allows for a partial stroke during cold shutdown, 4' but not a quarterly stroke during

. operation. By doing the stroke quar'terly F we exceed the requirement of the code.

9 ATTACHMENT 3 PAGE 53 0F 62 e

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5'  ! l UNITS 2 ANO 3 REVISION 9 PAGE 159 0F 173'

' ATTACittENT J TCN/EC - 4 N ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTFIR THAN OUARTERLY TEST INTERVAL (Continued) 15.2152(3)1204MUO87,SprayPump2(3)P013SuctionCheckValve,and, l 52(3)1204MUO88, Spray Pump 2(3)P012 Suction Check Valve 15.21.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every ,

three months.

15.21.2 Alternate Testing: Test these valves at cold shutdown i

. interval s. i 5

15.21.3 These valves are in the flow path of the Containment Spray Pumps.

'15.21.4 No flow path exists to exercise ihese valves to the open ,

position during plant operation without removing both trains i of Containment Spray and LPSI from service.

i 15.22$2(3)1204MU152,To#2HPSIHeader 15.22.1 Test Requirement: 0M-10, Para. 4.3.2, test nominally every three months. j j 15.22.2 Alternate Testing: -Test this valve at cold shutdown intervals.

15.22.3 This valve directs the flow from #2 HPSI header into the Reactor Coolant System hot leg.

I 15.22.4 Valve cannot be stroked at power because the HPSI pumps 4 - cannot overcome Reactor Coolant System Pressure.

Additionally, opening the HPSI Header Isolation valve during '

power operation would result in non-compliance with Technical Specification 3/4.5.2.

15.23 $2(3)1204NU155. HPSI Header #1 to Reactor Coolant System Loop 2 Hot Leg, 52(3)1204MU156, HPSI Header #1 to Reactor Coolant System Loop 2 Hot Leg Inlet Check Valve, 52(3)1204MU157, HPSI Header #2 to Reactor Coolant System Loop 1 Hot Leg, and, j $2(3)1204MU158. HPSI Header #1 to Reactor Coolant System Loop 2 Hot Leg 15.23.1 Test Requiremente OM-10, Para. 4.3.2, test nominally 'every throe months.

15.23.2 Alternate Testing: Test these valves at cold shutdown intervals.

ATTACHMENT 3 PAGE 54 0F 62 i

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NUCLEAR ORGANIZATION ENGINEERING' PROCEDURE S023-V-305' PAGE 160 0F 173

' UNITS 2 AND 3 REVISION 9 1 ATTACMENT -3 i TCN/EC oY v

ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL l (Continued)

15.23.3 'These valves direct flow from the discharge of the HPSI headers into the Reactor Coolant System Hot legs.

1 e

15.23.4 Full or_ partial stroke exercising of these valves while the ' l plant is at power would result in non-compliance with

Technical Specification 3/4.5.2. In addition, while the )

4 plant is at power, HPSI pumps cannot overcome Reactor Coolant System pressure, j j 16.0 STEAM ,

16.1 2(3)HV8200. Steam from Steam Generator'E089 to AFW Pump 2(3)P140, i 2(3)HV8201,steamfromSteamGeneratorE088toAFWPump2(3)P140 16.1.1 Test Requirement: Exercise quarterly in accordance with ,

, OM-10.  !

16.1.2 Alternate Testing: Manual stroke (partial) at cold shutdown i in addition to normal testing. l 1

i 16.1.3 These valves isolate the main steam leads coming out of the '

l containment from the steam generators and going to the steam driven AFPs.

16.1.4 The manual stroke is a non-Code required test and a cold shutdown interval has been judged as adequate to show the valves can be manually actuated if necessary in accordance with the E0!s.

16.2 2 3 HV8204, Steam Generator E089 Main Steam Isolation Valve '

2 3 HV8205, Steam Generator E088 Main Steam Isolation Valve

16.2.1 Test Requirement

OM-10, Paragraph 4.2.1: Full stroke exercise close at cold shutdown. Part stroke close quarterly 1 when full stroke testing is impractical.

16.2.2 Alternate Testing: Perform a full stroke close test at cold i shutdown. (Note: Stroke time is governed by Technical Specification 4.7.1.5).

i 16.2.3 These valves isolate the main steam leads coming out of the containment from the steam generators and going into the ,

steam plant.  :

i 16.2.4 Close on Main Steam Isolation Signal (MSIS).

ATTACHMENT 3 PAGE 55 0F 62 I 1

g NUCt. EAR ORGAN'IZATION ENGINEERING PROCEDURE- S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 161 0F 173 ATTACF# LENT TCN/EC g

' ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL p (Continued);

.16.2.5 Full stroke exercising at full plant power would'cause a loss of 50% of heat removal from the primary coolant system, a reactor trip on. asymmetric power in the core and actuation of the steam and pressurizer (primary) reliefs.

.16.2.6 The MSIVs must be open during power operation. Closure of i one or both of the MSIVs during power operation will result in a reactor trip. A partial stroke test could result in an i

inadvertent closure of an MSIV and a reactor trip..

u .

l 16.2.7 SCE 2erformed a Probabilistic Risk Assessment (PRE 1-91-22)

of tie partial stroke test of the MSIVs and determined the risk to the health and safety of the public is reduced by

approximately an order of magnitude by eliminating the i quarterly partial stroke test of the MSIVs during power 1-

, operation. The calculated offsite dose impact from i inadvertent closure of an MSIV during the partial stroke j testing is estimated to be 0.5 man-rem per. year. The calculated offsite dose from failure of an MSIV to close i during an accident due to eliminating the partial stroke testing is estimated to be 0.045 to 0.075 man-rem per year,

~

i: As a result, the aart stroke test during power operation is not performed. Tils 'is consistent with NUREG-1482 i .(Reference 2.5.3)'Section 4.2.4.

3~ 16.3.2(3)HV8419,MainSteamDumptoAtmosphere.and, 2(3)HV8421, Main Steam Dump to Atmosphere 16.3.1 Test Requirement: OH-10, Para. 4.2.1.1, test nominally every three months. ,

16.3.2 Alternate Testing: Test these valves at cold shutdown

! intervals, except for manual tests, which are done at refueling intervals.

16.3.3 These valves open to relieve main steam pressure in the main steam leads coming out of the containment at a pressure below the main steam relief valves. They therefore prevent the i necessity for actuating the mafn steam relief valves. Full

stroke exercising of these valves during power operation could result in a reactor plant transient due to energy released via the steam dump.

[ .

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ATTACHMENT 3 PAGE 56 0F 62

. NUCLEAR' ORGANIZATION ~EhGINEERING PROCEDURE .S023-V-3.5 UNITS 2 AND 3 . REVISION 9 PAGE 162 0F 173 l

• ATTACHMENTJ TCN/EC: WY ' l ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL l (Continued) 16.3.4 NORMAL' SYSTEM LINEUP f.

.1 The ADVs are rarely opened during power operation and are only.used during plant heat up and cool downs when the 1- ' condenser is not available. Therefore, the valves are normally-in their NSIS actuated position, and there is.

generally no need to perform a full closed stroke test of-the ADVs.

l e

16.3.5 QUARTERLY FULL STROKE .

I .1 Fully opening an ADV without-isolation of the steam flow

, path at power risks plant upset and trip as this allows a large steam release, approximately 5% of 3410 MW thermal, and a resultant 4

. tripped closed. pressure transient when the ADV isThe pressure tra i- Reactor Coolant System temperature excursions which could d

cause an Engineered Safety Feature (ESF) initiation with the associated reactor trip.

l-

.2 There is a maintenance block valve upstream of the ADV.

This valve could be closed to block steam flow to allow '

l the ADV to be fully opened for test without releasing ,

! steam. However, an isolated ADV is unavailable to perform its function with the block valve closed

necessitating entry into the action requirements of

Technical Specification 3.7.1.6 and aggravating the

unavailability of the ADVs from a plant reliability point

!< of view.

16.3.6 PARTIAL STROKE TESTING WITH PRESSURE APPLIED

.1 A partial stroke of the ADV can be performed, while the ADV is experiencing full system pressure, by opening the i valve to approximately 25%. The ADVs are designed with l- integral pilot valves which assist in opening the ADV 4 when it is under )ressure. The pilot valve equalizes

. pressure across tie ADV (partially) during the open

! stroke.

.2 Partial stroke exercising with main steam pressure l applied followed by closing the ADV in a'similar manner as would an MSIS actuation, demonstrates the ADV and its pilot valve's ability to open and close under actual i 'eaerating conditions.

ATTACMENT 3 PAGE 57 0F 62 t

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NUCLEAR ORGANIZATION . ENGINEERING PROCEDURE S023-V-3.5 .1 l ' UNITS 2 AND 3. REVISION 9 PAGE 163'0F 173 l ATTACHMENT 3 l WY-TCN/EC

, ALTIRMAIE IESTING JUSTIFICATION AND BASIS FOR OTHER THAN'00ARTERLY TEST INTERVAL (Continued)

. i 16.

3.7 CONCLUSION

.1 This proposed alternative testing method would be

' analogous to actual design conditions for ADV operation and can be performed with minimal impact to plant operations. The pilot valve stroke length is the first 3 5% of the stem travel. This fully exercises the pilot

[ valve and piston ring, and partially exercises the main plug.

.2 The pilot valve serves no function when the ADV is not under system pressure. The depressurized stroke test.is an artificiality that does not demonstrate the ability of

the ADV to function under design conditions.

! , 16.3.8 The manual strokes are done at refueling intervals.

Technical Specification 4.7.1.6.1.d requires verifying local

manual operation will fully open and close each ADV at least.

! once per refueling outage.

-16.4 2(3)PCV8463, ADV HV841g Nitrogen Accumulator Pressure Control Valve 2(3)PCV8465, ADV HV8421 Nitrogen Accumulator Pressure Control

-Valve i

16.4.1 Test Requirement: OH-10, Para. 4.2.1.1, test nominally every

three months.

16.4.2 Alternate Testing: ' Test at cold shutdown intervals in F conjunction with the. testing of the associated ADV. ,

i:

16.4.3 These valves open to maintain pressure in their respective i ADV actuator nitrogen supply header upon loss of instrument air. These valves are normally closed since the downstream

air pressure is maintained above 100 psig and the regulator

! valve is set at 80 psig. Nitrogen backup is required for rmall break LOCA when manual operation of the ADV is not 4 possible. These valves are destigned to fail open.

4 16.4.4 These valves are not Code valves, however, they have been included in the IST program to assure functionality. See General Note #5 in Attachment 2. The analysis in Reference 2.1.1 requires only certain tests for these valves. g The stroke time of these control valves verifies the open stroke. These valves are open stroked during IST of the ADVs i at cold shutdown intervals. Therefore the practical test frequency is cold shutdown in conjunction with the ADV IST.

ATTACHMENT 3 PAGE 58 0F 62-

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NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE 5023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 164 0F 173 ATTACMENT 1 TCN/EC WY t ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN'00ARTERLY TEST INTERVAL (Continued) 4 16.5 S2(3)1301NU1264. HV8419 Equalizing Ball Valve 52(3)1301NU1266 HV8421 Equalizing Ball Valve 16.5.1 Test Requirement: ON-10, Para. 4.2.1.1, test nominally every

three months.

J-16.5.2 Alternate Testing: Test these valves at cold shutdown

intervals.

I 16.5.3 These valves are normally closed and are opened to equalize

, the pneumatic pressure across the valve actuator to permit manual operation of the atmospheric dump valve. If these

- valves remain closed, actuator pressure would not be j' equalized, and manual operation would be difficult. This j could delay manual operation of the ADVs. Local manual i .. operation of the ADV is used when the ADV cannot be operated from the Control Room during: a steam generator tube rupture; main steam line break outside containment; feed water line break; fire and control room evacuation.

! 16.5.4 These valves are not Code valves, however, they have been included in the IST program to assure functionality. See General Note #5 in Attachment 2. MU1264 and MU1265 are open

, and closed stroked during IST of the associated ADV at cold shutdown intervals. In order to stroke the valve closed, the associated ADV must be declared inoperable because normal

- control air must be isolated. Therefore the practical test

frequency is cold shutdown in con. junction with the ADV IST.

F The response to Question 53 in Reference 2.5.2 is followed l for guidance in these cases. ,

, 16.6 S2(3)1301NUO21. HV8421 Nitrogen Supply Isolation Valve S2(3)1301NU1328, MV8419, Nitrogen Supply Isolation Valve 16.6.1 Test Requirement: OM-10, Para. 4.2.1.1, test nominally every three months.

16.6.2 Alternate Testing: Test these , valves at cold shutdown intervals.

4 4

i r

i

> ATTACHMENT 3 PAGE 59 0F 62 l

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' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3. REVISION 9, lPAGE-165 0F 173=

ATTACHNENT g.

TCN/EC

. ALTERNATE TESTING JUSTIFICATION'AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL F (Continued) i 16.6.3 These valves are maintained in the open position to provide a

source of nitrogen to the ADV -in case there is a loss of instrument air. NU1328 and NUO21 are required to be closed 3

to isolate nitrogen supply to the ADV actuators during manual operation of the ADVs. Manual operation of the ADV is required if the ADV cannot be operated from the control room

during:. steam generator tube rupture, main steam line break

' outside containment, feed water line break, fire and. control i room evacuation. These valves are also closed to crosstle f nitrogen accumulators if one ADV is inoperable or only one

ADV is to be used. No credit:Is taken for closure during an

accident. These valves are opened and closed during IST of ADV-at cold shutdown intervals when the ADVs are stroked open manually.

! . 16.6.4 The ADV'is inoperable when the backup nitrogen source is

isolated. NU1328 and NUO21 are not Code valves; however, j they have been included in the IST program to ensure i

functionality. . See General Note #5 in Attachment 2. These L valves are opened and closed during IST of the associated ADVs at cold shutdown intervals. Therefore the practical

test frequency is cold' shutdown in conjunction with the ADV.

IST. H 16.7 S2(3)1301NU003, Steam Supply - S/G E088 to AFP Turbine K007 Check

Valve S2(3)1301NU006, Steam Supply - S/G E089 to AFP Turbine K007 Check Valve

16.7.1 Test Requirement

ON-10, Paragraph 4.3.2, exercise the ,

valves every three months.

L J

• 16.7.2 Alternate Testing: Quarterly, perform a partial stroke test (open) of each valve using system flow. At each refueling outage, test the valves by partial disassembly, inspection

[

and manual stroking.

l 16.7.3 During partial disassembly the valves' internals will be j visually inspected for worn or corroded parts, and the valves' disks shall be manually exercised. Following 1 reassembly and prior to return to service, the valves will be tested by partial stroking using system flow.

1 ATTACHMENT 3 PAGE 60 0F 62 i

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I I  : NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 I

-PAGE 166 0F 173

UNITS 2 AND 3.- REVISION 9 .

ATTAClelENT 3

TCN/EC 4M-

! ALTERNATE TESTING JUSTIFICATION AND BASIS FOR OTHER THAN OUARTERLY TEST INTERVAL-(Continued)

~

16.7.4 The use of non-intrusive test techniques are being pursued, i

with some success, on these valves. Successful acoustic and magnetic. traces have been obtained to verify both open and closure of these valves. Nevertheless, we conduct disassembly and inspection every outage because of past

problems with these valves.. If it is determined that disassembly and inspection is no longer required, the non-

, intrusive techniques may be implemented.

2.

16.7.5 These valves are in the, main steam supply to the

- turbine-driven auxiliary feedwater pump. In the event of a

+

main steam line break, these valves close to isolate the 3

opposite steam generator.

I- 16.7.6 DURING PLANT OPERATION

.1 During normal plant operation, main steam pressure tends to open these valves. No )ressure source exists to reverse this pressure in tie steam line where these valves are located and allow detection of valve closure l or valve leakage. Consequently, with the present system design, verifying the closure of the AFP Steam' Supply check valves by leak testing or with reverse flow, while the plant is operating, is not practical. Although a

' temporary external pressure source could be connected to the down-stream piping and apply reverse pressure to these check valves, the required valve lineup would cause the associated auxiliary feedwater pump to be inoperable

during the test. ,

16.7.7 DURING COLD SHUTDOWN OR REFUELING MODES  :

. l l .1 Regardless of plant mode, there is no positive means of

verifying that the valve disc travels to the closed L position, with the possible exception of non-intrusive testing technicues. System connections, such as vents and drains (anc appropriate line isolation valves) are

not present in the system to allow verification of the

1 existence of a pressure differential across the AFP Steam i Supply check valves when they are in the closed position.

e E

ATTACHMENT 3 PAGE 61 0F 62 i

- NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE- 5023-V-3.5

UNITS 2 AND 3 ' REVISION 9 PAGE 167 0F 173 'j ATTACHNENT J

.TCN/EC  :

ALTERNATE TESTING ~ JUSTIFICATION AND BASIS FOR OTHER THAN 00ARTERLY TEST INTERVAL (Continued)-

, 16.

7.8 CONCLUSION

.1- ON-10 and NRC Generic Letter 89-04, Attachment 1, l

Position 2, identifies partial disassembly and inspection i as an acceptable alternative for stroking a valve when it i is impractical to use flow. With'the >ossible exception of non-intrusive testing techniques, t1ere'is no way to test-these check valves closed with the existing system l- design using reverse flow or pressure. ' Testing of these valves could only be accomplished after significant redesign of the system, such as installation of 1 additional isolation valves and appropriate vents'and .

drains in the high pressure steam piping. The high costs of the necessary design changes involved would not be

, justified by the improvement of the valve testing. i

, Further,.the addition of valves, supports and necessary  !

pi ing modifications could result in reduced plant re iability.

16.7.9 TEST SCHEDULE l .1 ON 10, Section 4.3.2.2, Exercising, Requirements, Paragraph (e) stipulates if exercising is not practicable during plant operations or cold shutdowns, it may be limited to full stroke during refueling outages.

.2 Section4.3.2.4(c),ValveObturatorMovement,further l states, "As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to verify

. operability of check valves may be used." ,

.3 Disassembly and inspection is performed in accordance r

with, and does not deviate from, ON-10, Para 4.3.2.4, and j GL 89-04, Position 2. I i

I E

9

23V35T92.W51 ATTACHNENT 3 PAGE 62 0F 62 L

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h NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 168 0F 173 ATTACHNENT i 9M I

TCN/EC STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED TO STROKE AT OTHER THAN THEIR SAFETY ANALYSIS LIMITS See Note 3.in Attachment 2- to this procedure - Valves with protected stroke I times are: )

Safety Analysis Valve Stroke Limit in Seconds 2(3)HV0508 BTC 40 2(3)HV0509 BTC 40 2(3)HV0510 BTC 40 )

2(3)HV0511 BTC 40 2(3)HV0512 BTC 40 2(3)HV0513 BTC 40 2(3)HV0514 BTC 40 2(3)HV0515 BTC 40 2(3)HV0516 BTC 40 2(3)HV0517 BTC 40 2(3)HV1105 BTC 10 2(3)HV1106 BTC 10  ;

2(3)HV4047 BTC 10 2(3)HV4048 BTC 10  ;

2(3)HV4051 BTC 10 2(3)HV4052 BTC 10  ;

2(3)HV4053 BTC 20 . I 1

2(3)HV4054 BTC 20 2(3)HV4057 BTC 20 2(3)HV4058 BTC 20 2(3)HV4705 BTC 40 i

BT0 41.5 2(3)HV4706 BTC 40  !

BTO 41.5 l 2(3)HV4712 BTC 40 l BTO 41.5 l 2(3)HV4713 BTC 40 BT0 41.5 l 2(3)HY4714 BTC 40 BT0 41.5 ATTACHNENT 4 PAGE 1 0F 5

~ NUCLEAR'0RGAN!2ATION- ' ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3' REVISION 9- PAGE 169 0F 173 ATTACMENT i y' l TCN/EC M JJ.fl0KE TIME ACCEPTANCE CRITERIA FOR VALVES RE0VIRED TO STROKE AT OTHER THAN~

THEIR SAFETY ANALYSIS LIMITS

] (Continued) 1 Safety Analysis.  !

. Valve Stroke Limit in Seconds j

'2(3)HV4715- BTC 33.5  !

BTO 35- 1 2(3)HV4716 BTC :1.4 ,

BT0 20 l 4 BTC 33.5  !

2(3)HV4730

- BTO 35 2(3)HV4731 .BTC 40 BT0 "41.5

. 2(3)HV4762 BTC 40 2(3)HV4763 BTC '40 2(3)HV5388 BTC 40 2(3)HV5434 BTC 40

2(3)HV5437 BTC 40 2(3)HV5686 BTC 40 2(3)HV5803 BTC 40 2(3)HV5804 BTC 40 2(3)HV6200 BT0 20 j 2(3)HV6201 BTO 20 l 2(3)HV6202 BT0 20 2(3)HV6203 BT0 20

, 2(3)HV6211 BTC ;40 2(3)HV6212 BTC 19.7 sec.0) g 2(3)HV6213 BTC 19.7 sec.U) 2(3)HV6216 BTC 19.7 sec.N

2(3)HV6218 BTC - 19.7 2(3)HV6219 BTC 19.7 sec.N 2(3)HV6223 BTC 40 l 2(3)HV6236 'BTC 40 ,

2(3)HV6366 BTO 12 2(3)HV6367 BTO . 12 2(3)HV6358 BT0 12 I

1 ATTACHMENT 4 PACE 2 0F 5

' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 170 0F 173

, ATTACHMENT

TCN/EC' STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED TO, STROKE AT OTHER THAN

THEIR SAFETY ANALYSIS LIMITS

.(Continued) i

Safety Analysis; Valve Stroke Limit in Seconds i 2(3)HV6369. BTO 12 i 2(3)HV6370 BTO 12-2(3)HV6371 BTO 12 BT0 12

{ 2(3)HV6372 i- '2(3)HV6373- BTO 12 2(3)HV6500 BTO 12

.2(3)HV6501 BTO 12 1

2(3)HV6569.- BTO 5

.- 2(3)HV6570 BTO 5

) 2(3)HV7258 BTC 40 2(3)HV7259- BTC 40

]. 2(3)HV7512 BTC. 40

2(3)HV7513 BTC- 40 2(3)HV7800 BTC 1 2(3)HV7801 BTC 1 2(3)HV7802 BTC 1 t  ?(3)HV7803 BTC 1 2(3)HV7805 BTC  ?

2(3)HV7806 BTC 1

! 2(3)HV7810 BTC 1 2(3)HV7811 BTC 1

[

2(3)HV7816 BTC 1

2(3)l'il911 BTC 40 2(3)Hve.; 00. BT0 20 2(3)HW'.01 BTO 20 2(3)HV8202 BTC 40

2(3)HV8203 BTC 40 .

2(3)HV8204 BTC 8

. '2(3)HV8205 BTC 8 2(3)HV8419 BTC 20

ATTACHMENT 4 PAGE 3 0F 5

~ e e

IE NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023-V-3.5-L . UNITS 2.AND 3 REVISION 9 PAGE 171 0F.173-L ATTAC} MENT TCN/EC L

i ' STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED TO STROKE AT OTHER THAN

, THEIR SAFETY ANALYSIS LIMITS p' (Continued)

Safety Analysis j Valve Stroke Limit.in Seconds 2(3)HV8421 BTC 20 -

I 2(3)HV9205 BTC 40 2(3)HV9217 .BTC 40

"- BTC 40 2(3)HV9218 2(3)HV9302 BT0 , 39.5

'2(3)HV9303 BTO 39.5 2(3)HV9304 BTO 39.5

. 2(3)HV9305 BTO 39.5

! 2.- 2(3)HV9306 BTC 40 i

2(3)HV9307 BTC 40 I

2(3)HV9322 BTO 30 2(3)HV9323 BT0 20 2(3)HV9324 BTO 20 2(3)HV9325 BTO 30 2(3)HV9326 BTO 20 2(3)HV9327 BTO 20 2(3)HV9328 BT0 30 2(3)HV9329 BTO 20 2(3)HV9330 BT0 20 2(3)HV9331 BT0 30 2(3)HV9332 BT0 20 2(3)HV9333 BTO 20 2(3)HV9334. BTC 40 2(3)HV9341 BTC 10 '

2(3)HV9347 BTC 40 2(3)HV9348 BTC 40 2(3)HV9351 BTC 10- .

2(3)HV9361 BTC- 10 2(3)HV9367 BTO 12 2(3)HV93.68 BTO 12 ATTACHMENT 4 PAGE 4 0F 5

i NUCLEAR ORGANIZATION , ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 9 PAGE 172 0F 173 ATTACHMENT i t ' i TCN/EC M'r  !

STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED TO STROKE AT OTHER THAN THEIR SAFETY ANALYSIS LIMITS i (Continued)  !

Safety Analysis Valve Stroke Limit in Seconds 2(3)HV9371 BTC 10

2(3)HV9433 BTC 10  !

i 2(3)HV9437 BTC 10 2(3)HV9821 BTC 5

. 2(3)HV9823 BTC ,

5 2(3)HV9824 BTC 5 2(3)HV9825 BTC 5

[ 2(3)HV9900 BTC 40

.- i 2(3)HV9920 BTC 40 2(3)HV9921 BTC 40 i

2(3)HV9948 BTC 12 2(3)HV9949 BTC 12

, 2(3)HV9950 BTC 12 4

2(3)HV9951 BTC 12 '

2(3)HV9971 BTC 40

]_

2(3)TV9267 BTC 40 NOTES: NSee NCR G-0852.

l i

?- \

\

i 23V35T92'.W51 ATTACHMENT 4 PAGE 5 0F 5 l

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-Y-3.5 UNITS 2 AND 3 REVISION 9 PAGE 173 0F 173 l ATTACHMENTJi l TCN/EC M& l ACCEPTANCE LIMIT CNANGE RECORD INSERVICE TESTICG PROGRAM FOR VALVES NOTES:

a. Use this Attachment to document a change in the acceptance criterion from the established value for any inservice test on a valve in this IST Program.

b. More than one limit and/or more than one valve may be addressed in one Change Record.

Identify multiple limits with a "/'. or equivalent. Any combination is acceptable provided the n sulting record is clear. (Examples: "BT0/BTC* and "open 12 sec/close 13 sec', or, "2(3)HY9J36/2(3)HV9367").

VALVE EQUIPMENT ID:

(Use ID as it appears in PEDMS.)

IST TEST TYPE (S):

CATE: ENGINEER MAKING CHANGE:

BAS!$ AND REFERENCE DOCUMENT:

UFPER LIMIT:

OLD LIMIT: NEW LIMIT:

(Number and Units) (Number and Units)

LOWER LIMIT (STROKE TIME ONLY):

OLD LIM *T: NEW LIMIT:

(Number and Units) (Number and Units)

THE NEW LIMIT HAS BEEN VERIFIED TO BE WITHIN THE SAFETY ANALYSIS LIMIT OF AND SOURCE (Number and Units) (Example: Tech Spec No. 4.5.2)

NOTE: This change is not pennitted if a safety analysis limits would be exceeded as a result.

l Change completed and Entered in ISTH:

signature and Date

[ Independently verified and approved in ISTH:

l Signature and Date Distributed:

l

, CDM (original)

• j IST Chron File Operations Procedures Group operations surveillance and Audits Group I

23V35T92.wSI ATTACHMENT 5 PAGE 1 0F 1 l