ML20155G708

Forwards Rev 9 to 10CFR50,App R Shutdown Logic Calculation, Per NRC 880309 Request During Public Meeting in Rockville,Md & Original Commitment for 880425.Mods Identified During Verification Process Will Be Complete Before Unit 1 Restart

ML20155G708
Person / Time
Site:	Sequoyah
Issue date:	06/10/1988
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8806200067
Download: ML20155G708 (240)

Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 FN 1578 Lookout Place

'JUN 101988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) APPENDIX R - RESP 0liSE TO REQUEST FOR INFORMATION Provided in enclosure 1 is revision 9 to the SQN 10 CFR 50, Appendix R, shutdown logic calculation. The calculation is being provided as requested by the NRC staff during the March 9, 1988 public meeting held in Rockville, Maryland, and in accordance with TVA's letter to NRC dated April 13, 1988.

This calculation was originally committed to be sent to NRC by April 25, 1988, in the April 13, 1988 letter. Extensions to the commitment due date have been coordinated with the staff.

Unit 2 plant configuration and associated Appendix R documentation reflect this revision to the shutdown logic calculation except where interim compensatory measures exist. However, unit 1 is currently in a verification phase. .The verification of unit I to revision 9 of the shutdown logic is currently scheduled for completion by July 11, 1988. Modifications identified during the verification process will be complete before unit I restart except where interim compensatory measures may exist.

. Enclosure 2 is a listing of commitments made by this letter.

If you have any questions, please telephone M. R. Harding at (615) 870-6422.

Very truly yours, TENNESS VALL AUTHORITY R. Gridley, Dir ctor Nuclear Licensing and Regulatory Affairs cc: See page 2 I

8806200067 880610 7 DR. ADOCK 0500 An Equal opportunity Employer

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U.S. Nuclear Regulatory Commission WUN 101988 Enclosure cc (Enclosure):

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Mr. .K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Ms. S. C. Black, Assistant Director for Projects

.TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike

-Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 l

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ENCLOSURE 1 Equipment required for safe shutdown in accordance with 10 CFR 50, Appendix R (SQN-SQS4-0127, revision 9) (B25 880429 821) i l

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TVA 10691 (ONE-GA-6-86) ONE CALCULATIONS l Title ,

l Plant / Unit .l l EQUIPMENT REOUIRED FOR SAFE SHUTDOLN PER 10CFR50 APPEN0lX R I SON 1&2 l lPpjur(ngOrganization lKEYNOUNS(ConsultRIMSDescriptorsList) lmr r., 0 048 OWWU/M4 l FIRE PROTECTION. SAFE SHUTDOLN, APPENDIX R l

l l Branch / Pro]eltidentifiers lEach time these calculations are issued, preparers rnust ensure that the l

l original (RO) RIMS accession nmber is filled in. '~

l SQN-SQS4-127 lRev (for RIMS' use) RIMS ACCESSION NUM8ER l l l l 1 l l _, l R0 l 841002H0001 l NEB 840913 222 l l Applicable Design Docunent(s) l l l [

lSQN-0C-V-24.0 l,R7 l 870722A0006 B45 870714 426 l ES SE M 4-10

[EN l R, 880229E0012(@ su aaooio u .> l lSAR y c m a m j g o w tm.(s>

l Revision 0 l l,!NFORMWHON GM.YT B e s R8 l R9 l RIO lSa fety-rela ted7 88oA29 s2i j Yes (x) No ( ) l lECN No. (or Indicate Not Applicabie)l l l [Statanent of Problem l l _. I N/A I FJ /A l l l l Prepared l)TathC l l Determine the functions and sets of l l_ David L. Wallace I l . @l l equignent required for safe shutdown of l l Checked l_ John H. Plat foot . j/MAIl lA -

/2f/8e l dA4 l Sequoyah Nuclear Plant under postulated l fire conditions as defined by 10CFR50, l

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l -l l 9-13-84 l1[#'k 1 88 ll $208b ll l l lUSE FORM l List all pages added l l I

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l$ PACE l VAFI*"5 l Ya f**** 5 l l l l REQUIRE 0lListallpageschangeo l lby this revision l

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l l l l l ABSTRACT <Theie calculation / containsan unverified assmption(s) that nust be verified later: U2 Yes ( ) No (x)> l l Dn D,e UI Yes (x) No()>l l

! 1 l This calculation defines the functions and sets of equignent within NTB's scope of ret,onsibility which are l l required to achieve safe shutdown in accordance with 10CFR$0, Appendix R Sections Ill.G and L. The l

l analysis developed a safe shutdown logic diagram which identified all functions and which' served as a basis l l for a more detailed analysis. The results include: (1) a tabulation of corponents which must operate to l l satisfy the safe shutdown paths via this logic diagram, and (2) a tabulation of required operator actions. l l

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( ) Microfilm and store calculations in RIMS Service Center Microfilm and destroy. () l (x) Microfilm and return calculatior.s to: Dave Renfro Address: W10 A52 C-K l l cc: RIMS, SL 26 C-K 3447F/JMS l V. A. Blanco, DNE OSC-A030, Sequoyah t

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, QA Redra TvA 10697 (0Nr cs.6-a6) DNE CALCULATTONS l Title (Plant / Unit i ECUlfHENT RE(XIIRED FOR SAFE SHUT 00iN DURING A DESIGN BASIS FIRE I SCN la2 froaringOrganization l KEY NOUNS'(Consult RIMS Descriptors List) 1 FIRE PROTECTION l anch/ Project identifiers lEach tirne.these calculations are issued, preparers rNst ensure that the e.. l original (RO) RIMS accession nu cer is filled in. ~*l l

lSCN.SQS4-127 lRev ffer RIMS' use)

_ RIMS ACCESSTON NUMBER l l l l_. I RO I 841002H0001 l NEB M0913 222

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Applicable Design Doctsnent(s) l M 0714 l

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R8 ISafety-related?

1 l R9 Yes (x) No ( )

lECN No. (or indicate Not Applicable)T P % i l lStatanent of Problem l l l' l l l Prepared -

T l l Evaluate the ability of SON to achieve a saf lDavidL.Wallace 1' ./ l lshutdownduringafireconsistentwiththe IChecked lV l l requirarents of Appendix R of 10CRF50.

'l_ John +f. Platfoot (P./. @// l-- l ) l l lkeviewed .

l y/l l l l_ A. P. Blanco nwV _

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[ ABSTRACT (These calculations contain an unverified asstsrption(s) that rmst be verified later. Yes (x) 1

- No ( })

l This calculation defined a design basis fire consistent with Appendix R of 10CFR50. It defines boundary conditient l which trust be tret to achieve safe shutdown and performs an analysis within these boundaries to daronstrate safe

! l shutdown capability. The analysis developed a safe shutdown logic diagram which identified all functions requir l l and which served as a basis for trore detailed analysis. Results are presented as requiraients and includet (l) a l l tabulation of comonents which must operate, including comonents which trust not spuriously operate to sat l

l Safe shutdown paths via this logic diagram, (2) a. tabulation of required operator actions, and (3) generic l l requiratents which contained factors that trust be considered in future analyses, i I l

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) Microfilm and store calculations in RIMS Service Center Microfildvl1 destroy. ()

( _d Microfilm and return calculations to: D WF QC11FRA Address: W10A s2 c- k' cc: RIMS, SL 26 C.K H. L. Jones, ONE DSC.N O3, SON ONEl-5190Q 1

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I ass f m e.c f l N heset blocks en the Sequosah Nuclear Plant Safe Shutdown Locle Diagram are expanded M devele,atng sraller lecic Jiagramt. which (Jentify the subsystrm(,6) and/or components requarcJ t o r re v J e t hs (unctien in the keved block. The keved logic diagrams are then

is K te centilr lists of equipment whu h may be required to achieve and nalntain safe W dds%9 under 'ostulated fire conditions. (

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I The keyed- blocks on the Sequoyah Nuclear Plant Safe Shutdown 1,ogic Diagres are ll expanded by developing smaller logie diagrams which identify the subsystee(s) a n d,' o r j c om pone n t s required to provide the function in the keyed block. The keyed logie diagrams are then used to compile lis t s of equigreent which may be requsted to achie.e and maintain safe shutdown unde r pos tulated fire conditions.

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CA1.CULATION D'ESIGN VERIFICATION (INDEPENDENT REVI 504 -SCS 4 -127 __ 9 Calculation No. Revision Dest MSAS Method of design verificat

on (Independent revibw) used (chock nothod used):

1 Design Revlow / '

2. Alternate Calculation 3 Qualification Test Justification (explain belcw): ,

Method 1: In the design rs view method, calculation and explain how the adeqyacy justity,the technical adequacy of the similar to anotr er,. based on accepted handbook was verifled (calculation is senaltivity'stuc lesincludedforcon{!dence,etc.). methods, appropriate Method 2: In the alternate calculation method, identify the pagos where the

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alternate calcul ation has been included in the calculation package and explain why this method is adequtta. -

Method'3: In the qualification test method, identify the QA documented

• source (s)-where testing adequately demonstrates the adequacy of -this calculation and explain. '

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Title:

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN I SON-SOS 4-0127 l l Revision [ Date l No. 1 l l Description of Revision l Approved l l 1 l 8 1 I l Revision 8 incorporates changes recommended by the l 2-12-88 l l

l Appendix R Resolution Team (reference Final Report - l l l l B45 880120 251). Changes include: t I.

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l l 1. Title of calculation revised. I  !

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l l 2. "Statement of Problem" and "Abstract" rewritten. l l I l l I  ;,

l l 3. General rewrite of calculation and various key diagrams l I l t l

l l to reflect scope as defined in Section 1.0.

' l l l l l l 4. Appendix D revised to delete previous contents and add ll 1 l

l l instnamentation list fo;- the MCR. l l- l l 1 l l l 'S . Restructuring of Shutdown Logic Diagram.

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l l l 6. New components added between this revision and l l l l l revision 6 are denoted with an "*" in Appendix C. l l I I ,

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l Revision 9 incorp' orates the following changes:

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l. l 1. Additional reference documents included l .I l l l l

l l 2. Revised Shutdown Logic (SDL) Figure 1 to add Latdown l 1 l l l l Capability (Key 48) to achieve Hot Standby. l

. l -l l l l 3. Revised Key 24 to add manual valves located in the l l

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\ l Hot Sample Room. l This changes Key 24 Appendix A & B. l l l l l l 4. Revised Key 28 for editorial changes and revised the l l

1 l l Key 28 SDL diagram (A103) l l l l l

1 l l S. Revised Key 37 to incorporate changes pandated by l l Reference 11.13. This resulted in changes to Key 37B, ll l l ,

l l '37H, 37J, 37K, 37H, 370 and 37P. Required changes l .

l l l to Key 37 Appendix A & B. l l l l l l

l l 6. Revised Key 48 entirely to include normal, excess, and l 1 l l l alternate letdown paths. l l l l l -

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MPw TABLE OF CONTENTS Page

1.0 Purpose and Scope

I 2.0' User Guide.

... .... ... . . . . . . . . . .. . . . . .. 1 3.0 Assumptions .

... ... ...... . . . . . . . . . ... .. 2 4.0 General Requirements 4.1 Accidents . .

.. ... . . . . . . . . ... . . .. .. 3

............ . .. .. . ... .. 3 4.2 Pneumatic Systems .............

4.3 Instrument Sense Lines . . . . . . . ...... .. 3 4.4 Electrical Support ............. . . ..... ... .. 3 4.5 Design Implementation . .. . .. .. 3

.. . . . . . .. .. . . .. . . 3 4.6 Containment' Isolation .......... . . . . . . . . 4 4.7 Fire Control . . . . . . . . . . . . . . .

...... . . 4 5.0 Requirements for Equipment Which Must Operate To Asrste Safe Shutdown.

5 .1.

.................... .. . ..... 4 General Discussion of Shutdown Logic . . .. .....;..- 4 5.2 Discussion of Specific Conditions Required for Hot Standby .

5.3 Discussion of Specific Conditions Required for Cold Shutdown 4 .

5 5.4 Monitoring Capability. . . . .. . . . * . .......... 5 6.0 Requirements for Equipment Which Must Not Spuriously Actuate to Assure Validity of Safe Shutdown Analysis .......... 5 7.0 This secticn has been deleted.

8.0 This section has been deleted.

9.0 Auxiliary Control Room Requirements . . . . . .......... 6 10.0 Regulatory Responsiveness . .. .,. . ., . . .

. _ , . . . . . . . . . . 6 11.0 References

. ... . .... . . . .. . . . .......... . 7 12.0 Background Information .

... . . . . . . . . .. . . . . . . 9

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s........ ..-y...~., .va our c. anu t wna PER 10CFR50' APPENDIX R Prspar:ad by/Date s

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. . . . . . . . . . . . . . .. . . . . . . . .. 12 Appendix A Key Components Required for Safe Shutdown Under Fire Al Conditions Appendix B- Operator Actions B1 Appendix C Listing of Components Required for Appendix R Safe Shutdown C1 Analysis Appendix D Instrumentation List for Main Control Room D1 Appendix E' Instrumentation List for Auxiliary Control Room El FIGURES Figure 1 Shutdown Logic biagram .

14 .

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cyuleMtler dtQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date 8 4 [ M h 't.//o/88 i SQN-SQS4-0127 Checked by/Date _ A d & 9//0//7

1.0 Purpose and Scope

The purpose of this calculation is to define the safety functions and sets of equipment required to achieve and maintain safe shutdown of Sequoyah Nuclear Plant under postulated fire conditions as defined by 10CFR50, Appendix R Sections III.G and L (Facility Operating License DPR-79).

-The :::p: cf thic d::ument in limited to thee; arca; cf ';TB; re.ye..ibil.tj es p ei.mm ly Jcfi..c in EN 0:0 CCP 0'-10. Sofe Ohmide-w ss

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fu. Peetuisted rices at Oeqccyeh Nmcleer Plant. This-SEE Lh--

m... mar 2.0 User Guide Due to the complexity of this document, this section on user guide was deemed necessary.

This calculation is divided into aix parts. The first is a preamble consisting of the numbered sections of the document which establishes general shutdownrequirements logic used. and the basis for the calculation, including the support these requirements.It is followed by. five appendices which develop and Appendix A to this calculation provides a comprehensive listing of all -

componen;s and their required configuration (i.e...open, close, must operate, etc.) and system lineup positions necessary. to achieve the ,

specific key functions. It also identifies spurious actuations which ,

must be prevented. The basis for the spurious actuation list is supported by sketches illustrating selected flow paths. Components on the spurious list are easily located on the sketches by an item number which is identified in the basis for spurious list. This item number is shown on the sketches within a triangle symbol.

Appendix B to this' calculation discusses (in tabular form) the actions.

required by the operator to support this analysis (sce assumption 3.6).

The control station where the operator is expected to take these actions is mentioned in this appendix. ..

AppendixA.C can be considered as the index of all components discussed in Appendix It (1) contains a complete listing and brief description of components; (2) identifies the key used for these components in Appendix A and B ; (3) references the flow, control or logic diagrams where these components can be found; and (4) identifies the item numbers used when these components are discussed in the basis provided for the spurious actuation list and sketches.

Appendix D contains a minimum listing of instrumentation needed for monitoring safe shutdown from the main control room.

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• Checked by/Date A.,l $$1 JJ/offf l Appendix E provides the listing of components and instruments needed as a minimum for monitoring safe shutdown from outside the main control room in the event of a postulated fire.

3.0 Assumptions (1) Both. units may be operating in any mode when a fire is postulated.

This is a baseline assumption chosen to be consistent with Appendix R requirements (Section III.G.a and b) and TVA's intended operation of the plant.

(2) No design basis events except the loss of offsite power are  !

considered concurrent with a postulated fire. (It is assured by the requirements of section 4.1 of this document.) j.

(3) The latest revisions of the DNE drawings and documents are assumed to reflect the plant configuration. This is an unverified assumption for unit 1 only.

of SQN unit 2 during cycle 4 It Forwill be verified after the restart unit 2 and common systems this has been verified by reviewing the as-constructed drawings.

(4) The A-train ERCW cooling water supplies the A-train CCS heat exchangers. The same is assumed for the B train lineup. (This is  ;

verified via Design Criteria SQN-DC-V-7.4 - ERCW System).

4 (6) Operations has' instructions (e.g., SOI-26.2) that incorporate requirements relative to operator actions which are necessary to, support this analysis (e.g., contents of Appendix B). This assumption is considered verified by virtue of the fact that this calculation has been coordinated with Operations prior to issue. }

. 3 (7) Except for a non-mechanistic loss of offsite power, there are no I failures a otherfire.

postulated than those which can be demonstrated to be effects of '

(8) For shutdown logic diagram Key 6 the flow characteristics of valves FCV-63-25, 26, 39, or 40 (any one) are suitable for short term (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) use as throttle valve,. This has.been verified by QIR l SQP-87-452. 1 l

t (9) Operation of the main steam valve vault ventilation system is not required during a postulated fire. This assumption has been I verified by QIR NEB 87295.  !

(10) The information found in Key 37 provided by 'VAC input and reference calculation NEB 850115 235, is assumed to be valid and correct.  :

This assumption has been verified by QIR NEB 87295.

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l 3448F/JMS

.# i t cie 6 ar.yvinc.u rux dM t dilVTDOWN PER 10CFR50 APPENDIX R Prepared by/Dato Yft1 4/lo/SP SQN-SQS4-0127'

• Checked by/Datek.d& 2//o/rf ,

4.0 General Requirements Appendix R to 10CFR50 (reference 11.1) requires that one path of systems necessary to achieve and maintain hot standby condition be free from fire damage and that systems required to achieve cold shutdown can be repaired within NRC.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless specific deviations have been approved by the References 11.2 through 11.6 provide further clarification of the requirements presented in Sections III.C and III.L of Appendix R.

4.1 Accidents It is required that a fire shall not result in a design basis accident (condition III or IV event) as defined by chapter 15 of the FSAR because mitigation of such accident is beyond the scope of this Appendix R anelysis, i.e.,

mitigation.

equipment and' safety functions appropriate for accident In addition, this calculation implicitly takes credit for compliance with Section III.0 of Appendix R in that a fire around the reactor coolant pumps does not result in seal damage and a subsequent LOCA (reference NRC approval of deviations for oil collection system-L44 860606 620).

4.2 Pneumatic Systems t

In general, no distinction is made in this document as to the energy source which is used to accomplish the function under consideration. -

However ,since the most common energy source is electrical, explicit mention is being made in regard to pneumatic systems. The integrity of air headers could be lost during a fire due to failure of soldered fittings and elastomers in various devices. (This situation is analogous to electrical circuits with common power supplies, i.e., Type I associated circuits.) The resulting pneumatic system failure effect-(e.g., unavailability of pneumatic power when required, and spurious operation of pneumatic valves) must be considered.

1 4.3 Instrument Sense Lines Fire effects upon instrument sense lines have the potential to render the instrument inoperable. If credit ,is being taken, for any instrument function or not to spuriously malfunction to satisfy the requirementstoof this document, then any fire effects upon the sense line for that instrument must be evaluated. Specific requirements are contained in SQN-DC-y-24.0.

4.4 Electrical Support Fire effects upon electrical end devices shall not preclude the -

availability of~the electrical power distribution system needed to support the requirements of this document. Note, detailed listing of electrical power distribution systems components (motor control centers, switchgears, distribution panels, etc.) necessary to support the requirements of this calculation is considered to be outside the scope of this document and will be addressed by the Electrical Engineering Branch (reference Electrical Equipment Block Diagrams - SQP S41210 006).

3 3448F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN .

PER 10CFR50 APPENDIX R Prepared by/Date M. M Z//o/2 SQN-SQSA-0127 Checked by/Dato _P.f. M i 4.5 Design Implementation Methods of demonstrating compliance with the requirements of this document are beyond its scope and are implemented by design criteria such as SQN-DC-V-24.0, 4.6 Containment Isolation Containment isolation is not required by sections III.C. J, L, and 0 of Appendix R because the limiting consequences for compilance with Appendix R include precluding fuel clad damage and maintaining reactor coolant pressure integrity in the event of a postulated fire.

4.7 Fire Control These aspects are outside the scope of this calculation and are addressed in SQN-DC-V-7.5 and SQN-DC-V-7.6.

5.0 Requirements for Equipment Which Hust Operate To Assure Safe Shutdown 5.1 General Discussion of Shutdown Logic -

It is required that a safe shutdown be achie'vable in the face of any '

equipment failure that can be directly'or indirectly caused by a

• postulated fire. This calculation contains a shutdown logic diagram (Figure 1) which defines the plant conditions that must be met to achieve a safe shutdown of Sequoyah Nuclear Plant following a postulated fire.

- The safe shutdown of Sequoyah via these conditions will assure that,the plant is first brought to the hot standby condition and then with the initiation of long-term heat removal and the necessary environmental controls to'the cold shutdown condition.

The shutdown logic diagram and the associated keys serve as the basis for the list of components described in Appendix A, C and E which must operate to achieve safe shutdown. The shutdown logic diagram permits use of any operable component which can be powered-by an onsite source to accomplish required functions without regard for their qualification.

The diagram permits loss of components which are required to mitigate design basis accidents (this is the basis for requirement 4.1). Single failures of required components need not be considered to determine a success path. All systems and components used for safe shutdown shall be capable of performing this intended function without exceeding their design limits.

5.2 Discussion of Specific Conditions Required for Hot Standby To achieve hot standby, a total of 8 conditions must be simultaneously met.

4 3448F/JHS

=

EQUIpHENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date _ d_[ M/o/gg SQN-SQS4-0127 Checked by/Dato _ f./ & l 3)/0/97 Condition RCS Inventory Control Steam Cenerator Inventiry Control Secondary Side-Pressure Control Secondary Side Isolation Initial Reactivity Control Onsite Electrical Supply Environmental Control Operator Integrity The inability to fully meet any one of these conditions will render the plant incapable of achieving and maintaining hot standby.

'5.3 Discussion of Specific Conditions Required for Cold shutdown Having achieve 4 9 t standby, the plant can achieve cold shutdown by

, satisfying the following three conditions:

Environmental Control Long Term Heat Removal Long Term Reactivity Control S.4 Monitoring capability .

Appendix D summarizes the minimum list of in'struments that are necessary to ensure safe shutdown frcm the MCR in the event of a fire.

6.0 Requirements for Equipment Which Must Not Spuriously Actuate to Assure Validity of Safe Shutdown Analysis An analysis of the effects of Type II* associated circuits should be performed for those keys where spurious activity would preclude the basis of the safe shutdown logic diagram (as represented by Figure 1). The components whose spurious actuation could prevent a safe shutdown were i

those that (1) are in-line valves in required flow paths (2) could divert I flow from a required flow path or (3) defeat the intent of the keyed functions where applicable.

As part of the review, a spurious safety injection signal, phase A f- containment

= t be-isolation signal and phase B containment isolation signal We M*'gg reviewed to ensure that they do not cause equipment to operate or realign and defeat a safety function.

The components whose spurious actuation would adversely affect the plant are listed in Appendix A. This appendix also provides sketches i

illustrating all in-line valves which could divert flow.

• l In evaluating the need for protection of circuits to preclude the various

' spurious actuation items listed in Appendix A consideration shall be given to the sensitivity of those circuits to firo induced spurious actuations. All spurious actuations that are considered by EEB to be credible (Reference r ) in a single fire and that could prevent safe shutdownasdefinedQnAppendixAshallbeprecluded.

0458802.10252. 5 4 3448F/JHS

• M* '

EQUlPHENT REQUIRED FOR SAFE SHUTDOWN .

I PER 10CFR50 APPENDIX R Prepared by/Date M NI. Z[/0/fs SQN-SQS4-0127 Checked by/Date A-l N A/M/77

• See references 11.2 and 11,3 for requirements for Type I and III associated circuits. These requirements are outside the scope of this document.

7.0 Section 7.0 has been deleted. The procedural requirements previously contained in this section are outside the scope of this calculation '

(Reference @ BZ5ESor.lolol 8.0 Section 8.0 has been deleted. The operational requirements previously contained in this section are outside the scope of this calculation (Reference @ 6:tSf802Jolol 9.0 Auxiliary Control Room Requirements For fires inside the control building, instruments located in the HCR may be lost, and evacuation to the auxiliary control room may be necessary.

Under these circumstances, the instrumeuts listed in Appendix E shall be physically separated and electrically isolated from fire effects in the control building such that safe shutdown from the auxiliary control room is assured. In addition, a path of equipment from Appendix A shall be operable (manual or automatic operation) and prevented from spurious operation. -

10.0 Regulatory Responsiveness IE Information Notice 84-09--Lessons Learned From NRCs Inspection of Fire Protection Safe Shutdown Systems, Revision 1 dated March 7,

- 1984--included the RCS cold leg temperature and the condensate storage (c$r) tank 4' level in its listing of minimum monitoring capabilities needed to

$*s ac.hieve a safe shutdown from the auxiliary control room. p unli6 The absence of RCS cold leg temperature monitoring is considered to be justified because during a reactor coolant system cooldown from the ACR, the steam generator pressure will be adjusted to the desired corresponding Teold temperature using steam generator PORV l controller. If a cooldown is in process'.ThoC ean be used just as well as Tcold to determine cooldown rate since delta "T" will remain .

relatively constant. Therefore, the accuracy in reading the steam generator pressure indicator will have minimal effects on the cooldown rates since the steam generator pressure is adjusted from the PORV I

controller. The steam generator pressure indication can be used to I '

verify the set point on the PORV controller and to determine Teold-(Referetice: NRC Approval of TCold Instrumentation for ACR Deviation l Request - L44 861010 079).

• l i I

l l

l l 6 i I

3448F/JHS I

1 l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN .

PER 10CFR50 APPENDIX R Prepared by/Date M /

• B-fd Checked by/Date RLC/a V/h9/sr The absence of CST level indication is justified becauso CST level indication is functionally not needed in the ACR. The absence of this '

instrumentation would in no way affect the ability of the operator to  !

achieve a safe shutdown. The CST has been sized to provide adequate water for most cooldowns. Because it is possible, however, that this l water source could be exhausted during a prolonged cooldown, the capability exists to switchover auxiliary feedwater pump suction to the l' Essential Raw Cooling Water System. Per reference 11.9, local monitoring of AFW pump suction pressure will ensure that manual switchover is accomplished (also reference SOI-26.2).

11.0 References ,

11.1 10CFR50 Appendix R 11.2 Generic Letter 81-12, February 20, 1981 11.3 ' Clarification Letter of Ceneric Letter 81-12, April-May 1983 11.4 SECY 83-269, July 5, 1983 11.5 IE Notice 84-09, February 13, 1984 ,

11.6

• Branch Technical Position CHEB 9.5-1 11.7 Reference Deleted 11.3 DET-NEB Calculation: "Emergency Lighting Requirements for Main and Auxiliary Control Room Lighting During Upset Conditions" R2 (SQN-OSG7-026) (B45 880210 430) 11.9 AOI-27, Revision 6 Control Room Inaccessibility 11.10 Essential Raw Cooling Water System Design Criteria, SQN-DC-V-7.4 11.11 Volume 2, Table 7, Sequoyah Nuclear Performance Plan 11.12 Reference Deleted 11.13 DET-NEB Calculation: "10CFR50, Appendix R. Heating, Ventilation and Air Conditioning Review" TI-ECS-95 (R3), (B45 880321 236) 11.14 SQN-DC-V-24.0, "Fire Protection for Appendix R Requirements" R2 11.15 QIR SQP-SQN-88-259, Revision 0, "Availability of Offsite Power 72 bS Hours Following an Appendix R Fire (B25 880312 074) 11.16 QIR SQP-SQN-88-361 Revision 0, "Lower Compartment Temperature for Appendix R" (B25 880409 003) 7 3448F/JMS

1 EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

~PER 10CFR50 APPENDIX R Prepared by/Date SAM Y u.gg SQN-SQS4-0127 Checked by/Date Al C.Mu h21/81_

11.0 References (Continued) 11.17 QIR SQP-SQN-88-275. Revision 1, "Heating Effects'on Aux Bldg Transformer Room Electrical Equipment During an Appendix R Event" (B25 880317 103) 11.18 QIR SQP-SQN-88-319. Revision 0, "Lower Compartment Temperature for Appendix R" (B25 880325 018) hi 11.19 l QIR SQP-SQN-88-355, Revision 0, "Lower Compartment Temperature for Appendix R" (B25 880408 028) 11.20 QIR NTB-SQN-88-107. Revision 0, "Lower Containment Temperature for Appendix R" (B45 880415 252)

O e

t 9 9 l

l 5

I ~~

i 7A 1 >

4 3448F/JMS l

=

~

3yU1PMENT REQUIRED FOR. SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date _8 4 df 4/to/tf SQN-SQS4-0127, Checked by/Date )./. U .3)tofty 11.15 The following SQN DNE drawings were used to generate component lists for unit 1.

47W801-1 R25 ' 47W848-1 R14

-47W801-2.

47W610-67-6 R8 R23 47W848-2 R8 47W610-63-1 R14 47W803-1 R17 47W848-2 R8 47W803-2 47W610-68-L R15 R25 47W848-3 R5 47W610-68-2 R14 47W809-1 R23 '47W848-8 R12 47W809-2 47W610-68-3 R17 R5 47W848-9 R10 47W809-5 47W610-68-4 R20 R8 47W848-12 R9 47W810-1 47W610-68-5 R19 R13 47W851-1 R17 47W811-1 47W610-68-6 R11

-R23 47W859-1 R12 47W610-68-7 R7 47W811-2 R13 47W859-2 R17 47W812-1 47W611-62-3 R5 R11 47W859-3 R18 47W813-1 47W611-62-4 Rll R21 47W859-4 R7 47W819-1 47W611-63-2 R9 R21 47W866-1 R24 47W830-4 47W611-63-4 R6

'R18 47W610-1-1 R16 47W845-1 47W611-63-8 R2 R19 47W610-1-2 R14 47W845 47W611-68-3 R9 R19 47W610-3-1 R16 47W845-3 47W611-99-7 R7 R18 47W610-3-2 R16 47W845-4 47W611-99-2 R5 R19 47W610-3-3 R12 47W845-5 47W611-99-6. R8 R9 47W610-62-2 R16 47W846-1 R18 47W610-62-3 R10

• 11.16 The following SQN As-Constructed drawings were used to verify component lists for unit 2.

47W801-1 R20 47W846-1 R16 47W801-2 47W610-62-3 R10 R23 47W848-1 R14 47W803-1 47W610-63-1 R13 '

R18 47W848-2 47W803-2 R5 47W610-67-6 R8 R25 47W848-3 47W809-1 R5 47W610-68-1 R12 R24 47W848-8 R15 47W809-2 47W610-68-2 R11 R4 47W848-9 R9 47W809-5 47W610-68-3 R10 R8 47W848-12 R9 47W810-1 47W610-68-4 R22 R13 47W851-1 R16 47W811-1 47W610-68-5 R22 R27 47W859-1 R14 47W811-2 47W610-68-6 R11 R10 47W859-2 R17 47W812-1 47W610-68-7 R8 R11 47W859-3,,

47W813-1

' R1.8 47W611-62-3 R5 R26 47W859-4 R7 47W819-1 47W611-62-4 R13 R20 47W866-1 R24 47W830-4 47W611-63-2 R9 R19 47W610-1-1 R17 47W845-1 47W611-63-4 R6 R19 47W610-1-2 R14 47W845-2 47W611-63-8 R2 R17 47W610-3-1 R17 47W845-3 47W611-68-3 R9 R14 47W610-3-2 R17 47W611-99-7 R7 47W845-4 R24 47W610-3-3 R12 47W611-99-2 R5 47W845-5 R7 47W610-62-2 R19 47W611-99-6 RS ,

~~

8 3448F/JMS

~ ~

'" EQUIPMEN H EQUIRED FOR-SAFE SHUTDOWN <

PER 10CFR50 APPENDIX R Prapired by/ Data /&dL[ [//0/88 3

SQN-SQS4-0127, Checked by/Date f./ LLJ 2}/offy 12.0 Background Information 12.1 10CFR50, Appendix R 12.2 EN DES-SEP 84-10, Safe Shutdown Analysis for Postulated Fires at Sequoyah Nuclear Plant 12.3 NEP 3.1 Calculations, R1, DNE INTERIM' ORDER FOR NEP-3.1 (B05~871119 500) 12.4 Sequoyah Nuclear Plant 10CFR50, Appendix R - Fire Protection Submittal, October 1981.

.12.5 A0I-10; Loss of Control Air, R13 12.6 AOI-12; Loss of Containment Integrity R6 12.7 AOI-13; Loss of Essential Raw Cooling Water, R10

~

'12.8 AOI-14; Loss of RHR Shutdown Cooling, R8 12.9 A0I-15; Loss of Component Cooling Water, R9 12.10 AOI-18; Malfunction of Pressurizer Pressure Controi System, R8 ,

12.11 AOI-20; th1 function of Pressurizer Level Control System, R7 12.12 AOI-21; Loss of 125V de Vital Battery Boards * '

12.13 50I-25; Loss of 120V ac Vital Instrument Power Boards

• 12.14 AOI-26; Loss of Control Room Annunciators, R1 12.15 A07-27; Control Room Inaccessibility, R9 12.16 SQN-DC-V-2.17; Remote Shutdown Criteria From Locations Outside the dhin Control Room, R0 12.17 SQN-DC-V-10.7; 10CFR50, Appe'n' dis R. ' Type II Items, R0 12.18 SQN-DC-V-24.0; Sequoyah Nuclear Plant General Design Criteria for Fire Protection for Appendix R Requirements R2 12.19 SQN-DC-V-11.2; Non-Class 1E Direct Current Power Distribution Systems Compliance With 10CFR50, Appendix R. R0 12.20 AOI-10; Plant Fires, R5 12.21 SOI-26.2; Fire Interaction Manual. R6

.

• 8 Procedures with varying revision levels - no influence on calculation 9

3448F/JMS

cyVarMths REQUIRED FOR SAFE SilUTDOWN

,- PER 10CFR50 APPENDIX R Preparad by/Date Nd.Gk O1/4/ff SQN-SQS4-0127 '

. Checked by/Date _/ / & 2/n/SP 12.0 Background Information (continued) 12.22 10CFR50, Appendix R NRC Correspondence .

Inspection of safe shutdown A02 840625 G02 capability and associated fire protection features TVA intentions to correct APP R -A27 840807 010 Confirmation of action - SQN A02 840817 011-Units 1 & 2 TVA response to C0A letter A27 840821 016 Meeting summary A02 840827 012 Monthly status report L44 840920 801 Coatings on IEEE-383 qualified L44 841918 800 Cables Monthly status report L44 841015 800

• Confirmation of action NEB 840913 605 Shutdown logic submittal L44 840917 803 ,

,Monthly status report L44 841109 806 -

Inspection report NEB 841121 604 50-327, 328/84-31 Inspection of compliance with NEB 841219 601 Appendix R Appendix R deviation requests L44 841218 800 Information requested by NRC' L44 841227 800

. ,12/12/84 Final report required by COA L44 841221 804 letter Additional deviation requests L44 850111 800 and fire door update .

Confirmation of action receipt NEB 850206 607 of final report l

} Revision to deviation request #15 L44 850304 805 l

Enforcement conference of 02/28/85 A02 650320 009 Report #'S 50-327, 328/85-01 A02 850403 009 10 3448F/JMS

tyUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R-g Prepared by/Date _ Na /~/A Y 2/1o/81

- SQN-SQS4-012 7, Checked by/Date _/ / /M a//s/fP 12.0 . Background Informatioa (continued) 12.22 .10CFR50, Appendix R NRC Correspondence SQN position on internal conduit L44 850412 808 sealing Removal of ERCW'and DG b1dg L44 850805 805 firewatches ERCW and DG b1dg deviation L44 850903 268 request and firewatch removal Report #'S 50-327, 328/85-37 L44 851127 389

'~

Completion of modifications L44 851129 802 associated with deviation requests Removal 9t firtwatches L44 860220 804 Revised emergency lighting L44 860305 812 commitment RCS cold leg temp indication L44 860319805 for ACR RCS cold leg temp indication L44 860502 807 for ACR-

' Approval of deviation requests L44 860606 620 Inspection report #'S A02 860813 001 50-327, 328/86-40

. Approval of Tcoid instrumentation L44 861010 079 for ACR deviation request Appendix R status update ,, , L44 861107 803.

Notice of violation (inspection A02 870121 005 report #'S 50-327, 328/86-66)

Modifications associated with L44 870116 802 deviation requests SQN modifications associated A02 870303 018 .

with deviation requests

~

. 11 3448F/JMS m

i m i es mu u a un i b -

i---in--W

< EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date 77t2, /C// t/ro/gg LSQN-SQS4-0127, Checked by/Date ) , / ff_1 2 jajff 13.0 Notes for SLDs (Figures- 1 through 12)

(1) Solid lines are used for paths leading to the Hot

'- Standby and Cold Shutdown Conditions. The logic diagrams will

_ require analysis to assure that all required conditions can be realized during a fire. The criteria for acceptability is as follows: Given a fire which effects any function on the diagram, the. required condition must be capable of being reached either via a parallel redundant or diverse path which is physically separated or protected from the fire or by virtue of the fact that the function may be considered immune to fire damage (e.g., the refueling water storage tank). .Any deviations must be appreved by the NRC.

(2). B$ocksdenotedwithanAandBsubscriptsaretrained.

is provided for this block. Redundancy (3) . Key componants are located in Appendix A.

(4) Spurious components are listed by item number and discussed in Appendix A and C.

4

• 6 4

1 O

12 i

3448F/JRtS i .

OECxCO Briouc KLCjn 4]29/9 x MN -Se sq-i27 P8'r n g;ai 6 m,:im:l=:' =c - , =:E >= F9 =

A s

,r a y e , i gy #i w

1. -a (fE w(') (=- )(5- )

WW r a- t (a-r) (m) (= -)

v v- '

A n

p: e argive w=gs f .r,:.

, y.n N'

=.. =l (c) (s) 1

(=-> ( a=) (e+)

(e=> ,

( =-) (=) .

. 1 Pe (=..)

I I

( = X =- )( =- ) -

= =.

,a,- -, - . .

-z

- , i l=- lg.,l V

(se) i (n.r)I

(==--)

o e

APPENDIX R SAFE SHUTDOWN LOGIC DIAGRAM FIGURE I

.sheee 13 ao

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

LEQUIPMENT! REQUIRED FOR SAFE SHUTDOWN PER;10CFR50 APPENDIX R-Prepared by/Date _NA [ Zh8/88 SQN-SQS4-0127 Checked by/Date ], / M ,7//a/f/

I e

4 m

4

. e APPENDIX A 4

J KEY COMPONENTS REQUIRED FOR SAFE SHUTDOWN UNDER FIRE CONDITIONS b

o sa

• 6 4

8 e

i J

. Al 3446F/JMS

I EQUIPMENT REQUIRED FOR SAFE bHUTDOWN PER'10CFR50 APPENDIX R

' Prepared by/Date _ N d.[ l/M/88-SQN-SQS4-0127 Checked by/Date _ /,/ Ad d. ,7//d/f7 APPENDIX A SEQUOYAH NUCLEAR Pl. ANT KEY 1 Availability.of CVCS Centrifugal Charging Pump This key requires that a centrifugal charging pump (CCP) be available to provide RCS makeup water while achieving and maintaining safe shutdown. To ensure that a CCP is operable, the supporting components and subsystems are required. The CCP pump. auxiliary lube oil pump must provide pump lubrication for startup of the However, if the lube oil pump (or its associated circuitry) is damaged by fire, the switch bypassing the oil pump must be used to start the CCP. The pump room cooler and its control circuitry must operate. The component cooling system (CCS) is required for pump, cooling.

-This key is organized as follows:

Item 1 - Functional logic diagram for CCP operability. '

Item 2 - Tabulation of components which must be operable.

Item 3 - Tabulation of spurious actuation which must be prevented. ,

This item is organized as foll'ows:

(1) Tabulation of spurious actuation for unit 1, path 1 (2) Basis for unit 1, path 1 items ,

(3) Simplified flow diagram for unit 1, path 1 '

(4)' Tabulation of spurious action for unit 2, path 1 (5) Basis for unit 2, path 1 items (6) Simplified flow diagram for unit 2, path 1 (7) Tabulation of spurious actions for unit 1 and 2, path 2, (8) Basis for units 1 and 2, path 2 items (9) Simplified flow diagram for units 1 and 2, path 2 Item 4 - Notes as used in items 1 through 3 above.

Operator actions required to support this k,ey are c,ontained in Appendix B.

0

~% i b

3446F/JMS

. EQUIPMENT REQUIRED FOR SAFE SliUTDOWN

' PER LOCFR50 APPENDIX R Prepared by/Date _ f d -

2//s/g3 SQN-SQS4-0127 -

Checked by/Date _f. /. $bl .?/ MAT

-r CCP OPERABILITY LOGIC Key 3

'CCS ERCW AUXILIARY HAND HEADER TO CCS FLOW

'UBE

. OIL SWITCH HEAT EX PUMP 62-104M Key 3 Key 3 ERCW TO ERCW ROOM ROOM HEADER COOLER COOLER FLOW I FAN AND -

THERMOSTAT I

ERClW TO LUBE h/ h/ sr

%/ h[ OIL COOLERS V y AND .

AND OR 1:ey 3

.y s AND Y +

CCP MECH _

CCP CCP SEAL COOLING ROOM LUBE OIL COOLING AND l

CCP OPERABILITY o

A3 3446F/JMS

7; EQUIPMENT REQUIRED FOR SAFE SHUTDOWN iI PER 10CFR50 APPENDIX R  ;)

. Prepared by/Date _ A t:t. U A t//o/3f SQN-SQS4-0127 l

i Checked by/Date _ #, / M ,?//s/fF

, APPENDIX A SEQUOYAH NUCLEAR PLANT KEY l (Operation List)

Path 1 Component Requirement Basis Centrifugal Charging Pump (CCP) A-A Must Operate Self Evident CCP Auxiliary Lube Oil Pump A-A (Note 12) Must Operate CCP t.ube Oil CCP Pump Room Cooler Fan A-A Must Operate Room Cooling Instrument Loop 30-183 (for fan control) (Note 13) Must Operate Room Cooling CCS Pump A-A) Either one CCS Pump B-B) (Note 8) Must Operate CCP Seal Cooling Must Operate CCP Seal Cooling.

0-FCV-70-197 (Unit 1 Only) (Note 9,14,15) Either Must Close 3-FCV-70-198 (Unit 1 Only) (Note 9,14,13) CCP Seal Cooling one Must Close ~

CCP Sea 1 Cooling ERCW supports CCP mechanical seal cooling, CCP room cooling, and CCP lube oil coolers.

Path 2 ,

CCP B-B Must Operate Self Evident CCP Auxiliary Lube Oil Pump B-B (Note 12) Must Operate CCP Lube Oil CCP Pump Room Cooler Fan B-B Must Operate Room Cooling Instrument Loop 30-182 (for fan control) (Note 13) Must Operate Room Cooling CCS Pump C-S (Note 10) i Must Operate CCP Seal Cooling >

ERCW cooling for CCS heat exchangers C is provided by normal supply header 2B or <

citernate ERCW header lA. For alignment see Key 3. 3 Note for information only: t According to Westinghouse report NS-RAT-PLRA-87-059, the charging pumps will still function prope'ely without CCS mechanical seal cooling. Thus, future revisions to this s ,

calculation may consider the deletion of the requirement for component cooling to the s:als. At the present time, however, this report is only applicable to the IPE j analysis, and additional information would be required f rom Westinghouse. (Reference istter TVA-87-625) -

i A4 3446F/JMS

-e

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX'R Preparedby/Dato.Nd[ J//d/88 SQN-SQS4-0127 Checked bylDate _ /..l $de.) 5}/*)?f m- APPENDIX A - KEY 1 SPURIOUS LIST FOR UNIT 1. PATH 1 For Unit 1, if Path 1 is used, the following spurious actions must be prevented:

~

Unit 1

• 1-FCV-70-156) ) - (Note 11) Any one Must Not Open

• • 1-VLV-10-545A ) Hust be closed

• • 1-VLV-70-546A ) , Must be closed 1-FCV-70-8 (Note 4) Must Not Close 1-FCV-70-9 ) (Note.4) Either one Must Not Open

• 1-FCV-70-10) (Note 4) Hust Not Open 1-FCV-70-2' (Note 4) Hust Not Close 0-FCV-70-34 (Note 4) (if CCS Pump 1B-B is used) Must Not Close

, 1-FCV-70-25 (Note 4) Hust' Not Close 1-FCV-70-64) (Note 4) Either one Must Not Open 1-FCV-70-74) (Note 4) Hust Not'open 1-FCV-70-26) (Noto 4) Either one Must Not Open 1-FCV-70-27) (Note 4) Hust Not Open 1-FCV-70-13) (Note 4) Either one Must Not Open 1-FCV-10-23) (Note 4) " '

Must Not Open 0-FCV-67-478 (Note 4) Must Not Close

• 1-FCV-67-146 (Reference deviation Hust Not Close L44 860606 620) 1-FCV-62-98 (Note 4) Must Not Cloce 1-FCV-62-99 (Note 4) Must Not Close ERCW Header 2A) Either one Must Be Available ERCW Header IB) _, (See Key 3)

• Hindwheel operation acceptable '

e* Manual valvo not subject to spurious actions A5 3446F/JHS

LEQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R

, Prepared by/Date Tf6I 1//o/88 SQN-SQS4-0127 Checaed by/Date _ A?./ ik$v( 2//siff APPENDIX A - KEY l

' Basis for Spur'ious List For Unit 1, Path 1 Item

• Comoonent Basis 1-FCV-70-156 Inadvertent opening of FCV-70-156. valve will open-up 1-VLV-70-545A a major flowpath. This would depress the heat removal l-VLV-70-546A capability of the CCS heat exchanger A and consequently result in inadequate heat removal from 3-tha CCP 1A-A mechanical seal heat exchanger. The heat removal capability of the CCS heat exchanger will not be affected if any of the manual valves, 1-VLV-70-545A or 1-VLV-70-546A are closed.

2- 1-FCV-70-8 ShuriousclosureofthisvalvewillitolateCCSheat exchanger A, thus terminating the heat removal of CCP punp lA-A mechanical seal heat exchanger.

3 1-FCV-70-9 At least one of these valves must remain closed to 1-FCV-70-10 prevent CCS crossover to the 3 Header. The inability to maintain at least one of these valves closed will challenge the ability of the CCS to remove heat from CCP 1A-A, mechanical seal heat exchanger.

4 1-FCV-70-2 Closure of this valve results in same consequence as that for item 2. But it will also prevent cooling of -

the spent fuel pit and thermal barrier booster pumps.

5 ^1-FCV-70-34 This valve must not be closed because it will isolate suction flow to the CCS pump 1B-B. Thus, he'at removal of the CCP pump 1A-A mechanical seal heat exchanger will be terminated snote, provil.ed pump i 1A-A is not operable).

l 1-FCV-70-25 f 6 This valve must nqt close,because it will isolate CCS

• heat exchanger A, and consequently result in the i termination of cooling to the unit i normal loads, [

which includes the CCP mechanical seals and the spent fuel pit.

'7 ,1-FCV-70-64

. - At least one of these valves must remain closed to l-FCV-70-74 prevent flow diversion. Flow diversion would result in inadec ate suction to CCS pumps 1A-A and IB-8, .

thus potential pump damage. Subsequently, heat removal of 1A-A mechanical seal heat exchanger challenged.

I 6 Item number references to simplified flow diagram and also Appendix C.

A6 3446F/JMS l

l-

EQUIPMENT . REQUIRED FOR SAFE SilUTDOWN

.PER 10CFR50 APPENDIX R f)

Prepared by/Date N(l[d#f-[lo/8F Checked bylDate kl bh ! 2//*/fl l

APPENDIX A 8 1-FCV-70-23 At least one of these valves must remain closed to 1-FCV-70-13 . prevent flow diversion. Flow diversion will result in inadequate component cooling flow to CCS A heat exchanger and CCP 1A-A mechanical seal heat exchanger. Thus, potential damage to CCP pump 1A-A.

9 1-FCV,67-146 Both of these valves must remain open to ensure 0-FCV-67-478 adequate heat removal from component cooling system train A equipment. Closure of any one of these valves will result in inability to remove heat from CCP 1A-A.

10 ERCW Supply See spur'ious list in Key 3.

14eaders 2A and IB (loa) 1-FCV-62-98 Spurious closure of any one of these valves may result 1-FCV-62-99 in loss of recirculation flow with subsequent damage to CCP 1A-A.

)

8 m

a A7 3446F/JMS I

n;.- .

. EQUIPMENT REQUIRED FOR ShFE SHUTDOWN PER 10CFR50 APPEND 3X R I

SQN-SQS4-0127-Prepared by/Date #42 z//o/gg Checked by/Date j f / Q ;; ,,,g

't ' e .

> - APPENDIX A C051PONENT COOLING TO CCP 1A-A MECHANICAL SEAL HEAT EXCHANGER l

V D '

~

xb 9

0 4

l' Item numbers which are discussed in the basis for spurious list.

A8 l

3446F/JMS i

l .

[ -

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

PER 10CFR50 APPENDIX R Prepared by/Date Nd [ B//o/gg -

SQN-SQS4-0127 Checked by/Date } } / Q A//gfy?

APPENDIX A - KEY l SPURIOUS LIST FOR UNIT 2, PATH 1

• - 2-FCV-70-156 ) (Note 1) Any one Must Not Open

• • 2-VLV-70-345A)

• • 2-VLV-70-546A) Must be Closed Must be Closed 2-FCV-70-15. (Note 4) -Must Not Close 2-FCV-70-195) (Note 4) Either one Must Not Open 2-FCV-70-196 ) (N'ote 4) 'Must Not Open 2-FCV-70-2 (Note 4) Must Not Close 0-FCV--70-39 (Note 4) (if CCS Pump 2B-B is used) Must Not Close 2-FCV-70-16 (Note 4)

Must Not Close 2-FCV-70-76) (Note 4) Either one Must Not Open 2-FCV-70-78) (Note 4)' Must Not Open l-2-FCV-70-28) (Na a 4) Either one Must Not Open 2-FCV-70-29) (Note 4) Mu;t.Not Open '

2-FCV-70-14) (Note 4) Either one Must Not Open 2-FCV-70-18)-(Note 4) Must Not Open 0-FCV-70-193(hiote2, 14) 0-FCV-70-194 (Note 2, 14) Must Not Open Must Not Open FCV-62-98 (Note 4) 2-FCV-62 (Note 4) Must Not Close Must Not Close

• 2-FCV-67-146 (Reference deviation approval Must Not Close L44 860606 620)

ERCW Header 2A) Either one ERCW Header IB) Must Be Available (See Key 3)

• Handwheel operation acceptable a

• • Manual valve not subject to spurious actions A9 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

.PER 10CFR50 APPENDIX R Prepared by/Date _ Nd [8 Z//o/88 SQN-SQSA-0127 Checked by/Date _ /./. M _ J//#/ff, APPENDIX A - KEY l' Basis for Spurious List For Unit 2. Path 1-Item

• Components Basis 12 2-FCV-70-15 This valve must not close, because it will isolate component cooling sysi9m heat excha iger B. This would terminate heat removal to the centrifugal charging pump B mechanical seel heat exchanger and

- other unit 2 train A supplied equipment.

13 2-FCV-70-195 2-FCV-70-146 At least one of these valves must remain closed to prevent' flow diversion. Flow diversion would challeage the ability of the component cooling heat exchanger B to remove heat from centrifugal charging pump 2A-A mechanical seal heat exchanger and other unit 2 train A supplied equipment.

O 14 p 4'-FCV-70-193 Same as item 13.

p 0-FCV-70-194 7

15 f- 2-FCV-70-2 Same as item 12.

16 2-FCV-70-156 Same as item 13. The heat removal capability of the 2-VI 't- 70-54 5 A CCS heat exchanger 2A1/2A2 will not be affected if 2-VL.-70-546A either manual valve 2-VLV-70-545A or 2-VLV-70-546A are cloJed.

17 FCV-70-28 FCV-70-29 At least one of these valves must remain closed to prevent flow diversion.

Flow diversion would result in inadequate flow through CCS heat exchanger B.

Thus, the ability'to remove' heat from CCP pump 2A-A mechanical seal heat exchanger will be challenged.

l 18 FCV-70-14 Same as item 17.

l FCV-70-18 19 FCV-70-16 Spurious closure of this valve would terminate component cooling flow to CCS heat exchanger B. ,

Thus, cooling of CCP pump mechanical seal heat exchanger 2A-A would be terminated.

• Item number references to simplified flow diagram and Appendix C.

A10 3446F/JMS

~

l e

r

? EQUIPMENT REQUIREL FOR; SAFE SHUTDOWN.

- PER 10CFR50.ArPENDfX R-Prepared by/Date 74?62 2//o/gg.

Checked by/Date f./ & A//o/PY APPENDIX A - KEY l Basis for' Spurious' List

. Unit.2,-Path 1-

. Item Components Basis 1 20f FCV-70-76 FCV-70-78 At 'leaat -one of these valves must remain closed to prevent flow diversion. . Flow diversion could result in potential damage to CCS pumps 2B-B and 2A-A.

9 21 FCV-70-39 If pump 2A-A is the only pump used in supplying

~

required unit 2 loads this valve must not close.

Closure of this valve isolates suction to CCS 2A-A mechanical seal.

22 2-FCV-67-146 . Closure of this valve will isolate CCS heat. exchanger B. ,Thus, cooling of CCP mechanical seal heat exchanger, 2A-A will be challenged.

r. .

22a ERCW Supply See spurious list for Key 3 Header 2A ,

and 1B '

4 4

, 4 4

e 0

All 3446F/JMS

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

EQUIPMENT REQUfRED FOR' SAFE SHUTDOWN

- PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prepared by/Date kd t//o/gp Checked by/Date ) . / - W ,2 / fof p f 3 .-

APPENDIX A UNIT 2 KEY 1 COMPONENT COOLING TO CCP MECHANICAL SEAL

. HEAT EXCHANGER 2A-A

,9> -

O e

e e

04 e

l l l

l-(

I A12 3446F/JMS l'<-

l

-m-.e-we.,e ...,m.y e ,..

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prepared by/Date M d [ 4//o/gg Checked by/Date ), / /R1 2)/o/fr APPENDIX A - KEY l Spurious List for Units 1 and 2, Path 2

,If Path 2 is used, then the following spurious actions must be prevented:

Units 1 and 2 0-FCV-70-12 (Note 4) Must Not Close FCV-70-3 (Note 4) Must Not Close 1-FCV-70-9) (Note 4) Either one Mus t Not Opett 1-FCV-70-10) (Note 4) Must Not Open 2-FCV-70-195) (Note 4) Either one Must Not Open 2-FCV-70-196) (Note 4) Must Not Open FCV-70-75 (Note 4) Must Not Close 1-FCV-70-64) (Note 4) Either one Must Not Open 1-FCV-70-74) (Note 4) Must Not Open 1-FCV-70-26) (Note 4) Either one Must Not Open 1-FCV-70-27) (Note 4)' Must Not Open 1-FCV-70-13) ($ote 4) Either one Must Not Open 1-FCV-70-23) (Note 4) Must Not Open 2-FCV-70-76) (Note 4) Either one Must Not Open 2-FCV-70-78) (Note 4) Must Not Open 2-FCV-70-28) (Note 4) Either one Must Not Open 2-FCV-70-29) (Note 4) Must Not Open 2-FCV-70-14) (Note 4) Either one Must Not Open 2-FCV-70-18) (Note 4) _, Must Not Open 0-FCV- 70-22 (Note 4) Must Not Close

• • • 0-FCV-6 7-L51) Eithe r One Must Not Close

• • 0-FCV-67-152)

ERCW Header.2B) Either One ERCW Header IA)

Must Be Available (See Key 3)

FCV-70-153 (Note 3) Any one Must Not Open

• VLV-70-545B Must be Closed

• VLV-70-546B Must be Closed

j.

• Manual valves not subject to spurious actions l

l ** Handwheel operation acceptable 1

• • • Power has been removed to 0 FCV 67 151 handwheet operation acceptable A13 3446F/JMS Y

EQUIPMENT REQUIRED FOR-SAFE SH TDOWN PER 10CFR50 APPENDIX R .

Prepared by/Date Nd. E//c/st

.SQN-SQS4-0127' Checked by/Date : M/ /W .2//a//f APPENDIX A - KEY l Basis'for Spurious List Units 1 and 2, Path 2 Item Component (s) Basis 23 1-FCV-70-64 At-least one of these valves must remain closed 1-FCV-70 to prevent flow diversion. Flow diversion could result.in potential damage to C-S CCS pump. Thus, this would challenge ab3.lity of CCS HTX C to remove heat from 1B-B-and 2B-B mechanical seal heat exchangers.

24 FCV-70-76 Same as item 23 FCV-70-78 25 FCV-70-26 At least one of these valves must remain closed FCV-70-27 to prevent flow diversion. Flow diversion would result in inadequate flow volume through CCS Heat Exchanger C. Thus, the ability to remove heat from CCP IB-B, 2B-B mechanical seal heat exchangers, spent fuel pit, and other train B required loads would be challenged. .

26 ,FCV-7 -28 Same as item 25-

~FCV-70-29 27 FCV-70-22 Spurious closure of~this valve would isolate component cooling flow to CCS HTX C. This would terminate CCS heat removal of train B equipment, for both its 1 & 2, 28 FCV-70-23 Same as item 25 FCV-70-13 29 FCV-70-14 Same as item 25 _,

FCV-70-18 30 FCV-70-12 Spurious closure of this valve would terminate cooling flow to CCP mechanical seal heat exchangers 1B-B, 2B-B and other train B supplied components.

Also, potential damage to heat exchanger tubes may

. occur.

' A14 i-3446F/JMS 0

7 EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date 77d // - ' 2//o/8f r

Checked by/Date Af & ,2)/ospy APPENDIX A 31 FCV-70-9 At least one of these valves nust remain closed FCV-70-10 to prevent flow diversion. Flow diversion would challenge ability of components cooling system.

to remove heat from 1B-B centrifugal charging pump mechanical seal heat exchanger.

'32 FCV-70-195 Same as item 31, except that, the ability to FCV-70-196 remove heat from 2B-B mechanical seal heat r

' - exchanger and other train B Header-2B loads-would be challenged.

33 1-FCV-70-3 Spurious closure of this valve would isolate component cooling flow to CCP IB-B seal heat exchanger.

34- 2-FCV-70-3 Same as item 33, but. terminate cooling flow to CCP 2B-B mechanical seal heat exchanger.

35 FCV-67-151 At least one of these valves must be open FCV-67-152 to prevent isolation of ERCW flow.through the

,C-CCS heat exchanger. - .

36 1-FCV-70-153 Spurious actuation of these valves will result in 2-FCV-70-153 flow diversion. Flow diversion would result in inadequate flow to the B CCP mechanical seal heat exchangers.

37 1-FCV-70-75 Closure of these valves will isolate flow from 2-FCV-70-75 tne train B CCP mechanical seal heat exchangers.

ERCW Header 2B See Key 3.

ERCW Header lA e

i A15 3446F/JMS l

-em

~ EQUIPMENT. REQUIRED FOR SAFE SHUTD0!'N

.PER 10CFR50 APPENDIX R .

Prepared by/Date N d. [, E//o/81 SQN-SQS4-0127 Checked by/Date k. / $ U A / /p g y _

APPENDIX'A:

UNITS'1 & 2, (KEY 1).

-Component Cooling to CCP Mechanical' Seal-lleat Exchangers 1B-B and.2B-B

. 4'v> .

4 e/

e '

l..  : .

e S

A16 3446F/JMS G

e

• EQUIIMF.Nr REQUIRED FOR SAFE SHUIDOWN '

-PER 10CFR50 APPEND 8X R

_SQN-SQS4-0127 Prepared by/Date Nd. [Id 2//4/f8 Checked by/Date /,/ [ds.2 J//#/ff APPENDIX'A SEQUOYAH NUCLEAR PlJuNT KEY 1 (Notes)

Note 1:

If this valve snuriously opens, component cooling water pumps 2A-A and 2B-B both must be operable or spent fuel pit cooling via CCS

. heat exchanger B must be isolated if manual. valves 2-545A or 2-546A are not closed. If the comp 6nent cooling water system temperature exceeds the system limits, soma of the larger non-safety loads (such as the gas stripper and boric acid evaporator package) must be isolated.

~

Note 2:

If both of these valves open, component cooling water pumps 2A-A and 2B-B both.must be operable.

Note-3:

Either the unit i valve or the unit 2 valve may spuriously open without acceptable.

affecting this path's operability. Manual isolation is Note 4:

A design change has been made under ECN-L6258 to remove power from this valve. .

Note 5:

A design change'has been made under ECN-L6258 to remove control air from this valve. Valve fails in the open position.

Note 6:

A design change has been made under ECN-L6258 to open this valve and remove power from it.

Note 7:

A design change has been made under ECN-L6258 to close this valve and remove power from it.

Note 8:

If CCS pump B-B is used, equipment associated with supplying B-train power will have to be evaluated.

Note 9:

If neither 0-FCV-70-197 nor 0-FCV-70-198 close, component cooling water pumps lA-A and 1B-B both must be opcrable.

Not'e 10: _CCS pump 1B-B or 2B-B can be used as a substitute if the appropriate valves are realigned. If needed, the possible valve realignments can be provided.

Note 11:

If this valve spuriously opens, component cooling water pumps IA-A and IB-B both must be operable or spent fuel pit cooling via CCS ,

heat exchanger A must be isolated if manual valves 1-545A or l-546A are not closed. If the component cooling water system temperature exceeds the system operating limits, some of the larger non-safety loads (such as the gas stripper and boric acid evaporator package) 1 must be isolated.

A17 3446F/JMS l

EQUIPMENT-REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date _ N d [ E//d/tf SQN-SQS4-0127 Checked by/Date A /. /D 2)/0/77 <

APPENDIX A I' Note 12: The lube oil pump must be operable or the handswitch (HS-62-1-4M) bypassing the oil pump must be used for the CCF start.

Note 13: Fan will start on high room temperature or pun.p start signal.

Note 14: If neither valve can be protected from spuriously opening and the requirements of note 9 (for key 1, path 1) and the requirements of note 3 (for key 1, unit 2) cannot be met, then the following must be accomplished.

• FCV-70-40~ Must close

• FCV-70-ll Any one Must close

• 0-70-529A _ Must be closed

• FCV-70 Any one Must close

• FCV-70-1 Must close

• 0-70-529B Must be closed OR

• I l-70-531 ] Must be closed

• Handwheel operation is acc'eptable for these valves.

Note 15: If these valves close an alternate path to cool the spent fuel pool must be initiated prior to pool boiling (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is the minimum time for boiling at maximum heat load conditions). Spent fuel pool

. cooling is not addressed further in this documentg A

skee, it b not regi,J bg PP"b t

A18 3446F/JMS e

• ii . EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

-PER 10CFR50 APPENDfX R SQN-SQS4-0127.

Checked by/Date A. /. M - Affo/ 77 SEQUOYAH NUCLEAR PIANT KEY 2 CHARGING FLOW CONTROL VALVE AND BYPASSES This key establishes the flow through the normal charging path. It requires that one of three valves in the discharge piping from the Centrifugal charging flow and sealpumps be open to provide the first portion of the normal charging injection.- This key's components are required if the normal charging flowpath is used for RCS makeup (see Key 34 for alignment) and/or if RCP seal injection is used to maintain RCP seal integrity and/or RCS make-up.

There are no spurious actuations associated with this key. If credit is being taken for RCP seal injection as the method for RCS make-up on Figure 1, an injection flow rate of 34 gpm is required to support a cooldown rate of 25'F/ hour. The cooldown rate will vary with the injection rate.

Instrument Loop F-62-93 Must Operate FCV-62-93 Any set Control Air Must Ee Open Opersfc ##' # #~" '

Must Be Available'

• VLV-62-534 Must Be Opened

• VLV-62-533 _

Must Be Closed

• VLV-62-526__

Must Be Opened

• VLV-62-522. Must Be Closed

. Instrument Loop L-68-320' Any One Must Operate Instrument Loop L-68-335 Must Operate Instrument Loop L-68-339_ Must Operate f

- cHandwheel operated valves.

N We f

9 t

t l

i

~ A19 3446F/JMS 1

e

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Dato' N d M Z//d/M SQN-SQS4-0127

• ', , Checked by/Date M / b J//a/ff

<- 85CUOYAHNUCLEARPLANT I XEY 2 -

CHARGING FLOW CCNTROL. VALVE AND BYPASSES Close Open diese Open-

'VLV-62-533 'VLV-62-534 "VLV-62-527 'VLV-62-526 M.-

l . .

q . -

opera Qp M&

FCV-6/ 3 tr Spl@

Control Air to Charging Flow FCV-62-93 instruments t

Available

, i 1

ANO yv yy .

AND -

AND I

- y+__ c CR e

KEY 2 s

• Handwheel-operated Valves 47520 .

- - ~ -..'i.,.k d 'te L s.,. '. . .: .,'.. .. ...%"2A:i.! s -

. je EQUIPMENT: REQUIRED FOR SAFE SHUTDOWN i

PER 10CFR50 APPENDIX R Prepared by/Date Nddb 2//0/81 SQN-SQS4-0127 ,

Checked by/Date #./. 4 %./ J//v///

4 SEQUOYAH NUCLEAR PLANT $

KEY 3 ERCW COOLING This key contains th'e main line equipment necessary to supply ERCW cooling

- water for those functions on the shutdown logic diagram which require it for cperation. .The normal cooling water supply to the CCS heat exchangers A, B, snd C shall be f rom' ERCW headers 2A, 2A and 2B respectively. The piping system.is set up such that alternate alignment is permitted to those heat sxchangers from headers 18, 1B and 1A respectively. Additional ERCW system ,

components are contained with keys 1, 9, 13, 19, 3 7 and 40.

A This key is' organized by header, lA, 2A, 1B, 2B, The'section for each header consist of (1) a functional logic diagram, (2) a tabulation of features which '

I must operate,- (3) a tabulation.of spurious actuations which must be prevented.. -

t (4) basis for spurious actuate items, and (5) simplified flow sketches of the header.

O 9

e 4

b.

I l  :

L-Y

, A21 3446F/JMS 4

I-

. . , . - . . - - , ....u,, . .. v w v .. . .

l PER 10CFR50 APPENDIX R f)

Prepared by/Dato 7T d [// e J'E//o/td~ l SQN-SQS4-0127 ,

Checked by/Date _ f./ W DRs/Pt .

SEQUOYAH NUCLEAR PLA?fr -

KEY 3 * ~~

ERC.J COOLING HEADER 1A ' ,.

Screen Wash Traveling ,

Pumps Screen ..

A-A AND D-A , A-A AND D-A ,

g . .

f .

i .

l ERCW 1-FCV-67-81 Pumps 1-FCV-67-147 J-A OR K-A 1-FCV-67-492

[ - - - -

pg ., .. ERCW Strainer . . . . _1-FCV-67-491A j " A 1 A - 4:- 1-FCV-67-66

.- - R-A Og Q-A -

., 2-FCV-67-66 i ', ~ '

l.

. ._s . .. . .

g.. ,

N V N# Np y, i

AND .. ,

hr l

l ERCW

l. Cooling I

Header 1A ,

I ,

~

,. A22 DNEr.-47 52q-08/ 31/ 87 t

r_

EQUIPMENT REQUIRED FOR SAFE SilUTDOWN PER 10CFR50 APPENDIX R Pcepared by/Date Y d.[ '

8l'*l88 SQN-SQS4-0127 Checked by/Date // M J//agY KEY 3 - ERCW llEADER 1A I ERCW Header IA (operation list)

ERCW Pump J-A) Either One ERCW Pump K-A)

Must Operate Must Operate-

~ SCREEN WASH PUMP A-A Must Operate TRAVELING SCREEN A-A**

Must Operate

'ERCW Pump Q-A) Either One ERCW Pump R-A)

Must Operate Must Operate  ;

SCREEN WASH PUMP D-A Must Operate Traveling Screen D-A**

Must Operate ERCW Strainer A1A-A Must Operate 1-FCV-67-491A (Strainer Flush) Must be Operable 1-FCV-67-66 (Diesel Cooling) .

Must be Operable .

2-FCV-67-66 (Diesel Cooling) Must be Operable

• • Screens to be visually inspected and manually backwashed per SOI-67.1

.ERCW Header 1A (Spurious List)

' '*1-FCV-67-81 (lA Header Isolation)

• l-FCV-67-147 Must Not Close p.

(lA/2A Header X-tie) Must Not Open-

• 1-FCV-67-492 (Strainer A1A-A Inlet) Must Not Close 1-FCV-67-125 (Note 1) (CS HX Isolation) Either One Must Not Open 1-FCV-67-126 (Note 1) (CS HX. Isolation) Must Not Open

• 1-FCV-67-127' (Vital HVAC)

Q*1-FCV-67-168 Must Not Close (Vital HVAC) ~ Must Not Close 1-FCV-67-491D. Strainer Flush)" Must Not Open

• 0-FCV-67-12 (Discharge Header Isolation)

• 0-FCV-67-364 Must Not Close (Discharge Header Isolation) Must Not Close

• Power has been removed per ECN L6258 C* Control air has been removed; valve to remain permanently open.

A23 3446F/JMS l

l

r EQUIPMENT REQUIRED FOR SAFE SHUIDOWN PER 10CFR50 APPENDIX R SQN-SQS4 0127 Prepared by/Date Wd[ z/gofgg Checked by/Date _ A /. $4d 9//0fff Basis for ERCW Header 1A'Sourious List Item Component Basis 133 1-FCV-67-66 2-FCV-67-66 Spurious c).osure of these valves will terminate ERCW cooling to diesel generators 134 1-FCV-67-125 1-FCV-67-126 At least one of these valves must remain closed to prevent partial flow diversion.

Thus, depending on the loads the heat removal of the A CCS heat exchanger will be challenged.

135 'l-FCV-67-127

. Closure of this va'1ve will terminate flow to the 1A centrifugal charging pump room and oil coolers,the RHR 1A pump room cooler and the service air compressor. (See keys 1, 13 and 40).

137 1-FCV-67-491A Improper operation of this. valve may prevent effective operation of A1A-A strainer.

138 1-FCV-67-491D Spurious opening of this valve will divert ,

a portion of the header 1A cooling water supply from the CCS A heat exchanger.

Consequently, the heat removal capability of the A CCS heat exchanger may be challenged.

139 0-FCV-67-12 These are train A ERCW discharge header 0-FCV-67-364 valves. Their closure will result in the loss of the ultimate heat sink and consequently inoperable. result in ERCW train A being 1-FCV-67-168 CCProomcoolerAsIpplycontrolvalve.

Power has-been disconnected to.this valve.

I A24 34467/3ng i.

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.'. ; EQUIPMENT REQUIRED FOR- SAFE SHUTNWN PER'10CFR50 APPENDIX R

.Nd[

~ Prepared by/Date Z//0/33 .

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Checked by/Dat'e /,/ & p//agf.

\

KEY 3 ERCW COOLING HEADER'1A d

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. A25 3446F/JMS G

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EQUIPMENT REQUIRED FOR SAFE SilUTDOWN PER 10CFR50 APPENDIX R Prepared by/Dato 7?d./2~/e 3//o/83 Checked by/Date . ,/. /d.4 J//e/f7

. SEQUOYAH NUCLEAR PLMIT .

, KEY 3 .

ERCW CCOLING HEADER 2A Screen .

Wash . Traveling Screen .-

Pumps A-A AND D-A .- A"A AND D-A , ,

. _ . 1 .

. c.

A* W F C'; L 7 ' S tlW(( _.2 ---~,p c=j -; 7 -- 5 3 -

ERCW ' ' ".',_ 1"'-. " ' .

n - - -

"' de 4 WW

. Pumps , , _ -~. ,. w ., hd (

'J-A O__S K-A ERCW Strainer

.A2A-A . 1- M - W-223 l ,- AND ~

2-FCV-67 ~~ 993 R-A QR O-A .

2-FCV-81 .

- ' . 2-FCV-492 , ,

2-FCV-491A '

._m.... ._. . ..

lt

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1 i . .-

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EQ'JIPMENT REQUIRED ~FOR SAFE SHUTDOWN

'PER 10CFR50 APPENDIX R Prepared'by/Date N 41 8 z//o/gg SQN-SQS4-0127

.. Checked by/Date _ A. / $U A//oppy KEY 3 ERCW HEADER 2A ERCW Header 2A (operation list) i ERCW Pump J-A) Either One ERCW Pump K-A) Must Operate Must Operate SCREEN WASH PUMP A-A r

Must Operate Traveling Screen A-A*

Must Operate ERCW Purp Q-A) Either One ERCW Pump R-A) Must Operate Must Operate SCREEN WASH PUMP D-A*'"

Must Operate Traveling Screen D-A Must Operate BRCW Strainer A2A-A Must Operate 2-FCV-67-491A (Strainer Flush) Must be Operable

• Screens to be visually inspec'ted and manually backwashed per SOI-67.1 .

ERCW Header 2A [ Spurious List)

• 2-FCV-67-81 (2A Header Isolation)

*1-FCV-67-223 (2A/1B X-tie) Must not close

• 2-FCV-67-223 (2A/1B X-tie) Must not close

, *2-FCV-67-492 Must not close (Strainer A2A-A Inlet) Must not close 2-FCV-67-125 (CS HX Isolation) Either One Must Not Open 2-FCV-67-126 (CS HX Isolation) Must Not Open 2-FCV-67-491D (Strainer Flush) Must Not Open

• 2-FCV-67-127 (Vital HVAC)

• • 2-FCV-67-168 (Vital HVAC) Must Not Close

• 0-FCV-67-12 (Discharge Header Isolation) Must Not Close

• 0-FCV-67-364 (Discharge Header Isolation) ~' Must Not Close Must Not Close Note': Alternate alignment available from ERCW Header IB

• Power has been removed per ECN L6258.

• • Control air has been removed; valve to remain permanently open

, A27 3446F/JMS

(

. EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER-10CFR50 APPENDIX R

_ _ Prepared by/Date Mt2. z/fe/gg Checked by/Date f././4 4 s//o/7/

' Basis for ERCW Header 2A Spurious List Item Co'mponent Basis 37 1&2-FCV-67-223 Spurious closure of these valves will interrupt cooling of CCS Heat Exchanger A & B. Depending on loads, potential heat exchanger tube damage.

38 2-FCV-67-168-Spurious closure of these valves will terminate ERCW flow to CCP 2A-A room cooler.

39 2-FCV-67-492 Spurious closure of this valve will isolate ERCW Header 2A-A. Thus, the CCS heat exchangers will lose its heat removal capability and subsequently cause damage to CCP A-A.

40 2-FCV-67-81 Same as item 39.

41 2-FCV-67-125 2-FCV-67-126 At least one of these valves must remain closed to prevent ERCW flow diversion. Depending on the load, inadequate heat removal of A and B heat exchangers may occur. .

42 0-FCV-67-364 0-FCV-67-12 These are train A ERCW header valves, their closure will result in the loss'of the ultimate heat sink and subsequently cause ERCW train A to become inoperable.

, 43 2 'CV-67-491D Spurious opening of this valve will divert a portion of the normal cooling water supply for the CCS Heat Exchangers A and B to the ultimate heat sink.

Consequently, the heat removal capability of the CCS Heat Exchanger will be challenged.

140 .2-FCV-67-491A Improper operation of this valve may prevent effective operation of strainer A2A-A1.

141 2-FCV-67-127 Closure of this valve will terminate flow to the 2A centrifugal charging pump room and oil coolers and the RHR 2A pump room cooler. (See keys 1 and 40.)

i

. A28 3446F/JMS l

EQUIPMENT REQUIRED FOR SAFE' SHUTDOWN 4

PER 10CFR50 APPENDIX R SQNESQS4-0127 Prepared by/Date' N d z//o/gg ,,

Checked by/Date / / W a,po,y

^ '

KEY 3 .

ERCW COOLING HEADER 2A

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A29 i 3446F/JMS 9

.v * * ~ u ac.yvint.U r0R SAFE SHUIDOWN PER 10CFR50 APPENDIX R  !

SQN-SQS4-0127 ExtPared by/Dato S A ( Y Lfio/sg ChecM 71/Date AA 44 4 2//o/99

-SEQUOYAH NDCLD.1L PIRf2

~

EET 3

.,.!,:?.($'*

' ERC'J CCOLING 2E.1DEit '1B

/.ivf.%gg?; .

1 Screen Traveling-Wash ,

Pumps Screen - - -

B-B AND C-B B-B AND C-B - - - -

.) p h , , , ,. . -

[, , ,

"' 1 *> .fr/- 67-B2 4

ERCN

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l gl',.iECV-67-223 gg7_yg

. , Pumps '

• i ,,1 N-B Q,R.P-B l U<C# memi.ner ib5C7-67-424 b._ l .i -

agqng_37 4g9 AND_ - 31EHB "

f-tTCW-67-490A y j,- . -

L-B DE.M-B fried 5-67-67 2.17ev-67-67

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EQU1PHENT REQUIRED FOR SAFE SHUTDOWN

.PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prepared by/Date N d 2//o/Ff Checked by/Date A,/ N / J//o/PT KEY 3 - ERCW Header 1B ERCW Header IB Operation List ERCW Pump L-B) Either One ERCW Pump M-B) Must Operate Must Operate

-SCREEN WASH PUMP B-B Must Operate Traveling Screen B-B*

Must' Operate ERCW Pump N-B) Either One ERCW Pump P-B) Must Operate Must Operate SCREEN WASH PUMP C-B '

Must Operate Traveling Screen-C-B*

Must Operate ERCW Strainer B1B-B .

Must Operate 1-FCV-67-490A'(Strainer Flush) Must be Operable 1-FCV-6 7-6 7 (Diesel Cooling) Must be Operable '

2-FCV-6 7-6 7 (Diesel Cooling) Must be Operable ,

• Screens to be visually inspected and manually backwashed per SOI-67.1 ERCW Header 1B Spurious Lly,t

• 1-FCV-6 7-82 (Meader Isolation) Must Not Close

• 1-FCV-67-424,(Supply to CCS MX) Must Open i

• 1-FCV-67-223 (IB/2A X-tie) Must Not Close

• 2-FCV-67-223 (IB/2A X-tic) Must Not Close

• 1-FCV-67-489 (Strainer Inlet) " '

Must Not Close t

1-FCV-6 7-123 (CS MX) Either One Must Not Open 3 1-FCV-67-124 (CS RX) Must Not Open 1-FCV-67-490D (Strainer Flush) Must Not Open

• 1-FCV-67-128 (Vital MVAC) Must Not close C*1-FCV-67-170 (Vital MVAC) Must Not Close

• 0-FCV-67-14 (Discharge Meader Isolation) Must Not Closo

• 0-FCV-67-365 (Discharge Header Isolation) Must Not close

• Power has been removed per ECN L6258. I s

Q* Control air has been removed; valve to remain permanently open. t

. i A31 3446F/JMS e

V EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

-PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prepared by/Date y?dZ 8/k Z//e/tt Checked by/Date f./ & 2//o/77 ERCW Spurious List Header IB Item Component Basis 45 1-FCV-67-489 Spuricus closure of this valve will isolate header 1B of ERCW flow.

46 1-FCV-67-82 Same as item 45 47 1-FCV-67-123 1-FCV-67-124 Same as item 58 but flow diversion through containment spray heat exchanger IB.

48 1-FCV-67-490D Same as item 52 49- 1-FCV-67-424 If header 1B is aligned to provide the cooling requirements of header 2A, the spurious closure of this valve would defeat this purpose. Thus, ERCW cooling to CCS A 2Al and 2A2 heat exchangers would be terminated as well~as other header 2A dependent components.

50 1-FCV-67-223 2-FCV-67-223 Header 1B,is the alternate header to the normal' supply header 2A.

If this header is utilized and 1-FCV-67-424 is

• open, the spurious closure of any one:of these valves will itolate ERCW cooling flow to the 2Al and 2A2 heat exchangers and other components requiring header 2A.

51 0-FCV-67-14 0-FCV-67-365 Spurious closure of any one of these valves will isolate the ultimate heat sink for the CCS heat exchangers and various unit 1 and 2 ESF loads.

142 1&2-FCV-67-67 Spurious closure of these valves will terminate ERCW flow to the diesel generators.

143 1-FCV-67-490A Improper operation of this valve may prevent ef fective operation of strainer BlB. -. -.

144 1-FCV-67-128 Closure of this salva will terminate flow to the station air compressor'lB, auxiliary room space cooler, and RHR 1B pump room cooler (see keys 13 and 40).

i A32 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 AlPENDIX R M

Prepared by/Date Nd2 [/I - FZ//o/ft ,

Checked by/Date _ / l N A//e/ft SEQUOYAH NUCLEAR PLANT KEY 3 ERCW COOLING HEADER 1B

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Item numbers which are discussed in the basis for spurious list.

A33 3446F/JMS e

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'PER 10CFR50 APPENDIX R Prepared by/Dats 7&d. W3//e/tg '

SQN-SQS4-0127 r e ked by/Date A.U. dd L A//o/f!

.~ N

, SEQUOYAR litiCLEAR PLA!Tr

. KEY 3 -

~- ERCJ HEADER 2B

. . ~ ' . I

• Screen Wash Traveling -

Pumps Screens -

E-B P,.EQ C-B C-B-AND-B-B. +

I

,g, Q4

.. . . z. .

f 2-FCV-67-82

-- 2-FCV-67-14 ERCW -- - - -

mps 2-FCV--67-48 1 ERCW Strainer 2-FCV.67-490A N-B OE P-B.

- . -~- - - -

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C00 Lit:G HEADER 2B . ,

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. A34 DilE4-47 52q-03/31/ 87

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

• PER 10CFR50 APPENDIX R Preparsd by/Date Nt2. 2/ro/gg SQN-SQS4-0127' Checked by/Date _ A. / & 2/#1pP KEY 3 - ERCW HEADER 2B (Alternat. alignment available from ERCW Header IA)

ERCW Header 2B (operation list)

ERCW Pump L-B) Either One Must Operate ERCW Pump M-B)

Must Operate l

SCREEN WASH PUMP B-B Must Operate Traveling Screen B-B* Must Operate ERCW Pump N-B) Either One Must Operate ERCW Pump P-B).. Must Operate l

SCREEN WASH PUMP C-B Must Operate l Traveling Screen C-B* Must Operate ERCW Strainer B2F,-B Must Operate 2-FCV-67-490A (Strainer Flush) Must be Operable

• Screens to be. visually inspected and manually backwashed.per SOI-67.1.

ERCW Header 2B Spurious List

• 1&2-FCV-67-82 (Header Isolation) Must Not Close

, *2-FCV-67-147 (1A/2B X-tie) Must Not Close

• 2-FCV-67-489 (Strainer Inlet) Must Not Close 2-FCV-67-123 (CS HX) Either One '4ust Not Open 2-FCV-67-124 (CS HX) Must Vot Open

• 2-FCV-67-128 (Vital HVAC) Must Not Close

• • 2-FCV-67-170 (Vital HVAC) Must No Close 2-FCV-67-490D (Strainer Flush) Must Not Open

• 0-FCV-67-14 (Discharge Header Isolativn) ,, _, .Must.Not Olose

• 0-FCV-67-365 (Discharge Header Isolation) Must Not Close

l.

• Power has been removed per ECN LGA58.

• • Control air has been removed; valve !s permanently open A35 3446F/JMS

-EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prspared by/Date N o. 2/10/88

$CN-SQS4-0127-Checked by/Date _/./ M .t Nv/rP Basis for ERCW Header 2B Spurious List Item Component Basis

,52 2-FCV-67-490D Spurious opening of this valve would divert a portion of

- the normal ERCW cooling supply for CCS heat exchunger C-S to the ultimate heat sink. Consequently, the heat removal capability of the CCS heat exchanger C would be challenged.

53- '2-FCV-67-489 When path 2 of key 1 is used this valve must not close.

Spurious closure of this valve will isolate the normal ERCW supply header flow to CCS heat exchanger C.

54 2-FCV-67-82 Same as item 53 55- 2-FCV-67-147 Spurious closure of this valve will terminate ERCW cooling to CCS C heat exchanger.

56 FCV-67-14 Spurious closure of this valve will isolate ERCW flow from the C CCS heat exchanger. Thus heat removal of CCP mechanical sesi hest axchangers 2B-B and 1B-B will be terminated. '

57 0-FCV-67-365 Same as 54 above .

58 2-FCV-67-123 If one of these valves fails to remain closed 2-FCV-67-124 then flow diversion would follow path through 2B containment spray heat exchanger.

59 2-FCV-67-170 See Key 1 Operation list.

148. 2-FCV-67-128 Spurious closure of this valve will terminate ERCW cooling to aux control air compressor, CCP room cooler, CCP oil cooler and RHR room cooler (see Keys 1, 13 and 40).

149 2-FCV-67-170 Spurious closure terminates ERCW cooling to 2B CCP. room cooler (see Key 1).

t I

l A36 3446F/JMS

EQUIPMENT. REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R

- SQN-SQS4-0127_ Prepared by/Date _'Nt2 2"gf _ 82//d/ft Checked by/Date f,f gg , ,,,,m 151 2-FCV-67-490A Improper operation of this valve may cause strainer B2B-B to function effectively.

_ Note 1:

The ERCW headers spurious lists contain the containment spray (CS) heat exchangers isolation valves (l&2-FCV-67-123. -124, -125, -126). Per the spurious lists, these valves are required to stay closed, isolating flow through all CS heat exchangers. It is acceptable, however, for one CS heat exchanger (per path used) to have cooling flow (i.e., CS heat exchanger lA can have flow through it provided heat exchanger 2A is isolated. The same is true for Train B).

-?

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8 4

3

• = es l

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l A37 l 3446F/JMS l

l L

lPER 10CFR50' APPENDIX REQUIPMENT: REQUIRED FOR SA

- SQN-SQS4-0127 Prepared by/Dete Nd /Mz//o/ts Checked by/Date _ f./ W ;tjioppy

.ERCW HEADER 2B

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l

. A38 i

3446F/JMS i .

I

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

'PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prspared by/Date Nd[ Z//o/#3 Checked by/Date / / [d/ J/#/fP SEQUOYAH NUCLEAR PLANT KEY 4 Volume Control Tank Suction This short key requires that the volume control tank (VCT) be aligned to provide a term water source for RCS makeup and for RCP seal injection. The VCT is suitable only as the short term water source. However, the VCT discharge valves are normally open. Therefore, this source is immediately available.

This source is required only until suction from the RWST (key 5) is provided.

Until this time both isolation valves must be prevented from spuriously closing.

When the RWST is aligned to provide pump suction (through LCV-62-135 or LCV-62-136),.then the VCT must be isolated or depressurized within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to prevent the hydrogen"cover gas from entering the charging line (reference NEB 841022 220).

If the alternate path is used for _ligning the RWST for CCP suction (key 5, path 2), then the VCT must be isolated or depressurized immediately (reference NEB 841022 220).

(Ope. ration and Spurious List) '

• LCV-62-132 Either One Must Not Close

• LCV-62-133 Until Key 5 Has Been Established Both Must Not Open After Key 5 Has Been Established Level Control Loop 62-129A (for LS-62-129B) Must Not Cause the and Loop 62-130A (for LS-62-130B)

Closure of LCV-62-132 or -133 Until Key 5 Has Been Established

~

• • Level Control Loop 62 129A (for LI-62-129) Must Operate

• Short term water source. In the event of a fire in an area that will affect these valves or associated circuitry, the operator should remove power f rom both valves (open brenkers at MOV board) or switch over to the RWST.

• • In the event of a fire, the VCT level indication should be closely .-

monitored. If the indication does not function properly (i.e., if 07. or .

1007 level is indicated or erratic level indication occurs), the operator should immediately switch over to the RWST or promptly stop the operating centrifugal charging pump (s) until the RWST can be aligned.

A39 3446F/JMS

l 4 EQUIPMENT REQUIRED FOR' SAFE SHUTDOWN PER.10CFR50 APPENDIX R SQN-SQS44127- Prepared by/Date 8 4. N N #E//o/st Checked by/Date f,/, fAL) .yjpojyy .

Basis for Key 4 Spurious List Item Component

, Basis 60 LCV-62-132

'LCV-62-133 Spurious closure of any one of these valves prior to establishment of suction from the RWST could result in the loss of suction to the CCP.

Spurious opening of both of these valves after Key 5 has been established could cause hydrogen binding of the CCPs.

E e

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\

T l'

I e

90 A40 3446F/JMS O

v

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

.PER 10CFR50 APPENDIX R Prepared by/Date N 42 4//0/f8 SQN-SQS4-0127 Checked by/Date f./ W .tno/ff SEQUOYAH NUCLEAR PLANT Ney 5 RWST SUCTION The long-term water source for RCS makeup and RCP seal injection (if used) is the RWST. It may be aligned by op'ening either FCV-62-135 or FCV-62-136.

The VCT will continue to supply makeup water for a sufficient time after letdown lines are isolated that credit may be taken for handwheel operution of these valves. These valves, however, are not adequately separated, and one postulated fire may render both valves incperable. Therefore, an alternate path is provided through the inlet pfping for 'the SI pumps and back to the inlet to the CCPs. If't.his flowpath is used, one of two inline valves.

FCV-63-6 or FCV-63-7 and FCV-63-5 and -47, must be opened. Sufficient NPSH is provided for the CCPs based upon the EN DES Calculation NEB 841022 220.

. This key also identifies the equipment whose spurious operation would divert flow from the RCS makeup flow path. This includes preventing the containment spray and RHR spray systems from actuating.

O 9

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A41 3446F/JMS

c, - ;

o

_ EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date N 6l r//o/tg -

-SQN-SQS4-0127 Checked by/Date' $ A & Alto /7J' SEQUOYAH NUCLEAR PIANT KEY 5 (Operation List)

-Fath 1

' *LCV-62-135) ---Either one Must open to access the RWST

• LCV-6 2-136 ) and not spuriously close

• LCV-62-132) -- Either one. Must close to isolate the VCT

• LCV-62-133)

_ OR

• LCV-62-135) -- Either one Must open to access the RWST

• LCV-6 2-136 ).

PCV-62-119 Must not fail to open to prevent over-pressurization PCV-62-120 of the VCT

• VLV-62-692I --- Bo t h

• VLV-62-693 Must be cic.ad to isolate VCT from nitrogen and hydrogen supply headers FSV-62-125" Must be opened within 24 hrs -

PCV-62-126 --- All i to depressurize the VCT PCV-77-89__ OR- .

, VLV-6 2-68 9"_j

-, Note: For' Path 1, if LCV-62-132 or LCV-62-133 are not closed or if the VCT-pressure is greater than 17.03 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 15.91 psig in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, or 12.56 psig in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then'the RHR system must be available, the RCS temperature below 2000F, and the CCP stopped.

(This note not applicable to Path 2.)

Path 2

• FCV-6 3-6 ) - ,

OR- i I .

• FCV-6 3-7 ) -

AND

• FCV-63-47 Must open and not spuriously I

• FCV-6 3-5 close (CCP suction from SIS)

• LCV-62-132) Either one Must close to isolate the VCT

• LCV-6 2-133 )

• Handwheel operation acceptable. Handwheel operation must be used to close LEV-62-132 or LCV-62-133 if power has been removed f rom them (see Key 4).

i A42 3446F/JMS I

l l

I

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

.PER'10CFR50' APPENDIX R Prepared by/Date '842. [ Z//d/ff

~SQN-SQS4-0127-Checked by/Date _/./ M .2//a/rP SEQUOYAH NUCLEAR PLANT KEY 5 (Spurious List)

Associated with both Path 1 and Path 2 Associated with Path 2

~

FCV-62-5 Must not close FCV-63 Must not close

,s If RHR pump A-A starts due tu a spurious ESFAS signal:

. *FCV-72-40, -41 Must not open FCV-74-12 Must open If RHR pump B-B starts due to a spurious ESFAS' signal:

f'

• FCV-72-41, -40 Must not open FCV-74-24 Must open -

If CS pump.A-A starts' due to a spurious ESFAS signal:. ,

• FCV-72-3'9 Must Remain Operable If CS. pump B-B starts due to a spurious ESFAS signal:

• FCV-72-2 Must Remain Operabic If either of the ECCS sump suction valves (FCV-63-72 or FCV-63-73) cannot -

be protected and spuriously open then FCV-63-1 must be cl.* sed, and FCV-72-20 and FCV-72-23 must remain closed to prevent RWST water backflow into the sump. Then FCV-63-72 and -73 must be manually closed before cooldown (approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). . , ,. .,

/

• If these valves open, they must be reclosed by the operator or the pump i'

'must be stopped. Handwheel operation acceptable if the pump can be stopped.

8 A43 3446F/JMS

1

{ :. ',

EQUIPMENT' REQUIRED FOR SAFE SHUTDOWN

,' I SQN-SQS4-0127' Prepared by/Date N4l 2//o/ft Checked by/Date R./ d4.4 .1)toppy l SEQUOYAH NUCLEAR PLANT KEY 5 RWST Suction l

ISOLATE DEPRESSURIZE OPEN VOLUME CONTROL VOLUME CONTROL FLOW TANK TANK FROM RWST

-]r 1r OR V If

~

AND t

Key 5 i

s I

A44 '

3446F/JMS i

l l

~

EQUIPMENT. REQUIRED-FOR SAFE SHUIDOWN

.PER 10CFR50 APPENDIX R Prepared by/Date N d 2//a/sk Checked by/Date _ // /%> J/M/ff SEQUOYAH NUCLEAR P1JMr KEY 5 RWST Suction Basis for Spurious List Item Component _ Basis 61 FCV-63-5, -6, -7 FCV-63-47 If path 2 is used, spurious closure of any one of these valves would isolate the required makeup flow from the RWST to the RCS and injection to RCP seals.

62 FCV-72-40, -41 If RHR pump A-A spuriously starts, inadvertent opening of these valves would divert a portion of the makeup flow to RHR spray nozzles. Makeup to the RCS may be inadequate.

63 FCV-72-41, -40

,If RHR pump B-B spuriously starts, same as item 62.

• 64 CS Pump A-A If this pump spuriously starts and valve FCV-72-39 is not closed, flow diversion will occur. Thus, makeup flow to the RCS and seal injection may be inadequate.

, 65 CS Pump B-B If this pump spuriously starts and valve FCV-72-2 is not closed, flow diversion will occur, thus, same as item 64 67 FCV-63-72 FCV-63-73 Spurious opening of any one of these valves will result in flow diversion to the containment sump.

Thus, same as item 64.

9 9

v A45 3446F/JMS w

1 m

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R

. SQN-SQS4-0127-Prepared by/Date N d2 N A j E//a/st t Checked by/Date f./. ',.M J//s//f KEY 5 (RWST SUCTION PATH 2) 9

/v b/ .

9 -

. v 9 4 e em 8 4 9

W i

9 I

A46 3446F/JMS I

..__. . , - . . . _ _ .----,_- ---- -=

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN-

-PER 10CFR50 APPENDIX R -

SQN-SQS4-012 7

Prepared by/Date- Nd2[//E z//o/pg Checked by/Date f./ h _ gjyjy KEYS 4 AND 5 (VCT AND RWST SUCTION)

E 6

6 v>

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d*

e 4

3 9

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e A47

~

3446F/JMS .

E' EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Preparsd.by/Date'Nd E//o/fr SQN-SQS4-0127 Checked by/Date f,/ M .2/#/p/

SEQUOYAH NUCLEAR PLANT KEY 6 ECCS CHARGING PATH The ECCS flow path is the safety-grade path for RCS makeup. It may be used if the normal charging path becomes isolated. To provide the flowpath an inlet and an outlet valve for the boron injection tank (BIT) must be opened. One'of these valves will be required to be manually controlled (open or closed) to throttle the flow to the RCS.** (Manual control to throttle will require connunication with MCR).

(Operation List)

• FCV-63-25)) Either One Must Open/ Remain f Operable

• FCV-63-26))

• FCV-63-39 ))' Either One Must Open/ Remain Operable

• FCV-63-40);

FCV-63-41),} Any One Must Close ,

FCV-63-42)

VLV-63-574),

An inlet valve and an outlet valve to the BIT must open and one of these

. . will be required to throttle the flow to the RCS.

• • These valves may be throttled for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (reference Section 3.0, assumption 8).

• dt 9

90

. A48 3446F/JMS 9

l

!- EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

! PER 10CFR50 APPENDIX R SQN-SQS4-0127' Prepared by/Date Nd2 2//e/88 Checked by/Date _ A/ & .7//a///

SEQUOYAH NUCLEAR PLANT KEY 6 ECCS CHARGING PATH OPEN FL W ISOLATION FLOW PATH FROM BIT FROM RWST

. TO BORIC ACID TANK b-

• epe 9

• h KEY 6 r

A49 3446F/JMS

,,,e,- ,m --y_

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN-PER 10CFR50 APPENDIX R Prepared by/Date _'N d. M - Z/9/dt SQN-SQS4-0127' Checked by/Date /, /. M 2/N/pp SEQUOYAH NUCLEAR PLANT KEY 7 RCS PRESSURE BOUNDARY ISOLATION If the components required for the normal' letdown path are rendered inoperable due to fire, closure of FCV-62-69 FCV-62-70, or all three of the regenerative heat exchanger outlet valves will.be required to ensure RCS pressure boundary integrity.

In all cases the RHR letdown line must remain isolated until the RHR system is required for bringing the plant to cold shutdown.

The RVHVS solenoid valves and pressurizer PORVS must remain closed or their associated block valves. capable of being closed to prevent the dopressurization of the RCS.

Operation List FCV-62-69) Either One Must Be Capable of Closure FCV-62-70) __ Must Be Capable of Civsure OR '

FCV-62-7E"" Must Be capable of Closure -

FCV-62-73  ! Must Be Capable of Closure FCV-62-74 Must Be Capable.of Closure Spurious List

• PCV-68-334 If PCV-68-344 should spuriously open, then FCV-68-333 must be capable of closing.

• PCV-68-340A If PCV-68-340A should spuriously open, then FCV-68-332 must be capable of closing.

FCV-74-1 ) Either One Must Remain Closed FCV-74-2 ) Must Remain Closed FSV-68-394) Must Not Open FSV-68-395) 1 Must Not Open OR FSV-68-396) -

i Must Not Open FSV-68-397) Must Not open ,

• See key 28 for instructions if FCV-68-334 or PCV-68-340A spuriously open.

Note: If RCP seal injection is used for RCP seal integrity , the RCS seal injection can also be used for pressurizer level control. The RHR system must be available within 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to continue the cooldown to cold shutdown and stop seal injection if normal or excess letdown is not available.

A50 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPF.NDIX R SQN-SQS4-0127 Checked by/Date A d (fa.L e2)to/17 SEQUOYAH NUCLEAR PLANT KEY 7 RCS PRESSURE BOUNDARY ISOLATION

• CLOSE *CLOSE

• CLOS E FCV-62-72 FCV-62-73 FCV-62-74

• CLOSE *CLOSE CLOSE CLOSE FCV-62-69 FCV-62-70 FSV-68-394 FSV-68-396 V V V FSV-68-395 FSV-68-397 AND PCV-68-334 PCV-68-340A I

OR v'll srt OR AND y /

l . _.

AND

, v KEY 7

• These-valves are required to b3 closed only if the normal letdown path is rendered inoperable due to a fire.

A51 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R .

Prepared by/Date Nd[ 4[/0/fd SQN-SQS4-0127 Checked by/Date ./ /. M W/#/II Basis for Key 7 Spurious List i.

RCS Pressure Boundary Isolation Item Component Basis 68 FCV-74-1 These valves are in series and required to be FCV-74-2 opened during the RHR cooldown of the RCS. If at least one of-these valves fail to remain closed prior to RHR heat removal, rapid depressurization due to loss of RCS inventory would occur. Thus, a LOCA would exist. Note these valves are a integral part of the RCS pressure boundary.

6

'9 PCV-68-334 This valve constitutes part of the RCS pressuro boundary. Spurious opening of this valve would result in a small break LOCA which is- isolable

'via closure of valve FCV-68-333. ,

70 PCV-68-340A Same as item 69 however the small break LOCA

• would be isolable via valve FCV-68-332, 71 FSV-68-396 FSV-68-397 These are reactor vessel vent isolation valves

' which are in parallel and constitutes an integral portion of the RCS pressure boundary.

72 FSV-63-394 Same as item 71.

FSV-68-395 4

! 4 A52 3446F/JHS I

-EQUIPMENT REQUIRED FOR SAFE SHUTDOWN ~

'PER 10CFR50 APPENDIX'R -

Prepared by/Date N d. Z//o/gg SQN-SQS4-0127 Checked by/Date 1,4/dsJ NM/ft SEQUOYAH NUCLEAR PIbNT KEY 8

. RCS Pressure Boundary Isolation In the event that the circuitry controlling the letdown lines are rendered inoperable due to a fire, the excess letdown lines must be isolated by closing FCV-62-54, FCV62-55, or FCV-62-56 to further ensure RCS pressure boundary control.

(Operation List)

.FCV-62-54) Any One '

FCV-62-55)

Must Be Capable of Closing FCV-62-56)

Must Be Capable of closing Must Be Capable of Closing CLOSE CLOSE CLOSE

.FCV-62-54 FCV-62-55

, FCV-62-56 y u V OR if KEY 8 '

1 i

A53 3446F/JMS

EQUIPMENT REQUIRED ~FOR SAFE _-SHUTDOWN

0ER 10CFR50 APPENDIX R SQN-SQS4-0127' Prepared by/Date Nd2/ E//o/df <

Checked by/Date M / M 3//887 SEQUOYAH NUCLEAR PLANT KEY 9

.RCP THERMAL BARRIER COOLING If RCP seal integrity is not provided by seal injection, thermal barrier cooling may be used in its place. The CCS is required to supply water to the thermal barrier booster pumps and the ERCW system is required for the CCS heat exchangers.

Ooeration List RCP Thermal' Barrier Booster Pump A-A) Either One Must Operate

• RCP Thermal Barrier Booster Pump B-B) Must Operate CCS Pump A-A) Either One'

• CCS Pump B-B) Must Operate ERCW cooling provided by normal supply header 2A or *

-alternate ERCW header IB. For alignment see Key 3.

0-FCV-70-197 (Unit i Only) Either One Must Close OR (CCS 0-FCV-70-198 (Unit 1 Only) (Note 9 & 14 of Key 1) Pumps A-A AND B-B must be operable) 0-FCV-70-193 (Unit 2 only) Either One Must Close OR (CCS 0-FCV-70-194 (Unit 2 only) (Note 9 &l4 of Key 1) Pumps A-A AND B-B Must be Operable)

. ~ .. .

This key is organized as follows; (1) tabulation of features which must

' operate. (2) a functional logic diagram -(3)' spurious actual tabulation, basis list, and simplified flow ' diagram for unit 1 and (4) spurious actuation tabulation, basis list, and simplified flow diagram for unit 2.

• If B-pumps tre used, equipment associated with supplying B-train power will have to be' evaluated.

A54 3446F/JMS

E EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER'10CFR50 APPENDIX R Prepared by/Date 7kt2 z//o/rg SQN-SQS4-0127 Checked by/Date f./. M A//a///

SEQUOYAH NUCLEAR PLANT KEY 9 THERMAL BARRIER COOLING

~

CCS HEADER A RCP THERMAL SPENT FUEL FLOW TO THERMAL , BARRIER B0OSTER BARRIER B0OSTER POOL HEAT EXCHANGER PUMr ISOLATION PUMPS A lB A B g y '/ V 5/if y Aht hf KEY 9 i

l.

• If B-pumps are used, additional i

equipment associated with

! supplying B-train power will .-

have to be evaluated.

A55 3446F/JMS l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date ' 8 42 [ 2//o/tr SQN-SQS4-0127~

Checked by/Date / /. 4/ad A//#/Pk SEQUOYAH NUCLEAR PLANT KEY 9 Unit 1 Spurious List 1-FCV-70-133 (Note 1) Must Not Close/ Remain Operable 1-FCV-70-134-(Note 1) Must Not Close/ Remain Operable 1-FCV-70-87 (Note 1) Must Not Close/ Remain Operable 1-FCV-70-90 .(Nota 1) Must Not Close/ Remain Operable 0-FCV-70-34 (Note _2) (if CCS pump 1B-B Must Not Close

.. is used) 1-FCV-70-25 (Note 2) Must Not Close 1-FCV-70-8 (Note 2) Must Not Close 1-FCV-70-9 ) (Note 2) Either one Must Not Open 1-FCV-70-10) (Note 2) Must Not Open 1-FCV-70-4 (Note 2) Must Not Close 0-FCV-67-478 (Note 2) Must Not Close 1-FCV-70-156 ) Any one Must Not Open 1-VLV--70-545A Must Be Closed 1-VLV-70-546A -

Mdst Be Closed -

0-FCV-67-14 (Note 2) Must Not.Close .

0-FCV-67-365 (Note 2) Must Not Close 1-FCV-70-13) (Note 2) Either one Must Not Open 1-FCV-70-23) (Note 2) Must Not Open 1-FCV-70-26) (Note 2) Either one Must Not Open 1-FCV-70-27) (Note 2) Must Not Open -

1-FCV-70-64) (Note 2) Either one Must Not Open 1-FCV-70-74) (Note 2) Must Not Open 1-TCV-67-146 Must Not close Spurious actuation associated with ERCW Header 2A or ERCW Header 1B Must be precluded (which ever one is being used) . .(see Key 3).

~

Note 1: These valves will close upon a spurious phase B containment isolation signal. They will be iequired to be reopened.

Note 2: A design change has been made under ECN-L6258 to remove power from this valve. '

A56 -

3446F/JMS

s EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date _N d2 [ M - 4//o/ts SQN-SQS4-0127' Checked by/Date /,/ W elftsjyy Basis for Key 9 - Unit 1. Spurious List Item Component Basis

73. 1-FCV-70-133 . Spurious closure of any one of these valves will 1-FCV-70-134 isolate header CCS flow to the RCP thermal barriers. If the RCP seal injection is not provided by seal injection closure of this valve will result in RCP seal damage, resulting in a LOCA.

74 1-FCV-70-87 Spurious closure of any one of these valves will 1-FCV-70-90 isolate header CCS flov to the RCP thermal barriers. If the RCP seal injection is not provided by seal injection closure of this valve will result in RCP seal damage, resulting in a LOCA.

75 0-FCV-70-34 Spurious closure of this valve is only a problem if CCS pump 1B-B is the only pump used. Thus, loss of heat removal mechanism to RCP thermal barriers.

76 1-FCV-70-25 Spurious closure of this valve will isolate train A

• component cooling flow to the RCP thermal barriers.

77 1-FCV-70-8 Spurious closure of this valve results in loss of train A component cooling to thermal barriers.

Note CCS heat exchanger A is isolated.

78 1-FCV-70-9 At least one of these valves must remain closed to 1-FCV-70-10 prevent flow diversion. If seal injection is required via thermal barriers, reduced fluid volume may result in loss of seal injection due to damaged RCP seals.

79 1-FCV-70-4 Same as that for item.77, t 4

80 0-FCV-67-478 Spurious closure of this valve will terminate ERCW flow to CCS HTX A.

81 1-FCV-70-156 Spurious opening of this valve will result in partial flow diversion. If seal injection is required by thermal barrier cooling, ability to remove heat may be challenged. .

82 ERCW Header 2A See spurious lir* for Key 3.

ERCW Header 1B AS7 3446F/JMS l

L.

EQUIPMENT REQUIRED FOR' SAFE SHUTDOWN

'PER 10CFR50 APPENDIX R SQN-SQS4-0127 Prepared by/Date N d / / /5,- p E//d/*t Checked by/Date _f, /. & ABagf Item Component' Basis 83 2-FCV-67-146 Closure of this valve will isolate CCS heat exchangers 2Al and 2A2. Thus, heat removal from thermal barrier may be challenged resulting in failure of RCP seal, and consequently LOCA.

84- 1-FCV-70-13 Same as that for item 78.

1-FCV-70-23 1-FCV-70-26 1~FCV-70-27 85 1-FCV-70-64 Flow diversion resulting in inadequate flow to 1-FCV-70-74 CCS pumps-1A-A and IB-B.

86 1-FCV-67-146 Spurious closure of this valve isolates ERCW flow out of CCS A heat exchanger. Thus, if thermal barrier cooling is required for seal integrity, RCP seal integrity may be lost and consequently resulting in LOCA.

9 9

e, a b me 0 4

A58 -

3446F/JMS

EQUI 1 MENT REQUIRED ~FOR' SAFE SHUTDOWN PER 10CFR50' APPENDIX R

• r, SQN-SQS4-0127 Prepared'by/Date No [ T d*/ft -

Checked by/Date _ f / W 'pj/oppy SEQUOYAH NUCLEAR PIANT KEY 9 THERMAL BARRIER COOLING - UNIT 1

'r h>

8

~

0 4

e

- Item numbers which are discussed in the basis for spurious list.

1 A59 3446F/JMS ll

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER~10Cnt50 .iPPENDIX R

- SQN-SQS4-0127 1repaced kylkne & fdA~ Zl/o/88 Chrdet kyske _A/ lN_ al/elff SEQUOYAH NUCLELt.J W T KEY 9 Unit 2 Spuricuts List 2-FCV-70-133 (Note 1) nusi h cau/Ammf:n Opesable

' 2-FCV-70-134 (Note 1) ht $ps. Cme /hwRs <Cperable 2-FCV-70-87 (Note 1) Must $si CadT.umnm operable 2-FCV-70-90 (Note 1) ms: h m ue/k mnfx paerable 0-FCV-70-39 (Note 2) (if CCS pump 2B-B is hus M dihr used) 2-FCV-70-16 (Note 2) mu t h c.asa 2-FCV-70-15 (Note 2) hs meC1ms 2-FCV-70-4 (Note 2) not Not Cwe

'2-FCV-70-195) (Note 2)} Either one ht he $ eto 2-FCV-70-196) (Note 2)'

2-FCV-70-156))

Any one mut.t65dbmu 2-VLV-70-545AL Nrd. 2411 mu1 h3 te Clumf 2-VLV-70-546A!i . .

ht 3e Gwatti 2-FCV-70-14) (Note 2)! Either one .Wrt $ci <gom

• 2-FCV-70-18) (Note ?)s riur,$ SM Opnu 2-FCV-70-76) (Nott ~) Either one 2-FCV-70-78) (Note 2) .hst XM 30c.c 2-FCV-70-28) (Note 2) Either one h1 M Jhmo 2-FCV-70-29) (Note 14. Key 1) h i.%c C4um 0-FCV-70-193 (Note 14. Key 1) ht he dbmo

.% rt 2 4 MtM m 0-FCV-70-194 (Note 14, Key 1) h 5 2 6 Ghuir 2-FCV-67-146 .

Spurious actuation associated with ht be yrw/httat ERCW header 1B or 2A (which evet one (C h Ley 3A is being used) .. - . --

Note' 1: These valves will close upon a spurkaus ptwre 1 este.23amma iisolation signal. They will be required to tw .rmpannti Note 2: A design etat.ge has been made under 505-E13F c.s renm2 pnwer frr1o this valve. .

=e N

. A60 3urT/2:'is l

I k .. d

a EQUlF4.ENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Dato _ M O N j T-[/#/ff SQN-SQS4-0127 Checked by/Dato A.l. /N 2/Joffy Basis for Spurious List - Unit 2 Item Component Basis 87 2-FCV-70-133 Spurious closure of any one of these valves will 2-FCV-70-134 isolate component cooling to the RCP thermal 2-FCV-70-4 barriers. RCS seal integrity will be challenged if 2-FCV-70-15 seal cooling is required via RCP thermal barriers.

2-FCV-70-16 88 2-PCV-70-87. Spurious closure of any one of these valves will

. 2-FCV-70-90 isolate the CCS flow from the RCP thermal barrices.

89 0-FCV-70-39 If only the CCS pump 2B-B is used same as item 88.

90 2-FCV-70-195 2-FCV-70-196 At least one of these valves must remain closed to prevent flow diversion. Flow diversion may result in inadequate flow through the RCP thermal barrices.

O .

91 ,2'-FCV-70-193 Same as item 90.

$5% I 0-FdV-70-194

• 92 2-FCV-70-14 Same as item 90.

2-FCV-70-18 93 2-FCV-70-76 At least one of these valves must remain closed 2-FCV-70-78 to prevent flow diversion. If FCV-70-39 is isolated and pump 2A-A is providing flow, flow diversion will not occur. Flow diversion will result in inadequate flow to the thermal barrier coolers.

' ~'

94 2-FCV-70-29 Same as ifem 90'.

2-FCV-70-28 t

A61 3446F/JHJ 6'

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN )

PER 10CFR50 APPENDIX R Prepared by/Date N 42 M sf44a/tt SQN-SQS4-0127 Checked by/Date A /. M J/<*>//f ,

REACTOR COOLANT PUMP THERMAL CARRIER COOLING - UNIT 2 KEY 9 ,

.. ,- %J y n , w <3 .~d-- .

?1

/ , [Le PJ

, 2e-e 2 - fcv-70-~+ ' fcv 19.3 FC V- 7c,- 4 9 '

c <

!mf-y h.)'l .

il h.

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%5 p d h <d u ,.T .2. - ee v'.-'  ; rc v-,.>- M pc a 1o ..o n Ta'I c

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k ,3 !fl di\

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B 2 -

J_ r e s - n -,. ;

gl ---a -

( 4 Wf.{#[4.-f) f ---* ~~

a a_ fev i

_F ~ 70-124 -H m fFev'70-4 - re v' t h k A

c 2 ra-8 In -

cc.s rev 3 g-pe.y o- s33 -

=U re v- 7.-

• d A ~5 U 70~37 d1 A

?/)- _ , -

l 9 7e v -7o-Ir W l

l a a -n l l 4 t's-

~ .-c e l .

N Il 7l _lf

% oA l .2 , -

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A62 DNE4 - 2111Q l

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EQUIPMENT REQUIRED FOR SAFE SliUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date 4M E[/o/83 SQN-SQS4-0127 Checked by/Date / / dk.1- s?//o/Py l

0 SEQUOYAll NUCI. EAR PLANT 2h KEY 11 i

MOTOR DRIVEN AUX FEEDWATER PUMP  !

A motor driven auxiliary feedwater (AW) pump along with the corresponding steam generator (SG) level control components (key 12) may be used to provide SG inver. tory control. Any of these pumps or the turbine driven AFW pump (keys 14 and U) may be use:1 for this function.

(Cperation List)

• A W pump A-A Either One Must Operate

• AW pump B-B Must Operate

• Pump used must supply the SGs being used for cooldown.

AW PUMP A-A AW PUMP B-B l I 0.".

e h i

Y KEY 11

.. }

A63 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prcoared by/Date Wa[ 2//o/g't SQN-SQS4-0127 Checked by/Date _ f./ /R J//o/ff SEQUOYAH NUCLEAR Pl. ANT KEY 12 STEAM GENERATOR LEVEL CONTROL The components listed 'in this. key are only required if the motor driven AFV pumps (key 11) are used to provide flow to the SGs. The SG level may t,e controlled automatically or manually. Automatic level control consist of automatic control of'the LCVs. This requires control air (key 13) for the valve controller.

Manual control consists of on/off operation of the AFW pump or throttling the flow to the SGs with manual valves. To monitor the SG 1evels, level indicators are required. (Refer to SOI-3.2, R30, section D.2, for manually throttling of valves to control SG level using the AFW system).

(Operation and Spurious List)

Path I r

' Automatic Level Control PS-3-164 Must Not Cause LCV to Close Loop L-3-164 (for LI-3-164 and LCV control) Must Operate LSV-3-164 Must Operate LCV-3-164 -

Must operate PS-3-156 Must Not Cause LCV to Close

- Loop L-3-156 (for LI-3-156. and LCV control) Must Operate -

LSV-3-156 .

Must. Operate LCV-3-156 Must Operate Control Air Supply, Path 1 (See Key 1,3) , , , , , ,

Must Operate OR Manual Level Control */" K,' 7.,.. ','_.}.)

, loop L-3-43 (for LR-3-43P1) (Any one) yk Must Operate Loop L-3-164 (for LI-3-164) s/'8/88 Must Operate loop L-3-39 (for LI-3-39) Must Operate LEV-3-164** __ Must Not Close loop L-3-56 (for LR-3-43P2) (Any one) Must Operate loop L-3-156 (for L'-3-156) M galt:

Must Operate Loop L-3-52 (f or LI-3-52)  ? C J-5: Must Operate LCV-3-15 6**  %,. ; : :: (w... "c.:; 2. ..j) ,, _Must Not Close

• Manual control consists of on/of f operation of the AFW pump (Key .ll) i or manually, throttling the following valves:

3-836 or 3-828 Either one (SG 1) 3-835 or J-827) Either one (SC 2)

• • Local operation acceptable.

.T. s lien of %e. thove kTs, Loop L-3-32 (fo< LT-3-3 8) ed L- 3-S I (?oc LT.3-St)my i

he. utilired for $res inside. containment %af affec+ sense la'nes as dehil<d is

. ggq 88Of LO 001. A64

! 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date M 8 Z//d/ft y SQN-SQS4-0127 Checked by/Date /,/. dM./ 2 N4/pp SEQUOYAH NUCLEAR PLANT KEY 12 (Operation and Spurious List)

Path- 2 Automatic Level Control -

PS-3-148 Must Not Cause LCV to Close Loop L-3-148 (for LI-3-148 and LCV control) Must Operate LSV-3-148 Must Operate LCV-3-148 Must Operate PS-3-171 _.

Muat Not Cause LCV to Close Loop L-3-171 (for LI-3-171 and LCV control) Must Operate LSV-3-171 Must operate

.LCV-3-171 Must Operate Control Air Supply, Path 2 (See Key 13) _ . , , Must Operate

~

Manual Level Contro1*/ - - - - -

Loop L-3-98 (for LR-3-98Pl7 (Any one) /s,/st Must Operate Loop L-3-148 (for LI-3-148) Must Operate Loop L-3-94 (for LT-3-94) _. Must Operate -

LCV-3-148** _

• Must Not Close Loop L-3-ill (for LR-3-98P2)' (Any one)

Must Operate Loop L-3-171 (for_LI-3-171) Must operate Loop L-3-107 (for LI-3-107); A */I" Must operate LCV-3-171** '- L-r - ? : 4 .'. : --, I M Must Not Close

• Munual control consists of on/of f operatioT of the AFW pump (Key 11) or manually

, throttling'the following valves:

3-834 or 3-826 Either one (SG 3) 3-837 or 3-829 Either one (SG 4)

• • Local operation acceptable.

' ~ ~

~1A IILM of St above LL, l. coes L--5 q3 (for L.T .3-9 5) & L.-3-WL. (for L.:'-3~ l&

i eles caed rug b<. gHliced for 4;<cs inside containmewt %+ affae+ sen se lines as A G2.9 850120 oot.

1 l

l l

A65 3446F/JMS

f!

EQUIPMENT REQUIRED FOR SAFE SBUTDOWN PER 10CFR50 APPENDIX R SQN-SQS4-0127 g gjgjg

.. Checked by/Date _ l A N J N N A KEY 12 STEAM GEllERATOR LEVEL C0llTROL C0tfrROL AIR SUPPLY AUTOMATIC C0!rIROL (Key 13) LC7-3-156 AUTOMATIC CCh*1'ROL C0!TTROL AIR SUPP:

LC7-3-164 LC7-3-148 (Key 13)

LCV-3-171 ' ,

t-- -

i t .._.

. e SGs 1 & 2 303 3 6 '

Level 3 U

• V'1

- INDICATICl{ INDICATION yy --

AND V V Manual Level Manual Level Control From Control From .

MCR 'MCR '

\*

l

l l

l

_- Y__V v $~'~

OR OR I -

1

\

l l~ Y y PATH 1" ~

~

P fTg '2 1 3

+ .

__ V V OP.

V

!- KEY 12 rh1 manual level cc.,0 trol is .

scomplished via manuai?y-ant

hrottling valves,W a- dn -backup-

.w uw44s=66vu p 6 4 uN1 ".hOuld De - 2/10/$g-ALTA ,

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date 124I[ E//o/ft SQN-SQ'S4-0127

- Checked t>y/Date / / & .W a//f Basis for Key 12' Spurious List u Item Component Basis 95 1&2-LCV 164 When path 1 is being used (train A, electric driven pump),

this. valve must be operable to control the AFW. flow to steam generator no. 1. Spurious closure of this valve may result in low steam generator level.

96 1&2-LCV-3-156 Same as item 95 except that steam generator no. 2 may be affected.

97 1&2-LCV-3-171 When' path 1 is being used (train B, electric driven pump) same-as item 95 except applies to steam generator no. 4 98 1&2-LCV-3-148 Same as item 99, but applies to SC no. 3.

e o

G e

e

• me e

l A66 3446F/JMS l

l

1 EQUIPMENT REQUIRED FOR $AFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date. N d [2/ Z//e/ft SQN-SQs4-0127 ,

Checked by/Date /N ##

. STEAM GENERATOR LEVEL CONTROL .

KEY 12 CST ""'5'"' -

sh ,

dencrafer

. .  : . A "**

~

LCV-3 il;9

$ltam rev.g7 1 7.' Cce6 *.

9 -livd IA-A h 9,,,

h RV 67

- Il& A I

LcV'1 ist Q k dwrg A n. 2 LCV 3-NF G

' Sterm ro c7 O b bre ~

itta s-a IB-B k g

-f/ E-c

-i24 *

' 47520 4

u

c:

EQUIPMENT REQUIRED FOR SAFE SHUTD0'4N PER 10CFRSO APPENDIX R Prepared by/Date Nd[ 4//o/fs SQN-SQS4-0127 Checked by/Date _[fS 2//ofyy SEQUOYAH NUCLEAR PLANT Key 13 CONTROL AIR This key contains the equipment necessary to supply control air for the following features on the shutdown logic diagram: steam generator level control valves, automatic control (keys 12, & 16), and SG PORVs (Key 26), and various dampers and valves' required for HVAC (key 37)

Path I contains the components requir'ed for auxiliary aar compressor A which provides control air s'upply to header A. Path 2 contains the equipment for air supply header.3.

Specific equipment in this calculation that utilizes control air may be manually operated - see individual keys for details.

T T

l

. A68 3446F/JMS

EQUIPMENT' REQUIRED FOR SAFE SHUTDOWN PER 10CFRr3 APPENDIX R

.SQN-SQS4-0127' Preparet 17EMe $A Eb"l81 Checked 7 L )Tet.r )J N 2JM/Py SEQUOYAH NUCLEAR PIANT KEY 13 (Operation and Spur 5vw )

Control Air Supply Path 1 Station air compressor A Mun Ogmate Control circuit for air compressor A Mtu1 Cptea k 0-FSV-32-42 0-FCV-32-82 he me crose h e 'Noi d ar.r 0-PS-32-82 ha Noe C:ntet: E!**e to C1tst

• • 0-33-500) . Either one he h Cirstuf.

• • 0-33-501) stut & cJmiersi OR

• Station air compressor B

- Control circuit for air compressor B Yuta @ nicitW 0-FSV-32-37 Mtu:t dowatte 0-FCV-32-82 h aNW C?hmt suas NM dTolhi; 0-PS-32-82

=

ha 9&rt (Ciumi: W6xt: to -

C11thE

• • 0-33-500) Either one lMust % d.lkisesti

• • 0-33-501) -

must Bk Gamsati QE e Auxiliary air compressor A must Gustxtrt,s:

Control circuit for aux. air compressor A Mud? dyeere 0-FSV-32-62 Mur$3M <Phme 0-FSV-32-61 Must lNot Came

• • • 1-FCV-67-127 Muf ? NM CRssr

~

FS-67-206 h$ NM Ctune Vat 2ve to

-C20sr j '0-FCV-67-205 TJust IW name

• • • 1-FCV-67-127 l

h c Nist d et e ,

PS-67-206 ' Gree pn 'if stah.on Aturt .ht Ems J'she to

- Gir* Compre nors Qtt d 5' E gg,gg

.._ OR 0-FCV-67-208 h5 k chmt-l~ ***1-FCV-67-128 g g 3 1 g g ,.y _

PS-67-209 l

' he $91 Cr.ure %1re to e C1cte FS-67-209 Ast Ms Caure 7alve to Cist:

This is a B-train compressor. If it is used, .egulpmect .eArmieted with L electrical B-train power will have to be evaluered, i ** Handwheel operation acceptable.

• • • A design change nas been made under ECN-L6238 op remove pont from ttis l valve.

Special Note: See general cequirements sectios 4,:l:

, A69 -

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN  !

PER 10CFR50 APPENDIX R Prepared by/Date Nd[ N#N#

SQN-SQS4-0127' Checked by/Date f./ W 2//o/f?

SEQUOYAH NUCLEAR PLANT KEY 13 (Operation and Spurious)

Control Air Supply Path 2

• Station air compressor A Must Operate Control circuit for air compressor A Must Operate 0-FSV-32-42 Must Not Close 0-FCV-32-85 Must Not Close 0-l'S-32-85 Must Not Cause Valve to Close

• • 0-33-500) Either one Must Be Closed

• • 0-33-501) Must Be Closed C OR Station air compressor B Must Operate Control circuit for air compressor B Must Operate 0-FSV-32-37 Must Not Close 0-FCV-3l.-85 Must Not Close 0-PS-32-85 .

Must Not Cause Valve to Close

• • 0-VLV-33-500). Either one Must Be Closed

• • 0-VLV-33-501) _ Must Be closed OR Auxiliary air compressor B Must Operate

, Control circuit for auxiliary air compressor B Must Operate 0-FSV-32-88 Must Not Close 0-FSV-32-87. Must Not Close

• • • 2-FCV-67-128 Must Not Close

~

"S-67-206 Must Not Cause Valve To close 0-FCV-67-205 . .. -.

Must.Not Close

• • • 1-FCV-67-127 l Must Not Close

• PS-67-206 Either paf( if .shNon & Must Not Cause comp' ressors Arc med.

_ Valve To Close

~

OR 0-FCV-67-208 Must Not Close

• d*1-FCV-67-128 Must Not Close PS-67-209 Must Not Cause Valve To Close -

-FS-67-209 Must Not Cause

- Valve To Close

• This is a A-train compressor. If it is used, equipment associated with A-train power will have to be evaluated.

• • Handwheel operation acceptable.

• • • A design change has been made under ECN-L6258 to remove power from this valve.

A70

- Spec,jd S te: Se gmy r ce 5cch t L 3446FDMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CTR50 APPENDIX R '

Prepared by/Dato Nd 4//o/t.

SQN-SQS4-0127 ,,

Checked by/Date // $/s / 2//o/p)

N SEQUOYAH NUCLEAR PLANT KEY 13 ,

CONTROL AIR

~

STATION STATION AUXILIARY AIR AUXILIARY AIR

/IR AIR . . COMPRE,SSOR A COMPRESSOR B CLMPRESSOR A COMPRESSOR 8 l

l l

1 l

y r 2/ . ,

OR l

.sf Key 13 l

l e

A71 47S20 e

• • , +

o.

l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date Nd Z/14[##

SQN-SQS4-0127' Checked by/Date /,,; /Af 2//o//f Basis for Spurious List KEY 13 Control Air Item Component Basis 99 N/A Not Used 100 0-FSV-32-42 Spurious closure of this valve would terminate ERCW cooling flow to the intercooler for compressor A.

101 0-FCV-32-82 Spurious. closure of this valve would isolata the control

- air ~. system f rom crain A auxiliary control air. Depending upon the loads serviced at the time, this may result in low header pressure, with the resulting Auxiliary Air Compressor picking up load.

102 N/A Not Used 103 0-FCV-32-37 Same as item 100 but applies to compressor B -

104 0-FCV-67-205 Spurious closure of this valve will' isolate ERCW flow from header 1A to the station air compressors.

-105 1-FCV-67-127 Spurious closure of this valve will isolate ERCW flow from header 1A to Auxiliary Control Air Compressor.

106 0-FCV-67-208 Same as item 104 but for header IB.

107 1-FCV-67-128 Same as item 105 but for header 1B.

108 Auxiliary Air The Auxiliary Control Air Compressor is starred whenever Compressor A system pressure falls to 80 lb/in.g..2 Failure of this compressor to operate will require the compressor for the other unit to pick up the load. Depending on the load services at the time, this may result in low header pressure.

109 FSV-32-62 Spurious closure of this valve will cause the Auxiliary Air Compressor A to fail. Therefore same as item 108.

110 FSV-32-61 Spurious closure of this valve will isolate ERCW cooling water to auxiliary control air compressor.

A72 3446F/JMS L

EQUIPMENT REQUIRED FOR SAFE SHUTDOUN

'PER'LOCFR50 APPENDIX R ~ -

Prepared'by/Date N A [ 2//h/ff

'SQN-SQS4-0127' Checked by/Date /,/ M _s//a//P Basis for Sp;trious List KEY D Control /.ir Item Component Basis '..

l 111 FCV-32-85

~

Same'asitemi01butfortrainB.

_-112 FSV-32-87 Same'as item 110.

113 FSV-32-88 Same as item 109.

0 e

4 g

\

l l

t k

E A73 3446F/JMS i

i l

l' l.

r l-EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date Nd 2//o/df SQN-SQS4-0127 Checked by/Date _ A / /?fd. plaffy SEQUOYAH NUCLEAR PLANT KEY 14 AND 15 AUX FEEDWATER SUPPLY TO STEAM GENER/. TOR FROM TDAFW The turbine driven AW pump may be' used to supply feedwater for SG inventory control.

If this pump'is used (as opposed to a motor driven pump, key ll),

the SG level control valves (key 16) corresponding to the two loops being used for cooldown must be operable.

For pump operation, a, steam supply from SG 1 cr 4 must be available. In addition, the turbine trip and throttle valve and governor valve must be operable.

(Operation and Spurious List)

AW Pump Turbine A-S gp Must Operate Instrument Loop P-3-138A. # Must Operate-Instrument Loop F-3-142 Must Operate Instrument Loop FIC-46-57 Must Operate Instrument Loop SC-46-57 Must Operate Turbine-Driven Aux Feedwater Pump A-S Must Operate

• FCV-l-51 Must Operate FCV-1-52 Must Operate

• FCV-1-17 Must Not Close

• FCV-1-18 . . . Nust.Not Close.

• FCV-1-15 Must t - Cim opua k #

OR

• FCV-1-16 Must Operate

• Handwheel operation acceptable.

A74 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN '

PER 10CFR50 APPENDIX R Prepared by/Date NA '-//*/tt SQN-SQS4-0127 Checked by/Date M / b N/0/FP SEQUOYAH. NUCLEAR PLANT KEY 14 and 15 AFW SUPPLY TO S.G FROM TDAFW PUMPS OPEN OPEN , STEAM SUPPLY TURBINE

. FCV-1-18 FCV-1-17

'TO DRIVEN AFW TURBINE PUMP

, OPEN , OPEN .

/

FCV-1-15 AFW TURBINE FCV-1-16

- ' SPEED CONTROL

,- OR V YV yy V

' ~

l .

AND' y

/ ~

KEYS 14 & 15 A75 47520 e w w

. EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date N2 E/2/ff SQN-SQS4-01271 Checked by/Date 4./. C .?//d///

Basis for TDAFW Spurious List KETS 14 and 15 114- FCV-1-51 Spurious actuation of this valve will affect the operation of the turbine driven Auxiliary Feedwater Pump.

115 FCV-1-17 Spurious closure of any of these valves will FCV-1-18 terminate steam flow to the Auxiliary Feedwater Pump turbine stop valves. Thus, same result as item 113.

'116 FCV-1-15 _ Spurious closure of this valve will terminate steam flow from SG No. 1 to the AFW pump turbine stop valve.

117 FCV-1-16 Same as item 116 but for SG No. 4 118 Turbine Inappropriate functioning due to spurious initiation Driven AFW on pump failure could result in the inability to Pump A-S control steam generr'.or level inventory. ,

152 P-3-138A the auxiliary feedpurap turbine (AFPT) speed control -

-" 3-100^ AL'c circuitry must be functional to ensure the .

F-3-142 -2/"N' availability for the AFPT to supply feedwater flow.

FIC-46-57 ,

SC-46-57 e = we m*

h i

A76 3446F/JMS L

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN '

I PER 10CFR50~ APPENDIX R )

Prepared by/Date Nd E//#/f#

SQN-SQS4-0127 Checked by/Date A / b #8#/#I l

__ -l TURBINE DRIVEll AFW PU.'iP I KEY 14 & 15 4

FeJ- i - it,

~

5. G .

. . . N*. Y Fcv- t-16

' CO NDEJJSATE -

STonAc,E TANK -

h p n y_,.,3 k, S' 6 -

l No.1 -

B Rv i-17 c *

.bPrcterred) 4 S. G.

u.1

• 1- Fcy

-on 2,N MU g,g, I- Fev

-nu i

h no.s EBCW '

trakup I - D I TDA FW g 1 -

PV t-Si A77 47520

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Irtpued tribh46 Y?t2SA Ll/#lt! '

SQN-SQS4-0127' Cbec.ket l'y/Ditte / / 8(re.,l S M !!

SEQUOYAH NUCLEAT ?D&"I KEY 16 Steam Generator Leret Cutird If the turbine driven AW pump is used to supply feedwews es t$r Sdis, the two level control valves corresponding to the Loops being med Jar enud'dhwm must be operable. The valves may be controlled avtama.tica337 s2 muituuSLyr Automatic control requires control air (key E3) for 1&c wa3M cuness31'er Manual control consists of handwheel operatscts e.f de ac7, T:te tatuad! . method of maintaining SG level requires monitoring in ne TX:B wati Daverl) Omtiscators.

(Reference 'S01-3.2, R30, section 2 for throt: Jing AG" Savel esntrai' 951!995.)

t 5

9

.e i es te m*

A78 D MT/.JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN  !

PER 100FRSO APPENDIX R SQN-SQS4-0127 Prepared by/Date [ 2//o/t/ l i

Checked by/Date f./. N JN#Nf hC/ h Operation and Spurious List Path 1 Automatic Level Control LCV-3-172-LSV-3-172 Must operate Must De-energize to Modulate LCV Instrument Loop L-3-172 (for LCV control) Must Operate Instrument Loop P-3-138A (for LCV control) Must Operate PS-3-140A Must Not Cause Valve to PS-3-140B Close Must Not Cause Valve to Close LCV-3-175 LSV-3-175 Must Operate Must Deenergize to Modulate LCV Instrument i. cop L-3-175 (for LCV control) Must Operate Instrument Locp P-3-138A (for LCV control) Must Operate.

PS-3-165A Must Not Cause Valve to PS-3-165B - Close Must Not cause Valve to Close Control Air Supply, Path 1 (see Key 13) Must Operate OR Manual Level Contro'1 gg tilOS

• LCV-3-172

,- - v : z l,v.a ' _ 1A y ~l Must Operate Instrument Loop L-3-98 (for LR-3-98P1) (Any one) Must Operate Must operate Instrument Loop L-3-94 (for,LI-3-94) Instrument -

-Must Loop Operate L-3-172 (for LI-3-172) %

• LCV-3-175 y L=, ";- % v=m<i*a""a w .

Must operate

. Instrument Loop L-3-111 (for LR-3-98P2) (Any one) Must Operate Instrument Loop L-3-175 (for LI-3-175) Must herate Instrument Loop L-3-107 (for LI-3-107) Must opcate Handwheel operation acceptable.

$\ lic a. 4 % a b R l fS b (o L 3-93 hr Lf-3-93) and L log [Ge LT-J- 106) #

y mg e utitsul For Rus insde cm%;nmen+ %F dfu+ sem U"' o M~* d y

i~ Grt ssoi2.o cot.

A79 3446F/JMS n-- -----g-- , - , ~

EQUIPMENT REQUIRED FOR SAFE SHUIDOLW

.PER 10CFR50 APPEND 2X R Prepared by/Date M SQN-SQS4-0127

1. dd/tf Checked by/Date // d4L 2ppj))

SEQUOYAH NUCLEAR PIANT KEY 16 (Operation and Spurious List)

Path 2 Automatic Level Control LCV-3-173 Must Operate LSV-3-173 Must Deenergize to Modulat? LCV Instrument Loop L-3-173 (for LCV control) Must Operate Instrument Loop P-3-138B (for LCV control) Must Operate PS-3-150A PS-3-150B Must Not Cause Valve to Close

.LCV-3-174 Must Not Cause Valve to Close Must Operate LSV-3-174 .

Must Deenergize to Modulate LCV Instrument _ Loop L-3-174 (for LCV control) Must Operate Instrument Loop P-3-138B (for LCV control) Must Operate

• PS-3-160A PS-3-160B Must Not Cause Valve to Close Control Air Supply, Path 2 (s?e Key 13) Must Not Cause Valve to Close Must Operate OR -

Manual Level Control 4 tjyfo

• MV-3-173 y =iL ' ~#

' ~ ' " ' ' "" } Must operate Instrument Loop L-3-56 (for LR-3-43P2) (Any one: Must Operate Instrument Loop L-3-173 (for LI-3-173) Must Operate Instrument Loop L-3-52 (for LI-3-52) -

Must Operate

• LCV-3-174 t 3 :. .: ;'

A

- i r a" o / 8h'# 8 Must Operate Instrument Lcop L-3-43 (for LR-3-43P1) (Any, one

.. Must Operate Ins trument J. cop L-3-17'- (for LI-3-174)

Must operate

/

Instrument Loop L-3-39 (for LI-3-39) Must operate

• Handwheel operatio1 acceptable.

.Cn l<'en. of %e o. bon LLs, Loops L-3-38(for L T 58) an d L-3-58 (for LE .5-s

~

k a+ilitecl for Arts isside. con +ainme n+ %f a.ffeet sense lines as ddatteel ..

m*f

g GA9 V60120 00l.

A80 3446F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R SQN-SQS4-0127 Checked by/Date 4./ 8.4.2 .7//o/PP

'SEQUOYAH NUCLEAR PLANT "- ,

KEY 16 ,

STEAM GENERATOR LEVEL CONTROL CONTROL AIR SUPPLY AUTOMATIC LEVEL (Key 13) -

CONTROL 2/4 SG .

l AND SG LEVEL MANUAL INDICATOR OPERATION 2/4 SG OF LEVEL CONTROL VALVES 2/4 SG -

4 y Y

~~~ '

( ANO l

I

. i 1

fV OR .

[ V l KEY 16 .

~

s 47520 l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date kd tho/88

.SQN-SQS4-0127

,, Checked by/Date A2 /d.Z R//eN/

I.

SEQUOYAH NUCLEAR PLANT Key 17 SUCTION FROM CONDENSATE STORAGE TANK In order to provide SG level control, a supply of feedwater is required for the AFW system.

The initial supply is the condensate storage /(C';. It is normally aligned and no' components are required to function ts key.

F 4

Normally '

Aligned

. No Action Required V -

KEY 17

[

1 i

l I

__ ~

A82 l 47520 1

~

EQUIPMENT _REQU8 RED FOR SAFE SliUTDOWN

'PER 10CFR50: APPENDIX R Prepared by/Date I ll E//d/8r SQN-SQS4-0127 Checked by/Date _pe J.d>L 1 al/dsfy SEQUOYAH NUCLEAR PLANT Key 19 SUCTION FROM ERCW After the CST (key 17) has reached its low level, the suction for the AFW system must be switched to the ERCW system. The valves corresponding to the pump being used .o supply ERCW to the SGs must be opened. The qualified water supply to the MDAFW pumps is from the discharge headers in the ERCW system.

Therefore,'a flow path in the ERCW system must be provided to the discharge header which supplies the pump in operation. Suction for the turbine driven AFW pump may be taken from either the A or B ERCW supply header.

O O

A 4

9 e

9 et #

D e

N A83 3446F/JMS

E- 'l e-

. EQUIPMENT REQUIRED FOR SAFE SHUTDOWN

'PER 10CFR50 APPENDIX R

, Prepared by/Date 7Tt2 4//0/s8

-SQN-SQS4-0127-Checked by/Date A.f. 64 d 2/4/ft

.s siY 19 - SUCTION FROM ERCW Operation and Spurious List Path 1 1-FCV-67-223 (Note 1) Must Not Close 2-FCV-67-223 (Note 1) Must Not Close 1-FCV-67-424 (Note 2) Must Not Open 1-FCV-67-478 (Note 3) Must not close If Motor Driven AFW Pump A-A Is Used:

• FCV-3-116A Must open

' *FCV-3-116B Must open 6

If Turbine Driven AFW Pump is Used:

• FCV-3-136A Must open

• F0V-3-136B '

Must open Path 2 2-FCV-67-147 (Note 3) Must not close If Motor Driven AFW Pump B-B Is U.ted:

• FCV-3-126A Must Open

• FCV-3-126B Must Open If Turbine Driven AFW Pump is Used:

• FCV-3-179A Must Open

• FCV-3-179B , , Must Open

• Handwheel operation acceptable.

~

Note 1: A design-change has been made under ECN-L6258 to open this valve and remove power.

Note 2: A design change has been made under ECN-L6258 to close this valve and remove power.

Note 3: A design change has been made under ECN-L6258 to remove power from this valve.

~~

, A84 -

3446F/JMS

EQUIPMENT REQUIRED'FOR SAFE SHUTDOWN PER 10CFR50 APPENDlX R -

Prepared'by/Date84,[2 r e//o/tr SQN-SQS4-0127 1

Checked by/Date _)). //.G,.2 2/to/r?

Special Note:

The ERCW headers spurious lists contain the containment spray (CS) heat exchangers isolation valves (l&2-FCV-67-123, -124, -

125 -126).

Per the spurious lists, th se valves are required to stay closed.. isolating flow through all CS heat exchangers.

It~is acceptable, however, for one CS heat exchanger (per path used) to have cooling flow .(i.e., CS heat exchanger 1A can have flow through it provided heat exchanger 2A is isolated. The same is true for Train B). .i e

0 4

49

• I d

( '

- A85 3446F/JMS 9

^ _ _ . . _ . _ . . . . - . - - - --

1. 6QUIPMENT.REQUERED.FOR SAFE SIUTCOWN

. .- g . -

PER 10CFR50 APPENDIX R i j

. SQN-SQS4-0127 .

Checked by/Date f./ L .ejtosyk  :

i

, KEY 19 I

SUCTION FROM ERCW

.l ,

4

. 1 ERCW H' EADER FLOW OPEN SUCTION VALVE PAIR TO-A B AFV PUMP '

A B A-SM V

v v h O -

a y AND KEY 19 Note the turbine driven pump can be associated with either train A or B.

A86 3446F/JMS

EQU1PMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFRSO APPENDIX R SQN-SQS4-0127 Prepared by/Date _Ne2[/A - t/ro/sg s

Checked by/Date ).A ffa./ D/n//?

KEY 20 Main Steam Isolation .

Secondary side isolation will be required if a loss of offsite power occurs, or a fire-damages the control circuitry of the steam dumps or main feedwater system. .'In either case, the main steam supply to-the turbines must be isolated.- This key.provides the preferred method of main steam isolation .

This requires closing the main steam isolation valves and ensuring that the main steam isolation bypass valves are. closed. The plant can then be cooled down by the PORVS.

FCV 1-147 9

Must Close FCV-1-4 Must Close FSV-1-4A Ei! her 'on.e Must Deenergize FSV-1-4B Must Deenergize

~

FSV-1-45" FSV-1-4E Either set Must Deenergize of two -

Must Decnergize FSV-1-4G)

FSV-1-4FI) Must Deenergize Must Deenergize FCV-1-148 Must Close FCV-1-11 Must Close FSV-1-11A)' Either one Must Deenergize FSV-1-11B)

Must Deenergize FSV-1-11F Must Deenergize FSV-1-11E Either set Must Deenergize of two FSV-1-11G Must Deenergize FSV-1-11H_

Must Deenergize FCV-1-149 .

Must Close FCV-1-22 Must Close FSV-1-22A) Either one Must Deenergize FSV-1-22B)

Must Deenergize FSV-1-22D Must Deenergize FSV-1-22E Either set Must Deenergize of two FSV-1-22G Must Decnergize FSV-1-22H_,

--Mus t Deenergize FCV-1-150 i Must Close A87 l 3446F/JMS.

l

- . - ,. ., . , -~ . - . - . . - . - - , --, -

cy u e r.1t.s t atyVIRED FOR SAFE S!!UTD0'4N PER 10CFR50 APPENDIX R 1

Prepared by/Date Nd k/4/EF SQN-SQS4-0127 Checked by/Date EA %2 2//ojty SEQUOYAH NUCLEAR PLANT Key 20 FCV-1-29 Must Close FSV-1-29A) Either one Must Deenergize FSV-1-298) Must Deenergize FSV-t-29D) Must Deenergize FSV-1-29E) Either. set Must Deenergize FSV-1-29G) of two Must Deenergize FSV-1-29H) - Must Deenergize FSV-1-4F AND FSV-1-4J Prior to closing the FSV-1-11F AND FSV-1-11J MSIV none of the FSV-1-22F AND FSV-1-22J groups of'2 solencid FSV-1-29F AND FSV-1,-29J valves may spuriously energize (This would block the air vent paths and prevent closure of the associated MSlV.)

The following set of spurious operations must not occur:

ALL ENERGIZED FSV-1-XA AND FSV-1-XB AND (FSV-1-XD OR FSV-1-XE OR FSV-1-XF)

AND (FSV-1-XG OR FSV-1-XH OR FSV-1-XI) .

X= 4 for S.C. 1 11 for S.G. 2 22 for S.G. 3 29 for S.G. 4 ENERGIZE FSV-1-XA -)U3 XD XE XF XG XH XJ l

OR OR y v V AND e

(UnacceptableOpeningor MSIV FCV-1-X NOTE: In the event a fire in the MCR the operator must pull the fuses in the #

control cir- 'or FCV-1-147, -148, -149, -150 to prevent possible spurious ope these valves. Also, the FSV-1-147, -148, -149. -150 mus t not spurious 1, . rgize. Spurious energitation would open FCV-1-147, -148,

-149, and -15^

. A88 -

3446F/JMS w--....

~

-EQUIPMENT REQUIRED'FOR SAFE SHUTDOWN

'PER 10CFR50' APPENDIX R

[ ',

p 59, ,'. ..

.SQN-SQS4-0127 Prepared by/Date _ hl2 Y W L/to/gf

y.

• 4 Checked by/Date f f fD 2/H/IP Key 21 STEAM 1,0AD IS0!ATION -

If the metn team isolation and bypass valves (key 20) cannot be closed, the steam load may be isolat~ d by closing ~ the main steam dump valves, the main turbine and stop MSR valves,.the 2nd stage reheats,-main feedwater pump turbine trip and throttle valves, and the isolation and bypass valves.

valves and will close on loss of power. .These valves are air operated FCV-1-77 Must Close FC's 75 Must Close FCV-1-284 Must Close FCV-1-29' Must Close FCV-1-298 Must Clo'se .

FCV-1-%75

. Must Close '

FCV-1-277 Meet Close FCV-1-279 Must Close FCV-1-75 FCV-1-84 Must Close FCV-1-91 ,, ,

Must Close FCV-1-98 Must Close Must Close 4

I e

A89 3446F/JMS J

4

"QUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R SQN-SQS4-0127 Propared by/Date 'N4 [ M/o/44

~

Checked by/Date J ,/. gle./ N h/ft h

SEQUOYAH NUCLEAR PLANT KEY 21 (Operation List)

FCV-1-103 FCV-1-104 Must Close FCV-1-105 Must Close FCV-1-106 Must Close FCV-1-107 M.st Close FCV-1-108 Must Cicae

{ Muse close FCV-1-109 FCV-1-110 Must Close

w. FCV-1-111 Must Close FCV-1-112 Must Close FCV-1 113 Must Close FCV-1-114 Must Close Must Close I

FCV-1-61 ) Either one Must Close FCV-1-62 )

Must Close FCV-1-64 ) Either one Must Close FCV-1-65 )

Must Close FCV-1-67 ) Either one' .

FCV-1-68 ) Must Close Must Close FCV-1-70 ) Either one Must Close FCV-1-71 )~

Must Close FCV-1-36) Either one FCV-1-37) Must Close Must Close FCV-1-43) Either one FCV-1-44) Must Close Must Close Note: No spurious list is required for this .,key; 4

O A90 3446F/JMS

j; " EQUIPMENT' REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R

• l Prepared by/Date 7fd M E//f/se SQN-SQS4-0127

,, Checked by/Date M.2 [4.4 #//v/p?

SE000YAH NUCLEAR-PLANT STEAM LOAD ISOLATI0tt 1 '

KEY 21 CLOSE MAIN CLOSE MSR CLOSE CLOSE TURBINE 2nd STAGE MAIN STEAM MAIN TUR81t1E TRIP riSOLATION

- OUMP VAL'VES TRIP AND STOP TROTTLE VALVES VALVES VALVES i i g

c h -=

,, .. AND o

e 9

KEY 21' e

e 4

8 e

f!

A91 47520 4

4 *

' - ' ' ' ~ ~

, , , . _ . , ,,_, _ _ - ,, - - - - - - - - - - - - - - - ~ - - - ~ - ' " ' ' - ' ~ ' -

'M O' "

EQUfPMENT: REQUIRED FOR SAFE SilUTDOWN PER 10CFR50 APPENDIX R

-SQN-SQS4-0127 Prepared by/Date I6l./b r./fo/gg Checked by/Date /. f. M .t/a//r ,

KEY 22 FEEDWATER IS01.ATION'

' Secondary side isolation will be required if a loss of offsite power occurs Lor, if the circuitry controlling the main feedwater supply is damaged due to a fire. --Termination of main feedwater supply can be accomplished by either closing feedwater valves or tripping the main feedwater pumps (key 23). This

' key requires closure of a feedwater isolation valve or a feedwater control valve in the feed to each SG.

for each'SG must be verified to be closed.In addition, a feedwater bypass isolation-valve (Must Operate)'

~

-FCV-3-35 ) Both -

FCV-3-35A) Must Close OR FCV-3-33 J FCV-3-483,Both -

TCV-3-48A) Must close .

OR

-FCV-3-47 _)

~

FCV-3-90-) Both Must Close FCV-3-90A) ~

]OR F(:V-3-6 7 . J FCV-3-103 [ Both --

FCV-3-103A)

}1ust Close .

1 OR FCV-3-100 J -

A92 3446F/JMS O

EQUIP.%NT REQUIRED FOR SAFE SlfUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date .N42 M t//o/3; SQN-SQS4-0127

,, Checked by/Date _ /./ 8d.Z e?//a//M SEQUOYAH NOCLEAR PLANT KEY 22 .

FEE 0 WATER

• FEEDWATER* FEEDWATER*

ISOLATION' CONTROL L0 FLOW VALVES VALVE -

. BYPASS CONTROL VALVE

, l l l AND

- - - V "_ .

- QR V

KEY.22 ~'

All four steam generators must be isolated. It is acceptable to use difforent success paths for ,

diiferent steam generators.

l 47520 9

lcA EOUIPMENT~ REQUIRED FOR SAFE SHUTDOWN

- PER c 10CFR50 APPENDIX R SQN-SQS4 ^127-Checked by/Date $./ //a.) 2j/offy' KEY 23 FEEDWATER PUMP TURBINE The, main' feedwater supply may be isolated by tripping the main feedwater pumps.

This key or key 22 is. required for secondary side isolation. Tripping the main feedwater control' pump requires closure of main feedwater pump turbine stop valves or valves.-

(Operation List)

'FCV-1-36) Either one Must Close FCV-1-37)

. FCV-1-38) Either one Must Close FCV-1-39)

FCV-1-43) Either one 'Must Close FCV-1-44)

FCV-1-45) Either one Must Close FCV-1-46) .

Note: "

If both pa'hs A & B of Key 20 (main steam isolation) are achieved, Key 23 will automatically be achieved. '

No spurious list is required for this key.

e*

O t

i A94

~

3446F/JMS J

. h5 __

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PIR 10CFR50 APPENDIX R Prepared by/Date .Nd d 2////43 SQN-SQS4-0127 Checked by/Dato Al & 4//>N?

MAIN FEEDWATER PUMP KEY 23 MAIN FEED." MAIN FEED PUMP TURBINE PUMP TURBillE STEAM STOP THROTTLE VALVE VALVE - .

At

,, . OR y

K.EY

.. 23 .

' i

, Steam supp'ly must be terminated to both feed pump turbines.

l

_ i-A95 47520

- EQUIPMENT REQUIitED FOR SAFE SifUTDOWN PER '10Cf1tSO APPENDIX R t* N . Y~# ~ O Prepared by/Date ,I' SQN-SQS4-0127' '

/;

Checked by/Date , NLC/h 4/8'f /"

KEY 24 - **

1 S/C BLOWDOWN ISOLATION To provide S/C blowdown isolation requires terminating blowdown flow from each steam generator and also assuring valves associated with the SG drain lines are also closed. ,

(Operation List)

~

FCV-43-55 '

FCV-1-7 Must close Must close OR .

FCV-1-181 ] Must close FCV-43-58 '

FCV-1-14 -

Must close OR -

' Must close

• .FCV-1-182_ \ Must close -

A

~

FCV-43-61 FCV-1-25 Must close Must close OR .

FCV-1-183 ]

Must close

? '

FCV-43-64 ~~

FCV-1-32 -

. Muse close OR Must close FCV-1-184

.- Must close

- OR

. -I VLV g 872 _

Must be closed VI$f868 l OR Mus t be closed OVLf869] , : Mus t be closed e VLV-'t i-XXX -

h.d- W. cloud m a See IJsle 1. 86 ke; w" b h u ng on P,y M7-

..- A96 3446F/JMS

=

.W

EQUIPMCiT REQUIRED FOR SAFE SHUTD0i!N .

FEA 10CTR50 APPENDIX R - '

. -Prepared by/ Data- O M ' Y-8"tr' .

SQM-SQS 4-0127... . . ' . . '

J' 'I; .;- ./*

Choeked by/Date NLC/N Ybfb b.

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.s, .. . . .

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.. .. ',??. .

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.m

. KEY 24 .

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. To Waste Disposal System -

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• Note 1 - Mandal isolation valves located in the Hot Samp'le Room (47W610-43-5)

. /. ,

must be closed should FCV-43-55 -58. -61, or -64 f ail to close.

. ,( % %.gt e h 46%yes oned,.kJ w'iN r., 34 reyec4've )

' ~

o

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. EQU8PMENT REQUIRED FOR SAFE SHUTDOWN

.PER 10CFR50 APPEflDfX R P1repared by/Date _7N

~SQN-SQS4-0127- t//o/3r Checked by/Date

f. / /4 J__2/MF8 SEQUOYAH NUCLEAR PLANT

• KEY 25 The secondary to provide secondarysafety sidevalves andcontrol.

pressure secondary relief valves (key 26) are required For each of the~two SGs being used for cooldown, term pressure the set of safety valves must be operable to provide short control.-

Operation List 1-VLV-00'.-5 2 2 1-VLV-00;-523] Must Operate 1-VLV-001-524 SGI Must Operate 1-VLV-001-525 Must Operate 1-VLV-001-52k_ Must Operate Must Operate 1-VLV-001-517 1-VLV-001-518 Must Operate 1-VLV-001-519 SG2 Must Operate 1-VLV-001-520 Must Operate Must 0perate 1-VLV-001-5 2_1 -

Must Operate 1-VLV-001-512 1-VLV-001-513 Must Operate' 1-VLV-001-514 Mus t _ Opera te

-SG3 -

1-VLV-001-515 Must Operaee Must.Operaee 1-VLV-001-51s_

Must Operate 1-VLV-001-527

, 1-VLV-001-528 Must Operate 1-VLV-001-529 SG4 Must Operate 1-VLV-001-530 Must Operate 1-VLV-001-531, Must Operate Must Operate Spurious List

• • PCV-1-5

• • PCV-1-12 Must Not Open

• • PCV-1-23 ,

J1ust Not Open ,

• • PCV-1-30 Must Not Open Must Not Open

*All valves, for any two SGs being used for cooldown , must be operable.

Operability assured by valve design.

• • If secondary side depressurization occurs, the operator must place the SG PORV handswitches in the "closed" position. ,

i A98

! 3446F/JMS

! ~

l _

L__ _

y' ~ ' '

7-- - -7 .; , .

4 EQUIPMENT REQUfRED FOR SAFE SHUTDOWN  ;

PER 10CFR50 APPENDIX R

.SQN-SQS4-0127 Prepared by/Date N 4, t-/'/e/'et l s

Checked by/Date ,A ?' d4.4 .UM_))9 SEQUOYAH NUCLEAR-PLANT KEY.26 SECONDARY = RELIEF VALVES

.The secondary pressure control'and relieffor.cooldown.

valves are required for. long-term, secondary side -

valves will be accessible-fez manual handwheel operation.The valves.are separated pressure is monitored in the'MCR for each~of the two loops being used forThe secondary side

-cooldown.

.being used' for cooldown. -The two valves which are chosen to operate must corres The othee two valves must not spuriously open.

' (0peration.Lisc)

PCV-1-5 )

PCV-1-12) Two Must. operate PCV-1-23) required

.PCV-1-30)

.For~ manual operation of the valves, any one of the three pressure _ indicators is. required for each of the two loops being used for cooldown.

Instrument loop P-1-2A (for Pi-1-2N) -

Must operate-Instrument loop,P-l-2B (for PI-1-2B) Any one' Must operate Instrument loop P-1-5 (for PI-1-5) _ Must operate Instrument'loopP-1-9A(forPI-1-9A[ Must operate Instrument loop P-1-9B (for PI-1-98) Any one Must operate

, Instrument loop P-1-12 (for PI-1-12) Must operate InstrumentloopP-1-20A(forPI-1-20i Must operate Instrument loop P-1-20B (for PI-1-20B) --Any one Must operate

- Instrument loop P-1-23 (for PI-1-23) ,_ Must operate InstrumentloopP-1-27A(forPI-1-27I5 Must operate Instrument' loop P-1-27B (for PI-1-27B) --Any one _Nust operate Instrument loop P-1-30 (for PI-1-30)

_ Must operate 4

m 9

i- =,

i. .

.I r

l I

i

' A99

3446F/JMS l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R' Prepared by/Dato Nti. #//a/34 SQN-SQS4-0127

,, Checked by/Dato _ M/ [ dst J//oA7 APPENDlX'A KEY 26 SECONDARY RELIEF VALVES "PCV-1-S S'.G. #1 -

OPERABILITY *PCV-1-12 S.G. #2

. PRESSURE -

OPERAEILITY PRESSURE INSTRUMENTAT10N

&~ CONTROL INSTRUMENTATION

& CONTROL i Ii lI

, . AND AND l .

• PCV-1-23 -

S.G. #3 ~

OPERABILITY "PCV-1-30 S.G. #4 PRESSURE OPERABillTY PRESSURE

' INSTRUMENTATION

& CONTP0L INSTRUMENTATION

& CONTROL l l l

l VV I

_y y

, AND

_, AND 2 out of 4 SGs

' Being used .

for Cooldown v gv AND t .

s ,,

KEY 26 47S20 Al00 .

?

EQUIPMENT' REQUIRED FOR SAFE SHUTDOWN Prepared by/Date DA# Y M !6

-PER 10CFR50 APPENDIX R SQN-SQSA-0127 Checked by/Date RLQM &hi APPENDIX A SEQUOYAH NUCLEAR PLANT Key 28 RCS PRESSilRE CONTROL In the event that the pressurizer heaters are lost, Sequoyah Nucicar Plant Special Startup Test No. 3. "Natural Circalation with loss of Pressurizer Heaters," determined that natural circulation conditions and saturation margin could be. developed and maintained under the degraded condition of loss of all pressurizer heaters. Furthermore, the depressurization rate over the te; ting

. period was approximately 100 psig/hr. A 10 percent increase in pressurizer level would result in.a greater than 100 psig pressure increase. Therefore

. charging the RCS to control pressure via level can be used in lieu of pressurizer heaters. Hence, the pressurizer heaters are not required for safe shutdown.

Additional backup for the validity of Special Startup Test No. 3 is provided by an analysis performed by Westint. house for the St. Lucie event of 1980. The results of this analysis shows that for a 25'F/ hour cooldown the pressure decay was 120 psi / hour and for a 50*F/ hour cooldown the pressure decay was 200 psi / hour. The pressurizer heaters were not modeled in the analysis.

(NEB 810501 301)

If the ability to depressurize the RCS using pressurizer sprays and PORVs is lost, reference 11.20 determined that the RCS could be depressurized to the

' RHR cut-in point by alternately filling and draining the pressurizer. For this reason, the keys associated with nake-up (keys 1, 2, 4, 5, 6, and 34) at.1

' letdown (Key 48) are included, since this method can be used as an alternate method of depressurizing the RCS.

j d

l l A101 3489F/JMS

EQUIPMENT REQUIRED FOR CAFE SMUTDOWN Prepared by/Dato_ #WM V"#-ed PER' 10CFR50 APPENDIX R p-Checked by/Dato_ RL( au 4/2 t/3g APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 28 Instrumentation One cold and one hot les temperature indicators are required for each of the NS-two loops being used for cooldown.

Instrument Loop T-68-1 (for TR-68-1P001) Must operate Instrument Loop T-68-18 (for TR-68-1P002) Must operate instruv.ent Loop T-68-41 (for TR-68-24P002) Must operate Instrunent Loop T-68-24 (for TR-68-24P001) Must operate I"nstrument Loop T-68-43 (for TR-68-43P001) Two Loops Must operate Instrument Loop T-68-60 (for TR-68-43P002) required Must operate Instrument Loop T-68-65 (for TR-68-65P001) Must operate Instrument Loop T-68-83 (for TR-68-68P002); . Must operate Instrument Loop P-68-69 (for PR-68-69) Any one Must operate Instrument Loop P-68-66. (for PI-68-66A) Must operate Instrument Ldop P-68-342C (for PI-68-342Al_ Must operate Spurious List _

• FCV-68-332 (Block Valve) og Must operat,e

• PCV-68-340A (PORV) 93 Must not open

• FCV-68-333 (Block Valve) Must operate OR OR

• PCV-68-334 (PORV)

Must not open PCV-68-340B'(Note 1) --

Must operate

, PCV-68-340D ( NJs i) Must operate Note 1: If PCV-68-340B spuriously opens, trip RCP No. 2.

spuriously opens, trip RCP No. 1 If PCV-68-3400

• For events 1nside or outside containment, the operator must be capabic of closing either of these valves in both paths (remotely from the MCR) if there is an excessive pressure decrease in the RCS, If this occurs, the ,

PORV and the block valve handswitches rust be placed in the closed position to prevent spurious opening due to the automatic pressure control circuits (e.g., PT-68-322, -323, -334, and -340).

- A102/04 y eno 3489F/JMS

• +

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date OW ' Wet:3 SQN-SQS4-0127 Checked by/Date_ /?LC/a=V/29/ai

-APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 28 Operational List -

t Preferred Flow Paths CCP A-A ~

CCP B-B -

Any One Hust Operate PDP Hust Operate .

Must operate AND FCV-62-84 (Auxiliary Spray)

Hust Operate OR PCV-63-340D (Normal Spray) ~'*

Reactor Coolant Pump #1 -

p.:st Operate Hust Be Available OR - ,

PCV-68-340B (Nonnal Spray) '

Reactor Coolant Pump #2 -

Hust Operate' ,

.

• Hust Be Available og'

' PCV-68-340A (Pressurizer PORV) ~ Hust Operate '

B7 FCV-68-332 (PORY Block Valve) - Hust Operate .

OR PCV-68-334 (Pressurizer PORV) Mutt Operate FCV-68-333 (PORV Block Valve) --

Hust Operate Alternate Flow Path - -

Le.fhe RCS P.chrup'Letd;= CA* 4 ase

~ Key 48 f.C5/ A

. M 4f%ktu(

n ss Key 1, 2. 4, 5, 6, anc' 34

( ,

e A1024 s 3'489F/JMS

i'repared by/Da teJ,);/ +2, . s g KEY 28 Reviewed by/Date (2L C /am V/29/ ff 6GO -Sqs4_ 27 '

CHARGING AUX SPRAY NORMAL SPRAY RCP NORS\L SPRAY RCP PUMP FCV-62-84 PCV-68-340D #1 PCV-68-340B a2 CCP-A CCP-B PDP V 'k VV Vy PORV'S AND BLOCK VALVES VWV PCV-68-340A FCV-68-332 PCV-68-334 PCV-68-333 I l V V V V

~

l .

PZR SPPN g CAPABILI'2Y Y V* RCP SEAL ECCS NORMAL INJECTION INJECTION CHARGING KEY 1,2,4 KEY 1.5,6 KEY 1,2,4,34 Vv y RCS WIDE RANCE ----

RCS TEMP. INSTR.

LETDOWN TE-68-1 YYV KEY 48

-IE-6 8- 18  ! -

TE-68-24 RCS WIDE RANGE TE-68-41 PRESSURE INSTR TE-68-43 '

PT-68-66 TE-68-60 PT-68-69 TE-68-65 l TE-68-83 m

e-a 5

(KEY 28 A103 0

e

r_: _

.n m y. . . .. C %Ushe.0 ~iUFsAr t. dntWOOi PER 10CFRSO APPENDIX =RL - Prepared b /DateMdhE/e i-SQN-SQS4-0127: Checked by/Date A?/ 8%A4 R/qjf

' APPENDIX A-Basis for Spurious List Key 28 Item ' Component Basis

-Loop-T-68-1 Loop-T-68-18 Simultaneous failure of two or more loops is highly unlikely. However, if 3 out of 4 were to spuriously fail, the operator would have no indication of temperature Loop-T-68-41 ( i . e . , Tavg ) .

Loop-T-68-24 Loop-T-68-43 -

Loop-T-68-60 Loop-T-68-65' toop-T-68-83 121 PCV-68-340A' The pressurizer power relief and block valve FCV-68-332 are in series and constitutes an integral portion of the RCS pressure boundary. If one of these valves were to spuriously open other 'ere -' pen a LCCA would result. g the could sst be closed 122 PCV-68-334 The pressurizer power relief and block valve

• FCV-68-333 are in series and constitutes an integral portion of the RCS pressure boundary. If one of thesevalvesweretospuriouslyopenwhtjethe ^^

other ".^: c r= a.4 W c^^n a LOCA would result.

le ele,eJ /E*' */"N3 123 PCV-68-340B l A spurious actuation resulting in the failure of PCV-68-340D the pressurizer spray valves to close will result in a depressurization transient.

d '

I W

l .

A104

. 3489 F/J.'!S l

, l '+[ ' .';ht!OIS$7TREQU$AEDFORSAF 6 SHUIDok

DURINC-AJDESIGN. BASIS FIRE Prepared by/Date f d. 8 M M 2/b/  !

Checked by/Dato 4', /. M wpog, '

' SQN.SQS4-0127.-

4r APPENDIX A i

SEQUOYAH NUCLEAR PLAffr XEY 28 RCS PRESSURE' CONTROL y; i i

4y  !

4 i

V>

~

~ .

1. y 4  !

,0  ;

P 4

. 8 I

L L

8 .

t P

i i

A105 j i

t b -

3489F/JMS t

4 U.1c.m nr.QU1HED FOR SAFE-SHUTCOWN Prepared by/Date N 4 [2d. M 32#/.

DURING A DESIGN BASIS FIRE SQN-SQS4-0127 Checked by/Date } S. D .2/ntf,

' ~

APPENDIX A Key 29 s

REACTOR TRIP Reactor _ trip breaker A or B may be tripped by the handswitches in the MCR.

Also, B.

the reactor may bo tripped using the motor-generator set breaker A or The reactor trip itself provides sufficient initial reactivity control.

Until a letdown path is established. RCS makeup should be limited to seal injection.

The makeup boron concentration must be greater than or equal to

-the RWST boron concentration. This will ensure subcriticality during cooldown to 200*F and an RHR letdown path is established for long term reactivity control >er i key 48 -(reference SOI 26.3).

(Operation List)

• Reactor Trip Breaker A HS-RT-1 or HS-RT-2 Must Trip l

OR

• Reactor Trip Breaker B HS-RT-1 or HS-RT-2 / 2/#8s Must Trip

_ ja*AND NI-318) Either one NI-32B) Must Operate Must Operate a The reactor can be manually shut cown from the main control room,'or if the fire damages the reactor trip breakers, the reactor can be manually shut down -

by de-energizing the control red drive motor-generators. There are four paths-to trip the reactor.

For each of two trains, there is a shunt trip path and an undervoltage trip path. The shunt trip path trips the reactor by energizing the shunt trip coil in the reactor trip switchgear through a handswitch contact in the main control room. The undervoltage trip path trips the reactor by de-energizing the undervoltage trip coil in the reactor trip switchgear through a handswitch contact in the main control room. For an undervoltage trip path to fail, a perfect short to another power source must occur.

For a shunt trip path to fail, the path must open without shorting.

It is therefore considered incredible that all four paths will fail in the specific fact thatmanner to disable cach respective path, particularly in light of the the trip handswitches in the main control room each utilize all four o

paths simultaneously when placed in the TRIP position, In addition..the reactor may be tripped locally at the' reactor trip switchgear and the motor-generator set supply breaker. Procedure FR-S.I. "ATWS", covers operator actions that may be required itt the highly unlikely event that all four paths fail in the manual trip circuits. The' reactor protection system will not be specifically protected from fire damage. The fall-safe design of the reactor protection system and diversity of input signals which can detect

• given event provide additional protection should an event occur before the operator could manually insert the control rods. The input signal cables are run in <

conduit which makes them less susceptible to fire damage. Fires which occur in the control building which are more threatening to the reactor protection system are fires for which the operator will manually insert the rods quickly to allow evacuation of the main control room.

A106 3489F/JMS s

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at.yu tay? FOR SAFE SiiUTCO'.v'4 DURING A DESIGN BASIS FIRE I>repared by/Date %'t2 /Mz//

SQN-SQS4-0127 Checited by/Date - #. /. @ .2pg ,

APPENDIX A the reactor may be tripped using the motor-generator ers.

re, b 9

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A107 3489F/JMS e

EQUIPMENT REQU3 RED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R Prepared by/Date NA[. 2/#/gs  ;

SQN-SQS4-0127 l

.. Checked by/Date f./ /A J .7//ostg l i

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APPENDIX A SEQUOYAH NUCI. EAR PI. ANT Key 29 REACTOR TRIP

Reaster Tras leetter Trip treaner A treater 8 , ,

1:5 47 8 er MS.47 1 er 115 4T.2 Set areamer A . Meter.Cenerater ) gewece gange.

ILS.47 2 38 8. 3 t*8 8e r L Insteattoe

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SQN-SQS4-0127 Checked by/Date _ #./ til 2//Oh

- ~ ~

APPENDIX A KEY 30 - RHR SHUTDOWN COOLING FLOW PATH The RHR system is required for long-term heat removal while bringing the plant to cold shutdown.

system. This key.i'dentifies the flow path needed for circulation of RCS acceptable. Handwheel operation of all valves required to provide the flow path is In addition, verification of flow rates can be done locally using pump suction and discharge pressure and a pump curve or utilizing clow indicators.

(Operation and Spurious List)

FCV-74-1 FCV-74-2 Must open

• FCV-74-32 Must open FCV-63-172 Must open Must not open Path 1 FCV-72-40, 41 FCV-63-8 Must not open KVC-74-36 Must not open FCV-63-72 Must operate FCV-63-93 Must not open FCV-74-16 Must not close FCV-74-3 Must remain open FCV-74-33 Must not close

• • FCV-74-12 Must not close -

FCV-74-35 Must open FI-63-91 Must close (See option note above)

Path 2 FCV-72-41, -40 FCV-63-11 Must not open -

Must not open FCV-74-21 FCV-74-28 Must not close FCV-63-94 Must remain open FCV-63-73 Must not close FCV-74-35 Must not open HCV-74-37 Must not close

• • FCV-74-24 Must operate Must open FCV-74-33 FI-63-92 " ' Must close (See option note above)

Note: Local and/or handwheel operation of all valves acceptable. Once valves are in proper position, the power should be removed to prevent spurious operation. TCV-b 3-17 2 a pue4euc h' :pca ; , ...,h...u -e ruul-aud - *- g st 2.u . .a -v u d. i- m i - -tm + & lh k ^L houn. **

• If valve is incapable of being used to throttle bypass flow around the heat ,

exchangers due to fire ef fects HCV-74-36 (path 1) or HCV-74-37 (path 2) t can be used as a throttle valve.

• • If miniflow valves are inoperable due to fit.: effects, the operator must l ensure a flow path to the RCS via the heat exchanger bypass prior to pump sta r t .

A109 l -

3489F/JMS

EQUIPMENT REQUIRED FOR SAFE ClluTDOWN Prepared by/Dato N A /

DURING A' DESIGN DASIS-FIRE 2.//c/tg Checked by/Date A.J. W 2j/opyf APPENDIX A I

se e paes A lof FCV-63-73 FCV-63-94 FCV-63-172 FCV-74-3f5 FCV-74-21 HCV-74-37 FCV-63-11 FcV 14-35 FCV-74-28 /<4 FCV-72-41 jND FCV-74-24 #/'/ff Must not open Hust not close ;6 a . ,m . a FCV-72-40,H FCV-63-93 FCV-63-8 FCV- 74-3/5 FCV-74-3 FCV-74-12 FCV-63-72 FCV-74-33 FCV-74-16 ff$rs FCV-63-172 3g g FCV-74-36 Huct not open Hust not Close iiu , u..A r AND (Path 2)

SeepysAlc1 FCV-74-1

+ vf FCV-74-32 AND (Path 1)

FCV-74-2 Must ^;- n;  %, ,

Hunt Open C P *4 8 r

l V

]ry 1r OR AND 1r KEY 30 o

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p.

SQN-SQS4-0127__ .

Checked by/ Data ~ f /, /kksi 1)ty '

. APPENDIX A r Key 30 Item "Component Basis 124 FCV-63-93 Spurious closure of this valve during RHR cooldown will terminate RHR. flow to Loops 2 & 3. Thus, the RHR cooldown path to loops 1 and 4 will be affected.

125 FCV-74-16 FCV-74-28 (Path 2) 'Same as item 124 heat reiaoval capability from path I will be terminated.

126. FCV-74-3 Same as item 124 If this were only heat FCV-74-21 (Path 2) removal path, reactor _ vessel temperature would start to rise.

127 FCV-63-172 FCV-74-33 Failure of these valves to maintain th'eir (for train B. required position will result in FCV-74-35) inability to maintain RHR cocidown path.

128' FCV-63-72 FCV-63-73 Spurious opening of these valves must be avoided to prevent draining the RWST to the containment sump and to prevent potential RHR

• pump cavitation during plant cooldown.

o t

. Alli t I

3489F/JMS t

. , w .LE.dEnr.yliARED FOR SAFE SHUTDOWN Propured'b'y/DateW 4 / M - t/n/c

,p . DURING:A DESIGN BASIS FIRE s

.SQN-SQS4-0127 f , Chseked by/Date /./ /'shi> 2,7fff, 4

APPENDIX A y ;.

'SEQUOYAH NUCLEAR PLANT Key 31 RHR. PUMPS

-long-term heat removal, one RHR pump and cooling to the associated heat ex. 'nger.are required. .The CCS is required RHR:s .

. I cooler and to the RHR heat exchanger.to provide cooling water to the The ERCW system is needed to supply cooling water to the CCS heat exchanger..

Component ar<*

satisfied..cooling and ERCW must be provided to assure RHR cooling requirements The same CCS and ERCW components used to achieve and maintain

. shutdown.

hot standby may be used for RHR system cooling while taking-the plant to cold To ensure sufficient heat removal when using only one CCS pump for CCS header A, the following nonessential loads must be isolated.

Non-Regenerative Letdown Heat Exchanger Spent Fuel Pit Heat Exchanger Cas Stripper and Boric Acid Evaporator Package

• If the train B CCS header is used for RHR cooling, the condensate .

demineralizer waste evaporator (CDWE) building must be isolated.

Operation List

. Path 1 '

.!WR pump A-A Must operate

• F V-70-156 Must open 0-FCV-70-197).Either one (Note 1) Must close 0-FCV-70-198 )

Path 2 " '

RHR pump B-B .

Must operate i

• FCV470-153 Must open

• Handwheel operation accepta bl e.

All2

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....:.. ar.yt. Ant.U r0.0 SAFE SilU rDOWN Prepared by/Date_N A. U b E/@-

'DURING A DESIGN BASIS FIRE SQN-SQS4-0127- -

APPENDIX A SEQUOYAH NUCLEAR PLMiT KEY 31 - RHR' Pumps Unit 1 Nonessential Loads ***

• 0-VLV-70-637) Either one Must be closed

• 0-VLV-70-661) Must be closed-

• 0-VLV-70-587) Either one Must be closed

• 0-VLV-70-574) Must be closed

• 0-VLV-70 636) Either one Must be closed

• 0-VLV-70-601) Must be closed Unit 2 Nonessential Loads ***

• 0-VLV-70-637) Either one Must be closed

• 0-VLV-70-661) Must be .losed

• 0-VLV-70-587) Either one Must be closed

• 0-VLV-70-574) Must be closed 0-FCV-70-193) Either one (Note 1) Must n'ot open 0-FCV-70-194) Must not open Note 1: If neither valve can be protected from spuriously opening, the following must be accomplished:

• FCV-70-40 Must close

• FCV-70-11 -

Any one ----. Must close

• 0-70-529A Must be closed

• FCV-70-41 Must close

• FCV-70-1 Any one- Mus'. close

• 0-70-529B Must be closed t

• 1-70-531 OR Must be closed

• Handwheel operation acceptable.

• • • See discussion on need isolate nonessential loads at start of this key.

A113 _.

3489F/JMS O

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EQUIPMENY REQUIRED FOR SAFE Shur 00'#N DURING A DESIGN BASIS FIRE Prepared by/Date U f//2 SON-SOS 4-0127 APPENDIX A ..,.

ERC'# COOLING ISOLATE NON- RHR PUMP A-A RHR PUMP 8-8 FOR CCS HTXs ESSENTIAL CCS AVAILABLE AVAIL A BLE LOADS l- 1 I CdSCOOLINGFOR RHR PUMPS AND OR' P.HR HTX l

"' I'I AND~ ..

I SUFFICIENT COOLING PROVIDED FOR RHR PUMPS TO tV -

FUNCTION AND

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EQU1PHEtiT REQUIRED FOR SAFE SituTD0Wil Prepared by/Dato_N d DURittG A DESlCtl BASIS FIRE E//1/#

SQti-SQS4-0127 Checked by/Date $ ,Y $A } 2//9/h APPEtlDIX A SEQUOYAH tlUCLEAR PLANT -

KEY 34 110RMAL CHARGIllG PATH The normal charging path is aligned during power operation. If the normal flow control valve (key 2),

FCV-62-93, is not available to throttle the charging flow, then the manual globe valves62-526 and 62-534 can be manually controlled to throttle the flow.

tiormal chargin's may be provided to the cold leg of loop 1 or the cold les of loop 4 Since either path may be in use, both paths must be -shown to be available at any time.

(Operation and Spurious List)

FCV-62-90 FCV-62-91 Hust Not Close/ Remain Operable Hust flot Close/ Remain Operable FCV-62-84 Must !!ot open FCV-62-85 ,

Hust Bo operable OR FCV-62-86 '

Hust Be Operable FCV-62-89 Hust flot close (Falls open) '

FCV-62 Hust Be Operable VLV-62-526 I l'

~

Hust Be Operable VLV-62-534 1 Must Be Operable e

er A115 3489F/JMS

E00lPMElli REQUIRED FOR SAFE SHUT 00Wil Prepared by/Date_

00 RING =A DESIGN BASIS FIRE M2

,..- SON-SOS 4-0127

., . Checked by/Datc_ f./. & .rn ,,

APPEN0lX A

. SEQUOYAH i1VCLEAR PLANT KEY 34

?!0RMAL CHARGillG PATH FCV-62-93 .

'FCV-62-89 MUST BE OPERABLE FCV-62-91 MUST NOT CLOSE FCV-62-90 MUST t10T CLOSE '

. . MUST NOT CLOSE t

62-526 'y y '

.and 62-534 'OR AVAILABLE l

yy V FCV-62-84 ANO CLOSE . FCV-62-8S FCV-62-86

! OPEN OPEN AL.

OR 5[y v AND l Y .

KEY 34 t

DNEl-S1860 A116 t -

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EQUIPMENT HEQUIRED FOR SAFE SHUTDOWN Prepared by/Dato f DURING A DESIGN BASIS FIRE M/;/K SQN-SQS4-0127 Checked by/Date_ #./. C 2//ajpr APPENDIX A Key 34 Item Component Basis 129 FCV-62-90 FCV-62-91 Any one valve will isolate makeup to the RCS if it spuriously closes.

FCV-62-89 FCV-62-93 130 FCV-62-86 This is an alternate charging path which must remain

, open if FCV-62-85 is closed.

131 FCV-62-84 Spurous opening of this valve would result in diversion of portion of charging flow. Thus level control _in RCS may be affected 131a FCV-62-85 S~purious closure of this valve will isolate the normal charging path.

If FCV-62-89 should. spuriously close manual bypass valve 62-538 can be used to reestablished normal makeup to RCS, to G

W I

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All?

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~

DURING A DESIGN BASIS FIRE SQN-SQS4-0127 .

1. #'N '

. APPEND 1lt A ,

NORMAL CHARGING PATH KEY 34-l y .

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- PER .10CFR50 APPENDIX- R- Prepared by/Date/AM8//e

.SQN-SQSA-0127- , '

APPENDIX A SEQUOYAH NUCLEAR PLMiT

, KEY 36 ACCUMULATOR ISOLATION As'the RCS depressurizes while the plant is brought to cold shutdown, the UHI and the cold leg. accumulators must be isolated.

URI isolation gag valves and the cold leg accumulator isolation valves.This If requires cl the accumulators cover gas. cannot be isolated, they must be depressurized by venting the Operation List UHI System:

87-550 Either one 87-552) _ - Must Open (depressurize tank)

Must Open (depressurize tank)

OR FCV-87-21 ) Either one FCV-87-22 ) Must Close Must Close AND FCV-87-23 ) Either one FCV-87-24 ) Must Close Must Close Note: Local Closure of all UHI valves acceptable. '

SIS Cold Leg Accumulators:

FCV-63-63 Accumulator No. 4 Vent  !

FCV-63-87 All must open to Accumulator No. 3 Vent, depressurize FCV-63-107 Accumulator No. 2 Vent FCV-63-127 accumulators Accumulator No. 1 Vent l

AND l

FCV-63-65 ' l Accumulators common v'e'nt i Must open Ad a g,s i Siff oR. -

It n ll'*l**

• FCV-63-67 FCV-63-80 Accumulator No. 4 Isolation Valve All must close to FCV-63-98 Accumulator No. 3 Isolation Valve isolate accumulators FCV-63-ll8 Accumulator No. 2 Isolation Valve Accumulator No. 1 Isolation Valve e NOTE: 100 Mar l{lol88 Prior to the RCS pressure dropping below 150 psig, the cold leg accumulators must intrusion into the RCS. Manual operationt af these

^^A valvesbe either isola is acceptable r^ct'SI: inside containment. (gygg l, (Reference SGN-SQ54-ot4q go#  ;

B45 811122, s+ L1) Al19 g tl"I" eer rz-m-iw ) c.nw~4c+e@~ - a uo r e ser m~<>.

4 3489F/JMS 3

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EOUlPMENT REQUIRED FOR SAFE SHUT 00WN Prepared by/Date 4 //6 7k 3/

OURING A DESIGN BASIS FIRE

~

SON-SOS 4-0127 .

Checked by/Date h 6 7//e/77 APPEND lX A ,.

KEY 36 - ACCUMULATOR-fSQLATION' - -

ISOLATE VENT ISOLATE VENT UHI NITROGEN SIS NITROGEN -

ACCUMULATOR FROM UH1 ACCUMULATORS FROM SIS .-.

ACCUMULATORS, ACCUMULATORS I

,r,r 3,,,

j 1

OR OR -

I

~

AND .

4 KEY 36 W

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ONEl-51860 A120

EQUIPHENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R prepared by/Dato_LM/ 1-ngo.

SQN-SQS4-0127 Chocked by/Date_ /?Ld/na 4/29/ff APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37 HVAC FOR COMPONENTS REQUIRED FOR HOT STANDBY AND COLD SHUTDOWN Thia key contains the HVAC equipment required to a:hieve and maintain hot standby.-

Refer to Key 40 for addi!!onal componento required to take the plant to cold shutdown.

Reference 11.13 the following' determined that HVAC is required for an Appendix R scenario in areas.:

Main control room air-conditioning Diesel generator building ventilation Turbine-driven auxiliary feedwater (TDAFW) pump room ventilation Centrigual charging pump room coolers Residual heat removal (RHR) pump room coolers (Key 40) 480 V transformer room ventilation Auxiliary building (AB) elevation 690' general floor air cooling (Key 370)

Reference 11.13 determined that, due to heat build-up in the following spaces (Elevation 690' penetration rcoms. Auxiliary instrument room, and Pressurizer bh heater transformer room) during the first 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of an Appendix R event, the designed cooling system or an equivalent system (i.e., temporary or general area ventilation) may be required after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, per reference 11.15, it should be noted that: "The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period allows sufficient time to restore offsite power, provide portable fans, or make repairs to HVAC equipment for longer term room cooling. Specific repair or corrective action procedures are noA (emphasis added) required for actions beyond this period."

Reference 11.13 also determined that the following HVAC systems are not required to support an Appendix R scenaria plant shutdown:

Steam valve vault ventilation 6.9 kV shutdown board room air-conditioning-480 V board room and battery room air-conditioning Cable spreading room ventilation

~

Essential raw cooling water (ERCW) pumping station ventilation Containment and containment instrument room cooling Component cooling system (CCS) and Spent fuel pit cooling (SFPC) pump coolers Pipe chase coolers o

A121 e

i 3489F/JMS 9

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y....m..udi.ys 6c.u tw 2 Art.'bitUfDOWN

'DURING A DESfGN-BASIS'FfRE Prepared by/Da 42 4 e/t >

SQN-SQS4-0127 Checked by/Date_4 1.lL 4.2//o/r! ,

APPENDIX A

~SEQUOYAH NUCLEAR PLANT KEY 37A i HVAC Appendix R Review Main Control Room Air Conditioning Operation List This set must operate or the set on the following page must operate.

A/C U A-A FC0 31A-20 Must run FSV 31A-20 .

Must open Must

• FC0 31A-176 de-energize

• Loop 31A-176 Must modulate TCV 31A-47 L instrument loop Must function TCV 31A-48 & instrement loop Must function TCV 31A-49 & instrument loop Must function TCV 31A-50 & instrument loop Must function FSV 31A-22A Must function FSV 31A-22B Must energize

• Loop 31A-22 Must energfze HS 31A-20A Must function HS 31A-20B Must function Must function

• Loop 31A-52 Loop 31A-136 .Must function Loop 31A-172 Must function '

Leop 31A-134 Must function Loop 31A-133 Must function Loop 31A-132 Must function Loop 31A-131 Must function Loop 31A-130 Must function Loop 31A-129 Must function Lcop 31A-128 Musy function Loop.31A-127 Must function Loop 31A-126 ,,

Must function Must function

• Control air required for this function.

Pbnudi control of these dampers can be taken to control main control room temperature in the event control air is not available.

. A122 3489F/JMS

g - --- -- q u i . . .J. i Kr.Qbine.u rw a r l:. SHdIDOWN -

DURING A DESIGN BASIS FIRE Pr epared by/Da te N48/C- /z/tt/

SQN-SQS4-0127. Checkcd by/Date_/ Z $4,,A .2//o/t.

' ~ ~

APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37A HVAC Appendix R Review Main Control Room Air Conditioning Operation List This set must operate or the set on the preceding page must operate. r A/C U B-B FC0 31A-23 Must run FSV 31A-23 Must open

• FC0 31A-177. Must de-energize

• Loop 31A-177 Must modulate TCV 31A-65 & loop Must function TCv 31A-66 &' loop Must function TCV 31A-67'& loop Must function TCV 31A-68 & loop Must function FSV 31A-39A Must function FSV 31A-39B Must energize

• Loop 31A-39 Must energize HS 31A-23A Must. function HS 31A-23B Must function Must function .

.*loop 31A-70

• Loop 31A-151 Must function Loop 31A-173 Must functicn Loop 31A-149 Must function Must function

. Loop 31A-148 '

- Loop 31A-147 Must function  :

Loop 31A-146 Must function Loop 31A-145 Must function Loop 31A-144 Must function Loop 31A-143 .Must function Loop 31A-142 Must function Loop 31A-141 Must function Must function.

• Control air required for this function.

Manual control of these dampers valve can be taken to control main control rocm temperature in the event control air is not available.

A123 B

3489F/JMS m

[ [. . . . i. . . [.liw . 5 r.u c vA 54r r.Sr:01 W.IN Prepared' by/Date 7kds//c'

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, PER'10CFR50~ APPENDIX R

^'

SQN-SQS4-0127

1. 1. 1. Y

- APPENDIX A SEQUOYAH NUCLEAR PLANT.

KEY 37A HVAC Appendix R Review Main Control Room Air Conditioning Path 1 (ERCW Header 1A)*

0-TCV-67-197**

Must Not Close Path 2 (ERCW Header IB)*

0-TCV-67-201**

Must Not Close t

• See Key 3 for ERCW cooling lineup.

• • Manually operated valves '

+

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EQUIPMENT .HEQUIRED FOR ' SAFE SHUTDOWN PER 10CFR50 APPENDIX R Preparad by/Date_ 044 +2YJTc_

.SQN-SQS4-0127 Checked by/Date /?LC/nsrqlLs/rf APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37B HVAC Appendix R Review Aux Inst Rooms Air Conditioning (Using Elec Board Room AHUs)

Operation List For the Auxiliary Instrument Room, reference 11.13 determined that heat build-up'due to a loss of cooling may necessitate that the designed cooling system (or an equivalent system) be reestablished after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the start of the event. .Therefore, local operator action may be required. hi However, reference 11.15 states that since sufficient time is available for repairs, specific procedures (pre-planned actions) are not required.

4 N

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?DURING~A DESIGN BASIS FIRE Prepared by/Dato 7628//. #E// /ts Chscksd by/Date_f.W ffwl Jjsopgl SQN-SQS4-0127 ,

t .

APPENDIX A SEQUOYAH NUCLEAR PLANT HVAC Appendix R Review KEY 37C Diesel Generator. Building Ventilation Operation and Spurious List "Diesel Generator Room'IA-A

-FCO-30-443 Must Open Elec. Panel / Gen. Fan Must Operate Exhaust Fan 1 HS-30-447B Must=0perate HS-30-4470 Must operate FCO-30-447 Must operate Must operate MD Exhaust Fan 2 Must Operate HS-30-451C HS-30-451B Must Operate FCO-30-451 Must Operate l Must Operate Electrical Board Room Unit lA-1 Elec. Bd. Rm. Ex. Fan Must Operate FCO-30-459 Must Open HS-30-459C Must Operate '

HS-30-459B Must operate .

9 The following instruments should not spuriously operate TS-30-451B) .A spurious low temperature signal would shut down the diesel TS-30-447B) room fans.

For both the electrical board room and diesel generator room, a spurious CO initiation signal should not occur. This would shut down the fans. 2 FCOs are motor operated. " '

O

, A126 3489F/JMS

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r.yutrAt..if REQUIRED FOR' SAFE SHUTD0b

' Prepared /Date 8 4. M 8 DURING-A DESIGN BASIS FIRE' /n/s SQN-SQS4-0127 ,

Checked by/ Dale // W .r/e/pf R '

APPENDIX A SEQUOYAH NUCLEAR PLANT HVAC Appendix R Review KEY 37C Diese'l Generator-Building Ventilation ,

Operation and Spurious List Diesel Generator Room 2A-A FCo-30-444 Must open Elec. Panel / Gen. Fan Must Operate Exhaust Fan 1 HS-30-448B Must Operate HS-30-448C. Must Operate '

FCO-30-448 Must Operate Must Operate AND Exhaust Fan 2 '

HS-30-452B Must Operate HS-30-452C Mus t Opera te FCO-30-452 Must Operate Must operate Electrical Board Room Unit 2A-A Elec. Bd. Rm. Ex. Fan Must Operate FCO-30-460 HS-30-460B Must Open HS-30-460C Must Operate

. Must operate -

The following instruments should not spuriously operate TS-30-44SB) A spurious low temperature signal would shut down the TS-30-452B) diesel room fans.

For both the initiation electrical signal should board room and diesel generator room, a spurious CO not occur. 2 This would shut down the fans.

FCOs are motor operated. ' '

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O A127 3489F/JMS e

r%'" gyssr.1t..n ~dt. QUIRED FOR SAFE dHUIDukN DURING A DESIGN BASIS FIRE,

. Prepared by/Date Ne2 2/u/

Chscksd by/Ds,te A./. 4%.h 2}/*/11 SQN-SQS4-0127 _ ,

APPENDIX A SEQUOYAH NUCLEAR PLANT HVAC Appendix R Review KEY 370 Diesel Generator Building Ventilation Operation and Spurious List Diesel Generator Room IB-B FCo-30-445 Must open Elec. Panel / Gen. Fan Must Operate Exhaust Fan 1 Must Operate HS-30-449B Must Operate HS-30-449C Must Operate FCO-30-449 , Must Operate AND Exhaust Fan 2 Must Operate HS-30-453B Must operate HS-30-453C Must Operate FCO-30-453 Must Operate Electrical Board Room Unit IB-B Elec. Bd. Rm Ex. Fan Must Operate FCO-30-461 Must Open HS-30-461B Must Operate HS-30-461C Must operate .

The following. instruments shculd not spuriously operate TS-30-453B). A spurious low temperature would shut down the diesel TS-30-449B) room fans.

For both the electrical board room and diesel generator room, a spurious CO2 initiation signal should not occur. This would shut down the fans.

FCOs are motor operated.

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, A128 3489F/JMS

.,....-.h o m .ac.u r u snet, shuTDoiN Preparedby/DateWk t/n, DURING A DESIGN BASIS FIRE Chscksd by/Date . #./, dh.4 .1/ W 1 APPENDIX A SEQUOYAH NUCLEAR PLANT HVAC Appendix R Review KEY 37C Diese'l Gentrator Building Ventilation Operation and Spurious List

. Diesel Generator Room 2B-B FCO-30-446 Must Open Elec. Panel / Gen. Fan Must Operate Exhaust Fan 1 HS-30-450B Must Operate HS-30-450C Must Operate FCO-30-450 Must Operate Must Operate AND Exhaust Fan 2 HS-30-454B Must Operate HS-30-454C Must Operate FCO-30-454 Must Operate Must Operate Electrical Board Room Unit 2B-B -

Elec. Bd. Rm. Ex. Fan Must Operate FCO-30-462 Must Open HS-30-462B Must Operate HS-30-462C ,

Must Operate The following' instruments should not spuriously operate TS-30-4505) A spurious low temperature signal would shut down the TS-30-454B). diesel room fans.

For both the electrical board room and diesel generator room, a spurious CO 2 initiation signal should not occur. This would shut down the fans.

FCOs are motor operated.

References:

47W866-9 (R8) 47W611-30-7 (R7) .

. A129 3489F/JMS

' W ..'..un nr.yuiar.U edR'SSFEl SHUTDOWN

DURING A DESIGN BASIS' FIRE- . Prepared by/Date ft1 [ M E/o/ ,

SQN-SQS4-0127- Chicked by/Date /./end. A/#/pf ,

APPENDIX A SEQUOYAH NUCLEAR _ PLANT HVAC Appendix'R Review KEY 37D Secam Valve Vault Ventilation System KEY.37D Operation during of the main the Appendix steam valve vault ventilation system is not required R scenario. This was a joint decision between <ain Kitchell, John Platfoot. Bobby Williams, and Emerson Rudacille made on August 10, 1984. .The decision was reached af ter it was pointed out that (1) the ventilation system is not safety related, and (2) components located in the steam valve vault required for shutdown are qualified for a main steam line break environment, a more seve~re criteria than loss of ventilation.

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- - - .7;Qasii'iida M QUikEDEFOR 5AFE SHUIDOWN DURING-~A DES!GN BASIS FIRE Prepared by/Date gct [M I M/4

'SQN-SQS4-0137 -

~

APPENDIX A SEQUOYAH NUCLEAR PLANT-

- KEY 37E Shutdown Boerd Room Air Conditioning Elevation 734 Equipment Needed for Plant Shutdown Following a Fire Per reference.11.13, cooling is not required for.this area..

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ll 'cyutrM NT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date

'DURING:A DESIGN BASIS' FIRE //A 4%

c SQN-SQS4-0127 Checksd by/Date / / ff,g j,,jg APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37F 480V Board Rooms and Battery Rooms Air Conditioning El 749

~ Per reference 11.13, cooling is not required 1for either the 480V Board Rooms IA,1A,15, 2B, nor for Battery Rooms I, II, III and IV. '

Note local operator action is required to validate assumptions made in reference 11.13 (see Appendix B of this document).

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- A132 3489F/JMS

c,,, [. c.yutkt.D FOR SAFE SHUIDOWN '

- DURING: A DESIGN BASIS FIRE ~

-Propared by/Date k [ d M/oe',

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. SQN-SQS4-0127 - - /#

-APPENDIX A SEQUOYAH NUCLEAR PIANT KEY 37G ,

10CFR Appendix R HVAC Review >

Cable Spreading Room *

-A requirement.for the use of ventilation for plant shutdown is not foreseen for.the cable spreading room as reviewed according to Appendix R guidelines. ,

However, the following points are. worth mentioning: ,

1.

The spreading room supply and exhaust fans are not-safety-related and are not required for shutdown, even during LOCA or HELB conditions. They are-

-powered from 480V reactor vent boards 1A-A and 1B-B (drawing 45W760-31-7). Those boards are load shed in the_ event of an accident.

(The board can, however, be loaded on the diesels -later if desired. )

2.

4 .

The largecooling portionload in the being spreading lights. . room is approximately 127,000 Btu /hr, a 4

3. >

-There is no vital heat-sensitive equipment or instrumentation located in the spreading room.

It is expected that it could get fairly warm in the '

spreading room with no adverse affects..

4.

If plant personnel decide to ventilate the spreading room af ter a fire, it could be accomplishid in several different. ways. If the supply fan .

and one 9xhaust fai are available these could be used, provided in-line dampers are opened either remotely or manually. Secondly, if the single supply fan isn't available, it's possible to ventilate the room with one

. exhaust opposite end fan of (if the usable) room.andOf by opening the door into the stairwell at the course, portable fans could also be used.

5.

To minimize heat buildup in the room during nonventilation periods, he

~

lights, which produce a significant amount of heat, could be turned off.  !

The fans are not required for shutdown, although there are several methods available to ventilate the spreading room, if desired. f l

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. A133  :

3489F/JMS i t

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EQUIPMENT REQUIRED FOR SAFE SHUTD0!!N Prepared by/Dato_d4V (LIf tp PER 10CFR50 APPENDIX R Checkcd by/Date_ ALChw 'IlL9/18 APPENDIX A SEQUOYAH NUCLEAR PLANT XEY 37H PRESSURIZER HEATER TRANSFORMER ROOM (EL 759) 10CFR50 APPENDIX R REVIEW The pressurizer heaters are not required for safe shutdown - see key 28.

However, because other essential equipment (see reference 11.17) required for safe shutdown is located in the Pressurizer Heater Transformer Room, reference 11.13 determined that heat build-up due to loss of cooling may necessitate that the designed cooling system (or an equivalent system) be re-established after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the start of the event. h1 Therefore, local operator action may be required. However, reference 11.15

,stta es s nce sufficient time is available for repairs, specific procedures i l (pre-planned actions) are not required.

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A134 3489F/JMS M

m . . . . c.. a nr.w ine.9 -Ud dArE dilUTD0'nN DURING A DESIGN BASIS FIRE Prepared by/Date N62 d M E//o/

SQN-SQS4-0127 Checked by/Date g / j d,,4 g g APPENDIX A (This page intentionally blank) t A135 MS9F/J.MS 9

I

-x....~... .sm a nc.u r un dar t. buufw N DURING A DESIGN BASIS FIRE Prepared by/Datefd 4/h/e SQN-SQS4-0127 Checked bylDato // &~ ~_ 2//oj77

' ~ '

APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 371 ERCW Eumping Station Drawing Ref: 37W900-3R6 -4R3 Per reference 11.13, cooling is not required for this area.

c 4 18 M

O A136 3489 F/ JF.S

EQUIPMENT REOUIRED FOR SAFE SituTD0'4N Prepared by/Dato__ CAV 4 u CO PER 10CFR50 APPENDIX R Checked by/Date_. /2LC/am e/2 9/8 SQN-SQS4-0127 1

APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37J Appendix R Review Containment Cooling System A temperature profile for lower containment has been developed assuming no containment cooling is available and assuming RCS blowdown (from the PORV's or RVMV's) to the PRT (reference 11.18).

The mass and energy released to containment following blowout of the PRT rupture disks vill produce an environment more severe than has been previously analyzed (excluding a HELB).

Mr0 and EEB have provided documentation (references 11.15 and 11.19) that all

.Appendix R safe required for equipment inside containment is qualified or fails in the position shutdown. Additionally, this documentation substantiated that several For example components were not "qualified" for the temperature excursion.

TM-68-1C, -24C. -43C, and --65C are not required except for fires inside the Control Building which require evacuation to the auxiliary control room; FSV-68-303 is not required for Appendix R. ,

In summary, containment cooling is not required for Appendix R.

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EQUIPMENT REQUIRED FCR OAFE OHUTDO'a'N Prepared by/Date_ dM V 71-EB PER 10CFR50 APPENDIX R SQN-SQS4-0127 Checked by/Dato RL C//tw '//29/F APPENDIX A SEQUOYAH NUCLEAR PLANT KE7 37K 480V TRANSFORMER ROOH VENTILATION EL 749 AUX BLDG Reference 11.13 has determined if ventilation is lost to one of the '

transformer rooms idue to a fire outside of the room) temporary ventilation at a rate of 5000 cfm of outside air must be supplied to that room. This measure must be taken withio 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (for rooms IA and 2B) and within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (for rooms 18 and 2A) fron, the staxt of the event. Additionally, the common board Rq transformers in rooms 1A and 2B usJst be load shed at one-half hour into the event. -

Note local operator action is needed to validate assumptions mado in

, Reference 11.13 (see Appendix 8 of this document).

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y. ....-. . .u.s v a n t.u r un dn e t, ditU 1DOWN DURING A DESIGN BASIS FIRE P re pa re .' by/Date XI/ M A Y4//,,

SQN-SQS4-0127 Checked ty/Date ,2 1. (d J 2//pfyY

~-

APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37L APPENDIX R REVIEW CONTAINMENT INSTRUMENT ROOM COOLING SYSTEM Per reference 11.13, cooling is not required for this area.

~

A139 34S9F/JMS w-

F-

f. s EQUIPMENT REQUIRED FOR SAFE SHUTDOWN t.

PER 10CFR50 APPENDIX R Prepared by/Date_ /lh/ /*df F9 Checked by/Date /(LC/ p 4/19/3.

i APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37H PENETRATION ROOM COOLERS

- Fot the Elevation 690' Penetration Room, reference 11.13 determined that heat build-up due .to a loss of cooling may necessitate that the designed cooling

,fstem the (or.an equivalent system) be re-established 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the start of event. Qq Therefore, local s

operator actions may be required. However, Reference 11.15 states since 'ufficient time is available for repairs, specific procedures (pre-planned actions) are not required.

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A140 3489F/JMS 5

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• worar a-ntQUIRED.FOR SAFE SilVTDOWN Prepared by/Date #d [ f//o/

.DURING A DESIGN BASIS FIRE.

, _ Checked by/Date_ M/ %jzajpg 4

APPENDIX A KEY 37N TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ROOM (TDAFWP)

UNIT 1, EL 669 Operation List DC Powered TDAFW Pump Room Exhaust' Fan Must Operate 1-HS-30-214 Must Operate 1-TS-30-214 Must operate Note: 1. The DC powered fan is connected to the vital batteries and is connected to the same power source to which the TDAFW pump controls are connected. The DC. fan will start upon pump start or upon high room temperature.

2. There is an AC powered fan available for cooling. However, this fan cannot be loaded onto the diesels.

3. There are no items . considered for spurious operation of the ventilation cooling for this space.

References:

47W866-2 R29 47W611-30-6 R14 -

47W610-30-6 R14 L

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A141 1

j 3489F/JMS i m l .

p _, . . i .i u at.yuthe.u von SAFE SilUTCOWN.

Prepared by/Date N67[Mr//o,

-DURING A DESIGN BASIS FIRE l

SQN-SQS4-0127 Checked b'y/DategA J/#/4, APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 37N TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ROOM (TDAFWP)

UNIT 2, EL 669 Operation List DC Powered TDAFW Pump Room Exhaust Fan 2-HS-30-214 Must Operate 2-TS-30-214 Must Operate Must Operate Note: 1. The DC powered fan.is connected to the vital batteries and is connected to the same power source to which the TDAFW pump controls are. connected. The DC fan will start upon pump start or upon high room temperature.

2. There is an AC powered fan available for cooling. nsever, this fan cannot be loaded onto the diesels.

3. There are no items considered for spurious operation of .the ventilation cooling for this space.

References:

47W866-il R19 47W611-30-6 R14 47W610-30-6 R14 9

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EQUIPMENT REQUIRED FOR SAFE SHttTDOWN Prepared bs/Date dJd h4 F5 PER 10CFRSO APPEtIDIX R Checked by/Date RLC/ ax 4/79/3' SQN-SQS4-0127 APPENDIX A SEQUOYAM NUCLEAR PLANT KEY 37 O BORIC ACID TRANSFER PUMPS & AFW

( PURPS COOLERS AND CCS & AFW PUMP COOLERS i

'2

'W Reference 11.13 determined that only one of the four auxiliary building S elevation 690' general floor area coolers (CCS & AFW pump space coolers and the AFW & Boric Acid Transfer pump space coolers) are required to operate for

( an Appendix R event, f This analysis is based upon one train of pumps (AFW & CCS) not being used

?-~~ after one-half hour into the event. That is, the analysis assumes only one

.AFW{and two CCS pumps are running one-half hour af ter losing the HVAC equipment.

Note local operator action is needed to validate assumptions made in Reference 11.13 (see Appendix B of this document).

F1 CCS/AFW pump space cooler 1A-A

• Must Operate *

• 1-FCV-67-162 CCS/AFW pump space cooler IB-B one out Must Operate

• 1-FCV-67-1Ci of four

~-~

' space BA/AFW pump space cooler 2A-A coolers Must Operate

• 2-FCV-67-217 BA/AFW pump space cooler 2B-B Must Operate

• 2-FCV-67-219

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• Manual operation is acceptable l

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- EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Dato. Ohld42/99 PER 10CFR50 APPENDIX R SQN-SQS4-0127 APPENDIX A SEQUOYAH NUCLEAR PLANT KEY.37 P.

CCS AND SPENT FUEL PUHP SPACE COOLERS (EL 714')'

Reference 11.13 determined that cooling is not required for this aret based upon operator actions described in Appendix B.

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. ; . . ... . . m t a c.u : r u n . sn r e, dit t.100h N -

-DURING.'A-DESIGN BASIS-FIRE Prepared by/DateTddz//s, SQN-SQS4-0127 Checked by/Date f / & pjgf,

• APPENDIX A

.SEQUOYAH NUCLEAR PIANT KEY 37R CHARGING PUMP COOLERS (EL 669)

Charging pump room cooling is included in Key 1.

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DURING A DESIGN BASIS FIRE Prepared by/DateNd[M//a, SQN-SQS4-0127 ,

. Checked by/ Data f f A M aja g APPENDIX A.

SEQUOYAH NUCLEAR PLANT KEY 37S AIR SUPPLY FOR HVAC The listedcomponents in Key 13.required for suppling control air to the HVAC equipment are Control Air Supply, Path 1 is required for all train A air-operated equipment unless manual control is available. Control Air Supply, Path 2, is required for all train B air-operated equipment unless manual control is available.

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APPENDIX A SEQUOYAH NUCLEAR. PLANT KEY 40 RHR PUMP COOLERS (EL 653)

When taking the plant from hot standby to cold shutdown, the only additional HVAC function required is RHR pump room cooling. This is supplied by the RHR pump room cooler with cooling water from the ERCW system.

Operation List RHR Pump 1A Cooling RHR cooler fan lA-A Must Operate

• Instrument loop 1-TS-30-175

• • 1-FCV-67-188 Must Operate Must Open RER Pump 1B Cooling .

RHR cooler fan IB-B

• Instrument loop 1-TS-30-176 Must Operate

• • l-FCV-67-190 Must Operate Must Open RHR Pump 2A Cooling RHR cooler fan 2A-A

• Instrument loop 2-TS-30-l75 Must Operate -

• • 2-FCV-6 7-188 Must Operate Must Open '

RHR Pump 2B Cooling RER cooler fan 2B-B

• Instrument loop 2-TS-30-176 Must Operate

• • 2-FCV-6 7-190 Must Operate. -

Must Open

• Fan motor control loop

• • A design change, has been made under ECN-L6258 *to remove air f rom 'this valve.

Valve has been failed in the open position.

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3489F/JMS 9

c.yu trMt.NT ' REQUIRED FOR SAFE SHOTDOW -

DURING A. DESIGN BASIS FIRE Prepared by/Date k // d M /a/s I' # ' #4I'

.SQN-SQS4-0127. ,

APPENDIX A SEQUOYAH NUCLEAR PLANT KEY 41 '

Key 41: Operator Integrity Communications capability: see reference 11.14 Lighting: see reference 11.8 and 11.14. (This establishes the requirements to implement 10CFR50 Appendix R, III.J.)

Access Control: Security systems and other door locking devices must not operate or fail to operate in a fashion that would prevent access by fire brigade or operators. Reference calculatio.:

EEB 841010 912.

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EQUIPMENT REQUIRED FOR SAFE SilVTDOWN prepared by/Date_[M/h pJ4 ps PER 10CFR50 APPENDIX R Checked by/Date /RLC/4-4 V/29/yf SQN-SQS4-0127 IPPENDIX A KEY 48 RCS LETDOWN CAPABILITY Reactor coolant system (RCS) makeup and letdown paths are used to control inventory by varying charging and letdown flow respectively. The components required for RCS makeup are defined in Keys 1, 2, 4, 5, 6 and 34. Along with inventory control, the makeup / letdown paths are also used to provide long term reactivity control by boration.

The availability of one of three paths (i.e. , normal, excess, or alternate letdown) will also provide an alternative means of depressurizing the RCS (see Key 28 and Appendix B).

$4 Normal Excess Letdown Alternate '

Letdown Letdown

_ _ ___ j

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RCS Letdown l

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EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepa ed by/Dato 04# d'N'fB PER 10CFR50 APPENDIX R i Checked by/Date RLC# 9. 4/29/f8 SQN-SQS4-0127 APPENDIX A KEY 48 RCS LETDOWN CAPABILITY

1) Normal Letdown During the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> followir.g an Appendix R fire, the operator can control RCS inventory, boration, and pressure by using the flow path defined by the following equipment:

FCV-62-69 Open FCV-62-70' Open FCV-62-72 )

Hust operate FCV-62-73 ) Any one Must operate FCV-62-74 )

Hust operate Normal Charging (Key'l.2,4,5 & 34) Must be available

• FCV-62-77 )

VLV-62-723 ) Close Either one Close -

RV-62-662 Si Must operate The above flow path can be used to control RCS pressure from 2235 psig to 600 psig.

To depressurize the RCS from 600 psig to the RHR cut-in point (380 psig)..two methods are available: ..

Method I The RCS will' depressurize from 600 psig to the RHR cut-in point due to cooldown caused by ambient heat losses'and decreasing core decay heat.

This meChod requires that all RCS make-up including RCP seal injection be terminated (i.e., securing the charging pump). However, this approach  ;

requires the thermal barrier heat exchangers and all supporting equipment be available to protect the RCP seals. RCS letdown through the RCP seals I i

to the PRT will enhance depressurization by draining the pressurizer.

The flow path utilizing thid option is defined by the following equipment:

NFCV-62-61 ) i Close X FCV-62-63 ) OR VLV-62-715 ) Close i Close ,'i RV-62-636 Operate Thermal Barrier Heat Exchanger (Key 9) ~'

Hust be i available  !

• • bdanval opentb'on is Accepfable.

A150 3489F/JMS l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date_ (M# 44149 PER 10CFR50 APPEND 2X.R Checked by/Date /2L C404 V/29/f t

, SQN-SQS4-0127 APPENDIX A KEY 48 RCS LETDOWN CAPABILITY l

Method II The RCS can also be depressurized from 600 psig to the RHR cut-in point l (using the pressurizer filling and draining process) by using the flow path defined by the following equipment:

FCV-62-69 Open FCV-62-70' Open FCV-62-72 ) Must Operate i FCV-62-73 ) Any One Must Operate FCV-62-74 ) Must Operate Normal Charging Must be (Key 1, 2, 4, 5, & 34) available

• FCV-62-77 Open PCV-62-81 Must Operate OR VLV-62-672 Sq Must Operate

• LCV-62-118 Open CCS to Letdown MX Must be (Either CCS,A or B &'ITCV-70-192) available

' hy

2) Excess Letdown If normal letdown is not available, the operator can elect to use the excess letdown path as defined by the following equipment:

p.Nd Ii FCV-62-54 . ..

Open FCV-62-55 Open FCV-62-56 Open FCV-62-59 ~

Open

• FCV-62-61 Open

• FCV-62-63 Open CCS to Excess Letdown MX Must be (CCS Pump A or B,#FCV-70-85, &TTCV-70-143) available <

CCS to Seal Water MX Must be (CCS Pump A or B) available

~

• Manual operation is acceptable.

b' b 3489F/JMS

T 64 N - Sci 34 - l 27 E utemen+ Re si<ed _ fer 9,epaad 6 lDar ** M*

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&fe. Skathwa per IOCFRSO Cheeked bgl DA Fw L' Appendix. R h ppendix A

. Keg 48

. RCS te+ dows Ggabmp

2) fxcess 'Lefdown (contino c d )

(Yethod 2: .

FcV-6a-5'f Open FCV- Go.- 55 Open .

FCV-6 A.- Sco Open -

PCV 5=1 0 pen .

-e FcV-c,1-G i Close t FcV- 6 3 -(o3 Close Pcv-6a Iis Aa&on8 Cl o se.

RV - c a - G 3(i M u s t Ope,it e.

1 CCs 40 Ex ce ss Letdown t% se be Ava. la ble.

Neaf 6.chger -

(CC3 pump A a 6, FCV ~1o-3 5l FcV-7o-14 Y)

1. Manual operation i s a.cceptable .

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EQUIPMENT: REQUIRED FOR SAFE SilVTDOWN PER 10CFR50 APPENDIX R Prepared by/Date_[M/ V4t ED SQN-SQS4-0127 Checked by/Date 4tf / m #/zf/tt APPENDIX A KEY 48 (Continued)

RCS LETDOWN CAPA3ILITY

3) Alternate Letdown In the event the nornal and excess letdown paths are not available, the following path can be used to control RCS pressure and/or inventory by filling and draining the pressurizer.

FCV-68-394

} Must open AND FCV-68-396 ]

OR Hust operate FCV-68-397 I Must operate OR FCV-68-395

, Must open i 7CV-68-396 l AND I Must operate

• OR FCV-68-397 i Must operate OR PCV-68-340A ] Must operate AND FCV-68-332 1 Must open OR PCV-68-334 l AND ~~

Must operate FCV-68-333 I Must open 4

A151 3489F/JMS

Prepared by/Date w N91v SGM-SGs4-lo.1 ,

Reviewdd by/Date Rt.( % v/ 9/tt 41 NORMAL LETDOWN (RCS Pressure 2 600- psig)

FCV-62-77 RV-62-662 FCV-62-77 PCV-62-81 CCS'to OR LCV-62-118 OR Letdown VLV-62-723 OPEN VLV-62-672 HX CLOSE-OPEN iP 1P c p ,

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== ,

FCV-62-69 FCV-62-72 Normal Chg FCV-62-70 OR Key 1.2,4, OPEN FCV-62-73 5 & 34 gg OR FCV-62-74 -

OBEN '

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(RCS Pressure < 600 psig)

FCV-62-61 Thermal RV-62-636 OR Barrier FCV-62-63 HX (Key 9) ['

OR V5V-62-715 crosv [

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k' A l52.

NORMAL e

LETDOWN '

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,=

SQ N -Sqs4 -l a? erepared by/Date _j).sg_ff c Reviewed/b /Datg ytt4gy/j/^),

EXCESS LETDOWN FCV-62-54 FCV-62-61 CCS tb CCS to FCV-62-55 'FCV-62-63 Seal Water Letdown FCV-62-56 HX HX FCV 62 59 CPE5! OPEN I t 4 l i l

CC{b FCV-62 61 RV-62-636

-gg OR FCV-62 63 OR V!.V 62-715 C?.0SE Excess L' Letdown f} ,

FCV-68-394 FCV-68-396 FCV-68-395 FCV-68-3 96 ~'

OR OR FCV-68-397 FCV-68-397 -

' 1 I I I t

t ti j ALTERNATE T.ETDOWN I

)I P

-m-

. PCV-68--340A PCV-68-334 .

FCV-68-332 FCV-68-333 - '

J' .-

Alternate Letdown Afg3 4

SG N-SCsS4 - 0117 APPEt40IX B OPERATOR ACTIONS e

0 4

w e

w 3445F,/JMS 81

tyuttMtNI dtQUIRED FOR SAFE 5 ur00aN PER 10CfR50 APPENDIX R prepared by/Date Ad[dz//o/gg

. Chscked by/Date__ A. A N/ J/MMY SQN-SQS4-0127 i! '

APPENDIX B OPERATOR ACTIONS

' Kev Comoonent Area of Action Comment 1.(path 1 Cent chg. pump Unit 1) A-A--- -Control room-- Assure pump running. If not running start pump. If pump fails to start then use bypass for auxiliary oil pump.

1 (path 2)

Unit 1)

Cent chg. pump B.B----Control room-- Assure purp running. If not running start pump. If pump fails to start, then use bypass for auxiliary oil pump.

2 VLV-62-534*~ - ---- -pl an t

~

If seal injection or e normal charging path is VLV-62-533 _ used for RCS makeup, one of these valves' must be OR.

open. If valve 534 is opened. valve 533 must be VLV-62-526*_ - - -- -- Pl an t closed. If valve 526 is opened, valve 527 must VLV-62-527 _ be closed.

OR FCV-62-93* h -----Control room _

Instrumant Loops-----Control room-.In the event of fire, the pressurizer level 68-320. -325, -339 indication should be closely monitored.

3 ERCW - -- --- -- - Pumping Manually clean traveling screens per 50!-67.1 header IA Station and 2A Verify flow usig local dischery pressure pd emP (v"'

3 ERCW ----------- Pumping - --- Manually clean traveling kreens per 50!-67.1 header IB Station Verify and 2B flow using local dischega. pressure sad eva e curve 4 LCV-62-132 ------ Plant OR or---- -One must be closed to ensure flow f ro he RWST.

Control room Handwheel operation acceptable. Note, however, that LCV-62-133, neither of these may be closed until key 5 has been established. In the event of a fire in an area that will effect these valves or associated circuitry, the operator should remove power from ttolh valves (by opening breakers at the MOV board) or switch over to the RWST. ,

L1-62-129--------Control room--In the event of a fire, the VCT level indication should be closely monitored. If the indication does not function properly (i.e., if 0% or 100% level is indicated, or erratic level indication cccurs) the operatar should oromotiv switch over to the RWST or oromotiv stop the operating CCP until switchover is achieved. Reactor should be tripped. ..

The VCT must also be isolated in the longer term by closing its outlet valves or depressurizing the VCT within 21. hours,

. . ~ - . . . _ -

3445f/JMS 92

cWitntNi atVUIRLO f 0R SME Trur00=N' Prepared by/Date N o. [ L/to/gg PER 10CFR50 APPEN0!X R Checked by/Date / .2//afg SQH-SQS4-0127 APpEN0!X B OPERATOR ACTIONS

' Kev Coroonent Area of Action Comment 5 (path I LCV-62-135' speci fic) ' Plant or ---Open for CCP suction from RWST. Handwheel operation control room' acceptable. In the event of a fire in an area that will af fect these valves or associated circuitry. .the operJtor should remove power from the valve in the flowpath being used (by opening breakers at the MOV board) to prevent spurious closure.

OR LCV-62-136_

LCV-62-132~

OR

--Plant or----Close to isolate VCT. Handwheel operation acceptable.

control room Handwheel must be used to close these if power has LCV-62-133_ been removed from them (see operator actions for Key 4).

OR LCV-62-135

--Plant or----Open for CCP suction from RWST. Handwheel operation OR Control room acceptable. "

LCV-62-136_

FSV-62-125 ---Control room--Open to depressurize VCT.

PCV-62-126 -

---Plant PCV-77-89 _ ---Plant OR VLV-62-689h Plant VLV-62-692~

---

Plant-----Close to isolate nitrogen and hydrogen supply VLV-62-693_ Plant headers. respectively.

Note:

If LCV-62-132 or -133 are not closed or if the VCT is greater than 17.03 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 15.91 psig in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, or 12.56 psig in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. then the RHR system must be available, the RCS temperature below 200'F. ano the CCP, stopped. ,

5 (path 2 FCV-63-6 " ---- --Plant ar ---Open for alternate CCP suction f rom RWST. Handwheel specific) OR control room

• operation acceptable. Once open. the operator should remove power from each of the valves in the flowpath to prevent spurious closure.

FCV-63-7 FCV-63-47 FCV-63-5 _

LCV-62-132~ --. -- -- Plant or ---Close to isolate VCT. Handwheel operation OR Control room acceptabk. Handwheel must be used to close LCV-62-133_ these if po-er has been removed from them. (See operator actions for Key 4).

3445' f/JM5 83

w w.e m o stVulWt0 FOR SAFE SHUiOOWNL Prepared by/Date M PER 10CFR50 APPEN0!X R 2//0/f8 SQN-SQS4-0127 Checksd by/Date M./ b 2//a/f7 APPEN0!X B OPERATOR ACTIONS Kev Coroonent Area of Action Comment 5 (both Containment spray -------Control room paths) Pump A-A --If spurious Phase B isolation signal is generated.

stop CS pump or close valve.

OR FCV-72-39 Control roo;;

Containment spray ---- --Control room Pump B-8 --If spurious Phase B isolation signal is generated.

stop CS pump or close valve.

OR FCV-72-2 Control room--

RHR Pump A-A-----------

Control room -- Stop pump i f i t spuriously starts.

FCV-74 ------ -- - - -Con trol room --Veri f y open i f RHR pump A-A sp- 'ously starts.

FCV-74 ---- ---- -- --Control room - Veri fy open i f RHR pump B-B spuriously s tart s.

FCV-63-1 ---- -- -- -- - --Con trol room -- Close to prevent RWST water back flow into the sump if FCV-63-72 and FCV-63-73 cannot be protected from spuriously opening. If this occurs. FCV-63-72 and FCV-63-73 must be manually closed before cooldown. .

RHR Pump B-B ---- ;----Control room -- Stop purp if it spuriously starts.

. 6 FCV-63-25~ -------Control room" Open one of these valves to provide ECCS charging OR path (through BIT) to the reactor vessel.

FCV-63 Control rooq.

~

FCV-63-39 --------Control room -Open one of these valves to provide ECCS charging OR path.(through BIT) to the reactor vessel.

FCV-63-4 Q_ Control root.

FCV-63-41 - -- -- -- -- -- -- Co n t rol r o om OR -C,1,ose any o.ne.to prevent diverting flow from charging path and back to the Boric Acid Tanks.

FCV-63-42 Control room OR -

VLV-63-574 Plant FCV-63-25--------Plant---- -fhrottle any as required to maintain RCS pressurizer FCV-63-26 level.

FCV-63-39 FCV-63-40 .

344SF/JMS B4 O

@.i;i..i MQuantu tud SM E SnUID0aN Prepared by/Date I[ d_ Z//o/f8 PER-10CFR50'APPEN0!X R

.$QN-$QS4-0127. Checked by/Date M 2 N 3 J/AP/#P APPENDIX B OPERATOR ACTIONS (ev Commenent Area of Action Comment 7 FCV-62-69 OR -------Control roo7-Close either to isolate letdown flow as required .

FCV-62-70 Control room OR FCV-62-72 Control room -Close whichever valve (s) is open to isolate letdown FCV-62-73 Control room flow as required.

FCV-62-74_ Control room _,

1&2-FSV-68-394------125V 1&2-FSV-68-395 vital---To preclude spurious opening of these valves pull Battery 182-FSV-68-396 fuses as identified in A0!-27A, Rev 6. page 3 of 9 Board I. '*

1&2-FSV-68-397 Panel 4 8

FCV-62-54-------Control room -Close any one (if all open) to isolate letdown path.

OR FCV-62-55 Control room OR FCV-62-56 Control room _ .

9- 1-FCV-70-133

---~~--Control room--A spurious Phase 8 containment isolation signal will 1-FCV-70-134 wait 1 Control room close thtse valves. They must be _ reopened for '

l-FCV-70-87 Control room cooling water to thermal barrier.

I-FCV-70-90_ Control room **

2-FCV-70-133

---

Control room-- A spurious Phase B containment isolation signal will 2-FCV-70-134 Unit 2 Control room close these valves. They must be reopened for 2-FCV-70-87 Control room cooling water to thermal barrier.

2-FCV-70-90_. Control room

- 1-VLV-70-545A'"-----Plant OR

---

Nust be closed i f 1-FCV-70-156 spuriously opens.

l-VLV-70-546A_ Plant -

~

2-VLV-70-545A - - - -- P l an t - - - w OR ust be closed if 2-FCV-70-156 spuriously opens.

2-VLV-70-546A_ Plant 3445T/JMS BS

--ww.e rou styyntu req SM L Shul 00=N ' prepared by/D.ste Nd

.PER 10CFR50 APPEN0!X R f//#[U

$QN-SQ$4-0127 Checked by/Date M I [/*d. 2//0/FF APPEN0!X B OPERATOR ACTIONS (ev Comoonent area of act+on Comment 9

0-FCV-67-197 -- -- ------ --Con t rol room' --Must be closed to isolate spent fuel pool heat OR 0-FCV-67-198 exchangers if both CC$ pumos IA-A and 18-8 are not Control room available.

OR l-70-531 Plant OR __

0-FCV-70 - ----Can t rol ~ea 0-FCV-70-Il Control room 0-70-529A Plant 0-FCV-70-41 Control room 0-FCV-70-1 Control room 0-70-5298.__ ----- - P l an t 0-FCV-70-40 ------Control rooI -Must be closed i f both 0-FCV-70-193 and 0-FCV-70-194 0-FCV-70-11 Cont.rol room 0-70-529A open and both CCS pumos ZA-A and 28-8 are not Plant available. '?ce :': ;;w.c 0-FCV-70-41 .s. siv..3 0-ici-;;-;;7 Control room ?

0-FCV-70-1 Control room

/fyj7,g 0-70-5298 Plant 1-70-531 Plant 10 N/A N/A No operator action required. '

11 AFW pump A-A ------------Control OR room--Verify one pump running and flowpath available. If AFW pump B-8 manual control is chosen for SG level, on/off operation of the pump is required, or manual throttling of the level control valves listed in the eperator actions list for Key 12. Refer to 50I-3.2, R30 for' manual throttilng of valves to control SG level using the AFW system.

12 Hanual valve 3-828 ---Plan 5 -----If path 1 automatic level control is used for SG OR 1 level control, throttle one of these valves.

or cycle the AFW pump on/of f to maintain level.

Manual valve 3-836, Plant

~ (See operator actions list for Key 11.) .

Refer to 501-3.2, R30. Section 02, for manual throttling of valves to control SG 1evel using the AFw system.

3445F/JMs 86

WutettNi HEQUIRED FOR SAFE SHUTOOWN Prepared by/Date. Nt2. [ d[IO/88 PER 10CFR50 APPEN0!X R SQN-SQS4-0127 Chacksd by/Date j ./, /M .2//p/#7 APPENDIX B OPERATOR ACTIONS Kev Comoonent Area of Action Comen t_

12 (Cont.) _

Manual valve 3-827

---Plant-----If path I automatic level control is used for SG OR 2 level control, throttle one of these valves, Manual valve 3-835 ---Plant or cycle the AfW pump on/off to maintain level.

(See operator actions list for Key 11.)

Refer to $0!-3.2, R30. Section D2, for manual throttling of valves to control SG level using the AFW system.

Manual-valve 3-826

---Plant-----if path 2 automatic level control is used for SG '

OR 3 level control, throttle one of these valves, or cycle the AfW pump on/off to maintain level.

Manual valve 3-834 ---/lant

~ (See operator actions list for Key 11.)

Refer to 50I-3.2, R30, Section D2, for manual throttling of valves to control SG level using the AfW system.

Manual valve 3-829 ---Plant----If path 2 automatic level control is used for SG.

OR 4 level control, throttle one of these valves.

or cycle the AfW pump on/of f to maintaio level.

Manual valve 3-837_ ---Plant (See operator actions list for Key 11.)

Refer to 50I-3.2, R30, Section 02, for manual throttling of valves to control SG level using the AfW system.

13 (path 1) Station air compressor A

---

Plant-----Must manually load" Compressor on diesels if aux air compressor not used.

OR Station air- ----- - Pl an t -

compressor B 13 (path 2) Station alr~

compressor A

---

Plant ----Must manual,ly. load compressor on diesels i f aux air compressor not used.

OR Station air -- -- -- Pl a n t

• compressor 8 344SF/JMS '

87

ov.,.. . sat stvuantu tud SAf t $hul00hN Prepared by/Date M b!"= //0/fg

.PER 10CfR50 APPEN0!X R _

SQN-SQS4-0127 Checked by/Date_. A. I. [ A f__edls /ff APPEN0!X 8 OPERATOR ACTIONS Kev Cocoonent Area of Action Covent 14 & 15 Turbine driven-- --- Control room Veri fy pump running and flowpath available, aux feedwater pump A-S 16 (auto control, Station air--------Must manually load compressor on diesel if auxiliary air compressor A cornpressor is not used.

path 1 OR and 2) Station air  !

compressor 8 16 (manual control.

LCV-3-17[-------Plant or---Manual control consists of remote operation from LCV-3-175 cont.rol room control room or handwheel operation in plant (SG path 1) level). Refer to SOI-3.2, R30, Section 02, for l manual throttling of valves to control SG level using '

the AFW system.

16 (manual control.

LCV-3-17[------Plant or---Manual control consists of remote operation from LCV-3-114 control room path 2)

~ control room or handwheel operation in plant (SG level). Refer to 50!-3.2. R30, Section 02, for manual throttling of. valves to control SG level using the AFW system. ,

- t 17 N/A N/A No operator action.

19 (path 1) ERCW headers----- ----- - -- Manuall y clean sc reens per 50!-67.1 1A and 2A (operation lists) \/9tif y flow, using local dUc hseg pressues daJ puaie tur n i

~

I e*

a==.

Y 88

ww.,K.ii uvuinto POR SAFE SHUf00WN Prepared by/Date N d PER 10CFR50 APPENDIX R Z//o/ff

_ Checked by/0ato__. M 2 d d .t //0/ty APPENDIX B OPERATOR ACTIONS Kev Cocoonent Area of Action Cowent FCV-3-116A~

FCV-3 116B

-- - -- Plant or ---Open f or motor-driven ATW pump A-.4 suction from control room ERCW af ter exhausting condensate storage tank.

Handwheel operat4on acceptable.

OR FCV-3-136A

---

Plant or ---Open for turbine-driven AFW pump suction from ERCW FCV-3-1360_ control af ter evhausting condensate storage tank.

room Handwheel operation acceptable.

19 (path 2)

ERCW headers ----------Manually clean screens per 50!.67.1 18 and 2B Verify flow usi (operation lists) ~

local clischer e. pressu't **J Pu=P cu"* -

19 FCV-3-126[

FCV-3-126B

---

Plan,t or---Open f or motor _ driven AFW pump B-B suction from control room ERCW af ter exhausting condensate storage tank.

Handwheel operation acceptable.

OR

• FCV-3-_175A FCV-3-179B

---

Plant or- --Open for turbine. driven AfW pump B-B suction from

~

control room ERCW after exhausting condensate storage tank.

Handwheel operation accept'able.

20 Control Power fuses---Plant-----In the event of d fire in the NCR, the operator Fn FCV-1-147 must pull the f. des in the control circuits for

-148 -149..-150 FCV-1-147 -148. -149. -150 to prevent possible spurious opening of these valves.

21 verify steam 1oad isolation.

.=--

22 verify main feedwater isolation.

23 Verify main feedwater pumps isolated. .*

3445F/JMS 89

EQUIPMENT REQUIRED FOR SAFE SHUIDOW Prepared by/Date O M 4 n-*f .

PER 10CFR50 APPEN0lX R t

Checked by/Date Al C/ A% '//zt/gt I SQN-SQS4-0127 APPEN0lX B I OPERATOR ACTIONS Key Correonent Area of Action Coninent 24 VLV-1-872 Plant Verify blowdown isolation or rnanually close these valves.

VLV-1-868 Plant OR YLV-1-869 Plant VLV-43-XXX Plant Verify FCV-43-55, -58, -61, or -64 closed or rnanually g close isolation valves in the Hot Sample Room (47610-43-5) (SG sample isolation valves).

25 PW-1-5 Control if secondary side depressurization occurs, operator PCV-1-12 Room nust p* ace the S/G PORY handswitch in CLOSED position.

PCV-1-23 PCV-1-30 26 PCV-1*5 (SG 1) Control room Remote or local control of any two required (rnust PCV-1-12 (SG 2) be to the same two SGs which are being used PCV-1-23 (SG 3) for cooldown).

PCV-1-30 (SG 4) 28 IF all pressurizer heaters are lost, THEN refer to A01-18 for cooldown instructions.

PCV-68-340A Control room Place respective handswitch in "closed" position if FCV-68-332 there is an excessive pressure decrease in the RCS.

PCV-68-334 ' ' '

FCV-68-333 RCP No. 1 Contr'ol room

~

Trip if PCV-68-3400 spuriously open RCP No. 2 control roan Trip if PCV-68-3408 spuriously open 3445F/JM5 810

4 $r;16 i dvu14t0 10R SAFE SHUf00W4 Prepared by/Date N A [ ##

PER 10CFR50 APPEN0!X R-SQN-SQS4-0127 APPENDIX B OPERATOR ACTIONS Kev Ca=aenent Area of Action Comen t 29 Reactortrif Control room breaker A (HS-RT-1 or HS-RT-2) ._

---Manually trip reactor if required.

QA Reactor trip -----Control room +

breaker B (HS-RT-1 or HS-RT-2)

Q3

~

M-G set breaker A ---- Pl a n t~l

---

Manually trip reactor with one of these breakers 3

A if fire damages the reactor trip breakers.

M-G set breaker 8 ----Pl an t

30. -e .

FCV-74-1 ------- Control room - -- Align flow path for RHR cooling FCV-74-2 or plant 3445F/JMS 811

\

-,.... .. =cwviatu tv< W E.St1UIDOWN Prepared by/Date 7f/2 2[/8/8F PER 10CFR50 APPEh0!X R Checked by/Date / / M M # # 8

~SQN-SQS4-0127 *

' APPENDIX 8 OPERATOR ACTIONS Kev Comoonent Area of Action Cemment 30 FCV-74-32 Plant Open to bypass flow around RHR heat exchangers. Use HCV-74-36 or HCV-74-37 if needed to throttle flow.

FCV-63-172 Plant If valve spuriously opens, . it must be reclosed. '-, im!

"^'

%-... W sto Ist 30 (path 1) FCV-72-40. -41 Plant An RHR flow path must be established and suf ficient flow FCV-63-8 verifled locally using pump suction ac1 discharge pressure and pump curve 03 flow indication.

HCV-74-36 FCV-63-72 FCV-63-93*

FCV-74-16  :

FCV-74-3 FCV-74-33 FCV-74-12 30 (path 2) FCV-72-41, -40 Plant See coment for path 1.

FCV-63-11 FCV-74-21 -

FCV-74-28 .

FCV-63-94 ..

FCV-63-73 ,

FCV-74-35 HCV-74-37 FCV-74-24

w. o 9

l .

i l

l I

e BilA

.w...vu

~

g. . ntyutatu'iuR SAFE hhUIDOW4 Prepared by/Date 'II A S //o/sg PER.10CFR50 APPEN0!X R lji 1

$QN SQ$4-0127 Checked by/Otte d ./ M fh&FF m

\ b i, APPEN0!X B

,- OPERATOR ACTION $~

Kev Comoonent Area of Action Coment

+

31 (path 1)

RHR' p6mp A-A-----Control room- --Start pump f or ,:csidc nn to cold shutdown, or stop pump if started on spurious $l signal.

FCV-70-156

---

Control room ---Open valve for coolirg water flow through RHR or plant heat exchanger. Handwheel operation acceptable.

0-FCV-70-197 - ---- Contrwl roos 0-FCV-70-198_ or plant OR FCV-70-40 ---Control room OR or plant FCV-70-Il OR 0-VLV-70-529A -

FCV-70-41 Close to isolate spent fuel pool heat exchangers.

---Control room OR ,er plant

• FCV-70-1 -

OR 0-70-5298 _

OR l-70-531 ] --Plant 1-VLV-70-637 - ----Pl an t **

OR l-VLV-70-661 -

1-VLV-70-587- --- --- Pl an t .

OR Close to isolate nonessential loads.

l-VLV-70-574 -

0-VLV-70-63I- ---- Pl an t OR 0-!$0L-70-601 -

4 l

e S

B12

' ' -wiretni st.VUIRED FOR SAFE SHUIDOWN-' Prepared by/Date d 2 II

- PER 10CFR$0 APPEN0!X R SQN-SQS4-0127 Checked by/Date M I M '2NNU ,

APPEN0!X B OPERATOR ACTIONS Kev Commanent Area of Action Comment 31 (unit 2, 2-VLV-70-637 Plant path-1) OR 2-VLV-70-6f1 L 2-VLV-70-538 Plant OR Close to isolate nonessential loads.

2-VLV-70-574 FCV-70-40 Control room OR or plant' FCV-70-ll OR 0-70-529A Close to isolate spent fuel pool heat exchangers

~

if 0-FCV-70-193 and 0-FCV-70-194 cannot be FCV-70-41 protected from spuriously opening.

- ---Cont rol room OR or plant FCV-70-1 OR OR

• 0-70-5298 -

1-70-53{. ---P1 ant 31 (path 2)

RHR pump B-B------Control room ---Start pump f ar cooldown to cold shutdown, or stop pump if started on spurious SI signal.

FCV-70-153-------Control room----Open valve for cooling water flow through RHR or plant heat exchanger. Handwheel operation acceptable.

~ 34 FCV-62-90

---

Control Rook .These valves will close.upon a spurious $!

signal. They will be required to be reopened.

FCV-62-91_-------Cont rol Room VLV-o2-526 - --- ~ ~ Pl an t OR Requires dedicated operator if desired to use valves for throttling VLV-62-53L 3445F/JMS, B13

EqulPMENT REQUIRED FOR SAFE SHUID0lJd Preparrd by/Date OA# 4*M W PER 10CFR50 APPEN0lX R SQN-SQS4-0127 APPENDIX B OPERATOR ACTIONS Key Caponent Area of Action Coment

,. 36 FCV-61-63 Plant or go Cu +-asy Prior to RCS pressure dropping below 457psig, FCV43-87 Control Rcan either the accumulators rnust be isolated or FCY43-107 depressurized by venting the nitrogen cover gas.

FCV43-127 Local operation is acceptable. C^^dhia m i mide AND

- = .tci = r.t a id s p. a M : 2 cess. D #*"'d8 FCV-63-65 Plant or Control Room

(,Re4 seg sosv.osv4 Ag o Btf Po ns v27 OR FCY4347 Plant or FCV-63-80 Control Rocyn FCV-63-98 FCV43-Il8

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

36 VLV-87-550 Plant Must open to depressurize UH1 gas accumulator if UHI OR isolation valves do not close.

VLV-87-552 Wege e a wegemeee e emem-ON e-eee _We4 - 4GWGGS

.-4S--G##OGW--4##****M*******************"**"***

e 9

l 1

I G

3445F/JMS 813 q

EQUIPMENT REQUIRED FOR SAFE SHUIDOWN Prepared by/Date yms 4 41.n PER 10CFR50 APPEN0lX R Checked by/Date /RLC//2u d29/f(

SQN.5QS4-0127 '

APPENDIX 8 Key Ca ponent Area of Action Conment 37A . Main ERCW header IA Manually clean traveling screens per 501-67.1. Verify.

Control Room- (operation list) flow using local discharge pressure and pump curve.

Air Conditioning ERCW header 18 Manually clean traveling screens per $01 67.1. Verify (operation list) flow using local discharge pressure and pump curve.

FCO-31A.176 Manual control of these HVAC dampers can be taken to FCO 31A-20 control MCR tenperature FCO-31A.177 FCo-31A-23 378 - Aux inst Auxiliary instru. In order to reduce the cooling load in these rooms, Room Air ment rocm lighting normal lighting must be turned out as soon as Conditioning HVAC possible, leaving only low wattage supplementary lighting. Due to heat build.up, cooling must be restored after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by use of tecporary g

• ventilation or the designed cooling system repaired, but reference 11.15 states specific pre-planned actions are not required.

37C . Diesel No operatcr, actions required for this key.

Generator Bldg ,

Yentilation

• 37D . Steam No operator actions required for this key.

Valve Vault Ventilation Sys 37F . 480V Rocrn I.lghting in order to reduce the cooling load in these rooms, Board and no. mal room lighting must be turned out as soon as Battery Boards M' possible, leaving only low wattage supplementary Air conditioning lighting.

370 - Cable No operator actions required for this key.

Spreading Room **

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

37H . Pressurizer HVAC Tetporary or general ventilation nnst be operational Heater Trans.

~

fonner Room within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter the start of the event due to heat build-up, but r(ference 11.15 states specific pre-planned actions are not required. /ty 37J No operator action is required for this key.

Containment

• Cooling

......... ......................................... ... ~..................._.........................

3445F/JMS B14 y + -- r p 3y --

g -

yn x.w.e.i..g . -wa w _i.w., - +

9

,(QUIPMENT REQUIRED'FOR SAFE Shul 00WN Pripared by/Date b d 94 e e> .

PER 10CFR50 APPEN0lX R SQN-SQS4 0127 Checked by/Date M / A d29/81 APPEN0lX B OPERATOR ACTIONS Key Conconent Area of Action Coment 37K - 480V Room 1A & 2B Plant Transfortner 5000 cfm of outside air must be supplied to the room Room within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Conmon board transformer must be load shed at one-half hour into the event.

Room IB & 2A Plant 5000 cfm of outside air snust be supplied to the room within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

370 AFW Room Lighting and BA in order to reduce the cooling load in these

'AFW & CCS Transfer; rooms, normal room lighting must be turned out CCS and as soon as possible leaving only low wattage AFNpwp supplementary lghting. Secure a1_l,but one AFW pwda,n{d two CCS pungsby

_ fl coolers one-half E5N after losing HVAC.

37M

__......................T_t!.?..-_....-

HVAC Penetration Ele. 690' penetration room cooling or adequate ventilation nwst be operational after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Room Cooler fran the start of the event, but reference 11.15 states specific pre. planned actions are not required.

J7P Room Lighting CCS & SFP Space In order to reduce the cooling load in tiese rocrns, normal room lighting must be turned out Cooler (El. 714) as soon as possibit- leaving only low wattage supplementary lighting.

' 37N - TDAFWP Rocrn Cooler No operator actions required for this key.

37R -

Charging No operator actions required for this key.

Pump Coolers (el 669) 375 -- ___ _..- ............ _

Air Supply No operator actions required for this key.

for HVAC 40- . . . . - . . .N/A

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

N/A No operator Action required.

ERCW to RHR Pwp Room Coolers 3445F/.1MS 815

F i

i EQUIPMENT REQUIRED FOR SAFE SHUTOOWN Preparsd by/Date__ 04# 414 Ett PER 10CFR50 APPEN0lX R Checked by/Date /?LC//A '//2.9/tf SQN-SQS4-0127 APPENDIX 8 48-RCS Normal Letdovn MCR The pripury purpose for RCS letdown is to letdown control RCS inventory. However, if the Capability Excess Letdown MCR pressurizer sprays and PORVs are not available normal, excess, and alternate letdown can be Alternate Letdown MCR used to dapressurize the RCS. Per reference 11.20, two methods are available to the operator to depressurize the RCS.

q Method I: The first method is to maintain {

pressurizer level at 25". of full scale using the ,

above letdown paths and let ambient heat losses depressurize the RCS to the RHR cut-in point.

' Method 11: If Method I is unacceptable, the RCS can be depressurized at a faster rate by using the above letdown paths to alternately fill and drain the pressurizer. This method has the effect of transporting mass and energy from the pressurizer to the RCS where it can be rejected. If this. method of depressurizing the RCS is used, the following' criteria must be satisfied:

• b

1. Pressurizer. indicated level must renuin between 20". and 80". of full scale.

2. RCS pressure must not exceed 2335 psig (PORY setpoint).

3. RCS tenperature and pressure cooldown limits shall conply with Tech. Spec. 3.4.9.1.

4. Pressurizer cooldown limits shall caTply with Tech. Spec. 3.4.9.2.

5. RCS subcooling rnargin shall be > 40*F. o Note: RCS subcooling nurgin should be as ,

- high as possible without vio!ating the Tech

• Spec conditions given in items 3 and 4 above, f,

Ref,, io Meg 48 h Appendix. A for

, pe,ao, m a. ch - '

/2m.

Ajnist +

344SF/JMS 816 1

t

[,

APPENDIX C

&nts in, (({S Append [v, denofsb wiYh as *% 9 are c.omponen$.5 AddeM be.fweto revidons 6 an d T $.e., new componenf.s).

• • CAUTION. This appendix is nothing more than an index to assist the user -

in locating specific requirements in the docucent. Since these specific requirements are often complex, they are expressed in Appendix A using conditional logic statements which tie the requirement to operability of other components. The reader is cautioned that the listing of a component in this appendix should not be considered as a requirement for that component without.first consulting the appropriate shutdown path in Appendix A.

VM in p u n N ;. e d 1[oM NOSE '. Tk Tw Lsm .ae) t in a ,'s Appen A7 a v.rdse: 6.'k uc0 acc. no+ +e 6e- used' wrVL Revisjan g of Als ca.lch-Son. Thi> Appendin does no+ list indrumentation -Foun~f {r A p pen d(y D ,, j 5, 2lIt S 98 e

i

- EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date DURING A DESIGN BASIS FIRE

, p, //[o g5 SQN-SQS4-0127 Checked by/Date M [ ' (/ z[#/ Fir APPENDIX C Shutdown Logic Component List Main Steam (1)

Key Reference Component (Item) Drawing Description 1&2-PI-1-2A 26 47W610-1-1 Main Steam Pressure Indication - Loop 1 1&2-PI-1-2B 26 47W610-1-1 1&2-FCV-1-4 Main Steam Pressure Indication - Loop 1 20 47W801-1 MSIV - Loop 1 1&2-FSV-1-4A 20 47W610-1-1 Loop 1 MSIV Air Supply Solenoid 1&2-FSV-1-4B 20 47W610-1-1 Loop 1 MSIV Air Supply Solenoid 1&2-FSV-1-4D 20 47W610-1-1 Loop 1 MSIV Air Vent Solenoid 1&2-FSV-1-4E 20 47W610-1-1 Loop 1 MSIV Air Vent Solenoid 1&2-FSV-1-4F 20 47W610-1-1 Loop 1 MSIV Test Solenoid 1&2-FSV-1-4G 20 47W610-1-1 Loop 1 MSIV Air Vent Solenoid 162-FSV-1-4H 20 ~47W610-1-1 Loop 1 MSIV Air Vent Solenoid 1&2-FSV-1-4J 20 47W610-1-1 Loop 1 MSIV Test Solenoid '

I&2-P-1-5 26 47W610-1-1 Loop 1 Atmospheric Relief Valve Control 1&2-PCV-1-5 . 26 47W801-1 Loop 1 Atmospheric Relief Valve ,

1&2-FCV-1-7 24 47W801-2 Steam Generator 1 Blowdown Isolation Valve 1&2-P-1-9A 26 47W610-1-1 Main Steam Pressure Indication Loop 2

-1&2-P-1-98 26 47W610-1-1 Main Steam Pressure - Indication Loop 2 1&2-FCV-1-11 20 47W801-1 MSIV - Loop 2 1&2-FSV-1-11A 20 47W610-1-1 Loop 2 MSIV Air Supply Solenoid 1&2-FSV-1-11B 20 47W610-1-1 Loop 2 MSIV Air Supply Solenoid 162-FSV-1-11D 20 47W610-1-1 Loop 2 MSIV Air Vent Solenoid 1&2-FSV-1-11E 20 47W610-1-1 Loop 2 MSIV Air Vent Solenoid 1&2-FSV-1-11F 20 47W610-1-1 . Loop 2 HSIV Test Solenoid 1&2-FSV-1-11G 20 47W610-1-1 Loop 2 MSIV Air Vent Solenoid

'l&2-FSV-1-11H 20 47W610-1-1 Loop 2 MSIV Air Vent Solenoid 1&2-FSV-1-11J 20 47W610-1-1 Loop 2 MSIV Test Solenoid G

W C1 DNE4-1639

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date ) @ PIO MT DURING A DESIGN BASIS FIRE / /

SQN-SQS4-0127 Checked by/Date N 8( b ('72//o/tg APPENDIX C Shutdown Logic Component List Main Steam (1) (Continued)

Key Reference Component (Item) Drawing Description 1&2-P-1-12 26 47W610-1-1 Loop 2 Atmospheric Relief Valve Control 1&2-PCV-1-12 26 47W801-1 Loop 2 Atmospheric Relief Valve Control 1&2-FCV-1-14 24 47W801-2 1&2-FCV-1-15 SG 2 Blowdown Isolation Valve 14,15 47W803-2 AFPT Steam Supply from SG No. 1 (116) l~

1&2-FCV-1-16 14,15 47W803-2 AFPT Supp'.y from SG No. 4 (117) 1&2-FCV-1-17 14,15 47W803-2 Steam Flow Isolation to AFPT (115) 1&2-FCV-1-18 14,15 47W803-2 Steam Flow Isolation to AFPT

. (115) 1&2-P-1-20A 26 47W610-1-2 Main Steam Pressure Indication Loop 3 -

1&2-P-1-20B

• 26 47W610-1-2 Main Steam Pressure Indication loop 3 1&2-FCV-1-22 20 47W801-1 MSIV - Loop 3 1&2-FSV-1-22A 20 47W610-1-2 Loop 3 MSIV Air Supply Solenoid 1&2-FSV-1-22B 20 47W610-1-2 Loop 3 MSIV Air Supply Solenoid 1&2-FSV-1-22D 20 47W610-1-2 Loop 3 MSIV Air Vent Solenoid 1&2-FSV-1-22E 20 47W610-1-2 Loop 3 MSIV Air Vent Solenoid 1&2-FSV-1-22F '20 47W610-1-2 Loop 3 MSIV Test Solenoid 1&2-FSV-1-22G 20 47W610-1-2 Loop 3 MSIV Air Vent Solenoid 1&2-FSV-1-22H 20 47W610-1-1 Loop 3 MSIV Air Vent Solenoid 1&2-FSV-1-22J 20 47W510-1-2 Loop 3 MSIV Test Solenoid 1&2-P-1-23 26 47W610-1-2 . Loop 3 Main. Steam Pressure Indication 1&2-PCV-1-23 26 47W801-1 Loop 3 Atmospheric Relief Valve 1&2-FCV-1-25 24 47U801-2' Steam Generator 3 Blowdown Isolation Valve, C2 DNE4-1639

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESIGN BASIS FIRE Ptspartdby/Date) /5'5' Checked by/Date N 4 #

l[to/ff SQN-SQS4-0127 APPENDIX C Shutdown Logic Component List Main Steam (1) (Continued)

Key Reference Component (Item) Drawing Description 1&2-P-1-27A 26 47W610-1-2 Loop 4 Main Steam Pressure Indication 1&2-P-1-27B 26 47W610-1-2 Loop 4 Main Steam Pressure Indication 1&2-FCV-1-29 20 47W801-1 MSIV - Loop 4 1&2-FSV-1-29A 20 47W610-1-2, 1&2-7SV-1-29B Loop 4 MSIV Air Supply Solenoid 20 . 47W610-1-2 Loop 4 MSIV Air Supply Solenoid 1&2-FSV-1-29D 20 47W610-1-2 Loop 4 MSIV Air Vent Solenoid 1&2-FSV-1-29E 20 47W610-1-2 Loop 4 MSIV Air Vent Solenoid 162-FSV-1-29F -20 47W610-1-2 Loop 4 MSIV Test Solenoid 1&2-FSV-1-29G 20 47W610-1-2 Loop 4 MSIV Air Vent Solenoid 162-FSV-1-29H 20 47W610-1-2 Loop 4 MSIV Air Vent Solenoid 1&2-FSV-1-29J 20 47W610-1-2 Loop 4 MSIV Test Solenoid 1&2-P-1-30 26 47W610-1-2 Loop 4 Main Steam Pressure Indication -

1&2-PCV-1-30 -

26 47W801-1 Loop 4 Atmospheric Relief Valve 1&2-FCV-1-32 24 47W801-2 1&2-FCV-1-36 SG 4 Blowdown Isolation Valve 21,23 47W801-1 High Pressure Stop Valve to HFPT A 1&2-FCV-1-37 21.23 47W801-1 High Pressure Control Valve to MFPT A 1&2-FCV-1-38 23 47W801-1 1&2-FCV-1-39 Low Pressure Control Valve to HFPT A 23 47W801-1 Low Pressure Stop Valve to MFPT A 1&2-FCV-1-43 21,23 47W801-1 High Pressure Stop Valve to HFPT B 1&2-FCV-1-44 21,23 47W801-1 High Pressure Control Valve to MFPT B 1&2-FCV-1-45 23 47W801-1 Low Pressure Control Valve to MFPT B 1&2-FCV-1-46 23 47W801-1 Low Pressure Stop Valve to MFPT B

'l&2-FCV-1-51 14,15 47W803-2 AFPT Trip & Throttle Valve

- (114) 1&2-FCV-1-52 14,15 47W610-1-1 AFFT Governor Valve 1&2-FCV-1-61 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine C3-DNE4-1639

h EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date36f2/I 5

.DURING A DESIGN BASIS FIRE '/

Checked by/Date N A [ Z//0/88 SQN-SQS4-0127 APPENDIX C Shutdown Logic Component , List Main Steam (1) (Continued)

Key Reference Component (Item) Drawing. Description 1&2-FCV-1-62 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine 1&2-FCV-1-64 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine 1&2-FCV-1-65 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine 1&2-FCV-1-67 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine 1&2-FCV-1-68 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine

-1&2-FCV-1-70 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine 1&2-FCV-1-71 21 47W801-1 Main Steam Stop and Control Valve to High Pressure Turbine -

1&2-FCV-1-75 -

21 47W801-1 Main Steam to MSR A2 1 &2--FCV-1-77 21 47W801-1 Main Steam to MSR B2 1&2-FC7-1-79 21 47W801-1 Main Steam to MSR C2 1&2-TCV-1-84 21 47W801-1 Main Steam to MSR A1 1&2-FCV-1-91 21 47W801-1 Main Steam to MSR B1 1&2-FCV-1-98 21 47W801-1 Main Steam to MSR C1 1&2-FCV-1-103 '21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-104 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-105 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-106 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-107 21 47W801-1 . Main Steam Dump Valve .

.1&2-FCV-1-108 21 47W801-1 Main Steam Dump Valve

'l&2-FCV-1-109 21 47W801-1 Main ~ Steam Dump Valve 1&2-FCV-1-110 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-111 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-112 '

21 47W801-1 Main Steam Du=p Valve 1&2-FCV-1-113 21 47W801-1 Main Steam Dump Valve 1&2-FCV-1-114 21 47W801-1 Main Steam Dunp Valve -

C4 DNE4-1639

EQUIPMERT REQUIRED FOR SAFE SHUTDOWN Preptr;d by/D3ts Y 8 F/e/JS DURING A DESIGN BASIS FIRE ' /

SQN-SQS4-0127 Checked by/Date $[YZl/c/68 APPENDIX C Main Steam (1) (Continued)

Key Reference Component (Item) Drawing Description 1&2-FCV-1-147 20 47W801-1 MSIV Bypass Valve 1&2-FCV-1-148 20 47W801-1 MSIV Bypass Valve 1&2-FCV-1-149 20 47W801-1 MSIV Bypass Valve 162-FCV-1-150 20 47W801-1 MSIV Bypass Valve 1&2-FCV-1-181 24 47W801-2 SG 1 Blowdown Containment Isolation Valve 1&2-FCV-1-182 24 47W801-2 SG 2 Blowdown Containment Isolation Valve 1&2-FCV-1-183 24 47W801-2 SG 3 Blowdown Containment Isolation Valve 1&2-FCV-1-184 24 47W801-2 SG 4 Blowdown Containment Isolation Valve 1&2-FCV-1-275 21 47W801-1 MSR A2 Low Power Bypass Valve 1&2-FCV-1-277 21 47W801-1 MSR B2 Low Power Bypass Valve 1&2-FCV-1-279 21 47W801-1 MSR C2 Low Power Bypass Valve 1&2-FCV-1-284 21 47W801-1 MSR Al Low Power Bypass Valve 1&2-FCV-1-291 21 47W801-1 MSR B1 Low Power Bypass Valve 162-FCV-1-298 21 47W801-1 MSR C1 Low Power Bypass Valve 1-VLV-1-512 25 47W801-1 Main Steam Safety Valve from SG 3 1-VLV-1-513 25 47W801-1 Main Steam Safety Valve from SG 3 1-VLV-1-514 25 47W801-1 Main Steam Safety Valve from SG 3 .

1-VLV-1-515 25 47W801-1 Main Steam Safety Valve from SG 3 1-VLV-1-516 25 47W801-1 Main Steam Safety Valve from SG 3 '

1-VLV-1-517 25 47W801-1 Main Steam Safety Valve from SG 2 1-VLV-1-518 25 47W801-1 Main Steam Safety Valve from SG 2 1-VLV-1-519 25 47W801-1 Main Steam Safety Valve from SG 2 1-VLV-1-520 25 47W801-1 Main Steam Safety Valve from SG 2 1-VLV-1-521 25 47W801-1 Main Steam Safety Valve from SG 2 1-VLV-1-522 25 47W801-1 Main Steam Safety Valve from SG 1 1-VLV-1-523 25 47W801-1 Main Steam Safety Valve from SG 1 1-VLV-1-524 25 47W801-1 Main Steam Safety Valve from SG 1 1-VLV-1-525 25 47W801-1 Hein Steam Safety Valve from SG 1 1-VLV-1-526 25 47W801-1 Main Steam Safety Valve from SG 1

_ 1-VLV-1-527 25 47W801-1 Hain Steam Safety Valve from SG 1 1-VLV-1-528 25 47W801-1 Main Steam Safety Valve from SG 4 1-VLV-1-529 25 47W801-1 Main Steam Safety Valve from SG 4 1-VLV-1-530 25 47W801-1 Main Steam Safety Valve from SG 4 1-VLV-1-531 25 47W801-1 Main Steam Safety Valve from SG 4 .-

1-VLV-1-868 24 47W801-2 SG Blowdown Heat Exchanger Isolation Valve 1-VLV-1-869 24 47W801-2 SG Blowdown Heat Exchanger Isolatioa Valve 1-VLV-1-872 24 47W801-2 SG Draindown Isolation Valve C5 DNE4-1639

]

iEQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESIGN BASIS FIRE Prepared by/Date_Nd;r/;y(rg Checked by/Date N d /~ 4//ggg 4

SQN-SQS'-0127 APPENDIX C Main & Auxiliary Feedwater (3)

Key Reference Comoonent (Item) Drawing Description AFW motor- 11 47W803-2 Motor Driven Auxiliary Feedwater Pump driven pump A-A AFW motor- 11 47W803-2 Motor Driven Auxiliary Feedwater Pump driven pump B-B AFW turbine driven Pump A-S 14&l5 47W803-2 Turbine Driven Auxiliary Feedwater s Pump 1&2-FCV-3-33 22 47W803-1 SG 1 Main Feedwater Isolation Valve 1&2-FCV-3-35 22 47W803-1 SG 1 Main Feedwater Control Valve 1&2-FCV-3-35A 22 47W610-3-1 Feedwater Low Load Bypass to SG 1

'1&2-L-3-39 12.16 47W610-3-1 SG No. 1 NR Level Loop

• 1&2-L-3-43 12,16 47W610-3-1 SG No. 1 WR Level Loop .

1&2-FCV-3-47 22 47W803-1 SG 2 MFW Isolation, Valve 1&2-FCV-3-48 22 47W803-1 SG 2 MFW Control Valve 162-FCV-3-48A 22 47W610-3-1 Feedwater Low Load Bypass to SG 2 1&2-L-3-52 12.16 47W610-3-1 SG 2 NR Level Loop '

162-L-3-56 12,16 47W610-3-1 SG 2 WR Level Loop 1&2-FCV-3-87 22 47W803-1 SG 3'KFW Is'olation Valve 2&2-FCV-3-90 22 47W803-1 SG 3 MFW Control Valve 1&2-FCV-3-90A 22 47W610-3-2 Feedwater Low Load Bypass to SG 3 1&2-L-3-94 12.16 47W610-3-2 oy 3 NR Level Loop 1&2-L-3-98 12,16 47W610-3-2 SG 3 WR Level Loop 1&2-FCV-3-100 22 47W803-1 SG 4 MFW Isolation Valve 1&2-FCV-3-103 22 47W803-1 .. SG 4.MFW.. Isolation Valve 1'&2-FCV-3-103A 22 47W610-3-2 Feedwater Low Load Bypass to SG 4 1&2-L-3-107 12,16 47W610-3 2 SG 4 NR Level Loop 1&2-L-3-111 12,16 47W610-3-2 SG 4 WR Level Loop 1&2-FCV-3-116A 19 47W803-2 ERCW Header A Isolation Valve 1&2-FCV-3-116B 19 47W803-2 ERCW Header A Isolation Valve l

l --

C6 DNE4-1639 l

t

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prsptrtd by/Dato D@#//e/55' DURING A DESIGN BASIS FIRE '/

Checked by/Date Nd[ 2[/0/33 SQN-SQS'4-0127 APPENDIX C Main & Auxiliary Feedwater (3)

Key Reference Component (Item) Drawing Description 1&2-FCV-3-126A 19 47W803-2 ERCW Header B Isolation Valve 1&2-FCV-3-126B 19 47W803-2 ERCW Header B Isolation Valve 1&2-FCV-3-136A 19 47W803-2 ERC'J Header A Isolation Valve 1&2-FCV-3-136B 19 47W803-2 ERCW Header A Isolation Valve

-1&2-P-3-138A 14,15,16 47W610-3-3 Turbine Driven AFW Pump Outlet Pressure t kx- P-3 -lMS

~

1(, 47W6to-5 3

-102-F-3-1355- l ' ,1;,;6- '

_ 7','010 3 JN;rb ' r.: Drives ATJ "usp Cutist Aka-

, Na m 2/u m 1&2-P-3-140A 16 47W610-3-3 AFW Pipe Break Detection Loop 3 1&2-P-3-140B 16 47W610-3-3 AFW Pipe Break Detection Loop 3 1&2-F-3-142 14,15 47W610-3-3 TDAFWP Flow Loop (152)

• 1&2-L-3-148 12 47W610-3-3 SG 3 Level Loop .

1&2-LSV-3-148 12 47W610-3-3 Solenoid for Loop 3 MDAF WP Level Control Valve 1&2-LCV-3-148 12(98) 47W610-3-3 SG 3 MDAF WP Level Control Valve 1&2-P-3-148 12 47W610-3-3 SG 3 Level Bypass Pressure Switch Loop '

1&2-P-3-150A 16 47W610-3-3 AFW Pipe Break Detection Loop 2 1&2-P-3-150B 16 47W610-3-3 AFW Pipe Break Detection Loop 2 1&2-L-3-156 12 47W610-3-3 SG 2 Level Loop 1&2-LCV-3-156 12(96) 47W610-3-3 SG 2 MDAFWP Level Control Valve 1&2-LSV-3-156 12 47W610-3-3 Solenoid for Loop MDAFWP Level Control Valve 1&2-P-3-156 12 47W610-3-3 SG 2 Level Bypass Switch Loop 1&2-P-3-160A 16 47W610-3-3.. AFW Pipe Break Detection Loop No. I 1&2-P-3-160B 16 47W610-3-3 AFW Pipe Break Detection Loop No.1

• 1&2-L-3-164 12 47W610-3-3 SG 1 Level Loop G

~

~

C7 DNE4-1639

. EQUIPMENT REQUIRED FOR SAFE SHITIDOWN Ptspartd by/D:ta M2//d/ST DURING A DESIGN BASIS FIRE '/ g SQN-SQS'4-0127 Checked 'uy/Date WOEb_2tlw/tt APPENDIX C Main & Auxiliary Feedwater (3) (Continued)

Key Reference Component (Item) Drawing Description 1&2-LSV-3-164 12 47W610-3-3 Solenoid for Loop 1 MDAF WP Level Control Valve 1&2-LCV-3-164 12(95) 47W610-3-3 SG 1 MDAF WP Level Control Valve 1&2-P-3-164 12 47W610-3-3 SG 1 Level Bypass Pressure Switch Loop 1&2-P-3-165A 16 47W610-3-3 AFW Pipe Break Detection Loop No. 4 1&2-P-3-165B 16 47W610-3-3 AFW Pipe Break Detection Loop No. 4 1&2-L-3-171 12 47W610-3-3 SG Level Loop 4 162-LCV-3-171 12(97) 47W610-3-3 SG 4 MDAF WP Level Control Valve 1&2-LSV-3-171 12 47W610-3-3 Solenoid for Loop 4 MDAF WP Level l Control Valve 1&2-P-3-171 12 47W610-3-3 SG 4 Level Bypass Pressure Switch Loop 1&2-L-3-172 16 47W610-3-3 SG 3 Level Loop

• 1&2-LCV-3-172 16 47W610-3-3 SG 3 TDAF WP Level Control Val.ve 1&2-LSV-3-172 16 47W610-3-3 Solenoid for. Loop 3 TDAF WP Feed Reg Valve .

1&2-L-3-173 16 47W610-3-3 SG 2 Level Loop 1&2-LCV-3-173 16 47W610-3-3 SG 2 TDAF WP Level Control Valve

• 1&2-LSV-3-173 16 47W610-3-3 Solenoid for Loop 2 TDAF VP Level ,

Control Valv'e*

1&2-L-3-174 16 47W610-3-3 SG 1 Level Loop 1&2-LSV-3-174 16 47W610-3-3 Solenoid for Loop 1 TDAF WP Level Control Valve 1&2-LCV-3-174 16 47W610-3-3 SG 1 TDAF WP Level Control Valve  ;

1&2-L-3-175 16 . SG 4 Level Control Loop  ;

162-LCV-3-175 16 47W610-3-3 SG 4 TDAF WP Level Control Valve i 1&2-LSV-3-175 16 47W610-3-3 -

Solenoid for Loop 4 TDAF WP Level Control Valve 162-FCV'3-179A -

19 47W610-3-3 ERCW Header B Isolation Valve r

N C8 DNE4-1639 I

EQGIPMENT REQUIRED FOR SAFE SHtTIDOWN Preptrcd by/D ts D/9F2/,e/Fr

'DURING A DESIGN BASIS FIRE

Checked by/Date N 42 [, c//o//g SQN-SQS'4-0127 APPENDIX C Main & Auxiliary Feedwater (3) (Continued)

Key Reference Component (Item) Drawing Description 1&2-FCV-3-179B 19 47W610-3-3 ERCW Header B Isolation Valve 1&2-VLV-3-826 12 47W803-2 Hanual Isolation of Auxiliary Feedwater Pump B-B to SG 3 1,2-VLV-3-827 12 47W803-2 Hanual Isolation of Auxiliary Feedwater Pump A-A to SG 2 1,2-VLV-3-828 12 47W803-2 Manual Isolation of Auxiliary Feedwater Pump A-A to SG 1 1,2-VLV-3-829 12 47W803-2 Manual Isolation of Auxiliary Feedwater Pump B-B to SG 4 1,2-VLV-3-834 12 47W803-2 Manual Isolation of Auxiliary Feedwater Pump B-B to SG 3 1,2-VLV-3-835 12 47W803-2 Manuti Isolation of Auxiliary Feedwater Pump A-A to SG 2 1,2-VLV-3-836 12 47W803-2 Hanual Isolation of Auxiliary Feedwater Pump 1A-A to SG 1 1,2-VLV-3-837 12 47W803-2 Manual Isolation of Auxiliary Feedwater -

Pump 18-B to SG 4 Ventilation (30)**

Key Reference j

Component (Item) Drnwing Description ,

t 1&2-T-30-175 40 47W866-8 RHR Pump Room Coolers Temperature Loop 1&2-T-30-176 40

{

47W866-8 RHR. Pump' Room. Coolers Temperature Loop

'1,2-T-30-182 1 47W866-8 CCP Rm Clr Temp Control Loop 1,2-T-30-183 1 47W866-8 CCP Rm Clr Temp Control Loop 1,2-TS-30-214 37N 47W610-30 Turbine Driven Auxiliary Feedwater Pump Room Vent Fan Temp Switch 1,2-HS-30-214 37N 47W610-30 Turbine Driven Auxiliary Feedwater Pu=p Room Vent Fan Handswitch .-

• • Note system 30 components associated with Key 10 are contained in reference 11.7.  !

C9 I DNg4 1639 i

i

EQUIPMENT REQUIRED FOR SAFE-SHUTDOWN Prspar:d by/Da';G_ DM7/f9/97 i DURING A DESIGN BASIS FIRE '

Checked by/Date N4[/h' t//c/g(

SQN-SQS'4-0127 APPENDIX C Ventilation (30)** (Continued)

Key Reference Component (Item) Drawing Description 1-TCO-30-443 37C 47W866-9 R11 DG Building Intake Damper 2-FCO-30-444 37C 47W866-9 R11 DG Building Intake Damper 1-TCO-30-445 37C 47W866-9 R11 DG Building Intake Damper 2-FCO-30-446 37C 47W866-9 R11 DG Building Intake Damper 1-FCO-30-447 37C 47W866-9 R11 DG Building Exhaust Damper HS-30-447B 37C 47W866-9 R11 DG Building Exhaust Fan Handswitch 1-TS-30-447B 37C 47W866-9 R11 DG Building Exhaust Temperature Switch 2-TS-30-447B 37C 47W866-9 R11 DG Building Exhaust Temperature Switch HS-30-447C 37C 47W866-9 R11 DG Building Exhaust Fan Handswitch '

2-FCO-30-448 37C 47W866-9 R11 DG Building Exhaust Damper 2-TS-30-448B 37C 47W866-9 R11 DG Building Exhaust Temperature Switch HS-30-4488 37C 47W866-9 DG Building Exhaust Fan Handswitch HS-30-448C 37C 47W866-9 DG Building Exhaust Fan Handswitch '

2-FCO-30-449 37C 47W866-9 R11 DG Building Exhaust Damper .

2-TS-30-449B 37C 47W866-9 DG Building Exhaust Temperature Switch HS-30-449B 37C 47W866-9 DG Building Exhaust Fan Handswitch HS-30-449C 37C 47W866-9 DG Building Exhaust Fan Handswitch 2-FCO-30-450 37C 47W866-9 R11 DG Building Exhaust Damper HS-30-450B 37C 47W866-9 DG Building Exhaust Fan Handswitch

• HS-30-450C 37C 47W866-9 R11 DG Building Exhaust Fan Handswitch 2-TS-30-450B 37C 47W866-9 R11 DG Building Exha'ust Temperature Switch FCO-30-451 37C 47W866-9 DG Building Exhaust Damper 2-TS-30-451B 37C 47W866-9 R11 DG Building Exhaust Temperature Switch HS-30-451B '

37C 47W866-9 R11 DG Building Exhaust Fan Handswitch HS-30-451C 37C 47W866-9 R11 DG Building Exhaust Fan Handswitch

• • Note system 30 components associated with. Key '10.are contained in reference 11.7.

t l

C10 DNE4-1639 L

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PreptrId by/Date N 987,/s/fg DURI!XI A DESIGN BASIS FIRE i Checked by/Date & [ t//o/as SQN-SQS4-0127~

APPENDIX C Ventilation (30) (Continued)**

Key Reference Component (Item) Drawing Description 2-TS-30-452B 37C 47W866-9 DG Building Exhaust Temperature Switch FC0-30-452 37C 47W866-9 DG Building Exhaust Damper HS-30-452B 37C 47W866-9 DG Building Exhaust Fan Handswitch MS-30-452C 37C 47W866-9 DG Building Exhaust Fan Handswitch 1-FCO-30-453 37C 47W866-9 DG Building Exhaust Damper 1-TS-30-453B 37C 47W866-9 DG Building Exhaust Temperature Switch HS-30-453B 37C 47W866-9 DG Building Exhaust Temperature Fan Handswitch HS-30-453C 37C 47W866-9 DG Building Exhaust Temperature Fan Handswitch 2-FCO-30-454 37C 47W866-9 DG Building Exhaust Damper Switch HS-30-454B 37C 47W866-9 DG Building Exhaust Fan Handswitch

• 2-TS-30-454B 37C 47W866-9 DG Building Exhaust Temperature Swi,tch HS-30-454C '37C 47W866-9 DG Building Exhaust Fan Handswitch 1-FCO-30-459 37C 47W866-9 DG Electric Board. Room Exhaust Damper HS-30-459B 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswitch -

HS-36-459C 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswitch 2-FCO-30-460 37C 47W866-9 DG Electric Board Room Exhaus't Damper HS-30-460B 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswitch HS-30-4600 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswitch 1-FCO-30-461 37C 47W866-9 DG, Electric Board Room Exhaust Damper HS-30-461B 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswiten HS-30-461C 37C 47W866-9 DG Electric Board Room Exhaust Fan

~

. Handswitch 2-FCO-30-462 37C 47W866-9 DG Electric Board Room Exhaust Damper HS-30-462B 37C 47W866-9 DG Electric Board Room Exhaust Fan Handswitch HS-30-462C 37C 47W866-9 DG Electric Board F.oom Exhaust Fan Handswitch

• • Note system 30 components associated with Key 14 are contained in reference 11.7. -

C11 DNE4-1639

EQUIPMDir REQUIRED FOR SAFE SHITTDOWN Preptr:d by/D:to M f 7 d /IT DURING A DESIGN BASIS FIRE / /

4 SQN-SQS'-0127 Checked by/Date NA MA_ z//c/py APPENDIX C Ventilation (30) (Continued)**

Key Reference Component (Item) Drawing Description Elec Panel / 37C 47W866-9 DG Room 1A-A, 2A-A, IB-B, 2B-B Gen Fan Elec Board 37C 47W866-9 Electrical Board Room Unit 1A-A, 2A-A, Room 1B-B, 2B-B Exhaust Fan Exhaust Fan 1 37C 47W866-9 Diesel Generator Room Exhaust Fan Exhau:t Fan 2 37C 47W866-9 Diesel Generator Room Exhaust Fan DC Powered TDAFW Pump Room Exhaust Fan 37N 47W866-11 Emergency Exhaust Fan RER Pump 1A Cooling

~ 40 RHR Pump 18 -

Cooling' 40 RHR Pump 2A Cooling 40

• RER Pump 28..

Cooling 40 RHR Pump Room 40 Cooler Fans 1A-A,1B-B, ,

2A-A,2B-B A/C (Cooling & Heating) (31)

Key Reference . .

Component (Item) Drawing Description HS-31A-20A 37A 47W867-2 }fGt Air Handling Unit Handswitch HS-31A-20B 37A 47W867-2 HCR Air Handling Unit Handsvitch 0-FCO-31A-20 37A 47W867-2 HCR Air Handling Unit Inlet Damper 0-FSV-31A-20 37A 47W867-2 HCR Air Handling Unit Solenoid Valve 0-T-31A-22 37A 47W867-2 HCR AHU Temperature Control Loop 0-FSV-31A-22A 37A 47W867-2 HCR AHU Cooling Fluid Solenoid Valve .

0-FSV-31A-22B 37A 47W867-2 HCR AHU Cooling Fluid Solenoid Valve

• • Note system 30 components associated with Key 10 are contained in reference 11.7. -

C12 DNE4-1639

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

-_- m

EQUIPMENT REQUIRED TOR SAFE SHUTDOWN Prqptred by/D:to D M 7/M IT

. : DURING A DESIGN BASIS TIRE //

Checked by/Date 'A 61 [ Y Lltc/tt SQN-SQS4-0127 APPENDIX C

, 1 A/C (Cooling & Heating) (31) Continued Key Reference Component (Item) Drawing Description 0-TCO-31A-23 37A 47W867-2 HCR AHU Inlet Damper 0-TSV-31A-23 37A 47W867-2 HCR AHU Solenoid Valve HS-31A-23A 37A 47W867-2 HCR Air Handling Unit Handswitch HS-31A-23B 37A 47W867-2 M':R Air Handling Unit Handswitch 0-T-31A-39 37A 47W867-2 HCR AHU Temperature Control Loop 0-TSV-31A-39A 37A 47W867-2 HCR AHU Cooling Fluid Solenoid Valve 0-TSV-31A-39B 37A 47'J867-2 HCR AHU Cooling Fluid Solenoid Valve 0-TCV-31A-47& Loop 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-48 " 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-49 " 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-50 " 37A 47W867-2 HCR AHU Cooling Fluid Control 4$ 8 e

G

~

C13 DNE4-1639 ,

i 6

EQUIPMENT REQUIRED.FOR SAFE SHUTDOWN Pecpr.r:d by/Dato_ DF# 2/[e/gi DURING A DESIGN BASIS FIRE '/

Checked by/Date Nd[ t[/o/fri SQN-SQS4-0127 APPENDIX C A/C (Cooling & Heating) (31) (Continued)

Key Reference Component (Item) Drawing Description 0-T-31A-52 37A 47W867-2 HCR AHU Air Controls 0-TCV-31A-65 & Loop 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-66 & Loop 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-67 & Loop 37A 47W867-2 HCR AHU Cooling Fluid Control 0-TCV-31A-68 & Loop 37A 47W867-2 HCR AHU Cooling Fluid Control 0-T-31A-70 37A 47WE67-4 HCR A:M Air Control 0-P-31A-126 37A 47W867-4 HCR AHU Condensing Unit Pressure Control 0-P-31A-127 37A 47W867-4 HCR AHU Condensing Unit Pressure Control 0-T-31A-128 37A 47W867-4 liCR ANU Condensing Unit Temperature Control 0-T 31A-129 37A 47W867-4 HCR AMG Condensing Unit Temperature Control 0-LG-31A-130 37A 47W867-4 HCR AHU Condensing Unit Oil Sump Level Glass

• Loop 31A-131 37A 47W867-4 HCR AHU Condensing Unit A-A 0-T-31A-132 37A 47W867-4 HCR AHU Condensing Unit Oil Pump Motor Temperature 0-T-31A-133 37A 47W867-4 011 Cooler HCR AHU Condensing Unit Control' Loop 31A-134 37A 47W867-4 HCR AHU Condensing Unit A-A -

0-ET-31A-136 37A 47W867-4 HCR AHU Condensing Unit Liquid Pressure 0-P-31A-141 37A 47W867-4 HCR AHU Condensing Unit Liquid Pressure 0-P-31A-142 37A 47W867-4 HCR AHU Condensing Unit Liquid Pressure

• 0-T-31A-143 37A 47W867-4 HCR AHU Condensing Unit Temperature Controls ,

0-T-31A-144 37A 47W867-4 HCR AHU Condensing Unit Temperature Controls ,

0-LG-31A-145 37A 47W867-4 HCR AHU Condensing Unit Oil Su=p Level Glass '

Loop 31A-146 37A 47W867-4 HCR AHU Condensing Unit B-B 0-T-31A1147 37A 47W867-4 HCR AHU Condensing Unit Oil Pump Hotor Temperature 0-T-31A-148 37A 47W867-4 Oil Cooler HCR AHU Condensing Unit Control

> l 0-ET-31A-151 37A 47W867-4 HCR AHU Condensing Unit Comp. Mtr. Power 'l Supply i Loop MA-143 37A 47W867-4 HCR AHU Condensing Unit B-B l CI4 DNE4-1639 i

i l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prep red by/D: tow F/,f/#S DURING A DESIGN BASIS FIRE

Checked by/Date N d [ g/fo/pg SQN-SQS'4-0127 APPENDIX C A/C (Cooling & Heating) (31) (Continued)

Key Reference Component (Item) Drawing Description 0-P-31A-172 37A 47W867-4 HCR AHU Condensing Unit Liquid Pressure 0-P-31A-173 37A 47W867-4 MCR AHU Condensing Unit Liquid Pressure 0-FCO-31A-176 37A 47W867-2 MCR ANU Inlet Damper 0-T-31A-176 37A 47W867-2 HCR AHU Inlet Damper Control 0-TCO-31A-177 37A 47W867-2 M1 AHU Inlet Damper 0-T-31A-177 37A 47W867-2 HCR ANU Inlet Damper Control C

A/C U A-A 37A 47W867-2 MS'R Air Conditioning Unit A/C U B-B 37A 47W867-2 PgR Air Conditioning Unit g ,11

1. 1 g e..__,..

eu._;m,

.,.3...

n. , , , .

wnw=1 Control Air (32) '

Key Reference Component (Item) Drawing Description 0-FSV-32-37 13 47W845-5 Station Air Compressor B Coolant Water

' Inlet Valve

• 0-FSV-32-42, 13(100) 47W845-5 Station Air Compressor A Coolant Water Inlet Valve 0-FSV-32-61 13(110) 47W845-6 Auxiliary Air Compressor A-A Cooling Water Inlet 0-FSV-32-62 13(109) 47W848-1 Auxiliary Air Compressor A-A Unioader Valve 0-FCV-32-82 13(101) 47W848-1 Auxiliary Air Compressor A-A Auxiliary Building Is'olation

'0-PS-32-82 13 47W848-1 Auxiliary Air Compressor A-A Auxiliary Building Isolation Control 0-TCV-32-85 13(111) 47W848-1 Auxiliary Air Compressor B-B Auxiliary Building Isolation Valve 0-PS-32-85 13 47W848-1 Auxiliary Air Compressor B-B Auxiliary Building Isolation Control -

0-FSV-32-87 13(112) 47W848-1 Auxiliary Air Compressor B-B Auxiliary Building Isolation l

C15 '

l DNE4-1639 l

l l

EQUIPMENT REQUIRED FOR SAFE SHITIDOWN Prcptrid by/Date D/92 7/foAr<f DURING A DESIGN BASIS FIRE //

Checked by/Date $ d ( Y t/u/fa SQN-SQS4-0127 APPENDIX C Control Air (32) (Continued)

Key Reference Component (Item) Drawing Description 0-FSV-32-88 13(113) 47W848-1 Auxiliary Air Compressor B-B U loader Valve Station Air 13(99) 47W846-1 Compressor Compressor A

• Station Air 13(102) 47W846-1 Compressor Compressor B Aux Air Compressor A 13 47W846-1 Compressor Aux Air Compressor B 13 . 47W846-1 Compressor Control Air Supply Path 1 12, 16 47W846-1 Control Air Supply -

Path 2 12, 16 47W846-1 ,

Control Circuit for Air Comp A ' 13 47W846-1 Control Circuit for Air Comp B 13 47W846-1 Control Circuit for Aux Air Comp A 13 47W848-1 **

Control Circuit for Aux Air Comp B -

13 47W848-1 Service Air (33)

Key Reference Component (Item) Drawing. Description 0-VLV-33-500 13 47W846-1 Station Air to Control Air Manual

. Isolation 0-VLV-33-501 , 13 47W846-1 Station Air to Control Air Manual Isolation ,.

, C16 DNE4-1639

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prcpered by/Dato DM ?/

DURING A DESIGN BASIS FIR,E

Checked by/Date N d [ 2//o/tt i

APPENDIX C Sample System (43)

Key Reference Component (Item) Drejng Description c1&2-FCV-43-55 24 47W611-1-3 Sample Line Cooler Isolation 01&2-FCV-43-58 24 47W611-1-3 Sample Line Cooler Isolation c1&k-FCV-43-61 24 47W611-1-3 Sample Line Cooler ,

. Isolation '

0162-FCV-43-64 24 47W611-1-3 Sample Line Cooler Isolation Fe?dwater Control System (46) '

Key Reference Component (Item) Drawing Description -

Loop FIC-46-57 14,15(b2) 47W610-46-1 TDAF WP Flow Control 4

Loop SC-46-57 14, 15 (152) 47W510-46-1 TDAF WP Speed Control ,

Chemical and Volume Control System (62)

Key, Reference Component (Item) Drawing Description '

+

1&2-FCV-62-54 8 47W809-1 Excess Letdown Isolation Valve 1&2-FCV-62-55 8 47W809-1 1&2-FCV-62-56 Excess Letdown Isolation Valve 8 47W809-1 Excess Letdown Isolation Valve 1&2-FCV-62-69 7 47W809-1 '$CS Loop' 3 Letdown F4cw VMve 1&2-TCV-62-70 7 47W809-1 RCS Loop 3 Letdown Flow Valve

- 1&2-FCV-62-72 7 47W809-1 Regen Heat Exchanger Letdown Isolation Valve 1&2-FCV-62-73 7 47W809-1 Regen Heat Exchanger Letdown Isolation Valve 1&2-FCV-62-74 7 47W809-1 Regen Heat Exchanger Letdown ..

Isolation Valvo l

~

~

C17 DNE4-1639 l

c.

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Pr: pared by/Dato]MW/-*E'>

DURINC A DESIGN BASIS FIRE Checked by/Date MtC/ A 'Mu/FF SQN-SQS4-0127 '

APPENDIX C Chemical and Volume Control System (62) (Continued)

Key Reference Component (Item) Drawint. Description 1&2-FCV-62 "4 34(131) 47W809-1 Auxiliary Spray Isolation Valve 1&2-FCV-62-85 34(131a) 47W809-1 Normal charging Isolation Valve 1&2-FCV-62-86, 34(130) 47W809-1 Alternate Charging Isolation Valve 1&2-FCV-62-89 34(129) 47W809-1 Charging Flow Control Valve 1&2-FCV-62-90 34(129) 47W809-1 Charging Flow Isolation Valve 1&2-FCV-62-91 34(129) 47W809-1 Charging Flow Isolation Valve 1&2-FCV-62-93 2,34 47W809-1 Charging Header Flow Control Valve (129) '

1-FCV-62-98 1(10a) 47W809-1 Centrifugal Charging Pump Minimum 2-FCV-62-98 1 Flow Isolation Valve 47W809-1 Centrifugal Charging Pump Minimum Flow Isolation Valve 1-FCV-62-99 1(10a) 47W809-1 Centrifugal Charging Pump 2-FCV-62-99 Isolation Valve 1 47W809-1 Centrifugal Charging Pump Isolation Valve .

PCV-62-119 5 47W809-1 PCV-62-120 VCT Isolation From Nitrogen 5 47W809-1 VCT Isolation From Hydrogen FSV-62-125 5 47W809-1 PCV-62-126 VCT Vent Isolation 5 47W809-1 VCT Vent Isolation 1&2-L-62-129A 4,5 47W809-1 VCT Level Loop 1&2-L-62-130A 4,5 47W809-1 VCT Level Loop 1&2-LCV-62-132 4(60),5 47W809-1 1&2-LCV-62-133 4(60),5 VCT Outlet Isolation Valve 47W809-1 -

VCT outlet Isolation Valve 1&2-LCV-62-135 4,5(60) 47W809-1 Charging Pump Flow f rom RWST 1&2-LCV-62-136 4,5(60) 47W809-1 Charging Pump Flow from RWST 1&2-FCV-62-77 48 47W809-1 1&2-PCV-62-81 48 Normal Letdown Isolation Valve 47W809-1 VLV-62-672 48 VCT Letdown Pressure Control Valve 47W809-1 PCV by-pass valve 1&2-TCV-62-79 48 47W809-1 VCT Letdown Temp. Control Valve [q 1&2-FCV-62-59 48 47W809-1 Excess Letdown Three-way Valve 1&2-FCV-62-61 48 47W809-1 1&2-FCV-62-63 48 Excess Letdown Isolation Valve 47W809-1 Excess Letdown Isolation Valve C18 4617F/JMS

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESICN BASIS FIRE Praparsd by/DIte_ AA# V#,00 SQN-SQS4-0127 Checked by/Dato. /200a

/ V/Lf/ff APPENDIK C Chemical and Volume Control System (62) (Contitued)

Key Reference Component (Item) Drawint Descriptier, 1&2-VLV-62-526 2,34 47W809-1 1&2-VLV-62-527 2 Charging Flow Manual Bypass Valve 47W809-1 CCP A Manual Isolation to Charging 1&2-VLV-62-533 2 47W809-1 1&2-VLV-62-534 2,34 47W809-1 B Manual Isolation to Charging VLV-62-538 34 Charging Flow Hanual Bypass Valve 47W809-1 VLV-62-689 5 RCS Makeup Manual FCV Bypass 47W809-1 VCT Cas Sample Manual Isolation YLV-62-692 5 47W809-1 VLV-62-693 5 Manual VCT Isolation From Nitrogen 47W809-1 1&2-Centrifug'al 1 Manual VCT 1 solation From Hydrogen 47W809-1 See Appendix A. Key 1 Charging Pump A-A 1&2-Centrifugal 1 47W809-1 Charging Pump B-B See Appendix A, Xey 1 1&2 CCP Room Cooler 1 47W809-1 Fan A-A -

See A'ppendix A, Xey 1 '

'CCP Room Cooler Fan B-B 1 CCP Aux. Lube Oil Pump A-A 1 47W610-62-2 Oil Supply for CCP A CCP Aux Lube Oil Pump B-B 1 47W610-62-2 Oil Supply for CCP B 1&2-LCV-62-118 48 47W809-1 VCT Level Control Valve 1&2-RV-62-662 48 47W809-1 Normal Letdown to PRT 1&2-VLV-62-723. 48 47W809-1 Normal Letdown Header Isolation Valve 1&2-RV-62-636 48 47W809-1 Excess Letdown Relief Valve to PRT 1&2-VLV-62-715* 48 47W809-1 Excess Letdown Header Isolation Valve C19 4617F/JMS

r EQUIPMENT REQUIRED FOR SAFE SHUIDOWN Prepsrcd by/Date D617///r/gf DURING A DESIGN BASIS FIRE '

/ /

Checked by/Date N A M It 2//e/rg SQN-SQS4-0127 APPENDIX C Safety Injection System (63)

Key Reference-Component (Item) Drawing Description 1&2-FCV-63-1 5 47W811-1 RWST to RHR Pump Flow Control 1&2-TCV-63-5 4,5(61) 47W811-1 RWST to SIS Pump Flow Control 1&2-FCV-63-6 4,5 47W811-1 SIS Pump Inlet to CVCS Charging Pump 1&2-FCV-63-7 4,5 47W811-1 SIS Pump Inlet to CVCS Charging Pump C1&2-FCV-63-8 30 47W811-1 RER Pump Supply to CCPs Flow Control c1&2-FCV-63-11 30 47W811-1 RHRP Outlet to SIP Inlet Isolation Valve 1&2-FCV-63-25 6 47W811-1 SIS Boron Injection Tank Shutoff 1&2-FCV-63-26 6 47W811-1 SIS Boron Injection Tank Shutoff 1&2-TCV-63-39 6 47W811-1 SIS Boron Injection Tank Shutoff 1&2-TCV-63-40 6 47W811-1 SIS Boron Injection Tank Shutoff 1&2-FCV-63-41 6 47W811-1 SIS Joron Injection Tank to CVCS Boric Acid Tank 1&2-FCV-63-42 6 47W811-1 SIS Boron Injection Tank to CVCS Boric Acic Tank .

l .

1&2-FCV-63-47 4.5(61) 47W811-1 SIS Pump 1A-A Inlet Valve CFC7-63-63 36 47W811-1 AT No. 4 Nitrogen Isolation Valve CFCV-63-65 36 47W811-1 AT No. 4 Nitrogen Vent Valve CFCV-63-67 36 47W811-1 AT No. 4 Flow Isolation Valve CFCV-63-71 48 47W811-1 Inboard CIV to CVCS Holdup Tank .

1&2-FCV-63-72 5(64), 47W811-1 Containment Sump Flow Isolation Valve 30(128) 1&2-FCV-63-73 5(64), 47W811-1 Containment Sump Flow Isolation Valve 30(128)

CFCV-63-80 36 47W811-1 AT No. 3 Flow Isolation Valve CFCV-63-84 48 47W811-1 Outboard CIV_,to CVCS Holdup Tank CFCV-63-87 36 47W811-1 AT No. 3 Nitrogen Isolation Valve 11&2-FCV-63-93 30(124) 47W811-1 RER Pump A-A Discharge to Cold Leg 2 & 3 4

.w

, C20 DNE4-1639

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESIGN BASIS FIRE Pr:psrsd by/Dite = /h/ e/rtu SQN-SQS4-0127 Checked by/Dato- It LC% 'k14lt1 APPENDIX C Safety Injection System (63) (Continued)

Key Reference Component (Item) -Orawinn Description 1&2-FCV-63-94 30 47W811-1 RHR Pump B-B Discharge to Cold Leg 14 4

• FCV-63-98 36 47W811-1

• FCV-63-107 36 AT No. 2 Flow Isolation Valve 47W8tl-1 .AT No. 2 Nitrogen Isolation Valve

• FCV-63-111 48 47W811-1 RHR CL Injection Cross Connect Flow

• FCV-63-112 Control 48- 47W811-1 RHR CL Injection Cross connect Flow control

• FCV-63-118 36 47W811-1

• FCV-63-127 36 AT No.1 Flow Isolation Valve 47W811-1 AT No. 1 Nitrogen Isolation Valve 1&2-FCV-63-172 30(127) 47W811-1 1&2-VLV-63-574 6 RHR Hot LeC Injection Isolation Valve 47W811-1 Boron Injection Tank Outlet Valve to Boric Acid and CVCS Holdup Tanks

. . Essential Raw Coolin8 Water (6 7)

Key Reference component (Item) Drawinn Description 0-FCV-67-12 3(139,142) 47W845-1

- ERCW Header A Return Discharge Canal 0-FCV-67-14 E*:stof f 'Ja1ve 3(51,56).9 47W845-1 ERCW Header A Return Discharge Canal 1&2-FCV-67-66 3(133,147)

Shutoff Valve 47W845-1 DC Hcat Exchanger Isolation valve 1-FCV-67-162 370 47W845-6 CCS & AFW Pump Space Cooler Isol. Valve 1-FCV-67-164 370 47W845-6 4

CCS & AFW' Pump Space Cooier Isol. Valve 2-FCV-67-217 370 47W845-4 R\

BA & AFW Pump Space ' Cooler Isol. Valve 2-FCV-67-219 370 47W845-4 BA & AFW Pump Space Cooler Isol. Valve C21 4617F/JMS l

l

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date N 2/147 DURING A DESIGN BASIS FIRE Checked by/Date 7Td z//g/gg APPENDIX C Essential Raw Cooling Water (67) (Continued)

Key Reference Component (Item) Drawing Description 1&2-FCV-67-67 3(44,142) 47W845-1 DG Hx Isolation Valve 1-FCV-67-81 3 47W845-2 Auxiliary Building ERCW Supply Header IA Isolation Valve 2-FCV-67-81 3(40) 47W845-2 Auxiliary Buildi.ng ERCW Supply Header 2A Isolation Vi-1ve 1-FCV-67-62 3(46) 47W845-2 Auxiliary Bui. ding ERCW Supply Header IB Isolation Valve 2-FCV-67-82 3(54) 47W845-2 Auxiliary Building ERCW Supply Header 2B Isolation Valve 1-FCV-67-123 3(47),19 47W845-2 Containment Spray Heat Exchanger 1B Supply Control Valve 2-FCV-67-123 3(58),19 47W845-2 Containment Spray Heat Exchanger 2B Supply Control Valve -

1-FCV-67-124 3(47),19 47W845-2 Containment Spray Heat Exchanger IB -

Discharge Valve 2-FCV-67-124 3(58) 19 47W845-2 Containment Spray Heat Exchanger 2B Discharge Valve

'1-FCV-67-125 3(134), 47W845-2 Containment Spray Heat Exchanger IA 19 Supply Control Valve

'2-FCV-67-125 3(41),19 47W845-2 Containment' Spray Heat Exchanger 2A Supply Control Valve 1-FCV-67-126 3(134),19 47W845-2 Containment Spray Heat Exchanger 1A Disenarge Valve 7-FCV-67-126 3(41),19 47W845-2 Contairmnt Spray Heat Exchanger 2A Discharge Valve 1-FCV-67-127 3,13 47W845-2 Supply. Valve for.ERCW Flow to Air (105.135) Conditioning Equipment 1A, and

' Service Air Compressor 2-FCV-67-127 3(141) 47W845-2 Supply Valvo for ERCW Flow to Air Conditioning Equipment 2A l

l C22 DNE4-1639 l

l If b _ _ - . . . . . ._ .

l~

t EQUIPMENT REQUIRED TOR SAFE SHUTDOWN Prepared by/Date Dd8_"J/mM!f DURING A DESIGN BASIS FIRE '

'/ -

. Checked by/Date 7(27 t//o/st

'SQN-SQS4-0127 APPENDIX C Essential ~ Raw Cooling Water (67) (Continued)

Key Reference Component (Item) Drawing Description

,1-FCV-67-128 3,13(107, 47W845-2 Supply Valve for ERCW Flow to Air 144) Conditioning Equipment IB, and Service Air Compressor 2-FCV-67-128 3(148),13 47W845-2 Supply Valve for ERCW Flow to Air Conditioning Equipment 2B 1-FCV-67-146 1(9), 47W845-2 , Component Cooling System Heat 9(83) .

Exchanger A Discharge Control Valve 2-TCV-67-146 47W845-2 Component Cooling System Heat 1(22),9

~

Exchanger B Discharge Control (86) Valve 1-FCV-67-147 3 47W845-2 Cross Connect Valve, Main Supply Control Header 1A 2-FCV-67-147 3(55),19 47W845-2 Cross Connect Valve, Main Supply Header 2B 0-FCV-67-151 1(35) 47W845-2 Component Cooling System Heat .

Exchanger C Discharge Control Valve 0-FCV-67-152 1(35) 47W845-2 Component Cooling System Heat Exchanger C Discharge Control Va'1ve 1-FCV-67-168 3 47W845-6 Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 1A 2-FCV-67-168 3(38) 97W845-4 Supply Valve for ERCW Flow to #

Centrifugal Charging Pump Room Cooler 2A 1-FC7-67-170 3 47W845-6 Supply Valve for ERCW Flow to Centrifugal Charging Pump Room Cooler 1B _.

2-FCV-67-170 3(59,149) 47W845-4 Supply Valve for ERCW Flow to

' Centrifugal Charging Pump Room Cooler

- 2B 1-FCV-67-188 40 67W845-6 Supply Valve for ERCW elow to RHR Pump Room Cooler 1A 2-FCV-67-188 40 47W845-4 Supply Valve for ERCW Flow to RHR Pump Room Cooler 2A 1-FCV-67-190 40 47W845-6 Supply Valve for ERCW Flow to RHR Pump Room Cooler 1B 2-FCV-67-190 40 47W845-4 Supply Valve for ERCW Flow to RHR p

Pump Room Cooler 2B C23 DNE4-1639 lc

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -~ ' - ~

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date_D/I82/[v/ff DURING A DESIGN BASIS FIRE '

4 Checked by/Date Nd[ E//o/sF SQN-SQS4-0127 APPENDIX C Essential Raw Cooling Water (67) (Continued)

Key Reference Component (Item) Drawing Description

^

I 0-TCV-67-197 37A 47W845-6 MCR A/C Discharge Isolation 0-TCV-67-201 37A 47W845-6 HCR A/C Discharge Isolation 0-FCV-67-205 13(104) 47W845-5 l Station Service and Control Air  !

Compressor Supply Header A Isolation Valve CFS-67-206 13 47W610-67-5 CPS-67-206 ERCW to Station Air Comp Train A 13 A7W610-67-5 0-FCV-67-208 ERCW to Station Air Co=p Train A 13(106) 47W845-5 Station Service and Control Air Compressor Supply Header 1B Isolation f Valve CFS-67-209 13 47W610-67-5 CPS-67-209 ERCW to Station Air Comp Train B 13 47W610-67-5 ERCW to Station Air Comp Train B 1&2-FCV-67-223 3(37,50), 47W845-2 Supply Header 1B 'to Header 2A 19 Isolation Valve .

0-FCV-67-364 3(42,139) 47W845-1 HeaderAReturbDischargeCanal Shutoff Valve 0-FCV-67-365 3'51,57), 47W845-1 Header A Retura Discharge Canal 9 Shutoff Vs.ltd I 1-FCV-67-424 3(49), 47W845-2 ERCW to Cor:ponent Cooling Water HTX 19 Header AB 0-FCV-67--478 1,9(80),19 47W845--2 Supply Valve ERCW to Component Coolant Heat Exchanger A fhi-FCV-67-489 3(45) 47W845-5 ERCW Stral.ner B1B-B Isolation Valve 2-FCV-67-489 3(53) 47W845-5 1&2-FCV-67-490A 3(53) ' ERCW Strainer B2B-B I. solation Valve 47W845-5 - S;rainer B Backwach Isolation Valve 1&2-FCV-67-490D 3(48,52) 47W845-5 1&2-FCV-67-491A 3(137) 47W845-5 Strainer B Backwash Isolation Valve 162-FCV-67-491D 3(43,138) 47W845-5 Strainer A Backwash Isolation Valve 1-FCV-67-492 '3 47W845-5 Strainer A Backwash Isolation Valve 2-FCV-67-492 3(39) ERCW Strainer A1A-A Isolation Valve ERCW Strainer A2A-A Isolation Valve ,

I i

C24 DNE4-1639

EQUIPHENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Cate DM 2//B/hff DURING A DESIGN BASIS FIRE ' '

/

Checked by/Date Id[ L//o/85 SQN-SQS4-0127 APPENDIX C Essential Raw Cooling Water (67) (Continued)

Key . Reference Component (Item) Drawing Description ERCW Pump J-A 3 47W845-5 Delivers EK W Cooling to Header 1A ERCW Pump K-A 3 47W845-5 Delivers ERCW Cooling to Header 1A ERCW Pump Q-A 3 47W845-5 Delivers ERCW Cooling to Header 2A ERCW Pump R-A 3 47W845-5, Delivers ERCW Cooling to Header 2A ERCW Pump L-B 3 47W845-5 Delivers ERCW Cooling to Header 1B ERCW Pump H-B 3 47W845-5 Delivers ERCW Cooling to Header 1B ERCW Pump N-B 3 47W845-5 Delivers ERCW Cooling to Header 2B ERCW Pump P-B 3 47W845-5 Delivers ERCW Cooling ~to Header 2B ERCW Strainer 3 47W845-5

.A1A-A Strainer for ERCW Header IA ERCW Strainer 3 47W845-5 Strainer for ERCW Header 2A A2A-A ERCW Strainer 3 47W845-5 Strainer for ERCW Header IB

.B1B-B '

ERCW Strainer 3 47W845-5 Strainer for ERCW Header 2B .

B2B-B .

ERCW Header 2A&lB 1(10,22a), 474845-5 3,9(62)

. ERCW Header 2D&lA 1(37) 3 47W845-5

• Screen Wash Pump A-A 3 47W845-5 CScreen Wash Pump B-B 3 47W845-5

• Screen Wash Pump C-B 3 47W845-S CScreen Wash Pump D-A 3 47P845-5 ..

,*Traveling Screen A-A 3 47W845-5

~

• Traveling Screen -

B-B 3 47W845-5

• Traveling Screen C-B 3 47W845-5

• Traveling Screen

• D-A 3 47W845-5 C25 DNE4-1639 6

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date D/?8 2//d I F DURING A DESIGN SASIS FIRE ' '

Checked by/Date [4A [ I4 Z[10/ft SQN-SQS4-0127 APPENDIX C Reactor Coolant (68)

U Key Reference Component _

_ (Item) Drawing _ Description 1&2-T-68-1 28(119) 47W610-68-1 Loop i Hot Leg Temperature Indicator 162-T-68-18 -

-28(119) 47W610-68-1 Icop 1 Cold Leg Temperature Indicator 1&2-T-68-24 23(119) 47WG10-68-2 Loop 2 Hot Lsg Temperature Indicator 1&2-T-68-41_ 28(119) 47W610-68-2 Lcop 2 Cold Leg Temperature Indicator 162-T-68-43 28(119) 47W610-68-3 Loop 3 !!ot Leg Temperature Indicator 1

,. 162-T-68-60 28(119) 47;r610-68-3 Loop 3 Cold Leg Temperature Indicator 1&2-T-68-65 28(119)- 47W610-68-4 Loop 4 Hot Leg Temperature. Indicator 1&2-P-68-66 28 47W610-58-7 RCS Pressure Loop for PI-68-66A

-162-P-68-69 28 47W610-63-7 RCS Pressure Loop for PR-68-69 162-T-68-83 28(119) 47W610-68-4 Loop 4 Cold Leg Temperature Indicator 1&2-L-68-320 2 47W610-68-5 Pressurizer Level Loop

- P ' " 3M - . 48 '

.7"O13 1- -200 P Pr =acc Lc~p-

-P-68=93&- . -2& _

' 7b'b13 <nOS PC3 Pree uc Lvvy '

162-FCV-68-332 28(121) 47W813-1 Pressurizer Relief Block Valve -

162-FCV-68-333 -

28(122) 47W813-1 Pressurizer Relief Block Valve 1,2-PCV-68-334 7(69),_ 67W813-1 Pressurizer PORV 28(122) 1&2-L-68-335 2 47W610-68-5 RCS Pressurir.e Water Level 1&2-L-68-339 2 47W610-68-5 RCS Prcr:surizer Water Lovel (ypf %6 3 >40 96- A B.'ei?-l -ROS-- PRZ Prema Lcvp 1&2-PCV-68-340A 7(70), 47W813-1 Pressurizer PORV 28(121) 1&2-PCV-68-340B 28(123) 47W813-1 Pressurizer Spray Valve 1,2-PCV-68-340D 28 4.7W813 1 Presuuri ce Spny Valva loop-1&2-P-68-342C 28 47V610-68-5. Pressuriser Pressure Instrtment Loop for PI-68-342A

/1&2-FSV-68-394 7(71) 47W813-1 Reactor Vessel Head Vent Isolatica 4

~ Valve gk [162-FSV-68-395 /(72) 47W813-1 Reactor Vessel Head Vent Isolation Valve 162-FSV-68-396 7(71) 47W813-1 Reactor Vessel Head Vent Throttle Valve

• 1&2-FSV-68-397 7(71,72) 47W813-1 Reactor Vessel Head Vent Throttle Valve 026 DNE4-1639 l

~-

I

. \'

'EQUIPME!C REQUIRED FOR SAFE SHUTDOWN - Prepared by/Date h k 7//oI T

- DURING A' DESIGN BASIS FIRE

' Checked by/Date 7T4td' L/1o/82 JSQN-SQS4-0127-4

,c APPENDIX C' m

Component Cooling Water System (70)

Key Reference Copponent (Item)' Drawing Description 0-FCV-70-1 1,31, .47W859-1 1&2-FCV-70-2 -1(4,15) SFPCS HX'B Outlet Isolation Valve 47W859-1 RHR HTX A Inlet Valve j 1&2-FCV-70-3 1(33,34) 47W859-1 RHR HTX B Inlet Valve I

~

, -1&2-FCV-70-4 9(79, 47W859-1 Hiscellaneous Equipment Header Inlet

87) Valve 1-FCV-70-8 1(2) .__ 47W859-1 CCS HTX A, utlet Isolation Valve 9(77) 1 11-FCV-70-9 1(3,31) 47W859 CCS HTX A & C, Outlet Isolation Valve 9(78)

.1-FCV-70-10 1(3,31) i 9(78) 47W859-1 CCS HTX A & C, Outlet Isolation Valve

0-FCV-70-11 1,31 1 47W859-1 SFPCS_Ex A Outlet Isolation Valve 01FCV-70-12 1(30) 47W859-1 i

CCS HTX C Outlet Isolation Valve l 1-FCV-70-13 1(8,28), 47W859-1 CCS HTX A & C Inlet Isolstion Valve 9(84) -

FCV-70-14 -

1(18,29) 47859-1 CCS HTX B & C Inlet Isolation Valve 9(92) 2-FCV-70-15 1(12), 47WG59-1 CCS HTX B Outlet Isolation Valve 9(87) 2-FCV-70-16 1(19), CCS 3x B Inlet Isolation Valve 9(87). ~'

2-7CV-70-18 1(18,29) 47W859-1 CCS HTX B E C Inlet Isolation Valve  ?

9(92) 0-FCV-70-22 1(27) 47W859-1 CCS HTX C Inlet Isolation Valve

' ,1-FCV-70-13 1(8,28), 47W859-1 CCS HTX A & C Inlet Isolation Valve 9(84) 1-FCV-70 25 1(6), 47W850-1 CCS NTX A Inlet Valve 9(76) -.

1-FCV-70-26 1(25), 47W859-1 CCS Pumps 1A-A and IB-B to C-S 9(84) Outlet Isolation Valve 1-FCV-s0-27 1(25), 47W85901 CCS Pumps 1A-A and IB-B to C-S 9(84) Outlet Isolation Valve 2-FCV-70-28 1(17,26) 47W859-1 CCS Pump 2A-A and 2B-B to C-S Outlet t

9(94) 2-FCV-70-29 1(17,26) 47W859-1

~

CCS Pump 2A-A and 2B-B to C-S Outlet t

9(94) Isolation Valve ,

E 0-FCV-70-34 1(5), 47W859-1 CCS Pump 1A-A to IB-B Inlet Isolation 9(75) Valve 0-FCV-70-39 1(21), 47W859-1 CCS Pump 2A-A to 2B-B Inlet Isolation 9(89) Valve 0-FCV-70-40 1,31 47W859-1 SFPCS Ex A Inlet Isolation Valve 0-FCV-70-41 1,31 47W859-1 SFPCS Ex B Inlet Isolation Valve C27 DNE4-1639

- ,..-.a-,u - + ,,, .,v- - ,s,,-,-n, ,-r---, , , , - , - - - , - , - , -e,

4 _ _

J EQUIPMENT REQUIRED FOR SAFE SHUTDOWN s-DURING A DESIGN BASIS FIRE Preparad by/Dato ' 049 e//*8#

4 SQN-SQS4-0127 Checked by/Date ALO/- V/29/r#

APPENDIX C Component Cooling Water System (70) (Continued)

Key Reference Component (Item) Drawint Description 1-FCV-70-64 1(7,23) 47W859-1 CCS Pumps 1A-A and IB-B to C-S Inlet 9(85) 1-FCV-70-74 1(7,23) Isolation Valve 47W859-1 CCS Pumps 1A-A and 1B-B to C-S Inlet 9(85) . Isolation Valve 1&2-FCV 75 1(37) 47W859-1 RHR Heat Exchanger B Return Header 2-FGV-70-76 1(20,24) Isolation Valve 47W859-1 CCS Pumps 2A-A and 2B-B to C-S Inlet 9(93) Isolation Valve 2-FCV 78 1(20,24) 47W859-1 CCS Pumps 2A-A and 2B-B to C-S Inlet 9(93) Isolation Valve 1&2-FCV-70-87 9(74,88) 47W859-2,3 Reactor Coolant Pump Thermal Barrier 1& 2-FC'*- 70-90 9(74,88) Return Isolation Valve 47W859-2,3 Reactor Coolant ~ Pump Thermal Barrier 1&2-FCV-70-133 9(73,87) Return ISOL Valve 47W859-2,3 , Reactor Coolant Pump Thermal Barrier 1&2-FCV-70-134 9(73,67) Coolant Isolation Valve 47W859-2,3 Reactor Coolant Pump Thermal Barrier 1&2-FCV-70-153 1(36),31 47W859-4 Coolant Isolation Valve 1&2-FCV- 70-156 1(1,16)

RHR Heat Exchanger B Outlet Valve 47W859-4 RHR Heat Exchanger A outlet valve 9(81),31 0-FCV-70-193 1(14), 47W859-1 9(91),

SFPCS Heat Exchanger A & B Inloc Valve 31-1&2-FCV-70-85 48 47W859-2,3 CCS to Exces'. Letdown HX 1&2-FCV-70-143 48 47W859-2,3

'CCS to ERcess Letdown HX' 1&2-TCV-70-192 48 47W859-2,3, CCS to Letdown HX $

C28 4617F/JHS

-e

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESIGN BASIS FIRE Prepard by/Date M /I,0IS /

g SQN-SQS4-0127 Checked by/Date Nd[8d t.//o/ES APPENDIX C Component Cooling Water System (70) (Continued)

Key Reference Component (Item) Drawing Description 0-FCV-70-194 1(14), 47W859-1 SFPCS Heat Exchanger A & B Inlet Valve 9(91),

31 2-FCV-70-195 1(13.32) 47W859-1 CCS HTX B & C Outlet Isolation Valve 9(90) 2-FCV-70-196 1(13,32) 47W859-l' CCS HTX B & C Outlet Isolation 9(90) 0-FCV-70-197 1,31,9 47W859-1 SFPCS HTX Supply Header Valve 0-VLV-70-529A 1,31 47W859-1 0-VLV-70-529B SFPCS HTX A Outlet Manual Isolation Valve 1,31 47W859-1 SFPCS HTX B Outlet Manual Isolation Valve 1-VLV-70-531 1,31 47W859-1 SFPCS HTX Return Manual Isolation Valve 0-FCV-70-198 1,9,31 47W859-1 SFPCS HTX Supply header Valve 1&2-VLV-70-545A . 1(1,16),9 47W859-4 RHR A Inlet Isoletion Valve 1&2-VLV-70-545B 1. 47V8f3-4 RER B Inlet Isolation Valve 1&2-VLV-70-546A 1(1,16',9 67W859 4 RER HTX A Outlet Valve 1&2-VLV-70-546B 1 A7W859-4 RHR HTX 1A-A Outlet Valve 0-VLV-70-574 31 47W859-2&J Non Regen Letd'okn HTX Manual Inlet 0-VLV-70-587 31 47W859-162 Non Regen Letdown HTX Manual Outlet 0-VLV-70-601 31 47W859-2 Comp Cooling to ERCW Manual Isolation Outlet 0-VLV-70-636 31 47'/859-2 ERCW Cooling to CCS Inlet 0-VLV-70-637 31 47W859-2,3 BAE&GS Ir.let. Isolation Valve.

0-VLV-70-661 31 47W859-2,3 BAE&GS Outlet Isolation. Valve CCS Pump B-B 1,9 47W859-1 CCS Pump A-A 1,9 47W859-1 CCS Pump C-S 1,9 47W859-1 RCP Thermal Barrier Booster Pump A-A 9 47W859-2 Booster Pump A-A 9 47W859-2 Booster Pump B-B 9 47W859-2 C29 DNE4-1639

EQUIPMENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date W B IT DURING A DESIGN BASIS FIRE '

' /

Checked by/Date Ndt /~ Z//o/fF

SQN-SQS4-0127 APPENDIX C Containment Spray (72)

Key Reference Component (Item) Drawing Description 152-FCV-72-2 4,5(63) 47W812-i Containment Spray Header B Isolation Valve 1&2-FCV-72-20 5 47W812-1 Containment Sump Isolation to CSPs 1&2-FCV-72-23 5 47W812-1 Containment Sump Isolation to CSPs 1&2-FCV-72-39 4,5(63) 47W812-1 Containment Spray Header A Isolation Valve 1&2-FCV-72-40 4,5(62),

30 47W812-1 RHR Spray Header A Isolation Valve I&2-FCV-72-41 4,5(62),

30 47W812-1 RHR Spray Header B Isolation Valve CS Pump A-A 4,5(63) 47W812-1 CS Pump B-B 4,5(63) 47W812-1 Residual Heat Removal (74) -

. Key Reference Component (Item) Drawing Description 1&2-FCV-74-1 7(68),30 47W810-1 RHR System Isolation Valve 162-FCV-74-2 7(68),30 47Wo10-1 RHR System Isolation Valve

-162-FCV-74-3 30(126) 47W810-1 RHR Pump A-A Inlet Flow Control salve 9162-FCV-74-12 5,30 47W810-1 RER Pump A-A Min Flow Valve 162-FCV-74-16 30(125) 47W810-1 RER HTX A Outlet Flow Control Valve 1&2-FCV-74-21 30(126) 47W810-1 RER B-B Pump B-B Inlet Flow Control Valve

$1&2-FCV-74-24 5 47W810-1 RHR Pump B-B Mini Flow Valve 1&2-FCV-74-28 30(125) 47W810-1 RHR HTX B Outlet Flow Control Valve

• 1&2-FCV-74-32 30 47W810-1 RER.HTX Bypass Flow Control Valve 162-FCV-74-33 30(127) 47W810-1 RER HTX A Bypass Valve 7162-FCV-74-35 30(127) 47W810-1 RER HTX B Bypass Valve C162-HCV-74-36 30 47W810-1 RER HTX A Bypass Valve

• 162-HCV-74-37 30 47W810-1 RER HTX B Bypass Valve

• 1&2-VLV-74-542 48 47W810-1 RHR HX Tube Drain Manual Isolation

• 162-VLV-74-546 48 47W810-1 RHR HX Tube Drain Manual Isolation RHR Pump A-A

• 31,4,5 (62)

• RER Pump B-B 31,4,5 (62)

C30 DNE4-1639 L

?

Prepared by/Date DM2[/c/$T EQUIPMENT REQUIRED FOR SAFE SHUTDOWN DURING A DESIGN BASIS FIRE //

Checked by/Date N d 4h#M SQN-SQS4-0127 APPENDIX C Waste Disposal System (77) w h /r3 Key Reference

-Component (Item) Drawing Description PCV-77-89 5 47W830-4 Waste Gas Compressor Isolation From VCT Vent Path A iivir =y=iem 77 w- pawaio associaied witn containmeni integrity ere

.tal .:d ir. :sf::cr.:: 11.7 - .M L/ts/n Upper Head Injection (87)

Key Reference Component (Item) Drawing Description 1&2-FCV-87-21 36 47W811-2 Accumulator to Rx Vessel Head 1 solation Valve 1&2-FCV-87-22 36 47W811-2 Accumulator to Rx Vessel Head Isolation Valve '

1&2-FCV-87-23 36 47W811-2 Accumulator to Rx Vessel Head Isolation -

Valve 1&2LFCV-87-24 36 47W811-2 Accumulator to Rx Vessel Head Isolation Valve 1,2-VLV-87-550 36 47W811-2 UHI Gas Header Manual Vent i 1,2-VLV-87-552 36 47W811 2 UHI Gas Accumulator Truck Fill Reactor Protection System (99)

Key Reference Component (Iten) Drawing Description HS-RT-1 or HS-RT-2 29 47W611-99-1 NI-31B 29 --

NI-32B 29 Reactor Trip -

Breaker A 29 47W611-99-1 Reactor Trip Breaker B 29 47W611-99-1

• Rod Drive Motor 47W611-99-1 Generator Set '

Breaker A&B 29 Indicates equipment / components that have been added since revision 6 of this calculation.

C31 DNE4-1639

f 1

-; EQUIPMENT REQUIRED FOR SAFE SHUTDOWN'. Prepared by/Da'te M DURING A DESIGN BASIS FIRE = 2//o/

- SQN-SQS4-0127' APPENDIX D 9

P b

e 9

• P A

I N

4#4 y':

9 8

4 a

9 6

y I-a f'.

o 1

a e t

W. O w, -,ww.,v-, m, N v ,m N e . - w.- m--e _ __ ..,_n,e,n_,n ...,w.w.w.-,mwa,-eme,,, _ . w r, n ve n,--e em-- , -- g, m

EQUIPHENT REQUIRED FOR SAFE SHUTDOWN Prepared by/Date Ndl. 2//$

-DURING-A DESIGN BASIS FIRE Ghecked by/Date_ $//% / J//o//f SQN-SQS4-0127 APPENDIX D APPENDIX D - INSTRUMENTATION LIST FOR MAIN CONTROL ROOM Indicator Description LI-68-339 Pressurizer Water Level LI-68-320 One of three Pressurizer Water Level L1-68-335A Pressurizer Water Level PI-68-342A RGS WR Pressure PI-68-66A One of three RCS WR Pressure PR-68-69 'RCS WR Pressure PI-1-2A Either one SG-1 Steam Press PI-1-2B SG-1 Steam Press-PI-1-9A .Either one SG-2 Steam Press PI-1-9B SG-2 Steam Press PI-1-20A Either one Two '

SG-3 Steam Press PI-1-20B Loops SG-3 Steam Press Required PI-1-27A Either one SG-4 Steam Press PI-1-27B SG-4 Steam Press LR-3-43 LI-3-174 LI-3-164

LI-3-38* -- Either one SG-1 NR Level LI-3-39 SG-1 NR Level LR-3-48 LI-3-156 --

LI-3-173 LI-3-51* --- Either one , SG-2 NR L'evel LI-3-52 SC-2 NR Level LR-3-98 LI-3,172 LI-3-148 LI-3-93* -- Elther one SC-3 NR Level '

LI-3-94 SG-3 NR Level LR-3-98 LI-3-175 LI-3-171 LI-3-106* --, Either one SG-4 NR Level LI-3-107 SG-4 NR Level 1

EQUIPMENT REQUIRED FOR SAFE SituTDOWN Prepared by/Date N 4 [

DURING A DESIGN BASIS FIRE t/te Checked by/Date_#.f. M _ py g/g APPENDIX D APPENDIX D - INSTRUMENTATION LIST FOR MAIN CONTROL ROOH Indicator Description TR-68-1 (Pen 1) RCS Loop 1 Hot Leg.

TR-68-1 (Pen 2) RCS Loop 1 Cold Leg TR-68-24 (Pen 1) RCS Loop 2 Ilot Leg TR-68-24 (Pen 2) RCS Loop 2 Cold Leg

_ Two loops TR-68-43 (Pen 1) required RCS Loop 3 Hot Leg TR-68-43 (Pen 2) RCS Loop 3 Cold Les TR-68-65 (Pen 1) RCS Loop 4 Hot Leg TR-68-65 (Pen 2) RCS Loop 4 Cold Leg Source Range Flux Monitor NI-92-31B Either one NI-92-32B -

Condensate Storage Tank Level

1. L1-2-230A

2. Either one for Tank A (Note 1)

LI-2-230D

3. LI-2-233A

4. Either one for Tank B (Note 1) i LI-2-233D Chemical and Volume Control i 1. LI-62-129 (Tank Level-VCT) Note 2

2. FI-62 93A (Charging Flow) Note 3 Note 1:

If MCR indication is not available, [ocal monito. ring of tank level or AFW suction pressure is acceptable Note 2:

Refer to key 4 for actions if this level indication is not available, Note 3: n r nt e.w y. RtL alot to This indicator in key 2.

is only required if the^ path u::':,:G "C" O is chosen d verified as ha,..n; ad:q= te-scparatie,..-* Denotes steam generator level tran m u,a sa y eu uu. m a zw u no wn.

ca y w,n u- a , na. ag.e-a o. ., n 3 - ~+

l evalvafed).

2 3560F/JMS

~

[ W N-SCg5'i - C12 l i~

APPENDIX E 4

t El l

3560F/JNs l

t I

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e.ydtes.M' REQUIRED FOR SAFE SHUTDOWN

.PERl10CFR50. APPENDIX R; Prepared by/Date 'b[ IN8/f-SQN-SQS4-0127 Chsched by/Date W ./ & ot/M //9 APPENDIX E Appendix E - Instrumentation List for Auxiliary Control Room:

Pressurizer Pressure and' Level Level

1. LI-68-325C Either one

2. LI-68-326C Pressure

1. PI-68-336C

2. PI-68-337C One of three

3. PI-68-342C Reactor Coolant-Hot' Lee Temperature

1. TI-68-1C (Loop 1) , A ll (*we leeps

2. TI-68-24C (Loop 2)- 'my ;-v Ivvys usca fui c oc id owrr-

3. TI-68-430 (Loop 3) {g;,f ,,

4. TI-68-65C (Loop 4)

Steam Generator Pressure and Level Pressure .

1. PI-1-1C (Loop 1) All four loops

2. PI-1-8C (Loop 2) 3.

-A.y i-v-lvuss usca fva seeldv-" f*7,j ps '

PI-1-19C (Looo 3)

4. PI-1-26C (Loop 4)

Level. .

1. LI-3-164C (Loop 1) 2.

/\ll fo'ur leopa LI-3-156C (Loop 2) -A..y

3. LI-3-148C (Loop 3) two !ccpa uscd for cc .1do.m 8g,

4. LI-3-171C (Loop 4) , .

. Source Range Flux Monitor

1. RI-90-210 Level-Indication for Tanks Volume Control Tank o

1. LI-62-129C

. E2 3534F/JMS L_

EQUIPMENT REQUIRED FOR SAFE SHlT1DOWN - Prepared by/Date N A / --

Z//o/F i PER 10CFR50 APPENDIX R SQN-SQS4-0127- ,

Chscked by/Date A/. /A / A//o/ff APPENDIX E Appendix E - Instrumentation List for Auxiliary Control Room:

Diagnostic Instrumentation for Shutdown Systems Auxiliary Feedwater System

1. FI-3-163C (Loop 1) All four. loof 3

2. FI-3-155C (Loop 2)

3. FI-3-147C (Loop 3) 'ny tu; leepe used fe. cocidc'm /hy/sr

4. FI-3-170C (Loop 4)

5. FI-3-142C (Aux FPT Disch)

Chemical and Volume Control Tank '

1. TI-62-800 (Ltdn Ht Exch Outlet) k

2. PI-62-92C (Chg Hdr Press)

3. FI-62-930 (Chg Hdr Flow)

4. FI-62-1370 (Emer Boration)

Safety Iniection System

1. FI-63-9tC (RHR Pmp A-A to RCS 2&3 CL) Either one

2. FI-63-92C (RHR Pmp B-B to RCS 1&4 CL)

Essential Raw Cooling Water

1. FI-67-61C (ERCW Supply Hdr A) Either one '

2. FI-67-62C (ERCW Supply Hdr B) \

y Residual Heat Removal

1. TI-74-38C (RHR Htx A Outlet Temp) Either one

2. TI-74-400 (RHR Htx B Outlet Temp)

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easg E3 3534F/JMS j L

s ENCLOSURE 2-Li'st of' Commitments

.1..~The verification of unit 1 to revision 9 of the Appendix R shutdown logic p is currently scheduled for completion by July 11,1988.

2. Modifications identified during the verification of unit i to the Appendix R shutdown logic calculation will be completed before unit i restart except where interim compensatory measures may exist.

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