ML20235Q422
| ML20235Q422 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/01/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710070588 | |
| Download: ML20235Q422 (164) | |
Text
- - _ - - - - - - _ _ - , _ _ _ _ _ _ _ _ _
4 TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 374ot SN IS7B Lookout place OCT 011987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 i
Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - APPENDIX R FIRE PROTECTION SAFE SHUTDOWN LOGIC CALCULATION
References:
- 1. Letter to NRC from L. M. Mills dated December 2, 1982
- 2. Letter to Steven A. White from B. J. Youngblood dated May 29, 1986, " Deviation Requests from Appendix R of 10 CFR Part 50"
- 3. Letter to S. A. White from B. J. Youngblood dated October 6, 1986, " Deviation Request Regarding T-Cold Instrumentation in the Auxiliary Control Room" The NRC project manager for SQN requested a copy of TVA calculation SQN-SQS4-127 (B25 860624 302) to support NRC's review of the fire protection program. This calculation is the Appendix R safe shutdown logic to which SQN is analyzed. It identifies the equipment required for safe shutdown during a design basis flre. Revision 6 to this calculation is included as an enclosure. The above references contain information pertaining to deviations from the Appendix R criteria.
Very truly yours, J TENNESSEE VALLEY AUTHORITY
\Ard he, R. Gridlb , Director Nuclear Licensing and Regulatory Affairs Enclosure cc: See page 2 8710070588 871001 hDR ADOCK 05000327 PDR yb An Equal Opportunity Employer l (
- l $
~ U.S; Nuclear Regulatory Commission
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00r['O11987:-
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- cc:. Mr. G. G. Zech,' Assistant Director
-for Inspection' Programs
' Office of.Special Projects U.S. Nuclear Regulatory Commission
'101 Marietta Street, NW, Suite 2900 Atlanta, Georgia' 30323 Mr.'J. A. Zwolinski, Assistant Director (Enclosure)-
for Projects Division of TVA Projects
' Of fice of Special . Projects LU.S.! Nuclear Regulatory Commission 4350 East-West Highway EWW 322 Bethesda, Maryland' 20814 Sequoyah Resident Inspector Sequoyah' Nuclear Plant 2600 Igou Ferry Road Soddy Daisy,-Tennessee 37379
.)
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ENCLOSURE
- l. SEQUOYAH NUCLEAR PLANT TVA Calculation SQN-SQS4'127, Revision 6 (B25 860624'302) i 1
i i
form TVA 10697 (EN DES 144) EN DES CALCULATIONS TITLE Equipment Required for Safe Shutdown PLANT / UNIT nor i ncvn sin Annt nrt 4.c n Sequoyah I and 2 l(k PREPARING ORGANIZAllOs '
OE/NED/OSG-7 DRANCH/ PROJECT IDENTIFIERS KEY NOUNS (Consult MEDS CIS DESCRIPTORS LIST) l' ire Protection Each tim the calculations are issued, preperers rnust ensure that the original (RO) ME DS accession Rev Ifor MEOS' use) MEDS accession number G i007 R D001 ) /J E % T W l\ 1 L ?. L
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[CN NUMBER (Enter "N/A"if there is no ECN)
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' C 6* e , e v. s i o<3 log STATEMENT OF PROBLEM O Determine the functions and sets of equ'pment required for safe shutdown of Sequoyah Nucicar Plant under postulated fire conditions.
.. A DS TH ACT j The keyed blocks on the Sequovah Nuclear Plant Safe Shutiinwn Iogic Diagram are expanded hv developing smaller tonic diagrams which identify the subsystem (s) and/or components required to provide the f inct Ion in the keyed block. The keyed logic dianrams are then used to compile lists of equipment which may he required to achieve and maintain safo shutdown under postulated ftre conditions, for each l<cy, a spurlona list 19 generated which containn the equipment where spurious ict uat ion would defeat the function provided hv the key.
(,] Continuation sheetbl used-l l Mwenlitri emt store ,siculation en Mt Os serwe, center.
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EN DES CALCULATIONS-verm TvA 10697 (EN DES 1 B4)
PLANT / UNIT Trd Equipment Required for Safe Shutdown Sequoyah 1 and 2 !
.. 'r.. per 10CFR50 Appendix R PREPARING ORGANIZATION KEY NOUNS (Connait MEDS CIS DESCRIPTORS LIST)
("'
OE-NEB-NSAT Fire Protection Each time these calculations are issued, preparers must ensure that the originet (RO) MEDS eccession BRANCH / PROJECT IDENTIFIERS number is filled in.
MEDS eccession number , ,[
Rev (for MEDS' use)
N/A B Bo&ODo %B 'a40013 pas MM^"M12"f0 an1019A0003 r/BNEB -'841017 21 9 21.V
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b sI bUh G s.)gure f Ud ((
ga,. fj [M J STATEMENT OF PROBLEM
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Determine the functions and sets of equipment required for safe shutdown of Sequoyah Nuclear Plant t nder postulated fire conditions. ]
- A
- ~ . . -
o N# ' ABSTRACT The keyed blocks on the Sequoyah Nuclear Plant Safe Shutdown Logic Diagram are i expanded by developing smaller logic diagrams which identify the subsystem (s) and/or f components required to provide the function in the keyed block. The keyed logic diagrams are then used to compile lists of equipment which may be required to achieve ,
i and maintain safe shutdown under postulated fire conditions. l i
For each key, a spurious list is generated which contains the equipment where spurious actuation would defeat the function provided by the key, i
Cnntinustion sheet (s) used.
Microfilm and destroy. O l b Microfilm and store calculation in MEDS Service Center. !
@ Microfilm and return calculation to: h(,ygg Addressy) ppg i . l
- - i
st REVISION LOG' p TitleEQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R I
" '[, "
' DESCRIPTION OF REVISION App ed .
l
.a i 1 Paragraph 2.3.4.f - For level indication of large tanks, the pump suction pressure was added as an alternative to local level l
indication. j i
Section 3.0 - Assumption 10 was added. The normal and alternate power supply to each battery charger was assumed available in the f
1 development of the component list. -
Section 6.0 - Added section referencing Appendix A.
1 Enclosure 1 - The enclosure had a general revision. The major ,,
l changes in the revision were
{
1
- a. Key 29 was revised to delete all automatic trips. j l
Deleted Key 32.
c.
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- d. Deleted Keys 37B, 37E, 371, 37J, 37K, 37L, 37M, 37 O&P, and 37Q.
Appendix A - This appendix was added to describe the functions provided by the keyed blocks oa the shutdown logic diagram.
2 Sections 2.0, 2.2.3, 2.3.4.e, 2.3.10, 2.5.1.b, and 3.9 - General revisions made for clarity.
1 Enclosure 1 - The enclosure had a general revision. The major ]
changes in the revision were: '
- a. Key 1, 9, 13,19, 37A, and 40 revised to reflect power or air removal from selected valves.
- b. Key 37F revised to delete cooling to battery rooms I, IV, and from 480V board rooms IA and 2A.
- c. Key 37N revised to delete auxiliary building general supply and exhaust fans (and control circuits).
Appendix A - Revised to more accurately reflect key functions.
Appendix B - This appendix was added to describe the operator -
ac tions required for each key.. -
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\
TV A 10534 (EN Ef513a.05
,. REVISION LOG
Title:
EQUIPMENT REQUIRED FOR SAFE SHUTDOWN PER 10CFR50 APPENDIX R lp ,
k " ';', "
, ' DESCRIPTION OF REVISION a,,$,o .
..s v
3 Enclosure 1 - The enclosure had a general revision. The major changes in the revision were:
- a. All notes in Key 1 were moved to a single page. )
- b. Valves 0-FCV-67-151, 0-FCV-67-152, and 1&2-FCV-67-146 (Key 1) . ,
were moved to the header lists in back of key. .
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- c. The balance of Key 37F was deleted.
Appendix A - Revised to reflect changes in Enclosure 1,~ and to more accurately reflect key functions. ..
Appendix B - Revised to reflect changes in Enclosure 1.
4 Section 3.0 - Assumption 11 was added. To prevent spurious operation of motor-operated valves (MOVs), the operator may remove power from the valves by opening the breaker at the MOV board.
l(k '
Enclosure 1 - The enclosure had a general revision.
Appendix A - Revised to reflect previous changes.
Appendix B - Revised to reflect changes in enclosure 1.
$ Enclosure 1 - Revisions were made on keys 28, 29, and 37J.
t Appendix B - Key 28 changed to reflect enclosure 1 change. -
Appendix C - This appendix was added to give a numerical listing of all equipment in the SLD, 6 Sections 2.2.2, and 2.4, and 3.0 - Editorial changes.
Enclosure 1 - Revisions were made on keys 1 and 9 F "*E #
I Appendix B and Appendix C - Corrected typographical erros. {
/Mded rnanvat ac.tions to keys I and 9 l
)
E75133.05 TV A 105 34 (EN oES-4 78)
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f TABLE OF CONTENTS
1.0 Purpose and Scope
, 2.0 DesignLCriteria .,
3.0 Assumptions' -
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4.0 Sources of Information 5.0 Lists' of Components for Fires Inside the Main Control Building
-6.0 '. Lists of Components for Fires Outside the Main Control Building 17.0 Summary of Results .and Conclusions .
8.0 Figures , _
Enclosure
- i
. Appendix'A
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' Appendix B' ,
Appendix C f.
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1.0 ' Purpose and Scope l lC ^ This calculation defines the safety functions and sets of equipment k required to achieve and maintain safe shutdown of Sequoyah Nuclear Plant '
under postulated fire conditions. ,
The safe shutdown logic diagram (SLD) (Figure 1) shows the paths available to provide the required functions for safe shutdown. For each safety function, the subsystems and/or components which provide the function are identified in logical "and" and "or" fashion. The SLD shows the optional safe shutdown paths.
On the SLD, each subsystem and component necessary for providing a safety function is given a key number. For each key which requires further~ -- _
expansion, another logic diagram is developed to show major components and the supporting system (s) which must operate. From these logic diagrams, lists of components required to provide the keyed block's. function are generated and compiled.
2.0 Design Criteria 10CFR50 Appendix R (reference 2.6.1),, requires that one train 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 i within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Re ferences 2.6.2 - 2.6.6 provide further clarification of the requirements presented in Sections III.G and III.L of Appendix R. To ensure that sufficient systems and components are available to shutdown the J , plant, the components must be tabulated to aid the evaluation for fire damage. The following criteria must be followed to ensure the requirements of the references are met. ,
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2.1 Design Basis Event The design basis event is a' postulated fire in any plant area whether or not it normally contains combustible material.
2.2 Limiting Safety Consequences and Required Shutdown Functions 2.2.1 No fission product boundary integrity shall be affected:
- a. No fuel clad damage
- b. No rupture of any primary coolant boundary The rupture of a primary coolant boundary shall consist of the failure of a RCS pressure retaining component with a resulting loss of primary coolant from the RCS. The loss of coolant may be either directly to containment or to another low pressure system not designed to contain the coolant. A controlled release of primary coolant via a systems such as the pressurizer PORV, reactor head vent l system and letdown does not constitute a rupture of the !
primary coolant boundary. -
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- c. No rupture of the containment boundary The rupture of the containment boundary shall consist of -
i("~ the uncontrolled release of the containment atmosphere.
km Failures of closed systems inside or outside of containment need not be postulated unless a, failure can be induced by a" J -
fire.
+
2.2.2 The reactor coolant system process variables shall be within those predicted for a loss of normal ac power. (This only applies to alternative or dedicated shutdown capability per RG 10CFR50 Appendix R, Section L.) ,
2.2.3 The shutdown capability shall be able to achieve and maintain -
suberitical conditions in the reactor, maintain reactor coolant' -
inventory, achieve and maintain hot standby
- conditions for 'J...
an extended period of time, repair cold shutdown systems within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, achieve and maintain cold shutdown conditions
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thereafter.
- As defined in the Technical Specifications.
2.3 Performance Goals .
2.3.1 The reactivity control function shall be capable of achieving and maintaining cold shutdown reactivity conditions.
2.3.2 The reactor coolant makeup function shall be capable of
, maintaining the reactor coolant level in the pressurizer.
2.3.3 The reactor heat removal function shall be capable of achieving and maintaining decay heat removal.
2.3.4 The process monitoring function shall be capable of providing j direct readings of the process variables necessary to perform and control the above functions (see section 2.5).
- a. RCS pressure and pressurizer level
- b. Reactor coolant hot leg temperature or core exit thermocouple and cold leg temperature or steam generator j Pressure (to calculate Tcold),
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- c. Steam generator pressure and wide range os narrow range ;
level. l l
- d. Source range flux monitor j
- e. Diagnostic instrumentation for shutdown systems
- f. Level indications for all tanks used i If the tank is very large and significant time is needed to use the water, then local. indication or pump suction i pressure is acceptable.-
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' 2.3.5 : The-supporting functions shall be capable lof providing the:
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, . process cooling, lubrication, etc. necessary to permit the
' operation *of the equipment used for safe' shutdown by the' ~
- l(Q. . .? systems.
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' 2.3.6 ' The equipment and systems _ used to achieve and maintain hot E.:"'
f standby conditions should be (1) free of fire damage; (2). capable of maintaining such' conditions for an extended time period : longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> . if the ' equipment required to 1 achieve and maintain cold shutdown is not available due to fire damage; and (3)' capable of being powered by an onsite emergency power system.'
2.3.7; The equipment and systems'used to achieve and' maintain cold shutdown conditions should be either free of fire damage or the - ~~
fire damage to such systems should be limited such that repairs- -1 can be made and cold shutdown conditions achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Equipment.and systems used prior to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> sfter the fire should be capable of being powered by an onsite emergency' -
power system; those used af ter 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may: be powered by -
offsite power.
2.3.8 These systems need not'be designed to (1) seismic. category I criteria; (2) single failure criteria; or (3) cope with' other plant accidents such as pipe breaks or stuck valves except where required for other reasons,.e.g., because of: interface with or impaction existing safety systems or because of adverse
- . . valve' actions due to fire damage.
.. bb 2.3.9 The two units can be'in any combination of operating modes at the time of'the fire. ,
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-2.3.10 Manual actions-by operations personnel may include manipulation of equipment-located in any accessible area of the plant provided such actions are within the capabilities of the minimum number of operators defined by the staffing requirements. F 2.3.11 In addition to the identification of equipment which must " -
operate for safe shutdown, that equipment whose spurious l operation would adversely affect the safe shutdown capability I must also be identified.
2.3.12 The systems and components used for safe shutdown shall be capable of performing their intended function within their design limits and if possible as demonstrated by previously '
accepted analysis.
.. 2.4 (Section contents incorporated into Section 3.0) R(e
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2.5 Alternate Approach to Meeting NRC Requirements
, 2.5.1 Instrumentation providing direct reading of process variables . ,'
,, (reference 6.2, Enclosure 1, paragraph 3.4; reference 6.4, Appendix C to' Enclosure, Section D; reference 6.5, Section 11).
- a. The above references do not. allow the use of SG pressure instrumentation to provide a reading of RCS cold leg temperature.
Justification 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 controller. If a cooldown is in process, Thot can be used just as well as Teoid to determine cooldown rate -
since delta-T will remain relatively constant.
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 controller. The steam generator pressure instrument can be used to verify the set point on the PORV controller and to determine Tcold.
)
- b. The above' references specifically do not allow the use of SG narrow range level for manual SG 1evel control. ,
Justification
- Procedures will be writ' ten to instruct the operator as to which AFW pump to use based on the. location of the fire, ensuring flow to'the intact SGs.
2.6 References -
2.6.1 10CFR50 Appendix R 2.6.2 Generic Letter 81-12, February 20, 1981 2.6.3 Clarification Letter of Generic Letter 61-12, April-May 1983 2.6.4 SECY 83-269, July 5, 1983
. 2.6.5 IE Notice 84-09, February 13, 1984 2.6.6 Branch Technical Position CMEB 9.5-1
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3.0 Assumptions
- 1. Both units may be operating in any mode when a fire is postulated.
( 2. No failures other than those directly attributable to a postulated firo -
are to be considered. ..
- 3. Design basis events which can be caused by a fire must be prevented from occuring or must be mitigated. Design basis events which cannot ph be caused by a postulated fire (except loss of offsite power) are not considered to randomly occur with a postulated fire.
- 4. Equipment required for safe shutdown during a postulated fire must be-capable of performing their safety function while being powered by both -
~-
an onsite emergency power system and an offsite power system.
- 5. Equipment required for safe shutdown during a postulated fire need not be designed.to meet seismic Category.I requirements, single failure criterion, or other design basis event criteria.
- 6. Manual actions by operations personnel may include manipulation of equipment located in any. accessible area of the plant provided such actions are within the capabilities of, the minimum number of operators defined by the staffing requirements.
- 7. During a post-fire shutdown, the fission product boundary integrity must be maintained (e.g., no fuel clad damage, no rupture of any
{(N' primary coolant boundary, no rupture of the containment boundary).
- 8. The safe shutdown analysis is based on the design reflected in the i latest revision of EN DES issued drawings and documents. A field .l verification will be required to ensure the analysis reflects the as constructed configuration.
- 9. The ERCW system must be aligned such that A-train ERCW cooling water is supplied to the A-train CCS heat exchangers. The same applies for the B-train lineup.
- 10. The normal and alternate auxiliary power supply to the vital battery chargers will be available.
- 11. To prevent spurious operation of Motor-operated valves (MOV's), the p4 operator may remove power from the valves by opening the breaker at the MOV board.
4.0 Source of Information
- 2. EN DES-SEP 84-10, Safe Shutdown Analysis for Postulated Fires at Sequoyah Nuclear Plant
- 3. EN DES-EP 3.03, Design Calculations ,
- 4. Sequoyah Nuclear Plant 10CFR50, Appendix R - Fire Protection Submittal, October 1981. ~
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'5. The following SQN EN CES drawings were used to generate component lists.
l l(T 47W801-1 R25 47W859-3 R18 47W801-2 R23 47W859-4 R7 -
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47W803-1 R17 47W610-1-1 R16 : ._ l
, 47W803-2 R25 47W610-1-2 R14 $
47W809-1 R23 47W610-3-1 R16 47W809-2 R5 47W610-3-2 R16 47W809-5 R8 47W610-3-3 R12 47W810-1 R13 47W610-43-3 R13 47W811-1 R23 47W610-62-2 R16 47W811-2 R13 47W610-62-3 R10 47W812-1 R11 47W610-63-1 R14 47W813-1 R21 47W610-68-1 R15 -
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47W819-1 R21 47W610-68-2 R14 47W830-4 ' R18 47W610-68-3 R17 47W845-1 R19 47W610-68-4 R20 _
47W845-2 R19 47W610-68-5 R19 47W845-3 R18 47W610-68-6 R11 -
47W845-4 R19 47W610-68-7 R7 47W845-5 R9 47W611-62-3 R5 47W846-1 R18 , 47W611-62-4 R11 47W848-1 R14 "
47W611-63-2 R9 47W848-2 R8 47W611-63-4 R6 47W848-3 R5 47W611-63-8 R2 j 47W848-8 R12 47W611-68-3 R9 j 47W848-9 RIO 47W611-99-7 R7 47W848-12 R9 47W611-99-2 R5 47W859-1 R12 47W611-99-6 R8 47W859-2 R17 ,
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5.0 Components for Fires Inside the Main Control Building The following instrumentation located in the auxiliary control room )
shall meet .the physical separation and electrical isolation requirements, such that a safe shutdown of the plant can be reached in the event of a fire in the control building. Additionally, a path of equipment from section 6 shall be operable (manual or automatic ~
operation) and prevented from spurious operation.
Pressurizer Pressure and Level Level
- 1. LI-68-325C
- 2. LI-68-326C
, Pressure 3
- 1. PI-68-336C
- 2. PI-68-337C q
- 3. PI-68-342C E75133.06 _ _ _ _ _ _
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, ' Reactor Coolant Hot Leg Temperature l 1
'TI-68-1C'(Loop 1)f '
C' " 16 e-
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- 2. .TI-68-24C:(Loop 2)
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'3.. TI-68-43C.(Loop 3) '
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,; 4. TI-68-65C'(Loop 4) 3 1
.j St'eam Generator Pressure and Level '
'l Pressure
'1. PI-1-1C'(Loop 1)
, 2. PI-1-8C (Loop 2).
3...PI-1-19C (Loop 3) ~'
.4. PI-1-26C:(Loop 4) ~L, Level -
- 1. LI-3-164C (Loop 1) -
- 2. LI-3-156C (Loop 2)
- 3. LI-3-148C (Loop 3)
- 4. LI-3-171C (Loop 4) _,
Source Range Flux' Monitor
- 1. RI-90-210
,(;;
I Level Indication'for Tanks Volume Control' Tank .
1.- LI-62-129C 1
v Pressurizer Relief Tank "
- 1. .LI-68-312C F
- 2. PI-68-311C Surge Tank
- 1. LI-70-63C
- 2. LI-70-99C Diagnostic Instrumentation for Shutdown Systems ,
. Auxiliary Feedwater System
.l
- 1. FI-3-163C (Loop l') 1
.2. FI-3-155C (Loop 2) '
L 3. FI-3-147C (Loop 3)
- 4. FI-3-1700 (Loop 4)
- 5. FI-3-142C (Aux FPT Disch)
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Chemical and' Volume Control-Tank
- 1. TI-62-800 (Ltdn Ht Exch Outlet)
- 2. PI-62-920 (Chg Hdr Press) "
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- 3. 'FI-62-930 (Chg Hdr Flow) , w
, 4. FI-62-37C (Emer Boration) E T 1 A '
Safety Injection System 4 1 i
- 1. 'FI-63-173C (RHR Return) -
c.~ o
. Essential Raw Cooling Water ~
- 1. FI-67-61C (ERCW Supply Hdr A) y
- 2. FI-67-620 (ERCW Supply Edr B) ,
4/
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Component Cooling System > -
s
- 1. PI-70-24C (CCS Htx A Inlet)
- 2. PI-70-17C (CCS Mtx B Inlet),
- 3. FI-70-159C (RHR Htx A Sup Hdr)
'4. FI-70-164C (Misc Equipment Sup Hdr)
- 5. F1-70-165C.(RHR Htx B'Sup Hdr)
( ,i 1.- TI-74-38C (RHR Feed A Out Temp)
- 2. TI-74-40C (RHR Feed B Out Temp) 6.0 Lists of Components For Fires Outsi'de the Main Control Room '
2f 1
Key logic. diagrams and component alists (Enclosure 1) were generated in d order - to identify all equipment required for any of the paths y ', 3 available for achieving and maintair.ipg s
. safe shutdown at Sequoyaii , f1 '3 Nuclear Plant under postulated fire fundicions. Individual lists of ' .U components were compiled for each keyed block on the safe shutdown C logie diagram (SLD) (Figure 1). Appendix A gives a brief description of the functions provided by each keyed block. Only those lists of components which correspond to the path (s) chosen on the SLD are required to achieve and maintain safe shutdown. j Each component list also includes a list of equipment whose spurious actuations would adversely affect the function identified in the keyed block. In some cases a small logic diagram is presented to more clearly identify combinations of '
spurious actuations which.are unacceptable. 4
!; The components whose spurious action could prevent a safe j i
I
. shutdown were those that (1) were inline valves in required flow paths (2) could divert flow fr3.n a required flow path or (3) could cause a design basis event and the required equipment to
, mitigate that event which may not be available because of fire *
- L damage. The shutdown logie dingram was used to generate a list
. 1 E75133.06 .
. . 7 .
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- 4- "-
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'off ec,mponents which: must operate and- a' set of marked-up d[r
{ '. showing.the componento and associated flow paths. The drawings were' use'd tolident .fy all of the:inline valves and allf ff the i
. k. valves which could divert' flow.- As part of:the review, a , . .. ~
spurious safety injection signal, phase A. containment isolation - :, [
,, signal and phase B containment isolation' signal were reviewed to i
' ensure that they did 'not' cause equipnent to operate or realign .
and defeat a safety function. The design! basis events were
- l. , ' reviewed to determine which events could bs caused by a fire.
f ' .
-For those' events which.could be caused by a fire, either the f mitigation system must be available O.ithe equipment'whose spurious' operation caused the event W a identified.
, For the sake z of conciseness, all ERCW components which are commoA ~ -
to'. the; keys required ERCW cooling 'are included only in Key 1."
d The remaining keys reference the applicable sections' of Key.1.
The equipment required for both headers of the Control Air System is contained in Yey 13. All components which require control air *
.1 to perform thdr safety function also require the equipment
- listed in Key 13.
- 7.0 . Summary of Re'suler and Conclusions . , '
q The lists.of components in this' calculation provide the' equipment necessary to perform the ' oafety functions required on the safe
.shutdoun logic diagram (SLD).' The subsystems and components y requiredjto schieve and maintain mafe shutdown will correspond to the patin' chosen on the SLD. Onlyi the components on .the lists' for.
(,l .-
the keyed blocks which lie along the chosen. path are needed for achieving and maintaining safe shutdodn. .
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,i ENCLOSURE 1 -
I (k
489 90 d
9' A
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1
)
i
Computed LL) Date M//t$-
Checked fee. Date y/r/n- .
, SEQUOYAH. NUCLEAR PIddiT KEY 1 (Operation List) -
Path 1 Centrifugal Charging Pump (CCP) A-A Must Operate
' CCP Auxiliary Lube Oil Pump A-A- (Note 13) 'Must Operate ~ ltt.}
CCP Pump Room Cooler Fan A-A' Must Operate Ins trument woop 30-183:(for fan control) (Note 14) Mus t 0perate CCS Pump A-A) - Either one Must Operate '
CCS Pump B-B) (Note 9),, Must operate }
ERCW Header 1A (Operation List) (Note 1) ~
ERCW Header 2A (Operation List) (Note 1) ,
FCV-67-168 (Note 6) Mus t Open
- 0-FCV-70-197 (Unit 1 Only) (Note 10) " ,. Either Must Close
- 0-FCV-70-198 (Unit 1 Only) (Note '10) , one Must Close [t').
~
Ins trument Loop L-68-335 (for LI-68-335A) - Any one Mus t Operate
(. Ins trument Loop L-68-320 (for LI-68-320 ) Must Operate Ins trument Loop L-68-339 (for LI-68-339A) _ Mus t Operate If the ECCS charging path or RCP seal injection are used for RCS makeup, the following charging pump miniflow valves mus t not isolate the miniflow line:
- FCV-62-98 (Note 5) Must Not Close FCV-62-99 (Note 5) . Mus t Not Close
- Handwheel operation acceptable.,
- If closure of one of these valves cannot be assured and the requirements of -
Note 10 cannot be met, the following must be accomplished:
- FCV-70-40 ) 1Any one Must Close
- FCV-70-11 ) Must Close
- Must be Closed 1 0-70-529A
- FCV-70-41 ) .
):
'.Any one Must Close M' -
- FCV-70-1 ) Must Close l
- 0-70-529B )~
Must be Closed
- 1-70-531 l Must be Closed 4 1
]
l i E24216.01 , NEB - Jan'.~ 31, 1985
- ' )
W Computed bO Date illtf/((5/ t *
'. Ch ecked fst Da te rds/nf-((' SEQUOYAH NUCLEAR PLANT KEY 1 (Operation List)
Path 2' L '
CCP B-B Must Operate l CCP Auxiliary tube Oil Pump B-B (Note 13) CCP Pump Room Cooler Fan B-B Must Operate Must Operate lD Instrument' Loop 30-182 (for fan control)- (Note 14) Hust Operate l E2
~
CCS Pump C-S (Note 11) Nust Operate lp-ERCW Header 1B (Ope ation List) (Note 1) ERCW Header 2B _(Operation List)- (Fate 1) - FCV-67-170 (No te 6) Must Open
, PJ Instrument Loop L-68-335 (for LI-68-335Ai Any. one Mu st Ope ra te -
.( Instrument Loop L-68-320 (for LI-68-320 ) Matt Operate
. Instrument Loop L-68-339 (for LI-68-339A) ,
Must Operate If the ECCS charging path or RCP seal injection are used for RCS makeup, the following charging pump miniflow valves must not isolate the miniflow line: . FCV-62-98 (Note 5) Must Not Close FCV-62-99 (Note 5) . Must Not Close l to ).- i
.. 1
-l 1
)
i
') .
E24216.01 NEB - Nov. 27, 1984 I l 1 i_ _ _ _ _ _ _ _ _
= d j
[ Computed b Date 4- I T- El,
~
j Checked Playcu. k Date d-/8~84-SEQUOYAH NUCLEAR PLANT - KEY 1. (Spurious List) ".-.' i- ., If Path 1'is used, the following spurious actions must be prevented: Unit 1
*1-FCV-70-156' ) (Note 12Y Any one 1-VLV-70-545A )
Must Not Open
,Must be closed'
' lO g
h 1 1-VLV-70-546A ) ,,_ Must-be Closed"- . 1-FCV-70-8 (Note 5) Must Not Close
- 1-FCV-70-9 ) (. Note 5' Either one Must Not Open 1-FCV-70-10) (Note 5 Must Not Open -
1-FCV-70-2 (Note 5)- Must Not Close 0-FCV-70-34 (Note 5) (if CCS Pump 1B-B is used) Must Not Close 1-FCV-70-25 (!!ote 5) Must Not Close i(k 1-FCV-70-64) (Note 5) Either one 1-FCV-70-74) (Note 5) Must Not Open Must Not Open 1-FCV-70-26) (Note 5) Either one Must Not Open - 1-FCV-70-27) (Note 5) - Must Not Open 1-FCV-70-13) (Note 5) Either one Must Not Open 1-FCV-70-23) (Note 5) Must Not Open 1-FCV-67-478 (Note 5) Must Not'Close 1-FCV-67-127 (Note 5) Must Not Close ERCW Header 1A (Spurious List) (Note 1) ERCW Header 2A (Spurious List) (Note 1)
- Handwheel operation acceptable g E24216.01 NEB - Jan. 29,19M
- s
I Computed b Date 4-ll-JG Checked Claw l Date fo~l8-86 lfk . ' .
/k l SEQUOYAH NUCLEAR PLANT KEY I (Spurious List) ~
Unit 2
*2-FCV-70-156 ) (Note h Any one Must Not Open RG 2-VLV-70-545 A) Must be Closed g 2-VLV-70-546A) __, Must be Closed <
2-FCV-70-15 (Note 5) Must Not Close 2-FCV-70-195) (Note 5) Either one Must Not Open -'. l 2 FCV-70-196) (Note 5) Must Not Open 2-FCV-70-2 (Note 5) Must Not Close
~
0-FCV-70-3 9 (Note 5) (if CCS Pump 2B-B is used) Must Not Close 2-FCV-70-16 (Note 5) , Must Not Close 2-FCV- 70-76) (Note 5) Either'one Must Not Open 2-FCV-70-78) (Note 5) Must Not Open 2-FCV-70-28) (Note 5) Either one Must Not Open 2-FCV-70-29) (Note 5) Must Not Open 2-FCV-70-14) (Note 5) Either one Must Not Open ' 2-FCV-70-18) (Note 5) _ Must Not Open 2-FCV-67-127 (Note 5) Must Not Close
**0-FCV-70-193 (Note 3) Must Not Open R4
**0-FCV-70-194 (Note 3) Must Not Open ERCW Header 2A (Spurious List) (Note 1) -
1-FCV-67-223 (Note 7) Must Not Close , 2-FCV-67-223 (Note 7) Must Not Close j 1-FCV-67-424 (Note 8) , Must Not Open
- Handwheel operation acceptable ,
**If neither valve can be protected from spuriously opening and'the requirements of Note 3 cannot be met, the following must be accomplished:
*FCV-70-40 5 Any one ~~ Must Close i
*FCV-70-11 ) Must Close R4
- Must be Closed 0-70-529Al
*FCV-70-41 ) Any one ~
Must Close l
*FCV-70-1 ) Must Close !
- 0-70-529B) ~~
Must be Closed OR - ,
- i 1-70-531 )] Must be closed E24216.01 NEB - Jan. 29, 1986
Computed bW Date tjJM)@ <
. Y Checked & Da te ' /2bo/n' h
, SEQUOYAH NUCLEAR PLANT KEY 1 (Spurious List)
- If Path 2.is used, then the following spurious actions must be ;
prevented: Unit s l ' and 2 0-FCV-70-12 (No te ' 5 ) ' Me at No t Clo se , , FCV-70-3 (No te 5 ) . Must Not Close , 1-FCV-70-9); '(No te 5) Either.one Must Not Open 1-FCV-70-10) (No te - 5 ) Must Not Open ,
'~
2-FCV-70-19 5) (No te 5) Either one- Must Not Open 2-FCV-70-19 6) .. (No te . 5 ) Must Not Open FCV-70-75 (Note 5)
- Must Not Close 1-FCV-70-64) (No te 5 ) ' Either one Must Not Open 1-FCV-70-74) (No te 5) Must Not Open
,1-FCV-70-26) . (No te 5 ) Either one Must. Not Open 1-FCV-70-27) (No te 5) Must Not Open 1-FCV-70-13) (No te' 5) Either one Must Not Open- -
1-FCV-70-23) (No te 5 ) - Must.Not Open 2-FCV-70-76) (No te 5) Either one
, Must Not Open 2-FCV-70-78) (No te 5) Must Not Open 2-FCV-70-28) (No te 5) . Either one Must Not Open 2-FCV-70-29) (No te 5 ) Must Not Open .
2-FCV-70-14 ) (No te 5) Either one Must Not Open ) 2-FCV-70-18) (No te 5) Must Not Open 0-FCV-70-22 (No te 5 ) Mast Not Close FCV-67-128 (No te 5) Must Not Close I l
.s. .
E24216.01 NEB - Nov. 27, 1984 I r
l T
. i. I Computed 8 h Date N - I T~ TG, -
Checked EXab)/ Date $-l$~86
/k -
SEQUOYAH NUCLEAR' PLANT KEY 1 (Spurious List)
' . ,' J
{ 1 2-FCV-67-147-(Note 5) Must Not Close l j p FCV-70-153' (Note 47-Any one MustNotOpen.lR6 VLV-70-545B Must be Closed R+ VLV-70-546B _ _ , . Must be Closed
~
p ERCW Header IB (Spurious List) (Note 1) ' ERCW Header 2B (Spurious List) (Note 1) R I(k-R4 t E24216.01 NEB - Jan. 29, 1986 o
Computed bQ Date 3-4-/(8~~- i Checked & Date .y/[/g5 C , SEQUOYAH NUCLEAR PLANT KEY 1 - ERCW Header 1A (operation list)- '~- i ERCW Pump J-A) Either One Must Operate-ERCW Ptanp K-A) Must Operate ERCW Ptanp Q-A) Either One Mus t Operate ERCW Pump R-A) Mus t Operate ERCW S trainer A1A-A Mus t Operate . 1-FCV-67-491A : Must Operate 1-FCV-67-66 Mus t 0 pen 2-FCV-67-66 Mus t Open
*1-FCV-67-72 Must 0 pen
~
ERCW Header IA (spurious list) 1-FCV-67-491D Must Not Open 1-FCV-67-492 (Note 5) Mus t Not Close - FCV-67-81.. (Note 5)
- Must Not Close 0-FCV-67-12 (Note 5) Must Not Close 0-FCV-67-364 (Note 5) Mus t Not Close I-FCV-67-125)(Note 15)~-Either One Mus t Not Open p,
. I( 1-FCV-67-126)(Note 15)~ Mus t Not Open 1-FCV-67-147 (Note 5) Mus t Not Open
*0nly if the 5th diesel generator is subs tituting for an A-train diesel.
i i 3 E24216.01 NEB - Jan'. 31, 1985 I
* ~
' ~
I Computed h w Date g,1, Es~ Cheeked. #N Date y/p/jd_ SEQUOYAH NUCLEAR PLANT '
, KEY 1 ERCW Header 2A (operation list) -
ERCW Pump J-A) Either One Mus t Operate - ; ERCW Pump K-A) Mus t Operate ' I ERCW Pump Q-A) Either One Mus t Operate i ERCW Pump R-A) Mus t Operate ' ERCW S trainer A2A-A ' Mus t Operate ~ .. 2-FCV-6 7-491 A Must Operate ~
**1-FCV-67-146 Mus t Operate
**2-FCV-67-146 Mus't Operate N.
ERCW Header 2A (spurious list) 1-FCV-67-491D Mus t Not Open 2-FCV-67-491D - Mus t Not 0 pen 1-FCV-67-492 (Note 5) - Mus t Not Close-2-FCV-67-492 (Note 5) Must Not Close 2-FCV-67-81 (Note 5) Mus t Not Close 2-FCV-67-125)(Note 15 *Either One Mus t Not Open g 2-FCV-67-126)(Note 15) Mus t Not 0 pen
. 0-FCV-67-364 (Note 5) ' Mus t Not Close 0-FCV-67-12 (Note 5) Mus t Not Close
~**Handwheci operation acceptable. -
p l
,i 5
a E24216.01 NEB - Jan'. 31, 1985 i u_ -- - -
Computed h u Date 1- to -fS~ Checked f// Date 3/f/g_ SEQUOYAH NUCLEAR PLANT
, KEY 1 ERCW Header IB (operation list) -*
ERCW Pump L-B) Either One Mus t .O perat e
. ERCW Pump M-B) Must Operate ERCW Pump N-B) Either One Must Operate ERCW Pump P-B)~ Must Operate ERCW S trainer BIB-B Mus t Operate ._.
1-FCV-67-490A Must Operate -*
.o 1-FCV-67-67 -
Must Open J2-FCV-67-67 Mus t Open
'*1-FCV-67-72 Mus t Open
~
ERCW Header IB (spurious list) 1-FCV-67-489 (Note 5) Mus t Not Close
' 0-FCV-67-14 (Note 5). Mus t Not Close - )
0-FCV-67-365' (Note 5) " Must Not Close I Mus t Not Close - 1-FCV-67 (Note 1-FCV-67-123)(Note 15) 5) lEither One Mus t Not Open gl ( 'l-FCV-67-124)(Note 15)j Mus t Not Open.
., 1-FCV-67-490D Mus t Not Open
*0nly if the 5th diesel generator is substituting for a B-train diesel.
i 1 1
. l l
E24216.01 NEB - Jan. 31, 1985 i
f. i I Computed Nlb Date 3~(p-W F Checked pg/ Date 5/p d f lr' ( SEQUOYAH NUCLEAR PLANT KEY 1 ERCW Header 2B (operation list)' '- ERCW Pump L-B) Either One Mus t Operate ERCW Pump M-B)- Mus t Operate ERCW Pump N-B) Either One Mus t Operate ERCW Pump P-B) Mus t Operate ERCW S trainer B2B-B Mus t Operate. . _ _ ~ CV-67-490A Mus t 0purate ,
**0-F CV-6 7- 15 2 ) Either one Must Operate p
**0-FCV-67-151) (Note 5) ,
Must Be opened
~
ERCW Hender 2B (spurious list) 1-FCV-67-490D Mus t Not Open 1-FCV-67-489 (Note 5) ' Must Not Close 2-FCV-67-489 (Note 5) - Mus t Not Close 2-FCV-67-490D Mus t Not 0 pen 2-FCV-67-82 (Note 5) Mus t Not Close 1-FCV-67-147 (Note 5) Mus t Not Open 0-F CV-67-14 (Note 5) Must Not Close 0-FCV-67-365 (Note 5) ~ Must Not Close 2-FCV-67-123)(Note 15) Either One Must Not Open g 2-FCV-67-124)(Note :15). , Mus t Not 0 pen
**0-FCV-67-151 (Note 5) -
Mus t Not Open j A.)
** Handwheel operation acceptable . ,
lp3 i I E24216.01 NEB - Jan. 31, 1985
Computed R m Date 4-18-8(, Checked Odd Date I- /8~86 SEQUOYAH NUCLEAR PLANT-KEY 1.(Operation List) ~ w..
. Note 1: - Components required for ERCW header flow' are listed in- the back of this key.
Note'2: If this valve spuriously 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 r:
are not closed. If the component cooling water system temperature % exceeds the system operating limits, some of the largernonsafty ~ loads.(such as the gas stripper and boric acid evaporator package)' must be isolated. _ Note-3: 'If both of these valves open, component cooling water pumps 2A-A and . 2B-B both must be operable. Note 4: Either the unit i valve or the unit 2 valve may spuriously open without affecting this path's operability. Manual isolation is Ma acceptable. " Note 5: - A design change is being made under ECH-L6258 to remove power from this valve. Note 6: A design change is being made under ECN-L6258 to remove control air from this valve. Valve f ails in the open position. Note 7: A design change is being made under ECN-L6258 to open this valve end remove power f rom it. Note 8: A design change is being made under ECN-L6258 to close this valve and remove power from it. Note 9: If CCS pump B-B is used, equipment associated with supplying B-train - power will have to be evaluated. 1 Note 10: If neither 0-FCV-70-197 nor 0-FCV-70-198 close, component cooling i water pumps 1A-A and 1B-B both must be operable. Note 11: CCS pump IB-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 12: If this valve spuriously opens, component cooling water pumps 1A-A and IB-B both must be operable or spent fuel pit cooling via CCS R' heat exchanger A must be isolated if manual valves 1-545A or 1-546A are not closed. If the component cooling water system temperature exceeds the system operating limits, some of the larger nonsafety loads (such as the gas stripper and boric acid evaporator package)
- must be isolated.
l ) L 1 E24216.01 NEB - Jan. 29, 1986 C_______________.
~
~ comptid 12u: 4-1t-so wega! oh@gG-IS-86 SEQUOYAH NUCLEAR PLANT KEY 1 (Operation List)
(Continued): 3-4'
' Note 13: The lube oil pump must be operable or the' switch bypa ssing the : oil-pump (which will be installed) must' be used for CCP stsrt.
Note 14: Fan will start on high room temperature or pump start ' signal. Note'15. The ERCW headers spurious lists contain the containment spray (CS) heat exchangers isolation valves (1&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, Rt 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). '
1 4 C
- v. . l 1
]
.l J
I s 1 e I i ex --. _ L __ _-.---_ _
' ~
v O e - l r w m ad s o o vHr d p o e I n R nWl ay oC o r p i R o l a l m
. t EC oi u .
a f rl P l ., l mm t i i ooo nx r sro ou e If R C a Cl A o V o 4 - HC 4 g l 4 ^- 1 r d e m nr . d a o ae e o w R l o H l op os r Ww v t r t y i C o e nr Rl Wl oa f EF C o ci R o , l EC pi x mx H 1 uu S P a C g yp C n rm .
/ hi au Wt l i p 1 Ci o l .
R wo) il e D E p cz xi N H uo A h euW CS a ee r 1 A t dRC Pb w , eEC C uo sn Cl p eiBB ml// x u AA H se srrr S . p AaTT ( C m C u Y l p o _ t i rg W on f i C l R S o E C o C c
,e D d v
M - r e l d a @ e C H w S o Cl CF
.lt ii
Computed t\ Lib 3 Date 11/1(/)s'y ( f Checked Z&& Date u j>/W C ,, SEQUOYAH NUCLEAR PLANT KEY 2 (Operation List) -
. :-a ,
a FCV-62-93 _
. Any se t Must Be Open
*VLV-62-534 Must Be Opened Must Be closed g
- VLV- 62-533 _
~
*VLV-62-526 -
Must Be opened -
~
*VLV-62-527 Must Be Closed
- Handwheel operated valves.
a l E24216.01 NEB - Nov. 27, 1984 B
Oa e-sV 2 6 - oL lV C* s
. r e
D v l N
'va r
i A d e 6 t 2 a 5 r e 2 p 6 o l nV e eL e pV . O* h w d n a H
- * . i 3
3 . 5 2 6 e - sV oL n'l V C* . 2
}J I
D I Y I R E N K A OL I J 4 \ 3 . 5 2 6 ~ nV \ eL pV O* ii n - e p3 O9 n2 i6 O a - mV eC RF 6
~
' Computed % D .Date M, f(r Checked . fat Date y/p/// :
I SEQUOYAH NUCLEAR PLANT KEY 4 (Operation ~ & Spurious List) .!
-*LCV-62-132 Must Not Close Until Key 5 Has Been Established
'*LCV-62-133 Mus t Not Close Until 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 132 or -133 Until Key 5 Has Been Established -
** Level Control Loop 62-129A (for LI-62 .129) Must Operate l/LJ
*Short tenn water source. In the event 'f a fire in an area that will affect .
E these valves or associated circuitry, the 'arator should remove power from both valves (open breakers at MOV board) or smitch over to the RWST.. N
**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 {1 100% level is indicated, or erratic level indication occurs) the operator '
should inunediately switch over to the RWST. __ t.- , l-l 1 E24216.01 NE B - J an . 31, 1985
i t ! Computed h O Date '5- /, - 85"~ Checked gec. Date y/p//(
)p SEQUOYAH NUCLEAR PLANT C , KEY 5 (Operation List) a..
-' Path'1' _
*LCV-62-135) ' Either one Mus t O pen.
'*LCV-62-136) Mus t Open
*LCV 132) . Either one Must Close
- *LCV-62-133) _,
Must close - y , OR -,
*LCV-62-135) Either one Mus t Open
~
*LCV 136) - Mus t O pen ,
~
P CV 119 Mus t Not Fail Open PCV-62-120 FSV-62-125~ These valves mus t be opened PCV-62-126- - within 24 hours to PCV-77-89 _ depressurize the VCT l
~
OR VLV-62-689 I
*VLV-62-692 These manual valves must
*VLV-62--6 93 be closed .!
Path 2
*FCV-63-6 ) Either one Mus t Open
*FCV-63-7 ) Mus t Open
*LCV-62-132) Either one Must Close
*LCV-62-133) Must Close
- Handwheel operation acceptable. Handwheel operation must be used to close LCV-62-132 or LCV-62-133 if power has been removed f rom them (see Key 4) .
p 1 Note: For Path 1 only, if LCV-62-132 or LCV-62-133 are not closed or the vcr lft 3 pressure not less than 17.03 lb/in2g in 24 hours, 15.91 lb/in28 in 36 hours, or 12.56 lb/in2g in 72 hours, then the RHR sys tem mus t be available, the RCS temperature below 2000F, and the CCP stopped. l R,5 ! (This note not applicable to Path 2) l l I E24216.01 NE B - J an .' 31, 1985 i
- t. .,
Computed hb[j Date 3-L, -W Checked fif Date 3/7/Pf SEQUOYAH NUCLEAR PLANT KEY 5 (Spurious List for Path 2) l p y '-- If Path 2 is chosen: FCV-63-5 Must Not Close FCV-63-47 Must Not Close . If RHR pump A-A spuriously starts: FCV-72-40 Mus t Not Open - FCV-72-41 Must Not Open .. l' FCV-74-12 Must Open If RHR pump B-B spuriously starts: FCV-72-40 - Must Not Open FCV-72-41 Must Not Open FCV-74-24 Must Open CS Pump A-A q Must Not Start OR
*FCV-72-? d Must Not. Open/ Remain Operable CS Pump B-B 1 Must Not Start OR
*FC7-72-39 I , Must Not Open/ Remain Operable
**FCV-63-72 Must Not Open
**FCV-63-73 Must Not Open
*These valves will open on a spurious Phase B containment isolation signal.
They will be required to be reclosed.
**If these valves cannot be protected and spuriously open, FCV-63-1 must be -
closed, 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 hours).
- i E24216.01 NEB - Feb. 25, 1985 l
L_______ _ _
- v. O 227 C 66 t 667 - -
_ L - - - VV - C VVV LL _ SCC VV . I FPP *
- _ e 1 5
9 : 3 N 8 _ 1 E 6 ,
- P - "
N2 I O 2 * ' _ E 6 4 r v _ P i O V- D C N L A C " 4 u a v 3 3 3 3 1 3 1
- E -
2 S 2 6 O 6
- L -
V C V C C L L R O O 2 2 3 3 E 1 1 S - - O 2 2 L 6 E 6 C - S - V O V C L C L C L V D 4 N r, A D N 4 A 6 3 1 7 i E - - E 2 3 f P 6 N 6 O - E - V P V C O C L F
, R R 4 O O 5 6 3 -
1 3
- N 6 2 E -
i S 6 P V . F - O C P V F O C
- L 6
l
, <- Computed bO Date INES)f4f (. (- t
' Checked //4 Date /e[,/v/.
f~, i L l(-~ SEQUOYAH' NUCLEAR PLANT l KEY. 6 (Operation List) '
-c
- ,r -
' *FCV-63-25 ) ' - Either 'One Must Open/ Remain Operable
*FCV-63-26) , Must open/ Remain Operable
~
j' *FCV-63-39) - Either One Must Open/ Remain Operable ! *FCV-63-40 ) Must Open/ Remain Operable - FCV-63-41) ' - Any One Must' Close ~~ FCV-63-42) Hust Close -- VLV-63-574) , Must close
*An inle t valve and an outle t valve to the BIT must open and one of these will be :
required' to throttle the flow to the RCS*. i f i it l i I-E24216.01 NEB - Nov. 27, 1984
ji
-g D
_6 R- . 2 . n_3 e6 - p
' O V- C F
4 f 'r r o 5 2 n3 e6 p - O V C F , 0 4 n3 e e6 p -
- O V C
F r i r u d 6 o n l1!+ a Y r
, E K .
9 3 n - e3 . p6 ~ O - V C . F E4 S7 O5 l r / L - C3 6 v f, /r
/4. '
2 r ;s 4
/'
e - s3 o6 V /n ((/e y l - e CV t t C a a F D D d r o Dd u
%k e -
1 4 b f Y s3 o6 l - CV udre d e 5 f C a 'k F p c e e r h
. ?l lIl P l!
C
Computed 6 0 Date h -83~ f. t Checked ftl/ Date y/p/rf SEQUOYAH ' NUCLEAR PLANT ( , EY 7 ,
- w l
"' . Operation List l FCV-62-69) ' Either One ' ~~ Mus t Close FCV-62-70) .,
Mus t Close
~
OR FCV-62-72 Must Close FCV-62-73 Mus t Close _
'FCV-62-74' ,
Mus t Close - Spurious List
*PCV-68-334 Mus t Not Open ~
*PCV-68-340A Mus t Not Open FCV-74-1 ) Either One Mus t Remain Closed FCV-74-2 )
" Mus t Remain Closed - N FSV-68-394) Mus t Not Open FSV-68-395) , ] Mus t Not Open
- OR FSV-68-396) l Mus t Not Open FSV-68-397) ,
Mus t Not Open i
*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 cooldown will be used for preocurizer level control. The RHR sys tem mus t be available within 15 hours to continue the cooldown to cold shutdown and stop seal injection if normal or excess letdown is not available, gg E24216.01 NEB - Jan. 31, 1985 s
s2 o6
'1 - .
CV
- C F ,
3 "' 7 d e - " n s2 o6 a l - I . CV ' C F-2 . 7 e2 s6 o - lV CC F f 1 7 r f Y f, o S E K v 0 7 e - s2 o6 l - l CV C F 9 = 6 e2 I s6 o - '. _ l V . CC - F
\
y l e .
Computed .hMk)Date II/Lf)Y9 Checked #t/- Da te /z/s/V ((f , SEQUOYAH NUCLEAR PLANT KEY 8 (Operation List) FCV-62-54) Any One Must Close FCV-62-55) Must close FCV-62-56) Must Close F l
/
)
i 1 j l l l l E24216.01 NEB - Nov. 27, 1984 _ _ - - ~ . - _ _ - _ . _ . . _ _
- 3. .
;O 7 -
.z"
~. .
[
.. h_
[ v\;; s
~ .
e .
% c ,
N'" T c, g
- l .
i z-
~
~
~
O I ,
)-
h - 6 5 e-s2 o6 l - CV C
.F ?
+
e 5 5 f e- i s2 y o6 V: g 8 l - CV C u .EY F - _ K
/W
~
6
/f -
(> e t 4 a - 5 D e2 _ s6 o-l V ._, CC F ._ g
~
y
/ ._
6 d _ e - k _ c e . h _ C lltl: ll! h -
7 ._ __ l
- j. y Computed NO Date' w to-p1;-~
/'
; Checked f44 Date 3b/gf 4 c.
{
.k , ' SEQUOYAH. NUCLEAR PLANT , y KEY 9. (Operation List) '
T
. 4 Function 6' ' RCP Thera 21 Barrier Booster Pump A-A) Either One Must Operate
[
< *RCP Thermal Barrier Booster Pump B-B) Mus t Operate
\ 'r CCS Pump A-A) Either One Must Operate ;
*CCS. Pump B-B) Mus t Operate
.ERCW Header IA (Operation List) (See Key 1) #,
ERCH Header .2A (Operation Li.sc) (See Key 1) k. i
; ***0-FCV-70-197 (Unit 1 Only) Either One Mus t Close
***0-FCV-70-198 (Unit 1 Only) "
Must close h
*If B pumps are used, equipment associated with supplying B-train power will have
,to be evaluated.
** Handwheel operation acceptable.
***1f neither 0-FCV-70-197 nor 0-FCV-70-198 close, component cooling water pumps 1A-A and 1B-8_ bor.h mus t be operable. If both pumps are not operable, the .;
fallowing mus t be accomplished: ""
**FCV-70-4 0 [ Any one , Must Close d **FCV-70-11 ) Muse Close }t,,3
[' ** 0-70-529A), , Mus t be Closed
**!CV-70-41 ) Any one Must close -l
**FCV- 7 0-1 ) Must close
** 0-70-5 2 9B),, ,
Must be Closed j
. OR i
** .1-70-531 1
Must be Closed I a 1 I i r
. e E24216.01 NEB - Jan. 31, 1985 i
' D d'n - ' . ,_
7- :,-
-Jy
.~ .
+
g
. ; .g
/$
Computed Ra.4. . Date N-IS s
" Checked N U) Date'Cr~$E'*SG~
/9" ; .
SEQUOYAH NUCLEAR PLANT -[ y
,' KEY 9 (Spurious List)
Unit 1 t- ';* , ERCW Header 2A (Spuri us List) (S$e Key '1) ' 1-FCV-70-133 (Note 1) i
') W Must Not Close/ Remain Operable (I 1-FCV-70-134 (Note 1)-
/ Must.Not'Close/ Remain Operable - ge
- 1-FCV-70-87 (Note 1). Must Not Close/ Remain Operable: , .
.1-FCV-70-90 (Note 1)~ Must Not Close/Rerain Operable l 0-FCV-70-34 '(Note,3) (if CCS pump 1B.-B Must Not Close" ,
i is used) , r 1-FCV-70-25 (Note 3) ' Must Not 01ose 1-FCV-70-8 (Note 3) Must!Not Close - < 1-FCV-70-9 ) (Note 3h Either one Must No',Open 1-FCV-70-10) (Note 3)L ' Mtist' Not" Open 1-FCV-70-4 (Note 3) , Must# Not Close 1-FCV-67-478 (Note 3) . Must Not Close 1-FCV-67-492.(Note 3)- Must Not Close 4
*1-FCV-70-156 )~ Any one. Must Not Open #j;
.-(. 1-VLV-70-545A) Must Be3 Closed, Must Be Closed kg, lk 1-VLV-70-546A).
1-FCV-67-125) (Note 6) .Either one Must Not..Open
.Must Not_0 pen-FCV-67-126)'(Note 6) 0-FCV-67-14. (Note 3) Must Nor,tClose j 0-FCV-67-365 (Note 3) . Must Pot 01ose 1-FCV-70-13) -(Note 3) Either one Must - tht sp<>n -
1-FCV-70-23') f(hte 3) Must M t'Open 1-FCV-70-26) (Not!e 3)- Either one Must Wel Open 1-FCV-70-27) (Note 3) Must Not Open 1-FCV-70-64) (Note 3) Either one Must Not Open 1-FCV-70-74) (Note 3) Must not Open a
- Handwheel, operation acceptable ; , g4
> /. l
.. .i
,,? ,
.4 78 h 4 l
-E24216.01 NEB - Apr. 8, 1986
L I
.?.O . 'k 1
Computed 8 h Date 4-l8" N
. N.. :
hh 1 Checked O[4N/ Date S-I8-D { ($" .
.- j 1
~
. .. SEQUOYAH NUCLEAR PLANT j
' KEY 9'(Spurious List) ,
t i- Unit 2 I l ERCW Header 2A (Spurious List) (See Key 1) ! N 2-FCV-70-133 (Note 1) Must Not Close/ Remain Operable 3- 'y 2-FCV-70-134 (Note 1) Must Not Close/ Remain Operable .. 2-FCV-70-87 (Note 1) Must Not Close/ Remain Operable - 2-FCV-70-90 (Note 1) Must Not Close/ Remain Operable 0-FCV-70-39 (Note 3) (if CCS pump 2B-B is Must Not Close used) 2-FCV-70-16 (Note 3) Must Not Close -
;2-FCV-70-15 (Note 3) Must Not Close 2-FCV-70-4 (Note 3) Must Not Close 2-FCV-70-195) (Note 3) Either one , Must Not Open 2-FCV-70-196) (Note 3) . Must.Not Open 1-FCV-67-492 (Note 3) Must Not Close
*2-FCV-70-156 )""-Any one Must Not Open Rl- d4 2-VLV-7 0-545A) Must Be Closed 2-VLV-70-546A)_ , Must Be Closed
((L. 1-FCV-67-125) (Note 6) Either one Must Not Open 4
' l-FCV-67-126) (Note 6) Must Not Open 2-FCV-70-14) (Note 3) Either one Must Not Open 2-FCV-70-18) (Note 3) . Must Not Open 2-FCV-70-76) (Note 3) Either one Must Not Open 2-FCV-70-78) (Note 3) '
Must Not Open
,, 2-FCV-70-28) (Note 3) Either one Must Not Open h :' 2-FCV-70-29) (Note 3)
, Must Not Open O **0-FCV-70-193 (Note 2) Must Not Open
**0-FCV-70-194 (Note 2) Must Not Open 1-FCV-67-223 (Note 4) Must Not Close 2-FCV-67-223 (Note 4) Must Not Close 1-FCV-67-424 (Note 5) Must Not Open
- Handwheel operation acceptable
**If neither valve can be protected from spuriously opening and the requirements of Note 2 cannot be met, the following must be accomplished:
**FCV-70-40 T Any one Must Close
**FCV-70-11 ) Must Close 0-70-529Q Hust Be Closed R4 '
~
**FCV-70-41 ) Any one Must Close
**FCV-70-1 ) Must Close
** 0-70-529B) --
Must Be Closed OR
** 1-70-531] Must Be Closed E24216.01 NEB - Apr. 8, 1986
' y, . ,
Computed L L) Dat e t- s -kT
' Checked f4#- Date 7/7/lft .
SEQUOYAH NUCLEAR PLANT -
, KEY 9 (Spurious List) -_
NOTES-
' Note 1: These ' valves will close upon a spurious phase B containment isolation signal. - They will be required to be reopened.
Note 2: If both of these valves open, component cool'ing water pumps 2A-A and-2B-B bo th~ mus t be operable. Note 3 A design change is being made under ECN-L6258 to remove power from ' this valve. Note 4: A design change is being made under ECN-L6258 to' open this, valve and , remove power. }L, Note 5: A design change is being made. under ECN-L6258 to close ithis valve and r emove power. jr Note 6: .The ERCW headers ' spurious lists contain the containment spray .(CS) heat exchangers isolation valves (162-FCV-67-123,-124,-125, -126) . Per the " . { (m.L 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 1A can have flow through it provided heat' exchanger 2A is isolated. The same is true for Train B). f E24216.01 NEB - J an. 31, 1985
$ g
e
'AH~* t'1w n
s rS* er eC me dC r pw a e i o eog up H t n q-L a en W wh .i C oc l a R l x ar E FE nt o - iB t i g d n di ay
- l epd d pe eut
, s s u
hl
, et a T
riv aw - sd e peb mt uao pit r c e B oe t , s s f s l o , I ah ao-
- mB* . -
r B er-h eB Ti rp _ P rm C au y RBP .D R D _ O V N u A _ v e r . e V _ t s l o - ao mB er -A r h eA Ti rp P rm _ C au RBP i _ l r ae _ mt _ Ar s eo _ rh o _ eTB - u . aor _ et e _ H is wrp _ - S orm . _ Cl au CFBP _ O .
~
_ j! ; t
.o
'I, 1
,g :g Computed M Date ll/O/('/ -
(
~
t y .. Ch ecked fft- Date is/ls/d ,
);;
' (l (( , SEQUOYAH NUCLEAR PLANT KEY 11 (Operation List) '
J - u.
-y
*AFW pump A-A Eith er .One Must Operate
*AFW pump B-B ' -
Must Operate
- Pump used nust supply the SGs being used for cooldown.
r 9 f! I k p E24216.01 NEB - Nov. 27, 1984 a _m-____:u._ __a
l 1
))l :; l l1 i lIl 1 .
\u y
= 1 s
B B . p m u P - W 1 A 3 Y 1 f R I 1 O . Y E K A Yf
/ f'g A 4 d,
/
h7 p m /I u P e e e t t a a _ W D, D A _
- ) _
- h . k f/ 5 k? d t e d r e a p k c e e r h P C -
=
6 1 !t lI i t
Computed StA Date 3-(, -l'S' Checked ffp . Date .Kly/yf SEQUOYAH NUCLEAR PLANT
~K- KEY 12. (Operation and Spurious List)'
l . Pa th ' l = :-- . 1 - Automatic Level Control
'PS-3-164 .
Must Not Cause LCV to Close Loop L-3-164 (for LI-3-164 and LCV control) Mus t Operate
'LSV-3-164 Mus t Operate LCV-3-164 -
Must Operate PS-3-156 Mus t Not Cause LCV to Close Loop L-3-156 (for LI-3-156 and LCV control) Must Operate -, ' LSV-3-156 ' - Mus t operate .
. LCV-3-156 Must Operate Control Air Supply, Path 1 (See Key 13) '
Mus t Operate
~
OR
- Manual Level Control Loop L-3-43 (for LR-3-43P1) -(Any one) " Mus t Operate Loop L-3-164 (for LI-3-164) Mus t Operate Loop L-3-39 (for LI-3-39) , - Mus t Operate jft)
I(, **LCV-3-164' .
,, Must Not Close Loop L-3-56 (for LR-3-43P2) -(Any one) Mus t Operate f 4Y~
Loop L-3-156 (for LI-3-156) Must operate Loop L-3-52 (f or LI-3-52) , Mus t operate lO
**LCV-3-156 Mus t Not Close -
-* Manual control consists of on/of f operation of the AFW pump (Key 11) or manually throttling the following valves:
3-828) Either one (SG 1) .- 3-836) 3-827) Either one (SG 2) 3-835)
** Locci operation acceptable.
E24216.01 , NEB - Jan. 31, 1985
- e
Computed M Date 3-4,-Pf' Checke d f/4 Date 3/7/W [ ~
, SEQUOYAH NUCLEAR PLANT KEY 12 (Operation and Spurious ~ List)
~
l - Path 2 , Automatic Level Contrc,1 PS-3-148 Must Not Cause LCV .to Close Loop L-3-148 (for LI-3-148 and LCV control) Mus t Operate LSV-3-148 -Mus t Operate LCV-3-148 - Mus t Operate ._- PS-3-171 Mus t Not Cause LCV to Close * ,_ Loop L-3-171 (for LI-3-171 and LCV control) Mus t Operate LSV-3-171 Mus t Operate
.LCV-3-171 Mus t Operate Control Air Supply, Path 2 (See Key 13) Mus t Operate ,
OR
- Manual Level Control Loop. L-3-98 (f or LR-3-98P1) IAny one)
Loop L-3-148 (for LI-3-148) Mus t Operate Must Operate h ( Loop L-3-94 (f or LI-3-94) , Must 0perate [q
**LCV-3-148 .
Mus t Not Close
. Loop 'L-3-111 (f or LR-3-98P2) -(Any one) Mus t Operate Loop L-3-171 (for LI-3-171) Mus t Operate Loop L-3-107 (for LI-3-107) *. Mus t Operate jp -
**LCV-3-171 ~
Must Not Close
.. 1
- Manual control consists of on/of f operation of the AFW pump (Key 11) or manually throttling the following valves: i I
3-826) Either one (SG 3) 3-834) 3-829) Either one (SG 4) --
~I 3-837)
** Local operation acceptable. 1 E24216.01 NEB - J an.' 31, 1985' e I L -
l p p , - u S
. r
< i A
)
l3 . _ o1 r t y ne oK C( v D N a vA l o r t n o C ' c 8 i 4 t 1 I a - ' m3 o - ~ t V uC l AL e i R v O
, e . '
l L l l o-ar - ut n nn 4 o ao i MC '
& t i 2
a r 3l c h s ei t svd a
. G en P S LI
' R O
n 1 2 o i i h u
& t t a a 1 l c P ei .
svd G en l SLI e d v e L l o l v R l ar O o ut r nn v
- t ao n MC o
C c64 i56 . t1 1 a - - m33 o - - t VV uCC ALL _
. rl
- D N
r, A y l p p - u . S r i A
)
l3 - o1 r t y ne oK C(
, 6
; ll
' Computed b (,Q Date ///2 f/D ;
t / 1 Ch ecked ' fc4 Date pl.,/& SEQUOYAH NUCLEAR PLANT KEY 13 (Operation and Spurious) -
't
- Control Air ' Supply Path 1 --
Station air compressor A Must Opera te Control circuit for air compressor A Must Opera te 0-FSV-32-42 Must No t Clo se a 0-FCV-32-82 Must Not Close 0-PS-32-82 ---" Must Not Cause . t Valve to Close' -
**0-33-500) Either one Must Be Closed
**0-33-501) __.
Must Be Closed j
- OR -
- Station air compressor B '
Must Operate
~
~~
Control circuit for air compressor B Must Operate 0-FS V-32-37 Must Not Close j Must Not Close 0-FCV-32-82 0-PS-32-82 - Must Not Cause
- Valve to Close
**0-33-500) Either one Must Be Closed
**0-33-501) ,__,
Must Be closed ERCW Header 1A (Operation list) (see Key 1) l ERCW Header 1A (spurious list) (see Key 1) 0-FCV-67-205 }bst Not Close
*** 1 -FC V 127 --- Must Not Close .
T" OR , ERCW Header IB (operation list) (see Key 1) l ERCW Header 1B (spurious list) (see Key 1) FCV-67-208 Must Not Close
***1 -FC V- 67-128 "-"
Must Not Close OR Auxiliary air compressor A Must Operate _ Control circuit for auxiliary air compressor A Must Operate 0-FSV-32-62 Must Not Close 0-FSV-32-61 Must Not Close j
***1-FCV-67-127 Must Not Close ERCW Header 1A (operation list) (see Key 1) ,
ERCW Header 1A (spurious list) (see Key 1) . l L *This is a B-train compressor. If it is used, equipment associated with supply B-train power will have to be evaluated.
** Handwheel operation acceptable.
***A design change is being made under ECN-L6258 to remove power from this valve.
Special Note: 1. Station air compressors may be used whenever copper tubing with soldered joints is not damaged by fire. 2.. Control air is only required when necessary to support main S3 control room HVAC and _AFW automatic level control. E24216.01 NEB - Nov. 27, 1984 W
__7-l Computed- kd Date . Ill'2 T/h i
. .t t l g, D' Checked fftc Date n,/>d/ ,
l 1(
, SEQUOYAH NUCLEAR PLANT KEY 13 (Operation and Spurious) 7 ..;
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-PS-32-85' Must Not Cause , Valve .to Close
**0-33-500)- Either one Must Be Closed. _!
**0-33-501) -
Must Be Closed j OR Station air compressor B Must Operate ]
- Control circuit for air compressor B Must Operate .
0-FSV-32 Must Not Close 0-FC V-32-85 --- Must Not close 0-PS-32-85 Mast Not Cause Valve to Close
**0-33-500) Either one ' -
Must Be Closed !
**0-33-501) --
Must Be Closed ERCW Header 1A (operation list) (see Key 1) ERCW Header 1 A (spurious list) (see Key 1) C 0-FCV-67-20 5 Must Not Close C**1-FC V-67-127 -- tbst Not Close OR ERCW Header 1B (operation list) (see Key 1)* ERCW Header 1B (spurious list) (see Key 1) 0-FCV 208 , Must Not Close . C**1-FC V- 67-128 , Mast Not Close
~~
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 Q**2-FC V- 67-128 Must Not Close ERCW leader IB (operation list) (see Key 1) ERCW Header 2B (operation list) (see Key 1) ERCW Header 2B (spurious list) (see Key 1) __, )
*This is'a A-train compressor. If it is used, equipment associated with supply A-train power will have to be evaluated.
** Handwheel operation acceptable.
' C**A design change is being made under ECN-L6258 to remove power from this valve. q 1
Special Note: 1. Station air compressors may be used whenever copper tubing { with soldered joints is not damaged by fire.
- 2. Control air is only required when necessary to support main f3 li control room HVAC and JWW automatic level control.
[ E24 216.01 NEB - Nov. 27, 1984 . N
r i B A r y o q r s a s i e _ 5 l r . p i x m u o A C l r '
. ~
R O - y
.f l r
i A
. A r
- r y o
' r s a s i e l r i p x m u o
- A C l
7 - 3 1 g Wn g V R O w y Ci e Rl ' s r K E o ~ ' o ' j C
- n B y f
o r i ro vt aAs is / t S e r p f m t o C D A U n h _ Y o r i ro t is aA s t e k S r _ - p ' _ m _ d _ o C r P
,h * <
l 6 i lt i
o t +. , Computed %b) Date ///M)/y - ( f~ p> Checked . fle& Da te. hj!o/r/ ' {C .
, SEQUOYAH NUCLEAR- PLANT KEY 14 AND 15 (Operation and Spurious List) -
- u. :._, ,
I
' AFW Pump Turbine A-S Must Operate Turbine-Driven Aux Feedwate r Pump A-S Must Operate .
Control . Circuit for. AFW Pump Turbine . Must Operate J Loop F-3-142 (for control of governor valve ~ Must Operate , l and trip' and throttle valve) - FCV-1-51 Must Operate FCV-1-52 Must operate ap
*FCV-1-17 Muat Not Close e
*FCV-1 -18 .- Must Not Llose
'i ( *FCV-1-15 _.
Muat Not.Close k OR
*FCV-1-16 - Must Operate -
- Instrument Loop P-3-138A _, -
Must Operate .
~
- Handwheel-operation acceptable.
f 1 l 1 l l I 4 l I' t I s E 24216.01 NEB - Nov. 27, 1984 I i u-_-_-_---__----_-.- -- _. - - _ . . - _ _ _ __ - -
u y
. n e
v i r D e n i b p rm uu TP p , o o L l o r t n o2 , C4 1 w-o3 P l - T FF r
. T D
N V f i A e' n i b f i r T ul o T. pt r t mnt uoi PC u c , Wd r F ni A aC [Y
/{f'[8 (
[f[!
/
o 7 t y e e t t l e pn a a pi D D ub S r u ) mT a , eW t F f C hh - SA L _ d e d r e
+
a k _ p c _ e e . r h P C - 1 '
Computed hd Date Checked p_ Date 4/ j,/N
, SEQUOYAH NUCLEAR PLANT KEY 16 (Operation and Spurious List) .
u Path 1 j-Automatic Level Control j LCV-3-17 2 Must Operate ~ LSV-3-17 2 Must Deenergize 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 Mast Not Cause Valve to Close PS-3-140B Must Not Cause Valve to Close LCV-3-17 5 Must Operate "
LSV- 3-17 5 Must Deenergize to Modulate LCV
' Instrument Loop L-3-175 (for LCV control) Must Operate Instrument Loop P-3-138A (for- LCV control) Must Operate PS-3-165A '
Must Not Cause Valve to Close PS-3-165B - Must Not Cause Valve to Close Control Air Supply, Path 1 (see Key 13) Must Operate OR I Manual Level Control -
*LCV-3-172 ,
Mu s t Ope ra te Instrument Loop L-3-98 (for LR-3-98P1) .(Any one) Must Opera te Instrument Loop L-3-17 2 (for LI-3-172) Must Operate Instrument Loop L-3-94 (for LI-3-94) _, Must Operate
*LCV- 3-17 5 Must operate Instrument Loop L-3-111 (for LR-3-98P2I-(Any one) Must Operate .-
Instrument Loop L-3-175 (for LI-3-175) Must Operate Instrument Loop L-3-107 (for LI-3-107)., Must Operate
- Handwheel operation acceptable.
1 I' E24216.01 NEB - Nov. 27, 1984
-_m___-______ _ _ _ _ _ - - _ _ _ _ _ _
L [ . , l Computed hW Date l/24 Ch ecked fd Date ,arbe/W . lG I - h SEQUOYAH NUCLEAR PLANT f KEY 16 (Operation and Spurious List) ~ '
~.
Path 2 Aut'omatic Level Control LCV-3-17 3 Must Operate !
' LSV-3-17 3 Must Deenergize to Modulate. LCV j Instrument Loop L-3-173 (for LCV control) Must Operate --
. Instrument Loop P-3-138B - (for LCV control) Must Operate .-~
PS-3-150A Must Not Cause Valve to Close PS-3-150B - Must Not Cause Valve to Close Must Operate LCV-3-174-LSV-3-174 Must Deenergize to M?dulate LCV Instrument Loop le3-174 (for LCV control) Must Operate
~
. Instrument Loop P-3-138B (for LCV control) Must Operate PS-3-160A Must Not Cause Valve to Close PS-3-160B -
Most Not Cause Valve to Close Control Air Supply, Path 2 (see Key 13)
- Mu s t Ope ra te OR I
Manual Level Control
*LCV- 3-17 3 _ Must Operate Instrument Loop L-3-56 (for LR-3-43P2) -(Any one) Must Operate Instrument Loop L-3-17 3 (for LI-3-173) Must Operate Instrument Loop L-3-52 (for LI-3-52) , , Must operate
*LCV-3-174 Must Operate Instrument Loop L-3-43 (for LR-3-43PI) L(Any one) Must Operate Instrument Loop L-3-174 (for LI-3-174) Must Operate Instrument Loop L-3-39 (for LI-3-39) , Must Operate .-
- Handwheel operation acceptable.
l I l 1 E24216.01 NEB - Nov. 27, 1984 i
)
S r i A :
)
l3 o1 r , t y n e o K C ( v V l o r t n o C ' V R c34 O i77 f t 11 a - m3 3
- ' fk 'l S
o - - t V V uC C AL L l o r t n -
, 2 n vo34 2
i o C77 1 1 . vht
& t l - - a a a33 P 1 l c ei u - -
nVV ' svd aCC G en MLL S LI
- R O
l o r * . t n n o25 1 4 o vC771 1 _ i t l - -
" ht a a 33 a l 3l c u - - P o e i n VV r s v d a CC t
n G en MLL S LI * , o C
, )l c25 i77 R t1 1 a - -
m33 , (Ol o - - , t VV _ uCC ALL v D N _ 3 v A _ 1, _ p p u _ S _ r _ i ,, _ A _ ) ' _ l3 _ o1 _ r t y ne eK . _ C( - ~
. e ;
s I i i : : .
l11j l _ ~ 4 _ + h q c . i i
=
D~ pF - n
)]
y od 7 , ldi e 1 l et r V anci Y mgAu E ri q K ol oe NANR , f
// - f f/ /rs ,
,I M/< h)f t
e t e a a D D Oa - l _ B
/ -
d _ e d -_
=.
r e
. a p
k c e e .
- r h .-
P C I i _
Computed & Date ll/L9)Q Ch ecked /C# ' Date /// s/W 1 l , SEQUOYAH NUCLEAR PLANT KEY 19 (Operation and . Spurious List) ' s m.. O,. Path 1 ERCW hea' der 1A (operation list) (see Key 1) ERCW header 1A (spurious list) (see Key 1)
..ERCW heade c 2A (operation list) (see Key 1)
ERCW header 2A (spurious list) (see Key _1) ._
-l
' l-FCV-67-223 (No te 1) '
Must Not Close FCV-67-223 . (No te 1) Must Not Close 1-FCV-67-424 (No te 2) Mu st No t Op'en , M 1-FCV-67-478 (No te 3 ) Must not close If Motor Driven AFW Pump A-A Is Used: -
*FCV-3-116A Must open ,
*FCV-3-116B Must open i
( If Turbine Driven AFW Pump is Used:
*FCV-3-136A Must open
*FCV-3-136B 'Must open
- Handwheel operation acceptable. -
No te 1: A design change is being made under ECN-L6258 to open this valve and remove power. No te 2: A design change is being made under ECN-L6258 to close this valve and remove power. ..- No te 3: A design change is being made under ECN-L6258 to remove power from this valv e. Special Note: The ERCW headers spurious lists contain the containment spray (CS) heat exchangers isolation valves (1&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 1A can have flow through it provided heat exchanger 2A is isolated. The same is true for Train B). E24216.01 NEB - Nov. 27, 1984 h
Computed hh Date )))Lf)(y ( f i (; , Checked f/4 Date ja/lo/fy l
'( ,
SEQUOYAH NUCLEAR PLANT.
- KEY 19 -(Operation and Spurious List) '
1 er Path 2-
.ERCW header 1B (operation list) (see Key 1)
ERCW header 1B (spurious list) (see. Key 1) ERCW hiader 2B (operation list) (see Key 1) , ERCW header 2B (spurious list) (see Key 1) _,
**2-FCV-6 7-147 Must not close If Motor Driven AFW Pump B-B Is Used: '~
*FCV-3-126A Must Open ;
'*FCV-3-126B Must open i
If Turbine Driven AFW Pump is Used'
*FCV-3-179A -
Must Open !
*FCV-3-179B Must Open'
- Handwheel operation acceptable.
**' A design change is being made under ECN-L6258 to remove power from this valve. .
l f i
' E24 216.01 NEB - Nov. 27, 1984
-- . _ .m__--_______ _
- _. 77
- 1 1 3 - -
-- 3 3 VV 'n - A CC eVV FF pCC
_ OFF
. 4 DN -4 D N
4A l B L A a_ ' r wr n s i d ne id I r
- aa aa Me Me I H I H
. o o t y t y l l wp - wp op op l
. l uA l u FS1 FS n e
m i v 0 or t D
._. - - p
\
R O v ne onum iip tb m - crW uuF
. A B 6 6
= TA
. 2 2 l
. 11 i .
33 n n - - e eV V ovB T . C t i F rp i DN a nD m
. I o - u .
4 A _ 3 i rP t o r e ct W uoF d SMA ' a e ' H 1' e R g
- or = O t a h
wc os , li FDB
;a.
- i. AB 66 1 1 l
. 11 33 n- - n
.. eVV pCC e
- OFF o v A.
ti 2 rp _ D nD m -
.uNA o - u
_ r 1 irP d r e t o ct W uoF s e.
. [SMA
.- l
'ge
_ . l I r a t . +
. h .
c
." s
.e i --_ m. L DA
~
' Computed %0 Date )) f)f')
Checked JAG Date' s . I((. SEQUOYAH NUCLEAR PLANT -
~~'-
g KEY 20 (Must Operate) Most close
~
FCV-1-147 FCV-1-4 Must close FSV-1-4A) Either one Must Deenergize FSV-1-4B) . Must Deenergize FSV-1-4D Must Deenergize FSV-1-4E ) Either set Must Deenergize
= FSV-1-4Gf ~of two Must Deenergize FSV-1-4H1 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-1-11D Must Deenergize FSV-1-11E ), ,,Either set Must Deenergize FSV-1-11C7 of two Must Deenergize FSV-1-11H1- Must Deenergize -
FCV-1-14 9 -- 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 FSV-1-22GT 'of two Must Deenergize Must Deenergize FSV-1-22H{ FCV-1-150 Must close FCV-1-29 Must Close
, FSV-1-29A) . Either one Must Deenergize
. FSV-1-29B ) Must Deenergize FSV-1-29DI Must Deenergize ,
FSV-1-29E). ,Either se t Must Deenergize i of two Must Deenergize FSV-1-29G] Must Deenergize - FSV-1-29H g E24216.01 NEB - Nov. 27, 1984 b w b
' Computed Wld Date 3-6-45~
' ~
l - Checked _pr/ Date .r/72'f l-L ( ' SEQUOYAH NUCLEAR PLANT . KEY 20 (Spurious List). -- l 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 solenoid: FSV-1-29F AND FSV-1-29J - valves may spuriously energize (This would block the air vent paths ~
~
and prevent closure of the associated MSIV.) The following set of spurious operations snust 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-YJ) X= 4 for S.G. I 11 for S.G. 2 22 for S.C. 3 C ENERG1ZE 29 for S.G. 4
~
FSV-1-XA XB _X_D XE XF XG XH XJ o OR , OR
*h o &
AND - v (UnacceptableOpeningof MSIV FCV-1-X NOTE: In the event of a. fire in the MCR the operator must pull the fuses in the control circuits for FCV-1-147, -148, ' -149, -150 to prevent possible jd spurious opening of these valves. 4 f LE24216.01 NEB - Feb. 25, 1985
n1 r2 E - e -
- V n1 eS '
E - DF - V, eS r DF o 4
. r
- a. 4 o e
z~ ' e iA r z gl - iA ri r g9 e - g r s
' r2 e n1 s
e - 1 z a t E - e
~i0
- g1 eS V p z
iDE n1 E - V DF
- r1 g99 eS .
- e:
r22 DF
~nl E :
e - - n1 1
~~ ? E - - -
-D?e! VV
- _ eSS
. E
. , DFF _
d*
' r '
o
'e g
e
-i il z
I i G1 1
' rl l g99 e: 8 r22 n1 1 4 e - - 0 E: 1 l 1 . n 1 'l 9 5
?
ei Dl e1 s - e1 s - i-eSSVV- - e1 2 t e1 1 ' oV oV DFF s - s - 1 C l C oV oV 3F CF l C l C 3 l
.I l CF CF A _
-A =
wD e e N z z A i gB
, iB y
, g2 '
r4 r2 e- e - n1 n1 E- . E - V - V eS eS DF DF
+ r + ro l
o l e e z . r z - i _
, iA -
r rA _ g2 ' e4 l r D l r2 l r D e g - r N e e - l . s N z n1 < A z n1 v A i E - iD E E - r r - V V e"E gd eS DF v_ g2 r2 e - - 2 2 eS DF uI uI n1 1 E - E - - 6I E -
- V V eS DF S
F r - g o r No e _ e z j z iGi l g g2 2 iT~ g r 7 r22 l e 4 e - - 9 4 1 n1 1 2 4
.n. -
I E - - 2 I 1 '
- 1. J D'
e"
- e1 s -
oV e1 s - oV eSS DFF VV e1 s - e1 s - l C l C oV oV CF CF j l C l C CF cF
- - g I
Computed hl.2Ib Date Uh_9)([y I / Ch ecked ,<?p Date p/skV SEQUOYNI NUCLEAR PLANT KEY 21 (Operation List) ' FCV- 1-10 3 FCV-1-104 Must Close Must Close FCV-1-105 Must Close FCV-1 -106 FCV-1 -107 Must Close Must Close FCV- 1-108 Must Close FCV-1 -109 Must Close FCV-1 -110 Must Close FCV-1-111 , Must Close FCV-1-112 Must Close FCV-1-113 Must close FCV-1-114 Must Close 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 Must Close FCV-1-68 ) Must Close FCV-1-70 ) Either one Must Close FCV-1-71 ) Must Close FCV-1-36) Either one -
Must Close FCV-1 -37 ) Must Close FCV-1-43 ) Either one Must Close FCV-1-44) Must Close FCV-1-84 ) Must close FCV-1-91 ) Must Close FCV-1-98 ) Must Close FCV-1-75 ) Must Close No te : No spurious list is required for this key. E 24 216.01 NEB - Nov. 27, 1984
g ;r --)
^ Computed U 0 Date 1 ole)f(f
!Y ( '
./ / ..
Checked fc/- Date /7//s/Pf ._ : SEQUOYAH NUCLEAR PLANT : KEY 21' (Operation. List)'
- o FCV-1-77') Muat Close Ie m
FCV-1-79 )~ Must Close - I z) i FCV-1-284) Must Close FCV-1-291) Must Close FCV-1 -298) . Most Close . FCV-1-27 5) - Must Close < l rg,):. . :! ,
~ FCV-1-27 7) Muat Close
%e FCV-1-27 9 ) . Must Close !
lD Notes No spurious list is required for this key. !, j I l i j P E24216.01 NEB - Nov. 28, 1984 )
r --
= - ,
T c
, .x s. i ;j-) ( .
s.g q .- ' n
' ~
Computed kLlA Da te N/2h18'Y , ii n'c
- r. I a -W
. Checked. //4 Date g h d . .j ' . .
.n /.
7(h. SEQUOYAH. NUCLEAR PLANT ' KEY .22 (Must Operate)- ' ' - - u; FCV-3-35 ) Both Must close "i'
. FCV-3-35A)~' l :Must Close -s -
OR $
--FCV-3 d Must Close
^'
4, 1". , sJ
; e. . .o 1 lfI i !S:1 k.1 \ _ ;
FCV-3-48 ) Both Nust Close ,y, FCV- 3-48A l ,
.l. ' tis st Clo se ;
OR '
, FCV-3-47 Must Close' ;.
J' , i
~
FCV-3-90 ) B o th . , Must Close ,
./
FCV-3-90A)J ! } Must.Close- .q'/ j oR p ! FCV- 3-87 I
- Must Close :. '
?
- 1. ,, ,
- 4. . i l }
s
. (p , .
1
-t t FCV-3-103 ) B o th Mus'y; ' Clot.e I .~. . C FCV-3-10 3A_)l l ' Muse!Close OR-l .FCV-3-100 Mus: Close .
\ . i I f
- 4 J
h-1
/
E24216.01 NEB - Nov. 27, 1984 1
. i
,. <4 l
_ .y 4 \ ', '
~
w 3 A f,. ,m A 3 s . 0 w {$s J3a 1-_ . _ 1 ik f:
, O F V
C _- se3- - oV u, -
~_ lC CF u D ~ ;
- 1 t N r
+
4 A - i I N r i A v, R Lw : V O vRO 0 A
; . _9
-. 3
- 0 a3 _
1 s - _ oV e3 f lC CF . s -
- oV 0
{' ~ lC 0 1
~. ; CF 1 7 -
8 e3
- s -
_.~ -S e3 oV s - l C [ oV , CF lC - CF '
- c. -
.h .
r
#ri 1
~
~
- I /
~ s 2
l
=
l
, 3 7 3 4 e3 e3 s- -
s - oV oV a: lC l C A - CF A CF 5 8 3 4 s3 e3 s - s - k aV cV R l C s lC k O CF 9 CF j ;' R
, r O
U ~< y D N r N A 3 A
~ , I3 5 f -
8 4 e3 e3 c - s - oV oV lC l C CF CF
~
i, .
[' . , 'y.; : x, -c
.. y% ;f;'
'u .T. 1 a
' 6 ';[ sj _ ,
n,; : 19 u, y _p
.. , o
- Computed. d .Date'))/y.dA// i'b\
,.. . , v? .e f 7 j'Y &lhe' 4/ls/hf CheckedY ;.l 3 f yl SEQUOYAH NUCLEAR. PLANT
. KEY 23 '(Operation List) -'
.a FCV-1-36) Either one ' Must Close .;
- FCV-1-37 ) Muae Close
. FCV-1-58) Either one Must Close FCV-1-39 ) Must Close ' I- t J.
FCV-l-43) Either one ' Must Close FCV-1-44 ) Must Close - 4': FCV-1-45) Either one' Must Close FCV-1-46) j) , Must Close f ,
~
' No te : If both , paths A & B of Key 20 '(main steam isolation) are t.fiieved, Key 23 will automatically be' achieved. ). 4 I
No. spurious list is rer/pired for - this* key. . .f
, w 1 .
.i. J j '
/ .['t y
f v.- l
' l .,
I v! , ys 5 .$ h l *
.e p,
Iy)
/ 6 i
1 i r i 1
'l c l*,j ,e ,-
I , I l
, /
)
4 1
,,4
' .1 t.
i s
.A I
l
-E24216.01 NEB - 35v '
27, 1984
, r
.[' I 1
,[ , *
- e
h ~ e1 s - V C F r o 5 4 e1 1 s - oV l C CF 4 4 e1 e -
'o l C V
CF ' r go 3 4 e1 s - oV l C CF A V i V D
. N v V A
/
J
- 9 3
e1 s -
. oV l C CF u
'r o
J 8 3 . e1 s - 7 oV 3 l C
- CF e1 s -
'oV l C CF e,
r r o 6 3 P e1 s - oV l C - CF 1 s
t ;. Computed hlth - Date 7))Lflgf f / Ch ecked . //p Da te ss//s,hY . I( SEQUOYAH' NUCLEAR PLANT . KEY -24 ' (Operation List) FCV-1-7 ) Either one' Must close
-FCV-1-181) Mast close
- FCV-1-14 ) Either one Must close FCV-1-182) Must close ,
N FCV-1-25 ) Either one Must close FCV-1-18 3) ' Must close - FCV-1-32 ) Either one' Must close FCV-1 -184) Must close r
.,_ 0R-1-872 Must be closed 1-868) Either one Must be closed 1-8 69 ) Must be closed E24216.01 NEB - Nov. 27, 1984 I
w d
s (o/N
,aT
,n a
e8 s6 o8 ' _ l - ? C1 4 e 8 s 1 o '
- l -
e1 C s - oV l C CF l J r ' o 1 2 3 3 8 - 1 e1 , s - e1 s - oV l C oV l C CF
,hI 7
CF l
] V
[OV I a t
~
'4 5 '
2 D
- N [;
e1 A s - 0 oV 1 l C , CF 2 8 1 e1 s - oV l C - . CF } j 3o} r 3(lQ f 4 . 1 8 e1 1
- 4 V
/
1 s - /
- oV e1 l C
- s - CF oV l C CF
)
l rj o b d N e1 7
- 1 u
s - oV ~ l C CF
j i: . Computed hlN Date p/L<///(L) { / l[, Checked fts _ Date r/d . 1 l: SEQUOYAH NUCLEAR PLANT .
- KEY 25 -
- . n Operation List 1-VLV-001-512 - Must Operate
' 1-vLV-001-513 Must Operate 1-VLV-001-514 - SG3 Must Operate 1-VLV-001-515 ' Must operate 1-VLV-001-516_ Must Operate _
~
1-VLV-001-517 Must operate 1-VLV-001-518 Must operate 1-VLV-001-519 '- SG2 Must Operate 1-VLV-001-520 Must operate _ 1-VLV-001-521_ Must Operate 1-VLV-001-522' Must Operate 1-VLV-001-523 Must Operate 1-VLV-001-524 - SG1 Must Operate 1-VLV-001-525 Must Operate 1-VLV-001-526_ Mu st . Ope ra te
~
1 -VLV-001-527 Must Operate 1-VLV-001-528 Must operate
' l-VLV-001-529 - SG4 Must Operate 1-VLV-001-530 Must Operate -
1-VLV-001-531_ Must 0perate Spurious, List
**PCV-1-5 , Must Not Open
**PCV-1-12 Must No t Open R.3
**PCV-1-23 Must Not Open -j
** PC V- 1 -30 Must Not Open d
*All valves, from 2/4 SGs being used for cooldown, must be operable.
Operability assured by valve design. l
**If secondary side depressurization occurs, operator nust place the SG PORV handswitches in " closed" position. .
1
)
E24216.01 NEB - Nov. 27, 1984 4 I
78901 rt
. y
_ oi
,22233 fl 55555 i
, - - - - - db ea
. 1 1 1 1 1 _ 00000 > sr uep _ 00000 - _ V VVVV g O L LLLL n - V VVVV i
- - - - - e .
1 1 1 1 1 b e l s b . __ ~ G an rg
~
S
' ei 4 ps 4
G
/
2 oe S I e d G mb e S o rtl 4 f s a uv m s . y e ,b lva 23456 22222 55555 aoe md
- - - - - vd r 1 1 1 1 1 l u 00000 - , l os 00000 l os
- - - - - - A ca VVVVV LLLLL VVVVV 1 1 1 1 1 f
S r w 5 4D r
) 2 f /N i
2A Y
- . E K
f S 78901 . 1 1 1 22 55555 1 1 1 1 1 00000 00000 VVVVV LLLLL VVVVV 1 1 1 1 1 M 4 2 G S t 3 g D s
)
k
- l 23456 1 1 1 1 1 55555
- - - - - d 1 1 1 1 1 00000 r 00000 a VVVVV -
LLLLL r VVVVV P C* 1 1 1 1 1 1 " i ' l1i
Computed k W Date ll/L9 Art /
. J /
l Checked idhc- Dateir,A$vbk/ E l SEQUOYAH NUCLEAR PLANT . KEY 26 (Operation List) i-' The two valves which are chosen to operate mast correspond to the two loops ; being used for cooldown. The other two valves must not spuriously open. l
*PCV-1-5 ) Must ope ra te ;
*PCV-1-12) _ Two
*PC V-1-23 ) required .
*PC V- 1-30 )
f For manual operation of the' valves, any one of the three pressure indicators is required for each of the two loops being used for cooldown.
~
~ ~
Instrument loop P-1-2A (for PI-1-2A) Hust operate Instrument loop P-1-2B (for PI-1-2B) -Any one Must ope ra te Instrument loop P-1-5' (for PI-1-5) _ , Mast ope ra te
~
Instrument loop P-1-9A (for PI-1-9A)
- Hast operate Instrument loop P-1-9B (for PI-1-9B) -Any one Must operate Instrument loop P-1-12 (for PI-1-12) _
Fb st ope ra te Instrument loop P-1-20A (for PI-1-20AU Must ope ra te Instrument loop P-1-20B (for PI-1-20B) "Any one Must ope ra te Instrument loop P-1-23 (for PI-1-23) ,, Must opera te Instrument loop P-1-27A (for PI-1-27Af"
- Must opera te Instrument loop P-1-27B (for PI-1-27B) -Any one Must ope ra te Instrument loop P-1-30 (for PI-1-30) _ . Mast opera te
- Handwheel operation acceptable. -
i s l i
ee
' n ee l 1 rm 3 rm
# uu # uu sr sr n
. st . st w es sd o G. r n G. rnes
'. ed SPI SPI sl C. uoo S gC n
I I 4i r
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. y y t t i 3 i 5l ' 2l
- i - i l 1 b 1 b
- a - a V r V r p
C e C e p P p e _ *P O
- O l nl eob
. eia r b t t uap d re
_ nec . a pc l l OA
- - I i 6
r j % Co y gfed Y bfl$f$f Chech.t$ A SflSf% Computed hh)_ Date f/lyAH5' f~~I
/
Checked.f46 Date f/4/ff T SEQUOYAH NUCLEAR PLANT KEY 28 (Operation and Spurious Lists) Two temperature indicators are required for each of the two loops being'used for cooldown. Instrument Loop T-68-1: (for TR-68-1P001) Must operate Inetrument Loop T-68-18 (for TR-68-1P002) Must operate ~. Instrument Loop T-68-41 (for TR-68-24P002) Must operate Instrument Loop T-68-24 (for TR-68-24P001) Must operate
. - Two loops Instrument Loop T-68-43 (for TR-68-43P001) required Must operate Instrument Loop T-68-60 (for TR-68-43P002) Must operate ~
Instrument Loop T-68-65 (for TR-68-65P001) Must operate Instrument Loop T-68-83 (for TR-68-65P002),. Must operate Instrument' Loop- P-68-69 (for PR-68-69 ) --- Any one Mus t operate g, Instrument Loop P-68-66 (for PI-68-66A) Must operate
' { g- Instrument Loop P-68-342C (for PI-68-342A)_ Must operate [(
k
**PZR Backup Heater A-A )
- Either one Must operate
**PZR Backup Heater B-B )' Must operate
*PCV-68-340A) Either one Must close
*FCV-68-332 ) Must close
*PCV-68-334 ) Either one Must close
*FCV-68-333 ) Must close
***PCV-68-340B Must Noi0 pen ({(p )
***PCV-68-340D Must NoT0 pen
*0perator must close these valves if there is an excessive pressure decrease in the RCS. The PORV and block valve handswitches must be placed in the closed g position to prevent spurious opening due to the automatic pressure control circuits.
SySW RCr
**If the pressurizer heaters are not available, the RRR gmust be available within 19 hours. Sequoyah Nuclear Plant Special Startup Test No. 3, " Natural
. Circulation with Loss of Pressurizer Heaters," determined that natural y circulation conditions and saturation margin could be developed and maintained I
under the degraded condition of loss of all pressurizer heaters. Furthermore, the , depressurization rate over the testing period was approximately 100 lb/in 2/hr, and a 10% increase in pressurizer level would result in a greater than 100 lb/in2pressure increase. Therefore, pressurizer heaters "are not required for safe shutdown, and cold l shutdown can be achieved in approximate'ly 19 hours. ' 1
***If PCV-68-340B spuriously opens, trip RCP No. 2. If PCV-68-340D spuriously opens, trip RCP No. 1. ,
l l E24216.01 NEB - May 13, 1985 l
n
- eo ri -
ut sa , st en ere dP m i u Wer gt S ns C an RRI t r e B z - i B r upr I . sue skt
- eca rae PBH r
t 3 i 8 O
.\lr-o h f
D N r s 2 y e
'_[{
3 e f h A K r , e A z - i r A _ u pr sue skt eca rae PBH y 2
/f'f /(f r n uo t i at ra
//f [/s
_ et e e pn eme t t d em a a iT u D D W r S gs et J C nn R aI R J L - k _ d e d C r e a k _ . p c _ e e _ r h P C l I- 6
^
r s Computed \ L U . Da te M323~ t i s. Checked g/ Date r/M6 - < SEQUOYAH NUCLEAR PLANT A KEY 29 (Operation List)
~,
- Reactor Trip Breaker A -Must Trip HS-RT-1 or HS-RT-2 ~~l Z OR
- Reactor Trip Breaker'B __j Must trip HS-RT-1 or HS-RT-2 _,
~ _
NI-31B) aEither one Must Operate
- NI-32B),. Must Operate The reactor can be manually shut down from the main control room, or if the fire damages the reactor trip breakers, the' reactor can be manually shut down by. ~
deenergizing the rod 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 seactor 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 deenergizing the undervoltage trip coil in the reactor trip switchgear through a handswitch 1' 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 N' incredible that all four paths will fail in the specific manner to disable each respective path, particularly in light of the fact tha t the trip handswitches in .
the main control room each utilize all four paths simultaneously when placed in the TRIP position. In addition, the reactor may be tripped locally at the
- reactor trip swit ;3 star and the motor ge,nerator set supply breaker. Procedure FR-S.1, "ATWS", ., eies opeitor actions that may be required in 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 fail-safe design of the reactor protection system and diversity of input _ signals which can detect a 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. The insertion of the rods provides additional reactivity control for hot standby
- and cold shutdown as discussed in calculation S53841221923. S, If these reactor trip breakers or handswitches are damaged due to a fire, the reactor may be tripped using the motor-generator breakers.
h E24216.01 NEB - May 13, 1985 _ _ . _ _ _ _ . _ _m._.__ . . _ - - - _ --._ .- - - -
ji j 1i I m R -
= -
e O]r g nn ao Ri . t
-v' ea cc ri ud on SI r .;
o .' tB a rr ee nk ea J Ge
- r rB o '
t t oe f MS % 9 D # 2
. N '
r A Y
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r o ptA a rr ee nk A- ea Ge I
- r -
rB o ' t t . oe - MS
=
r i R I f i O i p f p /gp ' - r r [ TBo rr12 I Q /g ' J oe - - tkTT caRR e e ae- - t t erSS a a RBHH D D
. b h 6 i
p b f d e d r r r e tao a k F rr1 2 oe- - . r p e h c e tkTT P C caRR ae - - erSS RBHH ll l s l1lllL
7
; u'. .
E
' N Computed h(4/d Date Ukf)([/
/ /
,. Ch ecked A/+ Da te wb,bV' SEQUOYAH NUCLEAR PLANT KEY 30 (Operation and Spurious List).
*FCV-74-1 'Must open
*FCV ~,-i Must open Pati. ! --
I
. *FCV-63-72 : Must not open. !
*FCV-63-93 Must not close
**FCV-74-16 Must noe close
*FCV-74-3 _ Must not close- ..
*FCV-63-172) - Either one Must not open
*FCV-74L33 ) ,
Must clo se - Pl F Path 2
*FCV-74-21 Must not close
, **FCV 28 Must not close
*FCV-63-94 Must not close
*FCV-63-73 .
Mu s t not open ,
*FCV-63-17 2 ) - Either one Must not open )
*FCV- 74-35 ),, ,
Must close M
- Handwheel operation acceptable.
** Local operation acceptable.
p i E24216.01 - NEB - flov. 28,1984
\
m b
O _ 3 6 V C . . F e l f b i 5 ) a 3 B t y
-
- p l 4
- n e n 7 ei c o
- s a c V or a d C lT e FC( n r
- o i i u q
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- V s 9
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- s a V or Cl T O *FC(
f i 0 D 3 N r y r A 1 s e K r 1 y
/
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)
l 1 bPg4
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- 'n
'P r
a p e r d k h C e c e g ,l
4
- l r ,
Computed bQ Date n/LT)ff-Ch ecked ify, _ Date nlg/y/ C SEQUOYAH NUCLEAR PLANT
- KEY 31 (Operation List). .
,a Path 1 RHR pump A-A Must operate
*FCV-70-15 6 Must open
**0-FCV-70-19 7) Either one Must close -
**0-FCV-7 0-19 8 ) - ,
Must close - J
~
Path 2
~
RHR pump B-B Must operate
*FCV-70-15 3 Must open Component cooling and ERCW supplies are
- assured for RHR cooling requirements.
The same CCS and ERCW components used to achieve and maintain hot standby may be used for RHR system cooling while taking the plant to cold shutdown.
- Handwheel . operation acceptable.
**These valves. apply to unit 1 only. If the closure of one of these valves cannot be assured, the following must be accomplished: -
*FCV-70-40 $~Anyone Must close
*FCV-70-11 ) , Must close
- 0-70-529Al, Must be closed
_ f
*FCV-70-41 ) -Any one Must close '
*FCV-70-1 ) -
Must close. .
- 0-70-529B) ._ Must be closed OR
*. 1-70-531). I Must be closed
]
L E24216.01 NEB - Nov. 27, 1984 I
4
.j.
~. !,
I Computed hQ Date H)Mld I ( Checked g/p__ Datetsb>ks! (( SEQUOYAH NUCLEAR PLANT KEY 31 - I Unit 1 Component Cooling Water System Nonessential Loads Unit 1 Path 1
*1-ISOL-70-637) Either one Must be closed
*1-190L- 70-661) Must be closed
*1-IS3L-70-587) Either one Must be closed -
~
*1-ISa b- 70-574) Must be closed -
*0-ISOL-70-636) Either one Must be closed
- 0-ISO L- 70-601) Must be closed
~
Unit 2 Component Cooling Water System Nonessential Loads Unit 2 Path 1
*2-ISab-70-637) Either one
- Must be closed
*2-ISO L-70-661 ) -
Must be closed
*2-ISOL-70-587) Either one Must be closed -
- 2-ISO L-70-57 4 ) Must be closed
**0-FCV-70-19 3) . Eith e r one . Must not open
**0-FC V- 70-19 4 ) Must not open
- Handwheel operation acceptable.
**If neither valve can be protected from spuriously opening, the following must be accomplished: ,-
b Must close
*FCV-7 0-40 ) -Any one
*FCV- 70-11 ) Must close
- 0-70-529A ) ,.
Must be closed
~
*FC V- 70-41 ) ~Any one Must close
*FCV- 7 0-1 ) Must close
- 0-70-529B)_ Must be closed-OR
- 1-70-531 ) ,_j i Must be closed i
E24 216.01 NEB - Nov. 27, 1984 O
m - . 4 , B B I p m u P R H - . R r ,, i ' 1 R O 1 I 1 f 3 i A D Y
- N E A , r A K p I 3 m
u P R H R 9/ S . V nC o C . M"/I 6 - ND/p/n Nl a ei - t t ans d o I / l ed et osa d e e sso t vp i s t a t a I eL f i nom eru D D D iPP f N c n i A i tR o _ f nHi f art _ O ul c : S orn oou A CfF
'g s
( # nX iT f . lH _ o d _ oS r e d _ e CC o r ._ C fd a p k _ W n c . e e C r ga _ R o n r h- _ Ef i s 1 P C ._ l p _ omX ouT ' CPH . SRR CHH CRR I s
l l
~
i .. Computed bld Date IllL4 /Q I i L Checked gu Date mbh/ l :
.. r SEQUOYAH; NUCLEAR PLANT m ,
KEY 34 (Operation and Spurious List)
*FCV- 62-90 ' Must' Not Close/ Remain Operable
*FCV- 62-91 Must Not Close/ Remain Operable FCV- 62-84 Must Not Open FCV-62-85 Must Not Close
~
FCV-62-86. Must Not Close , FCV-62-89 Must Not Close (Fail open) '
*0ne of these valves is . required to throttle ' the flow to the RCS. The other valve will have to remain open.
**See Note 1 on Key 34 logic diagram. .
Special Note: In the event the RCS makeup safety function is satisfied by the ECCS charging path (Key 6) or the RCP seal injection, this path R," is not necessary and does need to be qualified (i.e. , no cable separation required). , i
.'\
1 l 1
).
I E 24216.01 NEB - Nov. 27, 1984 i e i 1 e I
n2
- nee s di r n u n
e6 ao o p - 1 ad i _ OV eer r C F e t ns se eoeh gp
. u
; o pl h t ns N oct ii yy ,egy ra r ll rd am l l enh r aavac mme e ,
o v f rrwsl l s_ oooea a nnl vml rl v nn ww ,vnao r e 5 oom h 8 hh a . rt n2
- ssrcoi gef e e6 ssap n p - .
iiisd OV . d e , C , 56 , se
-F 88 wh ur
- - oc o .
22l eef 66f tb ee r s VV enneo CCh oahl FFt ncT c d 1 e s . e o4 t l 8 o C - N 2 n6 i - aV mC v eF R v 4 d 3 v* a V Y E K n e Y' _ p9 O8 n2 . i6 a - mV eC RF
/(( W
[r f
//j e e t t 1
a a s e9 D D t - a2 r6 e p V-
. OC
- F e,
r W r, kA/ I f 0 d 9 e e- 'd t 2 r e a6 a k
- p c r - e e eV r h pC OF P C p
L p u, Computed ((,aM Date n)MAM/
.( /
./ Ch ecked' t/s., Date als/4' _
SEQUOYAH NUCLEAR' PLANT . . KEY 36 ' (Operation List) A-u 87-550) Either one Must Open (depressurize tank) 1 87-552) Must open (depressurize tank) OR
~
~
FCV-87-21 ) Either one Must Close * - J. , FCV-87 ) Must Close .,; FCV-87-23 ) Either one .Must Close FCV-87 ) Must Close local' closure of valves acceptable. I l -L l'
.i l
6 I l l
. i E24216.01 NEB - Nov. 27, 1984 ]
1 A a
l
. E 4
2 l ,
. - i ,
7 , e8 s - oV < lC CF 4 R O 1 4 3 ', 2 *
- I 7
e8 s - oV lC , CF 2 _ 2 .
- I 7
e8 s - oV l C CF W 4 R O T r R ! 6 3 4 3 O % Y E f K 1 % 2
- I 7
e8 s - oV lC CF f k V 6<//p i _.
/ -
/
l l _ ( bfo/ - ' 2 5 e e n5 t t e - ' a a p7 D D O8 d k u P, 0 . . 5 n5 d e - e d p7 r e O8 a p k c e e r h P C i k _ = l1 , l l :
. Computed h DatelibkV_- l lcN i Checked h[k/k Date 12f7fD I
() '
'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 following page must operate.
AHN A-A Must run
'~
h
'FC0 31A-20 .
Muse open ~
..FSV 31A-20 Must deenergize-
' *FC0 31A-176 (Note 1)
- Loop 31A-176 Must modulate Mus t ' func tion lN >
TCV 31A-47 & loop Mus t ' function ~ TCV.31A-48 & loop Must function j TCV 31A-49 & loop Must function TCV 31A-50 & loop , Must function ;
.FSV 31A-22A . Must energize FSV 31A-22B Must energize
- Loop 31A-22 Must function HS 31A-20A Must function l /t.)
HS 31A-20B Must function {(N ' g
- Loop 31A-52 Must - function Loop 31A-136 Must func tion -
Loop.31A-172 . Must funetion Loop 31A-134 Must function 'l Loop 31A-133 Must function
' i Loop 31A-132 - Must funetion Loop 31A-131 l
, Must function ,
Loop 31A-130 Must function ! Loop 31A-129 Must function ~ ,_ J Loop 31A-128 Must function -i Loop 31A-127 Must function j Loop 31A-126 Must function { {
'* Control ' air required for this function. J Note 1: Manual control of this modulating valve can be taken to control main control room temperature.
E24216.01 NEB - Dec. 6, 1984 [ l
. )
i 1 I C Computed bY Date /8!7fS[
^
~
Q' ' ' - Checked h Nn q
& Date U f7/ W '
)
. i
;. SEQUOYAH NUCLEAR' PLANT % ..
KEY 37A j HVAC Appendix R Review Main Control Room Air conditioning Operation List I This set must operate or the set on the preceding page must operate.
] 4 AHU B-B Must run
~
~~
FC0 31A-23 - Must open FSV 31A-23 Must deenergize :
*FC0 31A-177 (Note 1) Must modulate l g/,
- Loop 31A-177 - Must function i TCV 31A-65 6-loop Must function ~
TCV 31A-66 & loop Must function TCV 31A-67 & loop Must function TCV 31A-68 & loop , Must function i FSV 31A-39A . Must energize FSV 31A-39B Must energize
- Loop 31A-39 Must function l O, ,
- HS 31A-23A Must function HS 31A-23B Must function l g; i
- Loop 31A-70 Must function Loop 31A-151 Must func tion -
Loop 31A-173 - Must function Loop 31A-149 Must function Loop 31A-148 ~ Must func tion Loop 31A-147 Must function Loop 31A-146 , Must func tion Loop 31A-145 Must function Loop 31A-144 , Must func tion _i Loop 31A-143 Must function Loop 31A-142 Must func tion I Loop 31A-141 Must function
- Control air required for this function.
Note 1: Manual control of this modulating valve can be taken to control y< main control room temperature. i E24216.01 NEB - Dec. 6, 1984 [
's _ _ _____
y. h Computed ~ hld ~ Date ))/2.#)([ i l i Checked f//- Date Itk/h/, 1 l i C -
, SEQUOYAH NUCLEAR Pl. ANT KEY 37A ,
. HVAC Appendix R Review ~&
Main Control Room Air Conditioning Path 1
- ERCW Header 1A (Operation List) (See Key 1)
ERCW Header 1A (Spurious List) (See Key 1).
~~
1
*1-10V-67-127 - . Must Not Close . . ,
Must Not Close 0-TCV-67-19 7 Path 2 . ERCW Header 1B (Operation List) (See Key 1)
- ERCW Header 1B (Spurious List) (See Key 1) l(
- 1-FC V- 67-128 0-TCV-67-201 Must Not Close Must Not Close l
*A design change is being made under ECN-L6258 to remove power from this valve.
I
# 4 1
L E24216.01 NEB - Nov. 27, 1984
/'
o , ; 4 .g T
-i.
Computed h L 1ti Date 3-(,-F l
. Checked 24 Dat'e' 7b/91~ '( . .
SEQUOYAH NUCLEAR PLANT . l
^
KEY 37B' '- l HVAC Appendix R Review Aux Inst Rooms Air Conditioning (Using Elec Board Room AHUs) l Operation List
.CoolintL is not required for this area. ~
See EN DES Calculation NEB 850115 235.. , EY' C. I
- 1. L.
t
'4 -
i E24216.01 NEB - Feb. 25, 1985 f i e-1
y t ;-y ( 1 Computed AM 'Date I L4fk'{ N
^
.w Checked Datelif7/f/jf SEQUOYAH NUCLEAR PLANT :. ^'
- - ,/ HVAC Appendix R Review KEY 37C -
Diesel'Cenerator Building Ventilation-1 Operation and Spurious List l
-Diesel Generator Room 1A-A' Of/fr FCo-30-443 ,
Must Open'
~
- Elec. Panel / Gen. Fan Must Operate Exhaust Fan 1 Must Operate >
HS-30-447B Must Operatec -
.HS-30-447C Must Operate-FCO-30-447 - Must Operate j OR Exhaust Fan 2 Must Operate j HS-30-4510 Must operate HS-30-451B Must Operate FCO-30-451 .,_ Must Operate
. Electrical Board Room Unit 1 A-1 Elec. Bd. Rm. Ex. Fan Must Operate ~!
FCO-30-459 Must Open HS-30-459C Must Operate HS-30-459B Must Operate 3 i 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. ,
~
t For both the electrical board room and diesel generator room, a spurious CC 2
. initiation signal should not occur. This would shut down the fans.
FCOs are motor operated. E24216.01 NEB - Nov. 29, 1984
~
l
3 7_ _ - -_ r .. ,
- c. y g i ;
y
). *}
Computed , MM Datef'f19ffY p- h Checked- Of DatelifE9h l . Q .i: '
, a
.o SEQUOYAH.!GCLEAR Pi. ANT' ~
HVAC Appendix R meview ' . KEY 37CI / I I Diesel Generator Building Ventilation "; Operation and Spurious List y Diesel Cenerator Room 2A-A
.- : o FCO-30-444 ,
i Must Open- , G-Elec. Panel /Cen. Fan Must Operate
~
f Exhaust Fan'1
~
y . ' Must Operate g
.HS-30-448B y Must operate -
HS-30-448C , Must operate FCO-30-448' _ g /' Must Operate Exhaust Fan 2 / Must Operate ' i 4 ' ' HS-30-452B Must Operate
.HS-30-452C Must operate :
FCO-30-452 _ Must operate l
\(t Electrical Board Room Unit 2A-A i I, Elec. Bd. Rm. Ex. Fan Must Operate FCo-30-460.
Must Open l j HS-30-460B Must Operate J HS-30-460C - Must Operate- 1 i The ' fo11owing instruments should not spuriously operate - TS-30-448B) -A spurious low temperature signal would shut down the diesel TS-30-452B) room fans. ! For both the ciectrical board room and diesel generator.. room, a spurious CO2 .i initiation signal should not occur. This would shut dot}1 the fans. j FCOs are motor operated.' q ,
'. h l l e'
' 'r j E24216.01 NEB - Nov. 29, 1984 ,
- 1 i '
J
p. (3g 3 7 i:
, 3. 7 o c
a 5
"q' 7 d//.,1
[l) k
.,. -t-
~
t . u . Computcd /R Date IJf29ffri l
.y j Checked w / Date ll/29fs'l
'h
, $ SEQUOYAH FUCLE.AR PLANT ~'
,, J- HVAC Appendix H Review
' KEY 37C Diesel Generator Building Ventilation 4
;j o l-
~ ~ v i
_ Operation and Spuriots List .i 1.if;ljTg' uy .u '
+ ,
l'. ., :f r
' Diesel Generator Room IB-B
~ ..
~
n:.# FCO-3,04Q , Nast Open -
.J, Elec; Ps.nel/ Gen. Fan .
Must Operate -
- (e .%
_ f _ _. _ i? Y , Exhiuss1Fa'n jl~ Must Operate - HE-30-449 B,< 0 Must Operate- - HS 30-449q- , . Must Operate FCO-30-4/f 0, . OR ,9 Must operate
,1 :. , -
' f
Y [ '
' Exhause Fan 2 '
Must Operate [' .HS 'IJ-453B - Must operate F HS-30-453C Must operate
/ FCO-30-453 .
Must Operate g - Electrical Board Room Unit' 1B-B
+
Elec. Bd. Rm. Ex. Fan Must Operate
-FCO-30-461 Must open .f 1 HS-30-461B Must Operate '
HS-30-462C
- Must Operate a
' c 1
The following instruments should not spuriously operate *'
)
TS-30-453B) A spurious low temperature would shut down the diesel room i TS-30-449B) fans. d i For. both' the electrical board room and d'iesel generator room, a. spurious CO2 initiation ( signal should not occur. This would shut down the fans .q l s
, . FCOs are motor operated.
]
i
.r ! .,
E24216.01 NEB - Nov. 29, 1984
, . p. ,
}: 3;
- g. r . ) , ' iI
~1[
i , .
. . Jil 1
' /r j I l 1 g
[ e , d
7,. ('
- t. .
'e .
3^
+
y f Computed p' _ ) Date f if 2([$ f['. Y ,
' Checked M Date h 9 N
, , , '.1 , zJ
,[j p).
SEQUOYAH EUCLEAR PLANT O~g.
.(
HVAC Appendix R Review x
> KEY 37C Diesel Generator Building Ventilation-
,f :
Operation and Spurious List- ' ' t .,/ Diesel Gen'drator Room 2B-B "y ( j- , g ; ,, . _. FCo-30-646 ' Must Open' ~~ . Elec. Panel /Cen. Fan Must Operate
^
. Exhaust Fan 1
- 1ust Operate >
; ,HS-30-450B < Must Operate -
HS-30-450C Must'Onerate FCO-30-450 - OR Mupt @ erate s6 , .
,( , .
o Exhafyt Fan 2 , Must Operate-HS-30-454B -A ' Must operate LHS-30-454C Must Operate FCO-30-454 _ M.ast Operate
~
d 1 Electtical Board Room Unit 2B-B
~ x r
5
?Elec. Bd. Rm. Ex. Fan , ,
Must Operate FCO-30-462 j Must open HS-30-462B Must Operato ; 13S-30-462C
- Must Operate The following instruments should not spuriously cherate '
>i -
*!GS 30-450B) A spurious' low temperature sdgnal would shut down the diesel id930-454B) " ro> om fans. # '
.i y For both t.he ' electrical board room and diesel generator room, a spurious CO 2 init.lation signal should not . occur. This would shet down the fans.
l j FCOs are motor operated. > ' -
References:
47W866-9 (R8) # y 47W611-30-7 (R7) ' i
,u E24216.01 NEB - Nov. 29, 1984 S
f
./ '
I d
Computed 6)fA. - Date _/Of/(.(((y
. ,e Checked Date/0f/6!hl SEQUOYAH NUCLEAR PLANT. .
HVAC Appendix R Review --:- i i,- KEY 37D~ Steam Valve Vault Ventilation System
-.' Operation of the main steam valve vault ventilation system is not required during the-Appendix R scenario, .This was a joint decision between Dwain Kitchell, John Platfoot, Bobby Williams, and Emerson.Rudacille made on 1 August 10, 1984. ,
s l l 1 l' ((C l
~
l l l l 1 I
. i 1
l l 4 i .i l E24216.01 NEB - Oct. 10, 1984 W t L s l l
~
> .l
V .
'; K Coinputed hkW Date s V i;.
Checked- fr%. Date 3/7/Vf"' SEQUOYAH NUCLEAR PLANT- .,
-.4 KEY 37E
.s .
- Shutdown Board Room Air Conditioning Elevation 734 Equipment Needed for Plant Shutdown Following a Fire-Cooling is not required for this area. See EN DES. Calculation NEB 850115.'235.. lR S
--~
-(
. [-
-i L l :. ( l u 1. I l l l l l E24216.01 NEB - Feb. 25, 1985 6
r 4
.(.
Computed h l J Date s- 6.- fr'f~
' ~
Checked Au Date 3 /7/95' SEQUOYAH NUCLEAR PLANT 4 KEY 37F ~
' 480V' Board Rooms and Battery Rooms Air Conditioning-El 749 '
Cooling is not . required for 480V Board Rooms IA, 2A, IB, 2B,.and is-not required' for' Battery Rooms I, II, III 'and IV. See EN DES Calculation NEB 850115 235. N.
- I- 3
(
.}k '
i l 9 i e
- E24216.01 NEB - Feb. 25, 1985 O
I:; . [ 1
. Computed- $- .
Checked RRdpateYaterolst SEQUOYAH NUCLEAR PLANT '" t-4- KEY 37G 10CFR Appendix R HVAC Review i Cable Spreading Room s
; A requirement' for the use of ventilation for plant shutdown is not foreseen for the cable spreading room _ as reve1wed according to - Appendix R guidelines.- '
However, the following points are worth mentioning: - The spreading room supply and exhaust fans are not safety-related .and are
. 1.
!not required for shutdown, even during LOCA or HELB conditions. :They are..
powered from 480V reactor vent boards 1 A-A and 1B-B (drawing 45W760-31-7). Thse boards are load shed in the event of an accident. (The board can,. however, be loaded on the diesels later it desired.) ~
- 2. .The, cooling load in the spreading room is approximately 127,000 Btu /hr, a large portior) being lights. -
3.' There is not vital heat-sensitive equipment or instrumentation located in the spreading room. It is expected that it could get fairly warm in the L spreading room with no adverse affects.
- 4. If plant personnel decide to ventilate the spreading room af ter a fire, it could be accomplished several different ways. If the supply tan and one exhaust fan are available these could be used, provided in-line dampers are
- opened either remotely or manually. -Secondly, if the _ single supply tan isn't available, it's possible to ventilate the room with one exhaust fan (if usable) and by opening the door into the stairvell at' the opposite end of'the room. Of course, portable fans could also be used.
. 5. To minimize heat buildup in the room during nonventilation period.s, the lights, which produce a significant amount of heat, could be shut off. .;-
The fans are not required for shutdown, although there are several methods available to ventilate the spreading room, if desired. I 1 1 E24216.01 NEB - Sep. 2, 1984
*l.
Computed N C. ate T /4 >_- 6' ' Checked O Date /4,/$ SEQUOYAH NUCLEAR PLANT "- 4-KEY 37H PRESSURIZER HEATER TRANSFORMER ROOH (EL 759) 10CFR50 APPENDIX R REVIEW It is assumed that all air conditioning is lost to the pressurizer heater
. transformer room. This condition results in a steady state space temperature of 140oF, . assuming the transformer operates 50% of- the time (see sheets 2 and 3.
.for calculation details).
Per conversation with J. Plattoot, the transformer should have no probeim operating in a temperature of 1400F. Also he pointed out,-unofficially, that the SQN CRDM A/C equipment has not oeprated for a year and the pressurizer. ~, heater transformer room has not been above 1000F. Therefore, the CRDM A/C equipment serving the pressurizer heater transformer room is not needed for shutdown following a fire. l l
~
l l I i ( , E24216.01 NEB - Sep. 2, 1984 1
Computed _RE ateJ0[/6hV i Checked (A}d C Date_lef/(krf SEQUOYAH NUCLEAR PLANT KEY 37H -e e PRESSURIZER HEATER TRANSFORMER ROOM STEADY-STATE TEMPERATURE ON LOSS OF COOLING REF AB-31C-103 (U)( A)( A T) Roo,m Wall U Factors Area PHX North .35 608 PHX R. B. Partition .229 988
~
PHX East Partition .259 912 PHX Floor .277 992 PHX Roof .461 992 -
.CRDM West Part. .424 380
~
CRDM East Part. .259 1520 CRDM South Part. .229 228 CRDM Floor .267 448 CRDM Floor .45 - 2250 CRDM Roof .461 . 2698 Heat Loads PHX CRDM Btu /hr 135,034 (excluding A/C motor) 106,950 (excluding A/C Equip) (A) 54,032 (excluding A/C & 2/3 55,950 (excluding A/C equip, Trans Load) Rad M-G sets, Full length Rod equip) (B) 74,288 (excluding A/C & 1/2 , 28,430 (excluding same as (B) (C) ) Trans Load) plus no lights , j l _I l I 1 4 E24216.01 NEB - Oct. 10, 1984
\
t 1 L 1 l l l .
)
l
'n ComputeaRitDee L >o//edy .
Checked- WC& Date /0/'/6/$ 7 l:: ( SEQUOYAH NUCLEAR PLANT - - a
, KEY 37H .. .
.,- ROOM STEADY-STATE TEMPERATURE ON LOSS OF COOLING l
REF AB-31C-103 < Qin " Qout Steady State Assume average surrounding air temp is . 850F for simplicity I
^~
PHX Room Continuous Load - '135,034 = (.35)(608)+(.229)(988)+(.259)(912)+(.277)(992)
+(.461)(992) AT .
135,034 = (1407.356)(X-85) - ' 180.950F=X at 1/3 Transformer 54,032 = 1407.356(X-85) Load 123.40F=X at 1/2 Transformer .74,282 = (1407.356)(X-85) X=137.780F Load say 1400F C_RDM Room . Full Load 106,950 = (.424)(380)+(.259)(1520)+(.229)(228)
+( . 28 7) (448) +( .45 ) (2250)+( .461) (2698)
AI
= (2991.866)(X-85) 120.,750 F =X i
E24216.01 NEB - Oct. 10, 1984
~L W
l; t ,.
, Computed h LtB Date 3-6-6 P
Checked ft/ Date. 3/7//f
' ~
'SEQUOYAH NUCLEAR PLANT. -~
KEY 37I-
~~-*
ERCW Pumping Station Drawing Reft 37W900-3R6, -4R3 Cooling is not required for this area. 'See EN DES Calculation NEB 850115 235. R.y .
~ .-
.f-I C
i i i l 1 l ( 1 I
)
E24216.01 NEB - Feb. 25, 1985 1 l
- - - . _- _ __ _O
- 1..
a
! . v 5 '
Computed \,1 M Date.1 3-&-f6~
; Checked- //.:4 Date ~ ,.77/f . //
'SEQUOYAH NUCLEAR PLANT -
KEY.37K ~~ 480V TRANSFORMER ROOM VENTILATION EL 749 AUX BLDG-Cooling is not required for this area. U See EN DES Calculation NEB 850115.235. . lLy L, se 1 e et il
)A 4
WD O l - I E24216.01 NEB-- Feb. 25, 1985 l l: d
.:.,.= >-
4 s .t.
, 06I.;
- \',_
Computed 10_ Date M l,' O .- { . Checked 2tf Date' 2}q)st' ,
~* *
" '[*- SEQUOYAH NUCLEAR PLANT KEY 37L APPENDIX R REVIEW T- , CONTAINMENT INSTRUMENT ROOM COOLING SYSTEM
.[
. .q -
Cooling is not- required for this area.
'~
.:1 - See EN DES Calculation NEB 850115 235. -
, q' 4
9 1 I e i .1
. , E24216.01 NEB - Mar. 25, 1985 L.
M 0
,7... ' Jl Q ,
1 .. +
,s Computed _ hbi,)Dat'e 3-445-
' Checked _;st/ ' Date 2/y)/f SEQUOYAH NUCLEAR PLANT .
*I KEY 37M ~' '
~'
PENETRATION ROOM COOLERS
. Cooling is. not required ' for this area.-
See EN DES Calculation NEB 850115 235. (Lj ' I
^
- \
l m * ( . 1 I l.
, j
'Ii
< l, i
I
)
I l. l E24216.01 NEB - Feb. 25, 1985 l 4 a 4 i' i-i
' i
o . i I Computed bla.L.) Date 11)u)$._- - o c Checked A/A. Date isb>/W '
-lh , ' SEQUOYAH NUCLEAR PLANT KEY 37N ; ,
I L - TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ROOM (TDAFWP) ;-x .. I' UNIT 1, EL 669 l Operation List i DC Powered TDAFW Pump Room Exhaust Fan Must Operate 1-HS- 30-214 Must Operate 1-TS-30-214 Must Operate _
'~- .--i Note 1. The DC powered fan is connected. to the vital batteries arrl 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 of this space.
1 Re fe renc es: 47W866-2 R29. 47W611-30-6 R14 47W610-30-6 R14 , 1
\
l l
)
I E24216.01 NEB - Nov. 27, 1984 l l O e 1
^
~ ~*
'!' Computed hid Date' > /,-fd~
i Checked 1/4 ' Date 3/7/rf-l l; l C SEQUOYAH NUCLEAR PLANT.. i.
- m -
KEY 37N-TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ROOM (TDAFWP) UNIT 2, EL 669 lk Operation List-DC Powered TDAFW Pump Room Exhaust Fan' Mus't Operate :l HS-30-214 Must Operate 2-TS-30-214 Must Operate . 4t[- The DC powered' fan is connected to the vita 1' batteries and is, Note: -- 1. 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 diese,1s.'
- 3. There'are no items consider'ed for spurious operation of.the ventilation: cooling of this space.
References:
'.47W866-2 R29 C '47W611-30-6 R14 47W610-30-6 R14-
~
.i 4 i
~
1 l t E24216.01 NEB - Feb. 25, 1985
- I
. J ]
Computed h1a_\h Date '3-/,-K
~
Checked 14/ Date 3/7kf" N- ' SEQUOYAH NUCLEAR' PLANT- .
- KEY 37 O&P ;-
" BORIC ACID TRANSFER PUMPS AND AUX FW PUMPS COOLERS, CCS AND AFW PUMP COOLERS, AND SFP AND THERMAL BARRIER BOOSTER PUMP SPACE COOLERS Cobling is not required for these areas.
See EN DES Calculation NEB 850115 235. I R.4 r .. ._. N i-e V I E24216.01 NEB - Feb. 25, 1985 i l [. . e h - - - - _ _ _ _ _ _ _ . - _ _ ._.. _ _ _
.(y)
'l.,
- f "
, Computed M mlA Date M -l'I
, ' ~ Checked' fu Date 7/7/d SEQUOYAH NUCLEAR PLANT. *
- / 2 w: , - '? KEY 37Q~ . .
u PIPE CHASE COOLERS (EL 669)
.I i
jcooling .ls not required for .this area. [ See EN DES. Calculation NEB 850115 235. g,y . g,m
.j ,
4 i I i # e l.
,g-
-I C-
.~,
i l, E24216.01 NEB - Feb. 25, 1985 l . l
- l .
l b _..___.__._.._._____._._.---m__._--w
Computed NLL S Date 11/19)f9 Checked //4 Date /s / ' SEQUOYAH NUCLEAR PLANT. *
. KEY 37R. 2 -
CHARGING PUMP COOLERS (EL 669) -L
.a
' Charging: pump room' cooling is included in' Key 1.
3- , , i.[f ' ',s. .- 1
= !
P
.i l
1 l
)
i i l h i 1 E24216.01 NEB - Nov. 27, 1984 l ll . 0 1
=
*mh m._-_- _ _ _ _ _ _ _ _ -- ._._
7__,_ Computed N Date 12/4/(( . C' 5' Checked Aff Date JN!J!/ f SEQUOYAH NUCLEAR PLANT ~., A
,,. KEY 37S i AIR SUPPLY-FOR HVAC 'l
, The components required for suppling control air to the HVAC equipment ' are y,; listed in Key 13.- Control Air Supply, Path 1, is required for all train- A' air-operated equipment'unless manual. control is available. ' Control Air /C ;
' Supply, Path 2, is required for'all-train B air-operated equipment unleos j
. manual control is available, f
O ! I(Q l p l E24216.01 NEB - Dec. 6, 1984
.k
A Computed b d ' Date Il/2.4)/('r ]
;(; - - -
t .c .< 1 Checked ,//.S Date jr/ss,/fV
' SEQUOYAH' NUCLEAR PLANT- .
" KEY 40 RHR PUMP COOLERS (EL 653) .
Operation List
.RHR Pump 1A Cooling RHR c oole r fan 1 A-A Must Operate
*Instrumen* loop. 1-30-175 Must Operate
' **1-FCV-67-188 &st Open RHR Pump 1B Cooling
. RHR cooler fan IB-B Must Operate
'
- Ins trument loop 1-30-176 Must Operate
; * *1-FCV- 67-19 0 Must Open , !
RHR Pump 2A Cooling i
'RHR cooler fan 2A-A Must Operate
- Instrument loop 2-30-175 Must Operate
**2-FCV- 67-18 8 Must Open RHR Pump 2B Cooling ,
RHR coole r fan 2B-B Must Operate .
*Ina trument . loop 2-30-176 Must Operate 1
**2-Ft V- 67-19 0 Must open
- Fan motor control loop '
i
**A design change is being made under ECN-L6258 to remove air from this valve.
Valve fails in open position. No te s: 1. No spurious signals needs be considered.
- 2. The coolers receiva ERCW water.
- 3. The cooler should start upon high room temperature or pump start. ;
- 4. The FCVs are air operated.
Re fe renc es: 47W610-30-5 R13
. 47W610-67-5 R10 47W611-65-1 R10 47W866-8 R19 E24216.01 NEB - Nov. 28, 1984 i
l L_-_______--___ - -
I j r Computed - W& Dette Il}M)(f
- ( r
[ Checked 2/4 Date ' Arb>/W
'K
, SEQUOYAH NUCLEAR PLANT
+
- KEY 40 1 -
ERCW TO RHR PUMP ROOM COOLERS ~~-* Operation and Spurious List
~- Path 1 (Units ' 1 & 2)'
ERCW Header 1A (Operational List) (See Key 1)
' ~
ERCW Header 2A (Operational List) (See Key 1) -. _ .
~
ERCW Header 1A (Spurious List) (See Key 1) (Unit 1) j; ERCW Header 2A (Spurious List) (See Key 1)'(Unit 2) ,
~ . ~ *FCV-67-127 Must Not Close -
Path 2 (Units 1 & 2) ERCW Header'1B (Operational List) (See Key 1)
/ -ERCW Header 2B (Operational List) (See Key 2)
ERCH Header 1B (Spurious List) (See Key 1) (Unit 1) ERCW Header 2B (Spurious List) (See Key 1) (Unit 2)
*FCV-67-128 Must Not Close
*A design change is being made under ECN-L6258 to remove power from this valve.
F E24216.01 NEB - Nov. 27, 1984 4 6
+
1 e
.-__.-m.m.__.-___.-._ ...____
e S
~N' ff m
O
*e 4
APPENDIX A i l
- \
f 1 l l
)
\
1 e 9 t 1 2 h
Appendix A Key 1
' This key requires that a centrifugal charging pump (CCP) be available to "'-
provide RCS makeup water while achieving and maintaining safe shutdown. There are two flowpaths through which the CCP may provide RCS makeup. The ECCS charging path (key 6) may be used, or RCS makeup may be provided through the RCP seals. The CCP is also required to provide flow if seal injection is used to maintain RCP seal integrity. _ To ensure that a CCP is operable, the supporting components and subsystems - are required. The CCP auxiliary lube oil pump mus t provide pump lubrication , for startup of the pump. However, if the lube oil pump (or its associated circuitry) is damaged by fire, the switch bypassing the oil pump (which will [N be installed) must be used to start the CCP. The pump room cooler and its ^~ control circuitry mus t operate. The component cooling system (CCS) is required for pwap cooling. The ERCW system is requird to supply cooling water to the CCS heat exchanger and the CCP pump room cooler, If a fire should cause the closure of '0-FCV-67-151, 0-FCV-67-152, and 1 and 2 -FCV-67-146, the operator has suf ficient time to manually open whichever of those valves (151, 152, or 1 and 2 - 146) required for ERCW - cooling flow through the CCS heat exchangers. With no ERCW flow through the
- heat exchangers (time lapse between valve closure and manual opening) the CCS functions as a passive heat sink until manual action can be taken (within approximately 2 hours).
Key 2 This key requires that one of three valves in the discharge piping f rom the CCPs be open to provide the first portion of the normal charging flow path (key 34) and seal injection. This key's components are required if the normal charging flowpath is used for RCS makeup and/or if RCP seal injection - is used to maintain RCP seal integrity and/or RCS make-up. l E54276.02 NE B - J an . 31, 1985
-. s
1 l. Key 4 4 This key requires that the volun ' control tank (VCT) be aligned to provide a _ short term water source for RCS makeup. 'The VCT will also serve as the short term water source for RCP seal injection if this method is chosen to maintain RCP seal integrity. The VCT discharge valves are normally open. Th ere fore , * .! this source is imediately available. Both isolation valves must be - - - prevented from spuriously closing. This source is required only until suction from the RWST (key 5) is provided. 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 hours to prevent the hydrogen cover gas from entering the charging line (reference NEB 841022 220). If the alternate path is used for aligning the RWST for CCP suction (key 5, path 2), then the VCT must be isolated or depressurized imediately (re fe rence NEB 841022 220). The longer piping length causes increased head losses. t l Key 5
~
The long-term water source for RCS makeup and RCP seal injection (if used) is ' the RWST. It may be aligned by opening either FCV-62-135 or FCV-62-136. The VCT will continue to supply makeup water for a sufficient time a f te r le tdown j lines are isolated that credit may be taken for handwheci operation of the j valv e s. These valves, however, are not adequately separated and one j postulated fire may render both valves inoperable. There fore an alternate l path is provided through the inlet piping for the SI pumps and back to the j inle t to the CCPs. If this flowpath is used, one of two inline valves, FCV- -! 63-6 or FCV-63-7, 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. 1 Key 6 1
/
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. l l l E54276.02 NEB - Nov. 27, 1984 s l
Key 7 o. For RCS pressure boundary isolation, the. normal letdown path must be . isolated.
- This requires the closure of FCV-62-69, FCV-62-70, or all three of the regenerative heat exchanger outlet valves.
,In- all cases the RHR letdown line must remain isolated until the RHR system '~"-
,, . is required for bringing the .the plant to cold shutdown.
The RVHVS solenoid valves must remain closed to prevent the depressurization of the RCS. Key 8' To further ensure RCS pressure boundary control the excess letdown lines mast ~ - ,. be . isola ted.- This requires closing FCV-62-54, FCV-62-55, or FCV-62-56.
, s
~
Key 9
- If RCP seal integrity is not provided by seal injection, thermal barrier coolin'g may be used in its place. The CCS it required to supply water to the thermal barrier booster pumps and the ERCW system is required for the CCS heat exchangers.
Key 11 A motor driven auxiliary feedwater (AFW) pump along with the corresponding steam generator (SG) level control components (key 12) may be used to provide
- SG inventory control. Any of these pumps of the turbine driven AFW pump (keys 14 and 15) .may be used for this func tion. i Key 12 The components listed in this key are only required if the motor driven AFW - i pumps (key 11) are used to provide flow to the SGs. The SG 1evel may be controlled automatic ally or manually. Automatic level control consists 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. .
E54276.02 , NEB - Nov. 27, 1984
.. -.-_-.___.-._..a.-
l { l Key 13 {] This key contains the equipment necessary to supply control air for those ((~ k functions on the shutdown logic diagram which require it for operation. Path 1 contains the components required for auxiliary air compressor A which provides control air for air supply header A. Path 2 contains the equipment' for air supply header B. - The following components require control air for operation. Steam generator level control valves, automatic control (keys 12 & 16), and SG PORVs if MCR operation is used. Various dampers and valves required for HVAC (key 37)
~
Keys 14 & 15 - The turbine driven AFW pump may be uts i to supply feedwater for SG inventory control. If this pump is used (as opposed to a motor driven pump, key 11), the SG icvel control valves (key 16) corresponding to the two loops being . used for cooldown met be operable. For pump operation, a steam supply from SG 1 or 4 must be available. In addition, the turbine trip and throttle valvt and governor valve met be ope rable. Key 16 If the turbine driven AFW pump is used to supply feedwater to the SGs, th e two level control valves corresponding to the loops being used for cooldown must be operable. The valves may be controlled automatically or manually. Autonatic control requires control air (key'13) for the valve controller. Manual control consists of handwheel operation of the LCV. The mnual method of maintaining SG 1evel requires monitoring in the MCR with le"el indicators. Key 17
- In order to provide SG 1evel control, a supply of feedwater is required for the AFW system. The initial supply is the condensate storage tank (CST). It is normally aligned and no components are required to function for this key.
Key 19 After the CST (key 17) has reached its low level, the suction for the AFW system mst be switched to the ERCW system. The valves corresponding to the
, pump being used to supply AFW to the SGs must be opened. The piping for the MDAFW pumps supply branches of f from the discharge headers in the ERCW system. The re fore , a flow path in the ERCW system mst 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. E54276.02 NEB - Nov. 27, 1984
i
.I I
Key 20 ((, ' For secondary side isolation, the main steam supply to the turbines must be isolated. This key provides the pre fe rred method of main steam isolation. l This requires closing the' main steam isolation valves and ensuring that the '
- 1, main steam isolation bypass valves are closed. ~ - - '
Key 21 If the main steam isolation and bypass valves (key 20) cannot be closed, the steam load may be isolated by closing the main steam dump valves, the main turbine trip and throttle valves and the main feedwater pump turbine trip and
' throttle valves. These valves are not powered by the diesel and will close
;)
on loss of power. l Key 22
~
For secondary side isolation, the main feedwater supply must be terminated 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. In adBition, a feedwater bypass l isolation valve for each SG must be veri'fied to be closed. Key 23 i 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 pump requires closure of main feedwater pump
- turbine stop valves or control valves.
- Key 24 J
To complete the secondary side isolation, a blowdown isolation valve for *each I SG must be closed, or the header valve must be closed. - l Key 25 The secondary safety valves and secondary relief valves (key 26) are required l to provide secondary side pressure control. For each of the two SGs being used for cooldown, the set of safety valves must be operable to provide short te rm pressure control. The valves are spring loaded and a' fire cannot cause them to open.
\
, l E54276.02 NEB - Nov. 27, 1984 e ..)
'. r
;j'
.1 i
ik , y, j g 4 Key 26 l jI - _ The. secondary [ relief valves are required for long-term, secondary side pressure . control and for cooldown. The valves are separated such that two
'd-d (f
I valves .will'be ~ accessible for manual handwheel operation. The secondary side - _ ; pressure is monitored in the MCR for each of the > two loops being used for 7,s J u cooldown. \ ; I Key.28 1
-RCS pressure control may be maintained by either automatic or manual operation :of the pressurizer heaters. Operatlpn requires that the RCS
' wide-range temperature indication for the two loops being used for cooldown and RCS pressurelindication _both be displayed in the MCR. ~
, a '. / -
l lIn.the-event that the pressurizer heaters care' lost, Sequoyah Nuclear Plant Sp'ecial Startup Teat No. 3, " Natural Circulation with' Loss of Pressurizer 4 Heaters," determined that natural circulation conditions and saturation R!) l
. margin could be developed and maintained under the degraded condition of loss -
- of all pressurizer heaters. Furthermore, the depressurization rare.fpver the testing period was approximately 100 psig/hr, and a 10 percent increava in pressurizer level would result in a greater,than 100 psig pressure increase.
'Therefore, pressurizer heaters > are . cot required for safe shutdown, and \ cold shutdown can be achieved in approximately 19 hours. \ '
Key 29 Once a fire has.been detected, the reactor must be tripped to bring the piant
,\
to hot standby. Reactor trip breaker A or B may be tripped by the 1 g handswitches in the MCR. Also, the reactor may be tripped using the motor- I generator set breaker A or B. The reactor trip itself provides suf ficient initial reactivity control. Make-up from the RWST will provide suf ficient negative reactivity insertion (ref. S53 841221 923). ' i- gJ( I
.
Normal charing may$be,heavided to the cold leg of loop 1 or the cold leg of lobe 4. Sinie ett'ner patN may be in use, both paths must be shown to .be D aval,lable at aqr time.
;j Key 35 -
p If the pressurizer heatera'ere . rot operable due to fire damage, the plant must be taken directly to cold ebutdown. This requires that the equipment in
~
l keys 30, 31, 36, and 40 be available to bring the plant to cold shutdown within 19 hours.
- Key 36 {
As the ACS depressurizes hhile the plant is brought to cold shutdown, the UHI and accumulators uust be isolated. Thie regoires closure of the UHI ; isolation gag valves atx! the eacumlator isolation valves. If the L accumulators cannot be isolated, they must be depressurized by venting the cover gas. i i
.(c -
l E54276.02 NEB - Nov. 27, 1984
Key 37 (1 This key contains the HVAC equipment required to achieve and maintain hot - standby. Air conditioning is mquired for the MCR.
.]k The' ventilation systems are required for. the DG building.
N
" ' Control air (key 13) is required for automatic operation of dampers and valves for main control room air conditioning.
Key 40 LWhen 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 coole r with cooling water from' the ERCW system. - - m e l e l l
]
q 1 l I i 4 E54276.02 NEB - Nov. 27, 1984
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162-P-1-2A 162-PCV-1-23 162-P-1-2B 162-FCV-1-25 162-FCV-1-4 162-7-1-27A 1&2-FSV-1-4A 1&2-P-1-27B 162-FSV-1-4B 162-FCV-1-29 ~ 1&2-FSV-1-4D 162-FSV-1-29A - 162-FSV-1-4E 1&2-FSV-1-29B l 162-FSV-1-4F 162-FSV-1-29D 1 162-FSV-1-4G 162-FSV-1-29E 162-FSV-1-4H 1&2-FSV-1-29F 162-FSV-1-4J 1&2-FSV-1-29G 162-P-1-5 162-FSV-1-29H 162-PCV-1-5 162-FSV-1-29J
'l&2-FCV-1-7 ~
1&2-P-1-30 162-P-1-9A - 1&2-PCV-1-30 162-P-1-9B 162-FCV-1-32 1&2-FCV-1-11 162-FCV-1-36 162-FSV-1-11A 162-FCV-1-37 162-FSV-1-11B 162-FCV-1-3 8 162-FSV-1-11D 16 2-FCV-1-3 9 162-FSV-1-11 E 162-FCV-1-43 RG j 162-FSV-1-11F 162-FCV-1-44 1 162-FSV-1-11G - 162-FCV-1-45 l 162-FSV-1-11H 162-FCV-1-46 162-FSV-1-11J , 1&2-FCV-1-51 162-P-1-12 162-FCV-1-52 I 162-PCV-1-12 , 162-FCV-1-61 l 162-FCV-1-14 1&2-FCV-1-62 - 162-FCV-1-15 162-FCV-1-64 - 162-FCV-1-16 162-FCV-1-65 l 162-FCV-1-17 1&2-FCV-1-67 j 162-FCV-1-18 162-FCV-1-68 ) 16 2-P-1-20A 162-FCV-1-70 l 1&2-P-1-20B 162-FCV-1-71 I 162-FCV-1-22 1&2-FCV-1-75 162-FSV-1-22A 1&2-FCV-1-77 1&2-FSV-1-22B 162-FCV-1-79 162-FSV-1-22D 162-FCV-1-84 l 162-FSV-1-22E 162-FCV-1-91 1 162-FSV-1-22F 162-FCV-1-98 162-FSV-1-22G 1&2-FCV-1-103 162-FSV-1-22H 162-FCV-1-104 1&2-FSV-1-22J 162-FCV-1-105 16 2-P-1-23 . 162-FCV-1-106 E75128.02 NEB-Jan. 29, 1986
^
l l L
' ' 1f Prepared $/fh) Date 3//.9/ff _
Checked h h) Date 4,~Af3 /&f .
, APPENDIX C ' .. ;_ ]
Shutdown Logic Component. List a: 1&2-FCV-1-107- 162-VLV-001-872 ! 162-FCV-1-108 1&2-FCV-3-33 i 1&2-FCV-1-109 1&2-FCV-3-35 l 1&2-FCV-1-110 162-FCV-3-35A . 1&2-FCV-1-111 1&2-L-3-39 -
., i 162-FCV-1-112- 1&2-L-3-43 -- i 1&2-FCV-1-113 1&2-FCV-3-47 1&2-FCV-1-114 162-FCV-3-48 . , .1&2-FCV-1J 47 1&2-FCV-3-48A 1&2-FCV-1-148 162-L-3-52 -
1&2-FCV-1-149 1&2-L-3-56 1&2-FCV-1-150 1&2-FCV-3-87 1&2-FCV-1-181. 142-FCV-3-90
-162-FCV-1-182 , 1&2-FCV-3-90A 1&2-FCV-1-183 1&2-L-3-94 f 1& 2-FCV 184 . 1&2-L-3-98 !
'l&2-FCV-1=??5. 1&2-FCV-3-100 l 1&2-FCV-1-277 162-FCV-3-103 1&2-7CV-1-279- 1&2-FCV-3-103A 162-FCV-1-284 1&2-L-3-107 1&2-FCV-1-291 162-L-3-111 .
p 162-FCV-1-298 1&2-L-3-116A l 1&2-VLV-001-512 1&2-L-3-116B l 1&2-VLV-001-513 1&2-L-3-126A 1&2-VLV-001-514 "1&2-L-3-126B l 162-VLV-001-515 ' 1&2-L-3-136A 1&2-VLV-001-516 162-L-3-136B , 1&2-VLV-001-517 , 1&2-P-3-138A _j 1&2-VLV-001-518 1&2-P-3-138B 1&2-VLV-001-519 1&2-PS-3-140A 1&2-VLV-001-520 162-PS-3-140B < 1&2-VLV-001-521 1&2-F-3-142 I 1&2-VLV-001-522 1&2-L-3-148 I
- 1&2-VLV-001-523 1&2-LCV-3-148
'l&2-VLV-001-524 1&2-LSV-3-148 1&2-VLV-001-525 1&2-PS-3-148 l .1&2-VLV-001-526 1&2-PS-3-150A
-1&2-VLV-001-527 1&2-PS-3-15CB l' . 1&2-VLV-001-528 162-L-3-156 1&2-VLV-001-529 1&?-LCV-3-156 162-VLV-001-530 1&2-LSV-3-156 1&2-VLV-001-531 162-PS-3-156 162-VLV-001-868 1&2-PS-3-160A 1&2-VLV-001-869 1&2-PS-3-160B ,
.E75128.02 NEB-May 13, 1985 I
e t
Prepared E a t- Date Al $G, Checked DlaNNfn Date $~l8*E4 f( APPENDIX C ;- , Shur.down Logic Component. List 1& 2-L-3-16 4 2-TS-30-448B RG 1&2-LCV-3-164 1-FCO-30-449-1&2-LSV-3-164 1-TS-30-449B 162-PS-3-164 2-FCO-30-450 1&2-PS-3-165A 2-TS-30-450B ~ 162-PS-3-165B- 1-FCO-30-451 u -
~"
mN, ' 1&2-L-3-171 - 1-TS-3 0-451 B - J162-LCV-3-171 2-FCO-30-452 162-LSV-3-171 2-TS-30-452B - 1&2 PS-3-171 1-FCO-30-453
~
162-L-3-172 1-TS-3 0-453 B 1&2-LCV-3-172 2-FCO-30-454 1&2-LSV-3-172 2-TS-30-454B 16 2-L-3-173 - 1-FCO-30-459 1& 2-LCV-3-173 - 2-FCO-30-460 162-LSV-3-173 1-FCO-30-461 1&2-L-3-174 FCO-30-462 ge 1& 2-LCV-3-174 0-FCO-31A-20 1&2-LSV-3-174 0-FSV-31A-20 lkm 16 2-L-3-17 5 0-T-31A-22 162-LCV-3-175 0-FSV-31A-22A 1&2-LSV-3-175 0-FSV-31A-22B - 1&2-FCV-3-179A - 0-FCO-31A-23 162-FCV-3-179B 0-FSV-31A-23 1&2-VLV-3-826 , 0-T-31 A-3 9 1&2-VLV-3-827 0-FSV-31 A-3 9A 162-VLV-3-82 8 , 0-FSV-31 A-3 9B 1&2-VLV-3-829 0-TCV-31A-47 . 162-VLV-3-834 0-CCV-31A-48 .. 162-VLV-3-83 5 0-TCV-31A-49 i 162-VLV-3-83 6 0-TCV-31A-50 l 1 & 2-VLV-3-837 0-T-31A-52 1&2-T-30-175 0-TCV-31A-65 1&2-T-30-176 0-TCV-31A-66 1& 2-TS-3 0-182 0-TCV-31A-67 1& 2-TS-30-183 0-TCV-31A-68 1 & 2-TS-30-214 0-T-31A-70 1-FCO-30-443 0-P-31A-126 2-FCo-30-444 0-P-31A-127 ; 1-FCO-30-445 0-T-31A-128 l 2-FCO-30-446 0-T-31A-129
'1-FCO-30-447 0-LG-31A-130 1-TS-30-447B 0-PCV-31A-131 .
2-FCO-30-448 0-TS-31A-132 NES-Jan. 29, 1986
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%_. E75128.02 .
O w -@ 8
[ Prepared _fE4) Date ' $~/B/py , Checked _ hL O _ Date f-/ndf
^
, APPENDIX C
_~.
~ Shutdown Logic Componsat List f
0-T-31A-133 1&2-FCV-62-89
, 0-PCV-31 A-134A - 162-FCV-62-90 0-PCV-31A-134B 1&2-FCV-62-91 ,
j 0-ET-31A-136 162-FCV-62-93 . 0-P-31A-141 1&2-FCV-62-98 - g' 0-P-31A-142 1&2-FCV-62-99 --
; 0-T-31A-143 , 162-PCV-62-119 0-T-31A-144 1&2-PCV-62-120 0-LC-31A-145 1&2-FSV-62-125 0-PCV-31A-146 162-PCV-62-126 -
0-TS-31A-147 162-L-62-129A 0-T-31A-148 1&2-L-62-130A 0-PCV-31A-149A 162-LCV-62-132 0-PCV-31 A-149B , 162-LCV-62-133 0-ET-31A-151 162-LCV-62-135
.0-P-31A-172 1&2-LCV-62-136 0-P-31A-173 162-VLV-62-526 / 0-FCD-31A-176 1&2-vLV-62-527 l(,i 0-T-31A-176 162-VLV-62-533 0-FCO-31A-177 162-VLV-62-534 0-T-31A-177 1&2-VLV-62-689
{ 0-FSV-32-37 1&2-VLV-62-692 'l 0-FSV-32-12 162-VLV-62-693 ; 0-FSV-32-611 162-FCV-63-1 3 0-FSV-32-62 ~1&2-FCV-63-5 0-FCV-32-82 162-FCV-63-6 ; 0-PS-32-82 1&2-FCV-63-7 . I 0-FCV-32-85 162-FCV-63-25 l
~'
0-PS-32-85 1&2-FCV-63-26 0-FSV-32-87 162-FCV-63-39 0-FSV-32-88 1&2-FCV-63-40 0-VLV-33-500 1&2-FCV-63-41 0-VLV-33-501 1&2-FCV-63-42 162-FCV-62-54 162-FCV-63-47 1&2-FCV-62-55 1&2-FCV-63-72 . 162-FCV-62-56 1&2-FCV-63-73 1&2-FCV-62-69 162-FCV-63-93 1&2-FCV-62-70 162-FCV-63-94
. 1&2-FCV-62-72 1&2-FCV-63-172 1&2-FCV-62-73 162-VLV-63-574 162-FCV-62-74 0-FCV-67-12 1&2-FCV-62-84 0-FCV-67-14 1&2-FCV-62-85 1&2-FCV-67-66 j
'162-FCV-62-86 1&2-FCV-67-67 r
E75128.02 NEB-May 13, 1985 l i N .
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L. 1 L Prepared 8A Date 4- 18'% 1 1- _ ' [' Checked D6441/c__. Date 6 -if-8 G l I k- APPENDIX C .. Shutdown Logic Component List 1-FCV-67-7 2 16 2-FCV-6 8-333 i 162-FCV-67-81 162-FCV-68-33 4 1&2-FCV-67-82 162-L-6 8-33 5A 162-TCV-67-123 16 2-L-6 8-33 9A 162-FCV-67-124 162-PCV-68-340A 162-FCV-67-125 16 2-P-6 8-3 420 162-FCV-67-126 162-FSV-68-394 162-FCV-67-127 16 2-FSV-611-3 95 162-FSV-68-396 162-FCV-67-128 162-FCV-67-146 162-FSV-6 8-3 97 162-FCV-67-147 0-FCV-70 ' RG 0-FCV-67-151 16 2-FCV-7 0-2 0-FCV-67-152 162-FCV-70-3 l 162-FCV-67-168 162-FCV-70-4 16 2-FCV-67-170 1-FCV-70-8 162-FCV-67-188 1-FCV-70-9 162-FCV-67-190 1-FCV-70-10 0-TCV-67-197 0-FCV-70-11 0-TCV-67-201 0-FCV-70-12 0-FCV-67-205 1-FCV-70-13 ' 0-FCV-67-208 2-FCV-70 14
. 162-FCV-67-223 2-fCV-70 15 ;
0-FCV-67-364 2-FCV-7 0-l 's 0-FCV-67-365 2-FCV-7 0-18 1-FCV-67-424 0-FCV-7 0-2 2 1-FCV-67-478 1-FCV-70-23 1&2-FCV-67-489 1-FCV-70-25 ' 162-FCV-67-490 A < 1-FCV-70-26 162-FCV-67-490D 1-FCV-70-27 162-FCV-67-491 A 2-FCV-70 28 162-FCV-67-491D 2-FCV-70-29 f ! 162-FCV-67-492 0-FCV-70-34 162-T-66-1 0-FCV-7 0-3 9 162-T-6 6-18 0-FCV-70-40 l 162-T-68-24 0-FCV-70-41 16 2-T-6 8-41 1-FCV-70-64 162-T-68-43 1-FCV-70-74 - 162-T-68-60 162-FCV-70-75 16 2-T-6 8-6 5 2-FCV-70-76 RC 1 162-P-68-65 2-FCV-70-78 i 162-F-68-69 16 2-FCV-7 0-87 ' l 16 2 -T-6 8- 83 162-FCV-70-90 16 2-L-6 8-3 20 162-FCV-70-133 162-FCV-68-332 l E75128.02 -k NEh Jon. 29, 1986 ) l I
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, I b: l L I I
Prepared Ru Date 4- / 8-% Checked Ob Yeu Date 6 - / 8'- S b. 1 l(L (; APPENDIX C
!; 4 Shutdown Logic Component List i 1&2-FCV-70-134 1&2-FCV-72-20 1&2-FCV-70-153 1&2-FCV-72-23 1 1& 2-FCV-7 0-156 1& 2-FCV-7 2-3 9 )
0-FCV-70-193 1&2-FCV-72-40 0-FCV-70-194 1&2-FCV-72-41 2-FCV-70-195 1&2-FCV-74-1 *; 2-FCV-7 0-196 1&2-FCV-74-2
' 0-FCV-70-197 162-FCV-74-3 ~
' 0-FCV-7 0-198 162-FCV-74-12 ;
0-VLV-70-529A 1&2-FCV-74-16 _ l 0-VLV-70-529B 1&2-FCV-74-21 1-VLV-70-531 162-FCV-74-24
-1&2-VLV-70-545A 1&2-FCV-74-28
~
162-VLV-70-545 B 1&2-FCV-74-33 1&2-VLV-70-546A ' 1&2-FCV-74-35 1 & 2-VLV-70-546 B 0-PCV-77-89 1&2-ISOL-70-574 1 & 2-FCV-87-21 1&2-ISOL-70-587 1& 2-FCV-87-22 0-ISOL-70-601- 1& 2-FCV-87-23 0-ISOL-70-636 162-FCV-87-24 i 1&2-ISOL-70-637 1&2-VLV-87-550 162-ISOL-70-661 1&2-VLV-87-552 1&2-FCV-72-2 1&2 AFW motor-driven pump A-A 1&2 AFW r;otor-driven pump B-B 1&2 AFW turbine-driven pump A S
- O Auxiliary air compressor A 0 Auxiliary air compressor B 1&2 Auxiliary lube oil pump A-A 1&2 Auxiliary lube oil pump B-B 1&2 Centrifugal charging pump A-A 1&2 Centrifugal charging pump B-B 1&2 Centrifugal charging pump room cooler fan A-A 1&2 Centrifugal charging pump room cooler fan B-B 162 Component cooling pump A-A 162 Component- cooling pump B-B
( 0 Component cooling pump C-S (Note: .Can be powered f rom train A or train B) R(, E75128.02 NEB-Jan. 29, 1986 c _ _ . _ _ - - . . - - _ _ . _ _ _ _ _ _ ., .~ - --J
u- , 6 II Prepared Mar Date' 4 $(, checked Oldk[AhDate (se- / 8- F 4. APPENDIX C
- Shutdown Logic Component List .
1&2 Containment spray pump' A-A l 1&2 Containment spray pump' B-B - 162 Diesel generator room A-A exhaust f an I-A . - 1&2 Diesel generator. room A-A exhaust fan 2-A - T. ., D 1&2 Diesel generator room'B-B exhaust fan 1-B
. '162 Diesel generator room B-B exhaust fan 2-B ,
1&2' Electric board room exhaust-fan A-A . 1&2 Electric board room exhaust fan B-B 1&2 Electric panel / generator fan A-A ~
' l&2' Electric panel / generator fan B-B 0 ERCW pump J-A.
- 0 ERCW' pump K-A.
0.ERCW pump Q-A (* 0 ERCW pump R-A O ERCW pump L-B
- 0 ERCW pump M-B 0 ERCW pump N-B.
0 ERCW pump P-B 1-ERCW streiner'A1A-A - 2-ERCW strainer A2A-A 1-ERCW strainer B1B-B ' 2-ERCW strainer B23-B , 1&2 Main control room AHU A-A 1 1&2 Main control room AHU B-B ; 1&2 Pressurizer backup heaters A-A 1&2 Pressurizer backup heaters B-B 1&2 Reactor trip breaker A 1&2 Reactor trip breaker B
.. . 1&2 RCP thermal barrier booster pump A-A
. 1&2 RCP thermal barrier booster pump B-B l 1&2 RHR pumps A-A l 1&2 RHR pumps B-B t
E75128.02 NEB-Jan. 29, 1986
. l,
.'(
I - Pre pared ' _ 8/f2u Date f//f//f"~~ ,
%:: Checked'b h g Date I//.2/#5~
i <. c APPENDIX'C ~.. , n. Shutdown Logic Component List - 182 ER room ' coolers " A-A 1&2 ER room coolers B-B L e 1&2 Source range monitor N1-31B 1&2 Source range' monitor N1-32B ~
.0 Station air compressor A
-0 Station air compressor B -
I' ( l s4 t 1 i E75128.02 ' NEB-May 13, 1985 i i M ..
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