ML20154C452
| ML20154C452 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/29/1986 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20154C420 | List: |
| References | |
| NUDOCS 8809140372 | |
| Download: ML20154C452 (80) | |
Text
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*, 8 DRAWING No. A-18172 ,
SREET 1 l 1 1
. 1 1
i SYSTEM EVALUATION DOCUMENT FOR GEORGIA POWER COMPANY FOR EDWIN !. 2AT::E UNIT 1 ** FOR TER I REACTOR RECIRCULATION SYSTEM (531) RIV. PROJ. NO. DATE BY DESCRIPTION CHX ENGR. SLD*R. 0 g .gg . p, A{ !$$UED PER REA HT-4619 g% _k)g(, 8809140372 890908 PDR ADOCK 05000321 P PNU
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A-18172 , SHEET .)_
!. SYSTEM OPERATION The Reactor Recirculation System ensures adequate core cooling during power operations by supplying coolant flow past the reactor fuel bundles. This flow is provided by i recirculating that portion of the core flow which is not i) boiled while passing through the core. The flow rate can be varied as one means of controlling reactor power.
The system consists of two (2) loops external to the Reactor d Pressure Vessel (RPV). Each external loop contains one variable speed motor-driven recirculation pump, two motor ! operated gate valves, and a motor generator set to control the recirculation pump speed. Suction is from the reactor vessel ; annulus and discharge is to the reactor vessel jet pumps. ; The Reactor Recirculation System has seven (7) wodes of . j operation: Normal. LPCI Injection, Recirculation Pusp Trips, Reactor Water Sample, RPV Botton Drain, Recirculet/.on Pump Seal ,
! Purge, and Shutdown Cooling Mode. !
I ' l The function of each mode (and therefore the components of a each subsystem) are safety related or non-safet" related as { indicated in Table 1, and further described in Section II. 1 l The general safety design criteria which are applicable to ! components in one or more modes are indicated in Section V, r and further discussed in Section II. ' Electrical design
- considerations are covered under the support systems listed in 4
, Section III. ,
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- . ee REACIOR RECIRCULATION SYSTEM (831) DRAWING NO. A-18172 SHEET _1.
!!. DESCRIPTION OF OPERATIONAL MODES A. Normal Operation Mode During normal operation, the reactor recirculation
.systen ensures adequate core cooling and reactivity .
control by maintnining forced circulation of water past the fuel bundles. The recirculated coolant consists of saturated water from the steam separators and dryers that has been subcooled by incoming feedwater. This water passes down the annulus between ths RPV wall and the core shroud. A portion of the coolant flows from the RPV through the two external recirculation leeps ta become the driving flow for the Jet pumps. The recirculation flow rate is controlled by varying the output frequency of the associated motor generators, thus varying the speed of the associated recirculation pump. Reactor power can be partially controiled by varying the recirculation flow rate without requiring control rod movement. This power change is accomplished by utilir.ing the large negative power coefficient found in - the BWR design. The void coefficient present in the reactor core is a function of the recirculation flow rate. An increase in core flow sweeps some of the voids from the moderator and causes an increase in reactivity. A , decrease in core flow results in the formation of more
- voids which decreases core reactivity. In the event of a Power failure to the recirculation pumps the systen has enough inertia to ensure that adequate circulation can be maintained to prevent damage to the fuel assemblies in the RPV core.
Tla Reactor Recirculation Systos is also designed to p r o v '. d e automatic load followiug capability over the range of approximately 70 to 1004 rated power. If feedwater flow is below 20 percent, the recirculation pump speed is automatically limited. Therefore, automatic protection against recirculation pump cavitation due to NPSH loss is provided by the 20 percent feedwater flow limiter. The recirculation flow is monitored by sensing elements i on each loop. This flow rate is transmitted to the Neutron Monitoring System (C51) so that the neutron flux / recirculation flow relationship can be calculated. If this calculated relationship deviates from the normal operational value as determined through analysis, the Neutron Monitoring System will initiate a SCRAM signal. REV 0 l 1
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t REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A- ( SHEET 5__18172 , r ! II. DESCRIPTION OF OPERATIONAL MODES ; A. Normal Operation Mode r {
- The Normal Operational Mode is safety related with the j following safety functions
- -
i j j o Reactor Coolant Pressure Boundary (RCPB) Integrity i 1 An example of a safety design basis event is the startup . l of an idle recirculation pump. ! i B. LPCI Injection Mode ' During this mode, portions of the Reactor Recirculation " j System piping are included in the LPC1 flow paths. ; f Upon the receipt of a LPCI injection signal (High Drywell , Pressure / Reactor Low Level 1), the reactor recirculation ] pumps are tripped (Reactor Low Level 2) and the discharge isolation valves (B31-F031A.8) close to avoid LPCI flou ' 1 out of a possible break in a recirculation line and to l assure that LPCI flow is directed through the jet pumps. , The LPCI Injection Mode is safety.related with the' following safety functions: - { i o Reactor Core Cooling Geometry l o Reactor Coolant Pressure Boundary (RCPB) ; Integrity i o Reactor Coolant Inventory l o High Energy Line Break Mitigation ; An example of a safety design basis event is a Loss of ! l Coolant Accident (LOCA). l I C. Recirculation Pump and/or Motor Generator Trips Mode i l The main recirculation pumps and motor generators have various trips associated with them, some of which have i safety significance. The recirculation pump is designed ; 4 to have sufficient inertia so that it gradually coasts ; down after a trip, thus smoothing any flow transients i i caused by cutting off recirculation flow. I Safety related trips occur with the following events: I Reactor Low Water Level (Level 2) Reactor High Pressure Trip Turbine Stop Valve Closure - (If the cesctor Turbine Control Valve Fast Closure - power is > 30% of rated) REV 0 } 1 I i
. . 1 REACTOR RECIRCULATION SYSTEM (331) DRAWING NO. A-18172 SHEET 6__
4
!!. DESCRIPTION OF OPERATIONAL MODES C. The safety related trips serve to reduce reactor power '
j in case of a reactor scram failure by increasing the void coefficient in the moderator (water). ; , 66 - Non-safety related trips of the recirculation pumps and/or motor generators serve to protect the equipment. These trips are listed on the Reactor Recirculation System Logic Diagrams. The Recirculation Pump or Motor Generator Trips mode is
! safety related with the following safety functionst o Reactivity Control >
j! o Reactor Coolant Pressure Boundary Integrity I An example of a safety design basis event is tripping two recirculation pumps. D. Reactor Water Sample Mode A connection off of the racitculation piping is provided for use in the event that the Reactor Water Cleanup System is out of service. The sample line is ; connected into an active portion of the recirculation , system to ensure that a representative sample of d reactor water is obtained. The sample line valves ( autosatically close on receipt of a containment l isolatien signal. - t The Reactor Water Sample Mode is safety related with j the following safety functionst i o Reettor Coolant Pressure Boundary Integrity , o Containment Isolation > An example of a safety design basiw event is a Loss of Coolant Accident. ] j E. Reactor Vessel Botton Drain Mode : 1 l A drain line is connected to the bottom head of the reactor vessel to permit flushing the bottom of the , reactor to the radweste system during plant shutdown. This drain is also piped to the main suction line of the j reactor water cleanup system. The valve in this line is normally open to permit flow to pass from the bottom of the reactor vessel to the cleanup system continuously ! during reactor operation. This is done to keep the drain l l line flushed out and to provide temperature readout of the ! coolant in the bottom of the reactor vessel by means of an installed thermocouple. l J REV 0 i I t I ) i j I _ __ __ _ J
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REACTOR RECIRCULATION SYSTEM (531) DRAWING NO. A-18172 SREET _1. II. DESCRIPTION OF OPERATIONAL MODES i E. The Reactor Vessel Botton Drain Mode is safety related ' with the following safety functions o Reactor Coolant Pressure Boundary Integrity 4 T. Recirculation Pump Seal and Purge Mode The recirculation pump seals are cooled by injection water supplied by the CRD (Cll) System. The pumps and the MG ! Sets are cooled by the RBCCW (P42) System. The pump seals ! are provided with a purge system to keep the seals clean ' by maintaining a net flow of clean water out of the seal - area, along the pump shaft, and into the recirculation system. A flow of (3) three to (5) five spa is
; continuous 1r arawn from the control rod drive hydraulic
, systen at all times. 4 The Recirculation Pump Seal and Purge Mode is safety ;
; related with the following safety function ! ! l l o Reactor Coolant Pressure Boundary (RCPB) ;
Integrity. ; i G. Shutdown Cooling Mode i The Shutdown Cooling Mode is an integral par.t of the RRR System (Ell). Reactor coolant is pumped from one of the i recirculation loops by one or both RHR Pumps and is discharged through the RER heat exchangers where it is , cooled by the RRRSW flow. The reactor coolant is then returned to the RPV via the recirculation loop.
- This mode contains no individual components from the l l Reactor Recirculation System except the segment of ,
l recirculation pipe where the RHR system ties in, flow elemente N013A.B which serve as pressure boundaries, and recirculation pump discharge isolation valves F031A.R which are closed. l The Shutdown Cooling Mode is safety related with the i following safety functionet o Reactivity Control o Reactor Core Cooling Geometry , o Reactor Coolant Pressure Boundary lategrity t o Reactor Coolant Inventory l I t 1 An example of a safety design basis event is a Shutdown i ] Cooling (RHR) Malfunction Decreasing Temperature. 1 ; REV 0 ; l
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REACTOR RECIRCULATION SYSTEM (531) DRAWING NO. A,18172 SREET ,{. III. SUPPORT SYSTEMS The following systems, in whole or in part, are required to support the operation of the Reactor Recirculation System. For detailed information pertaining to the functionally nuclear safety related portions of these systems, the respective system evaluation documents for each system should be consulted. A. Nuclear Roller System - 321
- 3. Residual Rest Removal System - Ill C. Reactor Building Closed Cooling Water System - P42 D. Control Rod Drive System - Cll E. Neutron Monitoring System - C51 F. Reactor Protection System - C71 G. Battery System - R42 H. Diesel Generator - R43
!. Uninterruptible power - R44 The following system supports the Reactor Recirculation System in a non-safety manner by providing Net Positive Suction Read (NPSR) for the recirculation pumps A. Feedwater System - N21 I
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING N0. A-18172 SEEET .]. SYSTEM EVALUATION DOCUMENT IV. REFERENCE DOCUMENTS DWG NO. REY. TITLE H-16063 16 Nuclear Boiler System P&ID. Sheet 2 , M-16066 16 Reactor Recirculation System P&!D. Sheet 1 N-16067 1 Reactor Recirculation System P&ID. Sheet 2 : E-16068 2 Reactor Recirculation System P&!D. Sheet 3 H-16076 7 Reactor Recirculation System M.G. Sets PLID H-17860 13 Reactor Recirculation Pump and M.G. Set Elementary Diagrams. Sht 1 H-17861 7 Reactor Recirculation Pump and M.G. Set Elementary Diagrass. Sht 2 H-17862 13 Reactor Recirculation Pump and M.G. Set ] Elementary Diagrams. Sht 3
; j H-17863 7 Reactor Recirculation Pump and M.G. Set Elementary Diagrams. Sht 4 H-17864 19 Reactor Recirculation Pump and M.G. Set i Elementary Diagrams. Sht 5 H-17865 10 Reactor Recirculation Pump and M.G. Set j Elementary Diagrams. Sht 6 i H-17866 15 Reactor Recirculation Pump and M.G. Set i Elementary Diagrams. Sht 7 L H-17867 7 Reactor Recirculation Pump and M.G. Set :
. Elementary Diagrams, Sht 8 . i H-17868 11 Reactor Recirculation Pump and M.G. Set 1 Elementary Diagrams. Sht 9 , H-17869 2 Reactor Recirculation Pump and M.G. Set ! Elementary Diagrees. Sht 10 ! H-17870 3 Reactor Recirculation Pump and M.G. Set i Elementary Diagrams. Sht 11 H-17814 13 Reactor Recirculation Pump and M.G. Set , Elementary Diagrams. Sht 12 r ! H-19913 0 Resctor Recirculation System Logic Diagram. ! Sht 1 H-19914 0 Reactor Recirculation System Logic Diagram. l Sht 2 !
- H-19915 0 Reactor Recirculation Systen Logic Diagram.
; Sht 3 i H-19916 0 Reactor Recirculation System Logic Diagram, i
- Sht 4 !
R-19917 0 Reactor Recirculation System Logic Diagram. I
- Sht 5 :
3-19308 A Operation and Maintenance Instruction Manual f Vol. !! - Reactor Recirculation System I i
] Unit 1 TSAR. Rev. 3. 3.7 4.3, and 7.9 Technical Specifications. Amend 124, 3/4.6 !
i 10CFR50 Appendix A. General Design Criteria No. t
! 1, 2 4, 12 13, 14, 15 30, 31 32, 55 t
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REACTOR RECIRCULATION SYSTEM (831) DRAWING NO. A-18172 SHEET _lo, ; SYSTEM EVALUATION DOCUMENT , 1 IV. REFERENCE DOCUMENTS Central Tile for the Environegatal Qualification of safety i Related Equipment, Section 8 (MNP-1), Rev. 19. I Review of Plant Systems per supplement 1 NUREG-0737, Comparison i to NRC Regulatory Guide 1.97 (Rev. 2) RNP-1 , i SCSI Calculation # SNR 86-003, Rev. 0 "Unit 1 Path 1 & 2 Safe l , shutdown Equipment List" ' J Bechtel Electrical calculation #76 Rev. O "Unit 1 Path 3 Safe Shutdown Equipment List". i . ]
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- ST8 TEM Evatustich 00CunEnf ELECTRICAL COMPOh8k1 IDEnT1FICAT104 anEET . Omaut>C j OMEET NO.s 2/
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- Ts REF. s . .
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<s REPORT DATE S 63/29186 .
E.I. NATCP wtCLEsa Ptahi th!T *0. 1 Daaw3mt he.s a.33372 met.s.4
^
[ - SYSTER E5aLuaTICu DCCupEnf ELECTRICAL ConP0hf61 IDEhflFItatten SnEET SMEET NO.s o a a BOs ChC. s " sTs aEF. s I TAG huntE4 s , _._ COnP0mE4T e . 8 Om nPL wupeEn s rusciromaL e EeutPMENISMs a PODE/RERa#ES I ELErEnfaar j s _._ ,pEsca1PTIch _. s Coot sEs Pators _ _ _ ., _ _ .. _.
- a ses ELEn i .__e a j _ _ _ _
a 8314E SSENESAT0a/PupP M870s sh a s3 sit susMt7863s .__ _ _ _ - . _ . . _ _ _ _ _ _ . -_ s SSA - , , ,,,,,, , 831a4 164 _ _ ,stetta 8th.mEuf Ostav8LT sh a ,systs shsM17863 _ ___..-._-_.s., _______._..a . s sEEC MATION__TeansFEa sh,s s3sts.susM17e62s._____
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sm Mgfa62:, . i 3 s 33taE : 244 eGEk FIELD.SR0une DETECT sh a 33sts sNsMgi462: _ s e s aees: a e e __ S334K._ 294 sC9eSa_9C.AVI Lget_g1L _,sh_. 83sts,smMtfe62: a 3 a e 8 sease a j g i 931aK 30a _ FLCIS DR MI SIL TEPP Agasu a 83:28 sNsN17860s , , _ , , , , s 3 e aeeaea e 3 33 tat sta CDC2a AC CIRC LUSE SIL sm s3sts susM37ette _. , , _ . s s saass: : :
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e nEPont Oste 8 08/29/06 E.I. M?TCH huCLEaN PLANY % NIT h0. 1 CAaWIh8 #0.s A-lett2 REv.s 0 SYSTEM EVALUATION DCCUMENT ELECTRICAL ConP0h861 IDENTIFICATION SMEET SMEET WO.s y
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s s sos OmC. s - - ~ ~ ~ : TAS hupSEA 8 j *T s ess #EF. s s COnPf ' I .C h s ~ ~~FumCV., . .L e E001PMEstens a MODErnEnanEt MPL !suMeER s ELEPENTany s __ ____ . DE S Ca I P T Ic h . ..__. s. CODE sEs P&ID/. . . _ . ._ __ . _ . _ _ e ( _.__s a s e s ELF.P. s s j i
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_._ 831aE__ 46A e eeeeea s s 474 __ _ sFS,;t SES TInC4 s _,s3 e stats :TsH17861sM00E A,9/CowimCLS Fe3sA.JoseIme CIRCUIT.._ _ _ s _ _ _ _ . . __ e 831aK e a s e a s a s.s a
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S31sE 544 C9414 SEN PUMP MOT 04 sh a s3sts *MsM17840s . . _ s s I s e sse eea e s 1 9 318E , 354 _ ,,_ s C9814,SEN PU'er MOTOR ___ e4 8 83sts sNsH1TS42s __ __ _ ,_ _ a s . s easaaa e j _.
REPORT DaTE 4 60/29/86 . E.I.,MaTCM huCLEa# PLahi' UNIT h0. 1 ORANING MO.s a=le172 REv.s 0 3YSTEM EvatbaTION 00CUMEMT ELECTRICAL COnPQN8kT 10EkTIFICaI104 3 MEET SHEET.hg.: gg t e s s 30s ONG. a # l sie REF. s s T AG 'huntf.R ' ? .. _ COMPONENT s
- MODE /REmaRRS
- 'O h MPL wuwsER s FUNCTIONAL e EGU1PMENTsMa ELEMEpiaNT s
DESCRIPTION _ _ s CDOE sEs PSIO/s _ ._ s
- ____: a ses ELEN 4 s e 331an la :SPCla SEN FIELO A4 PETER su a s33r: NsM17863 a e a ae ess '
s 331aP 2a ___ 30C Esc FIELO wJ'TMETER. sh s s3sZs aaeae sNsM17ss3ss ** 3 a s a s,_ __ 831aM_ _ 3A : 981A_SER_ AMMETER _th s e3:Ze sNsM17863: _ _ _ _ . . _ _
- e: eaea s s
8314M _ 44___ _ sac _FIELO VOLTMETER ___._ sh
- 43:2s nasM17863se _ _ _. ._ _ _ _ _ _ _ ___s e as a a s: seae e 831aMT __1a :TELEmaTT METER Teams ___ su s s3:2s susM17s63: __ __ _ ..__ _ __ ,_
a a i s eeasaa e s 3314R 34 :PUPP PNR Situal TO COMP eh a 83:2s susM17863: i l s sseaeas e s ,,_g estar en asEn mEur sR0cueIns en ass 2s susM17sa3s a s e3 a8 s s i i~ 331a4 __3a ___.sS001A_SEN FIELD.aNRETER s1 a s3stssea sNsM17863ss . a e
- s ss s 33144._ 64 Sec1A_SEN_FIELO_ AMMETER _sN_:.s3s2s sN M17863s_ _ . _. '
e a ssaaaa __ . ._ ,__ _ 1 g 33144 74 __ BLOCR067 BUS PONER AVAIL sk : 83 sis sNsM17861s __ . _ . _ _ _ _ . s e esaaae : s t 8314R . Sa __ _ sMG. SET A SPEED CONT.ST8 sh a s3:2s sass sNsM17864: : _ g s a - _ 531a3 _ ,la segeta ne SET A sh a s3:2s susM17st2s :
< s s a: aes: e g
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REACTOR RECIRCULATION SYSTEM (B31) DRAWINO NO. A-18172 REVISION STATUS SHRET SREET 2 3E3 E = 2 3:E3E =3E 3:2 23E E 3 3 3 3 3 3 32 32 3 2 32 E 3 33 E 3% *223333303333333333333335533 i l LATEST : l LATEST:: l LATEST : l LATEST!! l LATEST:: l SHEET: REV ::SEEET: REY ::SREET: REV :: SHEET: REV :: SHEET! REV :: 32232333E=E33333=3E22333=2=EE23E3E33333=232333333323=333233232333333333
- ll l :: : :: : :: : ::
1 : 1 : 0 :: 11 8 :: : :: : :: : ::
- 2 : 0 :: : :: : !! ! : : ::
, ! 3 : 0 :: : :: : :: : :: : :! 4 : 0 :: : :: : :: : :: ! ::
- 5 : 0 :: : :: : :: : :: : :
j : 6: 0 :: : :: : :: : :: !! i 7 l 0 :: : :: ll l :: ! !!
- 8 : 0 :: : :: : :: : :: : :: ;
i : 9: 0 :: : :: : :: : :: : ::
- 10 0 ll l :: : :: : :: : ::
i : 11 : 0 :: : :: : : : !! : !!
- 12 : 0 :: : :: : :: : :: ! ::
! 13 : 0 :: : :: : :: : :: : ll l 14 : 0 :: : :: : :: : :: : ::
- : 15 : 0 :: : :: : :: : :: : ::
l 16 : 0 :: : :: : :: : :: : ::
- 17 : 0 :: : :: : :: : :: : ::
- 18 : 0 ll : :: : :: : :: : ::
- 19 : 0 :: : :: : :: : :: : ::
- 20 : 0 :: : :: : :: : :: : ::
- 21 : 0 :: : :: : :: : :: : ::
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- 30 : 0 :: : :: : :: : : : :: I
, l 31 : 0 :: : :: : :: : :: : :: ! 32 l 0 :: : :: : :: : !! : :: '
- : 33 : 0 :: : :: : :: : :: : :: l I
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l 35 : 0 :: : :: : :: : :: : :: i
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. REV 0 a
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A-18172 SHEET _$_ I. SYSTEM OPERATION The Reactor Recirculation System ensures adequate core cooling during power operations by supplying coolant flow past the reactor fuel bundles. This flow is provided by recirculating that portion of the core flow which is not ' is boiled while passing through the core. The flow rate can be varied as one means of controlling reactor power. The system consists of two (2) loops external to the Reactor Pressure Vessel (RPV). Each external loop contains one variable speed motor-driven recirculation pump, two motor operated gate valves, and a motor generator set to control the recirculation pump speed. Suction is from the reactor vessel annulus and discharge is to the reactor vessel jet pumps. i The Reactor Recirculation System has seven (7) modes of operation: Normal. LPCI Injection, Recirculation Pump Trips, Reactor Water Sample, RPV Botton Drain, Recirculation Pump Seal i Purge, and Shutdown Cooling Mode. - The function of each mode (and therefore the components of each subsystem) are safety related or non-safety related as indicated in Table 1, and further described in Section II. i The general safety design criteria which are applicable to components in one or more modes are indicated in Section V, t and further discussed in Section II. ' Electrical d4 sign considerations are covered under the support systems listed in a Section III. l 4 I , < t i ! l 4 l l REV 0 I 1 l 1 i I .
REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A-18172 SHEET _1_ II. DESCRIPTION OF OPERATIONAL MODES A. Normal Operation Mode During normal operation, the reactor recirculation
. system ensures adequate core cooling and reactivity -
control by maintaining forced circulation of water past the fuel bundles. The recirculated coolant consists of saturated water from the steam separators and dryers that has been subcooled by incoming feedwater. This water passes down the annulus between the RPV wall and the core shroud. A portion of the coolant flows from the RPV through the two external recirculation loops to'become the driving flow for the jet pumps. The recirculation flow rate is controlled by varying the output frequency of the associated motor generators, thus varying the speed of the associated recirculation pump. Reactor power can be partially controlled by varying the recirculation flow rate without requiring control rod movement. This power change is accomplished by utilizing the large negative power coefficient found in - the BWR design. The void coefficient present in the reactor core is a function of the recirculation flow rate. An increase in core flow sweeps some of the voids from the moderator and causes an increase in reactivity. A decrease in core flow results in the formation of more ' voids which decreases core reactivity. In the event of a power failure to the recirculation pumps the system has enough inertia to ensure that adequate circulation can be maintained to prevent damage to the fuel assemblies in the RPV core. The Reactor Recirculation System is also designed to provide automatic load following capability over the range of approximately 70 to 100% rated power. If feedwater flow is below 20 percent, the recirculatien pump speed is automatically limited. Therefore, automatic protection against recirculation pump cavitation due to NPSH loss is provided by the 20 percent feedwater flow limiter. The recirculation flow is monitored by sensing elements on each loop. This flow rate is transmitted to the Neutron Monitoring System (C51) so that the neutron flux / recirculation flow relationship can be calculated. If this calculated relationship deviates from the normal operational value as determined through analysis, the Neutron Monitoring System will initiate a SCRAM signal. REY 0
+ .
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING No. A-18172 l SHEET _5_ _ i II. DESCRIPTION OF OPERATIONAL MODES < ? l A. Normal Operation Mode , i The Normal Operational Mode is safety related with the l l following safety functions: - ' l l o Reactor Coolant Pressure Boundary (RCPB) ( Integrity j An example of a safety design basis event is the startup f of an idle recirculation pump. j B. LPCI Injection Mode l During this mode, portions of the Reactor Recirculation System piping are included in the LPCI flow paths. Upon the receipt of a LPCI injection signal (High Drywell Pressure / Reactor Low Level 1), the reactor recircule. tion pumps are tripped (Reactor Low Level 2) and the discharge isolation valves (B31-F031A,8) close to avoid LPCI flow out of a possible break in a recirculatior. line and to i assure that LPCI flow is directed through the jet pumpu. The LPCI Injection Mode is safety related with the' l following safety functions: . e ! o Reactor Core Cooling Geometry l o Reactor Coolant Pressure Boundary (RCPB) j l Integrity ' o Reactor Coolant Inventory o High Energy Line Break Mitigation ' 1 > An example of a safety design basis event is a Loss of , Coolant Accident (LOCA). I C. Recirculation Pump aud/or Motor Generator Trips Mode ; r The main recirculation pumps and motor generators have ! I various trips associated with them, some of which have safety significance. The recirculation pump is designed ! to have sufficient inertia so that it gradually coasts ! down after a trip, thus smoothing any flow transients ; caused by cutting off recirculation flow. ! Safety related trips occur with the following events: l Reactor Low Water Level (Level 2) Reactor High Pressure Trip Turbine Stop Valve Closure - (If the reactor Turbina control Valve rest closure - power is > 30% i l of rated) , l REV 0 l l 1
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e, *. . REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A-18172 SHEET .6, II. DESCRIPTION Of OPERATIONAL MODES C. The safety related trips serve to reduce reactor power in case of a reactor scram failure by increasing the void coefficient in the moderator (water). O Non-safety related trips of the recirculation pumps and/or motor generators serve to protect the equipment. These trips are listed on the Reactor Recirculation System Logic Diagrams. I The Recirculation Pump or Motor Generator Trips mode is safety related with the following safety functions: o Reactivity Control o Reactor Coolant Pressure Boundary Integrity An example of a safety design basis event is tripping two recirculation pumps. D. Reactor Water Sample Mode A connection off of the recirculation piping is provided for use in the event that the Reactor Water Cleanup System is out of service. The sample line is I connected into an active portion of the recirculation system to ensure that a representative sample of reactor water is obtained. The sample line valves automatically close on receipt of a containment isolation signal. The Reactor Water Sample Mode is safety related with the following safety functions o Reactor Coolant Pressure Boundary Integrity o Containment Isolation An example of a safety design basis event is a Loss of Coolant Accident. E. Reactor Vessel Bottom Drain Mode A drain line is connected to the botton head of the reactor vessel to permit flushing the bottom of the reactor to the radwaste system during plant shutdown. This arain is also piped to the main suction line of the reactor water cleanup system. The valve in this line is normally oper to permit flow to pass from the bottom of the reactor vessel to the cleanup system continuously during reactor operation. This is done to keep the drain 4 line flushed out and to provide temperature readout of the coolant in the bottom of the reactor vessel by means of an j installed thermocouple. i f REV 0 1 l
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING NO. A-18172 SHEET _1. II. DESCRIPTION OF OPERATIONAL MODES E. The Reactor Vessel Botton Drain Mode is safety related with the following safety function:
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o Reactor Coolant pressure Boundary Integrity F. Recirculation Pump Seal and Purge Mode The recirculation pump seala are cooled by injection water supplied by the CRD (Cll) System. The pumps and the MG . Sets are cooled by the RBJCW (P%2) System. The pump seals are provided with a purge system to keep the seals clean by maintaining a net flow of clean water out of the seal - area, along the pump shaft, and into the recirculation system. A flow of (3) three to (S) five gym is continuously drawn from the control rod drive hydraulic system at all times. The Recirculation Pump Seal and Purge Mode is safety related with the following safety function: o Reactor Coolant Pressure Boundary (RCPB) Integrity. G. Shut.1own Cooling Mode The Shutdown Cooling Modo is an integral par.t of the RHR System (Ell). Reactor coolant is pumped from one of the recirculation loops by one or both RHR Pumps and is discharged through the RRR heat exchangers where it is cooled by the RHRSW flow. The reactor coolant is then returnad to the RPV via the recirculation loop. This mode contaisi no individual cosponents from the Reactor Recirculation System except the segment of recirculation pipe where the RHR system ties in, flow elements N013A B which serve as pressure boundaries, and recirculation pump discharge isolation valves F031A,8 whico are closed. The Shutdown Cooling Mode is safety related with the following safety functions j
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o Reactivity Control o Reactor Cora Cooling Geometry o Remetor Coolant Pressure Boundary Integrity o Reactor Coolant Inventory An exemple of a safety design basis event is a Shutdown Cooling (RHR) Melfunction necreasing Temperature. I REV 0 1
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REACTOR RECIRCULATION SYSTEM (B31) DRAWING No. A-18172 SHEET _l_ III. SUPPORT SYSTEMS The following systems, in whole or in part, are required to support the operation of the Reactor Recirculation System. For detailed information pertaining to the functionally , nuclear safety related poebious of these systems, the ' respective system evaluation documents for each system should be consulted. A. Nuclear Boiler System - 821 B. Residual Heat Removal System - Ell C. Reactor Building closed Cooling Water System - P42 D. Control Rod Drive System - Cll i E. Neutron Monitoring System - C51 F. Reactor Protection System - C71 ! G. Battery System - R42 H. Diesel Generator - R43 I. Uninterruptible Power - R44 The following system supports the Reactor Recirculation System in a non-safety manner by providing Not Positive Suction Head (NPSR) for the recirculation pumps: l 1 A. Feedwater System - N21 1 I i i i REV 0
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REACTOR RECIRCULATION SYSTEM (531) DRAWING No. A-18172 SHEET _}_ SYSTEM EVALUATION DOCUMENT , IV. REFERENCE DOCUMENTS DWG NO. REV. TITLE H-16063 16 Nuclear Boiler System P&ID, Sheet 2 H-16066 16 Reactor Recirculation System P&ID, Sheet 1 H-16067 1 Reactor Recirculation System P&ID, Sheet 2 , E-16068 2 Reactor Recirculation System P&ID, Sheet 3 H-16076 7 Reactor Recirculation System M.G. Sets P&ID ' H-17860 13 Reactor Recirculatiou Pump and M.G. Set l Elementary Diagrams, Sht 1 , i R-17861 7 Reactor Recirculation Pump and M.G. $st ' Elementary Dia_ rams, Sht 2 H-17862 13 Reactor Recirculation Pump and M.G. Set , Elementary Diagrams, Sht 3 H-17863 7 Reactor Recirculation Pump and M.G. Set j . Elementary Diagrams, Sht 4 H-17864 19 Resctor Recirculation Pump and M.G. Set j Elementary Diagrams, Sht 5 H-17865 10 Reactor RocLeculation Pump and M.G. Set a Elementary Diagrams, Sht 6 H-17866 15 Reactor Recirculstion Pump and M.G. Set Elementary Diagrams, Sht 7 H-17867 7 Reactor Recirculation Pump and M.G. Set Elementory Diagrams, Sht 8 . ]. H-17868 11 Reactor Recirculation Pump and M.G. Set Elementary Diagrass, Sht 9 L i H-17869 2 Reactor Recirculation Pump and M.G. Set i Elementary tiagress, Sht 10 H-17870 3 Reactor Recirculation Pump and M.G. Set Elementary Diagrams, Sht 11 R-17814 13 Reactor Recirculation Pump and M.G. Set Eles,ntary Diagrams, Sht 12 i H-19913 0 Roactor Recirculation System Logic Diagram, j Sht 1 j R-19914 0 Reactor Recirculation System Logic Diagram, i Sht 2 l H-19915 0 Reactor Recirculation System Logic Diagram, l Sht 3 ;
- H-19916 0 Reactor Recirculation System Logic Diagram, j ~
Sht 4 ) R-19917 0 Reactor Recirculation System Logic Diagram, Sht 5 S-19108 A Operation sad Maintenance Instruction Manual Vol. II - Reatetor Recirculation System i Unit 1 FSAR, Rev. 3, 3.7 4.3, and 7.9 j Technical Specifications. Amend 124, 3/4.6 ! i 10CFR50 Appendix A. General Design Criteria No. I 1 1, 2, 4, 12, 13, 14, 15, 30, 31, 32, 55 5 4 r REv 0 l
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T.EACTOR EECIRCULAFION SYSTRM (531) DRAWING NO. A-18172 . SHEET 30_ SYSTEM EVALUATION DOCUMENT IV. REFERENCE DOCUMENTS Central File for the Environmental Qualification of Safety Related Equipment, Section 3 (HNP-1), Rev. 19. Review of Plant Systema per Supplement 1 NUREG-0737, comparison to NRC Regulatory Guide 1.97 (Rev. 2) EMP-1 SCSI Calculation # SNR 86-003, Rev. O "Unit 1 Path 1 & 2 Safe Shutdown Equipment List" Bechtel Electrical Calculation #76, Rev. 0 "Unit 1 Path 3 Safe Shutdown Equipment List". l i S 4 1 1 I 4 i i ] 1 . REV 0 l
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[ E.I. MATCH NUCLEAR PLANS 3 UNIT h0. 1 DNAN1hG NO.s a-tetF2 REV.s 0 SYSTER EU A.t. '. pi'ON DOCUMENT ELECTRIC AL COMPONeb T 10thTIFICATION SMEET SMEETih0.8 3g.
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s TAG NUMBER a s COMPONENT s STs REF. : _ _ _ _ .. m _ _ _ 890E/REMARR5 . s Ch NPL Nunste a FUNCT10Nat : EQUIPMEhisMs s DESCFIPTIon___. e._ 00CE sCs P41D/8* _ ..__ _ ___ _ _ _ _ _ _ _ _ . ____.9 ELEMENTARY _ _ __ _ s . _ _ _ s 8 8 s sRs ELEn s ___[____.___. s _ a J318E 300 _.___sCOC2B_AC. CIRC Lute DIL__sh a s3 Zs ansM17903:e . _ _ _ _ _ . _ _ _ _ _ _ _ _ . . e a eaaaes a 538t" _ 398 _ .8C0038 AC CIRC LUPE 0!!.__sh -. _ _ , _ . _ , . _ . e ass s3stssaa sNsMIT903s. : _.__. 3 a s s 8318E 400 BC0048 AC CIRC LUGE OI L eh_s_s3:Zs susH179038 s e s. ss s : e 33sts susM179C2s .8 ~~-e 531st 418 sDC CONTR0; Fue TeamSFER sp ~ s aeeaas e s 53tBE_ _42G NORMAL DC CONT _PmR U/W_ sh s3*2s BNsM17902s. _ _ _ _ _ , _ _ _ _ _ _ _ a y a eaa: : : s
- _,__8318E___438 84T43 _._sm,s_03:Ze,sNsN17903: 8 a
s e asassa e t a _. 3 31 N __430 sATm3 _ .___ _ sh a s3:Ze sNsM17903: _ _, . ______._._,._ _ e s a sss s s sF03te_PUnP,DISCM 190( __s a stsZs sT8H17907sM00E.A,S/ CONT 4CLS,.MG ORIVE n0T04.eW8_ TRIP CET t__ _________ _ _ _ _ _ _ g 83:3E___449 s stss s s s s
, . 8 3 t BE ,.,_C58 IFeste PunP DISON_JSCL s3,s_ sis's,sTsMi?.907 sMOCE;A,B/CONTRCLS_F03tB JOGGING CET/MS_DRITE_pTR_CEf t
. : s aa: : es 8
__ g 85184 465 sF03te J0GCING CIRCUIT _ s3 sists'sisMIF870sM00E A,5/ CONT 4CLS F0318 JOSEInt CIRCUff 8 e s s aaa: : : a ^ 5 3* st .478 _ .sF8313 SE0_ tin [7 __ _ . 38 s sisIt sisN17afosM00E 8,8/ CONT 4CLS F03tB_J00SIpe CIRCUIT ._ , , i . _ _ _ _ ._ _ ,, e s a e ea : ss s ,. l 400 sFG3tB_AUM_ TIMER _st . stats s.sN17870sM00E A,5/ CONTROL 83 0315_JO981NS CIRCU1T
.__8318E e ases: e s s . __. g Edlet _s95 __ _ sF0313 JOCGT'sS CIRCUIT _ s3 s st:Is sv,M178FOsM00E A,8/CGMTECLS F0313 J068IIe6. CIRCUIT _ _ __ _ I _ _ .
a s aaeaa s s s.. 5315E . 508 sF0319.J5EGt46 CI4cu!T._ s3 e sists sTsMIT870sR00E 4,5/C04T4CLS F0310 JOSSING CIRCUIT ____a q ,, e eses: a s e 83tBE 528 sF0313 J0GG1h8 CIECu!T sS,s, sisT' TsMIT870s%0E .A,8/CONTSCL8 F0318 JOSSIMS. CIRCUIT t i s aes . ee s . t s3 : ess2. er:MtF870 6M00E A,5/ CONT 4CLO .F.63it. J.OSSIps CIRCUIT. . _ _ _ _ _ . .. e 8313E Sie IFe313 J0GSING.CIECUIT , ,,,,,,
.sh 23sts saan17905e i 331st 530 ___89401g SEN OVERCUseENT . . _ _ _ _ . _ _ , _ _ _ _ _ . _ _ _ _ . _ . _ ,_
4 e a aeeeae 3 __.____l___._ ___.._ ._____ _. 33tSE _. 349 BC9C18_SEM PUnP.MOTCR____sh a s3:Zs shsM17902: . e s s ? eass t e 53154 550 BCOC1g SEN PUPP MOTCR sh s 33 sis susMIF90cs e 3 e aaeee: a 8 s*1em te sSOC10 SEN FIELO AMPETER sh a s3sts sNsN17903s e g i e aseaes e s 8319R , , 29___30C_E3C .FIELO. WOLTMETEE _ sm e s 3 st s su sM17905 _ _ . . _ _ _ . _ _ _ _ e a e aaas s m e
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